ML20211P871
| ML20211P871 | |
| Person / Time | |
|---|---|
| Issue date: | 02/20/1987 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | NRC COMMISSION (OCM) |
| References | |
| WIR-870220, NUDOCS 8703020446 | |
| Download: ML20211P871 (22) | |
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vs February 25, 1987 For:
The Comissioners From:
T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INF0PMATION REPORT - WEEK ENDING FEBRUARY 20, 1987 A sumary 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*
Items Addressed by the Comission 0
Meeting Notices P
Proprietary or Other Sensitive Information (Not for Q
external distribution)
- No input this week.
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B703020446 G70220 T. A. Rehr,-AssTstant for Operations PDR COMMS NRcc Office of the Executive Director WEEKLYINFOREPT PDR for Operations
Contact:
T. A. Rehm EDO 492-7781
HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING FEBRUARY 20, 1987 Arkansas Nuclear One Unit 1 At 1:50 a.m. on Monday, February 9,1987, a main feedwater pump tripped.
The unit successfully completed an ICS runback to 45% power without tripp-ing the reactor protection system. Reactor pressure increased to 2290 psi.
which was close to the former high pressure trip set point of 2300 psi.
This trip set point was raised during the last refueling outage to 2355 psi.
The new high pressure set point of 2355 psi. probably saved the plant from an automatic reactor trip. The cause of the trip of the main feedwater pump was the trip cf the main feedwater pump high pressure lube oil pump.
The lube oil pump tripped because of a bearing failure. The licensee believes that the bearing was degrading over a period of time and operating at a low threshold pressure such that the redundant pump could not establish pressure in time to prevent the trip of the main feedwater pump. The licensee repaired the lube oil pump and returned to power.
Byron 1 On Saturday, February 14,1987, Byron 1 shutdown for its first refueling outage.
In addition to refueling, the licensee intends to perfonn eddy current inspections of the steam generator tubes, shotpeen the stean generator tubes, remove pipe whip restraints and jet deflectors and perform volumetric examination of the turbine. Startup, is projected for April 20, 1987.
Shipment of Reactor Vessel On February 18, 1987, the staff met with representatives of the Department of Energy (DOE) to discuss the packaging for the ship;aent of the Shippingport Reactor Vessel and Neutron Shield Tank from Shippingport, PA to Hanford, WA.
The 00E intends to submit an application for package certification later this year. The package will weigh approximately 930 tons and is about 18 feet in diameter by 43 feet long and primarily would be transported by barge.
Items of Interest A Demand for Information was issued to the United States Air Force (USAF).
This action was based on an Americium-241 contamination incident inside a radioactive work storage building at Wright-Patterson Air Force Base (WPAFB); the incident resulted in the activation of the Air Force Radio-logical Assistance Team and the decontamination of the facility at a cost of approximately $.5M to date.
No notification was provided to the NRC as required under 10 CFR 20.403(b)(3) and (b)(4); further, it was determined that WPAFB possessed more Americium-241 than authorized and in a form not authorized. The above raises a question as to whether the USAF will provide complete, accurate, and timely reports to the NRC as required.
Accordingly, the Demand was issued to obtain inforration to judge whether the USAF license should be modified or other enforcement action should be taken.
(EN87-09)
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0FFICE OF ADMINISTRATION i
Week Ending February 20, 1987 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers,1986 170 53 Received, 1987 113 10 Granted 70 3
Denied 23 4
Pending 190 56 ACTIONS THIS WEEK l
Received Lynne Bernabei, Requests, on behalf of her client,14 categories of Newman, Sobol, records regarding TVA plants.
Trister & Owens (87-103)
J.G. Fcrguson, Requests records on recent radioactive leakages at the The FAMUAN Crystal River nuclear power plant.
(87-104)
Ellen Law, Requests copies of hRC's response to 0MB's Circular A-ll International budget call for data on 43A, 43B and 43C.
Data Corporation (87-105)
(Anindividual Requests records maintained in the NRC on himself.
requesting information on himself)
(87-106)
(Anindividual Requests recoros maintained in the NRC on herself.
requesting information on herself)
(87-107)
W.F. Haskins, Requests a copy of Contract number likC-04-75-183.
