ML20247N266
| ML20247N266 | |
| Person / Time | |
|---|---|
| Issue date: | 03/29/1989 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-890329, NUDOCS 8904060228 | |
| Download: ML20247N266 (29) | |
Text
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b(Nk March 29, 1989 For:
The Commissioners From:
James L. Blaha, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING MARCH 24, 1989 A summary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.
Contents Enclosure Nuclear Reactor Regulation A
Nuclear Material Safety and Safeguards B
Nuclear Regulatory Research C
Analysis and Evaluation of Operational Data D
Governmental & Public Affairs E
General Counsel F*
Administration G
Information Resources Management H
Controller I*
Personnel J
Small & Disadvantaged Business Utilization & Civil Rights K*
Enforcement L
Consolidation M*
Regional Offices N
Executive Director for Operations 0*
Items Addressed by the Comission P
Meeting Notices Q
Proprietary or Other Sensitive Information (Not for R
externaldistribution) 4
- No input this week.
Jalne aha, Assistant for Operations ffice of the Executive Director for Operations g
James L. Blaha, OED0
~
8904060228 890329 PDR COMMS NRCC WEEKLYINFOREPT PDC R
HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING MARCH 24, 1989 H. B. Robinson CarolinaPower&LightCompany(CP&L),licenseeforHBRobinson(HBR) completed the first transfer of a spent fuel canister from the Spent Fuel Building, to its newly const-ucted independent spent fuel storage installation (ISFSI) at the HBR Unit-2 site : March 16, 1989. The ISFS! is a dry modular storage system licensed in 1986 to handle and store dry shielded storage canisters containing spent fuel assembles from HBR Unit-2. The ISFSI is part of a dry storage demonstration program jointly participated in by CP&L EPRI and DOE. Region II and NMSS have closely monitored this first transfer.
Quality Assurance Meetings with DOE High-Level Waste Management staff met with DOE staff and contractors at Las Vegas, Nevada on March 22, 1989 for two to determine which areas of the Design Acceptability Analysis (DAA) purposes:for the exploratory shaft facility need to be examined in an upcoming on-site review 6nd to participate in the monthly qv611ty assistance (QA) status meeting. At the request of the NRC, DOE performed the DAA to evaluate the adequacy of the certain design information provided in theSiteCharacterizationPlan(SCP). The DAA is a part of the staff's review of the SCP. The DAA on-site review is tentatively scheduled for April and will examine supporting documentation for the submittal that was provided to the staff in January. At the monthly status meeting, DOE will review progress it is making in qualifying its QA program and the NRC staff will review progress in completing its review milestones.
ASNT Spring Meeting-Task Force on National Certification of Radiographer Vandy Miller, Assistant Director for State Agreements, participated in the American Society of Nondestructive Testing (ASNT) Spring Meeting on March 20-23, 1989 in Charlotte, North Carolina. Mr. Miller was a guest speaker and panel member on radiographer safety. Mr. Miller also participated in the Task Force on National Certification of Radiographer meeting on March 21, 1989. The NRC position is that the Conference of Radiation Control Program Directors (CRCPD) will work with ASNT and the State of Texas in brokering the Texas test to those interested States desirous of Regulators administering the test. This will be for both NRC Agreement, as well as Non-Agreement States.
ASNT will administer the test to those States not desirous of CRCPD. The ASNT Board adopted the NRC position.
Accident Management On March 15, 1989 NRC staff met ~with representatives of NUMARC and EPRI. The principal purposes of the meeting were to discuss ongoing and planned NRC accident management research and its relation to NUMARC and EPRI plans. Presentations were made by NRC staff on studies to evaluate (1) depressurization of the RCS as a means to prevent rapid containment pressurization by direct containment heating, (2) Information needs of plant operations staff to effectively manage i
severe accidents and (3) problems of possYe recriticality if a damaged core is reflooded following melting of the control materials.
Plans were described for further evaluation of " Generic Accident Management Procedures for Near Term Evaluation and Implementation" presented in Table 1 of SECY-89-012, "Stafi Plans for Accident Mahagement Regulatory and Research Program." In addition, RES presented plans to provide industry with guidance on elements of a utility accident management plan as described in SECY-89-012.
i Office of Nuclear Reactor Regulation Items of Interest Week Ending March 24, 1989 Peach Bottom The ACRS has issued its letter, dated March 14, on Peach Bottom following its Subcommittee and full Committee meetings of March 8 and 9.
