ML20214F608
| ML20214F608 | |
| Person / Time | |
|---|---|
| Issue date: | 05/13/1987 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-870508, NUDOCS 8705260179 | |
| Download: ML20214F608 (31) | |
Text
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A May 13, 1987 For:
The Commissioners From:
T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING MAY 8, 1987 A sumary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.
Contents' Enclosure Administration and Resources Management A
Nuclear Reactor Regulation B
Nuclear Material Safety and Safeguards C
Nuclear Regulatory Research D
Governmental & Public Affairs E
General Counsel F*
Personnel G*
Analysis and Evaluation of Operational Data H
Small & Disadvantaged Business Utilization & Civil Rights I*
Special Projects J*
Regional Offices K*
CRGR Monthly Reports L*
Executive Director for Operations M
Items Addressed by the Commission N
Meeting Notices O
Proprietary or Other Sensitive Information (Not for P
external distribution) f '[j'l
- No input this week.
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hog 52hoks $0!
T. A. Rehe d ssistant for Operations WEEKLYINFOREPT PDR-Office of the Executive Director for Operations
Contact:
T. A. Rehm, ED0 492-7781
HIGHLIGHTS OF WEEKLY INFORMATION REPORT Fermi-2 WEEK ENDING MAY 8, 1987 The NRR/ Region III team audit of the Femi-2 maintenance program (April 20-24, 1987) revealed weaknesses in maintenance staffing, control of spare parts, planning-and scheduling of preventive maintenance and the i
existence of significant maintenance work backlogs. Senior NRC staff will' meet with the licensee at'the plant site on May 11, 1987, to discuss the audit results and to determine if the licensee should be authorized to continue with startup tests up to 75%. power (plant operation is currently limited to 50% power).'
Peach Bottom Atomic Power Station On May 4, 1987 the Philadelphia Electric Company announced the appointment of Admiral Dickinson M. Smith as Manager of the Peach Bottom Atomic Power Station. Admiral Smith is a retired Rear Admiral with over twenty five years of nuclear experience. Admiral Smith is a 1955 graduate of the U.S. Naval ~
Acadesny and holds a Master of Public Administration degree from the American University.
e Mixed Low-Level-Waste The staff reviewed an EPA Mixed Energy Waste Study (MEWS) which analyzed the current DOE management practices for HLW, TRU, and certain other radioactive
- wastes.
The study concludes that, in most cases, DOE's current management of HLW and TRU waste materials is equivalent or superior to RCRA requirements.
j The staff is evaluating a DOE final rule (10 CFR 962) on Byproduct Material i
(Federal Register; May 1, 1987), which adopts the position developed in the NRC/ EPA joint guidance on mixed waste definition.- The rule provides for chemical components-in all DOE mixed waste to be subject to regulation under RCRA.
L The staff is evaluating the impacts of the " Nuclear Protection and Safety Act of 1987" (S. 1085), a Bill introduced by Senator Glenn to:
(i) create an independent oversight board to ensure safe operation of DOE facilities; (ii) eliminate DOE's exemption from Occupational Safety and Health Act (OSHA) Standards; (iii) give EPA sole jurisdiction over DOE mixed waste; and (iv) create a Radiation Research Review Board to oversee DOE's research activities in radiation health.
l Status of Turkey Point 4 International Safeguards i
An IAEA/NRC team was at Turkey Point 4 on Saturday morning, May 2, as scheduled, l
to install IAEA seals on the reactor head to provide IAEA assurance on continuity l
of reactor core inventory.
IAEA surveillance cameras are currently in place and operational.
Upon arrival at the site, the IAEA inspection team was told that there would be a delay of 5 or more hours before the reactor head would be ac-cessible due to some liquid penetrant tests required on reactor vent welds.
The l
IAEA team could not remain on site beyond the original schedule; therefore, the l
sealing of the reactor head was postponed for the second time.
Class C Waste On April 30, 1987, Mr. T.C. Johnson, of the NMSS Low Level Waste staff, made a presentation to the Michigan Radioactive Waste Control Committee on the 10 CFR Part 61 Waste Classification System and on Class C wastes.
The Committee was addressing the issue of excluding Class C wastes from disposal if Michigan is selected as the host state for the Midwest Compact.
Following the presenta-tion, the Committee voted 6-1 to recommend to the Governor that it is reasonable to allow disposal of Class C wastes.
OFFICE OF ADMINISTRATION AND RESOURCES MANAGEMENT For 5-Day Period of May 1, 1987 - May 7, 1987 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS - 1987-Initial Appeal of Request Initial Decision Received This Week 18 1
Completed This Week 15 1
Carryovers From 1986 170 53 Received In 1987 263 23 Granted In 1987 178 7
Denied In 1987 76 22 Pending 179 47 ACTIONS THIS WEEK Received Janice Nickerson Requests copies of records related to the 1977 Pilgrim (87-246)
Unit 1 Radiological Monitoring Report No.10, regarding radioactive milk of cows located at the Plymouth House of Correction in Massachusetts.
Lynn Connor, Requests any correspondence concerning EAD Metallurgical, Doc-Search Inc., from August 7,1985, to the present.
Associates (87-247)
(Anindividual Requests copies of records related to his Reactor rcquesting Operator Requalification Exam.
information about himself)
(87-248)
Helen Ishii, Requests a list of the respondees for four requests for Digital proposals: RS-01E-87-120,125,126 and 127.
Engineering Inc.
(87-249)
Lynn Cunningham, Requests the status report of all Office of Investigations' The Times-Picayune investigations involving the Waterford nuclear power plant (87-250) and all materials relating to the investigations.
Lawrence Sperling, Requests copies of all records since March 30, 1987, McKenna, Conner pertaining to source materials licenses granted to
& Cuneo Fansteel, Inc., including records related to License (87-251)
SMB-911 and Docket 40-7580.
CONTACT: Donaje H. Grimsley 492-7211 MAY 8, 1987 ENCLOSURE A
2 Received, Cont'd Lawrence Sperling, Requests copies of all records pertaining to source McKenna, Conner materials licenses granted to Mallinckrodt, Inc.,
& Cuneo including records related to the Columbian-Tantalum (87-252)
Division of Mallinckrodt, licenses STB-401 and SUC-872 and Dockets 40-6563 and 40-233.
Lawrence Sperling, Requests copies of all records pertaining to source McKenna, Conner materials licenses granted to Wah Chang Corporation,
& Cuneo including records related to license STB-665 and (87-253)
Docket 40-943.
Lawrence Sperling, Requests copies of all records pertaining to any McKenna, Conner applications for licenses submitted by Boulder Scientific
& Cuneo Company of Mead, Colorado.
