ML20137S784
| ML20137S784 | |
| Person / Time | |
|---|---|
| Issue date: | 04/09/1997 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| SECY-97-078, SECY-97-078-R, SECY-97-78, SECY-97-78-R, WIR-970404, NUDOCS 9704150244 | |
| Download: ML20137S784 (19) | |
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1, Aoril 9.1997 SECY 97 078 For:
The Commissioners From:
James L. Blaha, Assistant for Operations. Office of the EDO Sub.iect:
WEEKLY INFORMATION REPORT - WEEK ENDING APRIL 4, 1997 Contents Enclosure 4
Nuclear Reactor Regulation A
Nuclear Material Safety and Safeguards B
Nuclear Regulatory Research C
Analysis and Evaluation of Operational Data D
4 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.
Original signed by:
Carl F. Dolinka for James L. Blaha Assistant for Operations, OEDO M. Biamonte. OEDO Document Name:
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20056 INFORMATION REPORT 4
Aoril 9.1997 SECY 97-078 i
For:
The Commissioners From:
James L. Blaha. Assistant for Operations, Office of the EDO l
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING APRIL 4. 1997 Contents Enclosure Nuclear Reactor Regulation A
Nuclear Material Saf' ty and Safeguards B
e Nuclear Regulatory Research C
Analysis and Evaluation of Operational Data D
General Counsel E*
Administration F*
Chief Information Officer G*
1 Chief Financial Officer H*
Personnel I
Small Business & Civii 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.
h' b
jf James L. Blaha M
d' i
Assistant for Operation /s. OEDO
/
Contact:
M. Biamonte. OEDO
e, i
Office of Nuclear Reactor Regulation f
Items of Interest l
Week Ending April 4, 1997 Salem Nuclear Generatino Station Units 1 and 2 RESTART SCHEDULE - Following is the latest schedule published by the licensee:
Mode 4 (heatup above 200 F). May 8: Mode 3 (above 350oF, all ECCS operable),
May 15: Mode 2 (reactor critical), June 11: full power, July 12, 1997.
l There are a number of issues, noted with an asterisk, that could potentially impact the licensee's restart schedule.
- CABLE SEPARATION - The licensee is still reviewing cable separation in the relay room.
It has expanded the number of cables being examined.
The l
licensee has determined that the issue can be addressed under the provisions of 10 CFR 50.59 and e.ioes not constitute an Unreviewed Safety Question.
The staff will review the licensee's 50.59 evaluation.
HEMO TO THE COMMISSl0N - A memo to the Commission on the status of Salem is with the EDO.
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- CONTAINMENT FAN COIL UNITS (CFCUs) - By letter dated March 27, 1997, the licensee described modifications that are being implemented to preclude water hammer on loss of offsite power. The submittal is under review..The amendment increasing the CFCU initiation time from 45 to 60 seconds is needed to support entry into Mode 3.
The staff is expecting to complete its review and issue the amendment in time to support entry into Mode 3.
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- RHR PUMP FLOW AND NPSH - Region I is sending a TIA that will request NRR assistance in evaluating the effects of increased RHR system pump flow, and a l
potential Unreviewed Safety Question and Mode 4 constraint.
FIRE BARRIERS - NRR and Region I have agreed upon a plan to resolve the fire i
barrier issue. The acceptability of 3reviously approved pre-1981 tests i
affecting Kaowool and 3M FS-195 fire Jarriers will be handled generically.
l The staff will conduct an inspection )rior to restart to review corrective / compensatory actions that lave been taken by the licensee on the l
plant specific unresolved items ide'ntified in the 1993 Inspection Report 93-80 for 3M Interam E-50 as well as for Kaowool and 3M FS-1.95. fire barriers.
Region I will provide the lead for the inspection and will coordinate preparation plans and inspection logistics with the licensee. The inspection is currently scheduled for the week of April 14, 1997.
l CONTAINMENT DESIGN TEMPERATURE - By letter dated June 18. 1996-, an amendment to Technical Specification 5.0, " Design Features." was submitted.
