ML20247L196
| ML20247L196 | |
| Person / Time | |
|---|---|
| Issue date: | 05/25/1989 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-890519, NUDOCS 8906020106 | |
| Download: ML20247L196 (42) | |
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- iw g i k kbk May 25, 1989 For: The-Commissioners From: James L. Blaha, Assistant for Operations, Office of the ED0
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Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING MAY 19,'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* !
G Administration Information Resources Management H Controller I*
J Persennel j Small & Disadvantaged Business Utilization & Civil Rights K*
L Enforcement M
Consolidation N
Regional Offices l Executive Director for Operations 0 {
Items Addressed by the Consnission P l Meeting Notices Q Proprietary or Other Sensitive Information (Not for R j
. external distribution) l i
- No input this week.
hok $M hhh a es 1 ssistant for Operations WEEKLYINFOREPT PNV Of ice of the Executive Director for Operations
Contact:
James L. Blaha, OED0 p
-492-1703- 1 (
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cy i HlGHLIGHTS OF WEEKLY INFORMATION REPORT i WEEK ENDING'MAY 19. 1989-9 Seabrook Unit 1 l i
On May 18, 1989, the Commissioners voted to deny the interveners' requests In order to give for stay of the authorization'to issue a low theD.C.CircuitCourtofAppeals(Court)powerlicense.an opportunity to r and any opposition that may be filed with 25,1989. the Court, at 4:00 no p.m. license authorizing EDT, or such low-power testing earlier date as the Court mayshall issue before Maydeny the stay requests now before it.
May 9-10 Meeting with the Department of Energy there was a meeting between NRC and the Department of Energy Dn May 9-10, 1989, (DOE) at whfch NRC presented preliminary staff concerns regarding DOE' CharacterizationPlan(SCP)(fortheYuccaMountain,Nevadasite Exploratory Shaft Facility ESF) Design Acceptability Analysis (DAA).
The meeting afforded DOE the opportunity to clarify information i related to the NRC concerns.
the meeting but declined to comment or ask questions about the preliminar concerns.-
Vermont Legislature Adjourns Without Enacting LLW Legislation The Vermont Legislature adjourned on W disposal facility.May 5,198 Vermont is
-provided for the preparation of a siting plan for a LL The Legislature is not scheduled to return until Janua:i continued access to the Beatty site through 1992.
to be enacted may jeopardize those negotiations.
Meeting with Pennsylvania on Status of Limited Agreement John McGrath,16,Region I State Agreements 1989 in King of Prussia Pennsylvania.
Officer, met The purpose of with rep j Pennsylvania on May the meeting was to discuss the status of Pennsyl Pennsylvania is not prepared to formally submit a reques agreement at this time.
'it can prepare the formal request. i i
Dedication Plaque _
Installation of the White Flint Dedication Plaque at the front entra completed on May 17.
Drinking Fountains New certified lead-free chilled water fountains manufactured began arriving at OWFN last week. As of May 18, twenty-one of the forty-oneT replacement fountains had been received.
shortly and will be tested thoroughly before being put into gener Bottled water will remain available until tests of the newly instal fountains have been completed and verified showing lead leve Federal standard threshold of 50 parts per billion.
, MAY 19, 1989
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- 'i OFFICE 0F NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending May 19, 1989-Limerick Units 1 and 2
- PREHEARING CONFERENCE ON CONTENTIONS DEALING W i-GRATERFORD PRISONERS the Commission issued an Order calling for a Licensing On April 14, 1989, Board to conduct proceedings ts consider the contention of an inmate at the [
Pennsylvania Graterford Prison questioning whether the radiological emergency response plan for Limerick, Units.1 and 2 provided adequate training for bus and ambulance drivers who may-be called upon to assist in evacuation of the maximum security prison. Pursuant to a notice of the ASLB established 12, 1989 into conduct the proceedings, a prehearing conference was held MayTh
. Philadelphia.
based upon an agreement in principal, as follows:
- 1. The Pennsylvania Department of Corrections committed to use_only Corrections Department employees as bus and ambulance drivers in the ,
event evacuation of the prison was required. No " civilian" drivers 1 will be utilized. .
2.- Philadelphia Electric Company has prepared lesson. This plans and will training !
provide training for all bus and ambulance drivers.
will .be completed within the next 30 days contingent on the Corrections Department employees being available.
The schedule established is to orovide an executed stipulation to the ASLB by May 30 1989 with the request t1at the hearings be terminated.
Limerick - Startup of Limerick Unit 1 Limerick, Unit I started pulling rods on May 15, 1989, starting up in Cycle 3.
11, 1989 for refueling. During the outage, the j
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The unit had shutdown January About 2/3 of the raload are entire core (764 fuel assemblies) was replaced.new The balancefuelof assemblie j
'that were intended to be loaded in Unit 2 were used in Unit 1 j assemblies that had been stored in the spent fuel pool. !
San Onofre Unit 1 On May 15, 1989, the NRC issued a license amendment to incorporate a license condition regarding the reactor vessel thermal shield whi mid-cycle inspection is performed.
ENCLOSURE A ,
.MAY 19, 1989 !
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TVA NUCLEAR POWER ORGANIZATION
.On May 17, 1989, the Tennessee Valley Authority (TVA) announced that Dr. Mark 0. Medford has been selected to fill the position of Vice President Currently,
- and Nuclear Technical Director in TVA's Nuclear Power Organization.
Dr. Medford is Manager of Nuclear Regulatory Affairs for Southern California Edison and serves as the primary interface with the NRC and manages all regulatory and licensing matters.- He has 14 years of experience with Southern Dr. Medford California Edison and was in the U.S. Navy nuclear program for 5 years. _
will report to TVA in June 1989.
