ML20128M528
| ML20128M528 | |
| Person / Time | |
|---|---|
| Issue date: | 07/03/1985 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-850628, NUDOCS 8507120005 | |
| Download: ML20128M528 (32) | |
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N W ebR ii i
4 July 3,1985 For:
The Commissioners From:
'T. A. Rehm, Assistant for Operations, Office of the EDO
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING JUNE 28, 1985 A sumary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.
Contents Enclosure
' Administration A
Nuclear Reactor Regulation B
4 Nuclear Material Safety and Safeguards C
l Inspection and Enforcement D
l Nuclear Regulatory Research E
1 Executive Legal Director F*
International Programs G
i State Programs H
l Resource Management I*
Analysis and Evaluation of Operational Data J
Small & Disadvantaged Business Utilization & Civil Rights K*
l Regional Offices L
i CRGR Monthly Report M*
l Executive Director for Operations N*
i Items Addressed by the Comission 0
I Meeting Notices P
Proprietary or Other Sensitive Information (Not for Q
external distribution) l
- No input this week.
/
8[5071{oo0 0pm PDR T. A. Rehm, n;;i..
r Operations gylt4FOREPT Office of the Executive Director P
i for Operations
Contact:
T. A. Rehm, EDO 1
492-7781 i
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HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING JUNE 28, 1985 Fermi-2 The licensee achieved initial criticality at 5:19 a.m. on June 21, 1985.
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The low power license had been issued on March 20, 1985; fuel load commenced on that same day and was completed on April 11, 1985. Tha Commission briefing to obtcin approval to go to full power is scheduled for July 10, 1985. The lictnsee estimates that it will be ready to Gxceed five percent of rated oower between July 11 and 18,1985.
Mancho Seco Nuclear Generating Station 0
On June 23, 1985, while on hot staniby (2155PSIG, 532 F) an about 20 GPM non-isolatable leak occurred in the high point vent on the hot leg from the B steam generator. The plant was being restarted from a refueling outage which began on March 15, 1985. The leak occurred 'in a weld made during the previous refueling outage to install high point ventsrequiredtomeetaNUREG-07g7 req 11rement. The leaks appear to be occurring from a thru wall 120 circunferential crack. The plant l
1s being placed in cold shutdown to investigate the crack and make l
repairs.
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Fuel Snipping Cast Nuclear packaging, Inc. has submitted an application on behalf of the Department of Energy for a Certificate of Compliance for a fuel shipping cask. The cask is to be used for the transport of the Three Mile Island core debris to the, Idaho,
National Engineering Laboratory, Idaho Falls, Idaho. The cask is designed to trang-port up to 7 canisters bf rail. It is expected that 2 casks and approximately 250 canisters will be required.
I Issuance of Broad License to U.S. Air Force
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The Materia'l Licensing Branch issued a Broad Scope License to the U.S. Air Force Radioisotope Committee, Brooks Air Force Base. Texas, on June 26, 1985. This license will replace the seventy-five material licenses presently issued to in-dividual Air Force units and bases. The broad license will reduce paperwork and provide a timely response to the Air Force's organizational and defense needs.
The license does not include reactor or nuclear weapons systems material. The license will be administered from the Nuclear Regulatory Commission (NRC) Head-quarters for approximately one year to assure an orderly implementat3cn of the program. When the implementation is complete the license will be assigned to NRC Region IV.
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JUN 2 81985
0FFICE OF ADMINISTRATION Week Ending June 28, 1985 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1984 179 23 Received, 1985 460 28 Granted 345 21 Denied 85 10 Pending 209 20 ACTIONS THIS WEEK Received Evan Rosen, Request for a copy of the video tape of a reactor WTOL-TV, Toledo containment test of November 1984.
(85-441)
David R. Ennis, Request for copies of power plant examination summary NUS Corporation sheets prepared by Operator Licensing Branch examiners (85-442) at the completion of their assignments for those individuals who applied for R0 and SR0 examinations at 11 plants.
Clifford A. Beck, Jr. Request for copies of regulations, etc., with regard to (85-443) obtaining records from the NRC.
(An NRC Employee)
Request for two categories of documents maintained (85-444) in the Document Management Branch.
Richard E. Webb, Request for a copy of " Evaluation of Transient Behavior Studies of Nuclear and Small Reactor Coolant System Breaks in the 177 Fuel Hazards &
Assembly Plant," Volume III, by Babcock and Wilcox Co.
Constitutional Law (85-445)
Robert Guild, Request for copies of records submitted to ASLB on Attorney At Law Shearon Harris by CP&L for in camera, ex parte review in (85-446) response to a discovery request for documents related to the inspector review panel and the report and associated documents pertaining to the charge of l
harassment.
I Steven C. Sholly, Request for 12 records referenced in draft 1 of Union of Concerned NUREG-0956.
Scientists (85-447)
ENCLOSURE A CONTACT:
J. M. Felton JUN 2 81985 492-7211 l
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Received Cont'd Steven C. Sholly, Request for records concerning the probabilities, Union of Concerned consequences, impacts, and magnitudes of in-vessel Scientists and ex-vessel steam explosions occurring during (85-448) core meltdown accidents at light water nuclear power plants.
Erich Riesenberg Request for a copy of NRC's standard criteria used (85-449) to determine the legitimacy of a request for a fee reduction or waiver for F0IA and Privacy Act requests.
Leonard I. Hellman, Request for the mailing list for IE Infomation Notices The Keenan issued by IE's Division of Emergency Preparedness and Corporation Engineering Response.
(85-450)
Donald F. Knuth, Request for computer printouts of infomation on hearings KMC, Inc.
~ for 26 specified plants.
(85-451)
Billie Pirner Garde, Request for all records related to inspection report Government 85-09 on the Braidwood plant.
Accountability Project (85-452)
Billie P. Garde, Request for all records related to inspection reports Government 50-348/83-16 and 50-364/83-14 on the Farley plant.
Accountabilit.y Project (85-453)
Billie P. Garde, Request for all records related to IE Information Government Notice No. 85-40, " Deficiencies in Equipment Accountability Qualification Testing and Certification Process."
Project (85-451) l Billie P. Garde, Request for all records relied upon by Mr. William Dircks l
Government in his analysis of the Quadrex Corporation's analysis l
Accountability of the South Texas plant, including information Project generated by Mr. Dircks or staff coments sent to (85-455)
Mr. Dircks about the Quadrex Report.
