ML20141G798
| ML20141G798 | |
| Person / Time | |
|---|---|
| Issue date: | 05/15/1997 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| SECY-97-105, SECY-97-105-R, WIR-970509, NUDOCS 9705220501 | |
| Download: ML20141G798 (24) | |
Text
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'tiav15.l'997 SECY 97 105
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fat:
The Commissioners.
frs;.
James L. Blaha, ' Assistant for Operations. Office of the E00 Sub.iect:
WEEKLY INFORMATION REPORT - WEEK ENDING MAY 9, 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*
Personnel 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 P
Executive Director for Operations 0*
Congressional Affairs R
[
- No input this. week.
g James L M gj James L. Blaha Assistant for Operations, OEDO-
Contact:
B.'McCabe. OED0
. Doc nt Name: C:\\ WEEK 509.
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- NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20556 INFORMATION REPORT May 15.1997 SECY 97-105 For:
The Commissioners From:
James L. Blaha. Assistant for Operations, Office of the EDO Subiect:
WEEKLY INFORMATION REPORT - WEEK ENDING MAY 9, 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*
Personnel 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 11 P
Region III P
Region IV P
Executive Director for Operations 0*
Congressional Affairs R
- No input this week.
m 7
ames L. Blata Assistant for Operations. OEDO
Contact:
B McCabe. OEDO EC FILE CSTER C
Office of Nuclear Reactor Regulation Items of Interest Week Ending May 9. 1997 Pacific Northwest National Laboratory's Insoection During the week of April 28 through May 2.1997. representatives from the Special Inspection Branch (PSIB) and the Quality Assurance and Maintenance Branch-(HQMB) performed an inspection of Pacific Northwest National Laboratory's (PNNL) facilities located in Richland. Washington.
The purpose of this initial inspection was to evaluate the adequacy of PNNL's management controls, engineering processes, and quality oversight programs relative to the production of Tritium Producing Burnable Absorber Rods (TPBARs) for use in Commercial Light Water Reactors. Although PNNL has implemented many of the programmatic controls associated with the production of TPBAR assemblies, issues related to commercial grade dedication processes, the safety classification of basic components, and the overall adequacy of the cuality assurance program remain open.
During the exit meeting both PNNL anc the host utility (TVA, Watts Bar) acknowledged the findings and confirmed the need for a timely resolution of open issues.
Subsequent to the site exit meeting. the staff contacted DOE and an informal briefing with their representatives is anticipated in the near future. A follow-up inspection at PNNL is planned for the late June 1997 timeframe.
0A Meetino with South Texas Bob Gramm and several members from HQMB and SPSB are meeting this week with HP&L representatives, at the South Texas Project (STP). to discuss the utility's approach to the implementation of a risk-informed graded quality assurance process.
Specific areas that will be discussed include STPs recent GA program change submittal, review of the staff's RAls, and evaluation of the U+ lity's proposed 3 tier quality program.
These discussions are intended to provide the staff with additional insights into the licensee's proposed 0A controls for safety-related SSCs that will meet Appendix B requirements in an alternative manner.
NUSMG Workshoo Lee Spessard Deputy Director of the Division of Reactor Controls and Human Factors (DRCH) and Jerry Mauck of the Instrumentation and Controls Branch attended the 16th Semi-Annual Nuclear Utilities Software Management Group (NUSMG) Workshop in Bloomington. IL on May 7-8, 1997.
Mr. Spessard gave a presentation on the NRR staff perspective on digital systems including a status on the update to Standard Review Plan (NUREG-0800) Chapter 7 to incorporate digital instrumentation and control (I&C) system review guidance and recent operating experience with digital I&C system modifications to operating plants.
Meetino with EPRI/NEI on Risk-Informed ISI. Aoril 29. 1997 Staff members from NRR and RES met with representatives of Electric Power Research Institute (EPRI). Nuclear Energy Institute (NEI), and the industry on
'MAY 9. 1997 ENCLOSURE A
l l.
April 29, 1997 at the NRC headquarters in Rockville, Maryland to discuss technical details of the EPRI sponsored Risk-Informed Inservice Inspection (RI-ISI) methodology.
The industry has submitted two methodologies to the staff for the implementation of RI-ISI of piping.
One methodology has been jointly developed by ASME Research and Westinghouse Owners Group (WOG) and the other methodology is being sponsored by EPRI.
Each of the two methodologies have their respective pilot plants.
In addition, ASME is working on three Code Cases for alternate examination requirements to ASME Section XI. Division 1 for piping welds.
Code Case N-577 is based on the WOG methodology, Code Case N-578 is based on the EPRI methodology, and the Code Case N-560 for ASME Class 1 piping only for which the EPRI methoddlogy is used.
There is currently an effort underway to revise' Code Case N-560 to include WOG 1
methodology also.
EPRI had made an initial presentation of its methodology on September 20.