The proposed amendment changed the design temperature and pressure of the containment by adding revised design parameters for the Main Steam Line Break (MSLB). The licensee has determined that the new MSLB parameters will cause yielding of the containment liner, but will not overstress the reinforced concrete shell. The staff is reviewing the submittal and has requested additional information concerning the liner anchors.
Although this amendment APRIL 4. 1997 ENCLOSURE A
t is.not considered a restart issue, it is expected to be issued prior to restart.
REACTOR COOLANT SYSTEM (RCS) FLOW SURVEILLANCE - By letter dated January 7.
1997, the licensee proposed a Technical Specification (TS) amendment to revise the 18-month surveillance to measure RCS flow. The current TS do not enable the plant to enter Mode 1 without having performed this surveillance within i
the last 18 months. The surveillance is performed when the plant is above 90 percent power.
Since both units have been shut down for more than 18 months.
l the surveillance has not been performed within the last 18 months. Thus, the-amendment must be issued to support entry into Mode 1.
The amendment was reviewed by Projects and sent to the Reactor Systems Branch (SRXB) for concurrence.
Projects is incorporating SRXB comments into the Safety l
Evaluation. The amendment is expected to be issued prior to Mode 1.
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CHILLED WATER SYSTEM - By letter dated February 11. 1997, the licensee has proposed a new Technical Specification section entitled " Chilled Water System." The Chilled Water System provides cooling for safety related systems, such as the Control Room Emergency Air Conditioning System and the l
Electrical and Relay Room. The Chilled Water System is comprised of three 50-percent chillers and two 100-percent pumps. The proposed amendment would allow one chiller to be out of service for 30 days; if another chiller is lost, the plant must shut down within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The amendment is under review by the Plant Systems Branch (SPLB) and the Probabilistic Safety Assessment Branch (SPSB).
SPSB has informed the licensee that the proposed 30-day Allowable Outage Time (A0T) for one chiller appears excessive and would be difficult to justify.
The licensee is considering reducing the A0T for one 1
chiller. The staff is treating the amendment as Priority 3: SPLB is targeting August 30. 1997, for com)letion of their Safety Evaluation.
However, the i
licensee has requested t1at the amendment be issued prior to restart, or shortly thereafter. Without this amendment, the licensee will have to perform 4
an operability determination of the Chilled Water System whenever a chiller or pump is out of service.
The licensee considers this an operator work around and does not wish to run the plant in this way for an extended period of time.
Projects is exploring the possibility of expediting review and issuance of this amendment.
Seabrook Station Unit 1 For a period of time during the northeaster storm on April 1.1997, two of three transmission lines to the Seabrook site were knocked out of service i
because of heavy wet snow accumulation on the transmission line termination bushings. With two lines out of service, the station, which had been operating at full power started to reduce Sower to 30%.
However, with power at about 90%. the lines were restored and t1e station was returned to full power. There were no other safety-related storm-related impacts upon the station.
The latest capacity and load projections on the NEP00L grid show a negative
-capacity for the 14-week period from May 31 to August 30, 1997.
If these capacity and load projections materialize. load relief up to Action 13 of the l
APRIL 4. 1997 ENCLOSURE A
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NEREX Operating Procedure No. 4 would be needed to mitigate the projected deficit. Actions through Action 13 include, in part:
o Curtailing certain dispatchable loads e
Purchasing power from other systems e
Using certain customer generation capacity contractually available e
Allowing the 30 minute reserve to go to zero
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Reducing the 10 minute synchronized reserve e
-Implementing 5% voltage reductions.
New Hampshire Governor Shaheen anc Public Service Company of New Hampshire (PSNH) will ask a mediator to settle the dispute over how the state will deregulate the electric utility industry.
