ML20045H745
| ML20045H745 | |
| Person / Time | |
|---|---|
| Issue date: | 07/14/1993 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| SECY-93-195, WIR-930709, NUDOCS 9307210211 | |
| Download: ML20045H745 (31) | |
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July 14, 1993 Lor:
The Commissioners From:
James L. Blaha, Assistant for Operations, Office of the ED0 Sub.iect:
WEEKLY INFORMATION REPORT - WEEK ENDING JULY 9, 1993 Contents Enclosure Nuclear Reactor Regulation A
Nuclear Material Safety and Safeguards B
Nuclear Regulatory Research C
Analysis and Evaluation of Operational Data D
General Counsel E*
Administration F
In ':n :lation Resources Management G
Controller H*
Personnel I
Small & Disadvantaged Business Utilization & Civil Rights J*
Enforcement K
Consolidation L
State Programs M
Policy Planning N*
Public Affairs 0*
j International Programs P*
Congressional Affairs Q
Regional Offices R
Executive Director for Operations S*
Meeting Notices T
- No input this week.
4 47 %
lames L. B aha ssistant for Operations, OEDO I
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Contact:
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D. Wheeler, OEDO 504-1733 i
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9307210211 930709
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COMMS NRCC PDR WEEKLYINFOREPT PDR
4 Office of Nuclear Reactor Regulation Items of Interest l
Week Ending July 9,1993 Foreion Trio and Technical Exchance on Diaital Instrumentation and Control Systems From June 19 to July 2, 1993, Jared Wermiel, Chief, Instrumentation and Controls Branch (HICB) and John Gallagher, Senior I&C Engineer, met with staff of DSIN, Paris; Siemens, Erlangen, Germany; AIN Vincotte, Brussels; Rolls Royce, Derby. UK; and NII, Bootle, UK to discuss issues involving digital instrumentation and control systems. The trip also included a tour of the Sizewell B nuclear power plant site with a focus on the control room and I&C equipment areas. Major parts of the technical exchange involved
- 1) discussions with Siemens staff on digital system design, particularly software development, verification and validation and testing, and
- 2) discussion with Rolls Royce staff concerning the results of the dynamic testing of the Sizewell B digital I&C system. Additional discussions were held with NII regarding the status of the safety case for demonstration of the digital I&C system reliability for licensing of Sizewell.
Information gained from these discussions will assist the staff in its reviews of the digital I&C systems proposed for the advanced reactors.
BWR Water level The P.eactor Systems Branch met with the BWROG at the EPRI NDE facility in Charlotte, North Carolina, on Friday July 9,1993. The purpose of the meeting was to observe and discuss testing that the BWROG is sponsoring related to the reference leg backfill modification. The backfill test program is intended to verify the adequacy of flow rates, determine the effect of system disturbances, determine the effect during simulated loss of control rod drive system, and determine the response of the instrumentation to simulated upset conditions, such as operator error to fully open flow control valves. The testing is expected to be completed in the near future.
Steam Generator Tube Inspection Update On March 14, 1993, a steam generator tube ruptured at Palo Verde Nuclear Generating Station, Unit No. 2, one week prior to a scheduled refueling outage. The rupture occurred high in the steam generator in the free span between tube supports.
The licensee has been conducting extensive eddy-current testing, using both the bobbin and rotating pancake (RPC) probes. All of the tubes in both steam generators (SGs) have been examined with the bobbin. Thirty-eight hundred tubes (out of a total of 11,000 tubes) will be examined with the RPC in both-steam generators between the 08H support and the first vertical support on the hot leg side. Also 10 percent of the tubes have been examined with the RPC between the tube sheet and the first support in both SGs.
For SG No. 1, 17 tubes with axial cracks have been found, as follows: two at or near the tube sheet, five at supports, and ten in the free span high in the SG. Ten of these were not detectable with the bobbin.
JULY 9, 1993 ENCLOSURE A
2 For SG No. 2, 84 tubes with axial indications have been found, as follows:
four near the O1H support, 40 at or near upper supports, and 39 in the upper free spans.
Thirty-six of these indications were not detectable with the bobbin.
Most of the defects found appear on an " arc" pattern of the tubesheet on the hot leg side high in the steam generator between the 08H support and the first vertical support after the 90 degree bend.
Expanded RPC examinations have focused on this area, with some sampling in other areas to confirm that the degradation is confined to the " arc."
Visual examinations of the tubes have revealed the presence of linear deposits. Thermal-hydraulic analysis indicates that the region where the indications are occurring is an area of the steam generator where deposition could be expected based on steam blanketing (film boiling) and possibly dryout. Although preliminary, it appears that axial cracking may only occur where large deposits exist in this region.
Arizona Public Service (APS) believes that the appropriate crack growth rate for tubes in the arc area is 2 mils per month, and that the appropriate crack growth rate for other areas of the SG is 1.4 mils per month.
Based on the examinations of the removed tubes and other data, the crack detection threshold for the bobbin and RPC probes is 50 percent and 40 percent, respectively. Applying the methods contained in Regulatory Guide 1.121, this results in an operating interval of six months until the next steam generator tube inspection (Unit 2 is fueled for a 15-month operating cycle). This information is preliminary pending receipt of the licensee's final report.
The eddy-current inspections with the RPC should be completed by about July 13. This will extend the outage until mid-August. The final report should be submitted to NRC in mid-July, with a final meeting with NRC about one week later. APS has been asked to address the implications of these inspection results on Units 1 and 3 by July 26.
