ML20210K081
| ML20210K081 | |
| Person / Time | |
|---|---|
| Issue date: | 08/14/1997 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| SECY-97-185, SECY-97-185-R, WIR-970808, NUDOCS 9708190137 | |
| Download: ML20210K081 (20) | |
Text
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p-Auoust 14. 1997 SECY 97-185 EQt:
The Commissioners Etom:
James L. Blaha, Assistant for Operations, Office of the E00 l
Sub.iect:
WEEKLY INFORMATION REPORT - WEEK ENDING AtMUST 8. 1997 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*
Human Resources I
Small Business & Civil Rights J*
Enforcement K*
State Programs L*
Public Affairs M
International Programs N*
Office of the Secretary 0
Region I P
Region II P
Region III P
Region IV F
Executive Director for Operations Q*
Congressional Affairs R*
- No input this week.
an-/45 9700190137 970814 PDR COMMS NRCC James L. Blaha WEEKLYINFOREPT PDRk Assistant for Operations. OEDO T
Contact:
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e UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20066 INFORMATION REPORT Auaust 14. 1997 SffY97-185 f_qt:
The Commissioners f_r09:
James L. Blaha Assistant for Operations. Office of the EDO t
Sub.iect:
WEEKLY INFORMATION REPORT - WEEK ENDING AUGUST 8, 1997 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*
f Chief Financial Officer H*
Human Resources I
Small Business & Civil Rights J*
Enforcement K*
State Programs L*
Public Affairs M
International Drograms 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.
W ames L. Blaha Assistant for Operations. OEDO
Contact:
D. Skeen. OED0 l
1
_-- -- J
Office of Nuclear Reactor Regulation items of Interest Week Ending August 8, 1997 Publication of Vodate to SRP Chaoter 7 in Federal Reaister The final version of the update to SRP Chapter 7. Instrumentation and Controls, was published in the Federal Reaister on July 31, 1997, at 62 FR 41103.
This update to SRP Chapter 7 incorporates staff review guidance on digital instrumentation and control systems.
It will also be made available on the NRC external internet web site in the near future.
Maine Yankee On Friday, August 1. 1997, the Maine Yankee Board of Directors announced that negotiations with PEco Energy for the sale of Maine Yankee were unsuccessful.
A formal vote of the Board regarding the permanent closing of Maine Yankee Atomic Power Station was taken on Wednesday. August 6, 1997.
On August 7, 1997, Maine Yankee officials submitted a letter providing certifications of permanent cessation of power operation and permanent removal of fuel from the reactor.
Nine Mile Point. Units 1 and 2 During the week of August 5, 1997, two members of the Russian commercial nuclear power regulatory body, GOSATOMNADZOR, are visiting NRC Headquarters and Region I as part of a joint agreement between the U.S. and Russia.
Mr. Boris Orechkine is Deputy Head of the North European GOSATROMNADZOR Regional Office with responsibility for the operation and inspection of eleven nuclear power plants at three sites.
Ms. Ioulia Volosnova is an interpreter with a strong technical background. During the week of August 11, 1997, they will visit Nine Mile Point Nuclear Station to observe the onsite engineering ins Mr.pection performed by Region I (Messrs. Leonard Cheung and Joe Carrasco).
Tom Foley of the NRR's Special Inspection Branch will serve as escort.
Crystal River 3 - Restart Proaress Florida Power Corporation voluntarily shut down its Crystal River Unit 3 facility in early September 1996, to address several performance and design weaknesses. The licensee is taking extensive corrective actions to improve its performance.
The licensee's major objectives during this outage are to restore safety system margins, reduce operator burden and to provide for defense in depth.
The effort will result in significant NRR involvement with approximately 30 licensing actions to be completed before the end of this year. Of these,.
approximately 8 licensing actions are currently under staff review and the remaining licensee submittals are expected within the next two months.
The staff is maintaining good communications with the licensee and monitoring the licensee's progress toward meeting their schedules for licensing submittals to ensure that the staff can complete its review consistent with the plant restart schedule.
