ML20211N174
| ML20211N174 | |
| Person / Time | |
|---|---|
| Issue date: | 12/11/1986 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-861205, NUDOCS 8612180155 | |
| Download: ML20211N174 (33) | |
Text
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December 11, 1986 For:
The Comissioners From:
T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK EMDING DECEMBER 5, 1986 A summary of key events is included as a convenience to those Comissioners who may prefer a condensed version of this report.
Contents Enclosure Administration A
Nuclear Reactor Regulation B
Nuclear Material Safety and Safeguards C
Inspection and Enforcement D
Nuclear Regulatory Research E
General Counsel F*
International Programs G
State Programs H
Resource Management I*
Analysis and Evaluation of Operational Data J*
Small & Disadvantaged Business Utilization & Civil Rights K*
Regional Offices L*
CRGR Monthly Reports M*
Executive Director for Operations N*
Itens Addressed by the Commission 0
Meeting Notices P
Proprietary or Other Sensitive Information (Not for Q
external distribution)
- No input this week.
/
i T. A. Re ssistant for Operations 8612180155 861211 PDR COMMS NRCC Office of the Executive Director NEEKLYINFOREPT PDR for Operations
Contact:
T. A. Rehm, E00 492-7781
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4 HIGHLIGHTS OF WEEKLY INFORMATION REPORT 4
WEEK ENDING DECEMBER 5, 1986 Seabrook, Unit 1 On October 7, 1985, a memorandum and order was issued that authorized the issuance of an operating license allowing fuel loading and precriticality testing at Seabrook, Unit fl. The Attorney General of the Commonwealth of Massachusetts (AG) appealed the Board's order. The AG's appeal raised a single question: Whether 10CFR50.33(g) requires that utility applicants file a radiological emergency response plan for the entire plume exposure pathway EPZ for the facility before any license maybe issued. The applicants have not submitted such a plan for~the portion of the EPZ that lies within the Commonwealth of Massachusetts. TheSeacoastAnti-PollutionLeague(SAPL) joined the AG's appeal.
In addition to endorsing the AG's single appellate claim, SAPL advanced additional discrete arguments of its own.
On November 29, 1986, the Board denied the appeal of the AG. The affirmance or reversal of the Board's October 7, 1986, order must await the disposition of the other issues raised by SAPL.
Three Mile Island - Unit 2 GPU Nuclear has submitted plans for the Post Defueling Monitored Storage j
(PDMS) plant configuration. The licensee's submittal outlines the plans to place the plant in a secured, monitored, maintained configuration that assures the protection of the public health and safety during an extended storage period. Defueling and shipment of the damaged fuel offsite will be completed prior to entering the PDMS phase. PDMS wiif also include removal of water from plant systems; packaging of all radioactive waste and either shipment offsite or placement in safe storage; reduction of radiation levels to allow continued monitoring, maintenance, and inspections; and implementation of NRC approved PDMS technical specifications. The licensee expects to be ready to enter PDMS at the end of the third quarter in 1988. The licensee's proposal does not include any conclusion on the ultimate disposition of the facility.
A Sequoyah Fuels Restart Sequoyah Fuels (SFC) is currently operating the entire plant with the exception of fluorination. SFC has started wanning up the fluorire cells preparatory to starting UF Fluorination is currently scheduled to start by December 8,6 production.1986, but if there is no trouble in starting up the fluorine cells, fluorinetion could start as early as December 4 or 5.
The filling of UF cylinders is scheduled to begin about Decerrber 10. Although there have been minor equipmpent problems that have been encountered as each piece is started up, SFC feels that they have not had as many problems as they anticipated.
Chinese Technical Delegation A Chinese technical delegation will be visiting active and inactive uranium processing sites during mid-December. The Division of Waste Management and the Uranium Recovery Field Office are providing support to the Office of I'nternational Programs for this tour. The delegation also plans to visit EPA and DOE offices during this time.
DECEMBER 5, 1986 i
OFFICE OF ADMINISTRATION Week Ending December 5, 1986 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT
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STATUS OF REQUESTS Initial Appeal of Request Initial Decision Ltrryovers, 1985 181 15 Received, 1986 835 233 Granted 637 100 Denied 211 85 Pending 168 63 ACTIONS THIS WEEK Received J.W. Lowenstein, Requests a copy of the proposal for RFP #610257.
American Office (86-825)
H. G. Brack, Requests NRC radiological surveillance reports for,all Center for nuclear power plants in the U.S.
Biological s
Monitoring, Inc.
(86-826)
Lyle Graber, Requests copies of enclosures to three specified re' cords.,'
NUS Corporation (86-827)
(NRCemployee)
Requests records regarding herself.
(86-828)
(NRC employee)
Requests specified records regarding her security (86-829) clearance.
Sarah Powell, Requests lists of NRC's publications with the offices that i
v Interactive sponsor or publish the publications, i
Features (86-830)
Lynn Connor, Requests a copy of the Preliminary Safety Information Doc-Search Document submitted about October 1, 1986, for the advanced.
Associates HTGR.
(86-831)
CONTACT: Donnie H. Grimsley 492-7211 DECEttBER 5, 1986 ENCLOSURE A 1
s
2 0
Received, Cont'd Charles Anderson, Requests a complete set of the 17 attachments referenced Shaw, Pittman, in the March 24, 1983 memorandum for Bernard Snyder Potts & Trowbridge from Lake Barrett,
Subject:
Summary of TMIPO Site
,3 (86-832)
Actions Related to the Polar Crane / Parks' Issues.
Robert Savini, Requests a list of all medical licensees who are Lixi, Inc.
authorized to use Gadolinium-153 on their license.
t (86-833)
Joan Bready, Requests a copy of SECY-86-349, " Balance of Plant."
KMC, Inc.
(86-834)
Mac McGraw, Requests a copy of the contract and bid abstract for Mac-Air, Inc.
ADM-87-206.
(86-835)
Billie Garde, APPEAL TO THE COMMISSION for the release of six records Government denied in their entirety and portions of 25 records in Accountability NRC's October 30, 1986 response to a request for records Project generated or prepared by Victor Stello since his (86-A-225-86-80) appointment as Acting Executive Director for Operations.
(86-A-226-86-82) 1 (86-A-227-86-126)
(86-A-228-86-127)
(86-A-229-86-131)
(86-A-230-86-166)
(86-A-231-86-201)
(86-A-232-86-209)
(86-A-233-86-263)
Granted Billie Garde.
In response to a request for all records regarding Government depositions of all NRC personnel deposed in the litigation Accountability between Houston Light and Power and Brown and Root, Inc.,
Project over the South Texas Project, made available 216 (85-378) records.
