NUREG-1150, Weekly Info Rept for Wk Ending 890922
| ML20248E463 | |
| Person / Time | |
|---|---|
| Issue date: | 09/27/1989 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| RTR-NUREG-1150 WIR-890922, NUDOCS 8910050242 | |
| Download: ML20248E463 (36) | |
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. September 27, 1989.
-For: The Commissioners From: James L. Blaha, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING SEPTEMBER 22, 1989 A sumary 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 external distribution)
- No input this week.
M Ja s L. Blaha, Assistant for Operations i
fice of the Executive Director l- for Operations
Contact:
n James L. Blaha, OEDO 492-1703 '
8910050242 890927 j D
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1 Qg HIGHLIGHTS OF. WEEKLY'INFORMATION REPORT WEEK ENDING SEPTEMBER 22, 1989 4 Browns Ferry, Units 1, 2 and 3 On September 15,1989, the Tennessee Valley Authority informed the staff-that it intended to submit a Part 21 notification concerning unqualified cables affecting operability of shutdown boards. Specifically, TVA recently discovered that the power cables for those HVAC units providing cooling to the
. shutdown board rooms are not environmentally qualified for harsh environments.
A Part 21 notification will be sent on September 20. The affected equipment 1 was manufactured by Ellis Watts Engineering of Ohio.
DOE Acceptance of Greater-Than-Class-C (GTCC) Low-Level Waste On September 14,1989, JosephColeman',U.S.DepartmentofEnergy(D0E), briefed
' the Advisory Comittee on Nuclear Waste on DOE's program for managing Greater-Than-Class C (GTCC) LLW. During this briefing, DOE described their program for limited acceptance of GTCC waste for interim storage, pending development of dedicated storage and disposal capacity. DOE is proposing to accept GTCC waste for interim storage provided that there exists a serious threat to public health and safety, that NRC or an Agreement State verifies this threat, and that the generator is financially unable to' provide storage.
According to DOE's schedule, their interim storage program would become
. operational in the first part of 1990.
Hurricane Hugo Hurricane Hugo came. ashore at Charleston, South Carolina at approximately midnight on September 21, 1989. Region II and Headquarters manned the incident response centers and monitored the plants in Georgia, South Carolina, and North Carolina, as well as fuel facilities in the storm affected area. .No Region II plants sustained significant damage nor did any facility experience a loss of off-site power as a result of this storm. 0ne facility, Brunswick, took its operating unit to cold shutdown as a precautionary measure. The other Brunswick unit had been placed in cold shutdown several days earlier as part of a scheduled refueling outage. During the storm, Notices of Unusual Events were declared by two facilities, Brunswick'and Susener, as a result of high winds.
NUREG-1150 Peer Review Meeting On September 13-14,1989, the NUREG-1150 Peer Review Group held a meeting in Albuquerque, MM. The committee discussed with RES staff and contractors responses to a series of questions raised subsequent to the first comittee meeting (in July 1989). Many of the questions related to how the NUREG-1150 probability distriubtions were developed (including how expert judgment was used) and applied in the risk analyses. The committee has scheduled its next meeting for January 18-19, 1990, in the Washington, DC area for further discussions with the staff on the NUREG-1150 external events analysis methods and other topics. A March 8-9, 1990, meeting was also scheduled for the committee to assemble and review a draft report of its findings. l Idaho Not To Accept Fort St. Vrain Spent Fuel Idaho Governor Cecil Andrus has written to the Department of Energy stating that the State is not prepared to accept shiments of spent fuel from Fort St. Vrain for the purposes of storage in Idaso.
Office of Nuclear Reactor Regulation Items of Interest Week Ending September 22, 1989 Arkansas Nuclear One, Unit 1 The Babco::k & Wilcox Safety and Performance Improvement Program (SPIP) programmatic audit is being performed on September 18-20, 1989 at the Arkansas One site in Russellville, Arkansas. The audit team consists of three contractors from INEL and the Arkansas One project manager. Programmatic audits have been completed previously for Crystal River, Unit 3; Oconnee, Units 1, 2 and 3; Davis-Besse; and Three Mile Island, Unit 1. The Rancho-Seco programmatic audit is delayed The second round of SPIP pending(~
audits determination of plans for future operation.the implementation audits) is plan The team has found that each utility has reviewed and implemented the SPIP recommendations in its own way, but all programs reviewed appeared to meet the intent of the B&W SPIP program.
Browns Ferry, Units 1, 2 and 3 On September 15, 1989, the Tennessee Valley Authority informed the staff that it intended to submit a Part 21 notification concerning unqualified cables affecting operability of shutdown boards. Specifically, TVA recently discovered that the power cables for those HVAC units providing cooling to the shutdown board rooms are not environmentally qualified for harsh environments.
A Part 21 notification will be sent on September 20. The affected equipment was manufactured by Ellis Watts Engineering of Ohio.
Turkey Point Unit 4 On September 15,1989 Unit 4 was manually scramed because of a large primary /
secondary load mismatch, which resulted from automatic closure of a turbine stop valve. The turbine stop valve closed on low EHC oil pressure, which was a result of oil leaking from a cracked weld in the EHC oil line. The rod control system began to insert rods automatically but stopped after only 4 steps of insertion.
The operators tried to manually insert rods with the control system but were unsuccessful. Therefore, the reactor was manually tripped. The rod control system failure is known in the industry as " urgent failure", which sometimes occurs in Westinghouse comparator whose voltageplants, signaland hadindrifted this instance was caused by a TThisdidn6V*/Taff$[t out of range.
the safety function of the separate reactor trip system. A manual safety injection was initiated per procedure when pressurizer level dropped to 12%.
However, no injection took place because RCS pressure dropped only to 1750 psi, l while the SI shutoff head is 1600 psi. The "C" steam generator experienced J some overfeed to about 85% (narrow range) because the solenoid-controlled MFW !
regulating valve did not close; this was caused by a sticking solenoid valve, I which was later discovered to have metallic shavings caught in it. The SG hi-hi level signal resulted in "C" MFW isolation valve closure, per design.
