ML20148G120
| ML20148G120 | |
| Person / Time | |
|---|---|
| Issue date: | 05/30/1997 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| SECY-97-108, SECY-97-108-R, WIR-970523, NUDOCS 9706050179 | |
| Download: ML20148G120 (21) | |
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$ v 30. 1997 SECY 97-108 For:
The Commissioners From:
James L. Blaha. Assistant for Operations. Office of the EDO Subiect:
WEEKLY INFORMATION REPORT - WEEK ENDING MAY 23, 1997 Contents Enclosure Nuclear Reactor Regulation A
Nuclear Material Safety and Safeguards B
Nuclear Regulatory Research C
i Analysis and Evaluation of Operational Data D
General Counsel E*
l Administration F
Chief Information Officer G*
Chief Financial Officer H*
Personnel I
Small Business & Civil Rights J
Enforcement K*
State Programs L*
Public Affairs M
J International Programs N*
Office of the Secretary 0*
Region I P
Region II P*
Region III P
Region IV P
Executive Director for Operations 0*
Congressional Affairs R*
- No input this week.
hj James L. Blaha 3q
,,, gB Assistant for Operations. OEDO
Contact:
h 5/
G. Tracy. OEDO bd
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Document Name:
C:\\ WEEK 523 Ah0 DfF~
OEDO GTracy JBL1ha 1
05/29/97 05/3o/97 9706050179 970530 PDR COMMS NRCC WEEKLYINFOREPT PDR j
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20556 INFORMATION REPORT May 30. 1997 SECY 97-108 I
For:
The Commissioners From:
James L. Blaha. Assistant for Operations. Office of the EDO Sub.iect:
WEEKLY INFORMATION REPORT - WEEK ENDING MAY 23, 1997 I
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
Chief Information Officer G*
Chief Financial Officer H*
Personnel I
Small Business & Civil Rights J
4 Enforcement K*
State Programs L*
Public Affairs M
International Programs N*
Office of the Secretary 0*
Region I P
Region 11 P*
Region III P
Region IV P
Executive Director for Operations 0*
Congressional Affairs R*
- No input this week.
C.9m ames L. Bleha Assistant for Operations. OED0
Contact:
G. Tracy. OEDO E!C E1E CMIER COPY '7~'I' 9
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Office of Nuclear Reactor Regulation Items of Interest Week Ending May 23. 1997 OCONEE Nuclear Station. Units 1. 2. and 3 Unit 2 has been shut down since April 22. 1997, and Unit 3 since May 1. 1997.
f Replacement of the Unit 2 high pressure injection (HPI) line where the weld 4
crack was located has been completed and restart preparations are underway.
Inspections of the Unit 3 nozzles have been completed and one thermal sleeve has been repaired.
i The licensee has discovered wear of the orifice assemblies in the minimum flow 4
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lines from the discharge of each pum) to the Letdown Storage Tank on Units 2 and 3.
There are 10 orifices in eac1 assembly with various orifice diameters.
Wear of these orifices could result in debris that may block flow or excessive
. minimum flow that would decrease the pump flow available from the HPI system in the ECCS mode. The Unit 2 orifice assemblies have been rebuilt from spare parts.
A lack of spare parts has delayed repair of the orifices on Unit 3.
1 Jnit 1 is susceptible to a similar problem and will evaluate when it is shut i
down (which will occur on June 14 at the latest).
l On May 14, 1997. a meeting was held with the licensee at OWFN to review the technical information related to the weld crack, thermal sleeves. Letdown j
Storage Tank level control and design, system operation, etc.
On May 16.
1997, the Region II Administrator conducted a )ublic meeting at Oconee. The
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Unit 3 Augmented Irspcction Team results and t7e status of the Unit 2 and 3 Confirmatory Action Letter were discussed.
Based on the evaluation results that have been reviewed by Region II and NRR. the plant modifications that have been completed. and the commitments that the licensee has made. the i
Regional Administrator explained that Units 2 and 3 may be restarted. The NRR and Region 11 staffs continue to closely monitor the licensee's activities associated with the many concerns that have been discovered.
FERMI During the recent power ascension from the extended outage to repair the main generator, the licensee detected indications of failed fuel.
The licensee reported that testing indicates that the failure is in a once-burned bundle and that the failure is more than a pinhole leak. The licensee has developed a plan to o]erate in a manner to mitigate the effects of the fuel failure, including t1e use of preconditioning and limiting the linear heat generation rate (LHGR) in the affected fuel bundle.