Update on Steam Generator Girth Weld and Feedwater Nozzle Inner Radius cracts at Indian Point Unit 2 (EMT5J A meeting was held on May 11, 1989 with the licensee and Westinghouse the to discuss the specific and generic aspects of the steam generator shell cracking.
licensee described the 1981 inspection results, the metalography fractureAll known crac mechanics evaluation, repair activities and future plans. !
girth weld No. 6 have been ground out and the excavations contoured. .The most severe cracking occurred in SG #2 with the deepest grind out of.1.42" (3.5" wall thickness) and maximum crack growth rate of 0.949" during a 14 month L . operating cycle. The thermal fatigue cracks in the feedwater nozzle inner The licensee reported that I- radius have been ground out of SG #2 and SG #3.
the feedwater distribution ring-support bracket, et the thermal sleeve location, are cracked in both of these SGs. The cracks are being removed to assess.the damage.
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) The licensee's proposed repair program for the girth weld is a weld butidup to i
a 0.75" excavation, perform a post weld heat treatment (PWHT) on SG #2 codThe owrate the other SGs in their existing condition.
tie downcomer flow resistance plate so that the cold auxiliary feedwater willTh impinge further down on the transition cone shell.
plant modifications and operating procedures to increase the average temperature of the auxiliary feedwater and reduce the amount of dissolvedHowev oxygen. These corrective measures were available in 1987.
the Westinghouse fracture mechanics analysis concluded that all SGs could l operate for the remainder of the plant life without significant flaw growth.
The Westinghouse predictions were overly optimistic, especially considering !
that cracks initiated and propagated even though that the water chemistry '
l control and low number of reactor trips during the last fuel cycle were among l
the best in the history of Indian Point Unit 2.
l y j The staff found a high degree of uncertainty inThe calculations.
the Westinghou pitting I
indicate a weld renair and PWHT of other SG's would be required. Based on the infor-and corrosive environment are, however, still present.
mation provided at the meeting, the staff recommended that Consolidated a mid-cycle Edison did magnet l ;
particle inspection wculd be an appropriate action.not provide a storage.
ENCLOSURE A
! MAY 19, 1989
3 Seabrook Unit l' On May 18, 1989, the Commissioners voted to deny the interveners' requests for stay of the authorization to issue a low power license. In order to give the D.C. Circuit Court of Appeals (Court) an opportunity to review stay claims and any opposition that may be filed with the Court, no license authorizing low-power testing shall issue before May 25, 1989 at 4:00 p.m.-EDT, or such earlier date as the Court may deny the stay requests now before it.
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ENCLOSURE A MAY 19, 1989 i l
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.0FFICE OF NUCl. EAR HATEP,IAL SAFETY AND SAFEGUARDS Items of Interest Week Ending May 19, 1989 SAFEGUARDS
, International Technical Support to the International Atomic Energy Agency (IAEA)
Two members of the Division of Safeguards and Transportation staff participated as members of the Technical Support Coordinating Comittee in an. annual meeting with the International Atomic Energy Agency (IAEA) Division Directors, held May 15-17, 1989 at Brookhaven National Laboratory, New York. The purpose of this meeting was to review and comment on the IAEA safeguards program and activities supported by the United States.
Domestic-Safeguards Visit to AlchemIE Robert Burnett, Director, Division of Safeguards and Transportation, toured the ALChemIE gas' centrifuge facility on the Department of Energy's'K-25 site on May 17. AlchemIE, a new NRC licensee, plans to use the facility for the commercial separation of non-radioactive materials for use in industrial, medical, and analytical ap)11 cations. The plant has safeguards implications because the centrifuge mac11nes are capable of enriching uranium as well as
.non-radioactive materials.
Transportation Meeting with British Aerospace t On May 16, 1989, the Transportation Branch staff met with Mr. Peter Sedgewick, ]
ChiefTestPilotforBritishAerospace(BAe). Also in attendance were staff s l
from the Lawrence Livermore National Laboratory, who are providing technical j
support to NRC for the development of test requirements for plutonium air i'
transport containers. The meeting focused on the performance of the BAe-146, the aircraft involved in the crash of PSA Flight 1771. This information exchange will be helpful in the development of crash testing requirements to p satisfy the Murkowski Amendment.
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l ENCLOSURE B MAY 19, 1989 J
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s INDUSTRIAL AND MEDICAL NUCLEAR SAFETY
. Materials Licensing r Meeting with Federal Aviation Administration (FAA) Officials to Discuss their '
Plans for Current Proposed Rulemaking Concerning the Use of Thermal Neutron Activation (TNA) Explosive Detection Systems (EDS) at International Airports Representatives from the Office of Nuclear Material Safety. and Safeguards -
(NMSS)metwithofficialsfromtheFederalAviationAdministration's(FAA)
Office of Civil Aviation Security to discuss proposed FAA regulations which would require all airlines to purchase an Explosive Detection System (EDS) which would detect plastic explosives in luggage. The Thermal Neutron Acti.va- i tion (TNA) device utilizes californium-252 which emits thermal neutrons to; activate the nitrogen atoms in plastic explosives. When activated nitrogen atoms are detected, a computer attached-to the system gives a warning signal that explosives in luggage are being smuggled onto an airplane. The Environ-mental-Assessment finding of no significant impact was completed by NRC in September 1988, and the first. license was issued to the FAA in February 1989.
Transportation Secretary Samuel Skinner has emphasized the need for improved' security in airports and scheduled the first of these devices to be' installed I at_ New York's JFK- Airport in June. The FAA plans to publish proposed rulemaking -! '
.in the Federal Register by June 16, 1989. Once this rule goes into effect, an~-
estimated 100 to 200 TNA devices will need to be licensed in both this country i' and abroad. NRC will be requested to' issue licenses to manufacturers, users and maintenance contractors'of the EDS. On the basis of discussions at this meeting, NRC plans to write a Licensing Guide to provide assistance to applicants'and licensees in preparing applications for new licenses for the use of these TNA devices at airports throughout this country. In addition, NRC will write and distribute a Standard Review Plan for both the Regions and Agreement State personnel to aid and facilitate the processing of these applications.