The RCS cooled about 52*F due to the SG overfeed.
SEPTEMBER 22, 1989 ENCLOSURE A
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.The SI signal started both EDGs. There was a small oil leak in an instrument line on one EDG; this was easily repaired and probably would not have prevented operation of the EDG if needed. A standby FW pump was started because MFW pump
^ restart was temporarily prevented by the high SG 1evel signal. A charging pump (4C), which is controlled by pressurizer level, unexpectedly went to idling speed as level rose and tripped off on low oil pressure. About 90 minutes after the event, the operators tried to restart a MFW pump. However, a manual valve would not open in the pressure equalization line across the MFW discharge valve, and the discharge valve motor burned out.
The event included several equipmert failures; however, the operators appear to have performed well. The operators commented that the E0Ps worked well. No safety system failures occurred. Some public interest has been noted because of a failure in the rod control system. It is important to note that this was not an ATWS event, and the reactor trip system performed per design.
The' licensee has investigated the event, determined the root causes of the failure and is repairing the equipment. Restart is expected by September 21.
The resident inspectors are following the licensee's activities closely.
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SEPTEMBER 22, 1989 ENCLOSURE A
Office of Nuclear Material Safety and Safeguards Items of Interest Week Ending September 22, 1989 SAFEGUARDS International International Atomic Energy Agency (IAEA) Inspection at General Electric (GE) facility An unannounced safeguards inspection by a three member IAEA team began on September 20, 1989 at the GE low enriched uranium fuel fabrication facility in Wilmington, North Carolina. The IAEA will audit the records and perform measurements.
Domestic Licensee Use of Tactical Exercise Results In November 1988, the NRC issued a final rule requiring, among other things, that Category I licensees carry out performance evaluation through tactical response exercises. The design, conduct, and critique of the exercises are discussed in NUREG/CR-5081, Tactical Exercise Planning Handbook. The Division of Safeguards and Transportation staff is now developing a guide, entitled
" Licensee Use of Tactical Exercise Results," which will enable a licensee to use the results of exercises to determine whether additional training or security improvements are needed.
. Transportation TN-RAM Lead Pour On September 15, 1989, members of the Transportation Branch travelled to Boston, Massachusetts to observe the pouring of the lead shield for the TN-RAM shipping cask. The TN-RAM cask was designed by Transnuclear, Inc. to transport irradiated hardware. The cask design was certified by the NRC on September 14, 1989.
The leau shield for the TN-RAM cask is 6-1/4 inches thick and required Prior to the lead peur, the cask and approximately 40,000 pounds of lead.The lead was gravity-poured into an annular space
' lead were heated to 850*F.
between inner and outer stainless steel shells and cooled from the outside by water spray. Additional lead was added to compensate for shrinkage as the lead solidified. The cask is x-rayed to verify there are no voids in the shielding.
INDUSTRIAL AND MEDICAL NUCLEAR SAFETY Fuel Cycle Safety West,Velley Demonstration Project A team safety assessment was performed at the West Valley Demonstration Proj2ct during the week of September 11, 1989. Inspectors from Region I SEPTEMBER 22, 1989 ENCLOSURE B
.and a staff member from Headquarters participated. The purpose of the assessment was to evaluate the safety of the Vitrification Facility at West Valley, which will be used to convert high-level liquid waste to borosilicate glass beginning in 1992 or 1993. The team found no shortcomings in three of the five areas evaluated: welding, ventilation systems, and environmental monitoring. In the fourth area, quality assurance; the team found some problems, but also noted improvements since the last team assessment in January 1988. .Most of-the problems identified were in the fifth area, component design and-fabrication.. The staff is preparing a written report describing
.each finding in detail, and the Department of Energy will be asked to respond to the more serious items.
LOW-LEVEL llASTE MANAGEMENT DOE Acceptance of Greater-Than-Class-C (GTCC) Low-Level Waste On September 14, 1989, Joseph Coleman, U.S. Department of Energy (DOE), briefed the- Advisory Committee on Nuclear Waste on DOE's program for managing Greater-Than-ClassC(GTCC)LLW. During this briefing, DOE described their program for limited acceptance of GTCC waste for interim storage, pending development of dedicated storage and disposal ca)acity. DOE is proposing to accept GTCC waste for interim storage provided t1at there exists a serious threat to public health and safety, that NRC or an Agreement State verifies this threat, and that the generator is financially unable to provide storage.
According to DOE's sch2dule, their interim storage program would become operational in the first part of 1990.
HIGH-LEVEL WASTE MANAGEMENT NRC-Staff Audit of DOE Yucca Mountain Project Office Audit During the week of September 11-15, 1989, Division of High-Level Waste Management (DHLWM) staff Mountain Project Office (performed an observation audit of the DOE Yuc Albuquerque, New Mexico. SNL is the DOE /YMP0 contractor for data management, performance assessment, and conceptual design activities.
The NRC team consisted of QA and technical staff who evaluated both the SNL QA program and the effectiveness of the DOE audit. The NRC team noted improvements in the implementation of the audit. The DOE auditors reviewed and utilized the requirements contained in implementing documents (e.g., QA l
and Division Operating Procedures, Work Plans, Design Investigation Memoranda, and Study Plans) and were thorough in reviewing the presented objective evidence. However, the NRC staff is concerned with the effectiveness of the QA program, since SNL had not identified deficiencies in previous audits and surve111ances. Because there has been limited implementation of the SNL program to date, DOE and NRC will monitor (e.g., by surveillance) the SNL program closely to ensure that future implementation is carried out in an acceptable manner.