(87-254)
Ellyn Weiss, Requests copies of 1987 correspondence (1) from the Vermont Harmon & Weiss Yankee Nuclear Power Corporation to Region I regarding pumps (87-255) in the residual heat removal system, with NRC's responses, and (2) from Region I to NRC headquarters regarding residual heat removal pumps in the Vermont Yankee nuclear power plant or the type used by Vermont Yankee.
Linda Bauman, Requests copies of all records from 1983 to the present Government related to the concerns of a named individual about the Accountability Comanche Peak nuclear power plant.
Project (87-256)
Chris Randolph Requests a list of all active nuclear reactors in the (87-257)
Southeastern section of the United States.
Paul Caffera Requests a copy of the Reactor Safety Study by (87-258)
Norman Rasmussen.
(An individual Requests records maintained on himself in the NRC.
requesting information about himself)
(87-259)
Barry Goldstein, Referral from the D0J of a request for NRC's FY 87 Legal Defense Civil Rights Implementation Plan update.
Fund (87-260)
Gregory Holmes, Requests copies of all records discussing investigations MHB Technical by the utility or NRC regarding problems with low pressure Associates safety injection and reactor coolant system pumps at the (87-261)
Palo Verde nuclear power plant.
MAY 8, 1987 ENCLOSURE A
3 Received. Coni'd Harold Nolan, Requests three categories of records regarding the i
Hadco & Associates December 9,1986 accident at the Surry nuclear power Inc..
plant.
(87-262)-
Kath Buffington, Requests four categories of records regarding PermaGrain The Bradford Era Products, Inc., of Karthaus, Pennsylvania.
(87-263)
~ Linda Bauman, APPEAL TO THE COMMISSION for the release of eight records Government denied in their entirety in NRC's April 13,.1987 response Accountability
-to a request for records relating to the Brookhaven Project National Laboratory investigation of the allegations of (87-A-23-85-213) a named individual.
Granted Steven Frantz, In response to a request for all SECY documents between Newman &
September 30, 1974 and February 12, 1976, relating to.
Holtzinger, P.C.
proposed revisions of 10 CFR 50.55a, Codes and Standards (87-136) for Nuclear Power Plants, made available three SECY papers.
Ellyn-Weiss, In response to a request for five categories of records-Harmon & Weiss related to containment, accidents, and storage at plants (87-146) of GE Mark I design and BWR fuel, informed the requester that three records subject to this request are already available at the PDR. Also informed the requester that one additional record subject to this request was referred to another federal agency for a disclosure determination and direct response to her.
Ken Bossong, In response to a request for three categories of records Critical Mass related to imported goods possibly contaminated as a (87-153) result of the accident at the Chernobyl plant, made available two records.
Informed the requester that one additional record subject to this request is already available at the PDR. Also informed the requester that additional records subject to this request was referred to other federal agencies for disclosure determinations and direct responses to him.
i David Rubinton, In response to a request for copies of all records related Government to an inspection by NRC staff on August 11-15,1986, of Accountability Ebasco's New York office, made available nine records.
Project Informed the requester that one additional record subject (87-177) to this request is already available at the.PDR.
Linda Bauman, In response to a request for copies of all records Government related to the March 11, 1987 mock disaster drill at the Accountability South Texas plant, informed the requester that two records Project subject to this request are already available at the PDR.
(87-225) itAY 8, 1987 ENCLOSURE A
~.
1*
4 Granted, Cont'd Barry Goldstein.
In response to a referral from the D0J for a~ copy of 4
Legal Defense Fund NRC's FY 87 Civil Rights Implementation Plan update, (87-260) made available a copy of the requested record.
Denied Lynne Bernabei.
In response to a request for copies of all records Bernabei & Katz related to the OI and OIA-investigations.into allegations (87-96) by a named individual of intimidation, harassment, and 1
safety problems at TVA plants, denied in their entirety records in the Office of Investigations,. disclosure of which would interfere with an enforcement proceeding.
Ophelia Williams, In response to a request for' copies of an April 10, 1986, J/R/A Associates memorandum from S. Chilk to V. Stello and an May 14, 1986, (87-118)-
. memorandum from V. Stello to the Commissioners regarding a Standardization Policy Statement, denied these records in their entirety because disclosure would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.
R.K. Buckles, In response to a request for copies of SECY-85-399 and NUS Corporation an October 20, 1986, memorandum from SECY to V. Stello, (87-129) denied these records in their entirety because disclosure would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.
(NRCemployee)
In response to a request for copies of records concerning (87-219) the evaluation, certification, and selection under Vacancy Announcement No. 87-0147-6, made available one record.
Denied portions of one record, disclosure of which would constitute a clearly unwarranted inva> ion of personal l
privacy.
-Billie Garde,-
In response to an APPEAL TO THE EDO for the release of Government three records denied in their entirety in NRC's October 15, Accountability 1986 response to a request for records concerning the Project reports listed in Board Notification 84-149 and records (86-A-219-84-779) relating to the release of the reports, denied portions of the three records, release of which could cause an unwarranted invasion of personal privacy and reveal the identities of confidential sources.
I t
i ItAY 8, 1987 ENCLOSURE A
WEEKLY INFORMATION REPORT DIVISION OF CONIRACTS WEEK D4 DING MAY 8,1987 -
IFB ISSUED IFB No.: RS-SEC-87-156
Title:
" Electrostatic Copying Services"
==
Description:==
To provide reproduction, document delivery and related services to the public and the PDR related to hard copy reproduction, microform to paper (blowback) reproduction and microform to microform reproduction.
-Period of Performance: One year Sponsor: Office of the Secretary Status: IFB issued on May 4, 1987. Bids due on June 2, 1987.
IFB No.: RS-ADM-87-202
Title:
" Photographic Reproduction Services"
==
Description:==
The contractor shall furnish all labor, materials, and equipment, in connection with processing and printing of negatives, prints and slides.
i Period of Performance: 24 months Sponsor: Office of Adninistration Status: IFB issued on May 7, 1987. Bids due on June 8, 1987.
RFP ISSUED RFP No.: RS-OIE-87-128
Title:
" Welding Technology and Codes Course"
==
Description:==
Provide technical training in welding technology and the applicable codes to enable IRC inspectors tc conduct in-depth inspections of NRC licensed power reactor facilities.
Includes revision of an existing course manual as well as presentation of the course.
Period of Performance: Five years Sponsor: Office for Analysis and Evaluation of Operational Data Status: RFP issued on May 5, 1987. Proposals due on June 8, 1987.