San Onofre Nuclear Generatina Station. Units 2 and 3 Several items of interest have occurred at the San Onofre site during the past two weeks. On June 30, 1993, the licensee found loose parts at the bottom of the Unit 2 reactor vessel while performing the 10-year inservice inspection.
The loose parts appear to be thermal sleeves from the cold leg safety injection nozzle penetrations. The licensee is in the process of performing a detailed safety assessment, but does not believe there were any significant safety implications for either unit because the flow skirt prevented the loose parts from reaching the fuel region. The licensee is reviewing the loose parts monitoring records to determine if there were any prior indications of this condition.
The licensee has completed the examination of elbows welded to the top of the feedring in Unit 2 steam generators in which the licensee discovered through wall erosion. The licensee has decided to replace 50 percent of the elbows during the current refueling outage and to reinforce the distribution box that splits the feedwater flow into the two halves of the feedring. The replacement elbows are made of chrome-molly alloy to reduce the effects of feedwater erosion.
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JULY 9, 1993 ENCLOSURE A
3 A meeting was held on July 1, 1993, in the Region V offices that included representatives from NRR to discuss the licensee's plans to inspect the Unit 2 steam generator tubes. The licensee plans to inspect 1800 tubes per steam generator (20% of total) using the bobbin coil method, and 500 tubes per steam generator in a kidney-shaped area in the center of the tubesheet using the rotating pancake coil (RPC) method. The licensee also indicated their plans to RPC inspect 400 tubes at the top of the bundle for any evidence of the free span axial cracks or tube support cracks that were detected at Palo Verde Unit 2.
The staff was informed on July 6, 1993, that 1) the bobbin coil inspection is almost complete, and one wear indication, 89 percent deep, was detected at the intersection of the 6th eggcrate support, 2) the RPC inspection of 500 tubes per steam generator is 50 percent complete, and one circumferential indication nat detected during the bobbin coil inspection was found at the top of the transition between expanded and unexpanded portions of the tube (top of the tube sheet area), and 3) an additional RPC inspection of 400 tubes per steam generator is 50 percent complete with no cracks detected so far (some evidence of tube outer diameter deposits has been detected). The licensee is reviewing expanding the sample size of RPC inspections.
Haddam Neck Plant The Individual Plant Examination for the Haddam Neck Plant was received during the past week. The core melt frequency was estimated at 1.8E-4.
The major contributors were LOCAs (31 percent) and loss-of-offsite power (20 percent).
The licensee did not identify any new major severe accident scenarios that would have required immediate action. The licensee is looking at various modifications that will lower the core melt frequency to lE-4 (exclusive of seismic and external flooding events which are still being studied).
On June 29, 1993, the licensee requested an alternative testing program for the feedwater system based on engineering evaluations as allowed by the 1992 edition of Section XI of the ASME Code. The required alternative testing is a result of cracking found in the feedwater nozzle welds.
The staff is reviewing this request but the licensee is working to the 1983 edition and the staff has only approved to the 1989 edition.
The plant declared three unusual events during the last week. The site lost off-site power twice and there was one failure of an automatic bus transfer unit. The licensee stated that all three events were initiated during the performance of Procedure 5.1-18, Test of Emergency Diesel-Generator 2A (EG-2A) with Partial loss of AC Coincident with Core Cooling Actuation.
The staff sent an Augmented Inspection Team (AIT) to the site to determine causes, safety implications, and review associated licensee actions. During one event, the shift supervisor's staff assistant mislogged the event as an Alert rather than an unusual event. When the computer requested radiological data the assistant entered false data regarding wind speed and direction data to proceed with the log-in.
Seauovah Units 1 a/nd 2 Unit I refueling outage continues.
's JULY 9, 1993 ENCLOSURE A
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4 On July 2,1993, the fuel assembly that was wedged in place on the lower fuel assembly guide pins was successfully removed from the core and placed in the spent fuel pool.
The Notification of Unusual Event was exited at 2335 hours0.027 days <br />0.649 hours <br />0.00386 weeks <br />8.884675e-4 months <br /> on July 5,1993, (the delay was caused by difficulty in placing the fuel assembly into.the upender for. transfer to the spent fuel pool). A small' cylindrical foreign object was found in the core location that may have caused the fuel bundle to tip when it was placed in the core.
It has been removed from the core and radiation levels indicate that it may have been in the core during the previous operating cycle. The lower core plate guide pins associated with the fuel assembly have been found to be bent slightly and will 4
be straightened. There has been no evidence of damage to the fuel. assembly,-
but it will not be reloaded into the core.
Investigation into the cause of the problem and the source of the foreign object is ongoing.
NRR and Region-II continue to monitor the evolution closely.
j Other activities associated with restart of Sequoyah -- program enhancements, evaluations, plant modifications, backlog work -- continue, with Unit 2 -
restart expected in mid-August. The Operational Readiness Assessment Team
-inspection is scheduled for July 26 to August 5,1993.
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'6 JULY.9, 1993 ENCLOSURE A i
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9 Office of Nuclear Material Safety and Safeguards Items'of Interest Week Ending July 9, 1993 NRC/ DOE Meetina with Five Nuclear Fuel Fabricators on Transoarency On July 13, 1993, representatives of the Nuclear Regulatory Commission, the Department of Energy (D0E) and the five licensed nuclear fuel fabrication facilities will meet at NRC to discuss the terms and provisions of the draft Transparency Agreement with the Russian Federation. The transparency issue is related to the U.S. purchase of the Russian highly enriched uranium (HEU) recovered from the decommissioned nuclear weapons. The Transparency Agreement would ensure the verification of the source of the Russian material and the end product of the material on the U.S. side. The NRC-licensed nuclear fuel fabrication facilities will be involved in processing of the Russian material into light water reactor fuel. A U.S. delegation is planning to travel to Moscow in mid-July to discuss with the Russian government the latest version of the draft Transparency Agreement which appears to be the final step before the implementation of the U.S.-Russian Federation HEU Purchasing Agreement signed on February 18, 1993.