SEPTEMBER 22, 1989 ENCLOSURE B Y - _-__
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n- Office of Nuclear Regulatory Research Items of Interest Week Ending September 22, 1989 i' Integrity of Reactor Components Blowdown Tests on MOVs Begin I
The first of a second series of blowdown tests on flexible wedge isolation valves in a high flow velocity, hot water environment was recently completed.
This accident environment is typical of that which can be expected to occur should a Reactor Water Cleanup System pipe develop a guillotine break outside a BWR containment. These isolation valves must close under these harsh conditions.
The tests are intended to provide important technical information on valve closure thrust requirements and motor operator diagnostic equipment measurements and capabilities related to Generic Issue (GI) 87, " Failure of the HPCI Steam Line Without Isolation".
The preliminary results and observations from the first test indicated that the disc travel was within 0.5 inches _of complete closure at operator trip. Therefore, the valve failed to completely isolate all f70w. The thrust plot indicates that the disc and guides may have experienced damage during closure.
These results are similar to those obtained in the first series of tests. Those test results were used in developing Generic Letter 89-10 " Safety-Related Motor Operated Valve Testing and Surveillance," that was issued on June 28, 1989.
Following removal from the test loop, the valve will be disassembled and inspected for damage. Similar tests on other typical isolation valves will be conducted. All information from these tests will be made available to utilities to use, as appropriate, in their response to GL 89-10.
Meeting to Review Evaluation of Core Damage frecuency Changes Due to Aging The work completed by Dr. W. Vesely, Science Applications International Corporation (SAIC), regarding the inclusion of aging effects on active component failure and the effect on changes in core damage frequency was presented and discussed with the NRC staff and management from NRR, RES, National Labora-tories and other contractors. The work will provide valuable input to the regulatory analysis supporting the license renewal rulemaking. The results were viewed as a first step in quantifying the changes in core damage frequency due to the effects of aging of specific active components.
The work also showed:
o an excellent usage of NUREG-1150 results as a baseline for judging the impact of aging for specific plants; o that a group of active components can most likely be identified which control the core damage frequency; 1
1 SEPTEMBER 22, 1989 ENCLOSURE C
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- o- thatlthe effects of aging can most likely.be. controlled by incor -
- + :porating maintenance and replacement schedules for components deemed q7 to be the main contributors that. impact the.PRA results; P o. that more credibility can be given'to the evaluation for establish-1 ing and developing regulatory actions pertaining to maintenance and license renewal rules.
J It wasithe consensus of the meeting attendees that the effects.of aging on p .g ' passive components such as pipes, pressure vessels and containments are also b important;as contributors to core damage and reduction in defense-in-depth.
Therefore, it was agreed that the aging effects on these components should
- also be reflected in this work. The acceptance of this latter. item demon-(strates the need for future aging-related research activity; therefore,.
technical basis for incorporating.the aging effects on these components into the'PRA will be developed under the Nuclear Plant Aging Research Program.
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' Containment Performance and Protection from Radiation NUREG-1150 Peer Review Meeting c
On September 14,1989, the.NUREG-1150 Peer Review Group held a meeting in Albuquerque, NM. . The committee' discussed with RES staff and contractors responses to a'. series of-questions raised subsequent to the first committee meeting (in July 1989). Many of the questions related to how the NUREG-1150 probability distributions were developed (including how expert judgment was used) and applied in the risk analyses. The committee has scheduled its next meeting for January 18-19,~1990, in the Washington, DC area for further
' discussions with the staff on the NUREG-1150 external events analysis methods and other topics. A March 8-9, 1990, meeting was also scheduled for the committee to assemble and review a draft report of its findings.
Resolving Safety Issues and Developing Regulations Policy on Exemption Dose Criteria Battelle Pacific Northwest Laboratory in Richland, Washington (PNL), under contract with the NRC, is developing a report that will be the technical basis for the implementation of the Commission's Policy on Exemption Dose Criteria as applied to criteria for unrestricted use of facilities after decommissioning.
On September 12 and 13, three members of the Division of Regulatory Applications met with~PNL staff members to discuss NRC staff comments and provide guidance on
.the content of that report. The issuance of the technical basis report, as a NUREG, is currently scheduled for December 1989. A companion document, which
.will provide interim guidance for the implementation of the Commission's Policy,
' using the PNL report as a technical b? sis, will be developed in parallel to the extent practical and on an expedited schedule.
OTHER ITEMS Regulatory Guide Issuance Reg. Guide 3.50, Rev. 1 " Standard Format and Content for a License Application to Store Spent Fuel and High-Level Radioactive Waste,"
SEPTEMBER 22, 1989 EHCLOSURE C
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September 1989, Task CE 402-2.
Contact:
W. Pearson, RES (301)492-3764 Regulatory Guide Withdrawal The NRC staff is withdrawing Reg. Guide 1.74, " Quality Assurance Terms and Definitions," because it has become obsolete. The guide endorsed ANSI N45.210-1973, " Quality Assurance Terms and Definitions," which has since been incorporated into ANSI /ASME NQA-1, " Quality Assurance Program Requirements for Nuclear Facilities." ANSI /ASME NQA-1 is endorsed by Reg. Guide 1.28, " Quality Assurance Program Requirements (Design and Construction).
Contact:
O. Gormley, RES (301)492-3743 SEPTEMBER 22, 1989 ENCLOSURE C
p Office for Analysis and Evaluation of Operational Data Items of Interest Week Ending September 22, 1989 Committee to Review Generic Requirements (CRGR)
The CRGR visited Fort Calhoun on September 21 and 22, 1989 to discuss with station management and plant operators matters relating to generic communi-cations and to the NRC regulations and policy on backfitting.