PROPOSALS UNDER EVALUATION RFP Nos.: RS-OIE-87-120 and 125
Title:
" Specialized Technical Training"
==
Description:==
Provide technical assistance to the NRC in the implenentation of identified needs and/or further developnent of programs to meet future needs for specialized technical training of NRC inspectors in the areas of Boiling Water Reactors (BWRs), and Pressurized Water Reactors (PWRs).
Period of Performance: 36 months Sponsor-Office of Nuclear Reactor Regulation Status: The ccmpetitive range has been established and negotiations are scheduled for the week of May 11, 1987.
MAY.8, 1987 ENCLOSURE A
Weekly:Information Report e
Division of Contracts PROPOSALS UNDER EVAIDATION (cont'd)
~
-RFP No.: RS-OIE-87-119'
Title:
" Technical Assistance in Developing and Inplementing Program 'and Procedures for Reactors Requiring Special Inspection Resources"
Description:
The contractor will provide technical assistance to NRC Regional & Headquarters Staff in developing and implementing programs and procedures for reactors with unusual probl e s during design, construction or operation, including unplanned outages.
Period of Performance:,Three years Sponsor: Office of Nuclear Reactor Regulation Status:. Negotiations have been cmpleted. Best and Final offers are due on May 20, 1987.
RFP No.: RS-ORM-87-216
Title:
" Systems Management /Progra Support"
Description:
. The centractor shall provide, on a task order basis, systes programming support for all NRC in-house cmputers which presently consist of Data General (DG) and Hewlett-Packard (HP) 16 and 32 Bit CPU's and associated peripherals.
Period of Performance: Three years Sponsor: Office of Adninistration and Resources Management Status: Best and Final offers received and forwarded to Source Evaluation Panel for review on May 7,1987.
CONTRACT AWARDED RFP No.: RS-CRM-87-236
Title:
" Acquisition of Electronic Telephone Instruments"
==
Description:==
The contractor shall provide electronic telephone instrments when ordered by PRC.
Period of Performance: One year
. Sponsor: Office of Adninistration and Resources Management Status: A fixed price requirments type Contract No. NRC-33-87-236 was awarded to Data Telecan in the amount of $66,119.30 effective May 8, 1987.
MAY 8, 1987 ENCLOSURE A
F-0FFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending May 8, 1987 s
La Crosse At 10:00 p.m., on April 30, 1987, La Crosse came to cold shutdown in prepar-ation for beginning the decomissioning of the reactor.
Current plant are to wait a few weeks for iodine to decay before removing of the head and defueling the reactor.
Shearon Harris, Unit 1 On Saturday, May 2,1987 Carolina Power and Light Company (CP&L) declared Shearon Harris Unit 1 commercial after satisfactory completion of its 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> acceptance run.
The unit is presently shut down for repairs and is scheduled for restart on May 5th.
Seabrook, Unit No. 1 The offsite emergency planning Atomic Safety and Licensing Board (ASLB) in a memorandum and order of January 9,1987 had ordered hearings on the New Hampshire Radiological Emergency Response Plan (NHREP) to commence June 1, 1987. The intervenors filed a motion to this order arguing that the schedule is so compressed that it will deny the parties to the Seabrook proceeding a fair hearing contrary to both 10 CFR 2.718 and the constitutional requirement of due process.
On May 1, 1987, the Atomic Safety and Licensing Appeal Board (ASLAB) granted the intervenors' (Seacoast Antipollution Lea New England Coalition on Nuclear Pollution) gue, Town of Hampton and appeal and ordered adjustments in the hearing schedule.
It appears by the ASLAB order that the earliest the NHREP hearings on these intervenors' contentions may commence is in July 1987.
In as much as the other intervenors (Towns of Kensington, Rye, Hampton Falls and South Hampton) did not join in the appeal motion, the ASLAB stated that the ASLB remains free to apply the schedule in the January 9,1987 order to the contentions of these intervenors.
MAY 8, 1987 ENCLOSURE B
La Crosse Daily Highlight 4
On Thursday, May 14, 1987, NRP staff will attend a La Crosse plant site visit. A brief meeting will te held with the licensee to obtain further insight into their decommissioning plans.
Fermi-2 The NRR/ Region III team audit of the Femi-2 maintenance program (April 20-24, 1987) revealed weaknesses in maintenance staffing, control of spare parts, planning and scheduling of preventive maintenance and the existence of significant maintenance work backlogs. Senior NRC staff will meet with the licensee at the plant site on May 11, 1987, to discuss the audit results and to determine if the licensee should be authorized to continue with startup tests up to 75% power (plant operation is currently limited to 50% power).
Intentional Reactor Trip Followed By Unplanned Trip At TMI-1 On May 1,1987 at 5:00 p.m. General Public Utilities (GPU) intentionally tripped the TMI-1 plant from 84% power in an effort to shock loose the crud in its once-through steam generators (OTSG). The intent was to redistribute corrosion products in the OTSG so as to improve heat transfer and permit the plant to achieve full power; TMI-1 has been limited since startup in March 1987 to 84% of full power because of fouling in the OTSG.
The trip was initiated by manually tripping the turbine which was followed by automatic reactor trip. The licensee's planned procedure included manually initiating Emergency Feedwater (EFW) and securing all reactor coolant pumps.
During EFW manipulation an operator had difficulty using an EFW flow valve l
controller, and a redundant flow control valve was used instead.
By the morning of May 2,1987, the plant was back up to 90% of full power and holding for Xenon build-in and to perform a Nuclear Instrumentation calibration. The planned trip a)peared to have succeeded in redistributing the steam generator crud. The s11ft supervisor attempted to switch channels on the neutron flux input to the ICS (Integrated Control System) so the calibration could proceed. He unknowingly flipped the wrong switch. As the calibration test proceeded to zero the flux signal, ICS properly responded l
with a significantly reduced feedwater demand causing a feedwater transient, and at 7:51 a.m. the reactor tripped on high pressure (maximum pressure reached l
was 2340 psi; the reactor trip and PORV open setpoints are 2300 and 2450 psi, respectively). Decay heat was removed with main.feedwater. There was no EFW or ECCS actuation. The operators apparently failed to confirm the automatic trip with a manual trip (required by procedures). The reactor was'made critical again by noen on May 2, and by 11:00 a.m. on May 3, 1987, TMI-1 was at 100%
power.
MAY 8, 1987 ENCLOSURE B
GPU stated in a conference call prior to the planned trip that if the trip achieves their purpose, they will use this approach again if OTSG fouling becomes a problem in the future. This policy has generic implications because the other 7 B&W-designed reactor units have experienced similar OTSG fouling problems from time to time.