The licensee is currently holding at 94 percert power because their established LHGR limit for the bundle has been reached.
The licensee is evaluating whether it will be possible to reach the existing o)erational limit of 96 percent power.
The 96 percent limit has existed since t1e previous cycle and is related to limitations in the secondary side of the plant.
ENCLOSURE A May 23. 1997
Emeraency Diesel Generator Air Start Motors i
i On 05/08/97, after replacement of EDG air start motors. the licensee j
identified the unit 2 EDG would not start for Jost maintenance testing. The licensee assembled a troubleshooting team whic1 tested the air start system i
over 200 times.
The team identified an a) proximate 4 percent failure rate of j
the air start motors to properly engage t1e EDG bull gear. The failure of the
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air start motors to engage and turn the EDG bull gear is known as pinion gear i
abutment (PGA).
i The licensee has EMD type EDGs with air start motors (ASM) manufactured by i
Ingersoll-Rand.
The licensee identified the new model (Ingersoll Rand ~88" i
style) required an additional 1/8" of axial movement of the pinion gear than the previous model (Ingersoll Rand ~89" style). The licensee had removed the 89 style ASMs and installed the 88 style ASMs without knowing the difference between the ASMs. Without the additional 1/8" of axial movement, the lower ASM could not port air to the upper ASM should the lower air start motor pinion gear abut with the EDG bull gear.
This condition would inhibit the second air start motor pinion gear from injecting.
Should a PGA occur (tested
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to be 4 percent at Quad Cities) on the lower air start motor. the second air i
start motor would not function and would result in the EDG failing to start.
The licensee determined the shared EDG also may have had the 88 style ASM installed in January.
Both the shared diesel and the Unit 2 diesel now have 1
the 88 style ASM with shims installed and have been declared operable as of I
05/19/97. The licensee has shared this information with the industry on the
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Nuclear Network and is evaluating this issue for Part 21 implications.
ENCLOSURE A May 23. 1997
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i Office of Nuclear Material Safety and Safeguards Items of Interest Week Ending May 23, 1997 4
Gaseous Diffusion Plant Regulatory Issues Meetina a
I On May 15, 1997. Nuclear Regulatory Commission staff from the Office of Nuclear Material Safety and Safeguards: the Office of Administration. Division of Security; and the Office of the General Counsel met with the U.S.
Enrichment Corporation (USEC) at their facilities in Bethesda, Maryland, to i
discuss regulatory and other issues affecting the Gaseous Diffusion Plants.
USEC presented information on operational issues, the status of certificate I
amendment requests, and closure of Compliance Plan issues.
The NRC presented information on the schedule and status for the proposed 10 CFR Part 76 i
rulemaking, the enforcement policy, and backfit.
Dam Safety Insoection at Comanche Peak On May 7,1997. Office of Nuclear Material Safety and Safeguards staff and an engineer from the Federal Energy Regulatory Commission (FERC) performed a routine inspection of the Safe Shutdown Impoundment (SSI) dam at Comanche Peak Steam Electric Station, near Glen Rose. Texas.
This inspection was the last reactor sto) on the Nuclear Regulatory Commission's initial Dam Safety Inspection Program tour. Texas Utilities Electric Co. (TU) personnel provided design and maintenance documentation, and accompanied the team on a " walkover" inspection. The SSI. which was completed in 1979 isolates an arm of Squaw Creek Reservoir, providing emergency cooling water in the event of catastrophic damage to the Squaw Creek Reservoir Dam.
No major problems were identified with the structure.
Preliminary results of the inspection were presented to TV in an exit meeting at the site. A final inspection report will be provided to the licensee following receipt of the FERC findings.
Meetina with the Department of Enerav on Criticality Analysis Methodoloav On May 7-8. 1997. Nuclear Regulatory Commission staff met with Department of Energy (DOE) staff and contractor representatives in Lynchburg, Virginia, to discuss DOE's criticality analysis methodology for the disposal of spent nuclear fuel in the proposed repository at Yucca Mountain. Nevada. The meeting began with a tour of the Framatome Technologies commercial fuel fabrication facility. The quality assurance (0A) provisions applied to fuel fabrication at this facility ensure that virtually no defective rods or assemblies will result at the end of tne process. The process includes 100%
inspection of all rods / assemblies, with numerous " hold points" along the way for both visual and other nondestructive examination and testing.
NRC staff suggested that DOE develop a similarly robust and comprehensive QA program for fabrication of repository waste packages.