Meetina with U.S. Enrichment Corocration On July 7,1993, staff members of the Offices of Nuclear Material Safety and Safeguards, Nuclear Regulatory Research, General Counsel, and Region III met with representatives of the U.S. Enrichment Corporation (USEC) to discuss NRC/USEC transition issues. The meeting focused on the USEC organization and the lease agreement between the Department of Energy and USEC. USEC indicated that it has in place the necessary Toxic Substance Control Act (TSCA) and Resource Conservation and Recovery Act (RCRA) agreements with state and regional offices of the Environmental Protection Agency. Additionally, USEC stated that it would be submitting a proposed rule of its own to NRC for con-sideration in developing the standards for the gaseous diffusion plants.
eudit of the Hiah-Level Waste Reoository Manaaement and Operatina Contractor On June 28-July 2,1993, the Division of High-Level Waste Management On-Site Representative (OR) observed the internal quality assurance (QA) audit of the Department of Energy (D0E) Civilian Radioactive Waste Management System Management and Operating (M&O) Contractor in Las Vegas, Nevada. The audit was performance-based and concentrated on the implementation of QA controls for the computer software programs and the Exploratory Studies Facility design process.
The DOE auditors concluded that with the exception of two minor deficiencies, the M&O QA program was being adequately implemented in those areas audited.
The OR believes that the overall conduct of the audit was marginally. effective since the two auditors that were observed had difficulty in scheduling and coordinating interviews with the M&O technical staff.
Timely corrective measures were taken to correct this problem which allowed the conduct of the audit to continue. The OR agrees with the auditors' findings that the M&O program was being adequately implemented in the areas audited.
JULY 9, 1993 ENCLOSURE B
2 Multi-Puroose Canister Workshoo On July 1-2, 1993, at Arlington, Virginia, staff of the Offices of Nuclear Material Safety & Safeguards and General Counsel participated in a Multi-Purpose Canister (MPC) Workshop sponsored by the Department of Energy's Office of Civilian Radioactive Waste Management (0CRWM). The purpose of the workshop was to provide the participants an opportunity to learn more about the MPC concept and to provide OCRWM with the perspectives of the participants on the concept. OCRWM was particularly interested in getting comments in the areas of (1) storage (reactor site and MRS), (2) transportation, (3) disposal /
repository, and (4) technical aspects of the MPC design. The workshop included break-out sessions that discussed each of these four areas in detail.
The workshop was attended by over 100 individuals, including representatives from utilities, the states of Nevada and Maryland, tribal groups, and vendors.
The participants identified a number of issues that OCRWM should address in developing the MPC concept. OCRWM indicated that it anticipates completing a preliminary Request for Proposals for the MPC program by October 1993 and conducting another MPC workshop shortly thereafter.
Meetino with Brookhaven National Laboratory on LLW Storaae Staff from the Offices of Nuclear Reactor Regulation and Nuclear Material Safety and Safeguards met with staff from Brookhaven National Laboratory (BNL) and Niagara Mohawk on July 8, 1993, to discuss approaches for storing low-level radioactive waste.
BNL is performing research for several utilities in the State of New York on the use of high density polyethylene liners for long-term storage of ion exchange resins.
Their work will be used by the utilities in the design of storage facilities for LLW, in anticipation of having no disposal option in the next year with the loss of access to the Barnwell disposal facility.
In addition to discussing a number of technical issues, Niagara Mohawk was interested in the different approaches that could be taken for the Nuclear Regulatory Commission review of their storage approach using polyethylene liners, such as topical reports, a request for a license amendment, NRC inspection of 50.59 reviews performed by the utilities, and submission of 50.59 analyses to the Region for review before placing waste into storage.
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Office of Nuclear Regulatory Research
. Items of Interest Week Ending July 9, 1993 Plannino for Possible Study of Retired Plant Staff from the Division of Engineering met with staff.from NRR to discuss potential uses.for the Trojan Nuclear Power Station. Areas of. interest
- include testing and examination of the containment-structure, aging of cables,-
testing and examination of steam generator tubes, testing of materials from the pressure vessel supports,- and testing of materials-from the reactor pressure vessel, vessel internals, and piping materials.- The staff. is preparing brief summaries of the high priority work that could be performed-using these structures, components, and materials, for discussion with NRC management, and subsequently, with the licensee. The staff notes.that significant financial and personnel resources would be required by this 1
undertaking. A meeting with the licensee is anticipated in early August-to discuss the phased approach being suggested by the staff.
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i JULY.9, 1993 ENCLOSURE C.
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Office for Analysis and Evaluation of Operational Data Items of Interest Week Ending July 9, 1993 Preliminary Notifications PN39340, Commonwealth Edison Co, (Quad Cities 1 & 2), Quad Cities Power Station to Remain Shut Down Due to Concerns Over Area Flooding.
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Office of Administration Items of Interest Week Ending July 9, 1993 Contract Awards A competitive contract was awarded to Electronic Automation Corporation of Columbus, OH, en July 6,1993 for the " Renovation of the Office of Personnel's Supreme Minitrieve." This devise, which stores official employee personnel folders will be renovated to correct recent problems that have caused system failure. The contract amount is $18,942, and the period of performance is from July 6, 1993 to October 4, 1993.