It is estimated that as many as.200 additional reactor trips could be generated in B&W-designed reactors over their remaining lifetime if the intentional trip approach is used to improve OTSG performance whenever fouling is a problem. WeunderstandthatDukePower(0conee)hasmade inquiries to GPU concerning the planned trip. GPU has committed to providing a plan by July 1987 describing their longer-term approach for resolving the steam generator fouling problem.
Peach Bottom Atomic Power Station On May 4, 1987 the Philadelphia Electric Company announced the appointment of Admiral Dickinson M. Smith as Manager of the Peach Bottom Atomic Power Station. Admiral Smith is a retired Rear Admiral with over twenty five years of nuclear experience. Admiral Smith is a 1955 graduate of the U.S. Naval Academy and holds a Master of Public Administration degree from the American University.
Turkey Point Unit 3 Today Florida Power and Light company (FPL) notified Region II that two pin hole leaks have been identified in the canopy seal weld area of the control Rod Drive on the reactor vessel head. Boric acid crystals were observed in the fan cooler duct above the reactor vessel head during last weekend.
Dye penetrant testing was performed and the two pin holes were identified on Wednesday.
FPL is currently assessing the leak and the necessary corrective measures.
Turkey Point, Unit 3, is currently in Cycle 11 refueling outage. Prior to the identified problem, the unit was scheduled for a June 15, 1987 restart.
Unit 4 is shutdown due to a boric acid leek in the lower seal of an instrumentation port column assembly. The Unit 4 restart is currently scheduled for May 25, 1987.
l t
MAY 8, 1987 ENCLOSURE B
.j FRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR MAY 5 - 10, 1987 1.
DEFUELING Pick and place defueling continued using a variety of tools. One canister was filled and.two previously filled canisters were-trarisferred to the spent fuel pool.
The leaking hose on the defueling water cleanup system was replaced.
The cause of the leak was a gash in the hose which appears to have been cut by the sharp edge of a defueling tool during transfer to a storage location.
The lower end fitting jack was installed in the reactor vessel.
Defueling crews were unable to engage it-between the-lower grid and lower end fittings of part length assemblies.due to interferences, primarily-fuel pins, in the access areas. The jack will probably be used this week if the interferences can be removed.
To date, approximately 93,000 lbs of core material have been removed out of a total of approximately 300,000 lbs. The total weight includes the weight of the core, 207,000 lbs; structural and absorber material, 78,000 lbs; additional mass added by oxidation of core and structural material; and mass added by partial melting of the core support assembly and core former wall.
2.
ENVIRONMENTAL MONITORING
_ US Environmental Protection Agency (EPA) sample analysis results show that TMI site liauid effluents are in accordance with regulatory limits, NPC requirements, and the City of Lancaster
. Agreement.
TMI water effluents are sampled from the station (Units 1 and 2)
' discharge and analyzed by EPA. Gamma spectrum analyses of the seven daily composited samples for April 18 - 25, 1987 indicated no TMI-2 related radioactivity.
EPA's gamma spectrum analysis of the NRC's TMI outdoor air sample for April 30 - May 7, 1987 showed no reactor related radioactivity.
The water works for the City of Lancaster composited seven daily samples from April 18 - 25, 1987.
EPA's gamma spectrum analysis of the composite sample showed no reactor related radioactivity.
3.
DECONTAMINATION ACTIVITIES i
Robot desludging in the reactor building basement continues. The dewatered sludge is being held in the modified spent resin storage tanks in the auxiliary building basement.
MAY 8, 1987-ENCLOSURE B
i 4.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Requests 52, 53 and 56.
Solid Waste Facility Technical Evaluation Report.
Heavy Load Safety Evaluation Report, Revision 3.
Processed Water Disposition Proposal.
Safety Evaluation Report for Use of Plasma Arc Cutting Torch.
Pressurizer Defueling Safety Evaluation Report.
Safety Evaluation Report for Defueling of the Core Support Assembly.
. Canister Handling and Preparation for Shipment Safety Evaluation Report, Revision 4.
Organization Plan Change Request 15.
Defueling Water Cleanup System Technical Evaluation Report Annual Update.
Defueling Canister Technical Evaluation Report Annual Update.
The staff issued a Proposed Determination of No Significant Hazard on Technical Specification Change Request 55 and published it in the Federal Register on May 6,1987.
5.
PUBLIC MEETINGS The next meeting of the Advisory Panel for the Decontamination of Three Mile Island Unit 2 will be held on June 10, 1987 from 7:00 - 10:00 PM at the Lancaster Council Chambers, Public Safety Building, 201 North Duke Street, Lancaster, PA.
Persons desiring to speak before the Advisory Panel are asked to contact Mr. Thomas Smithgall at 2122 Marietta Avenue, Lancaster, PA 17603 (telephone 717-291-1041). Persons desiring to submit topics or questions for the Advisory Panel to consider are asked to contact the Chairman, Mayor Arthur Morris,120 North Duke Street, Lancaster, PA 17602.
t MAY 8, 1987 ENCLOSURE B
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending May 8, 1987 Meeting on Notification Procedures Under Convention on the Physical Protection of Nuclear Material (CPPNM)
The Department of State. held a meeting on May 6, 1987 to discuss the procedures to be used for processing the notifications of shipments required under CPPNM.
Representatives from NRC (SGTR and 0GPA/IP), the Arms Control and Disarmament Agency, and the Department of Defense attended the meeting.
IAEA Safeguards Implementation at Westinghouse IAEA and NRC staff met with Westinghouse management personnel at the Columbia, SC site on April 30 and May 1.
The purpose of the meeting was to discuss IAEA concerns about the previous physical inventory at the LEU fuel fabrication plant and to develop improved procedures for the next inventory, which is scheduled for the end of this year.
A mutually agreed set of procedures was developed and will be presented to the IAEA at the upcoming annual Safeguards Implementation Review Meeting on May 26-28, 1987.
Status of Turkey Point 4 International Safeguards An IAEA/NRC team was at Turkey Point 4 on Saturday morning, May 2, as scheduled, to install IAEA seals on the reactor head to provide IAEA assurance on continuity of reactor core inventory.
IAEA surveillance cameras are currently in place and operational.
Upon arrival at the site, the IAEA inspection team was-told that there would be a delay of 5 or more hours before the reactor head would be ac-cessible due to some liquid penetrant tests required on reactor vent welds.
The IAEA team could not remain on site beyond the original schedule; therefore, the sealing of the reactor head was postponed for the second time.
Class C Waste On April 30, 1987, Mr. T.C. Johnson, of the NMSS Low Level Waste staff, made a presentation to the Michigan Radioactive Waste Control Committee on the 10 CFR Part 61 Waste Classification System and on Class C wastes.
The Committee was addressing the issue of excluding Class C wastes from disposal if Michigan
-is selected as the host state for the Midwest Compact.