Division of Operational Assessment (DOA)
During the week of September 18, AE0D and Region II, in coordination with NRR and NMSS, monitored the. progress of Hurricane Hugo and the actions taken by potentially affected licensees. The Headquarters Operations Center and the Region II Incident Response Center were placed in a state of enhanced readiness on September 21. Representatives of Region II, NRR and AE0D monitored the status of Brunswick through the early morning hours of September 22 over an open telephone line to the site. The Boisie Interagency Fire Center portable satellite communication system was transported to and installed at the Brunswick site and proved to be an effective backup communication link. The status of other licensees' preparations for the approach of Hugo were also periodically monitored.
During the week of September 18, the Incident Response Branch (IRB) published a manual on protective measures (NUREG/BR-0132) which is being distributed to the Regions. The manual contains standardized technical procedures dealing with a wide range of issues related to protective measures, including core damage assessment, event classification, and projection of consequences.
During the week
" Radiological of September Assessment 18,Consequence System for IRB also published Analysis a comp (uter program entitled, R for the Argonna National Laboratory code center to distribute it. RASCAL is a standardized code for conducting independent assessments of dose projections from isotopic releases, and it also has the capability to estimate releases based on dominant accident conditions.
Preliminary Notifications The following Preliminary Notifications were issued during the past week.
- a. PNO-II-89-65, Virginia Electric & Power Company (Surry Unit 2), Surry Unit 2 Restart.
- b. PNO-II-89-66, Carolina Power & Light Company (Brunswick Units 1 and 2);
Florida Power & Light Company (St. Lucie Units 1 and 2); Georgia Power Company (Hatch Units 1 and 2), Preparations for Adverse Weather Conditions.
- c. PNO-II-89-66A, Southeast Nuclear Facilities, Adverse Weather Conditions -
Update of PHO 11-89-66.
i SEPTEMBER 22, 1989 ENCLOSURE D l
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- d. PNO-II-89-67, Carolina' Power & Light Company (Brunswick Unit 2), Alert -
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e.- PNO-III-62, Kerr-McGee Chemical Corporation (Docket 40-2061), Ordinance Banning Shipments of Radioactive Material.
- f. PNO-IV-89-59, Department of the Air Force, USAF Radioisotope Committee, t Accountability Loss of Four Brachytherapy Seeds.
- g. _PNO-IV-89-60, Gritman Memorial Hospital, Incinerated Technetium-99m Generator.
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PH0-V-89-57, Pacific Gas & Electric Co. (Humboldt Bay Power Plant, Unit 3),
L Earthquake 45 Miles Southwest of Facility.
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SEPTEMBER 22, 1989 ENCLOSURE D
Office of Governmental and Public Affairs Items of Interest Week Ending September 22, 1989 INTERNATIONAL PROGRAMS:
International Visitors:
I On Friday, Mr. Tomihiro Taniguchi, Director, Nuclear Power Division, Agency of Natural Resources and Energy, Japan Ministry of International Trade and Indus-try, had separate meetings with Harold Denton, James Taylor and Eric Beckjord to discuss the current status and future direction of Japan's nuclear power program.
Exports / Imports During the week ending September 22, 1989, an export license application was received from the Uniwrsity of Washington / School of Oceanography for 3 micro-curies of U-233 for use in experiments at Institute of Earth Science, Hebrew University in Israel.
Licenses for export were issued to: 1) Mitsubishi International Corporation -
Natural Uranium for use as fuel at Tsuruga 2 in Japan; 2) Transnuclear, Inc. -
HEU for use as fuel in the HFR Grenoble Research Reactor in France; 3) General
- LEU for use as reload fuel for Fukushima I, Unit I in Japan; Electric Company
- 4) Mitsui & Co. (U.S.A.), Inc. - LEU for use as reload fuel for Fukushima II, Unit I in Japan; LEU for use in R&D of photo-ionization of uranium vapor lazer in Japan; Natural Uranium for experiments on vaporization of uranium metal;
- 5) Marubeni America Corp. - LEU for use as reload fuel for Shimane Unit I in Japan; and 6) Westinghouse Electric Corp. - LEU in the in Canada form of UOcont and return to the U.S.
STATE, LOCAL AND INDIAN TRIBE PROGRAMS Southern Governors' Association Annual Meeting Carlton Kammerer, the Southern Governors'Director AssociationofSGA)AnnualMeetingonSeptember17-19, State,(Local and Indian Tribe Programs, atte 1989 in Wilmington, Delaware. The Southern States Energy Board (SSEB) held its annual meeting concurrently in Wilmington on September 17, 1989. The SGA ac-complished the following:
o Adopted a resolution on transuranic (TRU) waste management which calls for southern States affected by the transuranic waste program to receive funding from the Department of Energy and the Department of Transportation at a level commensurate with that afforded the western States for the purpose of ensuring their waste transportation management capabilities.
o Adopted a resolution concerning hazardous waste management which calls for a continued close working relationship between the States and the Environmental Protection Agency and further l
SEPTEMBER 22, 1989 ENCLOSURE E
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[ states that SGA strongly. believes that Superfund and the Resource Conservation and Recovery Act (RCRA) should be
['I < administered in a coordinated manner to achieve an effective waste management strategy with necessary projections.for public-
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M . health and the environment.
L h o. Supported regional cooperation among States as a primary strategy to find solutions to hazardous waste management
,. ' problems.
e L'i o 'Will soon establish a task force to study the safety aspects of L new shipping casks.for the transportation of high-level
- radioactive waste-and TRU.
os Adopted an acid rain resolution, and o Elected Mississippi Governor Ray Mabus as Chairman and Kentucky g
, , Governor Wallace Wilkinson as Vice Chairman.
Meeting with Texas State Liaison Officer
' Auburn Mitchell, Energy Advisor to the Governor of Texas and Stato Liaison.
Officer . visited NRC Headquarters on September.18, 1989. He was accompanied by Lee Mathews, General: Counsel of the Texas Low-Level Radioactive Waste Disposal Authority. . Mr. Mitchell met with representatives of NRR:to discuss the status of South Texas and Comanche Peak. He met with representatives from NMSS to discuss-low-level waste issues including the Governors certification milestone requirement, mixed waste, the status of developing a' site in Texas, the pro-posed Environmental Protection Agency LLW standard, the status of naturally.
occurring.andaccelerator-producedradioactivematerials(NARM),and"below regulatory concern" (BRC) and mill tailings regulation.
