ML20149J413
| ML20149J413 | |
| Person / Time | |
|---|---|
| Issue date: | 07/23/1997 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| SECY-97-157, SECY-97-157-R, WIR-970718, NUDOCS 9707280211 | |
| Download: ML20149J413 (23) | |
Text
.
Q 0
July 23.1997 SECY 97 157 Fori The Commissioners From:
James L. Blaha, Assistant for Operations. Office of the EDO Sub.iect:
WEEKLY INFORMATION REPORT - WEEK ENDING JULY 18. 1997 Contents Enclosure Nuclear Reactor Regulation A
Nuclear Material Safety and Safeguards B
Nuclear Regulatory Research C
Analysis and Evaluation of Operational Data D
General Counsel E*
Administration F
Chief Information Officer G
Chief Financial Officer H*
Human Resources I-Small Business & Civil Rights J*
Enforcement K*
Stdte 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.
James L. Blaha Assistant for Operations, OEDO h]kC Dij
Contact:
T. Hiltz, OEDO Document Name:
C:\\ WEEK 718.
g.[A g c M /11- (f t,- ---
D0 t
07/J3/97 07h1/97 a7 'O
/
^
9707290211 970723 PDR COtMS fWtCC WEEKLYINFOREPT PDR
-(
s s
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20866 INFORMATION REPORT July 23.1997 SECY 97-157 For:
The Commissioners From:
James L. Blaha. Assistant for Operations. Office of the EDO Sub.iect:
WEEKLY INFORMATION REPORT - WEEK ENDING JULY 18. 1997 Contents Enclosure Nuclear Reactor Regulation A
Nuclear Material Safety and Safeguards B
Nuclear Regulatory Research C
Analysis and Evaluation of Operational Data D
General Counsel E*
Administration F
Chief Information Officer G
Chief Financial Officer H*
Human Resources I
Small Business & Civil Rights J*
Enforcement K*
State Programs L
Public Affairs M
International Programs N*
Office of the Secretary 0
Region I P
Region II P
Region III P
Region IV P
Executive Director for Operations 0*
Congressional Affairs R
- No input this week.
e James L. Blaha Assistant for Operations. OED0
Contact:
T. Hiltz. OEDO SECY NOTE:
TO BE MADE PUBLICLY AVAILABLE IN 5 WORKING DAYS FROM THE DATE OF THIS PAPER
Office of Nuclear Reactor Regulation Items of Interest Week Ending July 18, 1997 Millstone 2 Continued Operation Without a Startuo Rate Trio A startup rate (SUR) trip was originally provided in the older ABB-Combustion Engineering (CE) plants with analog protection systems (Palisades. Fort Calhoun. Maine Yankee, Calvert Cliffs, and St. Lucie) to provide protection for a startup accident in which control rods are withdrawn at a maximum rate from a subcritical condition.
Millstone 2 requested removal of the SUR trip from the plant technical specifications (TS) in 1978.
NRC allowed elimination of trip from TS and also required physical removal from the reactor protection systet RPS) to eliminate any possible degradation that could affect other safety related equipment.
All other licensed CE analog 31 ants still incorporate this trip in their RPS.
although not necessarily in t1eir TS.
CE has recently informed their utilities of the original design intent of this trip and the inadvisability of removing it from the RPS without due consideration of the events against which it provides protection.
CE recommended that utilities considering removal of this trip function from the RPS should assure themselves that the power excursion events initiated from subcritical conditions, which are currently l
protected by the SUR trip, will be afforded similar protection by other trips I
remaining in the RPS.
Based on this, the current fuel vendor for Millstone 2.
reanalyzed the uncontrolled control rod bank withdrawal event from a subcritical condition and credited the variable overpower (V0P) trip rather than the SUR trip. The Reactor Systems Branch has reviewed the revised analysis and has concluded that the V0P trip provides acceptable fuel protection and, therefore, continued operation of Millstone 2 without the SUR trip is acceptable.
l Axial Power Distribution Anomaly Caused by Crud Builduo Power distribution and reactivity anomalies have been observed at two Westinghouse plants. Callaway and Comanche Peak. The behavior is l
characterized by a gradual unexpeted power shift toward the bottom of the core which continues until near end of cycle when the power shifts back to the top of the core.