Following the presenta-tion, the Committee voted 6-1 to recommend to the Governor that it is reasonable to allow dise sal of Class C wastes.
MAY 8, 1987 ENCLOSURE C
2 Mixed Low-Level Waste The staff reviewed an EPA Mixed Energy Waste Study (MEWS) which analyzed the current DOE management practices for HLW, TRU, and certain other radioactive wastes.
The study concludes that, in most cases, DOE's current management of HLW and TRU waste materials is equivalent or superior to RCRA requirements.
The staff is evaluating a DOE final rule (10 CFR 962) on Byproduct Material (Federal Register; May 1, 1987), which adopts the position developed in the NRC/ EPA joint guidance on mixed waste definition.
The rule provides for chemical components in all DOE mixed waste to be subject to regulation under RCRA.
The staff is evaluating the impacts of the " Nuclear Protection and Safety Act of 1987" (S. 1085), a Bill introduced by Senator Glenn to:
(i) create an independent oversight board to ensure safe operation of DOE facilities; (ii) eliminate DOE's exqmption from Occupational Safety and Health Act (OSHA) Standards; (iii) give EPA sole jurisdiction over DOE mixed waste; and (iv) create a Radiation Research Review Board to oversee DOE's research activities in radiation health.
West Valley Demonstration Project The West Valley Demonstration Project completed a successful run of their Cement Solidification System.
This system will receive Class B and C liquid waste streams resulting from the high-level waste solidification operations for conversion into a disposable low-level waste form.
This continuous run was for fourteen.8-hour shifts and averaged about 3 drums per hour.
A portion of the run was observed by NRC staff.
URENCO NMSS staff will meet with Mr. Bader of URENC0 and Mr. Tom Merrick, Vice Presi-dent of Fluor Corporation, on May 27, 1987.
The meeting was scheduled at the request of Mr. Bader and is for the purpose of acquainting Mr. Merrick with the
'NRC licensing process.
Fluor Corporation is under contract to URENCO to assist
'them in their efforts to build and license a centrifuge enrichment facility in the United States.
UNC, Inc:
On April 29, 1987, a member of the Fuel Cycle Safety Branch discussed validation issues for nuclear criticality safety calculations with a UNC representative.
The license renewal application of UNC will be revised using the new validation information.
l l
MAY 8, 1987 ENCLOSURE C
3 P
Ory Spent Fuel Storace Westinghouse Electric Corporation has-submitted Revision 1 of_its topical safety analysis report for the model MC-10 dry spent fuel ' storage cask design for final-. staff review.
The MC-10 fuel basket design has been modified in response to. staff commints. ' Westinghouse has performed additional structural,
~
thermal, and criticality analyses supporting this modification.
VEPC0 plans to request license-authority to use this cask, in addition to the presently authorized CASTOR.V/21,,at its Surry. dry storage site,-once the Westinghouse design is approved.
Staff members met with Nuclear Assurance Corporation (NAC) on April 29, 1987, to discuss NAC's development.of a new ~ dry spent fuel, storage cask design for consolidated fuel assemblies.
The new cask will have a capacity.of 28_ fuel canisters (fuel rods from about 56. assemblies). '_The cask is to be included in DOE's' testing program at. Idaho National Engineering Laboratory.' Plans to submit a topical report.to' NRC on this design are not yet clear.
i '
Resubmittal of NAC's revised topical report for.the NAC S/T dry cask'is expected in mid-May.
Portions of NAC's quality assurance program and re-vision of report sections with respect to cask tipover and drop analyses were also discussed.
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NAY 8, 1987 ENCLOSURE C 4
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'0FFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending May 8, 1987 2D/3D Many small-scale experiments have shown that Emergency Core Cooling System (ECCS) rules prescribed.in'10 CFR 50 have a large margin of conservatism.
~
.However, there was considerable uncertainty in applying these small-scale test results to full-scale power reactors.
It was therefore considered desirable.to obtain large-scale test results before relaxing the current conservative ECCS rules. The 2D/3D International LOCA Research Program was initiated to fill this need.
Under the 2D/3D Program Japan Atomic Energy Research Institute (JAERI)' constructed,two large-scale test facilities called the Cylindrical. Core Test Facility (CCTF) and the Slab Core Test Facility (SCTF), and the Federal Republic of Germany (FRG) constructed a-full-scale test facility called the Upper Plenum Test Facility (UPTF). The NRC provided to these facilities advanced two-phase flow instrumentation and computer code analyses using the Transient Reactor Analysis' Code (TRAC).
JAERI personnel-reported that most of the U. S. instruments provided to the SCTF Core III worked satisfactorily. However, there were a few minor problems, which are being looked into by RES instrument contractors for satisfactory resolutions.
JAERI personnel also reported that they have spent a large amount of resourcesoto improve the U. S.-provided TRAC computer code in the area of LOCA reflood models. They noted that their version of TRAC (J-TRAC) runs much faster than U. S. TRAC when applied to the LOCA reflood period. LANL has also improved TRAC models for better representation of physical phenomena as well as for speeding up of computer calculations. Continuous dialogue between JAERI and RES/LANL will benefit both countries in developing better computer codes.
ECCS Regulation The NRC and others have completed a large body of research which investigated fuel rod behavior and LOCA/ECCS performance.
It is now possible to make a realistic estimate of the ECCS performance during a LOCA to revise the ECCS rule contained in 10 CFR 50.46 and Appendix K (proposed and to quantify the. uncertainty of this calculation. The NRC has published in the Federal Register 52 FR 6334) to permit more realistic analyses of ECCS performance. However in keeping with the admonition by the AEC in its
.1973 issuance of Appendix K, we propose to retain a margin of safety by a requirement that calculational
)
l MAY 8, 1987 Ef1 CLOSURE D
2 uncertainties be explicitly taken into account. This together with the demonstrated safety margin that will be retained in the 10 CFR 50.46 limits will provide a suitably conservative regulatory posture. An important regulatory change such as this requires a technical basis. The RES staff has completed a draft report "Compandium of ECCS Research for Realistic LOCA Analysis". This document contains a distillation of the research that, taken as a whole, is the technical basis.
It is being issued in draft form so that the public may comment on its contents.
It is also being circulated world-wide, and in particular to our associates in the International Code Assessment Program. The purpose of this report is to summarize this research and to serve as a general reference for the extensive researcF effort that has been performed. The report:
(1) summarizes the understanding of LOCA phenomena in 1974; (2) reviews experimental and analytical programs developed to address the phenomena; (3) describes the best-estimate computer codes developed by the NRC; (4) discusses the salient technical aspects of the physical phenomena and our current understanding of them; (5) discusses probabilistic risk assessment results and perspectives, and (6) evaluates the impact of research results on the ECCS regulations.