HIGH-LEVEL' WASTE MANAGEMENT May 9-10 Meeting with the Department of Energy On May 9-10, 1989, there was a meeting between NRC and the Department of Energy (DOE) at which NRC presented preliminary staff concerns regarding DOE's Site Characterization Plan (SCP)(for Exploratory Shaft Facility the Yucca Mountain, NevadaThe ESF)DesignAcceptabilityAnalysis(DAA). site and DOE's meeting afforded DOE the opportunity to clarify information in the SCP and DAA related to the NRC concerns. Representatives from the State of Nevada attended the meeting but declined to comment or ask questions about the preliminary NRC j concerns.
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MAY 19, 1989 ENCLOSURE B I
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L HIGH-LEVEL WASTE MANAGEMENT (cont'd) ,
Presentation for Advisory Comittee on Nuclear Waste On May 11, 1989, NRC staff members presented preliminary concerns regarding theDepartmentofEnergy's(D0E)SiteCharacterizationPlan(SCP)tothe l,:
Advisory Comittee on Nuclear Waste (ACNW). This was done to familiarize ACNW !
with the material it will be reviewing when the draft Site Characterization c Analysis (SCA) is transmitted for formal ACNW review on June 2, 1989. It was agreed that, in order to expedite the formal review of the draft SCA, l individual ACNW consultants responsible for reviewing concerns in particular !
disciplines would interact with appropriate NRC staff members by l teleconferences or visits prior to the next ACNW meeting-(scheduled for June 13,1989).
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a MAY 19, 1989 ENCLOSURE B
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g n 0FFICE OF NUCLEAR REGULATORY RESEARCH i
Items of Interest Week Ending May 19, 1989 Integrity of Reactor Components Meeting of the International Piping Integrity Research Group ;
The6thmeetingoftheInternational-PipingIntegrityResearchGroup's(IPIRG)
Technical Advisory Group was held in Taipei, Taiwan on May 8 - 10, 1989. The IPIRG is an international consortium of government and industry organizations formed to fund research investigating the failure behavior of cracked pipe under seimic or other dynamic loading. Each participant in the IPIRG has one representative on the Technical Advisory' Group (TAG). The TAG meets twice The reasons a year -- once in the U.S. and once in a participant's country.
for the meetings outside the U.S. are to permit more people from the various-participants'. organizations to. attend and contribute to the meetings.
This program has thus far been very successful and well received in the l international community. There are ten participants with total funding exceeding $6.2M. The participants have started discussing potential. follow-on work ~and, based on the results of this meeting, it is likely that such a J-program will be developed. i Prevention of Damage to Reactor Cores I.
Regulatory Guide 1.157 Regulatory Guide 1.157, "Best Estimate Calculations of Emergency Core Cooling System issuance.
Performance" was published in May 1989 and will be e 35996)whichpermitsapplicantsandlicenseestouserealisticcalculationsof !
emergency core cooling system response to loss-of-coolant accidents when determiningthattheacceptancecriteriain10CFR50.46(b)arenotexceeded.
This guide presents a broad data base for constructing realistic models Many modelsforand )
predicting phenomena pertinent to loss of coolant accidents. corre ;
L this guide provides a general description of acceptable methods to perform the l7 L
required uncertainty analysis. The promulgation of this guide is the culmination of more than 14 years of research, performed by the NRC and other institutions, designed to obtain a better understanding of reactor system l performance during a LOCA. l ENCLOSURE C ,
MAY 19, 1989 l l
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U, 42 Containment Performance and Protection from Radiation NUREG-1150 QA Meeting
' On May 8-9, 1989, RES staff and contractors met for a final quality assurance review of NUREG-1150, " Severe Accident Risks: An Assessment for Five U.S.
' NuclearPowerPlants"(SecondDraftforPeerReview). The principal focus of this QA review was the technical accuracy of the detailed risk analyses performed by the contractors, as summarized in the staff report. RES staff are
- now preparing the final version of the report, expected to be published in .l.
June.
Resolving Safety Issues and Developing Regulations Briefing on Decommissioning of Nuclear Power Plants Robert Bosnak, Deputy Director, DE/RES briefed the delegation from the Soviet Committee for Supervision of Nuclear Power Safety on the subject of i decommissioning of nuclear power plants. The subject of decommissioning was prefaced by a discussion of the number of U. S. plants reaching theSuch end of utilities i their current operating license terms early in the 21st century. '
emst soon decide whether they plan to decommission or renew their operating licenses. Decommissioning alternatives, funding provisions planning for decommissioning, and the level of residual radioactivity permitting unrestricted !
use were the subjects of interest. The Soviets indicated piens to decommission a number of first generation plants. Their second generation plants have a 1 design life of 30 years and they were interested in life extension concepts for these plants to keep them operating since there are shortages of electric o power in.certain regions of the Soviet Union. )
Recently Issued Publications Reg. Guide 1.157, Best-Estimate Calculations of Emergency Core Cooling System Performance, May 1989. ;
Contact:
H. Tovmassian, RES 301/492-3562 Reg. Guide 1.114, Rev. 2, Guidance to Operators at the Controls and to Senior Operators in the Control Room of Nuclear Power Unit, May 1989
Contact:
I. Schoenfeld, RES 301/492-3541 3
ENCLOSURE C MAY 19, 1989
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ITEMS OF INTEREST Office for Analysis and Evaluation of Operational Data Week Ending May 19, 1989 j Division of Operational Assessment i 1
On May 16, the IRB Chief and staff assessed the response capability of RI in conjunction with the Nine Mile Point licensee full-scale exercise. The overall performance of the region base and site teams was considered to be excellent.
