ML20246P916
| ML20246P916 | |
| Person / Time | |
|---|---|
| Issue date: | 09/06/1989 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-890901, NUDOCS 8909110255 | |
| Download: ML20246P916 (39) | |
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e September 6, 1989 For: The Commissioners From: James L. Blaha, Assistant for Operations Office of the EDO subject: WEEKLY INFORMATION REPORT - WEEK ENDING SEPTEMBER 1, 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 l 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 Gifices N Executive Director for Operations 0*
Items Addressed by the Comission P Meeting Notices Q Proprietary or Other Sensitive Information (Not for R externaldistribution)
- Ho input this week. j s909110255 COMI 890906 . ames L. Blaha, Assistant for Operations PDR WEEKLYIl{gyy.kC PDC fice of the Executive Director for Operations
Contact:
g[p' James L. Blaha, OEDO
' t 492-1703 l i 1 l
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l HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING SEPTEMBER 1, 1989 Meeting with USSR Academy of Science Delegation The RES Division of Engineering, Materials Engineering Branch, hosted an informal meeting with four Soviet Scientists who are touring the USA to make contacts under the Aegis of the Agreement for Cooperation signed between the US ASME Code and the USSR Acadery of Science. The Soviet personnel were:
Professors Eugene 0. Adamov, Director, and Sergei E. Bougaenko, Department Head, of the Institute of Nuclear Power Engineering, and Professors Nikolay A.
Makhutov, Department Head and Oleg A. Levin, Leading Scientist of the USSR Academy of Science.
They are particularly interested in studying factors affecting Itfe extension of plants, and are currently focusing on vastly improved measurements of stress in primary reactor systems. They are making very extensive measurements of stresses and temperatures in a YYER-1000 plant, and will share that informa-tion with us in a cooperative venture to produce better, validated analytical codes for stress predictions in plants. They will propose such cooperation to be included in the JCCCNRS Protocol for the 1990 meetings; for our part, we are quite interested to cooperate in this area, although we would hope to include work alr7ady underway by EPRI in this endeavor.
LaSalle Nuclear Power Station Unit 2
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On August 26,1989, Unit 2 experienced a reactor scram, at approximately 10% power, while shutting down in preparation for a 11anned six-day outage. During the scram it was noted that two of tie eight scram pilot I
solenoids remained energized although back up scram solenoids functioned to insert rods. The cause is under investigation and appears to involve scram signals from an unknown source combined with a scrcm contactor not opening imediately. The Senior Resident Inspector was in the control room at the time of the event. RIII dispatched a regional specialist to assist in the evaluation of the event and the 2icensee has committed to providing a. analysis of the event prior to restart.
Approval of TRUPACT-II Shippino Container On August 30, 1989, the Transportation Branch issued Certificate of Compliance No. 9218 for the TRUPACT-II shipping container. The container was designed by Nuclear Packaging, Inc. for the Department of Energy (DOE). D9E plans to use TRUPACT-II to ship contact-handled transuranic wastes from DOE defense facili-tics to the Waste Isolation Pilot Plant (WIPP). The container provides double containment and is not vented. TRUPACT-II weighs approximately 19,250 pounds when loaded with the maximum contents of 7,265 pounds.
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1 Office of Nuclear Reactor Regulation j l Items of Interest J Week Ending September 1,1989 1 H. B. Robinson An AIT has been formed to arrive at the H. B. Robinson site on August 28, 1989 to inspect the events associated with the August 21, 1989 shutdown, because of an identified deficiency in the Auxiliary Feedwater (AFW) System. The charter of the AIT calls for an evaluation of the significant. of the deficiency and its impact on safety system performance. ihe licensta's record shows that an AFW system actuation in 1986 first indicated a deficiency of the system.
Since that event, the licensee had additional opportunities to identify and correct the deficiency (e.g., two other AFW actuations in 1987; the Design Basis Reconstitution of the system in 198E). Therefore, another task for the AIT is to evaluate the licensee's action taken with regard to problems ide9tified with AFW performance. The AIT schedule is for the inspection report to be finalized on September 15, 1989.
MCGUIRE UNIT 1 While performing a design analysis in response to Information Notice 88-76, the licensee determined that the current annulus ventilation system setpoints for fan operation may not assure that the entire annulus region at all containment elevations remains at the required negative pressure during a postulated accident (between -0.5 and -3.5 inches of water). The licensee declared both trains of the annulus ventilation system inoperable and entered TS 3.0.3.
Discretionary enforcement was granted to the licensee (until 1420 EDT on August 25,1989) to enable the licensee to recalculate the appropriate setpoints for annulus fan operation. The licensee has recalculated the new setpoint to be 1.2 inches of water to -4.2 inches of water. The surveillsnee test has been satisfactorily performed for both trains of the annulus ventilation system and licensee in now out of both the discretionary enforcement and TS 3.6.1.8 LCO.
MC'GUIRE UNIT 2 On August 24, 1989, the licensee reported to the Netc a problem regarding base metal corrosion of the steel containment iteuel. The degradation is limited to a 30 foot section of the circumference, to a height of 1-1/2 inches from the containment floor and essentially consists of corrosion of generally 0.063 inch with pockets up to 0.1 inch. The source of leabge causing the corrosion is not known but is believed to have occurred several years ago and has only recently become significant enough to be visually noticeable. The most restrictive calculation for required minimum wall thickness yields 0.864 inch. The steel itner is nominally 1.0 inch thick at the base where the corrosion occurred. Hence, it does not appear that minimum wall thickness H mits has been violated. The licensee will inspect Unit 1 for similar indications as well as monitor this area on a weekly basis for the occurrence of standing water. Plans are to repair and recoat the area during the next outege.