The report will be available about May 20, 1987 as NUREG-1230.
MAY 8, 1987 ENCLOSURE D
ITEMS OF INTEREST OFFICE OF GOVERNMENTAL AND PUBLIC AFFAIRS WEEK ENDING MAY 8, 1987 INTERNATIONAL PROGRAMS:
Foreign Visitors On Monday Howard Shapar, Director General of the Nuclear Energy Agency, met with Chairman Zech, Commissioner Asselstine, RES Director Eric Beckjord, GPA Director Harold Denton, and GPA/IP Director James Shea to discuss international nuclear safety issues of mutual interest.
On Monday members of the GPA, NRR, and RES staffs met with Professor Yashahide Asada of the Department of Mechanical Engineering at Tokyo University (and advisor to the Japanese Ministry of International Trade and Industry) to discuss a number of topics related to the leak-befcre-break concept. During the exchange, Prof. Asada provided the NRC staff with useful information on pipe wall thinning studies in Japanese nuclear power plants.
On Wednesday Dr. Peter Fraser from Canada met with RES and NRR to discuss reactor aging, risk assessment, transboundary effects and the Price Anderson Act. This was Dr. Fraser's second visit to NRC as he assists in the Canadian Ontario provincial government's independent study of the safety, design, operating procedures, and emergency plans associated with Ontario Hydro's CANDU nuclear plants.
On Thursday representatives from the Directorate for Nuclear Safety and Health Protection in Italy met with staff members of RES to discuss the LaSalle PSA for NUREG-1150 and NRC expert systems activities in the field of PRA.
On Thursday Juan Bueno, the Director-General of Standards / Regulation in the Mexican Ministry of Environment and Urban Development, met with representatives from NMSS to discuss low-level and high-level waste in conjunction with the Laguna Verde Nuclear Power Plant.
Stat'e, local and Indian Tribe Programs Weekly Highlights - May 8,1987 Conference of Radiation Control Program, Directors, Inc., Annual Meeting The 19th Annual Meeting of the Conference of Radiation Control Program Director's will be held in Boise, Idaho, May 18 to 21. The meeting ~will be attended by about 250 persons including, Program Director's and staff from each of the 50 states, several local jurisdictions and staff from NRC, EPA, FDA, NBS, DOE FEMA and NIOSH. Harold Denton will present, during the opening seminar, a review of NRC activities during 1986. He will also meet separately during the second day with all the NRC's Regional State Liaison Officers and Regional State Agreement Representatives to discuss and solicit ideas regarding the Strategic Plan and Operating Plan.
MAY 8, 1987 ENCLOSURE E
l J. Lubenau will present a paper on incidents involving naturally occurring radioactive material (NORM) contamination. The paper is a follow-on to the October, 1986 Health Physics article on inadvertent radioactive contamination of manufactural products.
D. Nussbaumer, GPA/SLI; J.Yurko, PA; and E. Bailey, TX are co-authors.
Meeting with Idaho Radiation Control Program Officials GPA/SLITP and Region IV staff will meet with Idaho radiation control program and other Department of Health and Welfare representatives to discuss the Agreement State programs. The special meeting was arranged in conjunction with the Conference meeting and will cover recent organizational and personnel changes in the Department that affect the radiation control proneams.
Audio-Conference on Low-Level Waste.,
State, Local and Indian Tribe Programs, in cooperation with the National Conference of State Legislatures, is sponsoring an audio-conference for State legislators on low-level waste issues on Monday, May 11.
Issues scheduled for discussion are:
LLW management options - storage, treatment, disposal; financial liabilities and sureties; alternative disposal technologies; class C waste; and Below Regulatory Concern waste. At least ten states are expected to participate in the audio-conference, which will include presentations by staff from the Division of Low-Level Waste management and Decommissioning, NMSS.
4 i
MAY 8, 1987 ENCLOSURE E
Office for Analysis and Evaluation of Operational Data Items of Interest Week Ending May 8, 1987 CRGR CRGR reviewed a proposed NRC Bulletin specifying licensee actions to investigate
. pipe thinning due to erosion / corrosion effects.
The Committee recommended that the bulletin be approved after modifications and review by CRGR staff.
CRGR also reviewed a proposal for the long term resolution of BWR pipe cracking.
The Committee recommended approval after modifications and subsequent review by CRGR staff.
Trends and Patterns Analysis Branch A Commission briefing has been tentatively scheduled for the week of June 15, 1987 on staff activities regarding new plant initiatives. This briefing is intended to be a followup briefing to that of November 14, 1986.
INP0 is to brief the Commission on their new plant program on May 13, 1987 as part of their periodic briefing.
Reactor Operations Analysis Branch Palisades, Surry and Limerick are participating in a trial program to provide operational dsta which will be used in the development and validation of performance indicators.
Incident Response Branch Headquarters and Region III participated in the Dry Run for the Federal Field Employee exercise on May 5-6, 1987 and addressed the three phases of the FFE:
e.g., Day 1 - the initial response to a nuclear power plant accident, Day 2 -
offsite monitoring and assessment, and Day 10 - relocation and return of evacuatees.
The Dry Run identified areas that required further work and corrective actions have been assigned.
One area in particular where improvement is underway relates to the mechanism for coordinating protective action recommendations with the states of Illinois and Wisconsin.
A meeting is being scheduled for May 20 in Springfield, IL to review this issue in advance of the Management Meeting for May 21 in Chicago.
The following Preliminary Notifications were issued during the past week, a.
PNO-I-87-38, Public Service Electric and Gas Co., (Salem Units 1 and 2), Licensed Operator Tested Positive for Controlled Substance.
b.
PN0-I-87-39, Consolidated Edison Company of New York (Indian Point Unit 2), Single Failure in Auxiliary Feedwater Initiation Circuit.
c.
PNO-0SP-87-04, Tennessee Valley Authority (Sequoyah Unit 2), Spill of Reactor Coolant Into Containment.
MAY 8, 1987 ENCLOSURE H
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2 d.
PNO-III-87-56A, Cleveland Electric Illuminating Company.(Perry),
Steam Leak from Steam Drain Line - Update.
e.'
PN0-III-87-60A, Dairyland Power Cooperative (Lacrosse Boiling Water:
Reactor), Permanent-Shutdown of the Lacrosse Boiling Water Reactor Update.
f.
PNO-III-87-64, Cleveland Electric Illuminating' Company (Perry),
Manual Scram Due to Decreasing Reactor Water Level.
- g.
.PNO-IV-87-23,-Houston Lighting and Power Company, (South Texas Project) Serious Injury and a. Fatality.
h.