Following the tour, participants discussed the philosophy of " defense in depth" to prevent or mitigate a criticality event.
NRC staff indicated that regulatory requirements in 10 CFR Part 60 for criticality control are consistent with the " defense in depth" philosophy.
DOE representatives then discussed the use of criticality data from commercial reactor startups and May 23. 1997 ENCLOSURE B
J from laboratory experiments to validate the isotopic and reactivity models utilized for repository waste package criticality analyses. The primary issue here is whether configurations for commercial reactor and laboratory criti ality are sufficiently similar to repository waste package configurations to allow the data from the reactor and laboratory criticality to be used to validate the models for repository criticality analyses.
Discussions on Hiah-Level Waste Ouality Assurance On May 12, 1997. Division of Waste Management (DWM) staff met with Department of Energy (DOE). Office of Civilian Radinactive Waste Management (OCRWM). to discuss issues of mutual interest related to the Quality Assurance (0A) program for the high-level waste repository.
The videoconference, held at Nuclear Regulatory Commission Headquarters and in Las Vegas, Nevada, was also attended by representatives of the Nuclear Waste Technical Review Board: Clark County, Nevada: Nye County, Nevada; and the State of Nevada. Topics discussed
~ included the status and resolution of the Nuclear Regulatory Commission's open items: the DOE 0A consolidation effort; proposed revisions to the DOE top tier 0A document: data qualification: DOE responses to the recent independent management assessment of the OA organization: 0A oversight functions of the State of Nevada and the NRC: applicability of requirements in 10 CFR Part 21:
" graded" 0A approach efforts applied to structures, systems, and components and: proposed revisions to the list of structures, systems, and components.
The discussions also included DOE's request for formal clarification of' NRC's 10 CFR Part 21 requirements: proposed modifications to DOE's approach to data qualification to resolve NRC staff concerns: proposed modifications to DOE's OA trending program in response to NRC concerns; and reducing items on the 0-list through the " graded" 0A approach.
Resolution of NRC concerns on data qualification and the DOE 0A trending program depends upon DOE submittal of documents implementing the approach discussed at the May 12 meeting.
Sealed Source and Device Vendor Workshoo On May 8, 1997 members of the Medical. Academic, and Commercial Use Safety Branch, conducted a workshop on the application and review process for safety evaluation and registration of sealed sources and devices containing sealed sources.
Registration certificates, based on the safety evaluations, are used I
as the basis for licensing the possession and use of the products. About 65 Nuclear Regulatory Commission and Agreement State vendor personnel attended i
the one-day workshop. which was held at NRC Headquarters.
The workshop provided information and guidance in preparing a complete and succinct application to those who prepare applications for safety evaluation and registration of sealed sources and devices, so that review times may be minimized. The workshop concentrated on the types of information to be
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included in applications. the regulations that must be addressed, and available guidance that may be of assistance when preparing an application.
i NRC staff discussed the NRC review and approval process.
Specific topics l
May 23. 1997 ENCLOSURE B
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l' included review of sealed sources and devices intended for use by specific and general licensees, and products intended for use by persons exempt from licen5ing requirements in a wide range of commercial and industrial applications.
Feedback from workshop participants has been positive.
l Presentation at the American Colleae of Cardioloav l
On May 9. 1997, a representative from the Division of Industrial and Medical Nuclear Safety, made a presentation on "Recent Advances in Clinical Nuclear i
Cardiology" at the American College of Cardiology symposium.
Information on Nuclear Regulatory Commission physician licensing and physician training and experience requirements was provided to symposium participants.
In addition.
information was provided regarding Commission direction to staff regarding revision of 10 CFR Part 35.
Some symposium participants provided comments to NRC regarding the need to reduce the training required for nuclear cardiologists to become authorized users and on the need to eliminate or reduce the number of prescriptive requirements for low risk nuclear cardiology procedures.
Meetina with Deoartment of the Army j
On May 13. 1997, senior management representatives from the Ofi e of Nuclear Material Safety and Safeguards (NMSS). Rogion I, and Region III met with the l
Chief of Staff. U.S. Army Material Command, and other representatives from the U.S. Army, in Alexandria, Virginia, to discuss Nuclear Regulatory Commission concerns regarding the Department of the Army's commodity materials licenses.
NRC representatives discussed, in general terms, inspection findings and l
recent incidents related to the following subjects:
(1) command and authority for oversight: (2) accountability and control of licensed material; (3) communication between the organizations possessing the licenses and facilities 1
using the licensed material; (4) training of individuals: and (5) reporting of i
incidents. The Army agreed to address these areas and is taking action to i
correct them.