The ACRS stated that it found no reason to disagree with the staff's position that, subject to completion of certain well defined commitments to I
modifications of equipment and revision of procedures, the licensee can safely operate Peach Bottom. Although the staff did not present such a conclusion as a final conclusion of either the staff or the Commission the ACRS reached its conclusion based on the staff's presentation and on its findings developed to dated in the SER, the IATI and other activities.
The ACRS endorsed the staff's plans to continue close monitoring of operations.
The ACRS also concluded that the issues of concern to the Harford County representatives, Mark I containment and IGSCC, had been dealt with appropriately by the licensee and the staff.
H. B. Robinson Carolina Power & Light Company (CP&L), licensee for HB Robinson (HBR) completed the first transfer of a spent fuel canister from the Spent Fuel Building, to its newly constructed independent spent fuel storage installation (ISFSI) at the HBR Unit-2 site on March 16, 1989. The ISFSI is a dry modular storage system licensed in 1986 to handle and store dry shielded storage j
canisters containing spent fuel assembles from HBR Unit-2. The ISFSI is part
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of a dry storage demonstration program jointly participated in by CP&L, EPRI and DOE. Region II and NMSS have closely monitored this first transfer.
Brunswick Units _1 and 2, Robinson, and Harris Carolina Power & Light Company (licensee for Brunswick Units 1 and 2, Robinson,andHarris)announcedthatonApril1,1989,Mr.L.W. Eury, Sr. Vice President Operations Support, will replace Mr. E. E. Utley, as Executive Vice President. Effective May 1, 1989, Mr. Utley will retire.
Also effective April 1, 1989, Mr. R. A. Watson, Vice President Harris Nuclear Project, will succeed Mr. M. A. McDuffie as Sr. Vice President for Nuclear Operations. Mr. Watson will assume the responsibility for Nuclear Engineering and Services and for Operations Training and Technical Support for the company's Robinson, Brunswick, and Harris Nuclear Plants. Mr. McDuffie will be responsible for Special Nuclear Projects until his retirement on October 1, 1989.
North Anna. Units 182 As noted previously, the February 25, 1989 SGTL in the NA-1 SG "C,"
Row 3 Column 60 (R3C60) was caused by the upper portion of a SG plug on the hot MARCH 24, 1989 ENCLOSURE A
.- leg side breaking loose and being propelled up the hot leg side, puncturing the tube approximately 4 inches above the seventh support plate at the U-bend
)
tangent and denting a companion tube, R4C60.
j Although the February 25, 1989 SGTL occurred in the NA-1 SG "C", the licensee's recovery plan (outside of basic investigative actions) is now centered on NA-2.
NA-2 is presently in a refueling outage with restart scheduled for April 21, 1989.
The licensee's four nuclear units, Surry 1&2 and NA-1&2 are all presently shut down with NA-2 being the unit most likely available for restart in the near future.
It is noted that these four units supply about 40% of the licensee's j
grid power demands.
l The licensee has determined that about 50 of the susceptible W plugs are in place in the NA-2 SG's.
NA-1 has approximately 300 of the susceptible 31ugs in place.
The licensee and W are evaluating nine different types of plugs w1ich could be inserted into the susceptible plugs.
In addition, the licensee has mobilized a
" plug removal team" to evaluate better methods of removing plugs. As noted previously, removing the susceptible plugs in NA-1 SG "C" has been found to be a difficult process involving significant radiation doses.
Based on pulling the i
plugs on the hot leg and cold leg side from the above tubes, the licensee has j
determined that pulling 50 plugs with a 10% failure rate represents a dose rate j
of 69 man-rem. When a susceptible tube cannot be easily removed, three " jumps" have been required. One " jump" is equivalent to a personnel entry in the channel head of a SG. One entry into the channel head is equivalent to 300 mrem per minute. The " shine" from standing in front of a SG manway is about li rem per hour. Therefore, the licensee is also considering the use of robotics for any remedial recovery effort.
Meanwhile the licensee's investigation of NA-1 SG "C" tubes R3C60 and its companion tube R4C60 is progressing. Electron microscope photographs now available indicate 360* circumferential pure water stress corrosion cracking for a major portion of the fracture surface of the break in the plug.
It appears at-this time that a small 360* circumferential ligament was intact prior to the break. Laboratory examination (less than or equal to 3000X magnifi-cation) shows intergranular cracks and it is believed these cracks are associated with a minimal intergranular carbide precipitation which is most likely due to low mill anneal temperature. At this time it appears that E plugs from heat Nos 3513 and 3962 exhibit the susceptib'le microstructure.