1996. The purpose of this meeting was for EPRI to present more details of the methodology and address the concerns raised in the September 20. 1996 meeting.
EPRI representatives presented the technical details of its RI-ISI process includino a discussion of consequence and failure potential assessment due to ai3e failures, which are then combined to categorize piping segments for ISI.
EPRI representatives provided technical bases of its approach, examples of RI-ISI application, and a detailed discussion of pipe failure potential via degradation mechanism assessment.
Industry representatives also provided an executive update of pilot studies for FitzPatrick and ANO-2 plants.
Industry representatives stated that utility submittals for the pilot will be provided to NRC by September 1997.
l NRC staf f ccmmented that the performance monitoring feedback needs to be included in the EPRI RI-ISI process.
NRC staff also indicated that the RI-ISI process must address risk as discussed in the PRA Implementation Regulatory Guide DG-1061.
The staff members provided additional comments on the details of the EPRI methodology which will be documented in the Request of Additional Information (RAI) to be transmitted to NEI/EPRI.
The meeting concluded with the agreement that additional public meetings will be held to discuss further details of EPRI methodology and its application to pilot plants.
Accident Manacement On May 21 - 22, 1997, the first of a series of industry-organized
" demonstrations" of utility implementation of the formal industry position on severe accident management will take place at Comanche Peak.
The demonstration will include presentations on the utility's implementation process, the conduct of two mini-drills in which plant-specific severe accident management guidelines will be exercised, and a debrief / critique.
NRC staff attendance is being coordinated with NEI.
MAY 9. 1997 ENCLOSURE A
e, Seabrook Unit 1 -- Financial Issues The U.S. District Court in Rhode Island issued its decision regarding the lawsuit Northeast Utilities and Public Service Company of New Ham] shire (PSNH) brought to Federal Court on a range of issues related to the New lampshire Public Utility Commission's (NHPUC) February 28 order on industry restructuring.
The Court concluded that it has jurisdiction over NU's and PSNH's challenge of the NHPUC order and rejected the state's arguments that the dispute belongs at the NHPUC for rehearing and, then, in the State courts.
The U.S. District Court will begin hearings on the merits of the case in June.
The judge agreed to give NHPUC until then to modify its decision on several of the issues before the Court and which now are part of an ongoing rehearing process at the agency.
Demonstration The demonstration organized by a group called The Forces of Nature and led by a number of veteran anti-nuclear activists at the Seabrook site on April 26.
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1997, resulted in the arrest of about 50 persons when they scaled the fence at
-the south gate of the site.
An estimated 200 participated in the demonstration.
Plant operations were not interrupted. the demonstration was peaceful, and no injuries were reported.
Those arrested potentially face a small fine and some hours of community service.
1 Oyster Creek /Three Mile Island On May 2.1997. GPU. Inc. officials stated that, in response to inquiries from parties who have expressed interest in the purchase of the Oyster Creek Juclear Generating Station. GPU would be willing to entertain the possibility of selling the Three Mile Island Nuclear Generating Station, as well.
Unlike Oyster Creek, the early retirement of TMI-1 is not being considered
.because of lower operating costs at TMI-1.
No decision about the sale of TMI, or the sale or early retirement of Oyster Creek, has been made.
Fermi Unit 2. Restart Followino Main Generator Reoairs On January 17, 1997, during a turbine startup, an event occurred that led to motoring of the main generator.
The damage caused by this event required 4
sending the main generator rotor offsite for repairs.
These repairs have been completed and the generator has been reassembled. On May 6. 1997, the licensee synchronized the main generator to the grid.
The licensee is performing testing of various equipment during the startup and further balance shots may be needed to complete the balancing of the new low 3ressure rotors in the main turbine.
This will complete a refueling outage tlat started on September 27. 1996.
Byron. Units 1 and 2 -- IPEEE Comed submitted the Byron IPEEE repart in December, 1996. The methodology employed by Comed did not calculate an overall CDF but was intended to identify any significant vulnerabilities.
None were identified for seismic or NAY 9, 1997 ENCLOSURE A
other external events.. Comed also did not identify any significant
. vulnerabilities to fire. Since no individual compartment contributes more than
+
1.0E-06 to the core damage frequency (CDF).
The CDF for fire is approximately 3E-06 for each unit.
3 Oconee. Units 1. 2 & 3 On May 1,.1997. Duke Power Company (the licensee) was reviewing radiographs of nozzles on Unit 3 taken in November 1996,'looking for indications of a mispositioned nozzle in the high pressure injection (HPI) system similar to
)
what has been seen on Unit 2.
When a small gap was noted between the thermal j
sleeve 6nd nozzle in the 3Al nozzle. the licensee decided to shut down Unit 3 because of a concern of the pipe's susceptibility to thermal fatigue.