Sylvia Tognetti, Request for (1) copies of coments of Comissioners Christic Institute providing guidance to the staff on legislative (85-456) proposals, as referred to in a January 31, 1985, S. Chilk memo on SECY-84-146A, (2) Comission Staff Office coments in response to SECY-84-146A, and (3) OGC recomendations and proposed legislation in response to the above and on the subject of the Supreme Court i
I decision in Silkwood v. Kerr-McGee Corp. and punitive M 2 81985 ENCLOSURE A
Received Cont'd Steven C. Sholly, Request for copies of 10 documents referenced in Union of Concerned NUREG-1037.
Scientists (85-457)
Kenneth 0 Young, Request for machine readable copies of NRC Decisions Westlaw Services, from 1975 to date.
Inc.
(85-458)
William S. Philips, Request for a list of waste generators for 1984.
Stock Equipment Company (85-459)
Frank S. Hamblett, Request a copy of SECY-85-80, " Investigation Policy Newman &
on Rights of Licensee Employees Under Investigation."
Holtzinger, P.C.
(85-460)
Granted Steven Aftergood, In response to a request for copies of all correspondence Committee to between the NRC and the American Nuclear Society (ANS)
Bridge the Gap related to the 1984 ANS Report of the Special Committee (85-298) on Source Terms, made available seven documents.
Charles Barnes In response to a request for all documents maintained (85-252) in seven specified docket files, made available 259 documents.
Jan Flaharty, In response to a request for three categories of records Powder River Basin regarding Chem-Nuclear, Inc., and Waste Management, Resource Council Inc., made available 34 documents.
(85-298)
Mary Hargrove, In response to a request for four categories of records The Tulsa Tribune regarding the Oral Roberts University, the City of Faith (85-341)
Hospital and Clinic, and the City of Faith Medical and Research Center, located in Tulsa, Oklahoma, made available 34 documents.
Nina Bell, In response to three requests for records related to contacts Nuclear between NRC/ DOE and White House Officials, and between Information and these officials and representatives of utilities, state Resource Service regulatory commissions or agencies, or the financial (85-354,85-355, community regarding the Callaway, Diablo Canyon, and and 85-356)
Shearon Harris plants, made available 4 documents.
Informed the requester that an additional document subject to her requests is already located in the PDR.
JUN 2 81985 ENCLOSURE A
Granted Cont'd William J. Herrmann In response to a request referred from the Department and David G. Gilbert, of Energy for copies of documents involved in the Illinois Governor's drafting by the Atomic Energy Comission of Regulatory Office of Consumer Guides 1.46 and 1.60, infomed the requesters that Services documents subject to their request are already located (85-384) in the PDR.
Helen E. Brown, In response to a request for a copy of the NRC's current JBL International BPA purchase orders for courier services, made available Inc.
seven documents.
(85-407)
Ronald Stiles, In response to a request for copies of all records Board of Health, pertaining to NRC's relationship to the proposed
- Hawley, installation of microwave towers in Hawley, Massachusetts Massachusetts, and all records regarding health effects on humans and animals from microwave emissions, infonned the requester that the NRC has no documents subject to his request.
Steve Pasternack, In response to a request for records related to NRC's New Mexico State processing of FOIA requests, made available seven Universit documents.
(85-411 Alfred M. Wurglitz, In response to a request referred from the Defense Advanced Contract Audit Agency for a disclosure determination Technolog{,Inc.
on one audit report entitled, " Audit Report on (05-417, Evaluation of Task Order Proposal Submitted in response to RFP No. RS-0RM-83-452 Advanced Technology Inc.,
McLean, Virginia, Auait Report No. 6151-3T210002,"
made available the requested document.
David L. Meyer, In response to a request for a copy of NRC Form 313, Whitney & Dempsey
" Application for Material License," made available the (85-424) requested form and Parts 19, 20, 30, 32, and 170 of Title 10 of the Code of Federal Regulations.
i A. Neal Barkus, In response to a request for a copy of SECY-85-78, Hunton & Williams entitled, " Report on Assessment of Job-Related (85-434)
Qualification for Nuclear Power Flant Operators,"
dated March 5, 1985, made availaole a copy of the requested document.
Newal K. Agnihotri.
In response to a request for a copy of the code list EQES, Inc.
for the NRC's mailing lists, made available the (85-439) requested document.
Evan Rosen, In response to a request for a copy of the video tape WTOL-TV of a reactor containment test of November 1984 at (85-441)
Sandia Laboratories, informed the requester that the NRC does not have a copy of the requested video tape recording.
JUN 2 8 W ENCLOSURE A
Granted Cont'd Clifford A. Beck, Jr. In response to a request for copies of regulations, (85-443) etc. with regarding to obtaining records from the NRC, made available three documents.
Erich Riesenberg In response to a request for a copy of NRC's regulations (85-449) on fees and waiver of fees for FOIA and Privacy Act requests, made available three documents.
Denied Billie Pirner Garde, In response to a request for all records regarding IE Government Reports 50-445/84-32 and 50-446/84-11, on the Comanche Accountability Peak plant, made available 102 records. Denied six Project records in their entirety, disclosure of which would (85-151) reveal predecisional, working drafts of the staff of kegion IV and the Office of Nuclear Reactor Regulation.
Robert R. Belair, In response to a request for copies of documents Kirkpatrick &
related to radiological emergency plans for the Shoreham Lockhart plant since January 1984 and copies of correspondence (85-190) between NRC and the Long Island Lighting Company since January 1984, made available 81 documents.
Informed the requester that 14 additional documents are already publicly available in the NRC's Public Document Room.
Denied portions of four documents and 35 documents in their entirety, disclosure of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.
Debra D. Mcdonald, In response to a request for copies of all Nuclear Pharmacy, misadministration reports for the second, third, and Inc.
fourth quarters of 1984 pertaining to 18 specified (85-372) hospitals, inade available four documents. Denied five documents in their entirety, disclosure of which would interfere with an ongoing investigation.
(An NRC Employee)
In response to a request for copies of documentation (85-408) that supports her allegation to the Office of Inspector and Auditor (0IA), made available four documents.
Denied two documents in their entirety, disclosure of which would interfere with an ongoing enforcement proceeding.
ENCLOSURE A JUN 2 81985
WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING JUNE 28, 1985 PROPOSAL UNDER EVALUATION RFP No. : RES-85-106
Title:
" Piedmont Seismic Reflection Study"
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Description:==
Select a specific seismological problem related to the Southern Piedmont, design a program of seismic reflections and other geographical investigations, execute the program & interpret the resulting data. The information gathered is to be used to advance the state of knowledge on possible causes of seismicity in the Piedmont of Virginia & the Carolinas, particularly with respect to structure at hypocentral depths.