It is noted that the NA-1 broken plug comes from heat No. 3513.
The licensee's original intent to pull tube R3C60 is no longer considered viable because of the location of the break in the U-bend region.
ECT probes of the dented tube R4C60 are progressing slowly since a probe with a passable inner diameter has not yet been found. The licensee has made preliminary calculations of the velocity of the upper portion of broken plug.
Based on "no friction calculations" the lower bound is calculated to be 300 ft per see and the upper bound to be 2800 ft per sec. For the lower bound, this equates to a minimum of 50 foot-pounds of force required to puncture tube R3C60.
The NRC staff will meet with W on March 23, 1989 at 10:00 a.m. in Room 10/B/11 to discuss the generic aspects of these matters.
In addition, there will be a subsequent meeting with VEPC0 to discuss the NA-1&2 event and recovery plans.
This meeting will take place when the licensee and W have reached conclusions and proposed acceptable fixes for resolution of the NA SGTL.
MARCH 24, 1989 ENCLOSURE A
Office of Nuclear Material Safety and Safeguards Items of Interest Week Ending Narch 24, 1989 Safeguards Transportation Modal Study Workshop On March 14-15,'1989, staff from Division of Safeguards & Transportation (SGTR) and Lawrence Liveenc m National Laboratory (LLNL) met with the Western Interstate Energy Board's (WIEb';) High-Level Waste Committee to provide a i
technical briefing on the Modal Study. The Modal Study was completed in 1987 by LLNL, and evaluated the performance of spent fuel packages, designed to i
NRC's standards, under actual transportation accident. conditions. The WIEB Committee consists of technical and policy-level people from western states with an interest to enhance western state's understanding of issues relateo to the transport of spent fuel and other radioactive waste.
Low-Level Waste Pathfinder Decommissioning Northern States Power Company (NSP) is preparing an application for authorizing decommissioning by dismantlement of the remaining portions of the Pathfinder Plan Nuclear Facility, in Sioux Falls, SD. NSP is planning on a June, 1989
. submittal, and has requested a discussion meeting at OHFN on April 27, 1989.
The meeting would be to receive further guidance on the content of the Decommissioning Plan and supporting Environmental Report. NSP has been requested to specifically discuss plans for waste classification of the reactor vessel and internals. NSP is being assisted by Black and Veatch, which is providing support with architect-engineering efforts and document preparation.
Industrial and Medical Nuclear Safety i
Fuel Cycle Safety Meeting with Swedish Firm on Spent Fuel Storage 20, 1989, NRC staff met with representatives of the Swedish Nuclear Fuel On March and Waste Management Ccmpany to discuss allowance for burnup credit in spent fuel storage criticality analysis. The Swedish staff were interested in discussing this matter because they are considering the use of allowance for burnup credit in expanding the spent fuel storage capacity of Sweden's facility for central interim storage of spent fuel (CLAB) at the Oskarshamn nuclear power plant site.
The present CLAB capacity is 3000 tones of spent fuel.
MARCH 24, 1989 ENCLOSURE B
liigh Level Waste Management Quality Assurance Meetings with DOE High-Level Waste Management staff met with DOE staff and contractors at Las Vegas, Nevada on March 22, 1989 for two purposes:
to determine which areas of the Design Acceptability Analysis (DAA) for the exploratory shaft facility need to be examined in an upcoming on-site review and to participate in the monthly quality assistance (QA) status meeting. At the request of the NRC, DOE performed the DAA to evaluate the adequacy of the certain design information provided in theSiteCharacterizationPlan(SCP). The DAA is a part of the staff's review of the SCP. The DAA on-site review is tentatively scheduled for April and will examine supporting documentation for the submittal that was provided to the I
l staff in January. At the monthly status meeting, DOE will review progress it is making in qualifying its QA program and the NRC staff will review progress in completing its review milestones.
i MARCH 24, 1989 ENCLOSURE B
Office of Nuclear Regulatory Research Items of Interest Week Ending March 24, 1989 PREVENTING DAMAGE TO REACTOR CORES B&W Once Through Steam Generator (OTSG) Data Needs NRC staff and the Babcock and Wilcox Owners Group (B&WOG) met in Rockville on March 17, 1989, to discuss the conclusions and recorsnendations of the OTSG Technical Advisory Group (TAG) report. The OTSG TAG is a joint NRC/ Industry group formed in October 1987, to investigate thermal-hydraulic issues and data needed to further the understanding of the Babcock and Wilcox OTSG behavior under transient or accident conditions. The report is e culmination of all the work completed under the TAG, and it is expected to be published by the end of March 1989.