It l
~ appears that the licensee had not adequately dispositioned the gap when the radiograph was originally taken.
On May 3.1997. with the Unit 3 reactor shutdown and being cooled down and with pressure approximately 230 psig reactor coolant temperature approximately 215*F. one reactor coolant pum) running, and the Low Pressure
. Injection System in operation to cool down t1e reactor coolant system, the "B" i
HPI pump started cavitating. When the reactor coolant pump low seal water 4
flow signal automatically started the "A" HPI pump, it started cavitating also. The operators stopped both pumps. A Notification of Unusual Event was
- declared when it was recognized that the pumps were inoperable and the condition would exist past the shift that was on duty. The Region II and Headquarters Emergency Centers were manned in the Monitoring Mode.
Unit 3 pressure and temperature was stabilized and there was no immediate concern that conditions would worsen.
It was subsequently determined that cavitation of the.HPI aumps-was caused when all of the water was pumped from the Letdown Storage Tanc due to a faulty level indication. This false level indication (that indicated tank level was higher than actual level) was caused by the loss of water in the level detector reference leg, which was caused by a very slow leak in the reference leg that existed over the past two months.
As a i
result, both pump motors and pumps have been removed for inspection and l
repair. The pumps are 24-stage vertical centrifugal, deep well. pumps.
The licenm developed procedures and has flushed the HPI piping and is using the "C" Hi4 pump.
As a result of this event. Region II established an Augmented Inspection Team j
- on May 5. 1997.'to determine the facts relative to the Unit 3 event, assess licensee activities and access generic aspects that may apply to the.other Oconee units.
Region II also issued a Confirmatory Action Letter (CAL) on May 5,1997..
related to the Unit 2 HPI weld crack problem. Among other items, the CAL indicates that it is understood that concurrence of the Regional Administrator is needed before restart of Unit 2 or 3.
Unit I continues to operate'at full power and the licensee has submitted a Justification for. Continued 0)eration (JCO).
The staff wrote a Request for Additional Information dated iay 5.1997. related to the JC0 and to the weld crack problem.
The JC0 is under staff review.
MAY 9.!1997 ENCLOSURE A
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Replacement of the Unit 2 HPI line where the weld crack was located is progressing.
The NRR and Region II staffs are closely monitoring the licensee's activities associated with its investigation and repair of the weld crack and loss of the HPI pumps. A meeting with the licensee is being planned. The staff has contacted the B&W Owners Group and the potential generic aspects for other B&W plants is under investigation.
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MAY 9. 1997 ENCLOSURE A
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Office of Nuclear Material Safety and. Safeguards Items of Interest i
Week Ending May 9, 1997 Issuance'of ths Environmental Assessment-for General Electric-Wilminaton j
On May 6,-1997, the Nuclear Regulatory Commission staff issued a Finding of No l
Significant Impact (FONSI) and an Environmental Assessment (EA) in support of 3
the license. renewal for General' Electric Nuclear Energy Production's (GE) fuel 2
- fabrication facility in Wilmington. North Carolina.
The staff coordinated the preparation of the EA with the State of North Carolina. As a part of the i
i renewal review. NRC also evaluated plans to operate a new dry conversion i
process at the Wilmington site, GE submitted a summary of an Integrated Safety Analysis for the dry conversion process in support of the renewal i
review. The projected date for completing the renewal of the license is mid-July 1997.
Prior to renewing the license, several issues pertaining to criticality safety, chemical safety, operations, and training need to be i
resolved.
The NRC staff plans to meet with GE representatives on May 20.
a
-1997 to review these issues and to discuss GE's intended response.
Prooosal to Downblend Hiah-Enriched Uranium On April 30. 1997. Babcock & Wilcox (B&W) Navy Nuclear Fuel Division met with j
-the Nuclear Regulatory Commission staff to discuss B&W's intent to downblend excess U.S. high-enriched uranium into low-enriched uranium for use in j
commercial reactor fuel over the next five years.
The high-enriched uranium would be transferred from the U.S. Enrichment Corporation (USEC).
The discussions focused on changes that would be required to B&W's current license for its fuel fabrication facility in Lynchburg, Virginia, and the supporting information B&W would need to submit to the NRC including information to l
support the interface with the International Atomic Energy Agency.
Both B&W ana Nuclear Fuel Services submitted proposals to USEC at the end of i
April 1997 for the contract to downblend the uranium.
Based on the current contracting schedule, contract award is expected to occur within the next
.several months with initial transfer of uranium beginning in the Fall of 1997.
1 American Municioal Sewaae Association On May 6, 1997 staff from the Nuclear Regulatory Commission participated in a ineeting of the American Municipal Sewage Association held in Washington.
D.C.
Attending the meeting were representatives from the Environmental Protection Agency and a number of sewer treatment plant operators from various parts of the U.S.~ The topic of discussion was radioactive contamination of sewage sludge resulting from sewer discharges by NRC and other licensees.