Newport News Shipbuilding (87-108)
CONTACT:
Donnie H. Grimsley 492-7211 FEBRUARY 20, 1987 ENCLOSURE A J
2 Received, Cont'd Charles Ondash, Requests copies of records related to (1) the final rule DEV0NRUE on fees published at 51 Fed. Reg. 33224-33231, (2) the (87-109) proposed rule on fees published at 51 Fed. Reg). 24078-24090, (3) SECY-86-258, (4) NUREG-1100, and (5 the September 17, 1986 memo from J. Holloway to I. Bailey.
R.K. Buckles, Requests copies of transcripts of Connission meetings NUS Corporation on April 22, 1983, January 31, 1984, and July 2, 1984, (87-110) regarding Diablo Canyon and the Secretary's November 4, 1983 limited distribution memorandum regarding Diablo Canyon.
John Menz, Requests copies of specified records.
Simpson Thacher
& Bartlett (87-111)
Lynne Bernabei, Requests, on behalf of her clients, five categories of Newman, Sobol, records regarding TVA plants.
Trister & Owens (87-112)
Steven Sholly, Requests five categories of records related to IDCOR MHB Technical reports and Individual Plant Evaluations.
Associates (87-113)
Granted Poul Leventhal, In response to a request for copies of records pertaining Nuclear Control to possible shipment of nuclear materials allegedly Institute from French Polynesia in 1979-1980 via European ports (87-66) to the Middle East involving named individuals and companies, informed the requester that the NRC has no agency records subject to this request.
Harry Hammitt.
In response to a referral from the OMB of one record The Washington regarding F0IA fees and fee waivers, made available a copy Monitor, Inc.
of this record.
(87-101)
Ellen Law, In response to a request for copies of HEC's response to International OMB's circular A-11 buoget call for data on 43A, 43B and Data Corp).
43C, informed the requester that ccpies of records pertaining (87-105 to 43A and 43B are already available in the PDR in file FOIA-87-39. Also, informed the requester that the NRC did not have to prepare a schecule 43C.
FEBRUARY 20, 1987 ENCLOSURE A J
3 Denied Linda Bauman, In response to a request for copies of all recoros Government related to the May 30, 1986 letter from Thomas Westerman Accountability to TUGC0 regarding 4-86-A-109, made available six Project recoros. Denied seven records in their entirety, (86-726) disclosure of which would interfere with an enforcement proceeding. Denied portions of two records, disclosure of which would result in a clearly unwarranted invasion of personal privacy.
Billie Garde.
In response to an APPEAL TO THE COMMISSION for the Government release of OIA files regarding a request for records Accountability concerning a named individual's concerns at the Fermi Project nuclear power plant, continued to deny these records, (86-A-234-86-736) disclosure of which would interfere with enforcement proceedings.
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FEBRUARY 20, 1987 ENCLOSURE A I
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0FFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending February 20, 1987 Reaver Valley Unit 2 The applicant submitted a request for exemption from GDC-4 for certain austenitic steel piping in some of the balance-of-plant (B0P) systems.
This exemption would be the first ever granted to any plant applying
" leak-before-break" technology to 80P piping.
. Arkansas Nuclear One Unit 1 At 1:50 a.m. on Monday, February 9,1987, a main feedwater pump tripped.
The unit successfully completed an ICS runback to 45% power without tripp-ing the reactor protection system. Reactor pressure increased to 2290 psi.
which was close to the former high pressure trip set point of 2300 psi.
This trip set point was raised during the last refueling outage to 2355 psi.
The new high pressure set point of 2355 psi. probably saved the plant from an automatic reactor trip. The cause of the trip of the main feedwater pump was the trip of the main feedwater pump high pressure lube oil pump.
The lube oil pump tripped because of a bearing failure. The licensee believes that the bearing was degrading over a period of time and operating at a low threshold pressure such that the redundant pump could not establish pressure in time to prevent the trip of the main feedwater pump. The licensee repaired the lube oil pump and returned to power.
Seabrook Unit 1 On February 11, 1987, Seabrook, Unit I was in Mode 4 preparing to enter Mode 3.
At 3:10 p.m., the licensee discovered a breach in containment integrity when they found the 1" globe valves open on the personnel doors to the containment equipment hatch. These valves are opened to equalize pressure in order to open the personnel hatches to allow personnel access into the chamber leading into and out of the containment. When the personnel hatches are closed (as they were in this case), these valves are interlocked to close with the hatches. A failure in the inter 1ccking mechanism was found.