The NRC and the B&WOG agreed to endorse the TAG findings. With respect to whether additional experimental data is needed or not, the TAG concluded that (1) although there is little prototypic data related to OTSG auxiliary feedwater (AFW) behavior under transient and accident conditions, best-estimate code sensitivity studies showed that detailed knowledge of AFW behavior in an OTSGisnotrequiredfortransientpredictions;(2)certainOTSGgeometry dependent thermal-hydraulic phenomena, most of which are associated with OTSG depressurizhtion resulting in excess steam flow (e.g. entrainment, de-entrainment, liquid carryover), were found to have data deficiencies. The data deficiencies identified are only needed for assessment of best-estimate thermal-hydraulic code predictions of some B&W transients, but are not required for licensing purposes. The B&WOG agreed to go forward in a joint effort with NRC to obtain In the next few months NRC will work with the necessary(experimental data.B&WOGandtheElectricPowerResearchInstitute)to the industry how best to initiate an experimental program as identified by TAG.
Multi-Loop Integral System Test (MIST) Program Management Group (PMG) Meeting A MIST PMG meeting is scheduled for April 6,1989, at the B&WOG office in Rockville, Maryland. The MIST PMG meets three to four times a year to review the status of the MIST project. The MIST facility is designed to simulate thermal-hydraulic best-estimate codes in predictin i
d providing the Small Break Loss-of-Coolant Accident (SBLOCA) g B&W trans ents an data base necessary to satisfy NUREG-0737 (Clarification of THI Action Plan Requirements). This program is jointly sponsored by NRC, B&W Company, B&WOG, and EPRI. At this meeting, the PMG will provide all the comments needed for B&W to publish the 11 reports related to the MIST project. These reports incluce sunmary of the findings from all the testing, data and analyses of all the tests, and code comparisons against selected tests.
In addition, the PMG will review the B&W planning for the three remaining
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tests scheduled for the MIST facility. These tests will be completed by the summer r
I of this year. This contract is scheduled for closeout by the end of 1989.
(See Meeting Notices)
I ENCLOSURE C f
MARCH 24, 1989 L
2 1
Accident Management On March 15, 1989 NRC staff met with representatives of NUMARC and EPRI. The principal purposes of the meeting were to discuss ongoing and planned NRC accident management research and its relation to NUMARC and EPRI plans. Presentations were made by NRC staff on studies to evaluate (1) depressurization of the RCS
. as a means to prevent rapid containment pressurization by direct containment heating, (2) information needs of plant operatiens staff to effectively manage severe accidents and (3) problems of possible recriticality if a damaged core 1
is reflooded following melting of the control materials.
Plans were described for further evaluation of " Generic Accident Management Procedures for Near Term Evaluation and Implementation" presented in Table 1 of SECY-89-012, " Staff Plans for Accident Management Regulatory and Research Program."
In addition, RES presented plans to provide industry with guidance on elements of a utility accident management plan as described in SECY-89-012.
l 1
i i
ENCLOSURE C MARCH 24, 1989
Office for Analysis and Evaluation of Operational Data Items of Interest Week Ending March 24, 1989 Operational Assessment On March 23 and 24 the Brunswick Diagnostic Evaluation Team conducted its initial kick-off meeting. The meeting included briefings by NRR project personnel, Region II management and the Director, AE00. The diagnostic is scheduled to begin onsite the week of April 10, 1989.
On March 23, IRB staff met with NRR and RES in the first working group session to review the basic NRC guidance for protective actions in response to a severe nuclear power plant eccident.
Preliminary Notifications The following Preliminary Notifications were issued during the past two weeks.
a.
PNO-III-89-19, XRI Testing, Inc., Troy, Michigan, Stuck Radiographic Source.
b.
PNO-V-89-17, Arizona Nuclear Power Project, Palo Verde Unit 2, Shutdown of Palo Verde Unit 2 to Test Atmospheric Dump Valves.
c.
PNO-V-89-18, Washington Public Power Supply System, WNP-2, Unusual Event Due to Discovery of Nonconservative Assumptions in Post-Accident Control Room Exposure Calculations, d.
PNS-V-89-03, Southern California Edison Company, San Onofre Nuclear Genera _ ting Station, Fitness for Duty - NRC Licensed Operator Tested Positive for Controlled Substance.