The Perry Diagnostic Evaluation Team report was transmitted to the ED0 on May 16, for appropriate action.
Division of Safety Programs The fourth quarter CY 1988 Abnormal Occurrence report (HUREG-0090, Vol. 11, No. 4), has been delivered to Congress and released for general distribution.
Preliminary Notifications
- a. PNO-ADSP-89-02, Texas Utility Electric Company (Comanche Peak Unit 1),
Commencement of Augmented Inspection Team.
- b. PN0-ADSP-89-03, TU Electric (Comanche Peak Units 1 and 2), Significant Severe Weather Danage.
- c. PNO-II-89-35, System Energy Resources, Incorporated (Grand Gulf Nuclear Station), Shutdown in Excess of 48 Hours.
- d. PNO-II-89-36, B.P.B. . Instruments, Inc. (Agreement State License), Ruptured Cesium - 137 Well Logging Source.
- e. PNO-II-89-37,RadiationSterilizers,Inc.(StateAgreementLicensee), i Failure of WESF Capsules to Meet Preshipment Tests. j
- f. PNO-III-89-33A,CommonwealthEdisonCompany(ZionUnit1), Unplanned GaseousRelease---(Update).
- g. PNO-III-89-34, Robertshaw Controls Company (Agreement State Non-Licensee), ,
Missing Gauge Containing Cesium-137 Sealed Source. i
- h. PN0-III-89-35, Connonwealth Edison Company (Byron Unit 2), Shutdown to i
Repair Hydrogen Leak, I
PN0-IV-89-33, Houston Lighting & Power Company (South Texas Project, Unit 2), j 1.
< Reactor Shutdown Because of Inoperable Pressurizer Level Indication. !
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- j. PNO-IV-89-34, Arkansas Nuclear One (Unit 1), RCS Pressure Boundary Leakage.
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- k. SouthernCaliforniaEdison(SanOnofreUnit),ShutdowntoRepairSteam Generator Tube Leak.
- 1. PNO-V-89-29,SouthernCaliforniaEdison(SanOnofreUnit1), Aborted Restart of San Onofre Unit 1.
MAY 19, 1989 ENCLOSURE D l
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- ITEMS OF INTEREST.
> . 0FFICE OF GOVERNMENTAL AND PUBLIC AFFAIRS WEEK ENDING MAY 19, 1989 ,
INTERNATIONAL PROGRAMS:
Bomb Threat in Canada
!0n Wednesday the' Atomic Energy Control Board-(AECB) of Canada advised GPA/IP that a bomb threat had been telephoned to'the Canadian Nuclear AssociationLin
' Toronto by a person identifying himself as an agent of (Muammar) Khaddafi. The l bomb was' to' go off at 2 p.m. at an unspecified Canadian nuclear. facility, but Lactually did not (as of May 19). Canadian authorities are investigating the 3 matter. As a result of this incident, GPA/IP.is now working with the AECB's Planning and Coordination Section to develop procedures.to inform each other
. -of such events in the future.
International Visitors
-On Monday. Mr. J. C. Chenal, EdF, accompanied by D. Chavardes, Nuclear Attache j at the French Embassy, met with members of NRR, RES and-IP to discuss the !
status of NRC activities related to safety and licensing of advanced reactors.
E On Tuesday-a team from the Soviet Union, headed by-Dr. Vadim Malyshev,
, Chairman of. the' State Committee for' Supervision of Nuclear. Power Plant Safety, began a several-day visit to the U.S. On Wednesday the-visitors' toured the
.Calvert: Cliffs NPP and on Thursday visited Region II and'INPO. On Friday.the
-Soviet: delegation had' meetings with NRC Commissioners'and senior staff, and Chairman Zech and Chairman Malyshev signed'a statement on the planned exchange E of-inspectors this. summer.
.On Thursday Dr. Rex Nazare Alves, Chairman of the Brazilian National Nuclear Energy Commission (CNEN) and delegation met with Chairman Zech'to discuss
'NRC/CNEN nuclear safety cooperation.- These discussions were followed by a-
-ceremony to sign the; third renewal of the NRC/CNEN information exchange and cooperation arrangement. Afterwards, the' Brazilians were given a tour of the 1 Operations Center. Commissioners Roberts and Curtiss and Ambassador Kennedy Lattended'both the ceremony and the luncheon that followed.
o On Friday Mr..Yoshinori Tatsuta, Director, International Nuclear Power Safety ,
l Affairs, Agency for Natural Resources and Energy /MITI, and other Japanese !
1 visitors met with T. Murley, F. Gillespie, W. Bateman and G. Bagchi of NRR and l i R. Hauber, K.' Burke and H. Faulkner of GPA/IP. Discussions centered on the planned visit to Japan of a team of NRC inspectors interested in plant maintenance and a visit to'the U.S. this fall by MITI and other Japanese L representatives for the fifth NRC-MITI Bilateral Meeting on Nuclear Regulatory Matters. .t i
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STATE, LOCAL AND INDIAN TRIBE PROGRAMS Vermont Legislature Adjourns Without Enacting LLW Legislation The Vennont Legislature adjourned on May 5,1989 without enacting LLW 1egislation which would have, among other things, created a LLW authority and provided for the preparation of a siting plan for a LLW disposal facility.
The Legislature is not scheduled to return until January of 1990. Vermont is currently negotiating a contract with the Rocky Mountain LLW Board for continued access to the Beatty site through 1992. Failure of this legislation to be enacted may jeopardize those negotiations.