Conference of Radiation Control Procram Directors t
~
On April 29-30. 1997, a' senior management representative from the Office of Nuclear Material Safety and Safeguards (NMSS) participated in the annual
' meeting of the Conference of Radiation Control Program Directors in Tacoma.
Washington.' Presentations were made on revisions to Nuclear Regulatory MAY 9. 1997 ENCLOSURE B 4
u Commission medical regulations and on the NRC Strategic Assessment.
Discussions also took place related to the NMSS Business Process Reengineering efforts, materials licensing guidance consolidation. sealed source and device plans, and radiography.
Jeoartment of Enerav Central Interim Storace Facility Tooical Safety Analysis leoort Submittal On May 1. 1997, the Department of Energy (DOE) submitted its non-site-specific Central Interim Storage Facility (CISF) Topical Safety Analysis Report (TSAR).
The purpose of the submittal is to provide technical information on the CISF design and operations.
DOE has requested that the Nuclear Regulatory Comm1ssion staff review the submittal and prepare a safety evaluation report indicating that the TSAR is suitable to be referenced in an anticipated CISF application in accordance with 10 CFR Part 72.
DOE requests that the NRC staff complete its review by the end of FY 1998.
NRC staff is currently assessing its resource commitments and review strategy for this submittal.
.00E states in the TSAR that the CISF is designed as a temporary, above-ground.
away-from-reactor independent spent fuel storage installation for up to 40.000 metric tons of uranium (from commercial light water reactor spent nuclear fuel).
The design is non-site-specific, but incorporates conservative environmental and design factors (e.g., 360 mph tornado and 0.75g seismic loading) intended to be capable of bounding subsequent site-specific l
parameters.
DOE plans to receive spent fuel in dual-purpose canister systems i
approved by the NRC for transportation and storage (although it should be noted that several designs included by DOE are currently under NRC staff review). A transfer building will be provided for shielded transfer of canisters between transport overpacks and storage overpacks for those systems which do not provide for " direct yard" transfer.
Facility design and operations are intended to be flexible enough to allow for the addition of new vendor system designs. based upon extrapolation of present systems, subsequent,
to approval by the NRC.
The CISF is designed to have a minimum service life of 40 years with only routine maintenance.
DOE concludes that based upon the analyses presented in the TSAR for a site that falls within the environmental and design parameters established in the TSAR. the CISF can be constructed and operated in a manner that protects the public health and safety.
Meetina with Virainia Power on North Anna indeoendent Soent Fuel Storace Installation On May 5.1997. staff of the Spent Fuel Project Office met with representatives of the Virginia Power Company (VPC) to discuss their application for a license to operate an independent spent fuel storage installation at the North Anna power plant.
Discussions focused on the applicant's response to the Nuclear Regulatory Commission's first request for additional information, which was received by NRC on April 18, 1997.
Key outstanding issues are the liquefaction potential at the site, and the degree to which casks may slide on the concrete pad during a design basis earthquec, VPC committed to provide NRC additional information on the liquefaction analysis.'as well as the final analysis of cask sliding potential.
MAY 9. 1997 ENCLOSURE B
Meetino with Sierra Nuclear Corocration i
On May 6.1996, the Spent Fuel Project Office (SFP0) staff held a meeting with Sierra Nuclear Corporation' (SNC). the Certificate of Compliance (CoC) holder.
'of the Ventilated Storage Cask-(VSC-24) system design.
The pur)ose of the i
meeting was to discuss two of four non-conformances identified )y the Nuclear Regulatory Commission during an inspection of SNC and its fabricators on March 17-21. 1997 (NRC Inspection Report No. 72-1007/97-204. dated Aaril'15.
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1997). The two non;conformances' involve SNC's failure to (1) examine the
)otential. generic aspects of VSC-24 shield-lid weld failtres at Arkansas Vuclear One and Palisades Nuclear Generating Plant, and (2) submit a change to the CoC to correct a non-conservative requirement for the drain-down time j
limit of a loaded VSC-24.
t To address the non-conformance regarding the non-conservative drain-down SNC 1
plans to request a change to the CoC to specify a conservative drain-down time limit. To address the non-conformance regarding the shield-lid weld failures.
?SNC plans to determine the root cause of the weld cracking, evaluate the potential for delayed cracking, and develo)/ implement changes to the weld design and/or weld process to prevent craccing on future casks.
The SFP0 l
r staff is concerned that an undetected crack in the VSC-24 shield-lid weld i
could occur while a loaded cask is in storage. thus affecting the integrity of the cask confinement boundary.
Although the failure of both the cask's inner i
shield-lid weld and outer structural-lid weld would not pose an off-site
. threat to public health and safety, such an occurrence would cause the loss of
. the helium atmosphere inside the cask.