Dyster Creek Local Public Meeting H ' Region I representatives conducted a local public meeting for residents and local governing officials from around the Oyster Creek Nuclear Power Plant on September 19, 1989 in Toms River, New Jersey. The purpose of the meeting was to provide'the public with an overview of the NRC inspection process and to discuss access to NRC documents and participation in NRC public meetings and.to introduce NRC staff associated with the facility. The New Jersey Department of Environmental Protection outlined its nuclear power plant surveillance program.
Approximately 40 people attended the meeting which was very well received.
Maryland State Senate Hearing on Calvert Cliffs The Maryland State Senate Economic and Environmental Affairs Committee con-
- ducted a hearing on the status of.the Calvert Cliffs Nuclear Power Plant on September 19, 1989 in Annapolis, Maryland. Representatives from Region I and NRR provided the Committee with the status of the NRC review of the facility.
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SEPTEMBER 22.-1989 ENCLOSURE E
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' Region 'II' State Liaison Officers' Meeting -
An'NRC-State Liaison Officers' Meeting was held for-.the Governor-appointed
' State Liaison ~ Officers.(SLO) in Region II on September 19-20, 1989 in Atlanta, Georgia. The" purpose of.this meeting was'to provide a forum for discussion of'
. items of interest for State officials in Region.II,and the NRC. Presentations were made by various NRC staff on the regulatory functions of the Region, communications with the public,.the NRC Enforcement. Policy, the Commission:
interest'in States'. activities, status of Congressional. legislation, evaluation' of operational safety, and NRC views on mixed waste. A representative of the
- ' Southern States Energy Board (SSEB) gave a presentation on a recent SSEB trans-
- portation study and.a . representative from the Federal Emergency Management' Agency:(FEMA)<gave an overview of. the FEMA emergency response program.- There were also State presentations on mixed waste, the'Radiat i on Sterilizers, Inc.
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- incident, emergency response and updates on nuclear issues within each State.
West Chicago Passes Ordinance Banning Waste Shipments The City Council of West Chicago passed an ordinance on September 20, 1989 which prohibits the transportation of. radioactive materials through'the city for the purpose of. storage or, disposal in West Chicago without authorization
'from appropriate Federal and State' authorities. Kerr-McGee has been cleaning-up' contaminated areas of thorium waste which had been identified as a result of L aerial surveys performed by the Department of Energy. The sites in question Lare outside the city limits.
Uranium Mill Tailings Meeting-Vandy Miller, Assistant Director for State Agreements, participated in a meeting on uranium mill-tailings regulation on September 21, 1989 in Arlington,
' Texas. The purpose of the meeting was to discuss implementation of groundwater requirements for uranium recovery facilities with representatives from the mill
~ States (Agreement;andnon-AgreementStates). NRC will sponsor a workshop.on the. issue of groundwater requirements at uranium sites in early.1990.
Idaho Not To Accept Fort St. Vrain Spent Fuel Idaho Governor Cecil Andrus has written to the Department of Energy stating
.that the State is not prepared to accept shipments of spent fuel from Fort St. Vrain.for the purposes of storage in Idaho.- i 7
I SEPTEMBER 22, 1989 ENCLOSURE E
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Items of, Interest =
Week' Ending' September 22, 1989 y
' Contract Guards Replace' Federal Protective Officers at WFN-GSA has advised NRC<that because of resource constraints they will.have.to reassigntheWFNFederal. Protective' Officers (FP0s)tootherpostslintheDC U ' area effective October 1,'1989. . Thus, effective that date, Guardian Security.
. Agency personnel will be assigned full-time. to the 17th and 18th floors on weekdays from 7:00 a.m. to 7:00 p.m. FP0s will still be on call for special l, .assigments or emergencies at WFN.
Significant FOIA Requests Received-by the NRC for.5-Day Period September.15 21, 1989
- Request-for a copy of the.01 investigation report on testing of. fasteners at
- the. Comanche Peak nuclear power plant. (Stan Jones, Fort Worth Star-Telegram,
.F01A-89-394)
LRequest for:a copy of the November 1,--1986 draft " Configuration Management
- Handbook" p epared for NRC by NASA. (Rita Wirth, Gilbert / Commonwealth, Inc.,
~ . Request for background information and supporting records used at-Senior imanagement meetings on the Calvert Cliffs nuclear power plant. (Kirsten Burger,-
- State of Maryland, F01A-89-396)
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Request for a list of cases involving regulatory action that have led to criminal convictions. (Andrew Welt, Alpha Omega Technology, Inc., F01A-89-397)
' Request for a copy of an ED0 memorandum regarding NRC's regulatory impact
> _. survey.(OpheliaWilliams,J/R/AAssociates,FOIA-89-399)
Request'for copies of all. records concerning the following at Indiana University: (1) storage, removal, clean-up and transportation of radioactive materials and equipment; (2) burials of radioactive materials; and
.(3) accidents and violations related to the handling.of radioactive materials andequipment.(LeolaWolfe,F01A-89-401)
Request for copies of all records supporting two specified statements in Region Y's report on EE0 Initiatives.-(Tolbert Young, Northern California Council of Black Professional Engineers, F01A-89-402) _
u Request-for a copy of the selectee's abstract under solicitation RS-IRM-89-148.