This condition placed the unit into the Technical Specification 3.0.3 limited condition of operation action statement. Accordingly operators initiated plant cooldown.
Since it was a breach in containment, an unusal event event was declared at about 3:30 p.m. and notification procedures for an unusal event was followed.
The investigation of the interlocking mechanism failure is continuing.
FEBRUARY 20, 1987 ENCLOSURE B
, Byron 1 On Saturday, February 14,1987. Byron 1 shutdown for its first refueling outage.
In addition to refueling, the licensee 'ntends to perform eddy current inspections of the stean generator tubes, shotpeen the stean generator tubes, remove pipe whip restraints and jet deflectors and perform volumetric examination of the turbine. Startup, is projected for April 20, 1987.
Palo Verde Unit 3 On February 19, 1987, NRR issued an extension to the Palo Verde. Unit 3 construction permit to December 31, 1987. The applicant had filed a timely application for renewal of the construction permit, which would have expired on November 1,1986.
Currently, the plcnt is expected to receive its low power operating license in March 1987.
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i FEBRUARY 20, 1987 ENCLOSURE B
0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Endina February 20. 1987 Shipment of Reactor Vessel On February 18, 1987, the staff met with representatives of the Department of Energy (DOE) to discuss the packaging for the shipment of the Shippingport Reactor Vessel and Neutron Shield Tank from Shippingport, PA to Hanford, WA.
The DOE intends to submit an application for package certification later this year.
The package will weigh approximately 930 tons and is about 18 feet in diameter by 43 feet long and primarily would be transported by barge.
S_hieldalloy A representative of Shieldalloy met with representatives of the Division of Fuel Cycle and Material Safety on February 13, 1987.
Discussions were held on the additional information that is needed in order to complete the environmental assessment for license renewal.
Discussions were also held on the long term options available for the disposition of the slag material that is currently being stored on the Shieldalloy site.
Babcock & Wilcox, Apollo. Pennsylvania On February 17, 1986, G. H. Bidinger met with B&W representatives to review the draft license renewal document.
Significantly, additional process and facility information will have to be added to the safety demonstration.
The draft document was returned to B&W.
Meetina at Atomic Industrial Forum On Thursday, February 19, 1987, Sher Bahadur (NRC) and Jim Michael (EPA) will make a presentation on the Mixed LLW issue for the Atomic Industrial Forum Subcommittee on LLW.
Other NRC presentations will include Below Regulatory Concern (Kitty Dragonette), Waste Forms and Classification (Tom Jungling), and Low-Level Radioactive Waste Policy Amendments Act Program (Larry Pittiglio).
Meetina with Outside Group Maxine Dunkelman will present NRC's position on wastes that are below regula-tory concern to the Midwest Interstate Low-Level Radioactive Waste Commission on February 26, 1987 in Columbus, Ohio.
FEBRUARY 20, 1987 EflCLOSURE C
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2 IAEA Inspection at Turkey Point #4 On February 13, 1987, an NRC representative accompanied two IAEA inspectors to the Turkey Point #4 power reactor in Florida City, Florida to reestablish the spen fuel inventory.
The overall evaluation of the inspection was satisfactory.
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FEBRUARY 20, 1987 EtlCLOSURE C
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Office of Inspection and Enforcement Items of Interest Week Ending February 20, 1987 1.
Items of Interest A Demand for Information was issued to the United States Air Force (USAF).
This action was based on an Americium-241 contamination incident inside a radioactive work storage building at Wright-Patterson Air Force Base (WPAFB); the incident resulted in the activation of the Air Force Radio-logical Assistance Team and the decontamination of the facility at a cost of approximately $.5M to date.
No notification was provided to the NRC as required under 10 CFR 20.403(b)(3) and (b)(4); further, it was determined that WPAFB possessed more Americium-241 than authorized and in a form not authorized. The above raises a question as to whether the USAF will provide complete, accurate, and timely reports to the NRC as required.
Accordingly, the Demand was issued to obtain information to judge whether the USAF license should be modified or other enforcement action should be taken.
(EN 87-09) 2.
Civil Penalties Paid None.
3.
The following Significant Enforcement Actions were taken during the past week:
a.
