ML20214G565
| ML20214G565 | |
| Person / Time | |
|---|---|
| Issue date: | 05/20/1987 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-870515, NUDOCS 8705270107 | |
| Download: ML20214G565 (31) | |
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7 h PT) A g
May 20, 1987 For:
The Commissioners From:
T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING MAY 15, 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 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*
Regicnal Offices K*
CRGR Monthly Reports L*
Executive Director for Operations M
Items Addressed by the Comission N
Meeting Notices O
Proprietary or Other Sensitive Information (Not for P
external distribution)
- No input this week.
ii
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e705270107 B70520 PDR COMMS NRCC T. A. Rehm, Assistant for Operations WEEKLYINFOREPT PDRi-Office of the Executive Director for Operations
Contact:
T. A. Rehm, EDO 492-7781
HIGHLIGHTS OF WEEKLY INFORMATION REPORT j-WEEK ENDING MAY 15, 1987 Maine Yankee On May 7,1987, Maine Yankee informed the staff that a black metallic cylinder or rod 1/4 to 5/16 inches in diameter and approximately 4 inches long was found underneath the upender in a locked, screened area. The upender is used to load and unload fuel.
The rod was highly radioactive (approximately 1000 rem).
The area under the upender had been surveyed by health physics personnel approximately 5 days ago and no particular activity discovered.
On the morning of May 7, 1987, a new health physics survey found the rod.
Region I and Maine Yankee are investigating where the rod came from, how long the rod had been in the area under the upender and how it got there.
Maine Yankee is in its Cycle 10 refueling outage. The reactor head has not yet been torqued down but preparations are being made for that operation.
Alternate Concentration L W As a follow-up to the April 23 EPA Interface Council meeting, NRC staff met with EPA on April 29 to discuss arolication of EPA's Alternate Concentration Limit Methodology at licensed ura...um mills.
NRC and EPA agreed in 1984 to develop a mutually-acceptable methodology to establish Alternate Concentration Limits for contaminants in groundwater.
A mutually-acceptable methodology was proposed to resolve an interagency issue about EPA's site-specific concurrences that was created when EPA promulgated final standards for uranium mills in 1983.
NRC staff reviews of EPA's methodology indicate that it appears to no longer provide sufficient flexibility to establish concentration limits at uranium mills.
NRC staff identified nine concerns with the methodology at the April 29 meeting.
Based on the outcome of the meeting, NRC staff plans to assess potential impacts of implementing EPA's Alternate Concentration Limit Methodology at licensed uranium mills.
This assessment will provide a basis to select options for resolving the site-specific concurrence issue.
Incident Response Branch Headquarters and Region III participated in the Dry Run for the Federal Field Employee exercise on May 5-5, 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 assassment, 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.
The Office Director, AE00, Branch Chief, and members of the IRB staff met with representa-tives of the States of Illinois and Wisconsin on May 13 and 14, 1987 to discuss this issue and the coordination of Protective Action Recommendations (PARS) for the Federal Field Exercise in June.
An agreement was reached regarding PARS in a general emergency condition.
Anticipatory PARS will be made in cases where plant conditions are rapidly deteriorating or unstable.
Communication channels were also discussed and are being addressed.
Illinois Agreement The Chairman signed the 274b agreement with Illinois on May 14, 1987.
The agreement has been sent to the Governor for signature. The agreement will become effective June 1,1987 and about 800 materials licenses will he transferred to the State.. With the addition of Illinois, there are now 29 Agreement States.
MAY 2 0 W
l OFFICE OF ADMINISTRATION AND RESOURCES MANAGEMENT For 5-Day Period of May 8,1987 - May 14,1987 1
ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS - 1987 Initial Appeal of Request Initial Decision Received This Week 16 2
Completed This Week 18 3
i Carryovers From 1986 170 53 Received In 1987 279 25 Granted In 1987 191 7
Denied In 1987 81 25 Pending 177 46 ACTIONS THIS WEEK Received Susan Katz, Requests a list of the addressees in New York, New Jersey, EPA anc California for the January 1, 1987 memorandum from EPA (87-264) and NRC to all NRC licensees.
Martin Hill, Requests copies of any letters supporting or opposing the San Diego Magazine transfer of ownership and/or nuclear materials licenses of (87-265)
GA Technologies, La Jolla, California, in 1986.
C. Coleman Bird, Requests copies of six categories of records since Wald, Harkrader October 1,1985, related to procurement of stenographic
& Ross reporting services.
(87-266) 1 Eli Port, Requests tepies of quarterly reports on transfers between f
Radiation Safety the first quarter of 1980 through the last quarter of 1986 Services, Inc.
on transfers of licensed material to general licensees.
(87-267)
Francine Lee, Requests copies of all disclosable it. formation regarding Information Access the suspension of the 1986 license from Radiation (87-268)
Technology, Inc., Rockaway, New Jersey.
David Strouss, Requests records regarding an incident occurring on or Thronton & Early about March 23, 1986, at the Vermont Yankee nuclear power (87-269) plant involving the exposure to radiation by a named individuai.
4 CONTACT: Donnie H. Grimsley 492-7211 May 15, 1987 ENCLOSURE A
Received, Cont'd Linda Bauman, Requests ccpies of all records related to concerns of Government a named individual about the Watts Bar nuclear power Accountability plant.
Project (87-270)
Lyle Graber, Requests copies of Region inputs to NRR regarding status NUS Corporation of plant readiness for operating licenses for 10 (87-271) listed plants.
Linaa Bauman, Requests copies of all records related to concerns Government of a named individual regarding the South Texas nuclear Accountability-power plant.
Project (87-272)
Linda Bauman, Requests copies of all records regarding concerns of a Government named individual about Ebasco at the South Texas nuclear Accountability power plant.
Project (87-273) 8.E. Wolff, Requests records regarding the Atomic Disposal Company Ecology.and in Tinley Park, Illinois.
Environment, Inc.
(87-274)
E.F. Kurtz, Requests a list of all facilities licensed under 10 CFR Impell Corp.
Parts 30, 40, and 70.