ENCLOSURE D MARCH 24, 1989
4 Office of Governmental and Public Affairs Items of Interest Week Ending March 24, 1989 INTERNATIONAL PROGRAMS:
U.S. Nuclear Export Controls Meeting On March 14-17, Elaine Hemby from IP attended an interagency Technical Working Group (TWG) meeting at Battelle Pacific Northwest Laboratory to discuss the development and upgrade of NRC and Commerce Department export control lists for nuclear reactor and reprocessing technology, nuclear reactor material and equipment, and dual-use items. The meeting was attended by representatives from Lawrence Livermore, Oak Ridge National Laboratory, PNL, Argonne, LANL, Savannah River, Kirtland AFB, General Electric, Westinghouse, and the Depart-ments of Commerce and Defense. Topics discussed included the export control Nuclear Referral List upgrade, the Nuclear Technology Reference Book, and the MCTL (Militarily Critical Technologies List). A report was presented on the technical feasibility of converting the WPPSS-1 civilian power reactor to'a production facility. Other presentations covered the Soviet civilian nuclear power program, space reactors, high-temperature gas cooled reactors, and reprocessing facilities. This TWG and two others on nuclear explosive tech-nology and enrichment technology provide the technical input for the develop-i ment of U.S. export control lists on nuclear-related technology and commodities.
EXPORT / IMPORT During the past week ending March 24, 1989, applications for. export licenses were received from 1)
Edlow International for the export of 20,834 kilograms of low-enriched uranium for use as reload fuel in the ASCO Unit I nuclear power reactor in Spain.
Licenses for export / import were issued to:
1)
Mitsubishi International Corporation for export of 22,617.0 kilograms of low-enriched uranium for use as reload fuel for Sendai Unit 2, Region 7, in Japan.
2)
Mitsui&Co.(U.S.A.),Inc.forexportof 22,397.0 kilograms of low-enriched uranium for use as reload fuel for Hamaoka 2 in Japan.
3)
Mitsui & Co. (U.S.A.), Inc. for export of 9,061.0 kilograms of low-enriched uranium for use as reload fuel for Hamaoka 2 in Japan.
STATE, LOCAL AND INDIAN TRIBE PROGRAMS Rocky Mountain LLW Board Meeting j
The Rocky Mountain LLW Board met on March 16, 1989 in Montrose, Colorado. The i
Board received testimony from New Hampshire and Puerto Rico on why they should MARCH 24, 1989 ENCLOSURE E
2 not be found in noncompliance with the 1988 milestone in the Low-Level Radio-active Waste Policy Amendments Act of 1985. Vermont did not send a represen-tative, but provided written testimony. The Board voted to deny New Hampshire, Vermont and Puerto Rico access to the Beatty LLW facility for being in non-compliance with the Act. The Board also discussed proposals to contract to accept LLW from New Hampshire, Rhode Island, Vermont, Puerto Rico and the District of Colunbia. The Rocky Mountain Board did not make any decisions on this matter at the meeting, but directed the Executive Director on the Board to encourage the negotiation of contracts with these five entities.
Colorado Radiation Control Program Review Robert Doda, Region IV State Agreements Officer, Joel Lubenau and Donald Mackenzie, SLITP, began a review of the Colorado Radiation Control Program on March 20-24, 1989 in Denver, Colorado. The review continues on April 3-7, 1989.
ASNT Spring Meeting-Task Force on National Certification of Radiographer Vandy Miller, Assistant Director for State Agreements, participated in the American Society of Nondestructive Testing (ASNT) Spring Meeting on March 20-23, 1989 in Charlotte, North Carolina. Mr. Miller was a guest speaker and panel member on radiographer safety. Mr. Miller also participated in the Task Force on National Certification of Radiographer meeting on March 21, 1989. The NRC position is that the Conference of Radiation Control Program Directors (CRCPD) will work with ASNT and the State of Texas in brokering the Texas test to those interested States desirous of Regulators administering the test. This will be for both NRC Agreement, as well as Non-Agreement States.
ASNT will administer the test to those States not desirous of CRCPD. The ASNT Board adopted the NRC position.
CRCPD Regional Meeting Jack Hornor, Region V State Agreements Officer, participated in the Conference of Radiation Control Program Directors, Inc. Regional Meeting on March 20-22, 1989 in Vancouver, Washington. Mr. Hornor gave a presentation on the status of NRC and SLITP activities in materials regulation.