A competitive contract was awarded to The Pennsylvania State University, University Park, PA, on July 7, 1993 for basic research in the area of
" Critical Heat Flux (CHF) Phenomenon on a Downward Facing Curved Surface."
The contract amount is $288,038, and the period of performance is from July 7, 1993 to January 6, 1996.
GSA Buildino Deleoation Review GSA compiled a review of NRC's building delegation program on July 1, 1993.
The overall evaluation rating for the eleven delegated program areas were 95%
All findings and recommendations were administrative in nature.
Notification of Soent Fuel Manaaement and Fundina Plans by Licensees of Prematurely Shut Down Power Reactors A proposed rule that would amend regulations to clarify the timing of notification to the NRC of spent fuel management and funding plans by licensees of nuclear power reactors that have been shut down before the expected end of their operating lives was published in the Federal Register on June 30, 1993 (58 FR 34947). The proposed rule would require that a licensee provide the required notification either within two years of permanently ceasing operation or no later than five years before the operating license expires, whichever event occurs first. The comment period for the proposed rule closes September 11, 1993.
Sianificant F0IA Reouests Received by the NRC for the 4-day Period July 2 - 8. 1993 Request for a copy of the Agency Procurement Request which corresponds to DPA Case No. KMA-93-0080(A).
(Linda Heineman, Federal Sources, Inc., F01A-93-370)
Request for a copy of 01 Report 4-90-012.
(James Polan of Doerner, Stuart, Saunders, Daniel & Anderson, F01A-93-371)
Request for records regarding the Shoreham power plant pipe break outside containment (PB0C) criteria.
(Judith Lockhart of Mudge, Rose, Guthrie, Alexander 8. Ferdon, F01A-93-375)
Request for records regarding a June 18, 1993 letter from W.J. Jump, Houston Lighting & Power to the NRC.
(R. Alexander Glenn of Newman & Holtzinger, P.C.,F01A-93-376)
JULY 9, 1993 ENCLOSURE F
Office of Information Resources Management Items of Interests Week Ending July 9, 1993 Pisposition of Commissioner James R. Curtiss' Office Files On June 30, 1993, and July 1, 1993, the Office of Information Resources Management (IRM) discussed the disposition of Commissioner Curtiss' files with his staff to ensure that the Commissioner's chronological files are retained permanently by the agency, to ensure that official records not in the Office of the Secretary's (SECY) official files are provided to SECY for retention, to determine if the Commissioner plans to transfer his personal files to a private library or research institution, and to determine if Commissioner Curtiss desires temporary courtesy storage of any material at the NRC Archival Facility.
The Commissioner's staff reported that the chronological files are being copied in order to provide the records to SECY, that the SECY files contain all official records of the Commissioner's office, that the Commissioner plans to transfer certain files to the Hoover Institute, and that the remaining office files will be transferred to the Archival Facility for courtesy storage. The Commissioner's staff has contacted the Division of Security to coordinate its review of Commissioner Curtiss' personal files in accordance with NRC Management Directive 3.53, Part IV, " Procedures for Managing Papers of Federal Officials and Presidential Appointees."
Vital Records Proaram In accordance with NRC Management Directive 3.53, Part V, Section G(2), on July 2,
1993, the Director, Office of Information Resources Management, issued a memorandum to Office Directors and Regional Administrators requesting the identification of records to update the collection of records included in the NRC Vital Records Program.
Secure Facsimile New secure facsimile equipment has been installed in the NRC Operations Center and the Communications Center at White Flint. These facsimile machines operate with the Secure Telephone Unit (STU-3) and can be used to transmit and receive documents classified up to Top Secret. They also have an adapter that allows the processing of unclassified CCITT (International Telecommunications Standards Committee) Group 3 facsimile traffic.
Reouest for NUDOCS Access During the week of June 28 - July 2, thirty user transactions were processed.
Thirteen new public and seventeen new internal user accounts were added.
Total Public 263 Internal 1,257 Training 6
LPDR 78 Contractors 129 Total NUDOCS Accounts 1,733 i
1 JULY 9, 1993 ENCLOSURE G
Office of Personnel Items of Interest Week Ending July 9, 1993 Pre-Board of Directors Meetina for Wellness / Fitness Center Held On July 7, a pre-Board of Directors meeting for the Wellness / Fitness Center was held during which the draft Bylaws for establishing the non-profit corporation and the memorandum of agreement between the NRC and the Wellness / Fitness Center were reviewed.
Board members in attendance were Henry Rubin and Pat Kaplan, OP; Joann Manzek, CONS;- Roger Loos, OC; Marian Zobler, OGC; Victor McCree, ED0; Joseph Birmingham and Lee Berry, NRR. Sheila Drohan, NRC's fitness consultant, was also present.
General Services Administration Symoosium Attended Fred Shields of the Policy and Labor Relations staff recently attended the General Services Administration Telecommuting Symposium. This symposium provided an opportunity for attendees to learn about the latest developments in establishing telecommuting centers.
Arrivals LATTA, Robert SR. OPERATIONS ENGINEER (PFT)
NRR Departures MCGOLDRICK, Bernadine CLERK (STAY-IN-SCHOOL) (0PFT)
RI JULY 9, 1993 ENCLOSURE I m
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- 4 Office of Enforcement
.i Items Of Interest.