The actions under consideration include:
(1) combining the
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Army's 12 commodities licenses into fewer licenses--if not into a single license: (2) improving their inventory tracking database for commodities: (3) i creating a Department-level Radiation Safety Director and Radiation Safety Committee: (4) enhancing and emphasizing their training program: and (5) j establishing an enhanced and automated mechanism for reporting incidents.
The Army is currently undergoing a comprehensive independent audit of its program, which is being performed in accordance with a Confirmatory Order issued by j
Region III.
The findings and recommendations of this audit will be 1
incorporated into the Army's corrective actions.
Future meetings will be i
scheduled to discuss the scope and status of implementing the corrective j
actions.
Doerational Assessment at Fort St Vrain Indeoendent Soent Fuel Storace j
Installation i
On May 12, 1997, a Spent Fuel Project Office team to assess the operation 1 readiness of Department of Energy-Idaho (DOE-ID) to manage and operate the Fort St. Vrain independent spent fuel storage installation arrived at the site.
Last December. DOE-ID submitted a license transfer application to May 23. 1997 ENCLOSURE B
l assume licensed responsibilities for the facility from the Public Service Company of Colorado. The Nuclear Regulatory Commission team will also visit the Idaho National Engineering and Environmental Laboratory to assess DOE-ID oversight of the facility from a remote location.
Region IV is also participating in the assessment effort.
Meetina with Transnuclear. Inc. on Revisina the TN-32 Desian i
On May 8.1997, staff from the Spent Fuel Project Office met with representatives of Transnuclear. Inc. (TN) to discuss their plans to submit several amendments to the topical report for the TN-32 spent fuel storage cask.
This cask is designed to hold 32 pressurized water reactor assemblies.
The amendments will seek approval to store higher burnup and enrichment fuel in the TN-32, and approval of a lengthened design to hold longer assemblies with control rods.
Moreover. TN plans to submit a design for a new basket i
that will hold 68 boiling water reactor fuel assemblies.
Either simultaneous with the amendment for higher burnup and enrichment or soon thereafter. TN will request approval of the TN-32 under Subpart K of 10 CFR Part 72.
This approval would allow the cask to be used under the general license for dry spent fuel storage that is granted to all power reactors licensed under 10 CFR Part 50.
Use of the TN-32 is presently restricted to those sites that have a separate Part 72 license for an independent spent fuel storage installation.
Except for the amendment requesting a lengthened TN-32 design. TN expects to provide NRC all of the submittals before the end of fiscal year 1997.
Meetina with VECTRA Technoloaies Inc.
On May 9.1997. Spent Fuel Project Office staff met with VECTRA Technologies Inc. (VECTRA). to discuss VECTRA's April 10. 1997, response to a Demand for Information (Demand).
The Nuclear Regulatory Commission issued the Demand to VECTRA on January 13. 1997, in response to numerous deficiencies in VECTRA's Quality Assurance (OA) Program that were identi fied during NRC inspections between June 1995 and December 1996.
Performance Improvement International (PII) performed an independent assessment of VECTRA's OA Program and design change and control process in response to client and NRC concerns. The assessment and follow up corrective actions were presented by PII at the May 9 meeting.
VECTRA addressed the implementation status of the corrective actions and stated that the self-imposed work stoppage would not be lifted until all restart issues were resolved.
The NRC staff is continuing its review of VECTRA's written response to the Demand. The staff has requested further information from VECTRA to support the conclusions discussed in its response.
No decision on the adequacy of VECTRA's response will be made until all information has been received. At the conclusion of the meeting. NRC staff stated their intention to perform an inspection of VECTRA's corrective actions prior to restart of fabrication activities.
ENCLOSURE B May 23, 1997 1
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Office of Nuclear Regulatory Research Items of Interest Week Ending May 23, 1997 Recycle Subcommittee Meetina of the Interaaency Steerina Committee for Radiation Standards NRC staff met with their counterparts from EPA and DOE in a May 11, 1997 Recycle Subcommittee of the Interagency Steering Committee for Radiation Standards.
EPA provided a summary of the status of their rulemaking activities on the topic of rulemaking.
EPA has virtually completed its risk assessment modeling and cost / benefit analysis in support for a pre-proposed i
i rule for comment from the public. The timing of their pre-proposed rule is i
i undetermined. The proposal for NRC, EPA. and DOE to use one model for recycle j
risk assessment was discussed.