(Tracey Shelton, FSM Leasing,-Inc.,.FOIA-89-403) 6 Request for 14 categories of records from January 1, 1983, to the present related to circuit breakers. (Donald Pepperman of Blecher & Collins, FOIA-89-404)
I SEPTEMBER 22, 1989 ENCLOSURE G
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' " Items of Interest
. Week Ending September 22,~.1989 1989 Hispanic Employment Program Achievement Award Frank L. Elizondo has been awarded the Washington Metropolitan Area 1989 Hisaanic Employment Program (HEP) Achievement Award. This award is presented eac1 September by the Office of Personnel Management for outstanding n contribution-in furthering the recruitment and advancement of Hispanics in the Federal workforce. Mr. Elizondo is currently the Recruitment Officer in the Office of Personnel.
1990 Combined Federal Campaign' Activities The'1990 Combined Federal Campaign (CFC) was kicked off in the Commission Hearing Room, One White Flint North, on Monday, September 18, 1989. Chairman Carr presented awards to those offices who had made significant contributions
. to the 1989 CFC. .Special guest speakers included Carrie Crawford of NRC, Denise Ridgely of the American Red Cross, and Frank Hardin and Jackson Weaver of_WMAL Radio. The kickoff meeting was broadcast to all Regional Offices.
Training Conducted in Region IV Muel Meadows of Policy and Program Effectiveness conducted training sessions in Region ~IV on September 19 and 20, 1989. The training covered hours of work and' premium pay.'
Arrivals The following employee (s) reported this week:
Sharon Green, Clerk-Typist (PFT), NRR
.CraigTate, Investigator (PFT),01 DanielBarss,RadiationSpecialist(PFT),RIII Mark Satorius, Reactor Engineer Examiner (PFT), RIV Departures Andrew Bieniawski, Technical Intern (OFPT), ACRS Donald Cameron, Physical Security Inspector (PFT), RI Laurence Friedman, Sr. Health Physicist (PFT), RI RobertLoesch,RadiationSpecialist(PFT),RI SEPTEMBER 22, 1989 ENCLOSURE J
Office of Enforcement Items of Interest Week Ending September 22, 1989 Significant Enforcement Actions A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $625 was issued to Bradley Memorial Hospital, Southington, Connecticut on September 18, 1989. The action was based on violations involving the failure to: train workers, perform constancy tests, determine molybdenum-99 break-through properly, calibrate and test survey instruments, establish trigger levels, include all required information on various records, measure ventila-tion rates, and implement written procedures. (EN89-85)
A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $50,000 was issued to New York Power Authority (Indian Point 3) on September 19, 1989. The action was based on several security violations related to access control, personnel and package search, compensatory measures for degraded assessment aids, and illumination in the Protected Area. (EN89-86)
An Order Imposing A Civil Penalty in the amount of $500 was issued to Mayaguez Medical Center, Mayaguez, Puerto Rico on September 20, 1989. The action was based on numerous violations that, in the aggregate, were considered to !
represent a significant breakdown in management control of licensed activities.
(EN89-39A)
An Confirmatory Order Suspending License (Effective Immediately) was issued to Ultrasonic Specialists, Inc., Scott Depot, West Virginia on September 20, 1989.
the action was based on the licensee's request to terminate its license after an OE investigation, which is still in progress, was initiated in response to allegations that the licensee's president submitted inaccurate information to the NRC as to his statements of education, training, and experience in radiography.
(EN89-89)
A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $75,000 was issued to Commonwealth Edison Company (Zion) on September 21, 1989. The action was based on multiple examples of the failure to ensure that vital area barriers were capable of deterring intrusion. (EN89-87)
Civil Penalty Paid Philadelphia Electric Company (Limerick Nuclear Generating Station) paid the civil penalty in the amount of $75,000. The action was based on: (1)the inability of the operations staff to effectively utilize the Emergency Action Level Event Classification guides to properly escalate emergency classifications andmakeappropriateProtectiveActionRecommendations,and(2)thefailure to promptly correct deficiencies in the emergency preparedness program which were identified during previous Nuc1 car Quality Assurance audits. (EA89-126) l 1
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SEPTEMBER 22, 1989 ENCLOSURE L
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' Items of Interest Week Ending September 22, 1989 L1. : DOE West Valley Demonstration Project A; team review of[the Department of Energy's West Valley Demonstration -
Project was' conducted during the week of September 11. 1989. The nine person Monitoring Team ~was comprised of personnel from NRC Region I, NMSS-
,i andLan NMSS contractor. The team reviewed plans,. equipment and monitoring L programs:related to vitrification of .the high level waste at the. site,
- k. The Monitoring Team's principle recommendations were.to strengthen the DOE
^ contractor's design interface control. system and to provide more attention 1
j ,to deta11Lin'the vitrification: design review: process. The team also;
.determinedzthat the contractor's-internal self-assessment program should-'
be enhanced aseit relates to the Site Quality Assurance Program. No
.significant observations.or recommendations were made-with regard to the
> . Effluent Monitoring Program at the site.
E . 2.- :Calvert Cliffs
-On September 19,,1989, at 1:00 p.m., the NRC briefed the Economic and Environmental Affairs Committee of the Maryland State Senate on NRC's perspective of Calvert Cliffs. Mr. J. Wiggins.from Region I led the.
staff's presentation. He was accompanied by Messrs. R. Capra and S. McNeil of NRR and Ms. Rosetta Virgilio of SLITP..
4
- 3. Pilgrim Nuclear-Power Station A practice emergency preparedness exercise was conducted September 20, 1989,'at the Pilgrim Nuclear Power Station.- Representatives of the Federal Emergency Management Agency (FEMA) are assisting in the. training of offsite, pert,onnel. NRC personnel are observing the practice exercise.
- The full-participation exercise (to be observed and evaluated by NRC and FEMA)isscheduledfortheweekofOctober 10, 1989.
- 4. Pilgrim
' As of 7:30 a.m. on September 20, 1989, the reactor was at about 75% power.
-- On September 18, 1989, a Restart Assessment Panel Meeting was held at the NRC Region I Office to begin evaluations regarding licensee e
readiness for release from the 75% approval point and to allow
- . operation and testing up.to full power. The licensee also briefed H the Panel on their current assessment of the Power Ascension Test Program and requested release from the 75% approval point.