PSNH and its parent company Northeast Utilities have filed suits in federal and state courts over the NH Public Utility Commission's plan for deregulation. The companies claim the 1
plan would force them to write off an estimated $700 to 900 million of assets.
I which would force them into bankruptcy.
Prairie Island Units 1 and 2 i
Northern States Power Company has reviewed the spring snowmelt flood outlook from the National Weather Service and predicted the impact on Prairie Island s
Units 1 and 2.
Based on current conditions plus anticipated temperatures and i
precipitation through the snowmelt period the crest potential of the Mississippi at the Prairie Island plant is a) proximately 1.5 feet above the j
flood crest in 1993 (elevation 683.3 feet)'wlich was the most severe flooding
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in recent history. The estimated flood level is 'at approximately the 685 foot j
elevation. Grade level around the main buildings is at or above the 694 foot i
elevation. The Notice of Unusual Event level is at the 686 foot elevation and unit shutdown is at the 692 foot elevation. The crest date is estimated to occur sometime between April 12 and April 18. 1997. The licensee will-continue to assess the potential for spring flooding based on the most current information.
I Zion Units 1 ant 2 -- Ooerations Deoartment Evaluation and Reoraanization For the past week, the licensee has been evaluating all-personnel in the i
operations department to determine who will continue in operations and 3articipate in the restart of Unit 2.
The results of its evaluations were to 3e announced on about April 2.1997. Those personnel who were selected to remain in the operations department will commence a training program on April 7, 1997, to return Unit 2 to service. The licensee plans to startup Unit 2 using the improved standard technical specifications (ISTS) and will use ISTS to conduct its training. The operators who were not selected will no longer be in the operations department.
The reactor operators that chose not to participate in the evaluation process were evaluated by management and APRIL 4. 1997 ENCLOSURE A
their futures will be determined along with those of the other department members.
In January 1997, the licensee had unitized the management of the operations, maintenance, and work control departments.
Prior to the start of the training on April 7, 1997, the operations department will be consolidated into one organization, centered on Unit 2. instead of being unitized.
The other departments will remain unitized.
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APRIL 4, 1997 ENCLOSURE A
e Office of Nuclear Material Safety and Safeguards Items of Interest l
Week Ending April 4,1997
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Babcock and Wilcox Announces Intent to Restructure The Babcock.and Wilcox Company (B&W) has informed the Nuclear Regulatory Commission of its intent to restructure by forming a wholly-owned subsidiary called the. Babcock & Wilcox Company. BWX Technologies. Inc., (BWXT).
B&W is restructuring along business lines to improve its competitiveness.
B&W states i
1 that the restructuring will have no effect on NRC-related safety or financial i
responsibilities. The restructuring affects B&W licenses for the Naval Nuclear Fuel Division in Lynchburg, Virginia: former fuel processing d
i facilities in Apollo and Parks Township. Pennsylvania: Shallow Land Disposal Area at Parks Township Pennsylvania: and research and development facilities f
in Alliance. Ohio.
B&W is seeking NRC consent to the restructuring, which B&W intends to implement at the end of June 1997. Tne NRC staff will review the pro)osed restructuring to confirm that it will not adversely affect compliance i
wit 1 NRC requirements and to identify issues that require resolution prior to the restructuring.
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APRIL 4, 1997 ENCLOSURE B
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Office of Nuclear Regulatory Research Items of Interest Week Ending April 4. 1997 Attendance at the International Symoosium on Seismic Safety Relatina to Nuclear Power Plants RES and NRR representatives attended the. International Symposium on Seismic Safety Relating to Nuclear Power Plants.
The symposium was to foster an international information exchange on seismic design and engineering through presentations of invited speakers and discussions on'up-to-date research results and current engineering practices among participating experts. The emphasis was on practical solutions in nuclear power plant applications. More than 250 participants from about 25 countries were present at the symposium.