SEPTEMBER 1, 1989 ENCLOSURE A
@ nsas Nuclear One, Unit 2 (ANO-2)
On 08/23/89 with AN0-2 at 100% power, the licensee reported the identification of a condition outside the design basis for the unit. The condition involves a postulated single failure scenario for the post accident containment hydrogen analyzers. ANO-2 has two containment hydrogen analyzers each with independent suction and return lines to containment. The condition as reported is based on the fact that containment isolation valves located inside containment on the two independent return lines receive electrical power from the same safety bus.
In the event of an accident where these valves receh ed a containment isolation signal and a single failure of the electrical power subsequently occurred, these isolation valves could not be reopened remotely. In that case the sampling of hydrogen in containment would not be possible using the analyzer lines.
Discussions were held between AP&L, Region IV and NRR technical staff on 08/24/89. in which the licensee described short and long term corrective actions. Currently, AP&L is preparing a temporary procedure to insure that alternativepowerisprovidedtothevalvesinquestionwithin(approximately) 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. During the next refueling outage scheduled to begin late in September, the licensee will make necessary design changes to correct the single failure vulnerability. The staff found the planned actier,s to be acceptable.
Rancho Seco In an August 21, 1989 letter to SMUD General Manager, David Boggs, Golden State Energy (GSE) outlined several proposals to complete negotiations for the sale of Rancho Seco. The letter included four issues:
- 1. GSE would pay SMUD $99,000 to delay the sthrt of defueling activities
'or 2 weeks (until September 8,1989) to allow negotiations to be completed.
- 2. GSE would enter in to a fixed-price contract to conduct all plant closure activities.
- 4. A MOU concerning the sale of power from Rancho Seco to SMUD.
The SMUD Board met on 8-25-89 to vote on the first 2 issues. The Board voted in favor of delaying defueling activities until September 8, 1989 and accepted the $99,000 from GSE. However, the Board voted against GSE conducting any closure activities.
SMUD will meet with the NRC staff August 29,1988 at 9:00 a.m. in 128-11 to discuss plant status and closure activities.
As a result of the Board meeting on 8-25-89, GSE has cancelled the Leptember 6, 1989 meeting with the NRC.
SEPTEMBER 1, 1989 ENCLOSURE A
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1 Arkansas Nuclear One, Units 1 and 2 i
On August 25, 1989, at 6 p.m. (CDT) with ANO Unit I at 74 percent power, the licensee reported that a single failure vulnerability for the service water I
system could be created while using the "B" swing service water pump. The operational condition of concern is with the "B" swing service water pump operating along with either the "A" or "C" service water pump. In this condition, if a design basis event occurs concurrent with a loss of offsite power and a single failure of one emergency power source, the "B" swing service water pump could be in alignment feeding both service water loops and I the auxiliary cooling water loop. The "B" swing pump would not supply adequate flow to safety loads with this alignment. The licensee is implementing procedure controls for "B" swing pump, service water cross connect valves and auxiliary cooling water valve operation so that this condition would be prevented.
Regional action: The resident inspectors are monitoring licensee actions and will review the adequacy of procedure controls prior to licensee operation of the "B" swing service water pump.
Limerick, Unit 2 On August 25, 1989, the Commission as set forth in a Memorandum and Order, CLI-89-17, determined that the current licensing record provided the necessary basis for authorizing the issuance of a license to the Philadelphia Electric Company to operate the Limerick Generating Station, Unit 2 at full power. The Memorandum and Order authorized the NRC staff to issue a full power license to PECo to operate Limerick, Unit 2 once it has made the requisite safety findings under 10 CFR 50.57. The full power operating license was issued in the afternoon of August 25.
Limerick, Unit 2 exceeded 6% power the morning of August 26 and was performing stability checks on the feedwater control system. The licensee expects to begin rolling the turbines the morning of August 28th.
Fort St. Vrain Public Service Company of Colorado will discontinue power generation at the Fort St. Vrain Nuclear Generating Station as of 8-29-89. The licensee will stop efforts to restart the plant. The plant will be considered in the 100 day cooldown needed prior to defueling.
The plant was shutdown on August 18 with failed control rod drive mechanism.
Subsequently, the licensee discovered extensive cracking in the Incoloy 800 ring headers on 8 or 12 steam generator modules.
SEPTEMBER 1, 1989 ENCLOSURE A
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,7 Office of Nuclear Material Safety and Safeguards Items of Interest Week Endii? September 1, 1989 SAFEGUARDS Transportation Approval of TRUPACT-II Shipping Container On August 30, 1989, the Transportation Branch issued Certificate of Compliance No. 9218 for the TRUPACT-II shipping container. The container was designed by Nuclear Packaging, Inc. for the Department of Energy (DOE). DOE plans to use TRUPACT-II to ship contact-handled transuranic wastes from DOE defense facili-ties to the Waste Isolation Pilot Plant (WIPP). The container provides double containment and is not vented. TRUPACT-II weighs approximately 19,250 pounds when loaded with the maximum contents of 7,265 pounds.
INDUSTRIAL AND MEDICAL NUCLEAR SAFETY Fuel Cycle Safety Combustion Engineering - Hematite. Missouri On August 24, 1989, representatives of NRC Headquarters, Region III and Combustion Engineering Hematite Plant conducted a public meeting at Jefferson Junior College in Hillsboro, Missouri. The purpose of the meeting, requested by Missouri State Senator Jeremiah Nixon, was to provide the public with information regarding the planned expansion of uranium pelletizing operations at the Combustion Engineering Nuclear Fuel Manufacturing Facility.
Charles E. Norelius, Director of the Division of Radiation Safety and Safeguards, Region III, was the moderator for the meeting. After presentations by James Rode, the Plant Manager, and George Bidinger of the Headquarters staff, Senator Nixon and two private citizens of Jefferson County, who also have requested a hearing on the plant expansion, were given the opportunity to make statements and ask questions prior to opening the meeting to the remainder of the attendees.