Period of Perfomance: 2 years with additional one year option.
Sponsor: Office of Nuclear Regulatory Research Status: The competitive range has been established and negotiations are 4
scheduled for the week of July 8,1985.
CONTRACT AWARDED RFP No.: RS-0RM-312
Title:
" Lease of a Data Base Management System (DBMS)"
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Description:==
Contractor shall furnish and install a comercially available, fully developed and tested DBMS to serve as the primary tool for development of a Corporate Data Network within NRC.
Contractor shall also provide training, maintenance and
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other support services.
Period of Performance: One year following installation Sponsor: Division of Automated Information Services, ORM State:: A fixed price contract awarded to Cullinet Software, Inc. in the amount of $321,370.00 effective June 27, 1985.
CONTRACTS CLOSED-0VT NRC-03-79-102 Dartmouth College
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NRC-04-77-210 Georgia Institute of Technology l
NRC-04-76-286 University of Kansas NRC-02-83-029 University of Arizona l
ADMINISTRATIVE MATTERS l
On June 21, 1985, the Division of Contracts participated in a conference l
sponsored by Howard University and the National Science Foundation entitled
" Funding Research through Federal and Private Partnerships." The conference was designed to inform minority scientists and engineers in small businesses, historPally black colleges and universities, and other research institutions of opportunitiet to do technological research projects funded by the U. S.
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Government. NRC participated in a panel discussion with other agencies on federal research opportunities under the Small Business Innovation Research i
(SBIR) Program.
j JUN 2 81965
OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending June 28, 1985 Grand Gulf, Unit 1 Under a proposal released on June 20, 1985, Middle South Utilities, Inc., offered to make its shareholders bear one-third of the $3.4 billion cost of building Grand Gulf Unit 1.
However, this proposal has not placated rate-making authorities in Mississippi, Arkansas, and New Orleans. A member of the Mississippi Public ServJc i
Commission thinks that a bankruptcy-law filing by Mississrppi Power &
Light is a definite possibility. A.n article in the June 21, 1985 Wall Street Journal described the financial situation in some detail.
Fermi-2 The licensee achieved initial criticality at 5:19 a.m. on June 21, 1985.
The low power license had been issued on March 20, 1985; fuel load commenced on that same day and was completed on April 11, 1985. The Commission briefing to obtain approval to go to full power is scheduled for July 10, 1985. The licensee estimates that it will be ready to exceed five percent of rated power between July 11 and 18,1985.
Dvster Creek - (a) MSIV Closure Event of June 12, 1985 and (b)
Discrepancies in Plant Drawings Update (a) MSIV Closure Event-The plant is now in startup, at 0% power and inerting the containment, following a reactor trip on June 12, 1985. The trip was due to a low pressure MSIV isolation which was caused by the turbine No. I bypass valve failing open. The valve failure was caused by dirt in the electric pressure regulator.
The regulator has been repaired. The resident inspector has discussed the event with the licensee and believes that the licensee understands the event. The plant went critical Tuesday, June 18, 1985, at 2:30 a.m.
A delay in reaching power is associated with the licensee performing required surveillance tests.
The June 12th trip resulted from a loss-of-coolant event (500 gallons) because two valves on the line from the Scram Discharge Volume to the Reactor Building equipment drain tank did not close.
Blistering of paint onthe line to the equipment drain tank from hot RCS coolant caused smoke and set off the fire detection and sprinkler system. The MSIV isolation scrame signal could not be bypassed until the RCS was below 600 psig. Once below 600 psig, JUN 2 81985 ENCLOSURE B
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. the trip signal was bypassed and the Scram Discharge Volume was isolated and the leak stopped. The two valves on the line to the drain tank have been repaired; the licensee increased the stroke for one and replaced the spring in another. The valves have been tested and declared operable.
(b) Update of Drawing Discrepancies It was identified earlier that discrepancies in plant drawings had been discovered by a Region I inspection review of GPU Nuclear's (the licensee) responses to IE Bulletins 79-02 and 79-14. A meeting was held at Region I on June 13, 1985, to discuss with the licensee the basis for continued operation of the plant. The licensee's basis, which was accepted by NRC, was primarily that the 1985 inspections through June 14th conducted by the licensee did not change the prior 1979-1980 effort on Bulletin 79-14. Hence the licensee concluded the seismic piping design capability for the plant is valid. The Region will review the licensee's non-conformance reports on these discrepancies.
Byron 1 At 6:50 a.m. CDT on June 23,1985, Byron 1 achieved 100% power. -The 100%
power testing is expected to take 7-10 days. The plant will then be shut een for an anticipated 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> to replace leaking pressurizer safety valves and complete other items.
Byron I had received its full power license on February 14, 1985.
Waterford 3 At 9:19 a.m. on June 23, 1985, Waterford 3 returned to criticality after being shut down since May 29, 1985. The shutdown was necessary to perform maintenance and modifications to the electrical generator.following discovery of lead carbonate deposits in the generator during inspections conducted at the end of the 80% power test plateau. As of noon on June 24, 1985, I
Waterford 3 was at 60% power and is expected to reach 100% power by June 26, 1985. Transient testing of the plant (100% generator trip and 100% turbine trip - reactor trip) is. scheduled for July 2,1985, with completion of the 100-hour warranty run scheduled for July 9,1985.
JUN 2 81985 ENCLOSURE B l
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. i Shoreham License The D.C. Circuit Court of Appeals on June 25, 1985 issued an indefinite
" housekeeping" stay against the issuance of a 5% license for Shoreham.
The stay will remain in effect until the court rules on the merits of the stay request filed by NY State and Suffolk County.
Rancho Seco Nuclear Generating Station l
On June 23, 1985, while en hot standby (2155PSIG, 532 F) an about 20 GPM non-isolatable leak occurred in the high point vent on the hot leg from the B steam generator. The plant was being restarted from a refueling outage which began on March 15, 1985. The leak occurred in a weld made during the previous refueling outage to install high point l
VentsrequiredtomeetaNUREG-07g7 requirement. The leaks appear to be occurring from a thru wall 120 circumferential crack. The plant is being placed in cold shutdown'to investigate the crack and make repairs.
Limerick l
On June 20, 1985 the Philadelphia Electric Company petitioned the j
Commission to review and reverse the decision of the Appeal Board (ALAB-809, June 17, 1985).