DOE HLW Public Meetings Rosetta Virgilio, SLITP, and Dean Kunihiro, Region V State Liaison Officer, attended the Department of Energy's (DOE) public hearings on March 21, 1989 in Las Vegas, Nevada and on March 23, 1989 in Reno, Nevada. The purpose of these hearings was for DOE to inform residents about the site characterization plan and to receive comments from the public on DOE's plans for developing a high-level radioactive waste disposal facility at Yucca Mountain. These public hearings are required by the Nuclear Waste Policy Act. Senator Richard Bryan and Acting Governor Robert Miller made opening statements opposing the Yucca Mountain Site at the Las Vegas meeting. Senator Harry Reid submitted a written statement which also opposed the site.
Meeting at FEMA Region Charles Hackney, Region IV State Liaison Officer, attended a meeting at the Federal Emergency Management Agency (FEMA) Region VI office on March 21, 1989 MARCH 24, 1989 ENCLOSURE E
1 3
in Austin, Texas. The purpose of the meeting was to plan an emergency planning workshop with FEMA and State officials. The workshop is scheduled to be held on June 7-9, 1969 in Austin, Texas.
Iliinois Radiation Control Program Review Visit l
B.J. Holt, Region III State Agreements Officer, performed a program review visit of the Illinois Radiation Control Program on March 22-24, 1989 in Springfield, Illinois. The purpose of a review visit is to assess the status of the State's radiation control program and to assist the State in preparing for a routine review.
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MARCH 24, 1989 ENCLOSURE E
Office of Administration Items of Interest Week Ending March 24, 1989 1.
A contract was signed this week for installation of a 15 ton air conditioner and six stabilizing transformers to support the Otis elevators at OWFN. This equipment should prevent reoccurrence of the elevator problems experienced last summer.
2.
Draft NRC Acquisition Regulations have been submitted Offices and Regions for review and comment.
3.
Meetings were held March 22 with DOE Security personnel to discuss procedures for personnel security processing.
4.
A Rideshare Day Bethesda will be conducted in the Phillips Building Lobby on April 5, 1989. This action is in accord with our commitment to Montgomery County to encourage alternatives to single occupant driving.
Significant F0IA Requests Received for 5-Day Period of March 17, 1989 - March 23. 1989 Request for a copy of the bidders list for RFP RS-ARM-89-170. (Verda liullings, InternationalComputers& Telecommunications,Inc.,F01A-89-115)
Request for all records relating to decommissioning, termination of operations, accruals, or operating costs which refer to the licensee for the Vermont Yankee nuclear power plant and other specified utilities. (Barbara Cannon of Davis, Graham & Stubbs, F01A-89-ll7)
AmericanTesting& Inspection}Inc.(pectionReportandNo Request for a copy of the Special Ins Ronald Preston, American Testing &
Inspection, Inc., F01A-89-123 Request for copies of contract No. NRC-02-88-004 and the successful proposal.
(MichaelStafford,ERCInternational,F01A-89-124)
MARCH 24, 1989 ENCLOSURE G i
Office of Information Resources Management Items of Interest Week Ending March 24, 1989 1.
Master Inspection Planning System - Phase II The project team continues their work on the data and process requirements definition.
Interviews were conducted with 766 System users and support personnel to confirm the team's understanding of the 766 System requirements in areas other than power reactors. The requirements analysis is scheduled for completion on March 31, 1989.
2.
Regulatory Information Tracking System (RITS)
The first training session for the new DB2 Regulatory Information Tracking System (RITS) was given on March 20-21, 1989, by IRM personnel for Headquarters representatives from NRR, NMSS and AE00 as well as their contracted data entry support people. The training consisted of lectures and hands on training to provide the RITS user community with an understanding of the workings of the new RITS system as well as demonstrate the enhanced capabilities available by utilizing 082 (IBM's relationaldatabasemanagementsystem). The second training session was given on March 23 and 24, 1989, at Region V.
Participants included Once the training is completed p(ersonnel from Regions III, IV, and V. Region I and II will receive training on M be given approximately 3-4 weeks to further familiarize themselves with the system. RITS will become operational by late April.
3.
Professional Service Award John Skoczlas, Chief, Document Control Branch, IRM, has been selected by the Federation of Government Information Processing Councils (FGIPC) as the 1989 recipient of the IRM Professional Service Award for his outstanding contributions to the IRM community and for his work to enhance the agency's NUDOCS system. The award will be presented at the annual FGIPC Conference.