(87-275)
Shelley helkens, Requests a copy of a report regarding an 01A investigation hH Citizens vs.
of Region IV.
Price-Anderson (87-276)
Linda Bauman, Requests records regarding (1) letters dated April 28 Government 1987 from Mark Emerson, RIV, to two named individuals, Accountability regarding Allegation No. 4-87-A-007, and (2) records Project that were developed in the course of inspection report (87-277) 50-498/499-38 on tM South Texas nuclear power plant.
(NRC employee)
Requests records regarding an OIA investigation.
(87-278)
Lyle Graber, Requests copies of region inputs to NRR regarding NUS Corporation status of plant readiness for operating licenses for (87-279) four listed plants.
(NRCemployee)
APPEAL TO THE COMMISSION for the release of deniea 87-A-24-85-789) records regarding requests for records concerning an EE0 87-A-25-86-96) matter.
May 15, 1987 ENCLOSURE A
3 Granted
. Mike Johnson, In response to a request for copies of.all AE0D reports, hUS Corporation
" Semiannual Staff Evaluation of the Status of NPRD5" (87-137) after the fourth report dated January 1984, made available six records.
i Steven Aftergood, In response to a request for copies of four categories Conunittee to of records related to the rule to limit the use of HEU l
Bridge the Gap in research and test reactors, made available eight j
i (87-180) records.
Informed the requester that 39 additional records subject to this request are already available at i
i the PDR.
o Linda Bauman, In response to a request for records relating to the Government significant vibration in an auxilary water cooling system Accountability at the South Texas plant on March 11, 1987, made available-4 l
Project six records.
1 (87-216)
Lynn Connor, In response to a request for a copy of the scope of work Doc-Search for Mitre Corporation's task on the extension of operating i
Associates licenses, made available one record.
(87-220) l David Rubinton, In response to a request for copies of all records Government developed by the License Fee Management Branch about the 1
Accountability cost of the operating license review for the Comanche Peak j
j Project plant from December 3,1985, to the present, made available j
(87-227) six records.
Informed the requester that four additional records subject to this request are already available at l
l the PDR.
a Michael Knapik.
In response to a request for copies of all correspondence i
McGraw-Hill between E00 Y. Stello and persons outside NRC from i
(87-229)
January 1, 1987, to the present, made available 18 records, i
Informed the requester that eight records subject to this l
request are already available at the PDR.
Lyle Graber, In response to a request for a copy of SECY-86-359, informed i
NUS Corporation the requester that the requested record is already j
(87-243) available at the PDR.
Mike Johnson, In response to a request for a copy of a July 14, 1983 NUS Coporation memorandum from Olan Parr to Roger Mattson,
Subject:
ASB (87-244)
Interpretation of Requirements for Compliance with GDC 2 i
l and 4 with Respect to Protection of Specific Structures, Systems and Components from Internal Flooding or Internal i
Missiles, made available a copy of the requested record.
i 1
Lynn Connor, In response to a request for copies of correspondence i
Doc-Search concerning EAD Metallurgical, Inc., from August 7,1985 Associates to the present, infomed the requester that the NRC j
(87-247) located no agency records subject to this request.
I flay 15,1987 ENCLOSURE A i
l*
4 Granted, Cont'd (An individual In response to a request for records maintained in the _
l
{
requesting NRC on himself, informed the requester that the NRC has L
information about no records pertaining to him in its radiation exposure.
himself) document control, or the security systems of records.
(87-259) i l
4 Denied 0.W. Ward, In response to a request for records relating to Met Lab Met Lab, Inc.
Inc.'s License No. 45-09963-01, made available 51 records.
(86-677)
Denied 40 records in their entirety, disclosure of which would tend to inhibit the open and frank exchange of i
ideas essential tc the deliberative process.
s Linda Bauman, In response to a request for records related to 01 Government.
investigation A4-86-003 on the Comanche Peak nuclear power Accountability plant, which is discussed in Board Notification 86-22, Project made.available 10 records.
Informed the requester that (87-91) one additional record subject to this request is already available at the PDR. Denied one record in its entirety and portions of 11 records, disclosure of which would result in a clearly unwarranted invasion of personal privacy, i
David Rubinton, In response to a request for copies of all records of Government investigations of kickbacks or other improprieties Accountability regarding ex-NRC employees now working for TERA, Project including an October 1986 incident at the Crystal River (87-226) nuclear power plant, denied records in an OIA investigation file in their entirety, disclosure of which would interfere with an enforcement proceeding.
(Anindividual In response to a request for a copy of his Reactor 4
requesting Operator Requalification Exam, denied the record in infomation about its entirety, disclosure of which would tend to inhibit himself) the open and frank exchange of ideas essential to the (87-248) deliberative process.
Billie Garde, In response to an APPEAL TO THE EDO for the release of Government the denied portions of 85 records in NRC's May 22,1986 Accountability response to a request for records relating to the Comanche Project Peak Task Force, continued to deny these records, release (86-A-98-85-59) of which would tend to inhibit the open and frank exchange j
of ideas essential to the deliberative process.
Jennifer Puntenney, In response to an APPEAL TO THE EDO for the release of l
Safe Energy the denied portions of five records in NRC's July 16, Coalition of 1986 response to a request for records regarding the Michigan Fermi nuclear power plant, continued to deny four records (86-A-148-86-430) containing commercial or financial information.. Continued to deny one record the disclosure of which would result in a clearly unwarranted invasion of personal privacy.
liay 15,1987 ENCLOSURE A
5 Denied, Cont'd Jessie Deer in water, In response to an APPEAL TO THE ED0 for the release of Native Americans one record denied in its entirety regarding a request for a Clean for records regarding the license conditions applied Environment to the renewal of the source material license No. SUB-(87-A-13-86-889) 1010, Sequoyah Fuels Corporation, continued to deny this record containing commercial or financial information.