PNO-IV-87-24, Kerr McGee Corporation, Potential Media Interest - Kerr McGee Corporation's Intent to Sell Their Nuclear Operations.
i.
PNO-IV-87-5, Public Service Company of Colorado (Fort St. Vrain-Nuclear. Generating Station), Plant Startup after Prolonged Outage.
j.
' PNO-V-87-31A, Portland General Electric Company (Trojan Plant),
Potential Foot Exposure of 83 REM - Update.
k.
PN0-V-87-32A, Arizona Nuclear' Power Project (Palo Verde Unit 3),
Foreign Material-Found in Steam Generator - PNO-V-87-2 Update.
1.
PNO-RV-87-33,~ Sacramento Municipal Utility District (Rancho Seco),
Selection of a New Deputy General Manager, Nuclear.
t m.
PH0-RV-87-34, Sacramento Municipal Utility District (Rancho Seco),
Dual Train Decay Heat System Outage at Rancho Seco.
f L
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4 4
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Items of Interest Office of Enforcement Week Ending May 8, 1987 The following Significant Enforcement Actions were taken the week of May 4, 1987.
1.
A Notice of Violation and Proposed Imposition of Civil-Penalty in the amount of $500 was issued to Comdustrial Roofing Contractors, Inc.,
Hatfield, Pennsylvania. The action was based on the unauthorized storage of a moisture density gauge containing licensed material and the failure to secure the gauge against unauthorized removal from the place of storage that resulted in the inadvertent disposal of the gauge to a landfill.
(EN87-38) 2.
An Order Imposing a Civil Penalty in the amount of $388 was issued to l
Nurrie Construction Company, Muskogee, Oklahoma. This action was based on several violations involving failure to leak test a sealed source, conduct inventories of licensed material, use shipping papers during transportation of licensed material, and maintain security of radioactive material. The penalty was mitigated by 25 percent after the licensee responded to the Notice of Violation.
3.
An Order Imposing a Civil Penalty in the amount of $1,250 was issued to the University of Wisconsin, Madison, Wisconsin. This action was based on violations involving the failure to conduct appropriate radiological surveys during the course of an experiment and the loss of licensed material. The licensee responded to the Notice of Violation and the staff determined that the violations did occur as set forth in the Notice.
MAY 8, 1987 ENCLOSURE M
ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING MAY 8,1987 A.
STAFF REQUIREMENTS - BRIEFING ON ADVANCED BOILING WATER REACTOR REVIEW, 2:00 P.M., THURSDAY, APRIL 30, 1987, COMMISSIONERS' CONFERENCE ROOM, D.C.
OFFICE (OPEN TO PUBLIC ATTENDANCE) - Memo for the Record fm S. Chilk, SECY dated 5/7/87 The Commission
- was briefed by the General Electric Company and the staff on efforts to certify an advanced boiling water reactor.
Presentations for General Electric were delivered by:
- Bertram Wolfe, Vice President
- Daniel Wilkins, Manager, ABWR Programs
- Ricardo Artigas, Manager, Safety and Licensing General Electric recommended and the Commission agreed to be briefed in approximately six months on the status of the ABWR submittal for design certification There were no requirements placed on the staff at this meeting.
B.
STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND VOTE, 3:30 P.M., THURSDAY, APRIL 30, 1987, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) - Memo S. Chilk, SECY to W. Parler, GC dated 5/7/87 I.
SECY-87-68A - Northern States Power Company (Control Room Radios)
The Commission, by a 3-2 vote,** approved an order which completed the Commission's consideration of issues related to an October 20, 1986 NRC staff order to Northern States Power Company which directed the licensee to show cause why its operating license should not be modified to prohibit the use of radios, tapes, and television sets, or other audible entertain-ment devices in the control room of the Prairie Island and
~* Commissioner Asselstine was not present.
- Section 201 of the Energy Reorganization A S5841, provides that action of the Commission shall b ct, 42 U.S.C.
mined by a
" majority vote of the members present e deter-Asselstine was not present when this item wa Commissioner order to allow the will of the majority to prevail Zech did not s affirmed.
In Accordingly, participate in the formal vote of the Commission.
, Chairman of the decision.the formal vote of the Commission was 2 1 i had previously indicated thatChairman Zech and Commissione however n favor they would have affirmed their prior votesdisappro they would, respectively, een present MAY 8, 1987 ENCLOSURE N
Monticello nuclear facilities.
The order rescinds the October Chairman staff order and dismisses the proceeding.
20, 1986 Zech and Commissioner Carr disapproved the order and provided dissenting views noting that they would have allowed the proceeding to take its normal course.
II.
SECY-87 Emergencv Preparedness Rulemaking The Commission, by a 4-1 vote,* approved a final rule which changes the requirement for a full participation off-site,
exercise from within one year to within two years.of issuance of an operating license for full power.
Commissioner Asselstine disapproved and provided additional comments to be. published with the rule.
- Section 201 of the Energy Reorganization Act, 42 U.S.C.
55841, provides that action of the Commission shall be-deter-mined by a " majority vote of the members present."
Commissioner Asselstine was not present when this item was affirmed.
Accordingly, the formal vote of the Commission was 4-0 in favor of the decision.
Commissioner Asselstine, however, had previously indicated that he would disapprove this paper and had he been present he would have affirmed his prior vote.
FMY 8, 1987 ENCLOSURE N
NRR MEETING NOTICES
- o3 MAY 1, 1987 o
G ES DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 5/11/87 50-219 Room 326 To discuss Status of licensing NRC/GPUN A. W. Dromerick 10:00 a.m.
Phillips Building activities for Dyster Creek.
5/13/87 50-454/
4901 Fairmont Ave.
To discuss cooling tower per-NRC/ Commonwealth Ed. L. 01shan 10:30 a.m.
455 Bethesda, Maryland formance tests for Commonwealth Edison.
5/14/87 50-456/
Room 6507 To discuss management review of NRC/ CECO D. R. Muller 8:30 a.m.
457/454/ PD Nat'l. Bank Build the licensing status of all 455/2a9/
Commonwealth Edison plantr.
237/373/
374/254/
265/295/
304 5/18/87 50-029 Yankee Atom Ele. Co. To discuss SEP review of design NRC/ Franklin Res.
E. McKenna 1:00 p.m.
Frammington, MA codes and load combinations.
Yankee Atom /NCT Eng.
5/19/87 50-029 Yankee Atom Ele. Co. To discuss SEP review of design NRC/ Franklin Res.
E. McKenna 8:30 a.m.
Frammington, MA codes and load combinations.
Yankee Atom /NCT Eng.