August 8, 1997 ENCLOSURE A
__s
The licensee is making progress in its planned physical and design
- modifications consistent with its restart plans and milestones.
Some of the significant hardware modifications that have been completed are:
installation
-and testing of emergency feedwater (EFW) cavitating venturies (to prevent EFW
) ump runout), restoration of the steam admission valve to the turbine driven EFW to "A" train initiation (for: improving reliability of the EFW pump), and installation of a motor operator and remote operation of the EFW pump discharge crosstie valve (for reducing operator burden).
Modifications have commenced to improve the load capacity of the energy diesel generators (EDGs).
Each EDG modification is expected to take approximately 45 days.
Therefore.
l the licensee has submitted an exigent licensing amendment for a one time postponement of a required 31-day EDG surveillance on the protected EDG while the other EDG modification is in progress.
Dresden. Unit 2 - Feedwater Transient and Manual Scram of the Unit 2 On July 28. 1997. Dresden. Unit 2, was manually scrammed from approximately 87 percent power following a feedwater flow transient.
i While Unit 2 was operating at 100 percent aower the 2B reactor feed aump (RFP) minimum flow talve cycled open and tien closed. The licensee close to remove a 2B RFP f om service to repair the minimum flow valve.
Power was reduced w 87 perceit power to make the swa) from the 2B RFP to the 2C RFP.
Vessel level began increasing when the 2C R:P was brought on line.
The high level alarm of +35" was received in the control room, Operators took action to reduce feedwater flow by closing the feedwater regulating valve.
Following this action the reactor vessel water level decreased to the point where the low level alarm of +25" was received in the control room.
Operators than increased feedwater flow to compensate.
During the increase in feedwater flow the 2C RFP tripped on low suction pressure.
At that point the Unit Supervisor ordered the reactor be manually scranined. All systems operated as expected following the scram.
The licensee implemented the following corrective actions prior to Unit 2 restart.
1.
Procedure changes were implemented to strengthen the procedure concerning the swapping of feedwater pumps during power operation.
2.
All operators were trained on the eventi prior to standing watch 3.
Repair and restoration of the 2B RFP recirculation valve was completed.
As a long. term corrective action the licensee will implement 3-element control of the feedwater system, similar to Unit 3.
This will greatly reduce the challenge to operators.
Unit 3 returned to power on July 31, 1997, and is currently operating at 100%
power.
August 8. 1997 ENCLOSURE A
ZIONi Units 1 and 2 - Raisina Safety Concerns '
On-July 22, 1997, the staff issued a letter to Commonwealth Edison (Comed) stating thatsits analysis of-recent Allegation Management System issues at-Zion ' disclosed:a significant -increase in-the number of allegations' concerning-
-_ employment discrimination. -The letter requested a meeting with Comed to discuss the-steps-taken or being taken-to ensure that a safety conscious work
' environment exists at Zion Station.
On August 4. 1997, the Site Vice President (SVP) issued a memorandum to Zion Station employees explaining the mechanisms available to employees who wish to raise safcty issues. Concurrently.. the SVP issued a memorandum to Zion Station management emphasizing that an individual has a right to raise concerns about the operation of the station and-that it is a-violation of federal law and Comed and Zion-policy to discriminate against anyone who raises such a concern.
In addition, meetings with station personnel were held on August 4.1997, to ensure dissemination of management's position that employees should feel free to raise safety issues.
The resident inspectors attended at least one of the meetings. The residents and the region will continue to closely monitor allegations dealing with a chilling effect.
i August 8.-1997 ENCLOSURE A i
Office of Nuclear Material Safety and Safeguards Items of Interest Week Ending August 8. 1997 Meetina with the City of Cleveland On July 30, 1997, at the request of the city of Cleveland Nuclear Regulatory Commission representatives from Region III and the Division of Industrial and Nuclear Safety met with city officials and two city Councilmen to discuss Advanced Medical Systems (AMS). Inc., an NRC licensee that previously manufactured telethera)y sources.