Informed the requester that additional records subject to this request are already available at the PDR.
Dorothy Dickey, In response to a referral from the D0J of four records Public Utilities used, reviewed or relied upon in the D0J's investigation Commission, State of Pacific Gas and Electric's role in siting, licensing of California and constructing the Diablo Canyon nuclear power plant, (86-699) informed the requester that three records are already available at the PDR. Made available a copy of one record.
Diane Curran, In response to a request for records that relate to the Harmon & Weiss cadweld problem referred to in paragraph 8 of the (86-756)
October 8, 1986 letter from S. Long of NRC to R. Harrison of the utility regarding the Seabrook nuclear power plant, made available eight records.
Informed the requester that additional records subject to this request are already available at the PDR.
DECEMBER 5, 1986 ENCLOSURE A
y n
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e 3
Granted, Cont.'d 4
Steven Sholly, In response to a request for five categories of records MHB Technical related to a September 9-12, 1986 symposium, " Chemical Associates Phenomena Associated with Radioactivity Releases During (86-776)
Severe Nuclear Plant Accidents," at the American Chemical Society meeting, made available 29 records.
Lyle Graber, In response to a request for a copy of the enclosures to NUS Corporation the August 21, 1986 letter to C.O. Woody from J. Nelson Grace (86-791) regarding SALP reports for Turkey; Point and St. Lucie nuclear power plants, made available a copy of the requested records.
Beth Yearsin, In response to a request for a copy of the abstract of MilMark Services bids / proposals, DD Form 1501, for RS-0RM-86-293, made (86-801) available one record.
Informed the requester that one record subject to this request is already available at the PDR.
Lyle Graber, In response to a request for a copy of the enclosure NUS Corporation to an NRC letter dated July 24, 1986, regarding a request (86-803) for additional information on the Vermont Yankee spent fuel pool expansion, made available a copy of the requested record.
John Erb, In response to a request for reports on adverse reactions, Paul B. Episcope, malfunctions, or physician or patient complaints or Ltd.
problems regarding the Model 9000 pulse generator and lead (86-805) model 6917 distributed by Medtronics, Inc., made available 15 records.
Marshall Sunderland In response to a request for a copy of a record providing (86-819) the name of the qualified and designated person approved by NRC to hold the title of Radiation Safety Officer for the VA Medical Center, Gainesville, Florida, from January 1984 through September 1984, made available two records.
Donald Schlemmer, In response to a referral from the DOS of two records Government regarding a request for records pertaining to the Accountability Philippine nuclear power plant, made available the two Project records.
(86-822)
Denied t
Scott Klion, In response to a request for records dated from July 26, General Electric 1984, to present between Mozart Ratner and any NRC Company employee, made available 48 records.
Informed the (85-461) requester that additional records subject to this request are already available at the PDR.
Denied 01 records in their entirety, release of which could reasonably be expected to interfere with an ongoing enforcement proceeding.
I DECEMBER 5, 1986 ENCLOSURE A
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4 Denied, Cont'd Billie Garde.
In response to a request for all interim and final reports Government and records developed in connection with the Comanche Peak Accountability harassment and intimidation panel report issued November 4, Project 1985, made available 59 records.
Informed the requester (85-799) that additional records subject to this request are already available at the PDR. Denied portions of three records, disclosure of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process, constitute an unwarranted invasion of personal privacy, and reveal identities of confidential sources.
Neil Numark, In response to a request for three categories of records International regarding post-TMI operating licenses, made available Energy Associates 19 records.
Informed the requester that additional i
Limited records subject to this request are already available at (86-416) the PDR.
Denied portions of one record, disclosure of which would result in a clearly unwarranted invasion of personal privacy.
Mozart Ratner, In response to a request for copies of 13 specified Mozart G. Ratner, inspection reports, with related responses and replies P.C.
to responses and notices of violation, and two information (86-704) notices regarding GE's facility in Wilmington, North Tu olina, made available 14 records.
Informed the requester that three additional records subject to this request are already available at the PDR. Denied portions of 17 records containing proprietary information.
Charles Barnes In response to a request for three specified records cited (86-723) on page 42 of NUREG-1198, made available two records.
Denied portions of one record, disclosure of which would result in a clearly unwarranted invasion of personal privacy.
Linda Bauman, In response to a request for all records and investigations i
Government regarding the concerns of a named individual about the Accountability Fermi nuclear power plant, made available five records.
Project Denied records in 0IA files, disclosure of which would (86-736) interfere with an enforcement proceeding.
Steven Sholly, In response to a request for three categories of recorc's MHB Technical related to NUREG-ll50, denied all records subject to the Associates request, disclosure of which would tend to inhibit the (86-762) open and frank exchange of ideas essential to the deliberative process.
DECEMBER 5, 1986 ENCLOSURE A
5 Denied, Cont'd Barry Scanlon In response to a request for a list of all (86-783) communications between NRC and Psychiatric Diagnostics Laboratories of America, Inc., (PDLA) or Stauffer Chemical Company since January 1, 1985, particularly with regard to changes in management or ownership of PDLA, made available 17 records. Denied portions of one record, disclosure of which would result in a clearly unwarranted invasion of personal privacy.
Billie Garde, In response to an APPEAL TO THE ED0 for the release of Government the denied portions of four records regarding a request Accountability for records generated in connection with 01 investigation Project 4-84-039 on the Comanche Peak nuclear power plant, (86-A-200-86-379) continued to deny these records, release of which would constitute a clearly unwarranted invasion of personal privacy.
DECEMBER 5, 1986 ENCLOSURE A
WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING DECEMBER 5, 1986 RFP ISSUED RFP No.: RS-NMS-87-005
Title:
" Federally Funded Research and Development Center (FFRDC)"
==
Description:==
Establish a Center for Nuclear Waste Regulatory Analysis (CNWRA) to conduct technical assistance and research for NRC in support of its regulatory program as related to activities under the Nuclear Waste Policy Act (NWPA) for a high-level radioactive waste disposal system.
Period of Performance: Five years Sponsor: Office of Nuclear Material Safety and Safeguards Status: RFP issued on November 25, 1986.
Proposals due on February 10, 1987.
RFP No.: RS-0IE-87-121
Title:
" Training Course in the Medical Uses of Byproduct Material"
==
Description:==
Provide NRC materials inspectors with hands-on experience and classroom presentations in three general safety areas for the use of byproduct material: radiological health and safety procedures, personnel training and experience and facilities and equipment.
Period of Performance:
Four years Sponsor: Office of Inspection and Enforcement Status: RFP issued on December 1, 1986.
Proposals due December 30, 1986.