Applicants Sought For Diablo Canyon Independent Safety Comittee Pursuant California to the terms Attorney of thePacific General, DiabloGas Canyon settlement
& Electric proposed Company (PG&Eby)the and the California Public Utilities Comission's Division of Ratepayer Advocates and adopted by the California Public Utilities Comission (PUC), the PUC President G. Mitchell Wilk announced on May 10, 1989 the opening of the application period for qualified applicants to seek nomination to the Diablo Canyon Independent Safety Committee. The comittee will assess the safety of Diablo Canyon operations and has authority and discretion to review quarterly reports on the plant and conduct on-site inspections. The comittee will prepare an annual report of its observations and recommendations which it will submit first to PG&E for response, and then to the PUC, the Governor, the Attorney l l General, and the California Energy Comission.
A list of nine candidates will be nominated jointly by the President of the PUC, the Dean of Engineering, University of California at Berkeley, and PG&E and submitted to the appointing authorities. One member of the three-member panel will be appointed by the Governor, one by the Attorney General and one by the Chairman of the California Energy Comission.
Illinois General Assembly Considering Nuclear Safety Legislation The Illinois General Assembly is considering House Bill 2310, which " creates the Illinois Nuclear Facility Safety Act and amends various Acts administered by the Department of Nuclear Safety to provide greater regulatory powers by ,
the Department to reduce the possibility of nuclear accidents and to minimize the severity of such accidents at nuclear facilities". This legislation proposes to expand the role of IDNS in areas such as promulgation and enforcement of criteria for nuclear facility design, equipment, operation, inspection and maintenance. The bill also addresses ASME Code pressure vessel inspection, the resident engineer program and spent fuel storage and I
shipments. The bill is currently under consideration in the Illinois House.
l HB 2310 is subject to amendment by the House and has not yet been considered by the Illinois Senate. The Office of General Counsel is reviewing the legislation.
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Medical Use Workshop R. L. Woodruff, Region II State Agreements Officer, attended the NRC Medical Use Workshop on May 13, 1989 in Charleston, West Virginia. Kentucky Radiation l MAY 19, 1989 ENCLOSURE E L____-_-____
Control. Program staff members also attended this workshop which was sponsored by Region II for medical user licensees.
Meeting with Pennsylvania on Status of Limited Agreement John McGrath, Region I State Agreements Officer, met with representatives from Pennsylvania on May 16, 1989 in King of Prussia, Pennsylvania. The purpe;e of the meeting was to discuss the status of Pennsylvania's efforts to become a limited Agreement State for the purpose of regulating a LLW disposal facility.
Pennsylvania is not prepared to formally submit a request for a limited agreement at this time. The Commonwealth needs additional information before it can prepare the formal request.
Nine Mile Point Emergency Planning Exercise Marie Miller, Region I State Liaison Officer, participated in the emergency planning exercise at Nine Mile Point on May 16, 1989. Ms. Miller participated as the State Liaison at the State Emergency Operations Center in Albany, New York. As part of this exercise, a total of six Region I staff served as liaison with counterparts from the State.
ENCLOSURE E MAY 19, 1989
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OFFICE OF ADMINISTRATION ITEMS OF INTEREST WEEK ENPING MAY 19, 1989
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Dedication Plaque Installation of the White Flint Dedication Plaque at the front entrance was emnpleted on May 17.
Meeting with Parsons (White Flint Contract)
The Director of Administration and staff met with the President of Parsons on May 16 to review areas of contract performance.
Significant F0IA Requests Received by the NRC for 5-Day Period May 12 - May 18, 1989 in
-Request for records on the nuclear test reactor operated by Martin Marietta
- Karthus, Pennsylvania, during the 1950's. (Barbara Staley, Chem-Nuclear Systems, Inc. F01A-89-218)
Request for records that identify individuals or organizations that provide consulting services to ACRS. (F. M. Clikeman, Purdue University, F01A-89-220)
Request for copies of all internal NRC records regarding four specified records about the Nine Mile Point nuclear power plant. (Kathleen Crook, Devonrue, F0!A-89-221)
Request for a list of people subject to NRC licensing for the (Edward possession Klein,of natural thorium metal and/or natural thorium metal powder.
Ronson,F01A-89-223)
Request for a copy of a briefing transcript regarding a proposed enforcement action about the Pilgrim nuclear power plant. (Christopher Scales, Technical Analysis Corporation, F01A-89-224)
Referral from Department of Justice of records regarding possible criminal indictments of employees of the Sacramento Metropolitan Utilities District following the discharge of radioactive liquid effluents at the Rancho Seco nuclear power plant. (Morton L. Friedman of Friedman, Collard & Poswall, F01A-89-225) i ENCLOSURE G MAY 19, 1989 u _
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OFFICE OF INFORMATION RESOURCES MANAGEMENT Items of Interest -l Week Ending May 19, 1989
- 1. 10 CFR 52, "Early Site Permits; Standard Design Certifications; and Combined Licenses for Nucicar Power Reactors" The Office of Management and 3udget (0MB) approved the resubmittal of the information collection requirements contained in 10 CFR 52 after having rejected the initial submittr.l. The clearance was approved for the full three years with an estimated annual respondent burden of 22,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.
- 2. Maintenance Rule The draft final rule and draft regulatory guide,10 CFR 50.65,
" Requirements for Maintenance Programs of Nuclear Power Plants," have been submitted to the Conrnission (SECY-89-143). A decision to publish either a rule or a policy statement is still pending.
- 3. Probabilistic Risk Assessment Status Information System The physical database design, online screen program specifications and batch report specifications have been completed. Programming for online screens is 85 percent complete and unit testing of those programs has begun. A meeting with RES was held to develop a plan for data collection and entry.
- 4. Workload Information and Scheduling Program (WISP)
As the result of IRM's presentation of a Shared Data alternative to the Local Area Network (LAN)-based WISP implementation, NRR has funded a two-month prototype project. This project will demonstrate IRM's ability to develop SINET systems with a PC-based user friendly interface using Cullinet's " Cooperative Processing" capability. At the conclusion of the two-month period, NRR will determine which approach (Mainframe versus LAN) is the best vehicle for WISP. The prototype team is assigned and work is started.