4 May 15, 1987 EllCLOSURE A
d WEEKLY INFORMATION REPORT DIVISION OF CONIRACTS WEEK ENDING MAY 15, 1987 IFB ISSUED IFB No.: RS-ORM-87-247
Title:
" IBM Cabling Systen Canponents"
==
Description:==
The contractor shall provide IBM cabling system canponents to support IBM 5520 systems located at One White Flint North.
Period of Performance: Delivery within 45 days after contract award.
Sponsor: Office of Adninistration and Resources Management Status: IFB issued on May 13, 1987. Bids due on June 11, 1987.
PROPOSAL UNDER EVALUATION RFP Nos.: RS-OIE-87-120 and 125
Title:
" Specialized Technical Training"
==
Description:==
Provide technical assistance to the NRC in the implementation of identified needs and/or further developnent of programs e
to meet future needs for specialized technical training of NRC inspectors in the areas of Boiling Water Reactors and Pressurized Water Reactors.
Period of Performance: 36 months Sponsor: Office of Nuclear Reactor Regulation Status: Negotiaticas have been canpleted. Best and Final offers are due on May 20, 1987.
CONIRACT C WSED OUP NRC-10-79-375 Rehab Group, Inc.
4 i
May 15, 1987 ENCLOSURE A I
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0FFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending May 15, 1987 i
i Maine Yankee On May 7,1987, Maine Yankee informed the staff that a black metallic cylinder or rod 1/4 to 5/16 inches in diameter and approximately 4 inches long was found underneath the upender'in a locked, screened area. The upender is used to load and unload fuel. The rod was highly radioactive 4
(approximately 1000 rem).
f The area under the upender had been surveyed by health physics personnel i
approximately 5 days ago and no particular activity discovered.
On the morning 4
of May 7, 1987, a new health physics survey found the rod.
Region I and Maine Yankee are investigating where the rod came f om, how long j
the rod had been in the area under the upender and how it got there.
Maine Yankee is in its Cycle 10 refueling outage.
The reactor head has not o
j yet been torqued down but preparations are being made for that operation.
Indian Point Nuclear Generating Unit No. 32 It was announced May 11, 1987 that Mr. Leroy W. Sinclair will resign hia 4
position as President and Chief Operating Officer of the New York' Power Autho-ity. Mr. J. Phillip Bayne, currently-the First Executive Vice President Operations, will replace Mr. Sinclair.
The turnover is i
expected to take place in mid-July.
l Vsgtle Unit 1 On May 12 Unit 1 completed the 50% load rejection test from 75% power. At 4:00 am on May 13, the unit tripped from 90% power on 10-10 steam generator-level caused by inadvertent closure of a main steam isolation valve during maintenance.
Following this trip, the unit started a 7-day outage to inspect two turbine bearings with excessive vibration.
During this outage, pressurizer i
spray valves, block valves to the pressurizer relief tank, and a POPV will be l
repaired for leakage.
The unit expects to go back up in power on liay 20 and complete its 90% and 100%
power ascension te" *ng shortly thereafter.
The licensee still anticipates l
comercial ocoratt June 1, 1987.
4 ENCLOSURE B l
May 15, 1987 1
.-,_--__,.,_.._.._.,_,..-m,..-.-___._
NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT WEEK ENDING MAY 15, 1987 1.
DEFUELING Pick and place defueling_ continued. A new tool called the " core debris digger" was used extensively to remove fuel pins from the area where fuel assemblies A-6, A-7, and B-6 had been removed.
Using the core debris digger the licensee was able to remove partial assemblies A-8, B-7, C-6, and C-7.
The assemblies were placed on the debris bed to be trimmed and loaded into canisters.
One previously filled canister was transferred to the spent fuel pool.
2.
ENVIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results show that TMI rite 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. Gamma spectrum analyses of the seven daily composited samples for April 25 - May 2,1987 indicated no TMI-2 related radioactivity.
EPA's gamma spectrum analysis of the NRC's TMI outdoor air sample for May 7 - 14, 1987 showed no reactor related radioactivity.
The water works for the City of Lancaster composited seven daily samples from April 26 - May 2, 1987.
EPA's gamma spectrum analysis of the composite sample showed no reactor related radioactivity.
3.
DECONTAMINATION ACTIVITIES 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.
Desludging of the auxiliary building sump has been completed.
Four solidified liners were generated.
Robot tool failure has caused a temporary stop to scabbling in the Seal Injection Valve Room on the 281' elevation of the auxiliary building.
Preparations continue for an early June robot examination cf the west side of the reactor building basement.
o May 15, 1987 ENCLOSURE B
2 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.
Environmental Evaluation of the Post-Defueling Monitored Storcge Proposal.
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.
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.
At the meeting, GPU Nuclear will give the Panel a status report on the progress of the cleanup and will comment on the schedule for completing the remaining cleanup tasks. The Panel will discuss the timing for a final Commission decision on the disposal of the accident-generated water and will forward a recommendation to the Commission. Members of the public will be given the opportunity to address the Panel.
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). Perscns 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.
May 15, 1987 ENCLOSURE B
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending May 15, 1987 Modal Study Notice of Availability Published in Federal Register On May 12, 1987, NRC published a notice in the Federal Register (52 FR 17862) advising that the final report on the Modal study, entitled " Shipping Container Response to Severe Highway and Railway Accident Conditions" (NUREG/CR-4829) was available for inspection or purchase.
The Office of Governmental and Public Affairs also issued a brief press release on the availability of the Modal study.
On May 8,1987, the licensee reported the results of their reinventory of the HEU process.
The results of the reinventory were within regulatory limits.
The licensee's reinventory was conducted in response to an excessive inventory difference reported on the February 1987 inventory.
The overall combined inven-tory difference for the first inventory and the reinventory is also within regulatory limits.
Presently the NFS Erwin plant is in operation.
AlchemIE On Wednesday, May 13, 1987, fuel cycle staff met with A1ChemIE to discuss their progress in preparing their application pursuant to 10 CFR Part 50 for a license to enrich stable isotopes.
A1ChemIE believes they will be ready to submit two applications in mid-July.
One application will be for operation of the Centrifuge Plant Demonstration Facility (CPDF) located on the Federal Reservation (K-25 area) at Oak Ridge, Tennessee.