A Notice of Violation and Proposed Imposition of Civil Penalties was issued to Professional Consultants, Inc. (Missoula, MT) in the amount of $1,000. This action was based on multiple violations, a number of which were repeat violations from the previous inspection.
(EN 86-72A) b.
A Notice of Violation and Proposed Imposition of Civil Penalties was issued to Marcus Daly Hospital (Hamilton, MT) in the amount of $1250.
This action was based on several violations indicating a breakdown in the management oversight and control of its licensed activities.
(EN87-03) c.
A Demand for Information was issued to the United States Air Force.
(See Items of Interest).
4 The following IE Information Notices and Bulletins were issued during the past week:
a.
IE Information Notice No.86-106, Supplement 1, Feedwater Line Break was issued to all nuclear power reactor facilities holding an operat-ing license or a construction permit.
FEBRUARY 20, 1987 ENCLOSURE D
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The following IF Preliminar.y Notifications were issued during the past
. week:
I a.
PNO-I-87-11, GPU Nuclear Corporation (Oyster Creek), Unplanned i
Shutdown.
b.
PNO-I-87-12, New York Power Authority (FitzPatrick) Worker Extremity Overexposure.
t c.
PHO-II-87-11A, Virginia Electric and Power Company (Surry 182),
Preparations for Restart (Update).
i d.
PNO-III-87-22, Detroit Edison Company (Fermi) Authorization for Fermi to Increase Power Level to 50 Percent.
i e.
PNO-III-87-23, Toledo Edison Company (Davis-Besse), Two Electricians In.iured.
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PNS-V-87-01, Sacramento Municipal Utility District (Rancho Seco),
Unusual Event - Homemade Security Drawing Found on Site.
l g.
PNS-V-87-01A, Sacramentu Municipal Utility District (Rancho Seco),
Unusual Event - Homemade Security Drawing Found on Site (Update).
h.
PNS-V-87-02, Sacramento Municipal Utility District (Rancho Seco),
l Unusual Event - Receipt of Threatening Telephone Call.
i.
PNO-V-87-10A, U.S. Testing Company Inc. (San Leandro, CA), Possible Overexposure of Two Radiographers (Update).
.i.
PNO-V-87-12A, Arizona Nuclear Power Project (Palo Verde 2), Emergency i
Diesel Fire During Outage (Update),
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PNO-V-87-13 U.S. Testing Company Inc. (San Leandro, CA), Confirm-t atory Action Letter to U.S. Testing company 1.
PNO-V-87-14, Pacific Gas and Electric Company (Diabic Canyon 2),
l Shutdown for Greater Than 48 Hours.
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,i FEBRUARY 20, 1987 ENCLOSURE D
1 0FFICE OF Nt! CLEAR REGULATORY RESEARCH Items of Interest Week Ending February 20, 1987 Thermal / Hydraulic Technical Integration Center (TIC)
One of the functions of the TIC is to resolve priority issues. One such issue is to establish the differences in demands on plant safety systems and on operating personnel for three comparable abnormal transients in representative plants for each PWR vendor. The results of these comparisons will be integrated with other study results to develop NRC's reevaluation of B&W plant performance which should be completed during June 1987. The CE plant chosen for this study is Calvert Cliffs.
In order to assure the quality of plant modeling for this analysis, the contractor (INEL) will visit the Calvert Cliffs station on February 12-13, 1987 to review and discuss modeling details with plant operations staff. The Westinghouse plant chosen for this study is H. B.
Robinson.
INEL will visit the Robinson plant on February 19-20, 1987.
2D/30 I
The Upper Plenum Test Facility (UPTF) which is a full scale test facility located at Mannheim, Federal Republic of Germany, has been disassembled for facility modification and repair including U.S. instrument repair. The facility modification is in two areas:
1) installation of smaller water injection pipes in the core simulator so that the liquid entrainment from the cure can be more accurately simulated, and 2) installation of a steam / water i
separator feedback system in three intact hot legs to simulate the hot leg phenomena more accurately.
In addition, a pump simulator damaged during the 4
recent ECC bypass test will be repaired.
All of the degraded and failed U. S. instruments have been taken cut of the UPTF vessel. They are being replaced with new or refurbished instruments.