Seven additional private citizens raised issues during the public comment period. ,
One of the seven presented a petition with about 80 signatures of local people in support of the plant expansion. Approximately 200 people attended the meeting.
HIGH-LEVEL WASTE MANAGEMENT Technical Exchange on Substantially Complete Containment On August 29, 1989, representatives of the Nuclear Regulatory Commission (NRC).
Department of Energy (DOE) and the State of Nevada engaged in a technical exchange of information in the area of "substantially complete containment (SCC)."
This technical exchange with DOE was the first of a series of interactions that are planned to be held between August 1989 through December 1989.
SEPTEMBER 1, 1989 ENCLOSURE B
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L Both regulatory and technical concepts and ideas regarding SCC were discussed.
L The major discussion centered on concerns and uncertainties regarding approaches l:.
to establishing qualitative and quantitative criteria to meet the SCC requirement of 10 CFR Part 60. Other discussions covered the staff's point papers on SCC, l
I the DOE position on the point papers, and ongoing DOE activities in the area of l SCC.
1 NRC Staff Observation Audit of.U.S. Geological Survey The Division of High-Level Waste Management (DHLWM) performed an observation audit of the Department of Energy (DOE) Yucca Mountain Project (YMP) Office audit of the U.S. Geological Survey (USGS) in Denver, Colorado and Las Vegas, Nevada on August 14 through 23, 1989. The USGS is one of DOE's contractors '
that conducts geologic, geophysical, hydrologic, and seismologic investigations for the YMP.
The NRC team consisted of quality assurance (QA) and technical (geologists and hydrologists) staff who evaluated both the USGS QA program and the effectiveness of the DOE audit. While implementation of the USGS program is extremely limited, there appeared to be considerable improvement for the last staff observation l audit slightly over one year ago. Because of the limited USGS program i implementation to date, DOE and NRC will have to closely monitor the USGS to ensure that implementation continues in an acceptable manner.
SEPTEMBER 1, 1989 ENCLOSURE B
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Office of Nuclear Regulatory Research Items of Interest Week Ending September 1,1989 Intef rity of- Reactor Components Meeting with USSR Acadeny of Science Delegation The RES Division of Engineering, Materials Engineering Branch, hosted an informal meeting with four Soviet Scientists who are touring the USA to make contacts under the Aegis of the Agreement for Cooperation signed between the US ASME Code and the IJSSR Acadeny of Science. The Soviet personnel were:
Professors Eugene 0. Adamov, Director, and Sergei E. Bougaenko, Department Head, of the Institute of Nuclear Power Engh.eering, and Professm ;likolay A.
Makhutov, Department Head and Oleg A. Levin, Leading Scientist of the USSR Academy of Science.
They are particularly interested in studying factors affecting life extension of plants, and are currently focusing on vastly improved measurements of stress in primary reactor systems. They are making very extensive measurements of stresses and temperatures in a VVER-1000 plant, and will share that informa-tion with us in a cooperative venture to produce better, validated analytical codes for stress predictions in plants. They will propose such cooperation to be included in the JCCCNRS Protocol for the 1990 meetings; for our part, we are quite interested to cooperate in this area, although we would hope to include work already underway by EPRI in this endeavor.
Resolving Safety Issues and Developing Regulations Individual Plant Examination (IPE)
NUREG-1335, " Individual Plant Examination: Submittal Guidance," has been published and is now available in the Public Document Room. A Federal Register Notice announcing the availability of NUREG-1335 and initiation of the IPE process is expected to be published during the first week of September.
The NUREG document delineates the guidance for reporting the results of the Individual Plant Examination (IPE) to the NRC. All licensees of nuclear power plants will be sent a copy of NUREG-1335 as an attachment to a generic letter supplement (GenoricLetter88-20 Supplement 1). Licensees are required to submit within 60 days, their proposed programs for completing their IPEs; the results of the examination itself are to be reported within 3 years, s
i SEPTEMBER 1, 1989 ENCLOSURE C
Office for Analysis and Evaluation of Operational Data Items of Interest Week Ending September 1, 1989 Division of Operational Assessment On September 1, the 17-man Diagnostic Evaluation Team completed the first two weeks of its onsite evaluation of overall plant safety performance at Arkansas Nucleer One. The team is scheduled to return to Arkansas the week of September 11 to complete the evaluation.
On August 29, the AEOD Director, NRR Division of Radiation Protection and Emergency Preparedness Director and IRB Chief met with the Environmental Protection Agency's (EPA) Office of Radiation Programs management and staff representatives to discuss revisions to EPA's Protective Action Guides.
On August 31, IRB staff attended a meeting of the Federal Respnse Subcommittee of the FRPCC to discuss the planned revision of the FRERP.
Preliminary Notifications The following Preliminary Notifications were issued during the past week.
- a. PNS-I-89-12,PeachBottomAtomicPowerStation(Units 1and2), Bomb Threat.
- b. PNS-I-89-14 Philadelphia Electric Company (Peach Bottom Unit 3), Apparent Vandalism at Shutdown Unit.
- c. PNO-I-89-72A, Niagara Mohawk Power Corporation (Nine Mile Point Unit 2),
Augunted Inspection Team Exit at Nine Mile Point Unit 1 and Subsequent Press Conference.
- d. PNO-I-89-73, Yankee Atomic Electric Company (Docket No. 50-29), Reactor Coolant Pressure Boundary Leakage.
- e. PN0-II-89-59A, Carolina Power & Light Company (H. B. Robinson), AIT Dispatched to H. B. Robinson.