The anomaly is believed to be caused by subcooled nucleate boiling enhanced by crud deposition on the upper portion of the fuel.
In addition to the anomalous power distribution, estimated critical control rod position (ECP) deviations between actual and predicted values increased with core burnup due to the unexpected power shift.
Therefore, an additional safety concern is the potential adverse impact that the nonconservative ECP deviations might have on shutdown margin.
Specifically, the licensee for the Callaway plant has indicated that they will need to begin reducing power in mid-August to maintain shutdown margin within the technical specification limits and have increased the frequency that they verify shutdown margin to approximately twice a week.
July 18. 1997 ENCLOSURE A
L NRR and Region IV are following this issue and have requested a meeting with Westinghouse to discuss this anomaly in more detail, Salem Unit-2 Restart Schedule
. Salem. Unit 2. is planning to cool down for approximately four days beginning l
on July 23, 1997, to perform several corrective maintenance items, including j
the repair of leaks in both the primary and secondary systems. The licensee is projecting criticality late July - early August 1997.
The staff continued t
to closely monitor the licensee's readiness for restart.
l Zion. Units 1 and 2 Ooerational Readiness Demonstration Proaram 1
The staff met with Zion station managenent on 07/11/97, to discuss its-preparations for restart of Unit 2.
One of the subjects discussed was the licensee's Operational Readiness Demonstration Program.
The purposes of the program are to verify that 1) the operators and shift crews can implement l
management's expectations for plant operations, 2) management supports operations through day to day plant activities, and 3) communication and directions.for shift operations are effactive. The licensee identified a series of plant operating tasks which ir;cludes routine and _ infrequent surveillance activities and off normal evolutions. These activities were then i
combined with the normal scheduled activities (maintenance repairs, preventive maintenance activities, ou'; of services, etc.) to complete a station work and operations schedule. The demonstration program started on 07/07/97, and is expected to run through 08/15/97.
The region will observe selected evolutions during the operations demonstration period.
l l
I I
L l
f July 18, 1997 ENCLOSURE A
i
'm Office of Nuclear Material Safety and Safeguards Items of Interest Week Ending July 18, 1997 Subarouo on International Atomic Enerav Aaency Safeauards i
On July 15, 1997, an Office of Nuclear Material Safety and Safeguards staff
)
member chaired the meeting of the Subgroup on International Atomic Energy Agency (IAEA) Safeguards in the U.S., which was held at Nuclear Regulatory Commission Headquarters in Rockville, Maryland.
The meeting included representatives from the Department of State, the Department of Energy, and the Arms Control and Disarmament Agency.
A representative from the Department of Defense participated as an observer. Topics of discussion included:
potential eligibility of the Research and Test Reactor Fuel Element facility at Babcock and Wilcox (B&W) for IAEA safeguards, preparations for tritium production at an NRC-licensed reactor, finalization of an IAEA Facility Attachment for the tube vault at the Y-12 facility, IAEA inspections of high-enriched uranium downblending at B&W, and other current issues related to IAEA safeguards in the U.S.
Safeauards Workshoo and Tour for Chinese Deleaation On July 8-9, 1997, in coordination with the Office of International Programs, Division of Fuel Cycle Safety and Safeguards staff conducted a workshop for representatives of the People's Republic of China National Nuclear Safety Administration. -The primary focus of the workshop was on safeguards, but safety was also addressed.
Presentations were 3rovided on material control and accounting, licensing and inspection, and p1ysical protection requirements, as well as on Nuclear Regulatory Commission programs for nuclear criticality, radiological, chemical, and fire safety. On July 10-11, 1997, the Chinese delegation was escorted by NRC staff for a tour and aiscussions at the Siemens Power Corporation fuel fabrication facility in Richland, Washington.