5/20/87 50-029 Yankee Atom Ele. Co. To discuss SEP review of design NRC/ Franklin Res.
E. McKenna og 8:30 a.m.
Frammington, MA codes and load combinations.
Yankee Atom /NCT Eng.
N8 C
55 o Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) in the NRC and local public document rooms cm A summary of these meeting notices can be obtained by calling 492-7424
3 NRR MEETING NOTICES
- MAY 1, 1987 G
ES DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT.
5/21/87 50-354 Room 5033 To discuss the schedule for the NRC/PSE8G G. Rivenbark 1:00 p.m.
Air Rights Building installation of the new computer system for the SPDS and for having operational the four additional SPDS parameters required by license condition with Public Service Electric and Gas Company.
5/22/87 50-424/
Room P-114 To discuss status of outstanding NRC/ Georgia Power L. P. Crocker 8:30 a.m.
425/366 Phillips Building licensing actons on Hatch Units 1, Company 321 and 2, and Vogtle Units 1 and 2.
5/28/87 50-458 Room P-114 To review River Bend Station (RBS) NRC/GSU S. M. Stern 10:00 a.m.
Phillips Building plans on containment purge and containment venting.
6/11/87 50-219 Room 6507 To discuss the status of the NRC/GPUN A. W. Dromerick 10:00 a.m.
MD Nat'l Bank Build. Systematic Evaluation Program and the status of the drywell shell corrosion program.
6/15/87 50-458 Room P-114 To review River Bend Station (RBS) NRC/GSU S. M. Stern 10:00 a.m.
Phillips Building plans to revise their emergency m
i2i operating procedures.
S!
E
- Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) m in the NPC and local public document rooms o
A summary of these meeting notices can be obtained by calling 492-7424
NMSS MEETING NOTICES g
,m DIVISION OF FUEL CYCLE, MEDICAL, ACADEMIC AND COPMERCIAL USE SAFETY FOR WEEK ENDING May 8, 1987 w
DOCKET ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT l
5/12/87 70-135 &
Silver Spring, MD To discuss license renewal P. Loysen, NRC
@. Loyser 2:00 p.m.70-364 for Babcock and Pficox Apollo G. Bidinger, NRC facility and amendments for D. Culberson, B&W Babcock and Wilcox Parks D. Sgarlota/B&W Township facility.
5/12-13/87 DOE Auditorium To attend Spent Fuel Storage J. Roberts, NRC J. Roberts Germantown, MD Technical Exchange Meeting J. Schneider, NRC Annual technical review meet-ing on progress on DOE's Spent Fuel Development Program.
5/13/87 Project M-G Silver Spring, MD To discuss AlChemIE's T. Clark, NRC T. Clark 10:00 a.m.
preparations for an appli-G. Terry, NRC cation pursuant to 10 CFR L. Telfard, NRC Part 50 for enriching stable R. Fonner, NRC isotopes.
1 5/17-19/87 Wakefield, MA Present talk on the General R. Cunningham P. Cunningham l
Concepts of Broad Scope l
Licenses I
m h5/18-22/87 70-687 Tuxedo, NY To participate in licensee T. Clark, NRC T. Clark g
evaluation with Region I G. Comfort, NRC l
jg personnel (Cintichem) m
\\
o 5/21/87 L' Enfant Plaza, To attend Technical Code J. Roberts, NRC
-J. Roberts l
Washington, D.C.
Coordinating Group (TCCG)
J. Spraul NRC Meeting. A review and dis-J. Schneider, NRC cussion of technical computer i
code development activities by DOE and NRC/NMSS.
l
sMSS MEETING NOTICES g
DIVISION OF LOW-LEVEL WASTE MANAGEMENT AND DECOMMISSIONING
,co 8
DOCKET ATTENDEES /
NRC DATE/ TIME NUMBER LOCATI0tt PURPOSE APPLICANT CONTACT 5/8/87 Willste, 2nd Meeting to discuss disposal of low-level J. Greeves (LLWM) Tokar 2:30 floor conf waste.
J. Surmeier (LLWM) room M. Tokar (LLWM)
T. Johnson (LLWM)
Akira Omoto -(Tokyo Electric)
Mr. Goto (Japanese Gasoline Co.)
- ~
5/11'/87 Willste, 8th Audio conference with NRC staff and Reps fm NMSS, Sha ffner 10:00 floor conf selected State Legislators to discuss GPA, OGC, room low-level waste issues.
and Regional State Liaison Officers State Legislators DIVISION OF SAFEGUARDS AND TRANSPORTATION 5/18-20/87 NFS-Erwin Site visits R Burnett, SGTR Burnett Frwin, TN H Thompson, NMSS RII Reos Babcock & Wilcox Lynchburg, VA m
55 Willste Bldg.
Regular safeguards Representatives Baker 5/27/87 Es interface meeting from the ma.ior g;
9:00-12:00 to review matters offices and the
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of mutual interest Regions o
4
1 1
J NMSS MFFTING NOTICES q
g
-c DIVISION OF HIGH-LEVEL WASTE MANAGEMENT DATE LOCATION PURPOSE ATTENDEES CONTACT May 14,1987 Willste Building Generic QA technical meeting on two JKennedy Jrennedy.
Silver-Spring, MD draf t Technical Positions: Peer Review
.LRiddle 110/106 and Qualification of Existing Data JDonnelly ADuncan s
June 29 - July 3 Embassy Square Suites Meetings to discuss various activities PAltomare PAltomare i
2000 N Street, NW underway in HLW program, including NRC's ABender l
Washington, DC approach to identification and resolution BChampion of issues, status of NRC rulemakings, HLWM staff and demonstration of the pilot program States associated with the Licensing Support Indian tribes System DOE Federal agencies I
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May-9,~1987'
.RII MEETING NOTICE
[
DOCKET ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT.
NRC CONTACT Os 5/13/87 RII Office Enforcement Conference -
Licensee, Regional.Admini-Grace 1
10:00 a.m.
Oconee Facility strator, and selected RII staff members 4
5/14/87
.RII Office Management Meeting Same as above Grace -
10:00 a.m.
Florida Power and-Light Company i
5/20/87 Crystal River, FL Meeting with Florida Power Licensee, Regional.Admini -
Grace i
1:00 p.m.
Corporation management to strator, and selected RII discuss the Crystal River staff members facility 5/21/87 Crystal River, FL Meeting with Billy Griffin, Regional Administrator Grace 9:00 a.m.
Ex. V. Pres., Eng. 8 Const.,
Florida Power Corporation 5/28/87 Hartsville, SC Presentation of Operator Licensee management and Grace Certificates at Robinson operators, and Regional p.m.
Administrator
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