This loss could result in fuel cladding degradation and future fuel handling and retrievability problems.
During the meeting, licensees using the 1/SC-24 stated that they do not intend to load additional casks until the weld issue is satisfactorily resolved.
SNC plans to respond to the NRC Notice of Violation by May 15. 1997, and to 1
complete the lid weld evaluation by June 15. 1997. Additional actions on the delayed cracking issue may be required depending upon the results of the weld evaluation.
Renewal of Source Material License for Shootarino Canyon Mill On May 2. 1997. the Division of Waste Management renewed Source Material License SUA-1371 for.the-Plateau Resources Limited (PRL) Shootaring Canyon
. mill located in Ticaboo Utah.
The staff issued a five-year duration.
performance-based license that authorizes operation of the mill contingent upon:
(1) the approval of a final design for the tailings impoundment liner and the installation of that liner: (2) PRL's submittal of a technical evaluation of the existing cross-valley berm and the tailings dam: and (3) the Nuclear Regulatory Commission's confirmation, during a pre-operational
' inspection. that necessary standard operating procedures will be in place.
1 MAY 9. 1997' ENCLOSURE B v
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Office for Analysis and Evaluation of Operational Data Items of Interest Week Ending May 9. 1997 NUREG/CR-4674. Volume 24. " Precursors to Potential Severe Core Damaae Accidents: 1982-83. A Status Report" The Accident Sequence Precursor Program Report on 1982-83 operational events.
NUREG/CR-4674. Volume 24, was approved for publication on May 8.
This report documents the review and analysis of 1982 and 1983 licensee event reports (LERs) for precursors. The analyses described in this report were performed primarily for historical purposes to obtain the two years of precursor data for the NRC's ASP Program which had previously been missing.
In this effort.
more than 2100 LERs were reviewed for potential precursors. 435 LERs were selected for further detailed analysis, and 109 precursors were identified -
54 for 1982 and 55 for 1983.
'The most important precursor events for 1982-83 include:
failures of the automatic reactor trip capability at both PWR units at a plant, a steam generator tube rupture at a PWR with subsequent failure of a 3ressurizer power-operated relief valve to close, problems with residual leat removal and/or residual heat removal service water systems at two BWRs. loss of offsite power-related events with a degraded emergency power system at two BWRs, a reactor trip with an inoperable auxiliary feedwater pump and an inoperable pressurizer )ower-operated relief valve at a PWR, and a loss of offsite power event wit 1 an inoperable turbine-driven auxiliary feedwater pump at a PWR.
Prooosed Rule. 10 CFR 50.76. "Recortina Reliability and Availability Information for Risk-sianificant Systems and Eauioment."
1 On May 8. 1997 a'SECY paper on the subject rule was forwarded to the Commission. The paper describes the staff's evaluation of a proposed industry voluntary alternative to the rule.
The voluntary approach consists of (1)
INP0's Equipment Performance and Information Exchange (EPIX) system which provides component failure and demand data for a broad scope of systems and 4
(2) INP0's Safety System Performance Indicator (SSPI) system which provides train unavailability data for systems within its scope.
The staff would also use other information, such as Licensee Event Reports (LERs) which provide actual and spurious demand data for Engineered Safety Features (ESFs).
The SECY contains the staff's recommendations regarding the voluntary proposal.
PRELIMINARY NOTIFICATIONS (PNs) a.
PNO-I-97-027. Overlook Hospital. MISADMINISTRATION OF 10 DINE-131 DOSE FOR l
A WHOLE BODY I-131 SCAN.
b.
PNO-II-97-0238. Duke Power Company (0conee 2). EXTENDED SHUTDOWN - OCONEE UNITS 2 AND 3 (UPDATE).
MAY 9. 1997 ENCLOSURE D
4 c.
PN0-II-97-026. Duke Power Company (0conee 3) DEGRADED HIGH PRESSURE INJECTION PUMPS DURING PLANT C00LDOWN.
d.
PNO-II-97-026A. Duke Power Company (0conee 3). DEGRADED HIGH PRESSURE INJECTION PUMPS - UPDATE.
e.
PNO-II-97-0268. Duke Power Company (0conee 3). DEGRADED HIGH PRESSURE INJECTION PUMPS - UPDATE.
f.
PN0-III-97-039. Theda Clark Hospital. MISADMINISTRATION -- UNDERDOSAGE IN 10 DINE-131 TREATMENT.
g.
PNO-IV-97-025. St. James Community Hospital. EXCESSIVE DOSE RATES ON INCOMING PACKAGE CONTAINING 10 DINE-131 E.
h.
PNO-IV-97-026. Entergy Operations. Inc.
SHUTDOWN GREATER THAN 72 HOURS AFTER MANUAL SCRAM.