Meetina with the National Minino Association On July 15, 1997. Division of Waste Management (DWM) staff met with representatives of the National Mining Association (NMA), in one of a continuing series of bimonthly meetings to discuss topics and issues affecting uranium recovery regulation.
The DWM staff discussed the status of the uranium recovery Jortion of the final decommissioning rule, and the NMA presented feedbacc from the industry on the June 3-5, 1997, uranium recovery workshop.
In addition, the DWM staff discussed the status of the Title II Standard Review Plan (SRP) currently under development and, in particular, plans to incorporate the existing Alternate Concentration Limit technical position into the SRP.
DWM staff requested the NMA to urge licensees to provide the Nuclear Regulatory Commission with approximate submittal dates for future new license applications and amendment requests for planning purposes.
Finally, DWM informed the NMA that the September meeting will be the last of the regularly-scheduled meetings with NMA, due to resource limitations, but that meetings to discuss significant issues can be held as needed.
July 18, 1997 ENCLOSURE B
Meetina with Detroit Edison Comoany (Fermi 1) on Decommissionina 00tions On July 15. 1997. Nuclear Regulatory Commission staff met with representatives of the Detroit Edison Company (DECO), the Fermi 1 licensee.
DECO briefed the NRC staff on the status of its evaluation of Fermi I decommissioning o]tions.
DECO noted that, based on this evaluation, they have determined that tie industrial waste, such as sodium and asbestos.
Jose greater hazards than i
radiological contamination.
DECO expects to mace its plans for Fermi 1 decommissioning public within the next week.
Follow Uo Safety Insoection of Source Production and Eauioment Comoany. Inc.
On July 9-10. 1997. Spent Fuel Project Office staff conducted a follow up safety inspection at Source Production and Equipment Company, Inc. (SPEC).
SPEC is the holder of several Certificates of Compliance for transportation packagings for radioactive material.
During an earlier inspection (June 16-
- 19. 1997). the team identified significant deficiencies regarding the test recuirements of 10 CFR 71.73 and quality assurance (OA) controls over design anc testing activities.
Following the June inspection. SPEC committed to stop fabrication and develop corrective actions. The Nuclear Regulatory Commission acknowledged these commitments in a confirmatory action letter (CAL).
Since the June inspection. SPEC had successfully retested its transportation packagings, and implemented improved 0A measures.
However, the follow up inspection still found deficiencies in SPEC's OA program.
In response to the July inspection, on July 14. 1997. SPEC provided the NRC a corrective action plan, committed to update its 0A procedures with the help of an independent expert and to retrain all personnel performing quality-related activities before fabrication activities are resumed.
July 18, 1997 ENCLOSURE B
1.
Office of Nuclear Regulatory Research Items of Interest l
Week Ending July.18, 1997 Comoletion of First Phase of Tube Removals from Retired McGuire Unit 1 Steam Generators The first phase of tube removals from the retired McGuire Unit 1 steam generators has been completed.
Twenty previously plugged tubes were identified as candidates for removal based on the past inservice inspections.
Plugs from those tubes were removed, and the tubes were reinspected to confirm l
the previous inspection results and to provide the basis for selecting the l
. specific tubes to be Julled.
Secticns of 11 of the previously plugged tubes l
(106 feet total lengt1), which included ?6 tube support plate intersections and 23 indications identified by eddy current testing, were removed. The eddy i
current testing performed after the plugs were removed confirmed the presence of the indications detected in service that caused the tubes to be plugged and in addition, identified from one to three new indications in each tube.
Interestingly 3 of the 20 tubes had new circumferential crack indications on the ID of the plugged tube near the top of the tube sheet, suggesting either l
that the previous inspection missed these small indications or that there was sufficient moisture inside the plugged tube to permit further degradation after the plug had been installed.
The next phase of the tube removal will involve removal of two tube sheet sections containing a total.of 20 " undisturbed" tubes, with 8 of those tubes containing circumferential crack indications, and the removal of tube support plate sections containing 40 to 45 tubes. with 12 tubes containing crack indications.