-- The licensee conducted a dry run Emergency Preparedness drill on' September 20 in preparation for the full scale exercise scheduled for October 12-13, 1989. The dry run included site evacuation and accountability of station personnel, activation of emergency SEPTEMBER 22,.1989 ENCLOSURE N
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response facilities and emergency operations facilities, and.a-
~
partial. demonstration of simulated offsite evacuation.
Th'e NRC Restart Staff.is in extended day' shift coverage and will
-continue to monitor the licensee's performance throughout'the Power Ascension Test Program.- Region _I specialists are on site observing the dry run emergency drill.
SEPTEMBER 22, 1989 ENCLOSURE N
Region II Items of Interest Week Ending September 22, 1989 Region II-
- 1. Hurricane Hugo Hurricane Hugo came ashore at Charleston, South Carolina at approximately midnight on September 21, 1989. Region II and Headquarters manned the incident response centers and monitored the plants in Georgia, South Carolina,'and North Carolina, as well as fuel facilities in the storm affected area. No Region II plants sustained significant damage nor did any facility experience a loss of off-site power as a result of this storm. One facility, Brunswick, took its operating unit to cold shutdown l
~
as a precautionary mea;ure. The other Brunswick unit had been placed in cold shutdown several. days earlier as part of a scheduled refueling outage. During the storm, Notices of Unusual Events were declared by two facilities, Brunswick and Summer, as a result of high winds.
- 2. Florida Power & Light Company On September'18, the Regional Administrator was in Miami, Florida to present operator license certificates-to Florida Power and Light Company's Turkey Point operators.
' On September 19, the Regional Administrator and selected Region II and NRR managers were at the Turkey Point Nuclear Power Station to participate in a Management Meeting regarding performance of the Florida Power and Light Company's Performance Improvement Program.
- 3. Virginia Electric & Power Company On September 19, Commissioner Rogers, accompanied by the Director, Divi-sion of Radiation Safety and Safeguards, and a Project Engineer, were at the Virginia Electric & Power Company's Surry Nuclear Power Station for site familiarization.
- 4. State Liaison Officer's Meeting On September 19 - 20, the Regional State Liaison Officers' Meeting was conducted in the Region II Office.
SEPTEMBER 22, 1989 ENCLOSURE N
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Region III F Items of Interest Week Ending September 22, 1989 j
- 1. LaSalle Nuclear Power Station
-On' August 28, 1989, during a short maintenance outage, the Unit 2' main E
generator was flooded while an air purge of the generator was taking place.
The' service air system used for that purge had been cross-tied to the o clean condensate water system during an unrelated activity; The Unit 2 main generator. rotor was sent offsite for repair on September 16,.1989, and is expected back onsite'in mid-November for installation in the F Unit 1 main generator. Unit 1 is in a.70-day refueling outage expected to'end~in late November. The. Unit I rotor will be installed in the c, ' Unit 2 main generator by October 14, 1989, and Unit 2 will be returned to' operation.
- 2. Fermi 2 Nuclear Plant-During'a scheduled refueling shutdown on September 2, 1989, the licensee noted unusually high' vibration on the main turbine. One scheduled
. activity-during the outage was a full inspection of the turbine. During-the inspection of the No. 2 low pressure turbine on September 16
'and 17; 1989, the licensee identified damage to the rotating blades of-the 5th stage on both the turbine side and generator side. The generator side was worse with the shroud gone and nine blades separated from the
' wheel. One blade was missing on the turbine side. A consultant is onsite
~ to assist the licensee in evaluating the damage. Preliminary investigation indicates that the blades may have failed due to tangential vibration
- caused by' flow oscillations in the steam flow between the 4th and 5th stage.
Full core off-load is scheduled to be completed on September 23, 1989.
Reload is scheduled to begin on October 5,1989. The outage is approximately 2 days behind schedule.
b
- 3. .AdvancedMedicalSystems.-Inc.(AMS)
On September 10, 1989, C. J. Paperiello, Deputy Regional Administrator,
=and members of the staff met with representatives of AMS in an Enforcement Conference to discuss: (1) the licensee's failure to report to the NRC defects in the timers used by AMS in teletherapy units; and (2) the issue of a material false statement presented to 01 investigators by a former AMS Radiation Safety Officer.
- 4. Combustion Engineering, Inc.
On September 19, 1989, A. B. Davis, Regional Administrator, and members of.the staff met with the licensee to review the licensee's investigation
-into the cause of the uranium (UF6) release that occurred from their Hematite facility on August 29, 1989, their corrective actions and their plan for re-start of their facility. The licensee's facility modifications i
and corrective actions appear adequate and a Region III inspector is onsite monitoring startup.
< SEPTEMBER 22, 1989 ENCLOSURE N
- 5. Commonwealth Edison Company (Dresden) l As a result of problems identified with a waste storage room at Nine Mile Point, Region III contacted its licensees to determine if a similar ;
situation may exist. The Dresden Station identified a waste tank room l which has some residual waste on the floor from prior tank overflows and use for temporary water storage. On September 20, 1989, C. E. Norelius, j Director, Division of Radiation Safety and Safeguards, and staff conducted '
a Management Meeting with CECO to discuss the licensee's plans for decontamination and cleanup of these waste tank rooms. The licensee plans to clean the room during 1990. This schedule is acceptable to the Region. f i
- 6. Public Meeting on Motor Operated Valves t
On September 18, 1989, a meeting was conducted by NRR personnel at the O' Hare Marriott on Generic Letter 89-10 regarding motor-operated valves.
This'was a public meeting to review the Generic Letter and answer questions. Approximately 75 utility and vendor persons attended as well as Region III staff including the Deputy Director, Division of Reactor Safety.