- 5. NRC Paper Presented at NESC Conference Emily Robinson, IRM, attended the National Energy Software Center (NESC) conference May 15-17 at Argonne Nationpl Laboratory in Chicago, Illinois.
Ms. Robinson presented a paper written by her and Pat Bell of IRM on the history of NRC involvement with Center.
ENCLOSURE H MAY 19, 1989
0FFICE OF PERSONNEL ITEMS OF INTEREST Week Ending May 19, 1989 The Agency was saddened by the untimely death of Thomas Loy, RII.
Arrivals The following new employees reported this week:
Barry Kaufer, Reactor Systems Engineer (PFT), AE0D Matthew Guarini, Technical Intern (0PFT), NRR Departures Gaston Fiorelli, Resident Inspector (Nuclear Engineer) (PFT),
retired from RV.
Vicki Gordy, Secretary (PFT), RIV, transferred to the Department of the Army.
j MAY 19, 1989 ENCLOSURE J l
i Office of Enforcement Items of Interest f For the week ending May 19, 1989 Significant Enforcement Actions A Notice of Violation and Proposed Imposition of Civil Penalties in the amount of $500,000 was issued on May 18, 1989 to Virginia Electric and Power Company (Surry Power Station). The action was based on a major breakdown in the control of licensed activities, including the self-identification of deficiencies, conduct of appropriate evaluations, and institution of prompt and adequate corrective actions. (EN89-54)
A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of
$2,500 was issued on May 18, 1989 to Rappahannock General Hospital, Kilmarnock, Virginia. The action was based on an incident in which the NRC-required record of a quarterly Radiation Safety Committee meeting wasAn fabricated 01 by copying the investigation minutes of a previous meeting and altering the date.
determined that the fabricated record represented a meeting that, in fact, had not been held; however, the investigation could not determine who was responsible for the fabrication. (EN88-287)
Civil Penalties Paid Arkansas Power and Light Company, Arkansas Nuclear One Units 1 and 2, paid the civil penalty in the amount of $175,000. The action was based on two problems.
The first involved the licensee's failure to take adequate corrective actions for various identified conditions adverse to quality. The second problem involved various violations in which the licensee failed to properly control safety-related equipment. (EA88-284)
Duke Power Company, Oconee Units I, 2, and 3, paid the civil penalty in the amount of $25,000. The action was based on the failure to have two independent reactor building cooling trains operable as required. (EA89-32)
St. Agnes Medical Center, Philadelphia, Pennsylvania, paid the civil penalty in the amount of $2,500. The action was based on violations which indicated a significant lack of attention to and control of licensed activities by the Radiation Safety Officer, the Radiation Safety Committee, and Medical Center management. (EA88-298)
ENCLOSURE L MAY 19, 1989 f
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OFFICE OF CONSOLIDATION Items of Interest Week Ending May 19, 1989 TWFN Hearing Follow-up The Montgomery County Planning Board has scheduled a hearing on Thursday, i June 1, 1989 to review and clarify the conditions attached to the approval of the second building subdivision and site plan. l I
Following the vote to approve, on April 13, 1989, the developer indicated that the conditions imposed by the Board were either not clear or onerous to the extent that the developer would not proceed. Discussions followed. The developer requested clarification of the conditions. Any change in the con-ditions approved by the Board in a formal hearing require a new hearing and formal vote of the Board.
A specific time of day for the hearing probably will not be known until about Friday, May 26.
Drinking Fountains New certified lead-free chilled water fountains manufactured by Halsey-Taylor began arriving at OWFN last week. As of May 18 twenty-one of the forty-one replacement fountains had been received. The new fountains will be installed shortly and will be tested thoroughly before being put into general use.
Bottled water will remain available until tests of the newly installed fountains have been completed and verified showing lead levels below the Federal standard threshold of 50 parts per billion. ;
i ENCLOSURE M MAY 19, 1989
REGION I Items of Interest Week Ending Hay 19, 1989
- 1. DESIGN DEFICIENCY AT INDIAN POINT 2 An NRC team inspection at Indian Point 2 during the first week of May identified a design deficiency in the undervoltage (UV) detection circuit that could prevent the required safeguards equipment from sequencing onto the Emergency Diesel Generator (EDG) powered 480 Volt busses when required.
The undervoltage detection circuits for each of the four 480V safety busses include UV relays to detect undervoltage on the 480V busses. These circuits also control load shedding of the 480V busses, starting of the EDGs and sequencing of the safeguards loads onto the 480V busses. The four UV detection circuits are connected to a transfer switch that can be positioned to enable determination of the voltage on any of the four 480V busses. Upon loading of the EDGs.,a postulated single failure in the switch could lead to deenergization of several of the UV detection circuits thus preventing the associated safeguards loads from sequencing onto the 480V busses. The licensee has been asked to address this concern before startup from the'r current refueling outage.
- 2. INDIAN POINT 2 STEAM GENERATOR SHELL CRACKING Consolidated Edison Company is currently repairing cracked welds in the Indian Point Unit 2 steam generator shells and is considering performing a mid cycle inspection to confirm that cracking will not reoccur during the next operating cycle. In 1987 cracks were found on the inside surface of all four steam generator shells in the area of the girth weld that joins the upper and lower section of the steam generator just above the tube bundle. The cracks were removed by grinding during the 1987 outage and the plant was restarted on the basis that improved water chemistry would eliminate the cracking. However, new cracks were identified in the same areas in all four steam generators during this outage.
The licensee and Westinghouse have concluded that the cracking is due to corrosion assisted fatigue resulting from thermal stratification that occurs when colder auxiliary feedwater is fed into the steam generator during hot standby condition and other feedwater transients. Flow resistance plates in the annulus between the steam generator shell and wrapper inhibit effective mixing and cause thermal stratification at the girth weld location. In addition to grinding out the cracks and performing weld repairs in the worst affected steam generator (No. 22), the licensee plans to remove the flow resistance plates prior to returning to power.