A quick examination of ell 14 degraded drag bodies (DB's) and 4 breakthrough detectors (BTD's) indicated that the majority of these degraded instruments did not show any apparent sign of degradation. On appearance, they looked just normal. Only two dray bodies shcwed a small rupture in the cables. All of the degraded DR's and BTD s (except 2 DB's and 1 BTD) will be taken to ORNL for detailed examination to identify the cause of degradation or failure so that 4
i fixes can be planned for the next yearly outages. Two DB's and one BTD were left with the Germans for their examinations. All of the facility modification and repair are scheduled to be corrpleted by the end of March 1987, and the testing is to resume in April.
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FEBRUARY 20, 1987 ENCLOSURE E m.-
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2 OTSG Experiments Auxiliary feedwater in B&W Once Through Steam Generators (OTSG) is injected as a spray at the top of the tube bundle.
Flow characteristics of this spray, e.g., depth of penetration into the tube bundle and counter current flow with upflowing steam at the tube support plates is not well understood or modeled in existing codes. Consequently the primary-to-secondary coolant system heat transfer, a very important characteristic during both overcooling and undercooling transients, e.g., steam line break or feedwater line break, is also not well understood. NRC has initiated an OTSG experimental program which consists of full-scale single tube and multitube sector models of the OTSG.
The data from this program will provide information for improving the code modeling of OTSG for B&W plants.
The adiabatic single tube OTSG test fixture is in operation at the INEL.
Characterization data has been completed and has verified that the air flow capacity is sufficient to obtain complete flooding at the tube support plate under maximum expected auxiliary feedwater flow rates. Operation of the test fixture to obtain flooding data is currently in progress.
ROSA-IV The ROSA-IV system performs large-scale thermal-hydraulic tests under a cooperative prcgram with the NRC. The test results are used to help the NRC in resolving licensing and safety issues and in verifying scaling parameters in NRC safety analysis codes.
A 0.5% steam generator U-tube break sxperiment was conducted by the Japan Atomic Energy Research Institute (w iRI) on January 28, 1987. The experiment was successfully completed and labeled as SB-SG-01. Analysis of the natural circulation tests ST-NC-01 (5% power) and ST-NC-02 (2% power) continues at INEL. TRAC assessment work, using the ST-NC-02 experiment results continues at LANL. Good agreement between the data and the code have been shown until the 85% inventory level. Good agreement was obtained using the 3-tube steam generator model. This included the observation of steam generator recirculation.
A proposed power decay curve for the ROSA-IV Large Scale Test Facility (LSTF) was calculated by INEL using the basic approach that was taken by the Semiscale proiect. Another proposed power decay curve for the LSTF was calculated by LANL usino TRAC. The difference be. tween INEL and LANL's pcwer decay curve is small, but a large difference between JAERI and both INEL and LANL's curves was found. The JAERI's LSTF power decay curve is deemed overconservative.
FEBRUARY 20, 1987 ENCLOSURE E
OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING FEBRUARY 20. 1987-AIF Conference On February 12, 1987, Robert Wood spoke before the Atomic Industrial Forum's Conference on Insurance and Indemnity Issues, San Diego, California, summarizing current NRC rulemaking activities and other actions on decommissioning, property insurance, financial assurance for materials licensees, Extraordinary Nuclear Occurrence (EN0), and Price-Anderson.
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FEBRUARY 20, 1987 ENCLOSURE H
i OFFICE OF RESOURCE MANAGEMENT ITEM OF INTEREST Week Ending February 20, 1987 NUREG/CR-4012 VOL. 2, " Replacement Eneray Costs for Nuclear Electricity-Generating Units in the United States" The Cost and Statistical Analysis Staff has recently issued NUREG/CR-4012 Vol. 2, " Replacement Energy Costs for Nuclear Electricity-Generating Units in the United States: 1987-1991." This report provides short-term replacement energy cost estimates for 116 nuclear reactors expected to be operational during the 1987-1991 study period.
The replacement energy cost estimates were derived from probabilistic production cost simulations of power pools, and as such, are more accurate than general rules-of-thumb commonly relied on by the staff. These cost estimates should have wide application to a large number of regulatory impact analyses ongoing at the NRC.
Copies of this report are available from the NRC's Document Control Branch, Distribution Section.
ENCLOSURE I JANUARY 20, 1987
ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING FEBRUARY 20, 1987 l
A.