Cutting of these tubes will begin on July 23. 1997, and the entire activity is scheduled to be completed by August 8, 1997.
Progress on this project has stayed close to the contractor's schedule, and the cumulative personnel dose incurred through this phase is approximately 2 person-rem below the target exposure. The entire project is expected to be completed below the total exposure limit of 35 person-rem that was established by the licensee.
HELCOR Code. Version 1.8.4 Development and validation of the latest version of the MELCOR code, version 1.8.4 is now complete. and the code is ready for release.
This version of the code contains many new and important improvements reflecting, in part.
recommendations from the MELCOR Cooperative Assessment Program (MCAP). MCAP involves participation by MELCOR users from research and regulatory organizations around the world. The code improvements include incorporation of the Larson-Miller cree) rupture failure model for the bottom head, modeling of hygroscopic aerosol belavior in containments, and modeling for passive containment cooling systems.
Many models, including the ability to model flow blockages in the core, downward (reverse) flow in the core, enhanced boron-carbide reactions with steam, and modeling of an zirconium oxide shell to support fuel, have been enhanced. These changes have resulted in a code that runs faster and is more robust and more versatile.
Calculations have been l
performed to validate the new code version.
These calculations include plant j,
calculations.(BWR and PWR) for different sequences (e.g., station blackout and July 18, 1997 ENCLOSURE C
j L
calculations (BWR and PWR) for-different sequences (e.g., station blackout and induced steam generator tube ru)ture) and comparisons to experimental data (e.g.
VANAM M3 CORA 13. and Plebus B9+).
A letter formally announcing the 5
availability of MELCOR-1.8.4 to the international members of the Cooperative Severe Accident Research Program and to domestic users will be issued soon.
Decommissionina Decision-Process Workshoo On July 15-16. 1997, members of the RES and NMSS staff met with contracting staff from Sandia National Laboratories to discuss implementation issues related to developing guidance on releasing sites under the new site cleanup standard. The meeting focused on a review of the spectrum of expected cases--
from a simple case where a screening methodology would be sufficient to a complex case, such as those being studied in the radionuclide behavior and transport program, where site-specific 3arameters would need to be developed.
The information exchanged will assist tie NRC staff in developing the implementation guidance for the rule.
Public workshops addressing this guidance are planned for the fall of 1997.
Russian-American Hydroaeoloav Seminar On July 8-9. 1997. RES representatives, attended the Joint Russian-American Hydrogeology Seminar s3onsored by DOE, EPA, and RES/NRC at Lawrence Berkeley National Laboratory (L3NL). The seminar's objective was to bring together the leading scientists from Russian organizations working on radionuclide transport with their American counterparts to discuss field studies, data. and remediation efforts associated with radionuclide migration by means of ground-water transport. The seminar presentations focused on the environmental problems at the Mayak site dealing with ground-water plumes emanating from the disposal site at Lake Karachai toward the Mishelyak River; deep-well injection of liquid radioactive waste in Russia; and transport analyses at United States sites.
Presentations and discussions in the seminar provided the RES staff with direct information on the Russian field studies and analyses of the large-scale radionuclide plume migrations and on LBNL's cooperative state-of-the-science analyses.
The information will assist in evaluating potential radionuclide transport in ground-and surface-water systems at decommissioned sites in complex natural environments.
Status of Thermal-Hydraulic Test Facility (THTF)
To assess available facilities. the staff explored the possibility of whether the THTF test facility at Oak Ridge can be refurbished and operated to provide the data necessary for the thermal-hydraulic code improvement.
In a telephone conversation with Oak Ridge National Laboratory. the staff discussed the state of THTF.
The THTF program was sponsored by RES, and funding totaled a) proximately 15 to 20 million dollars over its course (in 1970 dollars).
~TiTF was conceived and constructed in the_mid-1970s.
Its Jurpose was to study blowdown heat transfer in a rod bundle representative of t1e core.
The focus of the tests was heat transfer under dispersed and film boiling conditions.
It was capable of full-pressure, full-power conditions.