The city officials including the Mayor's Executive Assistant, tie Director of the Department of Health, and officials from the Watei Pollution Control Commission, the Fire Department. Emergency Medical Services, and the City Law Department, expressed their concerns regarding:
the health and safety as)ects of emergency response at the licen.see's London Road facilities, t1e facility's outer appearance. and the unrasponsiveness of the licensee to requests and violations from various city departments.
The city Councilmen requested information on what the NRC is doing to require the licensee to address area residents' concerns about safety and health issues that appear to be associated with the facility (e.g.,
unexplained local cancer decreased proaerty values, inadequate site security.
l etc.).
The Councilmen also indicated tlat local residents are considering i
suing AMS for the unexplained health effects.
Local businesses have contracted for, and will soon release results of, an inde)endent review of AMS' risk to the local residential / business community. T1e city will Federal investigation of the issues surrounding AMS through the State' pursue s U.S.
Senators. The NRC staff agreed to review the city's concerns and meet again with the city representatives.
Meetina with American Association of Physicists in Medicine Committees On July 26-27, 1997, a member of the Divis' ion of Industrial and Medical Nuclear Safety participated as the Nuclear Regulatory Commission Liaison to the American Association of Physicists in Medicine's Nuclear Medicine and Therapy Committees.
Nuclear Regulatory Commission information provided to the Comittees included all relevant recent generic communications on nuclear materials. including the 1996 Information Notice on the Year 2000 issue. the draft Radiopharmacy Regulatory Guides. Regulatory Guide 8.39 on patient release, and NUREG-1516 (" Management of Medical Radiation Safety Programs").
The NRC Liaison made presentations on these topics, as well as on Victoreen electrometer/dosemeter cracked resistor circuitry, rulemaking to remove the five-year license term in 10 CFR 35.18 and revisions to Part 35.
Committee members indicated that they plan to participate in the 10 CFR Part 35 revision.
Meetino with Kazakstan Reaulatory Authorities During August 4-8. 1997, staff members from the Division of Fuel Cycle Safety and Safeguards and contractor personnel met with officials of the Atomic Energy Agency of the Republic of Kazakstan in Almaty Kazakstan, to review the status of Nuclear Regulatory Commission assistance in the development of material protection control and accounting (MPC&A) regulations and to update August 8, 1997 ENCLOSURE B
)
i
the work' plan for promulgating the regulations.
Following promulgation of-the regulations, assistance will be provided for the development of MPC&A licensing-and inspection programs.
Meetina'with-the Deoartment of Enerav On July 30. 1997, staff from the Division of Waste Management and the Spent Fuel Project-Office met with the Department of Energy (DOE) and DOE contractor staff-to discuss their approach to characterizing _and grouping the different types of DOE-owned spent fuel which will be disposed of in the planned high-level waste geologic repository at Yucca Mountain. Nevadh.
The DOE-owned spent fuel consists of 250 fuel types totaling -about 2500 metric tons of heavy -
metal (MTHM) at various DOE sites (e.g.
Hanford. Savannah River. Oak Ridge).
While the inventory of DOE-owned spent fuel is small compared to the amount of spent fuel anticipated from commercial light water reactors (about 63.000 MTHM). it varies widely in terms of its chemical composition, cladding.
l enrichment.-physical characteristics, and physical condition.
For example.
l some of the metallic fuel at Hanford is in a severely degraded condition.
The primary reasons for characterizing and grouping the DOE-owned spent fuel are i
to support development of waste package design concepts for the fuels and to evaluate the long-term performance of these waste packages in the repository
-environment.
DOE has consolidated the 250 types of spent fuel into 15 categories (e.g., U metal fuels. M0X fuels. U-Zr fuels) for performance assessment purposes.
l August 8. 1997
' ENCLOSURE B
Office of Nuclear Regulato'y Research r
Items of Interest Week Ending August 8, 1997 Reactor Pressure Vessel Lower Head Failure Exoeriments The fifth test in a series of tests on reactor pressure vessel (RPV) lower head failure was conducted successfully at the Sandia National Laboratories (SNL) on August 1. 1997.