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i MAY 9. 1997 ENCLOSURE D
.4 Gifice of Administration Items of Interest Week Ending May 9. 1997 U S. Enrichment Corocration (USEC)
Staff from the Division of Facilities and Security '(DFS) and the Computer Security and Oversight Section are completing a 10 CFR Part 25 and 95 inspection of the Paducah Gaseous Diffusion Plants (GDP). An exit meeting i
between USEC and senior DFS management-personnel was held on May 9. 1997.
During the inspection a demonstration of the DFS's new Record of Classification Actions (RCA) on line system for recording the creation of or change to classified documents was provided to USEC staff.
The demonstration was well received.
Small Business Reculatory Enforcement Fairness Act On May 8.1997, a new icon on the NRC Home Page was added to inform users of a toll-free number that the public may use to obtain guidance on requirements that may affect small entities. This icon is part of the NRC's outreach to small entities in response to the Small Business Regulatory Enforcement Fairness Act of 1996. The icon also provides a summary of the SBREFA and informs the public that the Office of Administration will serve as the point of contact for inquires and will forward them to appropriate staff for response.
[ontract Administration On March 31. 1997, the NRC received the State of Maryland Comptroller of the Treasury's decision to grant a refund of the sales tax paid in connection with utility bills under contract NRC-10-94-141. " Commercial Facilities Management Services." with TECOM. Inc. A refund check in the amount of $23.680.63 was received May 6. 1997.
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MAY 9. 1997 ENCLOSURE F
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Chief Information Officer Items of Interest Week Ending May 9. 1997 Sianificant FOIA/PA Reouests Received durino the 5-Day Period of May 2.1997 -
May 8. }997:
NMSS medical licensees on disk.
(FOIA/PA-97-155)
Budget. FY97 budgeted amount for software.
(F01A/PA-97-156)
OIG report number 97-107S.
(F01A/PA-97-157)
Award' citation wording related to an April 1996 presentation to named' individual.
(F01A/PA-97-158)
Haddam Neck power plant, radiological deficiencies, weaknesses, non-compliance issues and accidental exposures.
(F0lA/PA-97-159)
-Office of Investigations case no 1-86-004.
(F01A/PA-97-160)
Wats Bar plant. MOU with DOE re tritium production.
(F01A/PA-97-161)
MAY_9. 1997 ENCLOSURE G
Office of Personnel Items of Interest Week Ending May 9. 1997 Three Career Fairs Attended On May 7-8, 1997. David Diec and Tilda Liu. both from the Office of Nuclear Reactor Regulation. attended the Federal Asian Pacific American Council Career Fair held at the Double Tree Hotel in Rockville. Maryland.
On May 8-10. 1997.
Gloria Corbitt and Henry Rubin, both from the Office of Personnel, attended the Public Service Recognition Week Career Fair on the Mall in Washington, D C.
On May 10. 1997. Vicki Francis, from the Office of the Inspector General, and Mark Au, from the Office of Nuclear Regulatory Research, attended the Asian Pacific American Heritage Council Festival Career Fair in Washington. D.C.
The recruiters met with several excellent entry-level candidates at the career fairs.
Arrivals HOLMES. Stephen RADIATION SPECIALIST (PFT)
NRR LAIN, Paul FIRE PROTECTION ENGINEER (PFT)
NMSS LUNDY. Anna SECRETARY (0A) (PFT)
NMSS WATTENBERG. Marcia 0FFICE AUTOMATION ASSISTANT (PFT)
NMSS Retirements ABRUSCATO. Gisela SECRETARY (OA) (PFT)
NMSS GEHL Alice ADMINISTRATIVE ASSISTANT (PFT)
OCM Departures NONE MAY 9. 1997 ENCLOSURE I
l Office of Small Business & Civil Rights Items of Interest Week Ending May 9. 1997 SBCR Visit to Reaion I In res]onse to a request from the Regional Administrator. on May 5-6. 1997.
Irene _ittle and Ira Radden visited Region I.
The purpose of the visit was to participate in a working lunch with Managers and Supervisors to discuss their roles and responsibilities in implementing the Agency's EE0 Program.
The Regional Administrator and most of the Regional Supervisors attended the luncheon. The discussion included recruiting techniques. the Region I Mentoring Program for new hires. and the need for effective communication between employees and all levels of management.
There was also a meeting with EE0 Counselors and the EE0 Advisory Committee Representatives to discuss their roles in an effective EE0 Program.
Federal Subcontractina Forum On May 7. 1997. Von Deloatch. Program Manager. Small Business Program, attended a Subcontracting Forum s]onsored by the U.S. De]artment of Agriculture (USDA). The event. w1ich was a first for US)A. was well attended by representatives from the Federal and private sectors.
Mr. Steven L.
Schooner. Associate Administrator for Procurement Law and Legislation. Office of Federal Procurement Policy (0FPP). gave a presentation on the future of subcontracting in the Federal government. A panel comprised of Contracting Officers discussed subcontracting success stories and entertained questions j
from the audience.