- f. PNO-II-89-60A,SouthCarolinaElectric&GasCompany(V.C. Summer),
V. C. Sununer Reactor Trip - Shutdown Greater Than 48 Hours.
- g. PNO-II-89-61, Florida Power Corporation (Crystal River Unit 3), Loss of Decay Heat Pump (RWP-28) and Subsequent Reactor Trip.
- h. PNO-III-89-56, University of Cincinnati (License No. 34-06903-05),
Contaminated Laboratory.
- 1. PNO-III-89-57, Commonwealth Edison Company (LaSalle Unit 2), Reactor Scram.
SEPTEMBER 1, 1989 ENCLOSURE D
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- k. Pl?0-IV-89-52C, Public Service Company of Colorado (fort St. Vrain), Update of Unplanned Reactor Shutdown Due To Inoperable Control Rod.
- 1. PNO-IV-89-54,MobileLabs,Inc.(LouisianaAgreementStateLicensee),
Possible Radiographer Overexposure,
- m. PN0-IV-89-55, Public Service Company of Colorado (Fort St. Vrain),
Termination of Nuclear Operations,
- n. PNO-V-89-51 Pacific Gas & Electric Company (Diablo Canyon Unit 2),
Shutdown Greater Than 48 Hours Due to Reactor Trip Caused By A Failed Reactor Coolant Pump Motor Lead.
SEPTEMBER 1, 1989 ENCLOSURE D
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l Office of Governmental and Public Affairs Items of Interest Week Ending September 1, 1989 INTERNATIONAL PROGRAMS:
International Visitors On~ Friday Dr. Dan Litai, Director of the Licensing Division of the
' Israeli Atomic Energy Commission, paid a courtesy visit to GPA/IP. Dr.
Litai gave a brief outline of the status of Israel's research in the
' nuclear safety area and an update on the preliminary siting studies for
.the planned nuclear reactor.
Exports / Imports Export license applications were received from:
- 1) Gamma-Metrics - HEU 4 channels plus spares for use in neutron flux monitoring system in Spain.
- 2) Marubeni America Corporation - LEU for initial core load for the Shika Nuclear Power Station Unit 1 in Japan.
- 3) Westinghouse Electric Corporation - LEU in 1 test and-I dummy fuel assembly for hyrdaulic tests in Canada and return to the U.S.
Licenses for export were issued to:
- 1) Braunkohle Transport, Inc. - LEU reload fuel for Almaraz 2 in Spain.
- 2) Mitsubishi Inc. - LEU reload fuel for Genkai Unit 2 in Japan.
Australian-origin material contained.
- 3) General Electric Company - one Iontrac 200-series on-line
~ Chromatograph for experimental BWR loop testing for the Halden Reactor.
l STATE, LOCAL AND INDIAN TRIBE PROGRAMS Medical Use of Radionuclides Course An SLITP-sponsored course on the medical use of radionuclides was conducted on August 28-September 1,1989 in Oak Ridge, Tennessee.
Nineteen State inspectors participated in the training. The courst included an introduction to nuclear medicine, instrumentation and radiopharmaceuticals. The course-also included tours and laboratory exercises at the Oak Ridge Associated Universities' Medical and Health Sciences Division and the Radiological Emergency and Accident Training Center, Syncor, Inc. and the Nuclear Medicine and Radiotherapy Departments at the University of Tennessee Hospital.
SEPTEMBER 1, 1989 ENCLOSURE E
Safety Aspects of Industrial Radiography Course SLITP. conducted a course on the safety aspects of industrial radiography on August 28-September 1,1989 in Burlington, Massachusetts. Nineteen f . State inspectors participated in the training course. The course covered various aspects of industrial radiography safety and included a tour of a radiography camera manufacturer, a visit to an operational radiography.
site and an inspection of a radiography company.
Rocky Mountain Low-Level Radioactive Waste. Board Meeting The Region V State Liaison Officer attended the Rocky Mountain Low-Level Radioactive Waste Board meeting held on August 28, 1989 in Crystal Bay, Nevada.. The Board unanimously approved contracts with Maine, New Hampshire, Vermont, Rhode Island and the District of Columbia to accept LLW at the Beatty, Nevada LLW site from April 1,1990 to December 31, 1992. . While approving the contracts, the representative from Nevada indicated that the contracts did not satisfy the 1990 Governor's certification milestone requirements, but merely provided a place for the affected States to dispose of their wastes for the specified period, Savannah River Emergency Planning Exercise The Region II State Liaison Officer participated as a member of the Regional Assistance Comittee (RAC), which was invited by the State of South Carolina to informally evaluate the State's performance in the Department of Energy Savannah River Plant emergency planning exercise held on August 29,'1989. The State of Georgia also participated, but was not evaluated by the RAC, A critique was conducted on August 30, 1989 involving representatives from the Savannah River site and applicable State and' local officials. Generally the exercise went well, however DOE, South Carolina and Georgia agreed that there is a need for additional planning, which will be pursued.
Waterford-3 Emergency Planning Exacise The Region IV State Liaison Officer participated in an emergency planning exercise conducted at the Waterford-3 Generating Station on August 30, 1989 in Taft, Louisiana. Mr. Hackney was a member of the Regional AssistanceCommittee(RAC)whichevaluatedtheexercise. The exercise included State and local government participation.
Midwest LLW Compact Commission Meeting The Region III State Liaison Officer attended the Midwest LLW Compact Couaission meeting on August 31, 1989 in Ann Arbor, Michigan. The Compact Comission discussed the 1990 milestone Governors' certifications and received a briefing on the status of the site screening process in Michigan as well as a briefing on Michigan's FY'90 budget for the LLW program. i SEPTEMBER 1,l1989 ENCLOSURE E
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i" Office of Administration Items of Interest Week Ending September 1,1989 Safety Caution Signs Safety caution signs have been placed at the garage entrance and pedestrian crossing area at White Flint because of increasing concerns related to vehicle speed and pedestrian safety.