This test was performed in a 1/5-scale RPV lower head (0.96-meter diameter) with penetrations at a pressure of 10 MPa. The difference between this test ana previous tests was the presence of nine penetrations within a maximum heated region in conjunction with an edge heat flux distribution (i.e., simulating heat flux distribution in a convecting molten corium pool).
The purpose of this test was to examine the relative importance of vessel deformation versus configurations. The preliminary results showed that the vessel failed with a horizontal tear at about 36" latitude (90' is the vessel bottom center), i.e., in the maximum heat flux region, indicating vessel deformation is more significant than local penetration weld failure.
l Detailed examinations of the test results to determine the effective rupture area and the corresponding relationship with the vessel temperature distribution are under way.
Future tests will be performed at different heat l
loads and pressures.
Experimental data from these experiments will be used to j
assess and validate analytical models of RPV lower head failure.
Reoort on 00timizina Inservice Test Intervals A technical report. NUREG/CR-6508. has been published on " Component Unavailability Versus Inservice Test (IST) Interval: Evaluation of Component Aging Effects With Applications to Check Valves." This report provides methods for determining the optimum check valve inservice test interval considering aging and unavailability, including downtime because of tests and maintenance.
These results provide useful information that can be supplemented or u3 dated with plant-specific information. The models and results can also ]e used as input to PRAs to determine associated risk implications.
Trial Acolication of ATHEANA Dr. Catherine Thompson DST /RES and contractors from Sandia National Laboratories participated in meetings at the Seabrook nuclear power plant during the week of August 4 to begin the first trial application of ATHEANA (A Technique for Human Event Analysis). ATHEANA is an improved human error analysis (HRA) method under development by the Office of Nuclear Regulatory Research that incorporates a combination of performance-shaping factors and plant conditions to assess the likelihood that human errors will occur.
In addition, it provides a technique for assessing errors of commission (doing the wrong thing), which are not addressed in other HRA techniques.
This trial application will continue through the end of October.
August 8. 1997 ENCLOSURE C
l Meetina with NE1 and Licensees on New Risk-Informed initiative On July 30, 1997. RES. NRR,-AE00, and OGC staff members met with NEI and three potential pilot plant licensees on a proposed new risk-informed industry initiative. This initiative was proposed by NEI in a May 20, 1997 letter to Chairman Jackson and involves a broad review of plant-specific activities for their safety significance, their costs, and the associated regulatory requirements, with a goal of improved allocation of resources to the most safety-significant activities.
The three )ilot plants (South Texas. San Onofre, and ANC) are prepared to try out tie process after agreement has been reached on certain ground rules for the initiative.
Following discussion of both the process proposed by NEI and the conceptual approach, NEI agreed to formally submit a more detailed discussion of the proposed initiative for the staff's review, in general, the staff agrees that the approach proposed by NEI could be useful in identifying candidate areas for modifying requirements in a risk-informed fashion consistent with DSI-12.
Schedular and resource implications of working with NEI on their initiative are under discussion.
Foreian Procrams for Environmental Qualification (E0) of Electric Cables During July 16-24, 1997, members of the DET/RES staff visited four European countries--Germany, Switzerland France, and Sweden--for technical information exchange primarily on topics related to the environmental qualification (EQ) of electric equipment. Their visits included three nuclear power plants and a German test facility at Karlstein.
In general, the EQ requirements in the countries visited are similar to those in the United States.
Thus, EQ research results from those courtries are believed to be pertinent to our EQ program, even though the specific cable materials can be different from those used in the United States.
The staff members were briefed cn the various research programs and discussed o)portunities for continued technical exchange, particularly in those cases w1ere the data are believed to be most relevant.