Week Ending July 9,-1993 l
Sianificant Enforcement Actions A Notice of. Violation and Proposed Imposition of Civil Penalty 'in the amount of $2,500 was issued on' July 8,1993 to Columbus Hospital ~, Great Falls,
-i Montana. The action was based on a Severity Level III problem involving the licensee's failure to comply with the requirements of 10 CFR 35.32(a) (Quality Management Program). The base civil penalty was not' adjusted.
Escalation based.on NRC identification was offset by mitigation based on good licensee performance.
(EN 93-065)-
.i A Notice of Violation and Proposed Imposition of Civil. Penalty in the amount-of $2,500 was. issued on July 9,1993, to Mobile Cardiovascular Testing, Milwaukee, Wisconsin. The action was based on 12 violations that in the aggregate indicate management's failure to oversee the NRC licensed radiation safety program.
Examples of the violations include the failure to: conduct area radiation-surveys at the end of the work day; control licensed material;.
conduct training; and properly dispose of radioactive waste. The c.ivil penalty adjustment factors of the NRC Enforcement Policy were considered and on balance no adjustment to the. amount of the base civil penalty was warranted.
(EN 93-066)
A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $5,000 was issued on June 18, 1993,.to Mallinckrodt Medical-inc.,
St. Louis, Missouri. The action was based on a Severity Level III transportation violation at the. licensee's facility in Folcroft, Pennsylvania, A corrected civil penalty is being proposed since the initial determination of the. civil penalty amount was calculated using the base amount for a non-transportation violation ($5,000), rather than the base amount of a transportation violation ($1,000), which is $1,000 for a transportation-violation of this type.
(EN 93-059A) s Civil Penalty Paid.
Cassia Memorial Hospital, Burley,. Idaho,. paid the. civil penalty in the amount
.of $2,500.
The' action was based on a-Severity Level' III problem involving the licensee's failure to' establish a written Quality Management Program and 10 additional violations...The base-civil penalty ($2,500) was not adjusted:
. because escalation based on NRC identification was. balanced against mitigation for.the licensee's corrective actions.
(EA 93-121) i J
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JULY 9, 1993 ENCLOSURE K~
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Office of Consolidation Items of Interest Week Ending July 9, 1993 Second Buildina Status During the week, the interior construction prime contractor, OMNI, began ordering equipment and materials for the TWFN build-out. Sigal, the base-building prime contractor, reviewed final punch list items with GSA inspectors. KT Landscaping was on-site finishing up the irrigation system and a few remaining plantings.
OMNI subcontractor, Kirlin, began placing chilled water risers for the tenant phase of construction.
In the July 7 GSA progress meeting, NRC requested that GSA direct Lerner to redirect work on construction of the fitness center on the second floor as this facility will be relocated to the plaza level.
On July 7, the developer's representative reported that construction permits were in hand for floors 7, 8, 9, and 10. There were issues remaining to be resolved with County permitting officials on floors 2 through 6.
On July 8, the Director attended a meeting of the North Bethesda Transportation Management District Task Force at County Department of Transportation offices in Rockville. The Task Force is working on recommendations to the Montgomery County Council to establish a Transportation Management Organization (TMO) to administer traffic mitigation programs in North Bethesda.
The Transportation Action Partnership (TAP) is the prime candidate for becoming the TMO. The NRC has been a member of TAP since its inception in 1987 and the Director, Offi~ce of Consolidation, has been a member of the TAP Board of Directors since TAP was created as a not-for-profit service organization.
f JULY 9, 1993 ENCLOSURE L
Office of State Programs Items of Interest Week Ending July 9,1993 EPA Interaaency Indian Environmental Discussion Group Meetina Rosetta Virgilio, Office of State Programs, participated in the above subject quarterly EPA interagency meeting held July 7,1993 in Washington, DC.
Presentations and items for discussion included the following: MOV between the University of Northern Arizona and EPA, signed May 13, 1993; Indian Tribal Network for Tribal Governments; Federal Facilities Compliance; and the University of West Virginia's clearinghouse programs for small communities in the area of environmental training, national drinking water and wastewater.
Meetina with Michiaan Public Service Commission Representatives from the Michigan Public Service Commission met with Region III staff on July 7, 1993 to discuss various issues at Michigan nuclear power plants, including Big Rock Point's handling of loose parts in the core, and recent fuel handling problems at the Palisades plant.
JULY 9, 1993 ENCLOSURE M
CONGRESSIONAL HEARING SCHEDULE No. 28 C
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..fOCA LDATE%
' ASSIGN -
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- TIME;
. WITNESS;
- SUBJECTJ 1COMMITTsE
- MENT-
' PLACE-
$jg Gerke 07/14/93 9:30 Non-NRC Getting Results in Senators Pryor/Stevens 342 DSOB Federal Government Fedl Serv, Post Off & Civ Serv Senate Governmental Affairs Gerke 07/15/93 9:30 Commission NRC's Handling of Senators Lieberman/Simpson 406 DSOB Whistleblower Clean Air & Nuclear Regulation Complaints Senate Env & Public Works Co;bs 07/15/93 9:30 Non-NRC Environmental Res-Reps. Lloyd/Fawell 2318 toration and Waste Energy o
RHOB Management House Science, Space, & Tech y
2 H
G rke 07/15/93 10:00 Non-NRC Fedl Employees' Reps. Sawyer / Petri
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311 CHOB Occupational Safety Census, Stat, & Post Personnel p o Reps. McCloskey/ Burton Qp 9-hdQ Civil Service House Post Off & Civil Service 3
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l Coxbs 07/30/93 TBA Commission Agreement State Reps. Synar/Hastert Program Env, Energy & Natl Resources ghh I
i Hopse Government Operations Q
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Region I Items of Interest Week Ending July 9, 1993 I.