The RES staff presented a pa)er entitled. "U.S. Nuclear Regulatory Commission j
Seismic Regulations. Researc1. and Emerging Trends." and also participated in 1
-a panel discussion of invited representatives on the subject of Technical Issues and International Cooperation on Seismic Engineering of Nuclear Power Plants.
The international information exchange programs provide opportunities to learn from each other and effectively pool the limited resources together.
RES Meetjna with GE-San Jose Recardina BWR Reactor Vessel Internals on March 13. 1997 Joel Page of GSIB/DET attended this meeting which included representatives of the Idaho National Engineering & Environmental Laboratory (INEEL). The pur)ose of the meeting was to provide information associated with the meclanical engineering aspects of NRC's ongoing research regarding intergranular stress corrosion cracking of BWR internals.
Specifically, the meeting concentrated on the mechanical design details and the thermal / hydraulic performance aspects of the reactor vessel internals, including those associated with the reactor protection and emergency core cooling systems.
Joint Soecialists Meetina on NDE Techniaues Caoability Demonstration and Insoection Qualification Staff members from the Offices of Nuclear Regulatory Research (RES) and Nuclear Reactor Regulation (NRR) attended a Joint Specialists Meeting on NDE Techniques Capability demonstration and Inspection Qualification.
The purpose of the meeting was to provide an international forum for the discussion of recent developments results and of utility experience with NDE techniques capability demonstration and inspection qualification methods. The meeting provided an opportunity to com]are and assess the qualification principles from the American Performance )emonstration Initiative (PDI). the European Network for Inspection Qualification and as well as the IAEA guidelines specific to VVER's. Special emphasis was placed on NDE techniques APRIL 4. 1997 ENCLOSURE C
cyalification to detect and size flaws in order to assure structural integrity curing plant design life or into the period of license extension.
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Additionally, the RES staff member attended a meeting of the International Cooperative Group on Piping Performance.
The purpose of this meeting was to discuss activities since the last meeting of September 1996 and to discuss future activities. A steering committee was formed to solicit. commitment from utilities to partici) ate in the group's activities.
Future activities discussed included t1e objectives and scope of the group, a proposal for the piping performance data base program, management of data, costs, access to data, and organization of the group. The next meeting is tentatively i
. scheduled for October 1997 during the Water Reactor Safety Information Meeting in Bethesda, MD.
q Publication of Reaulatory Guides and Standard Review Plan Sections On April 1.1997, a Federal Reaister Notice was published (62 FR 15547) announcing the issuance and availability of the following regulatory guides and standard review plan sections: (1) Regulatory Guide 1.165. " Identification dnd Characterization of Seismic Sources and Determination of Shutdown
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Earthquake Ground Motions." (2) Revision 2 to Regulatory Guide 1.12. " Nuclear Power Plant Instrumentation for Earthquakes." (3) Regulatory Guide 1.166.
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" Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator Post-Earthquake Actions." (4) Regulatory Guide 1.167. " Restart of a Nuclear Power Plant Shut Down by a Seismic Event. (5) Standard Review Plan Section 2.5.1.
i Revision 3. " Basic Geologic and Seismic Information." (6) Standard Review Plan Section 2.5.2. Revision 3 " Vibratory Ground Motion." (7) Standard Review Plan Section 2.5.3. Revision 3. " Surface Faulting."
These regulatory guides and standard review plan sections are in support of amendments to 10 CFR Parts 21. 50, 52, 54 and 100 published December 11.
1996. (61 FR 65157) that update the criteria used in decisions regarding power reactor siting, including geologic, seismic, and earthquake engineering considerations for future nuclear power plants, and if requested on modification of operating reactors.