The rod bundle July 18. 1997 ENCLOSURE C 4
-'r
consisted of 64 rods in an 8 x 8 array. The bundle was heavily instrumented with rod internal thermocouples.
Void profile was measured with differential pressure gauges. The facility has been idle for approximately 15 years.
RELAP5 Maintenance The closecut of RELAP5 code maintenance at INEEL has begun.
RELAP5 code maintenance is being performed by SAIC.
The first task orders have been prepared to initiate work under the umbrella
]
contract entitled " Thermal-Hydraulic Research." The work will entail modularization of TRAC-P to facilitate the consolidation effort: interfacial area transport experimentation and modeling: development of numerical techniques for developmental assessnent (determining the fidelity of code comparison to data): and experimental investigation of entrainment in off-take pipes.
o i,
i.;
i 1
July 18, 1997 ENCLOSURE C
l.
Office for Analysis and Evaluation of Operational Data Items of Interest i
Week Ending July 18, 1997 Incident Resoonse Division GRD) Emeraency Resoonse Coordinators Workshoo Representatives from AE0D/IRD conducted the 29th Emergency. Response Coordinators Workshop in Region II.on July 14-16, 1997.
In attendance were the Emergency Response Coordinators. Assistants, and selected management from all NRC Regions. Areas of discussion included status of program FTE and new
' initiatives in the area of incident res)onse. Also present were-representatives from NMSS who briefed tie group on developments related to incident response regarding materials.
Preliminary Notifications (PNs)
L PNO-I-97-041. Babcock & Wilcox, PERSONNEL CONTAMINATION.
a.
b.
PNO-I-97-042. This is a test for PN using Wordperfect 6.1 for Windows.
1 c.
PNO-I-97-042A. Ambric Engineering Inc., PORTABLE GAUGE SOURCE BROKEN l
l FROM SOURCE ROD AND BELIEVED LEFT AT JOB SITE d.
PNO-I-97-043, Duquesne Light Co. (Beaver Valley 2), BEAVER VALLEY UNIT 2.
SHUTDOWN GREATER THAN 72 HOURS e.
PNO-II-97-037, Duke Power Co. (McGuire 2), SHUTDOWN IN EXCESS OF 72 HOURS FOR FAILED REACTOR COOLANT PUMP MOTOR STATOR f.
PNO-II-97-038. Bluefield Medical Center, STRONTIUM-90 (SR-90) APPLICATOR MEDICAL MISADMINISTRATIONS l
g.
PNO-III-97-058.-Mallinckrodt Nuclear Medicine, TWO MOLYBDENUM-99/ TECHNETIUM GENERATORS EXCEED DOT REQUIREMENTS h.
PNO-IV-97-040. Agreement State, DERAILMENT OF RAIL CAR CONTAINING RADI0 PHARMACEUTICAL GENERATORS 1.
PNO-IV-97-041. Agreement State Licensee (A. G. Wassenaar), THEFT OF PORTABLE GAUGE FROM STATE OF COLORADO LICENSEE j.
PNO-IV-97-042 Arkansas Agreement State (Porocel Corporation), LOSS OF PROCESS LEVEL GAUGE i
l July 18, 1997 ENCLOSURE D
Office of Administration Items of Interest Week Ending July 18. 1997 E Enrichment Corooration (USEC)
The Division of Facilities and Security (DFS) is coordinating NRC and DOE comments on USEC's preliminary information package that informs prospective bidders of the restrictions on foreign ownership, control or influence.
NRC's security inspection team composed of re)resentatives from DFS and IRM is scheduled to conduct an inspection of tle Portsmouth gaseous diffusion plan..
(GDP) during the week of July 28, 1997.
The plant will be inspected against the security requirements of 10 CFR Part 95 and the approved Portsmouth GDP security plan for the protection of classified matter.
Susoicious Packaae/Exolosives Detection /X-Ray Trainina Representatives of the U.S. Capitol Police will lead a three day training program (July 21-23, 1997) in the identification of suspicious packages, explosives detection and use of the x-ray screening equipment owned and used by NRC.