The second application will be for a construction permit for a new facility to be located naar Oak Ridge.
Audio Conference Call Sponsored by The National Council of State Legislators On May 11, LLWM staff particiated in an Audio Conference sponsored by the National Council of State Legislators under a contract with GPA.
Legislators or staff from the States of Connecticut, Kansas, Massachusetts, Nebraska, Wis-consin, Missouri, Pennsylvania, and Ohio participated.
The areat of low-level waste storage, financial liabilities, alternative disposal methods, Class C Waste, and Below Regulatory Concern Waste were covered.
The conference was very well received by the participants.
May 15, 1987 ENCLOSURE C
2 IAEA Meeting LLWM participated in an Advisory Group Meeting that was convened by the Inter-national Atomic Energy Agency (IAEA) in Vienna, Austria, May 4-8, 1987.
The purpose of the meeting was to review a draft document that updated the pre-viously published IAEA Safety Series Report No. 51, " Development of Regulatory Procedures for the Disposal of Solid Radioactive Waste in Deep, Continental Formations." The intent of the IAEA was to assure that its guidance documents reflect current approaches of member states.
At this time, the guidelines established by IAEA closely resemble the siting procedures that were promulgated by the U.S. Department of Energy in its site selection guidelines (10 CFR 960).
The Commission formally concurred in those guidelines in July 1984.
Alternate Concentration Limits As a follow-up to the April 23 EPA Interface Council meeting, NRC staff met with EPA on April 2') to discuss application of EPA's Alternate Concentration Limit Methodology at licensed uranium mills.
NRC and EPA agreed in 1984 to develop a mutually-acceptable methodology to establish Alternate Concentration Limits for contaminants in groundwater.
A mutually-acceptable methodology was proposed to resolve an interagency issue about EPA's site-specific concurrences that was created when EPA promulgated final standards for uranium mills in 1983.
NRC staff reviews of EPA's methodology indicate that it appears to no longer provide sufficient flexibility to establish concentration limits at uranium mills.
NRC staff identified nine concerns with the methodology at the April 29 meeting.
Based on the outcome of the meeting, NRC staff plans to assess potential impacts of implementing EPA's Alternate Concentration Limit Methodology at licensed uranium mills.
This assessment will provide a basis to select options for resolving the site-specific concurrence issue.
Groundwater Protection at UMfRAP Sites On April 30, 1987, NRC staff provided informal comments to EPA regarding a draft version of proposed regulations (in 40 CFR Part 192) for groundvater protection at Uranium Mill Tailings Remedial Action Project (UMTRAP) sites.
The groundwater part of the standard was remanded to EPA in 1985 by the Tenth Circuit Court of Appeals to establish groundwater protection standards for UMTRAP sites.
Under Title I of the Uranium Mill Tailings Radiation Control Act of 1978, DOE has been assessing and ramediating 24 uranium mill sites in the UMTRA Project since 1983.
EPA intends to propose the UMTRAP ground-water protection standards this summer with final promulgation anticipated by mid-1988 to avoid substantial delays in the UMTRA Project.
May 15, 1987 ENCLOSURE C
3 Environmental Standards for low-Level Waste Sites On May 7, 1987, LLWM staff met with EPA to discuss EPA's low-level radioactive waste activities.
fhe meeting primarily focused on EPA's draft standardt for environmental protection at low-level waste disposal sites, including provisions for groundwater protection, NARM waste disposal, and below regulatory concern levels.
EPA intends to propose regulations for low-level waste disposal in 40 CFR Part 193 before the end of 1987.
f 4
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i May 15, 1987 ENCLOSURE C
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1 0FFICE OF NUCLEAR REGULATGRY RESEARCH Items of Interest Week Ending May 15, 1987 Risk Based Performance Indicators In support of AE0D's perforniance indicator program, RES is developing improved performance indicators. One problem with developing a probabilistic indicator for unavailability of plant safety systems is that failure data are currently reported to NRC only at a system level, not at a train level.- In order to remedy this, Ed Jordan, AE00, is making plans for proposed rulemaking to change the LER rule-(10 CFR 50.73) to obtain train level data.. Dr. Sheron's Division is providing technical input, and Dr.
Morris' Division-is providing regulatory support for this proposed rulemaking.
I Station Blackout A-44 i
We made a full presentation of the Station Blackout (SBO) rule and its-bases to the ACRS subcommittee and the full committee last week. Okrent and Michelson raised questions about the need for seismic qualification of the equipment needed for coping with a SBO. Mr. Opeka of NUMARC presented the industry initiatives which indicated some misunderstanding with the staff position and was corrected by the staff.
Because of disagreement within the ACRS a letter will be sent next month.
ROSA-IV p
The NRC has a cooperative agreement with the Japan Atomic Energy Research
- i Institute (JAERI) to obtain data from the ROSA-IV Large Scale Test Facility j
(LSTF), in exchange for U.S.A. instrumentation and computer codes. LSTF is the largest thermal hydraulic test loop in the world for investigating small break loss-of-coolant accidents (SBLOCAs) and operational transients. The 6th JAERI-USNRC ROSA-IV Program Review Meeting was held at JAERI on April i
23-24, 1987.
3 Presented at the meeting were the Station Blackout Transient Test the simulated SG tube rupture test SB-SG-01 (i.e., an equivalent of rupturing 3.2 tubes in a PWR), flooding analyses for the steady state natural circulation tests, the 0.5 percent pressure vrssel (PV) bottom break LOCA experiment.
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2 B&W Plant Operational Safety Study A study was initiated to support the NRC staff in reevaluation of B&W plant safety.
It provides a comparison of the response of a representative plant for each PWR vendor, i.e., Oconee (B&W) H. B. Robinson (Westinghouse) and Calvert Cliffs (Combustion Engineering) to three specific transients i.e.,
loss of feedwater, small break LOCA and steam generator overfill. The study utilized thermal hydraulic analysis, human reliability analysis and probabilistic risk analysis results in an effort to evaluate operator burdens, demands on safety systems and the degree to which transient results are modeled in existing PRAs. The study found that operator burdens were well within operator capabilities and no major differences were found among vendor designs for either operator burden or remaining defense in depth of alternate systems to satisfy safety functions for the transients evaluated.