NRC staff recommended that further comparison of each agency's approach and differences be examined to determine whether there are differences in approach, and the significance of these differences before considering a single model, CONTACT: Robert A. Meck RPHEB/DRA/RES d
(301) 415-6205 IAEA Advisory Grouo Meetino on " Safety Asoects of NPP Aaina" 4
At the invitation of the Deputy Director General of IAEA. a member of the Electrical. Materials and Mechanical Branch participated and chaired the 5
Advisory Group meeting, on " Safety Aspects of Nuclear Power Plant Aging." held i
on May 5-9, 1997, in Vienna. Austria.
Representatives from nine member state countries participated: United States. United Kingdom. France. India. Canada.
l Japan, Korea. Russian Federation and Switzerland.
The participants presented their country's programs related to aging research, plant lifetime management, j
problems of NPP aging, safety assurance and approaches, and measures of aging.
The major elements of the current IAEA program on the safety aspects of NPP l
l Aging are:
- 1) to promote awareness of needs for aging management to maintain safety in operating NPPs. 2) to develop aging management guidelines for member 4
j states to use, and 3) to disseminate information and guidelines, and provide assistance to the member states on emerging issues related to aging. The staff anticipates continuing our support of this program and related activities of the IAEA's Safety Division 's programs.
i Cooperative Severe Accident Research Proaram (CSARP) Meetina 1
i The annual Cooperative Severe Accident Research Program (CSARP) S) ring 1997 Review meeting took place on May 5-8, 1997, at the Residence Inn )y Marriott.
Bethesda, Maryland. The meeting was attended by more than 117 research 1
l scientists, technical managers, and regulators from 18 CSARP Partner countries and from national laboratories, universities, utilities, and two federal j
agencies in the United States including NRC.
Progress in severe accident research and implementation since the Spring 1996 meeting was discussed in the areas of fuel-coolant interactions and debris coolability, in-vessel phenomena and lower head integrity, hydrogen behavior, source term research. DCH issue resolution. steam generator tube integrity, and severe accident codes.
ENCLOSURE C May 23, 1997
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i Meetino of Interaaency Committee on Standards Policy 7
i On May 13, 1997. the Interagency Committee on Standards Policy (ICSP) met at I
the NRC to discuss federal agency implementation of Public Law 104-113, 4
" National Technology and Transfer Act of 1955," and OMB Circular A-119.
" Federal Participation in the Development and Use of Voluntary Standards,"
This meeting was a periodic meeting of the ICSP, which is comprised of the agency Standards Executives required by A-119. Mr. John Craig (RES). NRC Standards Executive, provided an overview of NRC's use of codes and j
standards, and Direction Setting Issue (DSI)-13. " Role of Industry." Other agencies will make similar presentations in the future.
Meetings of the ICSP l
provide a mechanism for NRC staff to, among other things, interact with other regulatory agencies to discuss mutual issues regarding implementation of the law and circular, and interfaces with respective stakeholders.
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i ENCLOSURE C May 23, 1997 I
1 Office for Analysis and Evaluation of Operational Data Items of Interest Week Ending May 23. 1997 Preliminary Notifications (PNs) a.
PNO-I-97-029. Department of Veterans Affairs Medical Center. APPARENT 4
l MISADMINISTRATION INVOLVING UNDER-DOSING A PATIENT WITH I-131.
b.
PNO-I-97-030. Larchmont Imaging Associates. CONTAMINATED PACKAGE RECEIVED BY PRIVATE PRACTICE MEDICAL FACILITY.
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PNO-II-97-028. Hospital San Pablo. INADVERTENT INCINERATION OF SMALL
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CALIBRATION SOURCES.
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PNO-III-97-044. Community Hospitals of Indiana. Inc., UNDERDOSAGE IN IRIDIUM-192 TREATMENT.
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PNO-III-97-045 Mallinckrodt Nuclear Medicine. SHALLOW-DOSE OVEREXPOSURE i
TO THE THUMB 0F A RADIATION WORKER.
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PNO-III-97-046. Northern States Power Company (Monticello 1), PROPOSED MERGER TERMINATED.
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PNO-III-97-047. Northern States Power Company (Prairie Island 1. 2).
PROPOSED MERGER TERMINATED.
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PNO-III-97-048. Wisconsin Electric Power Company (Point Beach 1. 2).
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PROPOSED MERGER TERMINATED.