Position Exchanae Effective July 6,
1993, two Region I Division Directors exchanged positions.
Mr. Charles W. Hehl, formerly Director of the Division of Reactor Projects (DRP), is now the Director of the Division of Radiation Safety and Safeguards (DRSS).
Mr. Richard W.
Cooper, II, formerly Director, DRSS, is now the Director, DRP.
2.
Indian Point 3 Wayne Lanning, Region I Deputy Director of the Division of Reactor Projects, made a presentation on Wednesday, July 7 at West Point, New York, to members of the Four County Nuclear Safety Committee and the New York State legislature. The presentation was a briefing on the status of New York Power Authority performance deficiencies at their Indian Point Unit 3 facility as well as the recent NRC activities conducted in response to these performance problems.
In particular, Mr. Lanning discussed the recent Special Team Inspection (STI) he led at Indian Point 3 to review the root causes of their performance problems as well as NRC senior management's recent classification of Indian Point 3 as a Category 2 facility requiring close NRC monitoring.
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Region II Items of Interest Week Ending July 9, 1993 1.
Doerability/Dearaded Eouioment Workshon On July 7 and 8, Region II hosted an " Operability / Degraded Equipment" Workshop (GL-91-18) at the Sheraton Colony Square Hotel in Atlanta, Georgia.
Over one hundred utility and NRC employees participated. This is the last workshop in this series. These workshops were held in several locations around the country to familiarize utility employees with NRC policy and process, and to receive feedback from the licensees on specific examples at their facilities.
2.
Florida Power and Liaht Company - St. Lucie Unit 1 The licensee has reported that the Refueling Water Tank (RWT) has been leaking water into the ground at a rate of approximately 1.5 gallons per minute (GPM) since about June 15.
The licensee estimates approximately 51,000 gallons have leaked out (as of June 8) with a total release of approximately six curies of predominantly tritium entering the ground and groundwater.
The licensee has begun using 18 monitoring wells in assessing the extent of the tritium leakage.
No migration of radioactivity outside the plant boundary has been detected although in one monitor well near the leak an activity of 2.76 E-3 micro curies per milliliter (uC1/ml) was detected at the 35 foot level. The groundwater in this area is brackish and not a source of potable water either for plant workers or the surrounding Hutchinson Island public.
The licensee has informed the State of Florida (environmental regulation) of the low level radioactivity found in the well samples.
The exact cause and point of leakage is still being investigated. There is no visible external RWT leakage.
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1 Region III Items of Interest Week Ending July 9, 1993 1.
Quad Cities Nuclear Station Beginning on Saturday, July 3, 1993, the Region III office worked extensively with NRR in consulting with the Federal Emergency Management Agency (FEMA) Headquarters and FEMA Region VIII, and with State and local officials involved in emergency response for the Quad Cities Nuclear Station. The plant is located on the Mississippi River near Davenport, Iowa, in an area heavily impacted by flooding. A State of Emergency involving the flooding was in effect, with substantial dislocation of residents and restrictions on routes of travel, at a time when both nuclear units at the plant were preparing to start up from shutdown conditions.
FEMA Headquarters, FEMA Region VIII, and the State of Iowa, in consultation with the NRC, determined on July 8,1993, that plant startup would be acceptable since there was no major degradation of the emergency response capability.
2.
Quad Cities Nuclear Station On July 8 and 9,1993, the Relional Administrator; Acting Director, Division of Reactor Safety; ar.d Director, Division of Reactor Projects were on site at Quad Cities Nuclear Station to conduct an exit meeting of a special inspection team. The team was dispatched to review the circumstances and causes for the high pressure coolant injection (HPCI) turbine exhaust line rupture disc rupture which caused personnel injuries on June 9, 1993.
3.
Palisades Nuclear Plant An Augmented Inspection Team (AIT) was dispatched to the Palisades plant on July 8, 1993, for the inspection of circumstances associated with a damaged fuel bundle discovered on July 1,1993, and the inadvertent lifting of a fuel bundle during upper guide structure removal on July 6, 1993.
4.
Operator Licensina Meetina with Reaion III Licensees The acting chief, NRR Operator Licensing Branch along with Region III staff conducted an open meeting with Region III plant training..
representatives regarding the implementation of NUREG 1021, Revision 7,
" Operator Licensing Examiner Standards," on July 8,1993. The meeting consisted of a presentation on the proposed rule change to Part 55 and additional presentations on the specific changes to the Examiner Standards.
Pre-solicited licensee questions were presented with answers while questions from the floor were answered to the extent possible.
All questions and answers raised will be processed through the program office for final publication to all facility licensees.
JULY 9, 1993 ENCLOSURE R
Region IV 4
Items of Interest Week Ending July 9, 1993 1.
Manaaement Meetina with TV Electric The Regional Administrator and other Region IV management and staff met with the Group Vice President - Nuclear Engineering and Operations and other members of TV Electric management on July 8,1993, at the Comanche Peak Steam Electric Station. The meeting was held to discuss the results of the licensee's evaluation of the May 15, 1993, incident where licensed operators on Unit 2 increased reactor power at a rate in excess of procedurally prescribed fuel conditioning limits. This meeting was open to the public.
2.
Cooper Nuclear Station Public SALP Meetina The Regional Administrator and other members of the NRC staff will visit the Cooper plant site on July 12, 1993, to conduct a SALP meeting with Nebraska Public Power District management. This meeting is open to the public.