4.
IRM Help Line Meetino IRM staff met with program office ADP coordinators on March 22 to discuss the. new IRM Help Line. The service will be provided through the Information Technology Services Support Center contractor (AMCI) from the Phillips Building.
MARCH 24, 1989 ENCLOSURE H
u o
a Office of Personnel Items of Interest Week Ending March 24, 1989 Arrivals The following new employees reported this week:
Rene Cesaro, Secretary (Typing) (PFT), NRR Randy Moist, Quality Assurance Specialist (PFT), NRR Craig Hrabal, Task Manager (PFT), RES Departures Lisa K. Chan, Chemical Engineer (PFT),PFT), RES RES Cynthia L. Smith, Secretary (Typing) I Anthony J. Rizzo, Computer Assistant I,,PFT), R-III l
MARCH 24, 1989 ENCLOSURE J
v Office of Enforcement Items of Interest MARCH 27, 1989 The following Significant Enforcement Actions were taken the week of March 20, 1989 1.
A Notice of Violation' and Proposed Imposition of Civil Penalty in the amount of $50,000 was issued on March 17, 1989 to Houston Light and Power Company (South Texas Project, Unit 1). The action was based on the licensee's failure to install, prior to plant licensing in 1988, the vortex suppressors in the emergency sumps which supply the suction for the safety injection and contain-ment spray pumps in the recirculation mode.
(EN89-29)
An Order Imposing a Civil Penalty (Calvert Cliffs Units 1 and 2) on March 20 2.
in the amount of $300,000 was issued to Baltimore Gas & Electric Company 1989. The action was based on violations involving equipment qualification requirements of 10 CFR 50.49.
(EN88-31A) 3.
-A' Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $2,500 was issued to the Defense Nuclear Agency, Bethesda, Maryland on March 22, 1989. The action was based on a number of violations that included (1) failure to perform written safety evaluations, (2) procedure adherence problems, (3) failure to ensure all operators satisfactorily completed that requalification ; raining problem, and (4) discrimination, in violation of 10 CFR 50.7, against an employee who raised safety concerns.
(EN89-32) j The following Civil Penalties were paid the week of March 20, 1989 1.
Entela, Inc., Grand Rapids, Michigan, paid the civil penalty in the amount of
$1,250. The action was based on the findings that the licensee's RSO willfully failed to have eight individuals attend an approved training course in the use of moisture-censity gauges in accord 6nce with license requirements and allowed these individuals to use gauges devices without the supervision and physical presence of an individual who had received the approved training. Add'!ional violation for (1) failure to maintain adequate surveillance and conttc1 of a moisture-density gauge in an unrestricted area resulting in the gauge being run over by a construction vehicle and sustaining $3,000 in damages, (2) failure to report to the NRC Operations Center within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the event which caused dt s1X month intervals were not assessed a civil penalty. damage to property EA88-318) 2.
Brigham and Women's Hospital, Boston, Massachusettses paid t.he civil penalty in the amount of $5,000.
The action was based on failure to maintain adequate surveillance and control of a one curie gadolinium-153 source resulting in it being lost; and failure to provide adequate training to certain personnel authorized access to areas where radioactive material was located.
(EA 88-319)
MARCH 24, 1989 ENCLOSURE L
.. V t
3, Maine Yankee Atomic Power Company (Maine Yankee) paid the civil penalty in the amount of $75,000. The action was based on the failure to maintain positive control'over a ring of vital area keys, inadequate lighting in the isolation zone, inadequate escort of vehicles within the protected area, failure to maintain an open observable area in a portion of the isolation zone, and multiple examples of a failure to adequately) search personnel and packages entering the protected area.
(EA88-295 4.
Biomedical Diagnostic Services, Ltd., Troy, Michigan paid the civil penalty in the amount of $750. The action was based on failure to follow licensee's procedures in that personnel did not wear whole body and extremity dosimetry on several occasions and at several locations, did not test incoming packages of radioactive material for contamination, did not perform quarterly linearity tests the required length of time, and did not wear gloves when handling radioactive material; failure to supervise an indivicual, failure to survey and failure to perform leak tests at required frequency. The civil penalty was increased by 507 because the violations were identified by the NRC and the licensee did not provide assurance that sufficient audit capability existed to identify such violations. (EA 87-231)
Other The Department of the Air Force has responded to the Department of Justice concerning the constitutional 1ty of NRC imposing a civil penalty on them.