- 7. Zion Nuclear Power Station The Zion Station requalification program was evaluated by Region III examiners during the week of September 11, 1989. One of the three crews evaluated failed the simulator portion of the evaluation. To ensure confidence in the continued safe operation at Zion in spite of this crew failure a fourth and fifth crew were also evaluated on the simulator under various adverse conditions. The results of these evaluations were satisfactory. However, the Zion program for operator requalification will be designated Unsatisfactory based upon the failure of one crew to recognize an ATWS condition. Operators on the failed crew will require decertification by the NRC prior to resuming licensed activities.
- 8. Clinton Nuclear Power Station NRC requalification examinations were administered at the Clinton Nuclear Power Station the week of September 11, 1989, to eight Senior Reactor Operators (SR0s) and seven Reactor Operators (R0s). The facility failed three SR0s based upon the written examination; and one RO for the Job PerformanceMeasures(JPMs). Given the facility statistics of 75%
licensed operators passing the NRC requalification examinations, the Clinton Requalification Program would be considered satisfactory.
- 9. Kerr-McGee Corporation l
Dr. Carl J. Paperiello, Deputy Regional Administrator, at the request of the Mayor, attended an emergency meeting of the West Chicago, Illinois, City Council. At that meeting the Council passed an ordinance that would prohibit the intra-state transport of radioactive material and radiologically contaminated materials into the City of West Chicago for the purpose of storage or disposal. The purpose of the ordinance was to stop the Kerr-McGee Corporation from moving contaminated soil from homes SEPTEMBER 22, 1989 ENCLOSURE N
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- W outside the city limits to the factory site within the city limits. A court challenge by Kerr-McGee is expected by the City. Currently, under a Connission order on Kerr-McGee, material offsite with the exception of Cress Creek is source material and under the jurisdiction of the State of Illinois; material onsite and in Cress Creek is defined as byproduct-material under Section 11(e)(2) of the Atomic Energy Act (i.e. mill
-tailings) and under the jurisdiction of the NRC. Both Kerr-McGee and the State of Illinois have challenged the Commission ruling and the matter is in a Federal Court which has not stayed the order. While Kerr-McGee notified NMSS in a letter dated September 1, 1989, that it was proceeding-with this work, they_ did not request a license from the State of Illinois.
There is extensive press coverage of this matter. Region III is keeping NMSS'and the Office of State Programs informed. Both Region III and State inspectors have visited the work site and identified no safety problems.
Kerr-McGee has been told that the State of Illinois has jurisdiction in i
the case. Currently, all work has been halted-in response to the ordinance.
SEPTEMBER 22, 1989 ENCLOSURE N
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Region'IV-a;
.. , Items of Interest:
Week Ending September 22, 1989
' 1; States Agreement Meeting g A; meeting was' held in Region IV'on September 21, 1989, on groundwater L ; requirements pursuant to EPA's 40 CFR 192, NRC's 10 CFR.40, and compatible-R ' state regulations. This meeting was for managers;of state radiation control programs for uranium recovery facilities. All states-having such
- facilities were. invited to the meeting. It is expected that a workshop on-the same subject will be scheduled after the first of next year.
- 2. Waterford 3 Waterfor'd 3 began a scheduled l refueling outage at~12 midnight on September l22, 1989.. The outage is scheduled for 59 days, i
SEPTEMBER 22, 1989 ENCLOSURE N
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ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING SEPTEMBER 22, 1989 4
A. STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND V0TE, 10:00 A.M.,' MONDAY, E , SEPTEMBER ll, 1989, COMMISSIONERS' CONFERENCE ROOM, ONE WHITE FLINT NORTH,
?. ,
ROCKVILLE, MARYLAND (OPEN TO PUBLIC ATTENDANCE) - SECY to J. Taylor, Acting, EDO I. 'SECY-89-276 - Motion for Reconsideration Filed by Josech J.
p Macktal The Commission, by a 4-0 vote,~ approved an order' responding to an August 18, 1989,. notion by' Joseph J. Macktal_ requesting that
'the Commission reconsider its decision in.CLI-89-14 where in it.
declined to disqualify itself from deciding any future matters
< . involving Mr. Macktal. The order denied the motion to-reconsider.
II. SECY-89-194'-' Amendments to 10'CFR Part 34: Safety Requirements for Industrial Radioarachic Eauinment The Commission, by a 4-0 vote, approved amendments to 10 CFR i Part 34:which apply to industrial' radiography. The. amendments are intended to reduce radiation-exposure,to both radiography personnel and~the1 general ~public from the use of. radiographic equipment.. The Commission also modified its enforcement policy
- to add a" specific: example to put' licensees on notice that the 1fallure to. implement the requirements for dosimetry and equipment'may be:. considered a violation of.significant
. regulatory. concern.
The Commission also agreed to make the rule effective six
' months-after publication and agreed to the attached
- modifications.
The rule should be modified as noted, reviewed by the
' Regulatory Publication Branch for-conformance with the requirements of the Federal Register and returned for signature and publication.
B.- STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND VOTE, 10:30 A.M., FRIDAY, SEPTEMBER 15, 1989 COMMISSIONERS' CONFERENCE ROOM, ONE WHITE FLINT NORTH, ROCKVILLE, MARYLAND (OPEN TO PUBLIC ATTENDANCE) - SECY to W. Parler, GC dated 9/21/89-I. SECY-89-282 - Aeolicants' Reauest for an Exemotion from Requirement for an Onsite Exercise at Seabrook The Commission, by a 3-0 vote, approved an order responding to an August 11, 1989, motion from the Public Service Company of New Hampshire for an exemption from the requirement of 10CFR Part 50, Appendix E, Section IV.F.1, for the conduct of an onsite emergency exercise within one year before issuance of a full power operating license. The order denied the request.
Commissioner Curtiss did not participate in this matter.
_-SEPTEMBER 22, 1989 ENCLOSURE P
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