STAFF REQUIREMENTS - BRIEFING BY GPUNC ON STATUS OF TMI-2 CLEANUP, 10:00 A.M.,
FRIDAY, FEBRUARY 13, 1987, COPNISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC AIItNDANCE) - Memo SECY to V. Stello dated 2/20/87 i
The Commission was briefed by GPUNC on the status of the TMI-2 cleanup efforts, projection of future activities, and the status of TMI-1.
The Commission was also briefed by the staff on its oversight activities.
The following GPUNC representatives briefed the Commission:
- William G. Kuhns Chairman of the Board and CEO of GPU
- Philip R. Clark President and CEO of GPUNC
- Edward E. Kinter Executive Vice President, GPUNC
- Frank R. Standerfer Director, THI-2
- Robert Q. Marston Chairman of the Safety Advisory Board for TMI-2 Commissioner Bernthal urged the staff to carefully monitor the TMI-2 cleanup efforts to assure that the NRC obtain all of the data which could be used in NRC's source term ef forts. (NRR)
Chairman Zech requested the Secretary to arrange a Commission briefing by DOE to discuss the funding and research efforts relating to the TMI-2 cleanup.
FEBRUARY 20, 1987 ENCLOSURE O
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A NRR 18EETING NOTICES
- E FEBRtfARY 20, 1987 8
lis 00CKET APPLICANT /
$ CATE/ TIE NtstER LOCATION PURPOSE ATTENDEES NRR CONTACT f
2/23/87 50-315/
American Electric To discuss preliminary findings NRC/AEP/SAI/Comex/
D. L. Wigginton l
1:00 p.m.
316 Power Service Corp.
on Detailed Control Room Design D.C. Cook /W/Essex Review and perform a pre-imple-mentation audit. Please note:
Portions of the meeting / audit may be held in restricted areas of the plant; arrangements for attend-ance should be made before hand.
For information, call 614-223-2040.
2/24/87 50-315/
- eerican Electric To discuss preliminary findings NRC/AEP/SAI/Comex/
D. L. Wigginton 8:00 a.m.
316 Power Service Corp.
on Detailed Control Room Design D.C. Cook /W/Essex Review and perform a pre-imple-mentation audit. Please note:
Portions of the meeting / audit may be held in restricted areas of the plant; arrangements for attend-ance should be made before hand.
For information, call 614-223-2040.
2/25/87 50-315/
American Electric To discuss preliminary findings NRC/AEP/SAI/Comex/
D. L. Wigginton 8:00 a.m.
316 Power Service Corp.
on Detailed Control Room Design D.C. Cook /W/Essex Review and perform a pre-imple-mentation audit. Please note:
Portiens of the meeting / audit may r.,
M be held in restricted areas of 5
the plant; arrangements for attend-E ance should be made before hand.
A For information, call 614-223-2040.
j v
Copies of sursaries of these meetings will be rade publicly available and placed in the respective docket file (s) in the NPC and local public document rooms A suerurv cf these teeting notices can be obtained by calling 492-7424
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NRR MEETING NOTICES
- l FEBRUARY 20, 1987 5E l
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DOCKET APPLICANT /
5 OfTE/ TIME NUMBER LCCATION PURPOSE ATTENDEES NRR CONTACT j
2/26/87 50-315/
Donald C. Cook To discuss preliminary findings NRC/AEP/SAI/Comex/
D. L. Wigginton 8:00 a.m.
316 Nuclear Plant on Detailed Control Room Design D.C. Cook /W/Essex Review and perforin a pre-imple-mentation audit. Please note:
Portions of the meeting / audit may be held in restricted areas of the plant; arrangements for attend-ance should be made before hand.
For infc:mation, call 614-223-2040 2/26/87 50-528/
Room P-412 To discuss resolution of staff NRC/APS E. A. Licitra 9:00 a.m.
529/530 Phillips Build.
coseents on E0Ps.
2/26/87 50-219 Room P-422 An information exchange meeting NRC/GPUN J. N. Donohew 1030 a.m.
Phillips Build.
to discuss GPUN's plans for a program to mitigate the corrosion of the drywell shell which was discussed in the staff's evaluation dated December 29, 1986.
2/27/87 50-443 Room P-110 To discuss the proposed changes NRC/PSNH-NHY V. Nerses 20:00 a.m.
Phillips Build.
to the Seabrook, Unit 1 Standard Technical Specifications (TS),
future TS improvements and other g
low power licensing issues.