There may be a generic concern for plants operating with flow resistance plates installed.
- 3. JAPANESE DELEGATION A delegation from Japan visited Region I on May 18, 1989 and received a presentation from the Division of Reactor Projects in regard to the resident inspector program and inspection interfaces with Headquarters.
A tour of the Salem facility was conducted in the afternoon.
ENCLOSURE N MAY 19, 1989
te .
g REGION I 1
' Items of Interest ,.
Week Ending May 19, 1989
/
- 4. UPDATE ON STATUS OF SAFETY LIGHT ORDER
]
-The following items of interest have occurred in the last month with l respect to the Order issued on March 16, 1989 to Safety Light Corporation ij and nine other entities relative to the Safety Light facility in q Bloomsburg, Pennsylvania, a contaminated site,
- 1. One of 'the original recipients of the Order, Pinnacle Petroleum, Inc.,
petitioned to be deleted from the Order. After review of the reasons provided, the staff granted Pinnacle's request on April 24.
- 2. Counsel for the remaining parties requested a one-month extension for submission of the site characterization plan which was due May 1.
Following negotiations, the staff granted the extension in exchange for an agreement by the parties to submit certain information..
- 3. An inspection of current operations of the Safety Light facility on April 25 revealed no safety problems or radiation releases in excess of regulatory limits.
- 5. CALVERT CLIFFS A delegation from the USSR toured the Calvert Cliffs facility and received presentations from Baltimore Gas and Electric and from the NRC.
Mr. Samuel Collins, Deputy Director, Division of Reactor Projects represented Region I.
ENCLOSURE N MAY 19, 1989
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ITEMS OF INTEREST j REGION Il q WEEK ENDING: MAY.19, 1989
~1. FP8L' Discusses Corrective Actions in Operator Training and Requal On May 15, representatives of the Florida Power. and Light Company-
-were in the Region II Office to attend a meeting regarding long-term corrective' actions-to their operator training program and to discuss operator licensing requalification examination-issues at their Turkey Point Nuclear Power Station.
2.. Funeral Services Held.for Region II Branch Chief On May 17, funeral services for Thomas N.- Loy, Chief, Resource Managerent Branch, DRMA, were held in Mableton, Georgia.
Mr. Loy, age 45, died of cancer on May 15.
- 3. International Visitors On May 18, a delegation from the Soviet Union, accompanied by the Director Office of. Governmental and Public Affairs; and a member of his staff, were in the Region II Office to tour the office and L neet with. senior management regarding the proposed inspector L'
' exchange program to develop a mutual understanding of the inspection and regulatory processes.
ENCLOSURE N MAY 19, 1989
Region III Items of Interest Week Ending May 19, 1989
- 1. Operational Safety Review Team (0SART) Inspection l The Regional Administrator and members of the R ajonal and Headquarters staffs represented the NRC at the opening of tF: <5 ART inspection May 15, 1989, conducted under the auspices of the International Atomic Energy Agency (IAEA), at the Byron Nuclear Power Station. The inspection by a 15-member team of international representatives will end June 2,1989.
The OSART inspection is not intended to determine the plant's compliance with NRC requirements, but rather to provide an exchange of knowledge, experience, and best international practices between the safety experts on the team and plant personnel. The Byron visit is the 34th OSART review and the second one in the United States since the program was started by the IAEA in 1983.
- 2. Senior Management Meeting The semiannual Senior Management Meeting was conducted in Region III on May 17 and 18, 1989. Chairman Zech attended the opening session of the meeting. Other attendees were the EDO, the Deputy ED0's, the Office Directors and the Regional Administrators.
- 3. Allied Signal, Inc.
A major team inspection is being conducted from May 15-19, 1989 at the licensee's facility in Metropolis, Illinois. Team members include representatives from Region III, NMSS, the Environmental Protection Agency, the Department of Energy, and the Occupational Safety and Health Administration. The inspection is focusing on operational safety and will be providing input for license renewal.
I 4. Palisades On May 16, 1989, Mr. Edward Greenman, Director, Division of Reactor Projects, Mr. Richard Cooper, Chief of the Engineering Branch of the Division of Reactor Safety and other Region III staff, met with Consumers Power Company at the plant site for the regularly scheduled quarterly management meeting.
The purpose of the meeting was to discuss the status of the design l reconstitution effort, the response to the maintenance team inspection findings, the steam generator tube plugging and cracking issue and the corrective actions for the major contamination event that occurred last j year.
l MAY 19, 1989 ENCLOSURE N 1
- 5. Veterans Administration Hospital, Hines, Illinois During the course of a routine inspection conducted on May 17, 1989, Region III Radiation Specialists identified that manufacturing recommended service of the licensee's teletherapy unit was significantly overdue bringing into question safe operability of the unit. Region III management has been in contact with the hospital administrator to discuss prompt corrective action which may involve therapy facility shutdown. The facility currently treats approximately 40 patients ;
daily. l l
l MAY 19, 1989 ENCLOSURE N
_ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ . _ _ _ _ _ _ _ _ . __-__-____ _ ____ _ _ _ _ _ _ _ __ - a
4 REGION IV WEEKLY INFORMATION REPORT Week Ending May 19, 1989
- 1. USAF HP AND Bioenvironmental Engineering Symposium The regional Enforcement Officer participated in a U.S. Air Force -
Health Physics and Bioenvironmental Engineering Symposium on May 16, 1989, at Brooks Air Force Base near San Antonio, Texas.
He delivered a ger,eral talk on the NRC's enforcement policies.
- 2. Region IV Utilities Group Meeting .