The report notes that the quality of operator performance shaping factors, e.g., training, procedures, the quality of instrumentation, as reported by reactor operations staff correlate strongly with their response to the transients. This correlation could be useful for evaluation of trouble areas at operating plants.
Semiscale A series of experimental systen designs, all tested under the Semiscale program, addressed nearly every reactor thermal hydraulic transient and accident type of interest to NRC. This testing program was initiated in 1965 and was completed in 1986. A draft report summarizing the Semiscale design characteristics, uses of the data and significant results and conclusion has been received for staff review.
EPA Proposed Rule Relating to Reportable Quantity Adjustments to Radionuclides EPA published a proposed rule (52 FR 8172) on March 16, 1987, relating to reportable quantity adjustments to radionuclides. A preliminary assessment of this proposed rule indicates a potential conflict with NRC's proposed Part 20 and NRC's proposed rule relating to Emergency Planning for Fuel Cycle and Material Licensees. These conflicts will be identified to EPA.
Publications to be Issued in the Near Future
Title:
Low-level Waste Form Stability (Draft Regulatury Guide - Task WM 405-4)
==
Description:==
This regulatory guide will provide guidance on achieving stability in low-level waste #orms.
Contact:
Phil R. Reed, RES 443-7669 May 15, 1987 ENCLOSURE D
j 3
Title:
Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1 4
==
Description:==
The guide on inservice inspection has been revised to include new code cases, annulled code cases, revised code cases, and reinstated code cases subsequent to issuance of R-5 of the guide.
Contact:
E. O. Woolridge, RES 443-7782 4
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May 15, 1987 ENCLOSURE D
._=,- _. _ _ -.. _ _. _...
ITEMS OF INTEREST OFFICE OF GOVERNMENTAL AND PUBLIC AFFAIRS WEEK ENDING MAY 15, 1987 INTERNATIONAL PROGRAMS:
l Foreign Trip Reports 1
j J. R. Hilley and L. Parrett, 00E June 16-27, 1986; Visitcd France, the FRG, Sweden, and Switzerland:
The travelers attended and made presentations at PATRAM 86 in Davos, Switzerland; observed spent fuel transportation, handling)and storage operations at La Hague (Cogema), France, Simpervarp (Clab, Sweden, and i
Gorleben (DWK and BLG), FRG; and reviewed GNS and Transnuklear transportation / storage cask manufacture / test facilities in Dusseldorf and Essen,'FRG.
J. E. Smith, H. R. Payne, C. D. Griffies, and T. G. H'11, ORNL/FTR-2528 January 27-March 19, 1987; Visited t.he FRG:
Under the Advanced Instrumentation for Reflood Studies (AIRS) program, the travelers participated in the replacement of ORNL-supplied instruments at the Upper Plenum Test Facility (UPTF), Mannheim, FRG.
J. E. Hardy, A. V. Blalock, ORNL/FTR-2517 March 9-22, 1987; Visited the FRG:
At the UPTF in Mannheim, FRG, the travelers modified existing instrumentation signal conditioning to accept ORNL-fabricated AC signal conditioners and completed a system calibration under the AIRS program.
B. R. Bass, Engineering Mechanics Section Head, ORNL/FTR-2526 March 30-April 16, 1987; Visited the FRG and Spain:
In the FRG the purpose of this trip was to confer with Dr. Stam and the staff at Kernforschungszentrum Karlsruhe GmbH (KfK) to accomplish several objectives related to the computational analysis of the I
wide-plate phenomena in reactor pressure vessel steels and to present a seminar at KfK.
In connection with the discussions at the KfK, Mr. Bass accompanied Dr. Stam to the International Conference on Plasticity at i
the Technical University of Catalonia in Barcelona, Spain.
Charles Kelber, RES April 27-30, 1987; Visited France:
Mr. Kelber participated in the American Nuclear Society topical meeting on " Advances in Reactor Physics, Mathematics, and Computation" held in Paris. Attached to the report is a paper, in English, presented by t
M. Gondran, Electricite de France, entitled " Expert Systems for Reactor Operation--A User's Point of View."
May 15, 1987 ENCLOSURE E
State, local and Indian Tribe Programs Weekly Highlights - May 15, 1987 2-Audio-Conference for State Legislators On May 11. GPA/5LITP sponsored an audio-conference, in cooperation with the National Conference of State Legislatures, for State legislators and their i
staff. Representatives from NMSS' Division of Low-Level Waste Management and Decommissioning briefed the participants (8 States) on issues such as LLW management options, financial sureties and liabilities, alternative disposal 1
technologies, Class C waste and BRC waste. Robert Fonner, OGC, was also i
present to serve as a resource person.
States were chosen to participate on the basis of their positions in meeting the milestones of the LLRWPAA.
Preliminary feedback indicates the audio-conference was extremely successful and informative for all participants. Because the audio-conference format proved to be an effective and low-cost method of communicating with the States, it will be used more frequently in the future.
I Illinois Agreement The Chairman signed the 274b agreement with Illinois on May 14, 1987.
The agreement has been sent to the Governor for signature. The agreement will become effective June 1,1987 and about 800 materials licenses will be i
transferred to the State. With the addition of Illinois, there are now 29 Agreement States.
Agreement State Prcgram D. A. Nussbaumer anc'5 tate, local and Indian Tribe Program staff briefed i
Commissioner assistants on the Agreement State Program on May 14, 1987.
(CommissionerRoberts'staffwasnotpresent.) Briefings of other j
organizational elements are being arranged.
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I lby 15, 1987 ENCLOSURE E I
- -.. ~
Office for Analysis and Evaluation of Operational Data Items of Interest Week Ending May 15, 1987 I
Reactor Operations Analysis Branch AE00 has issued a memorandum summarizing the history of the loss of decay heat removal during part loop operation events.