PROPOSAL UNDER EVALUATION RFP No.: RS-ADM-87-173
Title:
" Career Counseling"
==
Description:==
Provide career counseling services to the NRC Headquarters and related support for the NRC Regional Offices.
Period of Performance: Two years Sponsor: Office of Administration Status: The competitive range has been established and negotiations are scheduled for the week of December 8, 1986.
DECEMBER 5, 1986 ENCLOSURE A
OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending December 5, 1986 Waterford 3 Waterford Steam Electric Station, Unit 3, owned and operated by Louisiana Power and Light Company, will shut down at midnight on November 26,1986 for its first refueling. The outage, which is scheduled to be 60 days duration, will be devoted to refueling operations, maintenance, station modifications and periodic surveillances. Waterford 3 has operated at an 85% capacity 4
factor sir.ce it was placed into commercial operation on September 24, 1985.
The plant is scheduled to be back on the grid January 25, 1987.
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Seabrook, Unit 1 On October 7,1986, a memorandum and order was issued that authorized the issuance of an operating license allowing fuel loading and precriticality testing at Seabrook, Unit #1. The Attorney General of the Commonwealth of Massachusetts (AG) appealed the Board's order. The AG's appeal raised a i
single question: Whether 10CFR50.33(g) requires that utility applicants file a radiological emergency response plan for the entire plume exposure pathway EPZ for the facility before any license maybe issued. The applicants have not submitted such a plan for the portion of the EPZ that lies within the Commonwealth of Massachusetts. The Seacoast Anti-Pollution League (SAPL) joined the AG's appeal.
In addition to endorsing the AG's single appellate claim, SAPL advanced additional discrete arguments of its own.
On November 29, 1986, the Board denied the appeal of the AG. The affirmance or reversal of the Board's October 7, 1986, order must await the disposition of j
the other issues raised by SAPL.
Haddam Neck Plant On November 30, 1986, Connecticut Yankee Atomic Power Company experienced increased leakage from the seal leak-off of the Loop 1 stop valve while attempting to manually restart the Loop 1 reactor coolant pump (RCP).
Procedures require that the loop stop valve must be closed prior to attempting a reactor coolant pump restart.
Following closure of the Loop 1 stop valve, and restart of the RCP, RCS leakage increased to a value of 18-20 gpm which required the licensee to declare an unusual event. The leakage path was 1
later identified as leakage through a small hole or crack in a check valve body in the gland steam leak-off pipe. The loop stop valve was reopened (backseated) and the leakage reduced to previous levels. The licensee is shutting down to replace the check valve prior to return to power.
DECEMBER 5, 1986 ENCLOSURE B i
. Turkey Point Plant, Units 3 and 4 Florida Power and Light Company informed the staff during a Turkey Point Plant meeting discussing USI A-44, " Station Blackout," that they were considering modifications to the onsite safety-related power distribution systems which would include additional diesel generators. The existing design at the Turkey Point Plant has two diesel generators which are shared between the two units.
The licensee's staff has stated that funding has been approved for the procure-ment of additional diesel generators and the engineering for the design modifi-catfor.s. The proposed modifications will be submitted for NRC review and approval within 6 to 9 months.
Millstone - 1 The main 24/345 kv step-up transformer failed at 9:21 PM November 30, 1986.
The auxiliary electrical load was picked up automatically by the Reserve Station Service Transformer. Although the rod select feature of the auto-matic load rejection capability functioned properly, an electrical fault associated with the transformer failure resulted in turbine overspeed and a reactor trip. The plant was subsequently brought to a cold shutdown con-dition. The plant will remain shutdown for about three weeks (estimated startup on December 22,1986) while the damaged GE transformer is replaced with the onsite W spare transformer.
River Bend Station On November 29, 1986, River Bend Station (RBS) went critical after an extended outage which began on October 4.
RBS is currently operating at 100% rated power. In October 1986, the licensee informed the SEC that in the absence of rate relief, the licensee might have to seek protection from creditors under the bankruptcy laws. Since that time, the Texas Public Utility Commission has declared River Bend to be in comercial operation, retroactively to June 16, 1986. While a declaration of commercial operation is not rate relief, l
per se, it is a necessary step to placing River Bend Station in the rate base in the State of Texas.
However, on December 2, 1986, the Louisiana PUC rejected a request for an emergency rate relief for the licensee for $100 million.
Three Mile Island - Unit 2 GPU Nuclear has submitted plans for the Post Defueling Monitored Storage (PDMS) plant configuration. The licensee's submittal outlines the plans to place the plant in a secured, monitored, maintained configuration that assures the protection of the public health and safety during an extended storage period. Defueling and shipment of the damaged fuel offsite will be completed prior to entering the PDMS phase.
PDMS will also include removal of water DECEMBER 5, 1986 ENCLOSURE B
from plant systems; packaging of all cdioactive waste and either shipment offsite or placement in safe storage;. eduction of radiation levels to allow continued monitoring, maintenance, and inspections; and implementation of NRC approved PDMS technical specifications. The licensee expects to be ready to enter PDMS at the end of the third quarter in 1988. The licensee's proposal does not include any conclusion on the ultimate disposition of the facility.
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DECE!! DER 5,1986 ENCLOSURE B
NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT FOR DECEMBER 1 - 7, 1986 1.
DEFUELING Visibility in the core region is 3 to 4 feet. A video of the top of the core surface was performed and is being evaluated. The top of the core surface was probed to provide a topographic contour.
2.
ENVIRONMENTAL MONITORING US 2nvironmental Protection Agency (EPA) sample analysis results show that TMI site liquid effluents are in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
TMI water effluents are sampled from the station (Units 1 and 2) discharge and analyzed by EPA. Ganum spectrum analyses of the seven daily composited samples (November 15 - 22, 1986) indicated no TMI-2 related radioactivity.
EPA's gamma spectrum analysis of the NRC's TMI outdoor air sample for November 25 - December 4,1986 showed no reactor related radioactivity.
The Lancaster water works intake composited seven daily samples (November 16 - 22, 1986) gamma spectrum analyzed by EPA showed no reactor related radioactivity.
3.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Reclamation of Defueling Water Cleanup System (DWCS) filters continues.
Fuel handling building ventilation systen modifications are almost complete. Testing will begin this week.
Pre-operational tests of the DWCS and Sediment Transfer systems are in progress.
Fuel canister preparation for shipment is in progress.
Installation of an ultraviolet light / ozone device for water treatment has been placed on hold for industrial safety studies.
4.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Request numbers 49, 51, 52, and 54.
Recovery Operations Plan Change numbers 31 and 33.
Solid Vaste Facility Technical Evaluation Report.