New Warehouse Negotiations Negotiations with GSA are proceeding regarding replacement warehouse space.
NRC will hire an independent safety consultant to examine the space before occupancy. Interim arrangements for storage and necessary supplies are proving satisfactory with little impact on ability to maintain deliveries.
Significant FOIA Requests Received by the-NRC for 5-Day Period August 25 - 31, 1989 Request for a copy of Agency Procurement Requast for KMA-89-0313. (Schalene Dagutis, Sequent Computer Systems Inc., F01A-39-371)
Request for three categories of records related to a spill of radioactive waste at the Nine Mile Point nuclear power plint between 1978 and 1981 and any other spills. (Jonathan Salant, Newhouse .lews Service, F01A-89-374)
Request for records after 1979 not in the PDR which refer or relate to the following entities and their connection with the thorium milling facility in West Chicago, Illinois: Kerr-McGee, American Potash and Chemical Corporation, and Lindsay Light. (Bruce deGrazia of Burditt, Bowles & Radzius, Chartered,F01A-89-376)
Request for copies of invoices from January 1989 through April 1989 for any service related to carpet / tile installation, repairs or any other carpet related services. (Carolyn Stuckey, Family Carpet Service, Inc., F01A-89-379)
Request for copies of (1) contract NRC-17-89-120 and (2) abstract of offers for IFB RS-SEC-89-120. (Veronca Romanow, Logistics Applications Inc.,
Request for five categories of records pertaining to the history of RFP IRM-89-178. (Larry Daniels, Fedreal Systems Group Inc., FOIA-89-381)
Request for copies of all records of a meeting held about December 15, 1986 between NRC and the utility regarding the Beaver Valley nuclear power plant.
(StevenSholly,MHBTechnicalAssociates,F01A-89-382) l l
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SEPTEMBER 1, 1989 ENCLOSURE G L_________
c Office of Information Resources Management Items of Interest-Week Ending September 1,1989'
- 1. Scientific Code Conversion EG&G Idoho has obtsined a copy of SmarTem 400 to access the DG MV/8000.
This was neces;ary to convert the SAKI Code graphics to DISSPLA. Work has begun. The T0XCHN code user guide draft documentation has been reviewed and chant,es:have been suggested to EG8G Idaho.
- 2. IRRAS ard SARA Training Training in the use of the probabilistic risk assessment codes IRRAS and SARA was held Au Thirty-six (36) gust 21 through 25 at the ITS Training Laboratory. persons att IRRAS sessions. Commissioner Rogers attended the Friday session on the =
SARA code. The student evaluations indicated that the training was successful and the instructors (EG&G personnel) effective.
- 3. Electronic File Transfer Updates were made to the IBM 9370 to permit high speed electronic file transfer to take place between NRC and other agencies: Department of Enugy, Federal Energy Regulatory Commission, National Institutes of Health, Oak Ridge National Laboratory, Idaho National Engineering Laboratory, Southwest Research' Institute and the Executive Office of the President.
- 4. TY 1990 Information Collection Budget TheOfficeofManagementandBudget(OMB)issueditsInformation Collection Budget (ICB) call on August 22, 1989. The Information and Records Management Branch (IRMB) received an advance copy on August 28 and is preparing a memorandum to all Office Directors anc Regional Admini-strators requesting their input to the ICB. The required information should be readily available from each office because IRMB informed the Information Management Coordinators (IMC) of the need for most of the data by memorandum dated April 6, 1989. The response to OMB is due October 31, 1989.
- 5. Files Maintenance and Records Disposition Workshops The fifth and final " Files Maintenance and Records Disposition Workshop" was presented August 23 and 24, 1989, by the Washington National Records Center staff at NRC. A total of 74 individuals attended the five sessions, including 12 Records Liaison Officers. Course evaluations were favorable and included comments recommending the course be required of all clerical, secretarial and administrative employees.
SEPTEMBER 1,_1989 ENCLOSURE H
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.6. Nuclear Documents System (NUDOCS)
NUDOCS/AD (Advanced Design) is currently scheduled for. implementation on September 25, 1989. Agency-wide briefings on the system upgrades, including distribution of users, pocket and reference guiies, are scheduled to begin on September 11, 1989.
- 7. Probabilistic Risk Assessment Status Information System Initial load of the PRA data in SINET for the 5 most recently coh'r>1eted-PRA studies was completed this week. QA and corrections are in progress with an anticipated end-of-week completion.
B. Replacement of PBX for E0C In reference to ARM-89-161, Replacement of. PBX for EOC, the closing date for responses from prospective vendors was August 30, 1989 at 3:00 p.m.
Only one vendor responded by the closing date.
J SEPTEMBER 1, 1989 ENCLOSURE H
a Office of the Controller Items of Interest Week Ending September 1,1989 FY 1991 Budget Request to OMB On Friday, September 1,1989, the NRC's FY 1991 budget request (Blue Book) was submitted to the Office of Management and Budget. Copies of the Blue Book were distributed to Branch Chiefs and above.
SEPTEMBER 1, 1989 ENCLOSURE I
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Y Office of Persor,nel Items of Interest Week Ending September 1,1989 Arrivals The following employee (s) reported this week:
MarjorieBriske,ResidentClericalAide(OPFT),RII Monica Canty, Secretary (PFT), NRR Michael Case, Operations Engineer (PFT), NRR Departures KevinWolley,ReactorOperationsEngineer(PFT),AE0D SEPTEMBER 1, 1989 ENCLOSURE J
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Office of Enforcement Items of Interest Week Ending September 1,1989 i
Significant Enforcement Atticns A Notice of Violation and Prcposed Imposition of Civil Penalty in the amount of
$24,000 was issued on August 25, 1989 to General Electric Company, Cleveland, ,
Ohio. The action was based on violations involving the failure to: perform !
surveys for fixed and removable alpha contamination, decontaminate areas in i excess of alpha contamination limits, perform breathing-zone air sampling, perform adequate surveys for airborne radioactivity, use adequate process ,
or engineering controls to limit airborne radioactivity to Appendix B limits, (
and to post a " Caution Airborne Radioactivity Area" sign. (EN89-78)
An Order Imposing A Civil Monetary Penalty in the amount of $2,500 was issued to Rappahannock General Hospital, Kilmarnock, Virginia ore August 30, 1989.