For example Siemens/KWU in Germany has a comprehensive long-term program on aging behavior of cable materials. The program includes loss-of-coolant accident (LOCA) testing of naturally aged cables and com with those aged artificially.parison of electrical and mechanical pro)erties The long-term cable studies performed ay Germany will provide useful data on the uncertainty associated with accelerated aging and Arrhenius methodology, which is one of the specific issues being addressed in the NRC's EQ program.
Researchers in Sweden presented relationships between the physical and electrical properties of cable insulating materials under LOCA conditions, which also may supplement NRC's ongoing program.
The staff will continue to interact with appropriate European institutions and organizations to ensure that all pertinent research results and operational experiences are addressed in our program.
August 8, 1997 ENCLOSURE C a
e OfficeLfor_ Analysis and: Evaluation of Operational Data
. Items of Interest-Week Ending August 8 _1997 Preliminary Notifications (PNs) a.
PNO-I-97-047.- Niagara Mohawk Power Corp. (Nine Mile Point 2), REACTOR SHUTDOWN DUE:TO UNIDENTIFIED' LEAKAGE =IN EXCESS OF TS LIMITS b.
PNO-I-97-046. Maine Yankee Atomic Power Co.-(Maine Yankee 1), PLAN DECOMMISSIONING ANNOUNCEMENT - MEDIA ATTENTION c.
PNO-II-97-042, Goodrich Testing & Engineering Co. (An Agreement State Licensee), STOLEN MOISTURE DENSITY MUGE d.
PN0-I-97-045, GPU Nuclear Corp. (0yster Creek 1), PLANT SHUTDOWN GREATER THAN 72 HOURS e.
PN0-III-97-065,'I111nois Power Co. (Clinton 1) -AUGMENTED INSPECTION TEAM TO REVIEW 4160 VOLT-CIRCUIT BREAKER FAILURE
-f.
PNO-I-97-048, Public Service Electric &-Gas Co. (Salem 2). SALEM UNIT 2 RESTART-
=l 4
August 8, 1997 ENCLOSURE D i
Office of Human Resources Items of Interest Week Ending August 8, 1997 Human Resources Staff Member Attends Interaaency Adult Decendent Care Meetina On August 7, 1997. Barbara Mack. of the Human Resources Development staff, attended the Interagency Adult Dependent Care meeting at the Office of Personnel Management. The guest speaker was Dana L. Pfeifer. Manager, Community Education. Visiting Nurse Association of Northern Virginia /VNA Community 1:0 spice, who focused on the many services available for the elderly through the Visiting Nurse Home Care System.
Thirty representatives from government agencies attended the session.
Arrivals 3ATEL, Priya GENERAL ENGINEER (PFT)
NMSS Retirements None Qgoartures GADZALA, Jack RESIDENT INSPECTOR (PFT)
RI t
August 8, 1997 ENCLOSURE 1
Office of Public Affairs Items of Interest Week Ending August 8, 1997 Media Interest A meeting at Watts Bar describing tritium testing attracted 50-60 demonstrators and media interest.
There was press interest in the Haddam Neck incident when a digital camera inadvertently actuated the halon system in the control room.
Newsday published a series of' articles on past and current problems with high-level waste, including the quality assurance of spent fuel casks, emergency l
preparedness for first responders, and technical problems at Yucca Mountain.
The Chicago Sun-Times has published numerous articles on the union problems at Zion.
Press Releases Headauarters:
97-111 Note to Editors: ACRS Meeting on August 27; defense-in-depth and risk-informed regulation 97-112 Note to Editors: ACRS Meeting on August 27: candidates for appointment t
97-113 NRC Terminates License for Decommissioned Fort St.
Vrain Nuclear Power Plant 97-114 Martin Named Director of Office for Analysis and Evaluation of Operational Data: Ross A)
Office of Nuclear Regulatory Research ) pointed to the ost 97-115 Note to Editors: ACRS meeting August 28-29 on Probabilistic Risk Assessment, Plant Operations, and Fire Protection 97-116 NRC Withdraws Proposed Rule on Reporting of Unauthorized Use of Radioactive Materials
.97-117 Note To Editors: ACRS Meeting on Materials and Metallurgy and Severe Accidents on August 26-27.