Heavy Load Safety Evaluation Report, Revision 3.
Disposal of Processed w ter Report.
a Safety Evaluation Report for Use of Plasma Arc Cutting Torch.
Ex-Vessel Defueling Safety Analysis.
DECEMBER 5, 1986 ENCLOSURE B
2
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Post Defueling Monitored Storage Proposal.
Temporary Reactor Vessel Filtration System Safety Evaluation Report, Revision 3.
5.
MEETING The Advisory Panel for the Decontamination of Three Mile Island Unit 2 will meet on December 10, 1986 from 7:00 PM to 10:00 PM at the-Holiday Inn, Center City, Harrisburg, PA. The meeting will be open to the public.
At this meeting, the Panel will receive a briefing from the licensee on their recent proposal for the Post Defueling Monitored Storage of TMI-2. Members of the public will be given the opportunity to address the Panel.
Persons desiring to speak before the Advisory Panel are requested to contact Mr. Thomas Smithgall at 717-291-1042, or write him at 2122 Marietta Avenue, Lancaster, PA 17603.
DECEMBER 5, 1986 ENCLOSURE B
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending December 5, 1986 Uranium Enrichment i
On December 3 and 4,1986, staff members of NMSS, RES and SEC met with DOE and Oak Ridge National Laboratory (ORNL) officials to discuss centrifuge en-richment technology and visit centrifuge development and test facilities at ORNL. The purpose of the visit by the NRC staff members was to obtain back-ground information and familiarization on key safety, safeguards, environmental and classification aspects of the technolony in view of recent inquiries and interest regarding private enrichment endesvors.
Sequoyah Fuels Restart Sequoyah Fuels (SFC) is currently operating the entire plant with the exception of fluorination. SFC has started warming up the fluorine cells preparatory to Fluorination is currently scheduled to start by starting UF December 8,6 production.
1986, but if there is no trouble in starting up the fluorine cells, fluorination could start as early as December 4 or 5.
The filling of UF cylinders is scheduled to begin about December 10. Although there have been minor equipmpent problems that have been encountered as each piece is started up, SFC feels that they have not had as many problems as they anticipated.
Chinese Technical Delegation A Chinese technical delegation will be visiting active and inactive uranium processing sites during mid-December. The Division of Waste Management and the Uranium Recovery Field Office are providing support to the Office of International Programs for this tour. The delegation also plans to visit EPA and DOE offices during this time.
Advance Notice of Proposed Rulemaking The Advance Notice of Proposed Rulemaking (ANPRM) concerning disposal of radio-active wastes that contain sufficiently small quantities, or low concentrations, of radionuclides that their disposal does not need to be regulated as radioactive, was published for comment on December 2, 1986. The ANPRM notes that generic rulemaking might provide a more effective and efficient means of dealing with disposal of wastes below NRC regulatory concern. Generic rulemaking would supplement the earlier Policy Statement issued in response to a mandate in Section 10 of the Low-Level Radioactive Waste Policy Amendments Act of 1985 (Public Law 99-24C).
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DECEMBER 5, 1986 ENCLOSURE C
2 Meeting with Atomic Industrial Forum (AIF)
Division of Waste Management staff will be meeting with the Atomic Industrial Forum's (AIF) Subcommittee on High-Level Radioactive Waste on December 16, 1986 to discuss current activities in the high-level waste repository program area, as well as AIF comments on NRC's Q-List Generic Technical Position. Staff from DOE's Office of Geologic Repositories will also attend the meeting and will brief AIF on the current status of activities at the three sites recommended for site characterization.
Meeting with DOE On December 9 and 10, 1986, NRC and DOE will hold a public meeting at DOE Headquarters in Washington, D.C., to discuss the Defense Waste Processing Facility at Savannah River, South Carolina. The purpose of this meeting is to get up-to-date infonnation on the status of the vitrification process to prepare for review of DOE's Site Characterization Plan and DOE's Glass Qualification and Testing Programs. The topics for discussion will include the vitrification process, process control programs, sampling programs and glass tests and data.
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DECEl1BER 5, 1986 Ef1 CLOSURE C
Office of Inspection and Enforcement Items of Interest Week Ending December 5, 1986 1.
Items of Interest a.
Hatch Spent Fuel Pool Leak j
On December 3, 1986, with Unit 2 in cold shutdown following a refuel-ing outage, approximately 140,000 gallons of water leaked from the spent fuel pool due to a loss of air to inflatable seals in the transfer canal seismic gap. Approximately 80,000 gallons drained to a swampy area adjacent to the plant. There have been no direct dis-charges to the Altamaha River. A Region II team, including regional supervision, resident, radiological effluents and chemistry, and environmental inspectors, have been deployed to the site.
2.
Civil Penalties Paid None.
3.
The following Sionificant Enforcement Actions were taken during the past week:
a.
A Notice of Violation and Proposed Imposition of Civil Penalty was issued to Gamma Diagnostic Laboratories (Attleboro, MA) in the amount of $5,000. This action is based on several violations involving failure to properly secure or maintain control of licensed material and improper health physics practices.
(EN 86-86) 4.
The following IE Information Notices and Bulletins were issued during the past week:
a.
IE Information Notice No. 86-21, Supplement 1, Recognition of American Society of Mechanical Engineers Accreditation Program for N Stamp Holders was issued to all nuclear power facilities holding an operating license or a construction permit, b.
IE Information Notice No. 86-98, Offsite Vedical Services was issued to all nuclear power reactor facilities holding an operating license or a construction pcrmit.
5.
The following IE Preliminary Notifications were issued during the past week:
a.
PN0-I-86-95, Northeast Nuclear Energy Company (Millstone 1),
Unscheduled Shutdown Greater Than 72 Hours.
b.
PNO-I-86-96, Connecticut Yankee Atomic Power Company (Haddam Neck),
Unscheduled Shutdown Greater Than 48 Hours.
DECEMBER 5, 1986 ENCLOSURE D
c.
PNO-II-86-90, Georgia Power Company (Hatch 1&2), AIT Dispatched to Investigate Leak From Spent Fuel Pools.
d.
PN0-III-86-139, Northern States Power Company (Prairie Island), Bomb 4
Threat.
e.
PNO-III-86-140, Norland Instruments (Fort Atkinson, WI), Sealed Radiation Source Found in Rental Car.
f.
PNO-III-86-141, Toledo Edison Company (Davis-Besse), Preparation for Restart.
g.
PNO-V-86-88, State of Oregon, Radioactive Waste Drums Washed Upon Washington and Oregon State Beaches.
h.