The staff and OGC are reviewing the Air Force's response to determine whether it should go forward with the civil penalty in the Wright Patterson matter.
1 MARCH 24, 1989 ENCLOSURE L
c Region I Items of Interest Week Ending March 24, 1989 1.
On March 21, representatives of Pennsylvania Power and Light Company (Susquehanna Units 1 & 2) were in the Region I Office to attend a Management Meeting to discuss recent outage lessons learned and the scope of the next scheduled outage.
2.
On March 21, representatives of James River Corporation (James River Graphics Group) were in the Region 1 Office to attend an Enforcement Conference regarding recurring loss of control over generally licensed byeroduct materials.
3.
On March 21, representatives of Pennsylvania Power and Light Company (Susquehanna Units 1 & 2) were in the Region I Office to attend an Enforcement Conference concerning excessive cooldown rate.
representatives of General Public Utilities Nuclear On March 22,(0yster Creek) were in the Region I Office to attend a Closed 4.
Corporation Management Meeting.
i MARCH 24, 1989 ENCLOSURE N
c
)
i Region IV Items of Interest Week Ending March 24, 1989 1.
Wolf Creek Nuclear Operating Corporation On Monday, March 20, 1989, Division of Reactor Safety and Division of Radiation Safety and Safeguards management and staff will meet with representatives of Wolf Creek Nuclear Operating Corporation in the Region IV office. Areas to be discussed include causes and corrective actions for high failure rate in reactor operator examinations conducted November 1988, security matters, and operations at Wolf Creek Generating Station.
2.
On Tuesday, March 21, 1989, Division of Reactor Safety management and staff will meet with training representatives from Region IV power reactor licensees at in the Region IV office to discuss ongoing changes in operator licensing and requalification programs.
3.
Fort Calhoun Station The President and Nuclear Vice President of Omaha Public Power District are in the Region IV office to meet with the Regional Administrator. They requested the meeting to present the results of studies they had performed to assess the progress of the Fort Calhoun Station.
4.
Fort St. Vrain On Wednesday, March 22, 1989, Division of Reactor Safety management and staff will meet with representatives from Public Service Company of Colorado at in the Region IV office to discuss operator licensing needs at Fort St. Vrain Nuclear Facility ouring decommissioning.
5.
Cooper Nuclear Station On Thursday, March 23, 1989, an enforcement conference will be held with representatives of Nebraska Public Power District in the Region IV office.
Areas to be discussed include inoperability of an emergency diesel generator in excess of Technical Specification limits and the corrective action program at Cooper Nuclear Station.
6.
ANO, Unit 1 Based on discussion with licensee representative.s on March 22, 1989, NRC Region IV understands that Arkansas Power and Light plans to request an energency technical specification change to limit licensed power to 74 percent on ANO, Unit 1.
This power limitation is because of the discovery by the Licensee of a more limiting small break loss of coolant accident than previously analyzed.
MARCH 24, 1989 ENCLOSURE N
c ITEMS ADDRESSED BY THE COMMISSION - Week Ending March 24, 1989 A.
STAFF REQUIRE 6NTS - PRELIMINARY BRIEFING ON THE STATUS OF NUREG-1150, 2:00 P.M., WEDNE 9AY MARCH 15, 1989, COMMISSIONERS' CONFERENCE ROOM, z
ONE WHITE FLINT NOR1n, ROCKVILLE, MARYLAND (OPEN TO PUBLIC AT1ENDANCE)
- SECY to V. Stello, JF., EDO dated 3/23/89 The Commission was bzlefed by the staff on the results from the NUREG-1150 studies addressing internally initiated events for five nuclear power plants (described in SECY-89-058, released at the meeting).
A comprehensive briefing on NUREG-1150 will be scheduled following Commission's receipt of the completed redraft of NUREG-1150.
The Commission made the following requests:
1.
Staff should provide the Richter Scale equivalence used in earthquake analyses.
2.
Staff should inform the Commission of any probabilistic risk assessment studies conducted on a combustion Engineering (C-E) designed plant, including any plan to perform such studies on a C-E as well as a Babcock &
Wilcox plant.
3.
Staff should inform reactor designers and suppliers of the major conclusions resulting from the NUREG-1150 studies.
4.
On or prior to April 17, 1989, copies of NUREG-1150 should be provided to the Advisory Committee on Reactor Safeguards.
5.
Staff should submit to the Commission the completed redraft of NUREG-1150 by April 17, 1989.
l 1
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