Participants include NRC staff from Headquarters, the Technical Training Center. Region III and the Walnut Creek Field Office: NRC contractors from the Headquarters mail room; and saecial agents in training from the FBI.
The schedule includes training by NRC's Radiation Safety Officer and a trip to Quantico. VA for an explosives demonstration.
July 18. 1997 ENCLOSURE F 4
Chief Information Officer Items of Interest Week Ending July 18,'1997 Sianificant F0IA/PA Reauests Received durina the 5-Day Period of
-July 11-17. 1997:
Waste Management. Inc., referral of record from D0J responsive to F0IA.
(F01A/PA-97-256)
Materials licensees in state of New Jersey and New York City area.
(F01A/PA-97-257)
Contracts $100.000 and over, names, addresses and phone numbers for specified contracts.
(F01A/PA-97-258)
- Commercial Facilities Management Services Contract No. NRC-10-94-141.
(F01A/PA-97-259)
Neely Research Reactor, Georgia Institute of Technology, license revocation, (FOIA/PA-97-260)
Sequoyah Power Plant. Unit 1,100% core thermal power rating.
(FOIA/PA-97-261)
Unpaid Treasury Checks, Limited Payability Cancellation lists for calendar year 1996, $1,000'and over, and non-individuals.
(F01A/PA-97-262)
July 18, 1997 ENCLOSURE G
4 Office of Human Resources Items of Interest Week Ending July 18, 1997 Arrivals GORDON, Dennis SECURITY SPECIALIST (REACTOR) (PFT)
NRR ORDAZ, Vonna REACTOR SYSTEMS ENGR (PFT)
NRR i
Retirements CAMPBELL, Nancy REACTOR ENGINEER (PFT)
NRR e
Deoartures HSU, Cynthia CLERK (OPFT)
ACRS 4
4 July 18, 1997 ENCLOSURE I
Office of State Programs Items of Interest Week Ending July 18, 1997
-Environmental Justice Subcommittee Meetina A representative from the Office of State Programs attended the July 17, 1997 meeting of the Interagency Working Group (IWG) on Environmental Justice (EJ)
Subcommittee on Policy and Coordination held in Washington, DC. The status of the several outstanding items was provided, as follows:
the Report to the President on Environmental Justice remains forthcoming: the Council on Environmental Quality (CE0) continues to incorporate comments on the Merch 26,
)
1997 Revised Draft CEO Guidance for ~Considering Environmental Justice under the National Environmental Policy Act (NEPA): a number of Subcommittee members continue to express the need for a memo from the President to all agency heads asking for continued support and commitment to promoting EJ throughout the Federal Government.
One of the various agenda items of interest to NRC was the Subcommittee *s discussion of the relationship of Executive Order (E0) 12898, " Federal Actions
'to Address Environmental Justice in Minority Populations and Low-Income Populations" to E013045, " Protection of Children from Environmental Health Risks and Safety Risks." The Administrator for the Environmental Protection Agency (EPA) and the Secretary of Health and Human Services (HHS) co-Chair the Task Force on Environmental Health Risks and Safety Risks to Children.
The Subcommittee Chair stated that Federal agencies are expected to support E0 13045, noting lead poisoning was the subject of an early EJ case under E0 12898.
The EPA announced its on-line EJ home page, which links to other Federal agencies, including HUD, DOE, HHS, D0J. DOT. The home page has an interactive EJ calendar of events and all users are encouraged to add any appropriate EJ events to the calendar.
The EPA home Jage address is es.inel. gov /oeca/oejbut.html (Note:
Tiere is no www:).
July 18, 1997 ENCLOSURE L 4
Office of Public Affairs Items of Interest Week Ending July 18. 1997 Media Interest-Chairman Jackson was interviewed by Channel 32 Howard University's television
- station, j
FOX-TV Philadelphia aired a story last week about the proposed Salem restart.
Press Releases Headauarters:
97-105 Note To Editors: ACRS Reports Reaions:
I-97-82 NRC Staff to Meet on July 17 With Northeast Utilities.