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PNO-III-97-049. Anheuser-Busch. Inc.. MISSING AMERICIUM-241 SOURCE.
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PNO-III-97-050. R. M. Wester and Associates. AMERICIUM-241 SOURCE DISCOVERED DURING SCRAP YARD SEARCH.
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PNO-IV-97-023B. Western Atlas Logging Services, UPDATE TO NONRADIATION WORKER EXPOSURE IN AN AGREEMENT STATE.
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PNO-IV-97-027. U.S. Air Force Radioisotope Comm.
(Brooks Air Force Base). MISSING TWO 8-MICR0 CURIE STATIC ELIMINATOR SOURCES.
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PNO-IV-97-028. Department of the Army (Evans Army Community Hospital).
MEDICAL EVENT INVOLVING DOSE TO EMBRYO / FETUS.
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PNO-IV-97-029. Madigan Army Med Center. POSSIBLE BRACHYTHERAPY j
MISADMINISTRATION.
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PNO-IV-97-030. Wolf Creek Nuclear Oper Corp. (Wolf Creek 1). MANUAL REACTOR TRIP DUE TO EXTRACTION STEAM LINE VALVE LEAK.
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PNO-IV-97-031. Usaf Radioisotope Committee. AIRCRAFT ENGINE CONTAINING NICKEL THORIUM CAUGHT FIRE AT A SCRAP YARD.
May 23, 1997 ENCLOSURE D
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Office of Administration Items of Interest 1
Week Ending May 23. 1997 4
Procurement Reform l
On May 20, 1997, a member of the Division of Contracts, provided a presentation to the Small Agency Council Procurement Committee on NRC's progress in implementing procurement reform for simali fied acquisitions.
The j!
3resentation included a brief summary of the NRC's Procurement Reinvention
_aboratory, a discussion of the efforts of NRC's Survey Team for Acquisition Reform, and an overview of training and guidance developed for NRC staff.
The committee expressed special interest in DCPM's market research center, which i
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was recently established to make resource information readily accessible to 1
contract specialists for use in evaluating potential sources for NRC contract work.
I U.S. Enrichment Corooration (USEC) i Staff from the Division of Facilities and Security (DFS) partici3ated in an NMSS briefing for Commissioners's Assistants on May 20, 1997.
T1e briefing included a discussion regarding the methodology proposed by the staff to make the statutory determinations regarding USEC's private successor required by the Privatization Act.
These determinations include ensuring (1) the successor is not owned, controlled, or dominated by an alien, a foreign corporation, or a foreign government: (2) that the issuance of a certificate would not be inimical to the common defense and security of the United States:
or (3) that the issuance of a certificate would not be inimical to the maintenance of a reliable economical domestic source of enrichment services.
An explanation was provided as to how DFS' foreign ownership, control or influence (FOCI) decision under the National Industrial Security Program would be used by the staff to assist in making the first determination.
Foreian. Ownershio. Control or Influence (FOCI) Meetina With DOE Staff At the request of the Department of Energy (DOE) members of the Division of i
Facilities and Security plan to meet with DOE staff on May 29. 1997, to discuss FOCI issues associated with the Portsmouth and Paducah gaseous diffusion plants (GDPs).
Specifically DOE believes that it is no longer their responsibility to conduct FOCI checks on USEC's subcontractors that recuire unescorted access inside the controlled boundaries of the Portsmouth anc Paducah GDPs since NRC now has regulatory responsibility for the leased portions of the plants.
Facility Manaaement Contract - NRC Headauarters The NRC facility management contractor (TECOM) hired a new Facility Supervisor. Mr. Roosevelt Dailey.
Mr. Dailey reported to his new position on May 15. 1997.
May 23. 1997 ENCLOSURE F
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l Rules Activity The.following document has been forwarded to the Office of Federal Register i
for publication:
o A final rule entitled "" Revision of Fee Schedules: 100% Fee Recovery. FY 1997" (Parts 170 and 171).
l Facsimile Teleohone Number and Address Change for the NRC's Office of the l
Secretary (Parts 2 and 110) l A final rule that amends NRC's regulations to change the name, address, and l
facsimile telephone of the Docket and Service Branch. Office of the Secretary, j
was published in the Federal Register on May 20, 1997 (62 FR 27494).
These amendments reflect a reorganization in the Office of the Secretary. The final rule became effective May 20. 1997.