In ALAB-809, the Appeal Board vacated earlier Licensing Board decisions granting an exemption from 10 CFR 50.47 for certain Graterford prisoner emergency planning issues.
Also on June 20, 1985, the licensee renewed its motion before the ASLB for an exemption from the requirements of 10 CFR 50.47 (a) and (b) as they relate to the two contentions admitted on the Graterford prisoners issues.
Vogtle Units 1 and 2 On June 27, 1985 the staff issued the Safety Evaluation Report for Vogtle Units 1 and 2.
The applicant is Georgia Power Company. The SER identifies l'4 open items. The ACRS subcommittee meeting is
. planned for July 18 and 19, at the Vogtle site followed by the ACRS full committee meeting in early August.
Perry A press release was issued by the Perry applicant (CEI) on June 25, 1985 announcing their consolidation with Toledo Edison (Davis-Besse) under a newly formed holding company that will provide overall management planning and policy making for the two utilities.
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CEI has advised the staff that the naming of the holding company is pending and that all arrangements will take about 6 months hence to complete.
JUN 2 81985 ENCLOSURE B
NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT Week Ending June 28, 1985 1.
PLANT STATUS The facility remains in long term cold shutdown with the Reactor Coolant System (RCS) vented to the reactor building atmosphere and the reactor vessel head and plenum assembly removed.
The reactor _ vessel plenum has been removed from the reactor vessel-and placed on its storage stand in the deep end of the fuel transfer canal. A dam has been installed between the deep and shallow ends of the fuel transfer canal. The deep end is filled with water to a depth of about 20 feet (about 5 feet above the top of the plenum).
The modified internals indexing fixture is installed on the reactor vessel flange and is flooded to elevation 327 feet 6 inches (151 feet above the top of the core region).
Calculated reactor decay heat is less than 12 kilowatts.
RCS cooling is by natural heat loss to the reactor building ambient atmosphere.
Incore thermocouple readings range from 71*F to 92*F with an average of 82*F. Average cold leg temperature is 56*F.
The average reactor building temperature is 62 F.
The reactor building airborne activity is 2.0 E-9 uCi/cc tritium, and 6.6 E-10 uCi/cc particulate, predominantly cesium 137.
2.
WASTE MANAGEMENT The Submerged Demineralizer System (SDS) was shutdown during this period.
EPICOR II processed batch 257 (10,937 gallons).
Total volume processed through SDS to date is 2,898,836 gallons, and the tet:1 volume processed through EPICOR II is 2,480,774 gallons.
Seventeen shipments of radioactive material / waste were made from the site during the period May 21 - June 26, 1985:
Contaminated laundry was sent to Royersford, Pennsylvania:
l June 5; 89 drums, 3 boxes June 11; 102 drums, 4 boxes June 19; 90 drums, 3 boxes June 26; 67 drums, 4 boxes
'May 21, 1985 - A Unit 1 gas sample to Oak Ridge Tennessee.
l May 24, 1985 - Unit 1, 16 boxes of filter material to Hanford.
May 30, 1985 - Unit 1, 15 boxes of filter material to Hanford, Washington.
. June 10, 1985 - A Unit 2 tank was sent to Buchanan, New York.
June 13, 1985 - A combined shipment of non-compacted waste was i
sent to Hanford Washington.
June 14, 1985 - A Unit I sample shipment was sent San Jose, California.
June 17, 1985 - A combined shipment of 112 drums was sent to hanford, Washington.
June 19, 1985 - Two Unit I sample shipments were sent to San Jose, California.
i 4-1 JUN 2 8 E65
' ENCLOSURE B i
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' June 19, 1985 - A Unit I sample was sent to Rockville, Maryland.
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. June 20, 1985 - A combined shipment of non-compacted waste in 18 boxes was sent to Richland, Washington.
June 21, 1985 - A Unit I shipment of two depleted resin liners was sent to Richland, Washington.
June 26, 1985 - A Unit 2 shipment, three spent resin liners and i
8 steel. boxes were sent to Hanford, Washington.
June 26,1985 - A Unit 2 shipment of cable samples was sent to Hanford, Washington.
3.
DOSE REDUCTION / DECONTAMINATION ACTIVITIES j
Shielding of the reactor building air coolers is in progress.
Average general area radiation dose rate is 36 mrem per hour on the j
347' level of the reactor building and is 160 mrem per hour on the 305' level of the reactor building.
4 4.
ENVIRONMENTAL MONITORING EPA sample analysis results show TMI site liquid effluents to be in accordance with regulatory limits. NRC requirements, and the City of Lancaster Agreement.
TMI water samples taken by the US Environmental Protection Agency at the plant discharge to the river consisted of seven daily composite samples taken from June 8, to June 15, 1985.
Gamma scans detected no reactor related radioactivity.
4 The Lancaster water sample taken at the water works intake and i
analyzed by the US Environmental Protection Agency consisted of a seven. day composite sample taken from June 9, to June 15, 1985. A gamma scan detected.no reactor related radioactivity.
t The NRC outdoor airborne particulate sampler at the TMI Site i
collected a sample between June 19, and June 27, 1985. No reactor related radioactivity was detected. Analysis showed I-131 and l
Cs-137 concentrations to be less than the lower limits of detectability.
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5.
REACTOR BUILDING ACTIVITIES
. Future work in the reactor building is focused on preparations for the first phase of defueling in September 1985. The 5-ton service crane was load tested and certified for use in the reactor building.
This crane will be used in preparation for. installation of defueling i
equipment but will not be used to transfer loaded fuel canisters.
Additional near term defueling preparations include installation of defueling platform, completion of the Defueling Water Cleanup System l
(DWCS) and modifications to the auxiliary fuel handling bridge.
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JUN 2 8 MS ENCLOSURE B l
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6.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES
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Installation of the DWCS continued. Partial DWCS turnover for processing RCS during early defueling is scheduled to be completed in late August.
Boration of the processed water storage tank Number 1 is continuing.
This tank, which will be used to flood the "A" spent fuel pool during defueling, contains water at a boron concentration of 4,580 ppm.
7.
NRC EVALUATIONS IN PROGRESS Defueling Water Cleanup'Eystem Teghnical Evaluation (including Revision 6)
Technical Specification Change Requests numbers 46, 48, and 50 Equipment Hatch Removal Safety Evaluation Recovery Operations Plan Change numbers 27, 29. and 32 j
Fuel Canister Technical Evaluation Fuel Handling Senior Reactor Operator Training Program Defueling Safety Evaluation 8.