PNS-V-86-07, Southern California Edison Company (San Onofre),
Unauthorized Manipulation of Plant Components.
f DECEMBER 5, 1986 ENCLOSURE D
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OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending December 5, 1986 Semiscale The Semiscale facility, now in a cold shutdown status, provided data over the i
last 12 years for improved understanding of PWR transient responses as well as data for code development and assessment. These codes are often used for NRC assessment of operating reactor transients as well as forming the basis for reactor design evaluations.. The Semiscale FS test series, which consisted of both feedwater line and steam line break experiments, provided experimental data for these risk significant transient types.
In conformance with 4
i requirements of the International Code Assessment Program, a series of con-figuration reports for the FS series has been issued and distributed to code developers and users.
In addition to providing detailed information on the physical and configuration characteristics of the Semiscale facility, the report contains calculated physical parameters, test-related letters and logs, drawings, operating specifications, pretest analyses, quick look reports, instrumentation uncertainty reports and heat loss characterization reports.
]
This information is essential for assuring the effective use of the test results in the regulatory process.
BWR Damaged Fuel Test DF-4 in ACRR j
i Damaged-Fuel test DF-4 was successfully performed in the ACRR test reactor at Sandia National Laboratories on November 21. The purpose of this test was to provide information on the effects of the boron-carbide control blades and the Zircaloy channel box walls upon fuel damage, core melt progression and hydrogen generation in BWR core-uncovery accident sequences for use in mechanistic modeling in BWR severe-accident codes. Core melt progression and hydrogen generation were identified as major areas of uncertainty in NUREG-0956.
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Sicnificant questions exist as to whether the flow integrity in the BWR channel l
box is preserved and whether blockages are formed inside the fuel bundle to cut off steam flow and hydrogen generation. Also significant are questions on the I
j effects of the boron-carbide upon core-melt progression and upon system j
chemistry and aerosol behavior. No previous integral in-pile data address these questions.
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DECEMBER S, 1986 ENCLOSURE E t...
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In DF-4 a test assembly containing a simulated BWR stainless-steel-clad boron-carbide control blade in the gap between two adjacent Zircaloy channel box walls with two rows of clad fresh fuel rods on either side of the walls (14 fuel rods in total) was exposed to conditions of a BWR core-uncovery transient.
An extensive thermocouple array provided information on temperatures and on the relocation of molten material, and optical cinematography provided information on configuration changes, aerosol formation, and some surface temperatures.
The very preliminary results indicate that DF-4 will provide important information on BWR in-vessel severe-accident behavior. As predicted in pre-test analysis, during the autocatalytic oxidation transient of the Zircaloy by the steam (that generates hydrogen), the control-blade and gap temperatures in DF-4 outran the fuel temperatures, so that Zircaloy melting, relocation, and apparent failure of the cha'nnel box wall occurred well before melting and relocation of the fuel cladding. The peak temperatures measured by tungsten-rhenium thermocouples in the control-blade gap were about 2600 K, and the peak thermocouple temperatures in the fueled region were about 2400 K, with the actual surface temperatures about 100 to 200 K higher. All the high-temperature tungsten-rhenium thermocouples remained functional throughout the test.
4 Very preliminary thermocouple data indicate that there was early downward relocat.on in the contrcl-blade gap of low melting material (molten stainless I
steel at 1700 K or a boron-carbide, stainless steel eutectic at 1500 K) with later substantial relocation of higher melting Zircaloy at 2100 K among the fuel rods and in the gap. The thermocouples indicated that heating of the i
j Zircaloy by steam oxidation continued after relocation. There was no cut off l
of the steam flow by blockage formation to stop the Zircaloy oxidation and hydrogen generation.
Definitive results of the DF-4 test will follow detailed analysis of the dita and x-radiography and post irradiation examination of the test fuel bundle, i
4 i
i i
i DECEMBER 5, 1986 ENCLOSURE E
i 3
Pressurized Thermal Shock Experiment 2 On Tuesday, Nov. 25, 1986, at approximately 3:30 p.m., the second pressurized thermal shock experiment, PTSE-2, was conducted by the personnel of the Heavy Section Steel Technology program at Oak Ridge National Laboratory. The purpose of the test was to further validate the PTS Rule, 10 CFR 50.61, to assure that the lowered, Charpy-upper-shelf energy for the irradiated steel in some of our older reactor vessels was adequate to survive a PTS accident.
The PTSE-2 test was comprised of a test vessel,1 meter in diameter and 2 meters long. The test material was a 2-1/2 Cr. 1 Moly steel heat treated so that its toughness properties simulated an irradiated low-upper-shelf Charpy-V energy weld found in some of our older reactors. A sharp flaw, a meter long and 15 mm deep, oriented in the axial direction, was embedded in the test material. The vessel was emplaced in the test facility, and heated uniformly to a temperature of approximately 285'C. The test facility provided for both pressurization and cooling using an ethanol water mixture at approximately
-20*C.
As the test began, but before the initiation event occurred, the Warm Prestress phenomenon was encountered again, and unequivocally demonstrated.
(Warm Prestress occurs when a crack, previously at a higher temperature and stress level, must be stressed to an even higher level at a lower temperature in order for crack initiation to occur; importantly, this scenario parallels the events under PTS accidents and provides protection against failure.) Subsequently pressurewasraisedtoovgrcomethewarmprestressandatastressintensityof approximately 140 MPa (m) the flaw initiated. The crack-jump arrested at a depth of 45 mm (30% of wall thickness) and at an estimated crack arrest value of 240 MPa (m)I, significantly above the ASME Code limit value of 220 MPa (m)I, and much above the upper shelf fracture toughness level as estimated from Charpy and J test values.
IC It is interesting to note that the same test material behaved quite differently during the Wide Plate Experiments WP-2.1 & 2.2.
In these cases no stable crack arrest was achieved at relatively low elastic stress.
It is presently thought that the difference in constraint conditions between the Wide Plate Tests and the PTSE's will eventually explain the difference in behavior.
If this is true then the behavior of this type of material (low-upper-shelf) in the actual reactor vessels in the event of a PTS scenario, leading to crack initiation may be more prone to inhibiting vessel failure than was originally believed.
Detailed post test analyses have begun and data will be announced as developed.
DECEMBER 5, 1986 ENCLOSURE E
I l
4 November 14, 1986 Earthquake in Taiwan h
At 21 20" 04.6s G.M.T., Taiwan encountered a major earthquake. The earthquake measured 7.0 on the Richter Scale and had a focal depth of 6 Km.
It occurred offshore about 30 Km east of the city of Hualien. The epicenter was located 23.98'N, 121.33*E. This earthquake is approximately 84 Km from the Lotung where the Soil Structure Interaction experiment is located (cooperative research program NRC, EPRI, and Taiwan Power). The duration of this earthquake was estimated to be from 40 to 50 seconds. More than 200 aftershocks were felt over the next 2 days.