Standard Desian Certification for the System 80+ Desian (Part 52)
A final rule that certifies the System 80+ design was published in the Federal l
Register on May 21. 1997 (62 FR 27840). Approving this design through l
rulemaking allows applicants for a combined license who intend to construct and operate the System 80+ design to do so by appropriately referencing this regulation.
The applicant for certification of this design was Combustion l
Engineering (ABB-CE). This final rule becomes effective on June 20. 1997.
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J Office of Personnel l
Items of Interest j
Week Ending May 23, 1997 Arrivals i
i C0YNE. Kevin GRADUATE FELLOW (PFT)
NRR FREDETTE. Thomas REACTOR ENGINEER (PFT)
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MUNDY, Thomas REACTOR ENGINEER (PFT)
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REIS. Terry PROJECT ENGINEER (PFT)
OE SILVA. Frances ATTORNEY (PFT)
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TELSON, Ross REACTOR ENGINEER (PFT)
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WELCH. Christopher REACTOR ENGINEER (PFT)
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4 Deoartures PHELPS. Karen SECRETARY (OA) (OPFT)
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i May 29. 1997 ENCLOSURE I
i Office of Small Business & Civil Rights i
Items of Interest Week Ending May 23. 1997 i
Wednesday. May 21. 1997. NRC's Small Business Program participated in the j
Defense Supply Service's Annual Procurement Opportunities Conference and j
Exposition. The purpose of this event was to bring together the large and small businesses to fulfill the requirements of the Federal Government.
Small small disadvantaged and women-owned businesses had an opportunity to display their products and services and discuss procurement opportunities with i
Federal agencies.
Tnis in turn, allowed Federal agencies the opportunity to i
identify highly competent small businesses to assist in their contracting needs.
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May 23. 1997 ENCLOSURE J J
Office of Public Affairs Items of Interest Week Ending May 23, 1997 Media Interest Region I had several calls about the teenager who ingested tritium from an
" exit" sign and the Haddam Neck proposed civil penalty.
Region III handled calls on both the Clinton and Point Beach planned restarts after long outages, and on fire protection issues at Braidwood.
School Volunteers Procram NRC hosted winners of the Special Science Fair Awards from the Montgomery Area Science Fair.
Students displayed their projects for the Commission and other NRC employees. Judges who participated included:
Vernon Hodge. Ronaldo Jenkins. George Hubbard. Tommy Le. Ramin Assa. David Matthews. NRR: Prasad Kadambi. John Craig. RES: Mysore Natarja and Heather Astwood. NMSS.
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Press Releases Headauarters:
97-075 Note to Editors:
ACRS Meeting j
'97-076 NRC Certifies GE Nuclear Energy's Advanced Boiling Water Reactor Design 97-077 Note to Editors: ACRS Reports on design basis verification.
proposed final policy on economic deregulation, policy on stockpiling of potassium iodide 97-07B NRC Establishes Special Assistance to Small Businesses97-079 NRC Sends Letters to Sierra Nuclear. Three Utilities on Spent Fuel Storage Cask Welding Problems Reaions:
I-97-52 NRC Proposes $650.000 Civil Penalty for Northeast Utilities for Alleged Violations at Haddam Neck Nuclear Power Plant I-97-53 Limerick Rated " Superior" in Three Areas. " Good" in Fourth Area of Latest NRC Assessment I-97-54 NRC Staff Advises New Jersey in Response to Ingestion of Radioactive Material by 16-Year Old Union Boy 11-97-39 NRC Schedules Meeting With Duke Power to Discuss the Restart of Oconee Units 2 and 3 May 23, 1997 ENCLOSURE M f
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i 11-97-40 NRC Staff to Hold Predecisional Enforcement Conference to t
d Discuss Crystal River Nuclear Power Plant Concerns With Florida Power IV-97-29 NRC Proposes to Fine Entergy $55.000 for Violations at Waterford 3 Nuclear Power Plant i
IV-97-30 Wolf Creek Rated ' Good' in Three Areas Acceptable in Fourth in l
NRC Assessment Report i
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May 23. 1997 ENCLOSURE M j
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i-Region I 4
Items of Interest Week Ending May 23, 1997 I
Tritium " EXIT" Sions in Union. New Jersey On Saturday. May 10. 1997, the NRC was notified by the State of New Jersey that a 16-year-old male in Union, New Jersey, had contaminated himself and his home after he dismantled tubes from an " EXIT" sign containing tritium that he 1
found in rubble of a demolished building in Union. New Jersey.
The home is now being decontaminated by a contractor selected by the State of New Jersey.