Nuclear. Energy Advisory Council Regarding Millstone Plant I-97-83 NRC.: Haddam Neck Officials to Meet on Radiation Control Problems I-97-84 Radioactive Source Recovered at Delaware Job Site I-97-85 NRC, Grand View Hospital Officials to Meet to Discuss Apparent Violations I-97-86 NRC Maine Yankee Officials to Discuss Cable Separation Issues I-97-87 NRC Rates Peach Bottom as " Superior" in Three Areas. " Good" in Fourth, in Agency's Latest Assessment of Plant's Performance 11-97-54 NRC Staff to Hold Conference With Centers for Disease Control to Discuss Apparent Violations 11-97-55 NRC Staff to Meet With FPC Officials in Washington on July.22 to Discuss Progress Toward Restart of Crystal River Nuclear Plant III-97-66 NRC Staff Proposes $50,000 Fine Against Wisconsin Public Service for Testing Violations at'Kewaunee Nuclear Plant III-97-67 NRC Staff to Meet With OSU Officials on A) parent Violations of Requirements for Handling and Storing ladioactive Materials July 18, 1997 ENCLOSURE M
3 IV-97-40 Comanche Peak Rated ' Superior' in all Areas in Latest NRC Assessment Report IV-97-41 NRC to Meet With Power Resources, Inc. to Discuss Apparent Violations I
l
)
I I
i l
1 l
July 18, 1997 ENCLOSURE M
Office of the Secretary Items of Interest Week Ending July 18, 1997 Commission Decision Documents Released to the Public Document Date Sub.iect 1.
SECY-97-110 5/29/97 Status Report on Implementation of Dam Safety Program
- SRM on 97-110 7/11/97 (same)
- Commission 7/11/97 (same)
Voting Record on 97-110 2.
SECY-97-117 6/3/97 Final Policy Statement on Restructuring and Economic Deregulation of the Electric Utility Industry
- SRM on 97-117 7/10/97 (same)
- Commission 7/10/97 (same)
Voting Record on 97-117 Neaative Consent Pacers Released to the Public 1.
SECY-97-120 6/16/97 Rulemaking Plan for Emergency Planning Requirements for Permanently Shutdown Nuclear Power Plant Sites 10 CFR Part 30.54(q) and (t): 10 CFR 50.47; and Appendix E to 10 CFR Part 50
- SRM on 97-120 7/10/97 (same)
Information Pacers Released to the Public 1.
SECY-97-135 7/2/97 Weekly Information Report -
Week Ending June 27. 1997 2.
SECY-97-142 7/10/97 Weekly Information Report -
Week Ending July 4. 1997 July 18. 1997 ENCLOSURE 0
l Federal Reaister Notices Released to the Public 1.
Barnett Industrial X-Ray, Inc. : Docket No. 30-30691-CivP: Establishment of Atomic Safety and Licensing Board 2.
. Radiological Criteria for License Termination. Final Rule:
10 CFR Parts 20, 30. 40. 50, 51. 70 and 72 3.
Radiological Criteria for License Termination, Uranium Recovery Facilities:
Request for additional comment on uranium recovery facilities:
10 CFR Parts 20 and 40 i
i July 18, 1997 ENCLOSURE 0 e
7 Region I Items of Interest Week Ending July 18, 1997 Reactive Insoection at Babcox & Wilcox From July.9-11, 1997. Region I staff performed a reactive ins)ection at the Babcock & Wilcox facility in Parks Township. Pennsylvania.
Tie inspection was an investigation of a June 26 incident involving three workers who were decontaminating a wall of one of.the buildings at the facility. The room previously had been the site of a plutonium scrap recovery operation.
Dust from the decontamination process resulted in significant plutonium contamination of the worker's protective clothing and resulted in a high l
breathing zone air sample result.
Bioassay results were below detectable levels for all three individuals, and work has been suspended until an internal investigation is completed and corrective actions are implemented.
Staff will review data gathered during the inspection as well as additional-information to be provided by the licensee, and will conduct a telephone exit conference on Monday, July 21.
l i
t l
l l
l f
I l
July 18, 1997 ENCLOSURE P l'
o.