The action was based on a violation in which the NRC-required record cf a quarterly Radiation Safety Committee meeting was fabricated by copying the minutes of a previous meeting and altering the date. (EN 89-52A)
An Order Imposing A Civil Monetary Penalty in the amount of $75,000 was issued to Duke Power Company (Catawba) on August 31, 1989. The action was based on violations involving an inoperable Unit 2 Containment Air Return Hydrogen Skimmer Train caused by a design modification wiring error and the licensee's failure to report a condition prohibited by technical specifications.
(EN89-53A)
A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $25,000 was issued on August 31, 1989 to South Carolina Gas & Electric Company (Summer Nuclear Station). The action was based on inadequate management controls that allowed a licensed senior reactor operator, who failed a portion of his annual requalification exam, to assume the duties of the operator-at-the-controls prior to retraining and retesting. The civil penalty was mitigated 50% because the event was promptly identified and reported by the licensee. (EN 89-80)
A Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $25,000 was issued on August 31, 1989 to Northeast Nuclear Energy Company (Millstone Nuclear Generating Station). The action was based on a failure to establish adequate procedures to prevent contamination to hydrolaze equipment via the hoses that ran into the reactor building during the hydrolaze operation and other violations associated with transportation offsite after completion of the operation. The base civil penalty was mitigated 50% due to the licensee's prompt and comprehensive corrective action.
(EN89-81)
Civil Penalty Paid Professional Service Industries, Lombard, Illinois paid the civil penalty in the amount of $20,000. The action was based on the failure to secure or main-tain continuous surveillance over an unsecured moisture-density gauge in the SEPTEMBER 1, 1989 ENCLOSURE L
back of an open bed pickup truck parked in an unrestricted area which was the third failure totime, in ancontrol properly intervallicensed of approximately material. 15(EA88-313 months,)that the licensee Grand Haven Board of Light and Power, Grand Haven, Michigan paid the civil penalty in the amount of $500. The action was based on the failure to: have l authorized and qualified individuals perform removal of gauges from their installed locations, perform source leak tests and device in-off mechanism tests at required intervals, maintain gauge levels legible, maintain records of receipt of byproduct materials, maintain records of device removals, and furnish a transfer report for generally licensed gauges to the Comission.
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Region 1 Items of Interest i i
Week Ending September 1,1989
- 1. SUSQUEHANNA UNITS 1/2 During the week of August 21, 1989, a team inspection was conducted on selected training programs, which included Health Physics, Maintenance I and Operations training. The purpose of this inspection was to evaluate training's implementation and effectiveness by performing an in depth review of the program, utilizing Inspection Procedure 41500 which references NUREG 1220 " Training Review Criteria and Procedures." The team j reviewed documentation and observed training performance in the form of I simulator, laboratory, on-the-job and in the classroom.
Overall the program was determined to be very strong with excellent communications between the training department and the plant. Fundamental to this strong program is upper level to line management support of training. One area of concern is the Licensed Operator Requalification Program, which does not require that individuals be removed from licensed duties after failing an annual requalification examination. This concern is under review with OLB, HFAB and members of the Region I staff.
- 2. AUCMENTED INSPECTION TEAM EXIT AT NINE MILE POINT UNIT 1 AND SUBSEQUENT FRESS CONFERENCE AnAugmentedInspectionTeam(AIT)investigatedtheuseofasub-basement for storage of solid and liquid racwaste by Nine Mile Point Unit 1.
Preliminary results are that in July, 1981, the licensee released about 50,000 gallons of slightly contaminated water to Lake Ontario and 75,000 to 100,000 gallons to a sub-basement in whicn about 150 55-gallon drums of radioactive sludge and spent resins were stored.
The licensee appears to have dealt properly with the release to the lake, but to have taken only limited actions to decontaminate the sub-basement.
The licensee subsequently permitted the waste liquid and sludge to remain in the sub-basement without a safety evaluation of the decision, which the team found to result in two apparent violations. Prior to the inspection, the licensee had initiated efforts to decontaminate the sub-basement and anticipates completion of cleanup activities by March 1990.
SEPTEMBER 1, 1989 ENCLOSURE N
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Region II Items of Interest Week Ending September 1,1989 l 1. Carolina Power & Light Company On August Company (CP&L28,)the Senior Vice President of Carolina Power and Lightwas in th Analysis Study. As a result of this study, 101 personnel were outplaced from the three nuclear sites.
l 2. FEMA /RAC
! On August 28-30, R. Trojanowski participated in the FEMA /RAC Evaluation I of the Savannah River Plant / State of South Carolina emergency exercise in Aiken, South Carolina. 4 i
- 3. Duke Power Company On August 29, representatives of the Duke Power Company were in the Region II Office to attend an Enforcement Conference regarding numerous security violations affccting all Duke sites. In addition, a Management Meeting to discuss the scheduling of medical exams for licensed operators was also conducted.
On August 31, a DRP Branch Chief and the McGuire Senior Resident Inspec-tor, were in Headquarters to attend a meeting with Duke Power Company and NRR to discuss the findings and conclusions from the steam generator tube and plug inspections during the refueling outage at McGuire Unit 2.