Reaions:
I-97-97 NRC Staff Assigns New Resident Inspector to Indian Point 3 August 8, 1997 ENCLOSURE M l
<I-97 98 NRC Staff Bars President of New Jersey Medical Firm; Consultant from Participating in Activities Licensed by Agency.
I-97-99 NRC Proposes $80,000 C1'il Penalty. Bars Two Former v
Workers for Records Falsification at Limerick Nuclear Plant I-97-100 NRC Region I Administrator Approves Restart of Salem-Unit 2 1-97-101 NRC Staff to Meet With Northeast Utilities. Public on Millstone 111-97-71 NRC Staff Proposes $110,000-Fine Against Illinois i
Power Co. for Circuit Breaker Maintenance at Clinton Nuclear Plant 111-97-72 NRC Augmented Inspection Team to Review Circuit l
Breaker Failure at Clinton Nuclear Plant-t H
-111-97-73 NRC to Hold Predecisional Enforcement Conference With U.S. army 111-97-74 NRC Commissioner Nils Diaz to Hold News Briefing Aug.
12 Following Visit to Dresden Nuclear Power Station
-l o
~ August 8, 1997 ENCLOSURE M
9 Office of the Secretary Items of Interest Week Ending August 8, 1997 Comission Decision Documents Released to the Public Document Dittg Subiect 1.
M970804A 8/4/97 Staff Requirements - Affirmation Session, Monday. August 4, 1997:
Secy-97-141 - Atlas Corporation: Docket No.
40-3453 MLA: LBP-97-9. Memorandum and Order (Denying Hearing Request) 2.
M970807B 8/7/97 Staff Requirements - Affirmation Session. Thursday, August 7, 1997:
1.
Secy-97-165 - Ralph L.
Tetrick. Atomic Safety and Licensing Board Initial' t
Decision. Memorandum and Order Denying Reconsideration and Stay, and Order on Remand: LBP-97-2. LBP-97-6 LBP-97-11:
and II.
Comsecy-97-017 - 7/30/97 Letter from Native American Petitioners in the Matter of Energy Fuels Nuclear.
Inc.
Corporation (White Mesa Uranium Mill:
Alternate Feed Material))
Neaative Consent Documents Released to the Public 1.
SECY-97-136 6/26/97 Removal of the Anne Arundel County /Curtis Bay Depot Site from the Site Decommissioning Management Plan
- SRM on 97-136 7/29/97 (same)
Information Pacers Released to the Public 1.
SECY-97-166 7/29/97 Recovery of Millstone Nuclear Power Station 2.
SECY-97-170 7/31/97 Weekly Information Report - Week Ending July 25, 1997 3.
SECY-97-171 7/30/97 Consideration of Severe Accident Risk in NRC Regulatory Decisions 4.
SECY-97-172 8/1/97 The Maintenance Rule: Monitoring the Quality of 10 CFR 50.65(a)(3) and Methods for Monitoring its Efficacy
?
August 8, 1997 ENCLOSURE O
4 Commission Corresoondence Released to the Public 1.
Memorandum from Chairman Shirley Ann Jackson to L, Joseph Callan.,EDO.
dtd 7/1/97, concerns the statement of core damage frequency of 10' as a fundamental Comission goal 2.
Letter to Congress dtd 7/30/97 provides the quarterly report on the nondisclosure of Safeguards Information for the calendar year quarter beginning April 1 and extending through June 30. 1997 3.
Letter to Dr. Robert E. Uhrig dtd 7/29/97 offers an appointment to a four-year term on the Advisory Comm' ?ee on Reactor Safeguards 4.
Letter to Senator Joseah R. Biden dtd 7/29/97 concerns fire barrier penetration seals at tie Salem facility 5.