PROJECTED SCHEDULE OF FUTURE EVENTS Start of Defueling: September 1985
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9.
PUBLIC MEETING The next meeting of the Advisory Panel is scheduled for 7:50PM, July 18,1985, at the Public Service Building, 201' North Duke Street, Lancaster, PA.
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4 ENCLOSURE B f
JUN 2 81985
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4 0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS j
Items of Interest l
Week Ending June 28, 1985 Meeting with Battelle Colun. bus
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- The Battelle Columbus researchers will brief on the current results of their contract to quantify experimentally the magnitude and chemical / physical form of radioactive material which could be released by sabotage ohhipments of vitrified waste, spent fuel from gas cooled reactors, and spent fuel from non-power reactors. The briefing will be on July 9, 1985, 1 p.m., lith floor con-ference room, Willste Building.
Discussions with French Security Experts i
Division of Safeguards personnel briefed representatives of the French Inter-ministeriel de la Securite Nucleaire (CISN) on domestic safeguards matters on 1
June 26th. The purpose of their visit was to develop recommendations for the General Secretary of the Conunittee regarding the upgrading of French nuclear security programs.
They were impressed with the security system at the Susquehanna reactor (visited I
on June 25th) and very interested in our proposed Access Authorization Rule.
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'Our statements regarding removing cipher 16cks from vital area doors to facili -
l tate rapid movement during emergencies was a suprise to them since they were about to recommend the addition of such devices in French plants. Briefings covered our design basis threat statements, and security measures required for power reactors, fuel cycle facilities, and material in transit.
Issuance cf Broad License to U.S. Air Force The Material Licensing Branch issued a Broad Scope License to the U.S. Air Force Radioisotope Committee, Brooks Air Force Base Texas, on June 26, 1985. This license will replace the seventy-five material licenses presently issued to in-dividual Air-Force units and bases. The broad license will reduce paperwork and provide a timely response to the Air Force's organizational and defense needs.
The license does not include reactor or nuclear weapons systems material. The license will be administered from the Nuclear Regulatory Commission (NRC) Head-quarters for approximately one year to assure an orderly implementation of the program. When the implementation is complete the license will be assigned to NRC Region IV.
EELOSME C JUN 2 81985 1
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2 Kerr-McGee Corporation On June 21, 1985, representatives of Kerr-McGee Corporation met with representa-tives of NMSS to discuss the additional environmental information being supplied in response to NRC questions on the UF6 to UF4 conversion amendment request.
Copies of the response were supplied to NMSS at the meeting.
During the course of discussions, a number of other topics were discussed including the hearing request on the UF6 to UF4 amendment, the comprehensive waste disposal amendment, and the license renewal.
Nuclear Fuel Serivces (NFS)
On June 20, 1985, a meeting was held between, representatives of NMSS, Region II, and NFS. The meeting was requested by NFS to present a plan for starting up additional operations using salaried personnel.
On June 21, 1985, a meeting was also held with representatives of the Oil, Chemical and Atomic Workers Unio _n (OCAW). These officials represented the striking workers at NFS. The meeting was requested by the OCAW so they could present their reasons why the staff should not allow NFS to restart production operations.
NMSS Radiological Emergency Response The NHSS Radiological Onergency Response Manual was revised to reflect procedural changes ressiting from the move of the NRC Operations Center. Copies of the revised manual have been distributed to all members of the Protective Measures Team for Materials and Transportation emergencies.
Fu ol thinninn rack Nuclear Packaging, Inc. has submitted an application on behalf of the Department of Energy for a Certificate of Compliance for a fuel shipping cask. The cask is to be used for the transport of the Three Mile Island core debris to the Idaho National Engineering Laboratory, Idaho Falls, Idaho. The cask is designed to trans-port up to 7 canisters by rail. It is expected that 2 casks and approximately 250 canisters will be required.
Spent Fuel Rule A draft regulatory analysis was sent to the CRGR cost analysis group on June 26, 1985.
EMCLOSU?,E C UN 2 8 B85 l
l h
OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending June 28, 1985 1.
The following Significant Enforcement Actions were taken during the past week:
a.
EN 85-11A, imposition of Civil Penalty in the amount of $50,000 was issued June 21, 1985 to Duke Power Company (McGuire Units 1 & 2).
The licensee responded to the Notice of Violation and Proposed Imposition of Civil Penalty (EN 85-11 dated February 13, 1985) in a letter dated March 22, 1985. This action involved the failure of the Upper Head Injection (UHI) accumulator system isolation valves to close at the required UHI accumulator water level at Duke's McGuire facility. After consideration of the licensee's response, the staff concluded that the violation did occur and that mitigation of the civil penalty is not warranted.
b.
EN 85-48, a Notice of Violation and Proposed Imposition of Civil Penalties in the amount of $2,500 was issued June 24, 1985 to Frances Mahon Deaconess Hospital, Glasgow, MT. This action is based on several health physics violations. One of the violations involved the use of licensed materials by an unauthorized user.
2.
The following IE Preliminary Notifications were issued during the past week:
a.
PNO-I-85-43, Power Authority of the State of New York (Indian Point, Unit 3), Steam Generator Girth Weld Indications.
b.
PNO-III-85-49A, Calumet Testing Service (Griffith, IN), Disconnected Radiography Source (Update),
c.
PNO-III-85-50, Detroit Edison Company (Enrico Ferme 2), Initial Criticality.
d.
PN0-III-85-51, Christ Hospital (Cincinnati, OH), Medical Misadminis-tration.
e.
PNO-III-85-52,RMIExtrusionCompany(Ashtabula,OH),TruckCrash Involving Uranium Ingots.
f.
PNO-III-85-53, Cleveland Electric Illuminating (Perry Units 1 & 2) and Toledo Edison Company (Davis-Besse), CEI, Toledo Edison Announce New Holding Company.
g.
PNO-V-85-37, Sacramento Municipal Utility District (Rancho Seco),
Unisolable Reactor Coolant Leak.
h.
PNO-V-85-38,PacificGas&ElectricCompany(DiabloCanyon), Arrests Resulting From Drug Investigation.
ENCLOSURE D
- 3.
The following IE Information Notices were issued during the past week:
a.
Not applicable.
4.
Other Items a.