JULY 9, 1993 ENCLOSURE R
July 9, 1993 g_
NRR Meetino Notice Docket Attendees /
Date/ Time Number location Purpose ADolicant NRR Contact G8 7/19/93 50-390 One White Flint North To discuss technical issues NRC/TVA P. Tam 10:30 Room 13B-15 identified by the staff in the 7/20-22/93 proof and review version of the 8:30 Watts Bar Unit 1 Technical Specification.
7/19/93 52-001 GE Nuclear Energy To discuss resolution of the NRC/GE S. Ninh 1:00-5:00 175 Curtner Avenue differences between the ABWR and 7/20-23/93 San Jose, CA 95125 previous designs on I&C TS.
8:30-5:00 7/20/93 50-335 One White Flint North To discuss seismic qualification NRC/FP&L J. Norris 8:30 50-250 Room IF-19 of mechanical and electrical L. Raghavan 50-251 equipment at St. Lucie Unit 1 and Turkey Point Units 3 and 4.
7/20/93 50-344 Trojan North Bldg.
To discuss status of NRC/PGEC0/ STATE M. Masnik 9:00-11:00 Presentation Room decommissioning activities at 0F OREGON Trojan Nuclear Plant the Trojan Nuclear Plant.
71760 Columbia River Highway Rainier, Oregon 97048 7/20/93 50-390 One White Flint North To discuss status, needed NRC/TVA P. Tam 1:00 50-391 Room 48-13 actions, schedules and priorities of various licensing issues for Watts Bar, Units 1 and 2.
7/21/93 None One White Flint North To discuss credit for Boron in NRC/WOG L. Kopp m
p 1:00-4:00 Room IF-19 spent fuel pools.
o 7/27/93 679 One White Flint North To discuss the NRC's and AECLT's NRC/AECLT D. Scaletti m
9:00-11:00 Room IF-19 pre-design certification application effort related to
--e the CANDU 3 design.
July 9e 1993 NRR Meetina Notice
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Docket Attendees /
Date/ Time Number Location Purpose Aeolicant
'NRR Contact-M e" -
8/2/93 52-001 One White Flint North To discuss the status of the NRC/ABB-CE/
S. Koenick 1:00-5:00 52-002 Room 2F-17/21 different vendor's advanced WESTINGHOUSE /
52-003 design review schedules (SECY-DOE /GE 52-004 93-097).
8/3/93 50-220 One White Flint North To discuss proposed permanent NRC/NMPC D. Brinkman 10:00 Room'48-11 repair methods for control. rod drive stub tubes at Nine Mile Point Nuclear Station Unit 1.
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, e Docket Attendees /
Date/ Time Number location Purpose Applicant NRC Contact 7/10 N/A Atlanta, GA Attend 38th Annual NRC C. Paperiello Meeting of the Health Other Government Agencies Physics Society Industry-Public 7/13 N/A OWFN To discuss the terms NRC.
P. Ting-Rockville, MD and' provisions of the DOE draft Transparency Agreement with the Russian Federation 7/15-N/A_
Rockville, MD Discuss the NRC C. Gaskin implementation of the NFS Fitness for Duty Rule B&W
- i at Category I Fuel Facilities 7/20 N/A OWFN IF-5 NRC/ DOE Quality NRC P. Brooks.
9:00a-2:45p Rockville, MD Assurance Meeting
' State of Nevada-DOE and local governments 7/21 N/A Bethesda, MD To conduct Scoping NRC M. Weber 7/26 San Francisco, CA-
- meeting for Generic-States, EPA, 7/27-Okahoma City,'.0K' Environmental Impact Industry 7/28 Cleveland, OH Statement on Rule-Public making to establish
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yj Date/ Time Number Location Purpose Applicant NRC Contact 7/27-28 N/A Las Vegas, NV Technical Exchange NRC C. Abrams on Exploratory Studies DOE Facilities (ESF) Title State of Nevada II Design and Design and local governments Control 7/29 N/A Rockville, MD Staff to meet with NRC P. Lohaus Senior Vice President Law Environmental, Inc.
of Law Environmental, Inc. to discuss 10 CFR Part 61 and implementing guidance i
8/31-9/3 N/A San Antonio, TX UMTRA Inspection at the NRC D. Rom Gunnison, CO Falls City, Texas, site Site Personnel i
l and UMTRA Inspection at the Gunnison, Colorado, site l
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RES Meetino Notices 8
Docket Attendees /
Date/ Time Number location Purpose Apolicant NRC Contact 7/12-14/93
-N/A Palo Alto, CA Meeting w/EPRI on Future MACE NRC, EPRI F.Eltawila Tests 9/13-14/93 N/A Holiday Inn Digital Systems Reliability NIST, NRC, and L.Beltracchi Crowne Plaza and Nuclear Safety Workshop industry 10/20-22/93 N/A Boston, MA Conference on Achievements of NRC, OECD/NEA, A. Rubin the TMI-2 Vessel Investigation Utilities / Industry, Project, sponsored by OECD/NEA OECD members, and NRC Public 1
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July 9, 1993 Office of State Proarams Meetina Notices o
E Docket Attendees /
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'Date/ Time Number location Purpose Applicant SP Contact U
7/7/93 NA Glen Ellyn, IL Meet with Michigan Michigan PSC R. Lickus 8
Public Service Commission staff on Big Rock Point 7/8/93 NA Jefferson City, M0 Meeting with Missouri EP Officials R. Lickus emergency planning officials 7/11-13/93 NA Madison, WI Midwest Legislative States R. Lickus Conference 7/12-13/93 NA.