Letter to Paul Leventhal. Nuclear Control Institute, dtd 7/28/97 concerns Commonwealth Edison Company's possible use of mixed oxide fuel in one or l
more of its twelve nuclear power plants Federal Reaister Notices Issued 1.
Apalication for a License to Export Nuclear Material: Cambridge Isotope La as 2.
10 CFR Part 20: Reporting Requirements for Unauthorized Use of Licensed Radioactive Material: Proposed Rule:
Withdrawal 3.
Joint Meeting of the ACRS Subcommittees on Materials and Metallurgy and on Severe Accidents: Notice of Meeting on August 26 and 27, 1997 Atomic Safety and Licensina Board's Issuances 1.
NORTHERN STATES POWER COMPANY (Inde)endent S)ent Fuel Storage Installation): Docket No.
72-18-IS SI: MEMORANDUM AND ORDER (LBP-97-13):
(Terminating Proceeding) 7/30/97 August 8, 1997 ENCLOSURE 0
e Region !
Items of Interest Week Ending August 8, 1997 Intearated Industrial Systems Insoection On July 31 - August 1,1997, Region I, accompanied by staff from the Division of Nuclear Materials Safety and Safeguards, conducted an inspection of Integrated Industrial Systems in Yaleville Connecticut.
This company manufactures and distributes fixed gauges containing radioactive materials.
The inspection identified a number of instances where the gauges differed from the design that had been approved by the NRC for distribution.
On August 7, 1997, Region I issued a Confirmatory Action Letter that confirmed the licensee s consnitment to review all of its drawings to identify any deviations from the ap deviations, proved design to evaluate the safety significance of any to report their findings to the NRC, and to request any needed modifications of the approved design.
L i
August 8, 1997 ENCLOSURE P
=.:
Region II Items of Interest Week Ending August 8, 1997 McGuire Nuclear Plant Emeraency Exercise-An off-hours exercise was conducted on August 6.1997, involving officials of-the State of North Carolina and the applicable local governments. The off-hours exercise was successful: however, one weakness was identified in the area of emergency action level notifications.
Virainia Electric and Power Comoany Meetina Representatives from Virginia Electric and Power Company were in the Region II Office this week to provide an update on Maintenance Rule activities at North
-Anna and Surry facilities.
Actions taken by the licensee include development l
of a new scope and performance criteria matrix, revising program procedures.
L providing training to implementing personnel, performing an interim l:
assessment, and making organizational changes.
h Duke Power Comoany - Oconee Nuclear Station Self-Assessment Representatives from Duke Power Company were in the Region II-Office to present a self-assessment of Oconee Nuclear Station performance, including a-discussion of the new Unit 3-integrated control system. -Licensee management focused the discussions on the overall performance in each of the SALP functional areas, highlighting strengths, areas of progress, and plant challenges.
Watts Bar Public Heeti m on the Tritium Demonstration Pro.iect An NRC public meetie a
'21d August 7,'1997 -in Sweetwater, Tennessee to provide an opportum
~
,iblic comment on the technical issues regarding i
the tritium productit a
.t Assembly (LTA) project.
Presentations by DOE, TVA. and NRC cove
't scope.. technical issues, regulatory reviews, and inspection effort.
- 1ng was well attended by the public and included U.S.-Congressiona, ocaff and local and national news organizations.
Concerns were raised on the tritium production in a commercial reactor.
Research Reactor Insoection Proaram Transfer On August 4. research reactor inspection and incident response activities that had been the responsibility of Region II were transferred to NRR.
August 8, 1997 ENCLOSURE P 4
Region III
^ Items of Interest Week Ending August 8, 1997 Clinton Nuclear Power Plant - Auamented Insoection Team Dispatched and Confirmatory Action Letter issued On August 5. 1997, an Augmented Inspection Team (AIT) was dispatched to the Clinton Nuclear Power Station to review the failure of a circuit breaker early that day during a change of pumps in the shutdown cooling system. The utility was preparing to start the plant up following a shutdown which began September
- 5. 1996.
A similar circuit breaker failed to open on July 22, 1997.