- 4. Florida Power Corporation On August 31, the Director, Division of Reactor Safety (DRS), and a DRS Section Chief, attended a meeting in Headquarters with NRR and the Florida Power Corporation regarding the recent Crystal River loss of off-site power events.
- 5. Differing Professional Opinion The Region received a Differing Professional Opinion (DP0) this week. The DP0 is being processed by the Region in accordance with established Agency procedures.
- 6. US/ USSR Inspector Exchange On August 31, 1989, a press conference was held at Catawba concerning the completed visit of three Soviet inspectors participating in the US/ USSR inspector exchange program. The inspectors will be returning to Washington, D.C. after visiting the Chattanooga Technical Training Center, Watts Bar, and the Region II Office.
SEPTEMBER 1, 1989 ENCLOSURE N l
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- 7. Alabama Power Company AlabamaPowercontinuesdiscussionwiththeUnion(IBEW)onanewlabor ,
contract which at'fects unionized workers at Farley. There is some indi-cation that a strike may occur early next week if an agreement has not '
been reached. The licensee's strike plans have been reviewed, and the Region is prepared to provide 24-hour coverage in the event of a strike.
- 8. H. B. Robinson Augmented Inspection Team (AIT)
On September 1, 1989, the exit interview for the H. B. Robinson AIT was conducted. The AIT was dispatched on August 28, 1989, to review auxiliary feedwater net positive suction head deficiencies.
- 9. Surry Power Station On September 1, 1989, a Management Meeting was held with YEPC0 concerning the restart of Surry Unit 2. The licensee discussed the unit's readiness for restart to include the impact of several recently identified correc-tive action deficiencies from previous NRC violations.
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Region III Items of Interest Week Ending September 1,1989 9
- 1. Perry Nuclear' Power Plant On Tuesday, August 29, 1989, the Region III Deputy Regional Admir.istrator, the Director of the Division of Reactor Safety, NRR's Director of Project Directorate III-1 and members of their respective staffs presented the Perry SALP 9 report to the the Cleveland Electric Illuminating (CEI)
Company, the CEO of Centerior Corporation and a representative from Ohio Edison. A large number of Perry Plant personnel, representatives of the State of Ohio, and one reporter also attended the presentation. The SALP was received well by the licensee and the CEI Vice President Nuclear discussed licensee actions in response to weaknesses pointed out by the SALP. Following the SALP meeting, the Deputy Regional Administrator and Director of DRS participated in a plant tour led by the licensee.
Observations on-the tour indicated good control of instruments out of service and lit annunciators, but poor housekeeping and material condition.
On the following' day August 30, 1989, Region III participated in the annual emergency response drill with the Perry site. No immediate safety issues were identified and thorough critiques are being conducted.
- 2. LaSalle Nuclear Power Station Unit 2
'On' August 26, 1989, Unit 2 experienced a reactor scram, at approximately 10% power, while shutting down in preparation for a planned six-day outage. Durirg the. scram it was noted that two of the eight scram pilot solenoids remained energized although back up scram solenoids functioned to insert rods. The cause is under investigation and appears to involve scram signals from an unknown source combined with a scram contactor not opening immediately. The Senior Resident Inspector was in the control room at the time of the event. RIII dispatched a regional specialist to assist in the evaluation of the event and the licensee has comitted to providing an analysis of the event prior to restart.
- 3. Duane Arnold On August 26, 1989, while performing a weekly power / load unbalance surveillance test, the plant experienced a' turbine trip and reactor scram.
During the event an auxiliary transformer feeder breaker failed and caused the loss of offsite power to a nonessential bus and one of two essential .
service buses. The emergency diesel generator started and supplied power to the essential bus until a transfer was made to the standby transformer.
All safety systems operated as required. The senior resident was on site and observed the licensee's investigation and corrective actions. The failed auxiliary transformer breaker was replaced and a defective current transformer associated with the power / load unbalance circuit will be replaced during an upcoming maintenance outage. The unit commenced operhtion on August 28, 1989, and is operating at approximately 70% power.
SEPTEMBER 1,.1989 ENCLOSURE N
- 4. Quad Cities Units 1 & 2 On August 30, 1989, the Director, Division of Reactor Frojects, and the Chief, Division of Reactor Projects Branch I, were at the Quad Cities Nuclear Power Plant for a routine meeting with the Vice President for BWR Operations and other licensee management to review and discuss recent plant operations, and to tour the facility.
- 5. Zion On August 26, 1989, the licensee declared sixteen of the twenty Main Steam Safety Valves (MSSV) on Unit 1 inoperable because the instrument used to test the MSSV setpoints may have been adversely affected by the high ambient temperature in the area where the equipment was used. An Unusual Event was declared at 10:56 p.m. and the unit was placed in hot shutdown (HSD)asrequiredbyTechnicalSpecification(TS)3.7.1.F.
That specification further requires that the reactor be placed in cold shutdown if the MSSVs could not be made operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Near the end of that time period, the licensee requested a short extension through enforcement discretion to complete the testing of the last four MSSVs. The Regional Administrator granted that extension to prevent the unnecessary transient on the plant. Less than two hours into the extension, the licensee completed the remaining testing and returned all MSSVs to operable status.
- 6. Davis Besse Nuclear Power Station Fermt 2 Kewaunee Nuclear Power Plant Point Beach Nuclear Plant Commissioner Curtiss and other NRC staff members visited Davis Besse and Fermi on August 29, 1989, and Kewaunee and Point Beach on August 30, 1989. The visits included meetings with resident inspectors, attending plan-of-day meatings, licensee presentations, and plant tours.
- 7. University of Cincinnati On August 24, 1989, the licensee reported that a research laboratory was determined to have significant levels of removable contamination. The licensee closed the laboratory pending decontamination. Low levn1s of technetium-99 contamination were found on the shoes and clothing of a laboratory worker but did not spmad outside the laboratory.