Construction Appraisal Team Inspection i
Director, IE; Chief, Reactor Construction Programs Branch, Division of Inspection Programs; Region IV Resident Inspector; Representative of NRR; and CAT members, attended the Clinton CAT Inspection exist meeting on June 21, 1985. Representatives of the State of Illinois Attorney General and Nuclear Safety attended.
b.
Large Pipe Failure at Fossil Plant Deputy Director, IE, was at the MoHave Power Plant (Fossil) in Nevada on June 27, 1985 to inspect the failure of large piping at that plant.
c.
Enforcement Conference Director, Enforcement Staff, and staff members were in Region I this week for an enforcement conference on Peach Bottom.
d.
Civil Penalties Paid (1) On June 17, 1985, payment in the amount of $50,000 was received from TVA (Browns Ferry) for enforcement action (EA 85-38) relating to violations involving l
the protection of vital equipment.
(2) On June 25, 1985, payment in the amount of $5,000 was received from Combustion Engineering (Windsor, CT) for enforcement action (EA 85-54) relating to violations involving unplanned exposure and failure to perform an adequate radiation exposure survey.
e.
Incident Response A representative of the Incident Response Branch, Division of Emergency Preparedness and Engineering Response, conducted a tour of the Operations Center for management representatives from Florida Power and Light on June 24 and visitors from France on June 26. A tour was conducted on June 28 for representatives from the Perry Nuclear Power Plant. These
^ tours discuss the agency's incident response program.
JUN 2 81985 ENCLOSURE D
. r f.
Vendor Programs The Vendor Program Branch, Division of Quality Assurance, Vendor, and Technical Training Center Programs, conducted the following inspections this week:
Continuation of inspec-Nuclear Energy Services, Greensboro, NC.
tion to review the fabrication of canisters used to remove, ship, (1)
The inspection will include and store the damaged core of TMI-2.
b observation of specific critical fabrication steps to ensure that work is being accomplished in accordance with written procedures to achieve the approved designs and implementation of the QA Pro '
gram including the qualification of welding and inspection personnel.
General Electric, Wilmington, NC. To inspect fuel manufacturing (2) with special emphasis on testing of fuel pellets and followup on previous inspection findings.
g.
Quality Assurance On June 24-28, 1985, representatives of the Quality Assurance Branch, Division of Quality Assurance, Vendor, and Technical Training Center Programs, visited the Millstone 3 Nuclear Power Plant to Assurance Program.
h.
Program Development Status Three inspection procedures dealing with maintenance were submitted to One of these, a generic maintenance inspection be issued this week.
procedure that has been written to be performance-based, has been placed in the BASIC section of the operating reactor (2515) program In addition, a revised to give it increased inspection emphasis.
table of contents for the IE Manual was submitted for issuance.
i.
11 Notifications GPU Nuclear Corporation procured replacement parts from Dresser (1)
Industries for the electromatic relief valves (EMRVS), Model Replacement parts supplied by Dresser were
~
1525 VX-2-SMY-1.
Dresser for an upgraded valve design, model 1525 VX-3-XFB-11.
did not notify GPUN that parts being supplied were from an up-4 graded design and that care must be exercised in interchanging Oyster Creek plant engineering considers that these parts.
certain configurations, in which a pilot disc of the cpgraded design is installed with a pilot disc stem of the old design, could leave excessive clearance such that the solenoid does not lift the pilot disc stem sufficiently to actuate the EMRV.
ENCLOSURE D JUN 2 8 585 4
(2) Written 10 CFR Part 21 notification dated 06/11/85, has been received from Anchor / Darling Valve Company regarding a problem related to tilting disc check valves with tack welded bushings which was recently reported to Achor / Darling. Tack welds were found cracked which could allow the hinge pin bushing to work free of the disc and compromise valve function. Fix is to replace tack welding bushings with a later design using a shoulder on the bushing instead of a tack weld.
Plants with valves to te notified by Anchor / Darling include:
Farley, Arkansas Nuclear One, Brunswick, LaSalle, Palisades, Beaver Valley, Cooper, Millstone 3, Rancho Seco, Summer, San Onofre 2 and 3, Point Beach, WNP-2, and two foreign plants.
(3) Part 21 phone notification 06/18/85 by an employee of Nelson Electric (Tulsa, OK). Low voltage motor control centers pro-vided to Duke Power (McGuire and Catawba), Boston Edison (Pilgrim), and Allied Gulf (Fuel Reprocessing Facility) 1972 have a control power transfonner in them which is used to reduce line voltage from 600 or 480 VAC to 120 VAC. These control power transformers have an aluminum nameplate attached to them with adhesive which could fall off with age and result in a short Crcuit or other malfunction. The specific systems where these might have been used are unknown. The transformers were provided by HEVI Duty Electric Company.
HEVI duty changed their adhesives in 1979 so transformers manufactured after this date should be o.k.
Corrective actions proposed by Nelson are:
(1) remove the tag and keep a separate record of data, (2) remove the tag and reattach with newer glue, (3) remove the tag and reattach adjacent to the transformer, (4) reattach tag with drive screw or pop rivet.
~
Nelson will followup with a written report and notify the facilities involved.
/
ENCLOSURE D JUN 2 81985
OFFICE OF NUCLEAR REGULATORY RESERCH Items of Interest Week Ending June 28, 1985 Meeting to Present Results of French Tests on a Main Coolant Pump Shaft Seal Under Station Blackout Conditions A meeting was held on June 20 to inform NRR and other NRC staff about the results of tests on a full-scale reactor coolant pump shaft seal recently completed in France. Although the seal was fullwale, a pump was not part of the tests. The tests were funded by Westinghouse, the Westinghouse Owners Group and by the French participants. Our consultant who observed the tests made presentations at the meeting and is being funded under the Mechanical Equipment Qualification Program.
During station blackout (SB) all offside power and auxiliary power are unavailable to the plant. This causes the pump shaft rotation to cease.
Seal injection and cooling water are lost permitting shaft seal exposure to primary coolant conditions. This could lead to seal failure and result in a LOCA. The NRC concerns are defined in GI-23 and USI A-44.
The French tests were conducted on a seal typical in French pumps; however, the seal has some characteristics similar to Westinghouse seals ir. 'J.S. pumps.
(It should be noted that Westinghouse was involved in these tests to obtain information that can be used to satisfy staff concerns about their seals).
The test results showed that seal leakage was far less than expected.
Also, a subsequent inspection of the disassembled seal showed very t
little degradation of the seal parts. The results are still under review; therefore, it is not apparent that all NRR concerns have been resolved by these tests.