On August 6,1997. Region III issued a Confirmatory Action Letter (CAL) to l
Illinois Power Company documenting the utility's agreement to, among other things, form an independent investigation team to establish the failure mechanism for the breaker under the observation of the AIT.
The CAL also documents that the utility will meet with the NRC to discuss the breaker l
repairs and failure determination prior to restarting the plant.
l Commonwealth Edison Meetina On August 5.1997. a management meeting was conducted in the Region III Office. Lisle. Illinois, between management representatives from Commonwealth Edison Company and members of the NRC staff to discuss the performance indicators that Comed is using to monitor and assess performance of the utility's nuclear
)ower stations. At the meeting. Comed also discussed actions that were being taten to improve performance at the stations. This is the utility's second meeting with NRC staff following the April NRC Commission Meeting regarding the 50.54(f) letter issued by NRC to Comed.
Predecisional Enforcement Conference with Detroit Edison Comoany On August 6. 1997, a predecisional enforcement conference was conducted in the Region III Office. Lisle Illinois, between management representatives from Detroit Edison Company and members of the NRC staff. The discussion focused on inadequate maintenance and corrective action on certain switches, gears, and motor-operated valves, affecting safety systems at the plant. Also discussed was the utility's failure to take corrective action regarding an inadequate calibration technique used on oxygen monitors inside the plant containment building.
Predecisional Enforcement Conference with the U.S. Army On August 8, 1997, a predecisional enforcement conference was conducted in the Region III Office. Lisle Illinois, between management representatives of the U.S. Army and members of the NRC staff. The discussion focused on the Army's apparent failure to adequately manage its radiation safety programs at various military installations. The Army is licensed by the NRC to use radioactive material -- tritium, americium-241, and nickel-63 -- in such applications as self-luminous fire control devices (weapons sights), chemical agent detectors, and in chemical agent monitors.
August 8. 1997 ENCLOSURE P l
o
0' Predecisional Enforcemant Conference with Northern States Power Comoany On August 8,1997, a predecisional enforcement conference was conducted in the Region 111 Office Lisle, Illinois. between management representatives from Northern States Power Com)any and members of the NRC staff. An NRC inspection completed June 13 found tlat the criteria for measuring the flow of auxiliary feedwater pumps did not accurately reflect the design requirements for the pumps. The inspection also determined that the plant staff had found a test-criteria problem with the testing of other pumps in 1991, but did not expand its review of pump testing to the auxiliary feedwater system.
}
August 8, 1997 ENCLOSURE P
m Region IV Items of Interest Week Ending_ August 8, 1997 NRC Heetina with Houston Liahtina and Power Comoany on Auaust 5. 1997
-On August-5, 1997, a meeting was held between Houston Lighting and Power Company, the licensee for-the South Texas Project Electric Generating Station and NRC Region IV personnel.
This meeting was held to discuss the status and plans for the instrument scaling and setpoint programs.
San Onofre Manaaement Meetina A meeting was held in the Region IV office between Region IV and Southern California Edison management, on August 5, 1997,_to discuss the San Onofre-Nuclear Generating Station Employee Concerns Program implementation and
-status,-
l Waterford 3 Performance Imorovement Plan Meetina-On August 6, 1997, personnel from Waterford 3 met with the NRC Regional and Headquarters staffs to discuss the progress toward completion of their performance improvement plan.
Meetina with Nebraska Public Power District Industry Advisory Grouo (IAG)
On August 7, 1997, the Nebraska Public Power District IAG met with the Region IV Regional Administrator and members of the Region IV staff-in Arlington, Texas. The IAG reports directly to the Board of Directors. The IAG discussed their role and operating procedures.
Diablo Canyon Manaaement; Meetina On August 7,1997, the NRC staff and Pacific Gas & Electric Company (Diablo Canyon) managers met in the Region IV office to discuss the-licensee's self-assessments and. improvement programs in the areas of engineering and
-maintenance, August 8, 1997 ENCLOSURE P