Past regulatory and industry actions, and proposed remedial actions to reduce the frequency of such events and better prepare the operating organization to cope with such events, should they occur, is presented.
Technical Training Center s
The TTC Director and Director, Divisi~on of Operational Assessment met with representatives from NRR, NMSS and RES during the week of May 11, 1987 to discuss technical training needs associated with the new organization and ways by which those needs can be met.
As an immediate response, the TTC will increase class size on a trial basis for selected classes.
The TTC will pursue the need for development'of new courses through the Needs Survey and Training Advisory Group input.
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.
The Office Director, AE00, Branch Chief, and members of the IRB staff met with representa-tives of the States of Illinois and Wisconsin on May 13 and 14, 1987 to discuss this issue and the coordination of Protective Action Recommendations (PARS) for the Federal Field Exercise in June.
An agreement was reached regarding PARS in a general emergency condition.
Anticipatory PARS will be made in cases where plant conditions are rapidly deteriorating or unstable.
Communication channels were also discussed and are being addressed.
A member of the IRB staff made a presentation on Reactor Systems and Severe Accident Assessment for the Hazards Management course at FEMA's Emergency Management Institute in Emmitsburg, Maryland on May 11, 1987.
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.
MAY 15, 1987 ENCLOSURE H 1
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c.
PN0-I-87-40, Philadelphia Electric Company, (Peach Bottom Atomic Power Station), Contractor Employee Terminated for Possession of Marijuana.
d.
PN0-I-87-42, Phildelphia Electric Company, (Feach Bottom Atomic Station),
Non-Licensed Operator Found Sleeping.
e.
PN0-0SP-87-04, Tennessee Valley Authority (Sequoyah Unit 2), Spill of Reactor Coolant Into Containment.
f.
PNO-III-87-56A, Cleveland Electric Illuminating Company (Perry), Steam Leak from Steam Drain Line - Update.
4 g.
PNO-III-87-60A, Dairyland Power Cooperative (Lacrosse Boiling Water Reactor),
l Permanent Shutdown of the Lacrosse Boiling Water Reactor - Update.
h.
PN0-III-87-64, Cleveland Electric Illuminating Company (Perry), Manual Scram Due to Decreasing Reactor Water Level, i.
PNO-III-87-65, Illinois Power Company, (Clinton, Unit 1), Intoxicated Guard.
J.
PNO-III-87-66, Commonwealth Edison Company (Byron, Unit 1), Water Hammer in Main Steam Line.
k.
PNO-III-87-66A, Commonwealth Edison Compnay (Byron, Unit 1), Water Hammer in Main Steam Line (Update).
1.
PNO-IV-87-5, Public Service Company of Colorado (Fort St. Vrain Nuclear Generating Station), Plant Startup after Prolonged Outage.
m.
PNO-IV-87-23, Houston Lighting and Power Company, (South Texas Project)
Serious Injury and a Fatality.
n.
PNO-IV-87-24, Kerr McGee Corporation, Potential Media Interest - Kerr McGee Corporation's Intent to Sell Their Nuclear Operations.
o.
PNO-IV-87-26, Sequoyah Fuels Corporation, (Sequoyah Uranium Hexafluoride Conversion Facility), UF 6 Cylinder Plug Defect Identified.
p.
PN0-V-87-31A, Portland General Electric Company (Trojan Plant), Potential Foot Exposure of 83 REM - Update, q.
PNO-V-87-32A, Arizona Nuclear Power Project (Palo Verde Unit 3), Foreign Material Found in Steam Generator - PN0-V-87-2 Update.
r.
PNO-RV-87-33, Sacramento Municipal Utility District (Rancho Seco), Selection of a New Deputy General Manager, Nuclear, s.
PNO-RV-87-34, Sacramento Municipal Utility District (Rancho Seco), Dual isoin Decay Heat System Outage at Rancho Seco.
MAY 15, 1987 ENCLOSURE H
t.
PN0-RV-87-36, Arizona Nuclear Power Project (Palo Verde, Unit 2), Palo Verde Unit 2 Reactor Shutdown Greater Thank 48 Hours, u.
PN0-RV-87-37, Portland General Electric Co., (Trojan), Fatigue Fracture on Safety Injection Fill Line on "A" Accumulator.
i f1AY 15, 1987 ENCLOSURE H
4 Items of Interest Office of Enforcement Week ending May 15, 1987 The following Significant Enforcement Actions were taken the week of May 11, 1987.
1.
An Order Imposing a Civil Penalty in the amount of $250.00 was issued to Yellowstone County Surveyor's Office, Billings, Montana. This action was based on several violations involving failure to (1) provide dosimetry to personnel using licensed material, (2) store licensed material properly, (3) maintain personnel exposure records, (4) adhere to transportation requirements, and (5) perform leak tests. (EN 86-06A) 2.
A Notice of Violation and Proposed Imposition of Civil Peralty in the amount of $50,000 was issued to Commonwealth Edison Company (Dresden, Units 1,2,and3). The action was based on failure to ensure the integrity of the protected area barrier. (EN 87-39)
,I 3.
A Notice of Violation and Proposed Imposition of Civil Penalty in the i
amount of $100,000 was issued to Detroit Edison Company (Fermi 2). The action was based on significant deficiencies in the implementation of the surveillance testing program. The violations involved the lack of control of plant equipment availability during testing activities, inadeouate scheduling of a surveillance test, and deficiencies in test procedures and personnel error in the performance of test activities.
(EN87-40)
Civil Penalty Paid the week of May 11, 1987.
1.
Georgia Power Company (Hatch, Units 1 and 2) paid the proposed penalty in the amount of $50,000. The action was based on failure to follow plant procedures which resulted in the loss of approximately 141,000 gallons of water from the spent fuel pools through the fuel transfer canal seals.
(EA87-27)
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May 15, 1987 ENCLOSURE M
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ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING MAY 15, 1987 A.