The MESB will continue to work closely with NRR to develop a basis for judgments regarding seal behavior under SB conditions.
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l EELOSURE E JUN 2 81985
2 Containment Leakage Rate Testing In a June 11, 1985 letter, the ACRS recommended that the proposed revision to 10 CFR 50, Appendix J, and its daughter regulatory guide MS 021-5, be issued for public comment. Also on June 11-12, 1985, G. Arndt, J. Pulsipher and D. Lurie participated in a biennial ANS Workshop on Integrated Leakage Rate Testing, providing the attendees a status report on the NRC's activities in this area and answering questions. They also met with the ANS 56.8 Working Group (Pulsipher and Lurie are members) on June 12-13, 1985, to coordinate the proposed regulatory guide endorsing ANS 56.8 and the revision to the standard being prepared by the Working Group.
It was a productive meeting yielding wording on most positions that ' ay be acceptable for inclusion m
in both the revision to the standard and, until the revision is issued, in the endorsing regulatory guide. A revision to the regulatory guide is being prepared as a result of this meeting. The next meeting of the CRGR on this subject is scheduled for July 8,1985.
LOFT Test LP-FP-2 1
i The final LOFT test, LP-FP-2 is now scheduled for the afternoon of July 3, 1985.
This test is scheduled to reach peak cladding temperatures of not less than 2100K for not less than three minutes.
Test LP-FP-2 will be the most severe test of a represenatative reactor fuel assembly to date.
The test data will used to validate related, ex-reactor experiments and for assessment of reactor accident codes, including those for release and transport of fission products.
To achieve the targeted test conditions, the LOFT reactor completed a preconditioning power run on June 26.
The reactor was shut down until June 30 to adjust Cs/I fission product ratios and then brought back up to power for an l
additional 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.
The test transient will be initiated by scramming the reactor.
As soon as the reactor is scrammed, coolant discharge valves will be opened, to l
pennit coolant discharge and reactor core heatup to and above the planned 2100K peak cladding temperature. The test vill then he terminated by closing the coolant discharge valves and reflooding the core. Temperature, flow and fission product instrument readings will be monitored and recorded before, during, and after the experiment.
l N LOSURE E JUN 2 81985
3 Publications to be Issued in the Near Future
Title:
Design and Fabrication Code Case Acceptability ASME Section III, Division 1 (R.G. 1.84, Rev. 23)
==
Description:==
The guide on Design and Fabrication Code Cases has been revised to include new code cases, annulled code cases, revised code cases and reinstated code cases subsequent to issuance of R-22 of the guide.
Contact:
E. O. Woolridge 443-7917
Title:
Materials Code Case Acceptability ASME Section III, Division 1 (R.G.1.85,Rev.23)
==
Description:==
The guide on Material Code Cases has been revised to include new code cases, annulled code cases, revised code cases and reinstated code cases subsequent to issuance of R-22 of the guide.
Contact:
E. O. Woolridge 443-7917
Title:
Inservice Inspection Code Case Acceptability ASME Section XI, Division 1 (R.G. 1.147, Rev. 4)
==
Description:==
The guide on inservice inspection has been revised to include new code cases, annulled code cases, revised code cases, reaffirmted code cases and reinstated code cases subsequent to issuance of R-3 of this guide.
Contact:
E. O. Woolridge 443-7917 i
JUN 2 81985 i
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING JUNE 28, 1985 International Visitors On Tuesday Mr. Si Jung Yeh, Dean of the College of Nuclear Science of the National Tsing Hua University in Taipei, Taiwan, met representatives of the NMSS Division of Waste Management and the NMSS Division of Fuel Cycle and Material Safety to discuss NRC's activities related to high-level waste management in the U.S. with particular emphasis on site selection, monitored retrievable storage, and the arrangement of spent fuel.
On Wednesday Mr. Yves L. Majorel and Mr. Jean-Jacques Vagnieux of the French Comite Interministeriel de la Securite Nucleaire, an inter-agency government organization that is the highest authority in France on all nuclear security and safety questions, met with staff members from NMSS for discussions concerning the physical protection of nuclear reactor and fuel facilities and nuclear material during transportation. They also met with the Emergency Preparedness staff for a tour of and briefing on the Operations Center.
i JUN 2 81985 ENCLOSURE G l
t
0FFICE OF STATE PROGRAMS j
ITEMS OF INTEREST WEEK ENDING JUNE 28, 1985 l
Health Physics Course l
The second 1985 five-week course in Basic Health Physics for Agreement State personnel will comence at Oak Ridge, Tennessee, on July 8,1985.
Y n
1
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4 l
f JUN 2 81965
-ENCLOSURE H
OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEM 0F INTEREST WEEK ENDING JUNE 28, IJ85 AE0D published a semiannual review of the nonreactor events for the period July-December 1984(AE0D/N502). The review covered the 113 nonreactor events that occurred in this time period and indicated that the number and type of events were about the same as reported during prior semiannual periods.
Significant events singled out as abnormal occurrences were: accumulation of uranium in a ventilation duct; and distribution by two pharmacies of technetium contaminated with molybdenum. An annual summary and assessment of nonreactor events will be prepared in the future.
1 h
i
(
28g ENCLOSURE J
Region V 1
Week Ending June 28. 1985 l
Update on SMUD Activities Updating LRS Report Follow-Up On June 12, 1985, the Region V Administrator, Director, Division of Reactor Safety and Projects, the Rancho Seco Senior Resident Inspector, and other regional personnel met with the SNUD Board of Directors Subcomunittee and senior SMUD management responsible for implementing the LRS report recommendations.
e i'
The Region V Administrator observed that, while objective assessment of the licensee's progress since the previous meeting was difficult since the plant had been in a refueling and modification outage during this period, some i
positive achievements by SMUD were apparent: the licensee completed the outage with no significant radiation protection deficiencies, in contrast with the previous outage in December, 1984; the outage was conducted as scheduled, in l
ninety days, while maintaining adequate work controls; and IIIsudit of the licensee's equipment qualification program had been completed with no significant deficiencies.
~
SMUD made a comprehensive presentation of the status of implementation of the i
LRS report recommendations. The highlights of this presentation were:
i Approximately 70 percent of the 119 recommendations have been completed, at least to the extent that a corrective action program has been developed and implemented. Another 20 percent of the recommendations j
have been scoped and target completion dates established, generally in j
1985. The resolution of the remainder of the recommendations is associated with the completion of a detailed review of the Chemistry and i
Radiation Protection Department by General Dynamics (Electric Boat Division) for SNUD, and preliminary corrective action from this study has j
begun.
l The SMUD Board Chairman expressed an unequivocal commitment to ensuring j
that the changes made by SMUD would be effective, and would afsnificantly improve SMUD's performance relative to the industry.
c SMUD will start to restructure the nuclear organization in July, 1985.