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MAY'9. 1997 ENCLOSURE J t
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Office of Public Affairs H
ltems of Interest Week Ending May 9. 1997 Media Interest There was media interest in the meeting with Sierra Nuclear on their spent fuel cask.
HQ and Region IV fielded numerous calls on the ASLB decision supporting the CAN contention re9arding environmental justice of the proposed Claiborne Parish, LA, enrichment facility.
School Volunteers Proaram Jack Foster, NRR. was interviewed by an 8th grade student from H.P. Woodlawn Middle School on engineering careers at NRC.
Press Releases ligadauarters:
97-069 NRC Seeks Public Comment on Proposed Regulatory Guidance for Power Reactor Licensees Making Changes to Facilities or Procedures 1
97-070 NRC Considers Changes to Regulations for Transportation of High Level Waste Containing Plutonium 1
97-071 Note to Editors: ACRS Meeting June 3 97-072 NRC Advisory Committee on Nuclear Waste to Meet May 20-22 in i
Rockville. MD i
97-073 Note To Editors: ACRS Meeting May 28-29 97-074 Note To Editors: ACRS Meeting June 10
[ Legions:
1-97-47 NRC Prohibits Veterinarian From Using Radioactive Materials.
Proposes $4,000 Civil Penalty for Several Violations 1-97-48 NRC, Connecticut Company to Discuss Apparent Violation involving Watches I 97 NRC Staff Conditionally Authorizes Restart of Nine Mile Point 1 11-97-36 NRC Sends Ir.spection Team to Oconee Nuclear Power Plant MAY.9. 1997 ENCLOSURE M
11-97-37 NRC to Hold News Conference May 12 in Miami on Florida Nuclear Plant Hurricane Plans 4
11-97-38 NRC Staff Issues Assessment of Performance at St. Lucie III-97-42 NRC Names New Senior Resident Inspector at Fermi 'uclear Power Plant III-97-43 NRC Names New Resident Inspector at Point Beach Nuclear Power Plant 111-97-44 NRC to Hold Predecisional Enforcement Conference on Apparent Violations of NRC Fire Protection Requirements at Braidwood Plant 111-97-45 NRC to Hold Predecisional Enforcement Conference on Apparent Violations of NRC Requirements at Clinton Plant
.III-97-46 NRC Names New Resident Inspectors at LaSalle Nuclear Power Plant 4
a MAY 9. 1997 ENCLOSURE M
1 Region I Items of Interest Week Ending May 9. 1997 DOE Meetino At the ABB (CE) Site. Windsor. CT Region I staff of the Decommissioning and Laboratory Branch attended a meeting sponsored by DOE at the ABB (CE) site Windsor, CT, on May 7, 1997.
The 1
purpose of the meeting was to discuss DOE's role in the cleanup of the site under the Formerly Utilized Site Remedial Action Plan (FUSRAP).
DOE is initiating development of a site characterization plan with onsite work 4
expected to begin in early 1998 and continue through 2002.
Meeting attendees included representatives from the Connecticut Department of Environmental Protection and the Town of Windsor Health Department.
t KAY 9, 1997 ENCLOSURE P t
Region II Items of Interest Week Ending May 9, 1997 licensee Senior Manaaers Visit Reaion__ll On May 5. 1997, several managers from nuclear power plant facilities and the Institute of Nuclear Power Operations (INPO) visited the Region II office.
The visit was conducted as part of the INPO Senior Nuclear Plant Management course. The visit included a discussion of NRC Regional operations by the Regional Administrator and a briefing on operations of the Region II Incident Response Center Isomedix (Veaa Alta. Puerto Rico)
On May 8, 1997, Region II held a Predecisional i.nforcement Conference with representatives of Isomedix and Abbott Health Products. Inc. (AHPI).
The purpose of the conference was to discuss the February 12. 1997, operation of a megacurie pool irradiator in Puerto Rico for a period of 2.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> without a licensed irradiator operator 3 resent at the facility The license had been held by AHPI at the time of t7e event, but was transferred to Isomedix on March 19, 1997. The licensee discussed the circumstances surrounding the event. causes, and corrective actions.
Florida Power Corooration Representatives from Florida Power Corporation were in the Regional Office to attend a Crystal River engineering meeting.
The licensee discussed their discovery efforts to date for determining the Extent of Condition for problems related to Design Control, unreviewed safety questions, and corrective actions.
4 Representatives from Florida Power Corporation were in the Regional office to attend a management meeting to discuss Crystal River progress toward restart of the plant.
Items discussed included plant modifications, actions required by the Confirmatory Action Letter issued March 4.1997, and progress toward correcting specific issues of concern which led to the extended shutdown.
Duke Power Comoany -- Oconee The Oconee special inspection of the Unit 2 high pressure injection line pipe crack is continuing.