The city of Taipei is about 130 Km from the epicenter. The major damage observed was the collapse of a 3-story market building, a 15-degree tilt to a 12-story office building, and cracks in the walls and staimells of a school building.
At the Chinshen Nuclear Power Plant Units 1 and 2 located 150 Km from the epicenter, the maximum acceleration measured at the containment base mats was 0.029 There was no observed damage to the plants which operated through the earthquake. These plants are founded on finn rock. These plants are well instrumented and Taiwan Power Company intends to conduct a postearthquake study of these facilities and will make the results available to the NRC. Since very few operating nuclear power plants have been subjected to earthquake loadings, this information could be extremely valuable to the NRC and utilities operating nuclear power plants.
Jasanese and the Brookhaven National Laboratory Sign an Agreement to Test a )WR Primary Coolant Loop Model On Monday, December 1, 1986, Mr. Takashi Fujii, President of the Japanese Nuclear Power Engineering Test Center (NUPEC) and a team of Japanese visited the Brookhaven National Laboratory (BNL) to sign an agreement with BNL to conduct high level seismic tests on a half size PWR Primary Coolant Loop System on the NUPEC shaker table at Tadotsu (world's largest).
G. Arlotto and J.
Richardson of the NRC were in attendance at the signing. This is a cooperative test funded by the Japanese Ministry of International Trade and Industry (MITI),theNRC,andtheElectricPowerResearchInstitute. BNL will work with NUPEC to carry out these tests in 1988. The tests are part of an agreement between MITI and the NRC (signed by Chairman Zech in August 1986) to carry out vibration tests at Tadotsu. Results of the tests will be used to validate piping response computer codes in the inelastic range.
DECEMBER 5, 1986 ENCLOSURE E
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING DECEMBER 5, 1986 Foreign Visitors On Monday Mr. M. Hayashi, President of the Japanese Power Reactor and Nuclear Fuel Development Corporation, made a courtesy call on Chairman Zech.
Commissioner Bernthal and H. Faulkner of IP also met with Mr. Hayashi.
On Wednesday Mr. T. Fujii, President of the Nuclear Power Engineering Test Center (NUPEC) in Japan, made a courtesy call on Chairman Zech.
Mr. Fujii was in the United States to sign an agreement between the Brookhaven National Laboratory and NUPEC which implements the seismic cooperation outlined in the umbrella NRC-Japan Ministry of International Trade and Industry Agreement which Chairman Zech signed in Tokyo in August. This research will take place at the Tadotsu facility in Japan which contains the largest " shaker table" in the world. Several RES staff members also met with Mr. Fujii to discuss seismic research cooperation.
During this week the International Atomic Energy Agency (IAEA) installed, tested, and ran at its computer center in Vienna, Austria, the source term code package which Chairman Zech presented to IAEA Director General Blix last September. Two Battelle Columbus employees conducted an informal in-house workshop on the source term package for IAEA employees.
d
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DECEMBER 5, 1986 ENCLOSURE G
1 i
0FFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING DECEMBER 5, 1986 Low-Level Radioactive Waste Compacts Steve Salomon and Rosetta Virgilio, OSP, attended a one-day workshop on December 3, 1986, sponsored by the National Conference of State Legislatures in conjunction with the U. S. Department of Energy on the States' Responsibility and Authority under the Low-Level Radioactive Waste Policy Act Amendments of 1985. Dr. Malcolm Knapp, Division of Waste Management, presented the NRC perspective on the development and regulation of low-level waste disposal sites.
There were approximately 40 representatives from States, industry and press.
The workshop preceded the annual State / Federal Assembly held at the Hyatt Regency-Capitol Hill, December 4-5, 1986.
National Conference of State Legislatures Rosetta Virgilio OSP, attended the annual State / Federal Assembly held this year at the Hyatt Regency-Capitol Hill, December 4-5, 1986. Waste and trans-portation issues were of particular interest to NRC.
On the afternoon of December 4,1986, a resolution was proposed by a State representative from New Mexico at the National Conference of State Legislatures' State / Federal Assembly Committee Meeting on Environment, Natural Resources and Energy, that would urge Congress to reorganize the NRC to create a single
.administratorship. The resolution stated this was necessary because the NRC
- has been criticized in the past and there is a need to inspire public confidence.
The Committee voted to hold over decision on the resolution until their upcoming August 1987 meeting, thereby allowing Committee members more time to discuss the issue.
State Program Review The New Hampshire radiation control program will be reviewed the week of December 8, 1986, by Region I.
State of Texas Enforcement Action I
Iso-Tex, Inc. is a waste broker licensed by the Texas Radiation Control Program.
l A number of serious violations had occurred on which Texas had taken various enforcement actions. On November 17, 1986, a judgment was signed in the 200th District Court of the' State of Texas against Iso-Tex, Inc. The Court ordered Iso-Tex, Inc. to pay $629,900 in civil penalties for past violations.
Penalties are calculated based on a combination of violations, dollar amounts, and length of time violations existed. The current license authorizes storage i
only, therefore, Iso-Tex, Inc. is no longer authorized to receive waste.
DECEMBER 5, 1986 ENCLOSURE H
-,-,_x-_r,____.
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ITEMS ADDRESSED BY THE COP 91ISSION - WEEK ENDING DECEMBER 5,1986 A.
STAFF REQUIREMENTS - BRIEFING IN ADVANCE OF PUBLICATION OF DRAFT NUREG-1150 (SOURCE TERM), 2:00 P.M., WEDNESDAY, NOVEMBER 19, 1986, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) - Memo SECY to V. Stello, EDO dated 12/1/86 The Commission was briefed by the staff on the status of its source term effort as it relates to publication of draft NUREG-1150.
The Commission requested the staff to address during its quarterly source term briefing, scheduled for December 17, 1986, the following items:
i Resources needed for program completion.
Realistic schedule for program completion.
1 If additional funding would provide a quicker resolution to j
the direct containment heating and similar outstanding technicci issues.
Chairman Zech requested the staff to submit a paper, prior to the January 15, 1987, meeting, outlining how policy matters related to implementing the safety goal policy, severe accident policy, source term efforts, and other important issues, such as j
the lessons learned from Chernobyl, are being integrated into a consistent overall program.
The staff stated that its upcoming Commission paper would address commissioner Asselstine's question as to whether the research program canceled due to funding constraints would have reduced any of the uncertaintics in the results of NUREG-1150.