STAFF REQUIREMENTS - BRIEFING ON STATE OF THE NUCLEAR INDUSTRY, 2:00 P.M.,
THURSDAY, MAY 7,1987, COMMISSIONERS' CRITERETICE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE - Memo S. Chilk For the Record dated 5/18/87 The Commission
- was briefed by industry representatives on the following topics:
- Overview and report on industry improvement initiatives and reorganization
- NUMARC activities, agenda in transition
- Technical policy issues The following industry representatives made presentations to the Commission:
- John Conway, Executive Vice President Consolidated Edison of New York
- Sherwood Smith, Chairman, President, and Chief Executive Officer l
Carolina Power and Light Company
- Byron Lee, Jr., Executive Vice President Commonwealth Edison Company
- John Taylor, Vice President El ctric Power Research Institute The Commission emphasized to the industry representatives the need for the industry.to continue efforts in source term research, to focus attention on improving operation and main-tenance performance (including consideration of human per-formance aspects), and to interface with overseas counterparts on their programs to improve safety.
There were no requirements placed on the staff.
- Commisuloner Asselstine was not present.
Commissioner Roberts did not participate.
l
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May 15, 1987 ENCLOSURE N
3:
NRR MEETING NOTICES
- 4E MAYIQ3 1987
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c5 DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 5/18/87 50-412 Beaver Valley Power To permit NRC management to NRC(NRR/RI)/ Utility P. S. Tam 8:30 a.m.
Station (ERF) assess the operational readiness Shippingport. PA of Beaver Valley Power Station Unit 2.
5/19/87 Room P-118 Priority Meeting on Lessons NRC A. C. Thadani 9:00 a.m.
Phillips Building Learned from Diablo Canyon Loss of RHR Event.
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 Atos/NCT Eng.
5/18/87 50-396 Room 524 Management Meeting with Summer NRC/SCE&GCo J. B. Hopkins 1:00 p.m.
Phillips Building to dicuss the NRC Reorganization 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 Atos/NCT Eng.
5/20/87 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 En5 5/21/87 50-327/
Chattanooga Choo Choo OSP staff will receive a present-NRC/TVA T. S. Rotella 8:00 a.m.
328 Hotel ation by TVA on status of essential Imperial Ball Room elements of restart program for p;
Chattanooga, TN Sequoyah Nuclear Plant.
b h!
- 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 c)
A summary of these meeting notices can be obtained by calling 492-7424
l NRR MEETING NOTICES
- MAY1%1987 k
,lE APPLICANT /
5 DOCKET
" DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT I
5/21/87 50-289 Room 6507 To discuss results of tests on NRC/GPUN G. E. Edison 9:30 a.m.
Maryland Nat. Bank steam generator tubes.
Building 5/21/87 50-354 Room 5033 To discuss the schedule for the NRC/PSE&G 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 Gcs Company.
5/21/87 50-155 Room 6507 To discuss the licensee's plans NRC/ Licensee J. R. Hall 1:00 p.m.
Maryland Nat. Bank for resolution of the staff's Building concern on environmental qualifi-cations of Big Rock Point Electrical Cables.
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 and 2, and Vogtle Units 1 and 2.
321 To review River Bend Station (RBS) NRC/GSU S. M. Stern 5/28/87 50-458 Room P-114 10:00 a.m.
Phillips Building plans on containment purge and containment venting.
"M o
E Copies of stzmaries of these meetings will be made publicly available and placed in the respective docket file (
- o"o in the NRC and local public document rooms 492-7424 A summary of these meeting notices can be obtained by calling
NRR MEETING NOTICES
- g MAY 15;1987
.G M
00CKET APPLICANT /
CATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 6/3/87 50-250/
Room P-110 To discuss proposed Technical "NRC/FPL-D. G. Mcdonald 8:30 a.m.
251 Phillips Building Specifications relating to Special Test Exceptions and Refueling Operations.
6/4/87 50-250/
Room P-110 To discuss proposed Technical NRC/FPL D. G. Mcdonald 8:30 a.m.
251 Phillips Building Specifications relating to Special Test Exceptions and Refueling Operations.
6/4/87 50-250/
Rcom P-110 To discuss proposed on-site power NRC/FPL D. G. Mcdonald i
1:30 p.m.
251 Phillips Building system upgrade.
t 6/11/87 50-219 Room 6507 To discuss the status of the NRC/GPUN A. W. Droserick i
10:00 a.m.
MD Nat'l Bank Build. Systematic Evaluation Program and l
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 operating procedures.
"=9 h
- Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) g in the NRC and local public document rooms A summary of these meeting notices can be obtained by calling 492-7424
.. ~ - _ ~ _ -
NPSS MEETING f:PTICES I
DIVISION OF FirFL CYCLE, PEDICAL, AC/DEMIC AND C0feERCIAL IIFF SAFETY
~
ui FOR WEEK EllDING May 15.1987 co N
D00FT-ATTENDEES /
DATE/ TIME NUMBEP.
LOCAT'ON PURPOSE APPLICANT NRC CONTACT 5/15/87 R/A Fairfax Pospital Site visit with Janice Dunn-Lee N. McElroy l
1:00-4:00 Fairfax, VA the Consissierers S/17-19/87 Fakefield,t'A Present talk on the General R. Corningham R. Cunningham Concepts of Proad Scope Licenses 5/1P-22/87 70-687 Tuxede. NY To participate in licensee T. Clark, NRC T. Clark i
I evaluation with Renfon I G. Comfort, NRC personnel (Cintichem) 5/20/87 40-E793 Silver Spring, MD To discuss amendment recuest L. Rouse, NRC L. Reuse i
for Molycnrr's Yorir facility W. Pennington, NRC i
to blend and distribute rare Represertatives of I
earth residues Molycorp 5/21/87 L'Frfant Plaza, To attend Technical Code J. Roberts, NRC J. Pcberts L
kashington, D.C.
Coordir.atino Group (TCCG)
J. Spraul, NRC Meeting. A review and dis-J. Schneider, NRC cussion of technical eneputer code development activities by i
g DOE and NRC/NMSS.