S 3/19/87 50-369/
Room P-110 To discuss tentative requests NRC/ Duke Power Co.
D. Hood E 8:30 a.m.
370/413/ Phillips Build.
for additional information 5
regardinc proposed removal of the RTD bypass manifold.
o Copies of sunmaries of these meetings will be nade publicly available and placed in the respective docket file (s) o in the NRC and local public document rooms A sumary of these reeting notices can be obtained by calling 492-7424
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N*tSS EETING NOTICES A
FON EEK EISING: 2/20/87 E
Division of Fuel Cycle and Material Safety E
ATTENDEES /
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DOCKET DATE/ TIE NisSER LOCATION PURPOSE APPLICANT Inc CONTACT m
2/23-24/87 Willste To discuss requirements for large Reps fa letSS.
Hickey Bldg.
irradiators.
Region I & III.
IE. AE00 & SP 3/2/87 Washington, Meeting at DOE re: Radiation R.Cunningham(FC)
Cunningham
' 1:00-3:00 DC Protection Matters.
R. Hauber (IP)
Reps of DOE.
State Dept..
EPA, FDA & INTLO 3/4/87
- Willste, To discuss NRC actions related to R. Cunningham (FC)
Cunningham 2:00 Room 562 authorized reprocessing in the L. Rouse (FC) past.
T. Rothschild (OGC)
Mr. Deuster (AGftS, consultant in the AGits B&W suit) 3/4/07 030-Glen Attend Enforcement Conference re:
P. Vacca (FC)
Vacca 9:00 00394 Ellyn, IL Cleveland Clinic Foundation.
Reps of Licensee
& Region III 3/9-12/87
- Paris, To Chair meeting of CRPPH dealing R. Cunningham (FC)
Cunningham France with radiological issues related to l
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19155 MEETIIIS IIOTICES E
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.o DOCKET ATTEISEES DATE/ TIME IIt318ER LOCATI0ff PURPOSE APPLICAIIT 4 WMT 3/2-3/87 Surry Co., VA Post licensing evalu-S.McKay, VEPC0
- 0. Smith ation for dry cask C.Loffman.Surry storage at VEPCO's Sorry Power Station to establish generic licensing review criteria Division of Waste Management rione b
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.s February 23,1987' RII MFETING NOTICE q
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ATTENDEES /
E CCCKET CATE/ TIME NdMBER LDCATI0h PURPOSE APPLICANT NRC CONTACT U
02/25/87 Homesteao, FL Enforcement Conference Same as above Ernst
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Crystal River, FL g
o.6 3/2-3/3/87 Jensen Beach, FL/
Chairman Zech touring Regional Administrator Grace Miami, FL St. Lucie/ Turkey Point and selected regional sites and resident staff members 3/3/87 RII Office Fundamentals of Inspection Selected RII staff members Course 3/6/87 RII Office Enforcement Conference Licensee Regional Grace 1:00 p.m.
Duke Power Company - Oconee Administrator and selected RI! staff members 3/12/87 HQs Office Vogtle Full Power Commission Comunissioners, Licensee 2:00 p.m.
representatives and RII staff members 3/13/87 RII Office W. W11gus, FPC, will make Selected RII Staff Members Grace 9:00 a.m.
presentation to selected RII Staff Members 3/16-20/87
'II Office Resident Inspector Meeting Senior and Resident Reyes Inspectors 3/24/87 RII Office Vogtle Readiness Review Licensee and selected Reyes 10:00 a.m.
Meeting PII staff members 3/31/87 Atlanta, GA Georgia Power Company-Licensee representatives Grace m
M SALP Meeting Regional Administrator and E
Selected RII Staff Members E
E 3/31-4/2/86 RII Office Fundamentals of Inspection Selected RII Staff Members Crienjak o
Course
REGION III MEETING NOTICES' m
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WEEK ENDING: March 8,1987 4
U COCKET ATTENDEES /
ODATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NPC CONTACT 03/02/87 50-295 Region III Enforcement Conference-Consnonwealth Edisor.
A. R. Davis
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i 10:00 a.m.
50-304 Company (Zion) t i
03/04/87 License Region III Enforcement Conference Cleveland Clinic A. B. Davis-A.M.
No. 34-00466-02 P
O C
A
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