The Region IV Utilities Group (RUG) met in Arlington, Texas, on May 17-18, 1989. During the morning of May 18, representatives from Region IV Division of Reactor Projects, Division of Reactor Safety, and Division of Radiation Safety and Safeguards met with the Region IV RUG to discuss issues of common interest. Project Directorate IV, NRR, participated in the discussion.
l l
MAY 19, 1989 ENCLOSURE N I
l -
Region V Items of Interest Week Ending May 19, 1989
- 1. San Onofre Nuclear Generating Station, Unit 1 During the evening of May 16, 1989, the licensee initiated a restart of San Onofre Unit i following completion of the Cycle X refueling outage.
This outage also involved resolution of questions regarding three broken mounting bolts for the thermal shield and a number of other technical issues identified during the outage. During the startup on May 16, however, the licensee concluded that the newly installed intermediate range nuclear instrument (NI) channels were not sufficiently stable and could generate a startup rate trip. Licensee management decided to abort the startup at that point. The unit remains in Mode 3, with additional troubleshooting of the NI system in progress.
- 2. Rancho Seco Nuclear Generating Statio_n, On Thursday, May 18, 1989, the Board of Directors of the Sacramento Municipal Utility District voted three to one (with one Director abstaining) to approve a Memorandum of Understanding with Babcock &
Wilcox and Bechtel Power Corporation to enter into a "long-term teaming arrangement" for the operation of Rancho Seco. The proposed arrangement does not include equity participation by Babcock & Wilcox or Bechtel.
ENCLOSURE N MAY 19, 1989
4 I
I 1
EXECUTIVE DIRECTOR FOR. OPERATIONS Week Ending May 19, 1989
+
GA0 Entrance Meeting on May 10, 1989 GA0 conducted an entrance meeting at the NRC on May 10, 1989 concerning an au dit GAO is conducting for Congressman Dingell. The purpose of the meeting was to introduce the audit areas and to identify the necessary points of contact within the NRC. Four audit areas were discussed. The first three dealt with stainless steel piping: thermal fatigue cracking and its' impact on the leak-before-break analysis methodology; NRC and.
industry research and development in the area; and stress corrosion cracking. The fourth area was the NRC's program and activities inThethe area of vendors supplying counterfeit and substandard materials. 4 staff volunteered to provide background documents and identified points of contact. The effort is expected to continue over the summer with the report to be issued in the fall.
I MAY 19, 1989
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1 j
19, 1989_
ITEMS ADDRESSED BY THE COMMISSION - Week Ending May A. STAFF REQUIREMENTS - BRIEFING ON STATUS OF OPERATO 10, 1989, IN THE AREA 0F REQUALIFICATION EXAMS, 2:00 P.M., WEDNESDAY, MAY '
COMMISSIONERS' CONFERENCE ROOM, ONE WHITE FLINT NORTH, ROCXVI l 10 PEN TO PUBLIC ATTENDANCE - SECY to V. Stello, Jr., EDO dated S/17/89 The Commission
- was briefed by the staff on the program.
The Commission requested the staff to closely monitor thethe operator training program at Turkey Point and to re reactors, on the licensee's performance, the license assure safe plant operation.
- Commissioners Carr and Rogers were not present.
B.
STAFF REQUIREMENTS - NPOC BRIEFING ON THE STATE OF THE NUCLEAR 10:00 A.M., WEDNESDAY, MAY 10, 1989, COMMISSIONERS' LONFERENCE ROO '
WHITE FLINT NORTH, ROCKVILLE, MARYLAND (OPEN TO PUBLIC ATTENDANCE -
SECY to V. Stello, dated 5/17/89 The Commission
- was briefed by representatives of the Nuclear j Power Oversight Committee (NPOC) on the industry's perspective f of the state of the nuclear industry.
Presentations were made by the following industry representatives:
- Joseph M. Farley l
}
Chairman, Nuclear Power Assembly Executive Vice President - Nuclear The Sputhern Company .
- J. Phillip Bayne President and CEO New York Power Authority
- James J. O' Conner Chairman and CEO Commonwealth Edison Company There were no requirements placed on the staff at this meeting.
- Commissioners carr and Rogers were not present.
l MAY 19, 1989 ENCLOSURE P L_______-_-__-_-_--________
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. C. STAFF REQUIREMENTS - PERIODIC BRIEFING BY ADVIS0RYN NUCLEAR WASTE (ACNW),
10:30 A.M., THURSDAY, APRIL 27, 1989, COMMISSIONERS' CONFERENCE ROOM, ONE WHITE i FLINT NORTH, ROCKVILLE, MARYLAND (OPEN TO PUBLIC ATTENDANCE) - SECY to V. Stello, dated 5/17/89 The Commission
- met with the Advisory Committee on Nuclear Waste (ACNW) to discuss nuclear waste related issues before the commission.
The Commission expressed interest in receiving future comments and recommendations from the ACNW on the following topics:
- a. Issues raised by the State of Nevada (i.e., active tectonism, .
recent volcanic activity, and mineral resources) in regard to 1 the Yucca Mountain site for the DOE repository of nuclear waste.
- c. Whether the NRC is providing sufficient and timely guidance 1 to DOE on performance acceptance criteria for disposal of l greater-than-Class-C wastes as progress is made in this area. ~
- d. Alternative options for disposing greater than class-C-waste, including sealed sources returned to DOE, in other than the nuclear repository at Yucca Mountain, should the capacity of the repository be less than expected.
- e. The extent to which the application of the Resource Conservation Recovery Act (RCRA) requirements to the disposal of mixed waste would afford a significant increase in protection of the public health and safety'over and above that provided under 10 CFR Part 61.
- f. Anticipated interface between the ACNW and the Nuclear Waste Technical Review Board.
- g. The potential usefulness of conducting a probabilistic risk assessment (PRA) study on the HLW repository facility.
- h. The extent to which NRC staff needs to develop an independent capability for modeling and repository site.
- Commissioner Carr was not present.
ENCLOSURE P MAY 19, 1989
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