Commissioner Carr referenced page 11-9 of draft NUREG-1150 which l
stated that the staff would develop and propose guidelines for l
Commission approval which will be used as a basis for determin-ing whether a level of safety ascribed to a plant is consistent with the safety goal policy.
He requested the staff to provide its schedule for submitting that paper.
The staff recommended to reserve time in mid-January 1987, to brief the Commission on the final version of draft NUREG-1150, just prior to its publication.
i l,
(Subsequently, SECY tentatively scheduled the briefing for l
January 15, 1987.)
i DECEtiBER 5, 1986 ENCLOSURE O L
B.
STAFF REQUIREMENTS - DISCUSSION /POSSIBLE VOTE ON DAVIS BESSE RESTART, 10:00 A.M.,
FRIDAY, NOVEMBER 21, 1986, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) - Memo SECY to V. Stello, EDO dated 12/1/86 The commission was briefed by the licensee and the staff on the readiness to restart Davis Besse.
The following representatives of the licensee participated in the discussion:
- J. Williams, Senior Vice President, Nuclear 1
Toledo Edison Company
- B. Ginn, CEO Centerior Energy Corporation
- P. Smart, President, Toledo Edison Company
- J. Weed, Director of Systems Engineer
- P. Hildebrandt, Group Director Engineer
- S. Jain, Director of Nuclear Engineering j
- W. O'Connor, Assistant Plant Manager, Operations
- S. Smith, Assistant Plant Manager, Maintenance The Commission voted 5-0 to permit the staff to authorize the restart of Davis Besse after the staff has made appropriate findings and determinations.
C.
STAFF REQUIREMENTS - BRIEFING ON INITIATIVES TO IMPROVE MAINTENANCE PERFORMANCE, 10:00 A.M., THURSDAY, NOVEMBER 20m 1986, COMMISSIONERS' CONFERENCE ROOM, D.C.
0FFICE (OPEN TO PUBLIC ATTENDANCE? (SECY-86-316) - SECY Memo to V. Stello, EDO l
dated 12/2/86 The'Commissio.n was briefed by the staff on the results of Phase I of the Maintenance and Surveillance Program Plan (MSPP).
The i
l purpose of the Phase I study was to describe the current status I
of maintenance in the industry by surveying existing maintenance practices and assessing their effectiveness.
The staff recommended that the Commission:
1.
Direct the staff to prepare and submit a proposed NRC policy statement on maintenance; and 2.
Note the EDO has directed NRR and IE to implement Phase II of the MSPP as it relates to assessing the effectiveness of industry's recent maintenance initiatives.
DECEMBER 5, 1986 ENCLOSURE 0
Chairman tech requested the staff to Do what it can to get results soon.
Examine international as well as domestic program for insights.
Concentrate on balance of plant maintenance needs.
Review if the frequency of on-line testing and surveillance should be reduced.
Commissioner Asselstine expressed concern that NRC's approach to j
maintenance is reactive and that a more proactive approach is i
needed.
Commissioner Carr highlighted an industry problem of high maintenance personnel turnover and noted that steps must be taken to ensure the availability of experienced personnel for maintenance activities.
Commissioner Carr also noted that a "fix it now" philosophy is needed.
Commissioner Roberts cautioned the staff that conclusions drawn from a historical review of licensee event reports must be carefully reviewed since reporting requirements changed during the time period examined by the staff.
D.
STAFF REQUIREMENTS - PERIODIC MEETING WITH NUMARC, 2:00 P.M., THURSDAY, NOVEMBER 20, 1986, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC AIItNDANCE) - SECY Memo for the Record dated 12/5/86 The Commission met with the Nuclear Utility Management and Human z
l Resources Committee (NUMARC) for a status briefing on the following committee activities:
access authorization, training accreditation, fitness for duty, maintenance, operator requali-fication, station blackout, containment integrity, safety goals, j
decay heat removal, check valve reliability, 10 CFR 50.59, plant life extension, and the upcoming restructuring of the nuclear power industry associations, Presentations by NUMARC were made by the following representatives:
i l
- James H. Miller, Jr., Chairman NUMARC Steering Committee l
President, Georgia Power Company
- Warren H. Owen, Vice Chairman 1
NUMARC Steering Committee i
Executive Vice President l
Engineering, Construction and Production Group Duke Power DECEMBER 5, 1986 ENCLOSURE 0
- Bruce Kenyon, Chairman NUMARC Security Working Group Senior Vice President of Nuclear Pennsylvania Power and Light Company
- John H. Ferguson, Chairman NUMARC Technical Subcommittee President and CEO Virginia Power Commissioner Asselstine urged NUMARC to place high priority on maintenance efforts and suggested an early meeting for NUMARC to present its plans.
Therewerenostaffrbquirementssetatthismeeting.
E.
STAFF REQUIREMENTS - BRIEFING ON IMPROVING EFFECTIVENESS OF INITIAL STARTUP PROGRAMS, 10:00 A.M., FRIDAY, NOVEMBER 14, 1986, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) - tiemo SECY to V. Stello, EDO dated 12/4/86 The Commission
- was briefed by the staff on the need to improve effectiveness of initial startup programs at the nation's nuclear power plants.
Chairman Zech requested the staff to provide another briefing on initial startup programs after the operational data has beer.
carefully correlated and conclusions drawn.
The briefing should include the data from which the conclusions are based.
Commissioner Bernthal requested the staff to review plant operating data and determine if recently licensed large plants have a tendency to experience more problems than older designs, such as two-loop Westinghouse PWRs.
He also requested that staff provide the Commission with a better summary of the data used in reaching its conclusions, and that those data be correlated with other indicators, such as plant capacity factors, AEOD plant studies, and SALP ratings.
- Commissioner Asselstine was not present.
l l
l DECEMBER 5, 1986 ENCLOSURE 0 l
1 4
! h DECEMBER 5, 1986 b?
lG DOCKET APPLICANT /
l8 DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 1
i 12/9/86 Room P-412 Discuss the SPDS testing program NRC Staff / Licensee E. A. Licitra l
8:30 a.m.
Phillips Building results (morning) and Tech. Spec. Staff / EG&E j
change requests & Palo Verde Unit
{
3 licensing submittals 12/9/86 50-267 Room TBA Discuss Fort St. Vrain's Emer-NRC/PSC/EG8G C. S. Hinson 9:00 a.m.
Bethesda, MD gency Electrical Power System Design Compliance with the Single Failure Criterion j
12/9/86 50-260 MNBB - Rs. 6507 Discussion of the Design Baseline NRC/TVA M. J. Campagnone 9:00 a.m.
Verification Program / Configuration 2:00 p.m.