Region II
)
Items of Interest Week Ending July 18. 1997 General Electric Comoany On July 16. Region II participated in the General Electric fuel fabrication plant emergency exercise.
Region II's participation included a Base Team and two site participants. The exercise was fully successful with all objectives being met and no exercise weaknesses.
Centers for Disease Control and Prevention (CDC)
The CDC met with Regional staff for a pre-decisional Enforcement Conference on July 17. The apparent violations discussed included failure to adecuately
- secure licensed material, failure to conduct inventories of licensec material.
fai' lure to calibrate survey instruments (repeat) and posting issues. The licensee outlined corrective actions and indicated their plans to have an independent review of the radiation safety program performed.
j 1
i i
[
July 18. 1997 ENCLOSURE P l
Region III Items of Interest Week Ending July 18, 1997' Prairie Island Dakota Community Insoection Observation The Prairie Island Dakota Community partici3ated in its first observation of an NRC inspection July 14-18,1997, at the 3rairie Island Nuclear Power Station.
This inspection observation was the result of the recent Commission decision to afford the Prairie Island Community the same opportunity as adjacent states under the Commission's Policy Statement on Cooperation with i
States at Commercial-Nuclear Power and Other Production and Utilization J-Facilities. The inspection which was observed by a representative of the j
Prairie Island Community covered radiation protection and effluents.
Predecisional Enforcement Conference with Ohio State University
)
The Deputy Regional Administrator and-other members of the regional and headquarters staffs met with Ohio State University, Columbus, Ohio, officials j
on July 17, 1997, in the regional office for a predecisional enforcement conference. 'The conference addressed apparent violations identified in NRC inspections conducted between June 1996 and April 1997.
These apparent violations included exceeding time limits for storage of radioactive waste, failing to make periodic inventories of radiation sources, failing to re lost or missing radioactive material or not reporting the loss promptly, port and-failing to pro)erly secure packages containing radioactive material and laboratories w1ere the material was used.
Some of the apparent violations.
were similar to violations noted in earlier NRC inspections.
i July 18, 1997 ENCLOSURE P
Region IV Items of Interest Week Ending July 18, 1997 Pre-Decisional Enforcement Conference with Omaha Public Power District On Monday, July 14th, the Regional Administrator and members of the Region IV and NRR staffs met with representatives of the Omaha Public Power District to conduct a pre-decisional enforcement conference. The purpose of the pre-decisional enforcement conference was to discuss several apparent violations regarding the Fort Calhoun Station fire protection program.
Meetina on River Bend Station (Enterav)
On July 17, 1997. Region IV held a public meeting with Entergy at the Region IV office. The purpose of the meeting was to discuss licensee implementation of its Strategic Plan for the River Bend Station. The meeting focused on transition from River Bend's Long Term Performance Improvement Plan to the new Strategic Plan.
The meeting was attended by the Regional Administrator and the Director Walnut Creek Field Office.
Enforcement Conference On Friday. July 18. Region IV conducted a predecisional enforcement conference with a former San Onofre Nuclear Generating Station operations department supervisor. The conference was based on the former supervisor's apparent deliberate failure to report two arrests to his employer. The conference was conducted by conferencing between the regional office in Arlington, Texas and IRS offices in Laguna Niguel California.
July 18. 1997 ENCLOSURE P
[
~
1 Office of Congressional Affairs Items of Interest Week Ending July 18. 1997 i
CONGRESSIONAL HEARING SCHEDULE, No. 27
........... * ? ::
!OCA) fiDA%,
~
.. iC
!;TIMEj sWITNESS1 TSUBJECTs iCOMMITTEER i;CONTAqj ij;PLACEj
- B mummusumuseumu manussamu Combs 07/22 9:00 Dept. of S.
964, Ward Valley Senators Murkowski/ Bumpers 366 DSOB Interior, GAO Land Transfer Act Energy & Natural Resources i
i July 18, 1997 ENCLOSURE R