On August 25, 1989, two Region III radiation specialists were dispatched to the University of Cincinnati to review the contamination survey findings, the licensee's handling of the laboratory contamination event and the adequacy of the radiation safety program.
I On August 30, 1989, Region III issued a Confirmatory Action Letter to the University requiring the licensee to review adequacy of surveys, training, j and equipment for all research laboratories. Region III is following the licensee's corrective action.
SEPTEMBER 1, 1989 ENCLOSURE N
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- 8. . Perry-On August 31,1939. the Director of. Radiation Safety and Safeguards met with the licensee to discuss the licensee's recent changes in their
- security plan. The licensee is making the changes due to findings of a self-initiated safeguards Regulatory Effectiveness Review. Region III staff concluded that the review was thorough and the licensee's corrective.
actions appeared appropriate.
- 9. Combustion Engineering (CE)
On August 29, 1989, the licensee notified Region III that uranium had inadvertently been released from a UF6 to 002 conversion process line at CE's Hematite, Missouri' facility. An Augmented Inspection Team consisting
.of staff from. Region III and NMSS arrived onsite on August 30, 1989, to review the cause of the event and the licensee's actions. There were no significant personnel uptakes of radioactive material. Offsite surveys and environmental sampling are being performed by the NRC and licensee.
SEPTEMBER 1, 1989 ENCLOSURE N
Region IV Items of Interest Week Ending September 1,1989
- 1. Fort Calhoun Station An enforcement conference was held on August 28, 1989, in the Region IV office with representatives from Omaha Public Power District to discuss the apparent violations identified in a physical security inspection conducted July 24-27, 1989, at Fort Calhoun Station.
- 2. Fort St. Vrain Public Service Company of Colorado announced to employees and the general public yesterday afternoon its decision to halt operations immediately at Fort St. Vrain. The company lead notified Region IV earlier of the action.
Extensive madia coverage resulted in the Denver area. Region IV also has responded to media inquiries.
The company attributed its decision to the financial impact of an anticipated lengthy outage to deal with metallurgical problems, including one through-wall crack, in a ring header of the plant steam generator system. These problems were found while work was under way to remove a faulty control rod assembly.
Public Service announced in December that it would halt Fort St. Vrhin operations no later than June 30, 1990, when defueling and decommissioning would begin. It now is beginning a 100-day cooldown in 1 reparation for defueling, which is expected to take about 30 months. T1e NRC staff has the defueling safety analysis under review.
In its announcement, the company said that, while some employee layoffs are expected during the coming year, there will be no work force reduction for at least a mranth. More than 500 persons are now associated with Fort St. Vrain operations.
- 3. Sequoyah Fuels Corporation On August 28, 1989, Mr. Reau Graves, President, Sequoyah Fuels Corporation, met with the Director, Uranium Recovery Field Office. Topics discussed included the results of the 1989 summer maintenance shutdown, progress in waste reduction, and the status of various management initiatives. He also reported that the recent open house had been attended by 240 employees and their families, and 38 local residents. TPe open house was felt to have been a great aid in public acceptance of the plant, a problem since the accident.
SEPTEMBER 1, 1989 ENCLOSURE N
Region V Items of Interest Week Ending September 1,1989
- 1. Palo Verde Nuclear Generatino Station On September 1,1989, the Regional Administrator, members of the Region V and NRR staffs met with ANPP management to discuss recent events at Palo Verde Unit 2-and to continue to monitor readiness for restart of Unit 3. Local news media representatives also attended the management -
meeting. A closed maintenance team inspection exit meeting was held immediately prior.to the management meeting.
SEPTEMBER 1, 1989 ENCLOSURE N
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t ITEMS ADDRESSED BY THE COMMISSION - Week Ending September 1, 1989-STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND VOTE, 3:30 P.M., FRIDAY, j A.
AUGUST 25,-1989, COMMISSIONERS' CONFERENCE ROOM, ONE WHITE FLINT NORTH, 1 ROCKVILLE, MARYLAND (OPEN TO PUBLIL AlltNDANCE) - SECY to W. C. Parler, !
.GC dated 8/31/89-I. SECY-89-257 - T==ediate Effectiveness Review for Full Power l
Licensina of TAimarick, Unit 2 The Commission, by a 4-0 vote, approved an order.which provided the Commission's decision on its immediate effectiveness review of Limerick, Unit 2.
The order indicated that the Commission determined that the record in the proceeding provided the necessary basis for I
authorizing the issuance of a license to the Philadelphia Electric Company ("PECo") to operate the Limerick Generating Station, Unit 2 (" Limerick") at full power. The Commission found that the balance of factors set forth n.10-CFR Sec.
2.764 (f) (2) (1) as well as consideration of environmental matters under the National Environmental Policy Act ("NEPA")
favored commencement of operation now rather than waiting for the outcome of the proceeding currently pending before the Atomic Safety and Licensing Board (" Licensing Board")
concerning severe accident mitigation design alternatives (SAMDAs"). The decision was without prejudice to the Licensing Board decision,1and the license is subject to amendment as result of the outcome of that proceeding. Since the Commission expects that there will be a Licensing Board decision on the merits of the SAMDA issue-before the first' refueling outage,.it did not need to consider the matter of whether full power operation beyond the first refueling outage should be subject to further conditions based on the outcome of the Licensing Board proceeding. 'The Commission also noted that any further requirements on the licensee that might be reasonably foreseen to arise out of the Board's consideration of SAMDAs would not be foreclosed by'the present authorization.
Finally, the Order noted that an August 24, 1989, stay request from LEA was denied.
I SEPTEMBER 1, 1989 ENCLOSURE P
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