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i APRIL 4. 1997 ENCLOSURE C
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Office for Analysis and Evaluation of Operational Data Items of Interest Week Ending April 4, 1997 Reactor Analysis Br3nch Sucoort of Reaulatory Information Conference Jose Ibarra and Hal Ornstein made presentations at the Regulatory Information Conference.
j Jose Ibarra's presentation addres. sed the recently completed "Assessnent of Spent Fuel Cooling," which has been issued as NUREG-1275,.Vol. 12.
j Hal Ornstein's presentation addressed control rod insertion problems at foreign operating reactors.
AEOD Case Study C97-01. " Grid Performance Factors" AE00 issued the final report for Case Study C97-01
" Grid Performance Factors " The study was initiated to document operating ex)eriences which may have impacted nuclear power plant operations and the availa)ility of offsite power for the period of 1985 to the present.
The draft report was issued in July of 1996 for comments.
NRC staff and industry organizations responded.
Subsequent to the issuance of the draft report, AE00 personne1' have interviewed government and industry personnel concerning the reliability of offsite power.
Problems described in the study and by industry self-assessments, as well as uncertainties introduced by the restructuring of the electric industry indicate the need for the NRC to monitor grid conditions on a regular basis.
Information Notice 97-14 Issued on AE0D Study on Assessment of Soent Fuel Pool Exoerience An Information Notice (IN 97-14) was issued March 28 informing nuclear power plant operating license holders of the AEOD assessment of operating experience involving spent fuel' pool cooling ana inventory losses described in NUREG-r 4
1275, Vol. 12. " Assessment of Spent Fuel Cooling." The NUREG was issued in February. The IN highlights results of the AE00 independent study results from the analysis of operating ex>erience with spent fuel pools.
While the
_ study found that the relative risc due to loss of spent fuel pool cooling is low compared with non-spent fuel pool events the review determined that consequences are highly dependent on human performance and individual plant j
design features.
l Pilarim Event On A)ril 1 1997. IRD staff members supported Region I during NRC's monitoring of tie loss of off-site power at the Pilgrim nuclear power plant. Additional Headquarters staff who supported Pilgrim monitoring activities were members of
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Project Directorate 1-3 Electrical Engineering Branch, and Instrumentation and Controls Branch of NRR, and Reactor Analysis Branch of AE00.
The event terminated around-midnight April 2. 1997.
APRIL 4. 1997 ENCLOSURE D
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PR$L'IMINARY NOTIFICATIONS (PNs)-
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a.
PNO-I-97-018. GPU Nuclear Corp. (Three Mile Island 2) PROTEST RELATED TO THE TMI UNIT TWO ACCIDENT.
b.
PNO-I-97-019. Boston Edison Co. (Pilgrim 1) UNUSUAL' EVENT AT PILGRIM DUE i
TO LOSS OF POWER AND STORM RELATED IMPACT AT OTHER REGION I PLANTS.
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c.
PNO-II-97-019. Chem-Nuclear Systems. Inc.
LOSS OF VALVE FROM EQUIPMENT.
IN TRANSIT.
d.
PNO-III-97-029. Wci Steel. Inc., CONTAMINATED SCRAP METAL.
e.
.PNO-IV-97-016. Washington Public Power Supply System. (Washington Nuclear
-2), TECHNICAL SPECIFICATION REQUIRED SHUTDOWN OF PLANT.
'PNO-IV-97-017.EnterffEDDURINGLOADINGOFTHIRD,SPENTCASK. Operatio
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RELATED CRACK IDENTI g.
PNO-IV-97-018. Pacific Gas & Electric Co. (Diablo Canyon 2). PARTIAL LOSS OF MAIN FEEDWATER PUMP AND REACTOR TRIP RESULTING IN SHUTDOWN GREATER
'THAN 72 HOURS.
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Office of Personnel f
Items of Interest Week Ending April 4.1997 i
In-House Workshoo on Deoression Held On April 3. 1997. Dr. Bruce Kehr, a local psychiatrist, presented a two-hour' L
workshop on depression in the workplace. Approximately 80 employees attended.
l The program was a repeat of a presentation made in March, at which time a
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separate session was held for supervisors. Dr. Kehr was asked to come back to j
. accommodate those who were unable to attend the earlier sessions.