Oswego, NY Nine Mile Point EP Officials M. Miller Emergency Planning Exercise 7/12-15/93 NA Washington Washington Radiation State J. Hornor Control Program Visit 7/13-15/93 NA Darr, SC Summer EP Exercise EP Officials R. Trojanowski 7/19-23/93 NA Montgomery, AL Alabama Radiation State R. Woodruff Control Program Review 7/19-8/20/93 NA Oak Ridge, TN Health Physics Course States D. Sollenberger 7/21-23/93 NA Sante Fe, NM LLW Forum LLW Officials S. Salomon 7/25-29/93 NA San Francisco, CA NARUC Summer Meetings PUCs S. Droggitis 7/26-28/93 NA Newhill, NC Harris Emergency EP Officials R. Trojanowski Planning Exercise im 7/26-30/93 NA Burlington, MA Industrial Radiography States J. Myers f
Course l
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.~..aF 7/26-27/93 NA Rockville, MD Compatibility Workshop NRC/ States S. Schwartz
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-o 7/28-29/93 NA Zion, IL Zion Emergency EP Officials R. Lickus Planning Exercise 7/28-30/93 NA Rockville, MD LLW Regulators Workshop LLW Regulators L. Person P
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- l July 9, 1993 Reaion I Meetina Notices 8
Docket Attendees /
Date/ Time Number location Purpose Applicant NRC Contact 07/21/93 50-277 Region I Peach Bottom Performance Selected NRC Staff Anderson 10:00 a.m.
50-278 Assessment Meeting Memoers and Licensee 07/21/93 50-289 Middletown, PA 10 R Outage Briefing Selected NRC Staff Rogge 1:30 p.m.
50-320 Members and Licensee 07/22/93 50-309 Region I Radiological Protection Selected NRC Staf' Lazarus 10:30 a.m.
Program and Refueling Members and Li
.3ee Activities
- 07/28/93 50-333 Scriba, NY SALP Management Meeting Selected NRC Staff Eselgroth 1:00 p.m.
Dates covering 4/19/92 Members and Licensee thru 4/17/93
- This meeting had previously been scheduled for July 19, 1993
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July 9, 1993 Reaion 11 Meetina Notice h
Docket Attendees /
Date/ Time Number location Purpose Applicant NRC Contact P
07/13/93 70-143 RII Office Enforcement Conference RA, RII Staff Stohr E
10:00 a.m.
Nuclear Fuel Services and Licensee 1
1:00 p.m.
50-390 RII Office Maragement Meeting RA, RII Staff Ebneter 50-391 TV3 - Watts Bar and Licensee 07/15/93 50-348 RII Office Meeting with Alabama RA, RII Staff Ebneter 10:00 a.m.
50-364 Power Co. - Farley and Licensee to discuss corrective actions 1:00 p.m.
50-327 RII Office Meeting with TVA -
RA, Ril Staff Ebneter 50-328 Sequoyah regarding and Licensee the Restart Panel 07/15/93 50-269 Seneca, SC Presentation of Certs.
Dir. of DRP, Merschoff 6:00 p.m.
50-270 to Newly Licensed RII Staff, and 50-287 Operators at Oconee Duke Power Co.
Managers and Operators l
07/20/93 50-413 York, SC Presentation or Certs.
RII Staff, Duke Power Co.
Reyes 50-414 to Newly Lice.. sed Managers and Operators Operators at Catawba 07/27/93 50-335 RII Office Self-Assessment Meeting DRA, RII Staff Reyes l
10:00 a.m.
50-389 FP&L - St. Lucie and Licensee f
l 07/28/93 50-269 Seneca, SC SALP Presentation DRA, RII Staff Reyes 1
10:00 a.m.
50-270 DPC - Oconee and Licensee f
50-287 07/29/93 50-325 RII Office Meeting with CP&L to DRA, RII Staff Reyes 10:00 a.m.
50-324 discuss Brunswick's and Licensee three-year plan H
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July 9, 1993 RIII Meetina Notice Docket Attendees Date/ Time Number location Purpose Applicant NRC Contact 7/20/93 50-315 Site Indiana Michigan Deputy Regional Administrator Greenman 50-316 Power Co.
Selected Staff (D. C. Cook) SALP Presentation 7/21/93 50-263 RIII Northern States Power Director, Division of Greenman Management Meeting Reactor Projects 7/22/93 RIII Commonwealth Edison Regional Administrator Greenman Company - Quality Selected Staff Assurance 7/26/93 50-331 Site Iowa Electric Light &
Director, Division of Greenman Power Co..
Reactor Projects Site visit and plant tour. (Duane Arnold) 7/27/93 50-341 RIII Detroit Edison Company Director, Division of Greenman Fermi - Mgmt. Meeting Reactor Projects 8/02/93 50-456 RIII Commonwealth Edison Regional Adminstrator Martin l
Briadwood - Meeting w/
l Site V.P.
7/30/93 50-254 RIII Commonwealth Edison Regional Administrator.
Greenman 50-265 Company - Quad Cities Selected Staff Management Meeting EP O
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h July 9, 1993 Reaion IV Meetina Notice is S
Docket Attendees /
NRC Date/ Time Number location Purpose Aeolicant Contact 7/12/93 50-498; RIV (1) QDPS Seismic Operability Houston L&P B. Beach 1pm & 3 50-499 (2) FWIV Bypass Valve Operability
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