The reorganization combines the LRS recommendations, feedback from SMUD Department Managers, and an organizational development consultant retained by SNUD.
I l
The-licensee is significantly enhancing its capabilities to perform root cause analysis of events by staffing a new group dedicated to this function, somewhat analogous to the independent safety evaluation group required of licensees such as San Onofre and Palo Verde.
The licensee has started to strengthen its own engineering department i
capabilities by developing comprehensive SMUD design procedures (previously delegated to Bechtel), and by increasing the ratio of SNUD engineers to contract engineers from the current 1:5 ratio to 1:1 by January, 1988.
i i
ENCLOSURE L JUN 2 81985 1
J
. Shift Technical Advisors, who are all licensed Senior Reactor Operators, will be reviewing operating procedures as they are used in the field following the current outage, to feedback errors and inconsistencies suspected to exist in some of them.
The Region V Administrator stressed the necessity for ensuring that implementation of the LRS recommendations actually occurred after programs were initiated. It was noted that followup on the actions which had been initiated was crucial to the realization of improvements by SMUD. After the meeting, the Senior Resident Inspector met with the Manager of Nuclear Operations staff to indicate several examples of such items. The Region V Administrator and the SMUD Board agreed that another meeting in about three months was appropriate to review SMUD's further progress and effectiveness in implementing the LRS recommendatioes.
The impression given by SMUD at this meeting to Regio.2 V was clearly that SMUD is actively changing and improving their organization, setting higher standards than previ~ously, and committing to more professional operations.
Region V intends to continue to closely monitor the details of these changes to assess their impact, and is guardedly optimistic that they will be effective.
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JUN 2 81985 l
l t
L
k' i
ITEMS ADDRESSED BY THE C069tISSION - WEEK ENDING JUNE 28, 1985 l
A.
STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND VOTE. 9:45 A.M.
WEDNESDAY, JUNE 19, 1985 COMMISSIONERS' CONFERENCE R00ft. D.C. OFFICE (OPEN TO PUBLIC 3
ATTENDANCE - Memo SECY to H. Plaine dated 6/28/85 I.
SECY-85-217 -- Shoreham -
.Intervenor Renewal of Request to I'
Supplement Environmental Impact Statement I
The Commission, by a 4-1 vote, approved an order denying a request by New York State and Suffolk County for the Commission to prepare a Supplemental Environmental Impact Statement which l
would evaluate the costs and benefits of Shoreham low-power l
operations, assuming no Shoreham full power operation.
Commissioner Asseletine disapproved and indicated he would
{
provide separate views.
4 (Subsequently, on June 20, 1985 the Commission reaffirmed their vote after the order was revised to respond to constissioner Asselstine's separate views.)
B.
STAFF REQUIREMENTS - AFFIRitATION/ DISCUSSION AND VOTE. 2:20 P.M., THURSDAY.
JUN: 20,1985. C0ff1ISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTINDANCE? - Memo SECY to W. Dircks. H. Plaine. C. Kannerer and J. Fouchard dated 6/18/85 I.
'SECY-85-217 - Shoreham -- Intervenor Renewal of Request to fy m1_ement Environmental Impact Statement The commission,* by a 4-1 vote, approved a revised order responding to a March 6, 1985 request by New York State and Suffolk County for the Commission to prepare a supplemental Environmental Impact Statement which would evaluate the costs and benefits of Shoreham low-power operations, assuming no Shoreham full power operation.
Commissioner Asselstine dis-approved and provided separate views.
~
(Subsequently, on June 20, 1985 the Secretary signed the order.)
- This item was previously affirmed on June 19, 1985 and was reaffirmed after changes were made in the original order.
f JUN 2 8 25 ENCLOSURE O
I ITEMS ADDRESSED BY THE C0!CISSION - WEEK ENDING JUNE 28, 1985 i
B.
Continued II.
SECY-85-169 -- Director's Denial of 2.206 Petition (In the Matter of Consumers Power Company), DD-84-17
{
The Commission, by a 5-0 vote, approved an order that affirms the decision of the Director of Inspection and Enforcement denying a February 10, 1984 10 CFR 2.206 petition by Billie Priner Garde related to the construction of the Midland Nuclear Power Plant.
(Subsequently, on June 24, 1985 the Secretary signed the i
order.)
i L
JII.
SECY-83 Final Pressurized Thermal Shock Rule l
The commission, by a 5-0 vote, approved a final rule on pressurized thermal shock.
You should forward the Federal Register notice for signature j
and publication.
Licensees and the appropriate Congressional committees should
- l also be advised and a public announcement released.
- r..
STf FF RFr.:liRFi4F iT5 - AFFIRMATION / DISCUSSION AND VOTE 11:45 A.M., MONDAY, j
JUNE 24, 1985 C0tWISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC i
AIItNDANCE) - Memo SECY to H. Plaine dated 6/28/85 l
1 I.
SECY-85-224 - Shoreham -- Suffolk County /New York State Motion for Stay of Low-Power License i
The commission, by a 4-1 vote, approved an order denying the stay requested by Suffolk County and the State of New York.
The conunission did continue the administrative stay until 5:00 p.m. on June 27, 1985 to allow orderly processing of stay requests in the U.S. Court of Appeals.
Commissioner Asselstine disapproved the order and provided separate views.
i l
(Subsequently, on June 24, 1985 the Secretary signed the order.)
t l
1 ENCLOSURE O i
JUN 2 81985
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=
NMSS MEETING NOTICES FOR WEEK ENDING: 6/27/85 w
Divisioa of Fuel Cycle and Material Safety g
ATTENDEES /
DOCKET DATE/ TIE NUPSER LOCATION PURPOSE _
APPLICANT NRC CONTACT i
7/11/85 71-9195 Willste Discuss pending application for Reps fm GE Odegaarden 9:00-12:00N GE-2000 package (General Electric).
H. Lee (FC)
R.Odegaarden.(FC),
7/12/85 New York, Expansion of the biomedical waste Dr. Yalow (VA)
Cunningham NY rule.
R.Cunningham(FC) 4 Division of Waste Management None Division of Safeguards Nonc I
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