1997 Federal Savinas Bonds Kick-off Rally Held l
.0n March 31. 1997 Henry Rubin attended the 1997 Federal Savings Bonds Cam)aign Reception and Kick-off Rally at the Andrew W. Mellon Auditorium in Waslington. D.C.
Attorney General Janet Reno was the keynote speaker, who again will serve as the Campaign Chair.
NRC's 1997 Savings Bonds Campaign
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will run from May 12 to June 12. 1997.
Arrivals EDGERLY. John REACTOR ENGINEER (PFT)
RIV l
RICHMOND. John PROJECT ENGINEER (PFT)
RII SIV. Nathan SR LEVEL ADV FOR PROB RISK ANAL (PFT)
RES Deoartures CHILK. Samuel DIR. COMM DECISION TRACKING SYS PROJ (PFT)
SECY FOULDS. Ronald SR RESEARCH ENGINEER (PFT)
RES i
1 APRIL 4. 1997 ENCLOSURE I
1 Office of Public Affairs Items of-Interest Week Ending April 4. 1997 Media Interest Press reporters attended the Maine Yankee meeting regarding the plan for restart.
One reporter from the Arkansas Gazette attended the exit meeting for the design inspection at Arkansas Nuclear One.
School Volunteers Proaram Tom Frederichs. NRR spoke about NRC and nuclear reactors with two 5th grade classes at St. Christopher's School in Chicago.
1 Press Releases Headauartgrg.97-055 Note to Editors: ACRS reports97-056 NRC Releases Final Decisions on Strategic Assessment Issues97-057 NRC Advisory Committee on Nuclear Waste to Meet April 22-24 in Rockville. MD 97-058 NRC Names New Chief Financial Officer Reaions:
I-97-32 NRC Staff to Meet With Public to Discuss Molycorp I-97-33 Radioactively Contaminated Valve Reported Missing From Truck Stop in Paulsboro. N.J.
I-97-34 NRC Rating of Indian Point 2 Nuclear Power Plant Finds Decline in Overall Performance of Facility I-97-35 NRC to Meet With Public on Nine Mile Point Core Shroud Inspection 11-97-28 NRC Staff to Hold Predecisional Enforcement Conference to Discuss Farley Nuclear Power Plant Concerns With Licensee 11-97-29 NRC Commissioner Diaz to Visit Surry Nuclear Power Plant 11-97-30 NRC Staff to Hold Predecisional Enforcement Conference to Discuss-Vogtle Nuclear Power Plant Concerns With Licensee APRIL 4. 1997 ENCLOSURE M
.h IIJ-97-33 NRC to Hold Predecisional Enforcement Conference With Midwest Imaging Diagnostic. Inc., on Apparent Violations of NRC Safety Requirements t
IV-97-21 NRC Staff Proposes to Fine Fairbanks Hospital $2,500 in Misadministration Case IV-97-22 NRC Staff Proposes $100.000 Fine for Violations at Wolf Creek a
APRIL 4. 1997 ENCLOSURE M
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Office of International Programs l
Items of Interest l
Week Ending April 4.1997 l
Foreian Visitors -- Jaoan On Wednesday April 2,1997. Deputy Director General Tomihiro Taniguchi, Agency for Natural Resources and Energy. Ministry of International Trade and Industry of Japan, met with Chairman Jackson, During their discussions, he briefed her on the status of Japan's nuclear power program and the effects of the recent fire and explosion at the Tokai Works of the Power Reactor and Nuclear Fuel Development Corporation (PNC).