The NRC confirmed that only three generally-licensed tritium " EXIT" signs had been originally distributed to the subject building.
Region I identified and i
contacted the three companies which formerly owned the demolished building at q
this site. These companies had possessed the signs under a general license.
Two Region I inspectors visited the site and met with representatives of the family and the companies who were responsible for the " EXIT" signs on Friday, j
May 16. Region I will arrange for return of the signs to the manufacturer, J
Self-Powered Lighting Company, after the signs are decontaminated by representatives from DOE's Brookhavel National Laboratory, who collected them i
during the initial event response.
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May 23, 1997 ENCLOSURE P i
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Region III Items of Interest Week Ending May 23. 1997 2
Wisconsin Eneroy Comoany and Northern States Power Comoany - Meraer Terminated On May 16, 1997. Wisconsin Energy Company and Northern States Power Company announced they were terminating their plans for a proposed merger of the two companies into a new company. Primergy Corporation.
A May 14 decision by the Federal Energy Regulatory Commission (FERC) had remanded the case to an FERC 1
settlement judge for further negotiations, including the possible sale of some
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generating facilities and other actions.
The utilities attributed their decision to changing regulatory policies on i
mergers and to further regulatory delays as a result of the FERC decision.
The proposed merger had been announced May 1. 1997.
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Manaaement Meetina with Illinois Power Company - Clinton Restart Status On May 15. 1997, a management meeting was conducted in tne Region III Office.
Lisle. Illinois, between management representatives from Illinois Power and members of the NRC staff to discuss the Clinton Power Station's restart activities.
During the meeting. Illinois Power Company staff discussed the status of the restart items.
There were a total of 55 restart action plan items and 44 of the action items have been completed.
Current startup restraints include:
circuit breaker inspection and refurbishment and open condition reports.
Illinois Power will submit reports on the remaining restart action items to NRC Region III by May 28. 1997.
Predecisional Enforcement Conference with Commonwealth Edison - Braidwood On May 14, 1997, a predecision6 enforcement conference was conducted in the l
Region III Office, Lisle. Ii:1nois, between management representatives from Commonwealth Edison Company and members of the NRC staff. The enforcement conference reviewed apparent fire protection violations at the Braidwood Station. The violations were initially identified by the utility in mid-1996.
They included roll-up doors which did not meet the specified three-hour rating as fire doors and several instances of inadequate separation of electrical cables in parallel portions of safety systems.
Predecisional Enforcement Conference with Illinois Power Comoany - Clinton On May 15. 1997, a )redecisional enforcement conference was conducted in the Region III Office. _ isle Illinois, between management representatives from Illinois Power Company and members of the NRC staff.
The enforcement conference covered apparent violations of NRC requirements in the utility's failure to take prompt and appropriate corrective action to address recurring examples of degraded lubricants on several types of circuit breakers. The lubrication problem resulted in the binding of various breaker components and May 23, 1997 ENCLOSURE P
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the failure of safety-related and critical non-safety-related circuit breakers during testing and during operation.
The degraded lubrication 3roblem 1
resulted from inadequate breaker preventative maintenance and t1e use of unapproved lubricants.
Manaaement Meetina with Commonwealth Edison Comoany - Dresden On May 12, 1997, a routine monthly meeting was conducted at the Dresden Nuclear Power Station Training Center between management representatives from Commonwealth Edison Company (Comed) and members of the NRC staff to discuss l
the status of various actions being conducted by Comed in response to NRC's November 1996 Confirmatory Action Letter (CAL).
The CAL was the result of concerns that last fall's Independent Safety Inspection of Dresden identified with the Dresden Station's engineering activities and control of design calculations.
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Maintenance Team Insoection Exit Meetina - Dresden On May 12, 1997, a maintenance team inspection exit meeting was held at the Dresden Nuclear Power Station Training Center to discuss the preliminary findings of a two-week onsite team inspection held at the plant as a follow-up to last fall's Independent Safety Inspection of Dresden.
The inspection l
identified issues in procedural adherence, work control, and engineering support.
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t May 23, 1997 ENCLOSURE P l
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Region IV Items of Interest l
Week Ending May 23, 1997 l
SALP Meetina at Wolf Creek Generatina Station On May 22, 1997, the Regional Administrator Region IV. along with other Region IV and NRR staff, attended a public meeting at the Wolf Creek 2
i Generating Station to discuss the results of the latest Systematic Assessment of Licensee Performance.
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l May 23, 1997 ENCLOSURE P i
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