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i NMSS MEETING NOTICES page 2 ATTENDEES /
2F POCKET x PATE/ TIME NiptBER LOCATION PURPOSE APPLICANT NRC CONTACT
.G ts5/26-27/87 San Francisco, CA To attend pro.fect meeting J. Roberts, NRC J. Roberts on dry storige reviews at it. Schwartz, LLNL Lawrence Livermore Lah.
C. Chou, LLNL 5/27/87 9th F1. Conf.
Meeting with Mr. Bader, H. Thonpson URENCO, and Mr. Merrick, R. Cunningham FLOUR Corporation, regarding L. Rouse the engineering work /licer-sing process for uranium enrichment 5/31-F/5/87 Albuquerque, NM To attend (D. McCaughey) and G. Bidinger, NRC G. Bidinger to serve as faculty member D. McCaughey, NRC (Bidinger) at University of New Mexico Shcrt Course on Nuclear Criticality Safety 6/2/87 M/A New England Speaker or the revision N. McElroy N. McElroy l
Chapter Health of Part 35 Society Members l
Physics Society l
Burlington, FA 6/3-5/87 N/A Tororto, Canada Speaker on the revision M. McElroy N. McElroy of Part 3S at Annual Meeting of the Health Physics Society DIVISION OF HIGH-LEVEL HASTE MANAGEMENT 6/29-7/3/87 Embassy Square Suites Meetings to discuss various activities PAltomare NStill 2000 N Street, NW underway in HLW program, including NRC's ABender Washington, DC approach to identification and resolution BChampion 7,
pq of issues, status of NRC rulemakings, HLWM staff
[;
and demonstration of the pilot program States pg associated with the Licensing Support Indian tribes pg System DOE Federal agencies c,
.h page 3 i
NMSS MEETING NOTICES g
MVISION OF LOW-LEVEL WASTE MANAGEENT AND DECOMISSIONING I
s<
G DOCKET ATTENDEES /
NRC h DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT CONTACT E
5/IH/MI Boston, MA Giving presentation on Issues related M. Knapp (LLWM)
M. Enapp l
to low-level Waste Management at the NRC Broad Scope License Symposium.
i 5/18/87 1717 11 Street ACRS Meeting on GTCC and Mixed Wastes ACRS Members M. Dunkelman i
2:45 Room 1046 G. Roles (LLWM)
Washington, DC T.C. Johnson (LLWM)
S. Bahadur (LLWM)
S/20/87 Willste, 9th Meeting to discuss LLW Vitrification T.C. Johnson (LLWM)K. McDaniel 9:00 floor conf System G. Roles (LLWM) room 5/21/87 Boise, ID To present NRC's Perspective on Mixed National Conf.
S. Bahadur LLW on Radiation Control Program Directors 5/21/87 Denver, C0 Meeting with DOE staff in preparation K. Westbrook(LLWM)K. Westbrook for review of remedial action plans M. Young (LLW )
and to attend NRC workshop.
S. Smykowski (LLWM)
Johnson, (LLIM)
.i 6/2-3/87 Denver, 00 Participate in URF0 Workshop on M. Fliegel (LLlM) 5. Bilhorn Uranium Mill Tailings Reclamation T. Johnson (LLWM)
S. Bilhorn (LLWM) i DIVISION OF SAFEGUARDS AND TRANSPORTATION None E
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J May 15, 1987 RII MEETING NOTICE E
DOCKET ATTENDEES /
DATE/ TIM.;
NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT l
G i
i G
5/20/87 Crystal River, FL Meeting with Florida Power Licensee, Regional Admini-Grace 1:00 p.m.
Corporation management to.
strator, and selected RII discuss the Crystal River staff members facility i~
5/21/87 Crystal River, FL Meeting with Billy Griffin, Regional Administrator Grace 9:00 a.m.
Ex. V. Pres., Eng. & Const.,
Florida Power Corporation t
5/26/87 Dothan, At Meeting with Pres, and CEO Regional Administrator, Grace 1
9:30 a.m.
of the Farley Facility to J. M. Farley, P. Mcdonald, i
discuss matters of mutual and three plant Directors interest 5/28/87 Hartsville, SC Presentation of Operator Licensee management and Grace l
p.m.
Certificates at Robinson operators, and Regional Administrator i
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NRC FORM 255 CONTmACT NUMeER l
(10 761 NRC-03-87-026 DIVISION OF CONTRACTS MOOlfICATION NUM8E R US. NUCLEAR REGULATORY CCMMIS$ TON WASHf NGTON. O.C. J0555 D NEw 0 MoolflCATION OTHE R ISMeolvl NOTIFICATION OF CONTRACT EXECUTION CONTnACT BASED ON:
TO:
Themis P. Soets. Director AuTHORlrATION NUMBER r
ITottel Division of Safety Review and Oversight RFPA No. NRR-87-026 OATE
/g g
[j'al 12/30/86 CONTRACT CHANGES PER THIS ACTION
[
FR M yCe r. Bazin g/f/87 W
toetel Contract Negotiation Branch No. 2 OlVISION OF CONTRACTS. ADM 3
CONTRACTOR INanw A Locaten!
EXtCUTION DATE SBA/ International TcChnical Services, Inc.
4/N/87 420 Lexington Avenue, Suite 2518 New York, NY 10170 TYPE OF CONTRACT Cost-Plus-Fixed-Fee l
P;OJECT TITLE PE RIOD OF PE RF ORMANCE Review and Evaluation Of the Design Features of the VVER-440 Reactor PRINCIPAL INVESTIG ATOR Dr. Hideko Komoriya NRC AUTHORIZED R(PRESENTATIVE Brian Sheron A n No B&H NUMBER FIN NUMBER 3 0500.507 20-19-50-53-7 D-1756 AMOUNT NEW NRC FUNDS S 54,282.00 FUNDING TOTAL FY QZ FUNDING S 54,282,00 TOTAL NRC OBUGATIONS S 54.202.00 CVERNMENT PROPERTY AT T ACHM(NTi$l:
0705270155 070414 PDR CONTR CONT R ACT DOCUM(NT I one g
NRC-03-07-026 PDR NMC FORM 266 il M 01
_.