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APRIL 4, 1997 ENCLOSURE N
e Office of the Secretary Items of Interest Week Ending April 4. 1997 Historian Sam Walker, the NRC Historian, delivered a talk at the annual meeting of the Society for History in the Federal Government, held at the National Archives in College Park. Maryland on April 3 and 4.1997. As a part of a session on
" Writing the Nuclear History of the Cold War Era." he discussed the
int'sllectual challenges and rewards of his work on the history of nuclear regulation. The session was attended by a standing room audience of 40-50 people.
Participants in the conference included federal historians, contractors, and other scholars with an interest in the history of the federal government.
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APRIL 4, 1997 ENCLOSURE 0
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Region I
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Items of Interest Week Ending April 4, 1997 Outreach to Harvard University On March 28, 1997. John Kinneman made a presentation on the Regulation of Radioactive Materials Users to about 50 participants in a class on Occupational and Environmental Radiation Protection at the Harvard School of Public Health.
APRIL 4, 1997 ENCLOSURE P l
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1 Region 11 Items of Interest Week Ending April 4,1997 Viroinia Electric & Power Comoany - North Anna & Surry On April 2, the Commonwealth of Virginia Power hosted a Radiological Emergency Preparedness Seminar for local government emergency management representatives. The meeting agenda included )articipation and presentation
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on NRC' programs from the Surry and North Anna Resident Ins)ectors and Regional 1
Staff members. The meeting was conducted at the Virginia Power Company.
Innsbrook Technical Center, Richmond, Virginia.
Foreion Visitors in Reaion II Office Region II will be hosting Messrs. Andrie and Dimov from the State Office of.
Nuclear Safety of the Czech Republic. They will be visiting at the Catawba Nuclear Site from March 31 through April 11, 1997.
Messrs. Furness and Ascroft-Hutton from the United Kingdom (UK) Health and Safety Executive were in the Regional Office to meet with regional management.
Meetina with Secretary of Puerto Rico Deoartment of Health (PRDH)
On April 3. 1997, the Director, Division of Nuclear Materials Safety, the Director, Division of Industrial and Nuclear Material Safety, NMSS, and Regional staff met with the Secretary of the Puerto Rico Department of Health in San Juan, Puerto Rico. Other attendees at the meeting were D. Saldana, Director of the Radiological Health Program: D. Olivo, Assistant to the Secretary in the Environmental Health: L. Vissepo. Legal Counsel to the Secretary: and W. Townsend Ophthalmologist from the University of Puerto Rico and advisor to the Secretary.
The PRDH and NRC agreed upon the actions to constitute the followup.
APRIL 4, 1997 ENCLOSURE P
Office of Congressional Affairs
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Items of Interest Week Ending April 4. 1997 CONGRESSIONAL HEARING SCHEDULE No. 12 I OCA :-
DATEJ
' ASSIGN 2 1 &.-
l TIME
% WITNESS-
- SUBJECT 5.
jCOMMITTE$$
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y MENT:
PLACE nu mmmesmusammmmmmmmmmmmmmme Madden TBA 9:30 DOE DOE's FY98 Budget. Offc of Senators Domenici/Reid 124 DSOB Energy Research Energy & Water Development Appropriations Gerke 04/07 2:00 James King Nomination of James King as Senators Thompson /Glenn 342 DSOB OPM Director Governmental Affairs Gerke 04/14 TBA Atlanta Electricity Deregula-Reps. Schaefer/ Hall 04/18 Richmond tion Field Hearings Energy & Power 05/02 Chicago Commerce 05/09 Dallas Madden 04/18 9:30 TBA Debt Collection Improvement Reps. Horn /Maloney 2154 RHOB Act Gov't Mgmnt. Info & Tech Gov't Reform & Oversight Madden 04/22 9:30 TBA DOE's F 98 Budget.
Senators Domenici/Reid 124 DSOB Environmental Management Energy & Water Development Program Appropriations Madden 04/23 10:00 TBA Two-Year Federal Budget Senators Thompson /Glenn 342 DSOB Governmental Affairs APRIL 4. 1997 ENCLOSURE R m
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