Phillips Rs. P422 Control Management Program to be implemented at BFN-2 prior to restart 12/9810/86 50-451 Room 6110/MNBB 12/9 Discuss IP's responses to staff NRC/EG&G Idaho /IP B. Siegel j
9:00 a.m.
Room P-114 comunents and questions on the
{
Phillips Bldg. 12/10 Inservice Test Program submitted by IP in February 1985 for Clinton Power Station 12/9-11/86 50-412 Beaver Valley Unit 2 Meeting with the applicant to NRC/DLC P. S. Tam 4
l 9:00 a.m.
(SEG) Building develop the Technical Specifica-Shippingport, PA tion (TS) for Beaver Vcliey Unit
, m
) M 2
i 5 i E i
Copies of sununaries of these meetings will be made publicly available and placed in the respective docket file (s) in the NRC and local public document rooms l
A summary of these meeting notices can be obtained by calling 492-7424
- 5 DECEMBER 5, 1986 9
w DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 12/10/86 50-341 Suite 1301 Discuss the results of studies NRC/NRR/ Deco /
J. J. Stefano 9:00 a.m.
Landow Bldg.
conducted by DECO and DECO pro-R=gion III posed resolution of issues per-taining to failure experienced with Femi-2 emergency diesel generators 12/10/86 50-259/
Room P-412 Discuss Fire Protection Program NRC/TVA M. Grotenhuis 9:00 a.m. &
260, 296 Phillips Building Management & plans for Appendix 1:00 p.m.
R-Brown: Ferry Electrical Design Review Calculations Room P-422 Discuss the following items NRC/B&WOG W. A. Paulson 12/10/86 1:00 p.m.
Phillips Building regarding the B&W Owners Group review of the Integrated Control 1
System /Non-Nuclear Instrumenta-tion 12/10-11/86 50-424 Vogtle Plant Unit 1 Pemit NRC management to assess NRC/ Georgia Power M. A. Miller 2:30 p.m.(Wed)
Waynesboro, GA the operational readiness of Company 8:00a.m.(Thurs)
Vogtle Unit 1 12/10-12/86 50-275 Pacific Gas & Elec.
Discuss with Pacific Gas and NRC/PG&E H. Schierling 8:15 a.m.
50-323 Conference Room 2L Electric the current status 45 Freemont Street of the soil structure interaction i
San Francisco, CA (SSI) efforts of the Long Tern m
l M
Seismic Program for the Diablo fy Canyon E
m
(
Copies of sunmaries of these meetings will be made publicly available and,placed in the respective docket file (s) l in the NRC and local public document rooms l
A summary of these meeting notices can be obtained by calling 492-7424
l T
M i
n NRR MEETING NOTICES
- i DECEMBER 5, 1986 j
9 f
DOCKET APPLICANT /
y DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 12/11/86 50-295 Room 6110 Discuss Zion's Detailed Control NRC/ Ceco J. Norris 9:00 a.m.
50-304 MNBB Room Design Review 12/11/86 50-261 Room AR 5203 Discuss the incorporation of Fire NRC/CP&L G. Requa 9:00 a.m.
Air Rights Building Protection Technical Specifications into the H.B. Robinson-2 FSAR i
12/11/86 50-213 Suite 208 Discuss interim and long tem plant NRC/N.U.
F. M. Akstulewicz i
10:00 a.m.
Landow Building modifications to resolve ECCS i
concerns following small break LOCAs 12/11/86 50-316 Westinghouse Office Discuss the heavy loads and crane NRC/ Indiana &
D. Wigginton i
12:30 p.m.
4901 Fairmont Ave.
requirements for the auxiliary Michigan Electric Bethesda, MD building to facilitate the steam Company generator replacement and travel near the spent fuel pool Room P-114 DECO presentation of projected NRC/NRR/ DECO J. J. Stefano 12/11/86 50-341 1:00 p.m.
Phillips Building service life of newly installed REGION III turbine bypass lines l
12/11/86 Room P-110 Discuss the status of the BWOG NRC/CEOG W. A. Paulson 1:00 p.m.
Phillips Building Owners Group activities including (1) charging pump reliability; 9
(2) CEOG Davis-Besse action plan; i
P and (3) tasks described in a
]
{
August 6, 1986 letter from CEOG 4
"o Copies of sunnaries of these meetings will be made publicly available and p1pced in the respective docket file (s) l in the NRC and local public document rooms A summary of these meeting notices can be obtained by calling 492-7424
-\\-
o E
NRR MEETING NOTICES
- l g
DECEMBER 5, 1986 l
I g
DOCKET APPLICANT /
g DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 12/15-16/86 50-369 McGuire Site Discuss events resulting from NRC/ Duke Power Co.
D. Hood j
9:00 a.m.
50-370 Cornelius, NC procedures
]
12/18/86 50-261 Room P-110 Discuss Pressurized Thermal Shock NRC/CP&L/EPRI/
G. Requa 10:00 a.m.
Phillips Building (PTS) concerning the H.B. Robinson Unit 2 plant l
I i
i i
i i
c.
r e
9 f
os s
p 8
i 55 i
m l
r-Copies of sunenaries of these meetings will be made publicly available and,placed in the respe,ctive docket file (s) l in the NRC and local public document rooms f f j
'j
- y. -
j A summary of these meeting notices can be obtained by calling 492-7424 e
V i,
,~
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NMSS MEETING NOTICES FOR WEEK ENDING:
12/5/86 t
Divisirn of Full Cycle and Material Safaty h!
DOCKET ATTENDEES /
Eg'DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT A
- o n
,; 12/17/86 M-44 Willste To discuss NuPac concrete cask R. Haelsig, et al.
Roberts 88 9:00 am 5th floor topical report submittal.
(Nuclear Packaging, Inc.)
conf room J. Roberts (FC)
.g 12/23-30/86 40-8027 Gore, OK To participate in oversight for restart of Sequoyah Fuels.
L. Gordon (FC)
Gordon/ Crow Division of Waste Management DATE LOCATION PURPOSE ATTENDEES CONTACT 12/16/86 Washington, DC Meeting with the Atomic Industrial J. Linehan J. Linehan Forum Subcommittee on High-Level S. Bilhorn Waste, discuss current high-level R. Boyle waste repository program activities, R. Browning Q-List Generic Technical Position W. Lilly comments, and status of activities at three sites recommended for site characterization.
Division of Safeguards 05 hh None
!5 m
"O l
REGION III MEETING NOTICES
!R n
'.I WEEK ENDING:
12/20/86 9
y
'g DOCKET ATTENDEES /-
,g DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 12/17/86 50-461; Rcgion III SALP Illinois Power Company J. G. Keppler 1:00 p.m.
50-462 Clinton 1
i I
4 5
E R
9 I
l