Repairs have been completed on Unit 2 and inspections are in progress for Unit 3.
Region II and the Office of Nuclear Reactor Regulation are evaluating the licensee's Justification for Continued Operation of Unit 1 and evaluating responses to a Request for Additional Information on the restart of Unit 2.
Based on current progress, a meeting with the licensee is scheduled for May 15 to discuss the restart of Unit 2.
In response to a failure of two High Pressure Injection pumps on Unit 3, an Augmented Inspection Team (AIT) was initiated on May 5.
The AIT inspected the circumstances surrounding the failure along with an assessment of the MAY 9. 1997 ENCLOSURE P
s licensee's event response and corrective actions. An exit was held at the site with the licensee on May 9.
A public exit will be held during the meeting on May 15.
A Confirmation of Action (CAL) letter was issued to the licensee on May 5.
concerning actions Oconee will take as a result of the cracked pipe and the High Pressure Injection (HPI) pump failures.
Atlanta Area Federal Emoloyee Awards Several Region II managers and employees were nominated for the Atlanta area Federal Employee-of-the-Year Awards.
One Region II manager was honored as one of three finalists for Excellence in Management.
Awards were presented to winners on Friday. May 9. 1997, at the World Congress Center. The awards program is presented by the Federal Executive Board of Atlanta.
Deoartment of the Navy A Severity Level III violation was issued to the De]artment of the Navy. NRC Master Materials License. as a result of improper s113 ment of a package containing iodine-125 from the Navy Drug Screening La) oratory in Jacksonville.
Two improperly packaged vials containing a total of 250 microcuries of iodine-125 broke during the shipment resulting in contamination of the outside surface of the package.
Radioactive contamination was also found in the vehicle used to transport the package to Brooks Air Force Base in Texas.
A Civil Penalty was not issued because of the Drug Screening Laboratory's prior good performance and prompt and comprehensive corrective actions.
l MAY 9. 1997 ENCLOSURE P l
Region III Items of Interest Week Ending May 9. 1997 Predecisional Enforcement Conference with Indianaoolis Deoartment of Caoital Asset Manacement On May 6, 1997. a predecisional enforcement conference was conducted in the Region III Office. Lisle. Illinois, between management representatives from Indiana)olis Department of Capital Asset Management. Indianapolis, Indiana, and mem)ers of the NRC staff.
Discussion focussed on an NRC inspection in March at the agency which discovered a number of apparent violations. The violations included the failure by the agency to conduct a physical inventory of its nuclear gauges every six months as required. The last inventory _
performed was in July 1996.
Manaaement Meetina with Commonwealth Edison Comoany On May 7,1997, a management meeting was conducted in the Region III Office, Lisle. Illinois, between management representatives from Commonwealth Edison Company (Comed) and members of the NRC staff to discuss the LaSalle Station Restart Plan.
During the meeting, Comed staff discussed the status of the implementation of various aspects which support the Restart Plan. Also discussed at the meeting was the LaSalle Operations High Intensity Training (HIT) Program for licensed and non-licensed operators and the status of the Corrective Action Program (CAP). Comed has not yet submitted a final Restart Plan for NRC review which can be evaluated based on performance measures that are established within the plan.
At the meeting. NRC staff requested that Comed officials discuss the t
performance-indicators that are being used to evaluate the effectiveness of the Restart Plan during upcoming performance review meetings.
MAY 9, 1997 ENCLOSURE P i
O Region IV Items of Interest Week Ending May 9, 1997
~
Public Meetino at Fort Ca]floun Station On May 5. 1997, the Region IV Regional Administrator, and Region IV staff, attended a public meeting at Fort Calhoun Station to discuss the root cause and corrective actions associated with an extraction steam line break that occurred on April 21, 1997.
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MAY 9. 1997 ENCLOSURE P
Office of Congressional Affairs items of Interest Week Ending May 9. 1997 CONGRESSIONAL HEARING SCHEDULE, No. 17 OCA.
- DATE
.' TIME.
WITNESSz SUBJECT !
COMMITTEE CONTACT PLACE ummmmmmmmmmmmmm-Combs 05/13 3:00 Hearing and H.R.
629, Texas Low Reps. Schaefer/ Hall 2123 RHOB Markup Level Waste Compact Energy & Power Commerce Madden 05/14 1:00 Secretary Pena DOE's FY98 Budget Reps. Sensenbrenner/ Brown 2318 RHOB Science Gerke 05/22 9:30 TBA Financial Implications Senators Murkowski/ Bumpers 216 HSOB of Restructuring the Energy & Natural Resources Electric Utility Industry Gerke 06/12 9:30 TBA Benefits and Risks of Senators Murkowski/ Bumpers 216 HSOB Restructuring to Energy & Natural Resources Consumers and Communities MAY 9. 1997 ENCLOSURE R