ML19301E362
| ML19301E362 | |
| Person / Time | |
|---|---|
| Issue date: | 02/05/1986 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-860131, NUDOCS 8602130421 | |
| Download: ML19301E362 (39) | |
Text
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February 5, 1986 Fo r:
The Coccissioners From-T. A. Rehm, Assistant for Operations, Office of the EDO Subiect:
WEEKLY INF0PMATION REPORT - L'EEK ENDING JANUARY 31, 1986 A summary of key events is included as a convenience to those Conmissioners who nay prefer a condensed version of this report.
Contents Enclosure Administration A
Nuclear Reactor Regulation B
Nuclear Material Safety crd Safeguards C
Inspection and Enforcement D
Nuclear Reculatory Research E
Executive Legal Director F*
Internaticnal Programs G
State Programs H*
Fesource Management I
Analysis and Evaluation of Operational Data J
Srell & Disadvantaged Business Utilization & Civil Rights K
Regional Offices L
CRGR Monthly Reports M*
Encutive Director for Operations N*
Items Addressed by the Commission 0
Meeting Notices P
Proprietary or Other Sensitive Information (Not for Q
external distributien)
- No input this week.
C A
ill T. A. Rehm, Assistant for Operations
/
Office of the Executive Director U,1 for Operations I it:
Contact:
/r;'
T. A. Rehm, EDO V
492-7781 0FC
- A0/EDO /
_ _ _ _ _ : _ _ _ _ _ _ 4.)
NAME :TARehm;pv DATE :2/ 6 /86 OFFICIAL RECORD COPY
t i
HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING JANUARY 31, 1986 Millstone 3 ih71 stone 3 began rod withdrawal at 2:50 p.m. on Thursday, January 23, 1966 and achieved initial criticality at 10:00 p.m. that ever.ing.
Comanche Peak During a routine review of various licensing documents comencing on January 24, 1985, the staff review found that the construction pemit for Unit I had expired on August 1, 1985.
It also appears that the applicant had not made a timely filing for a renewal of the construction pemit. The construction pemits had previously been extended for Unit I and 2, and Unit 2 is now scheduled to expire on August 1, 1987.
This infomation is preliminary and the applicant and NRC staff are currently examining the extensive licensing record. The ASLB will be notified as appropriate.
Nuclear Fuel Services, Inc. (NFS)
On January 27-28, 1986, members of NM55 and Region II staff met with representatives of NFS (licensee) to discuss HMSS questions and comments related to the review of the NFS application for license renewal.
As a result of the meeting, it was decided by both parties that a major revision of the NFS application is needed.
On January 28, 1985, members of NM55, SP, Region II (observer), and ELD staff met with personnel from the Oil, Chemical and Atomic Worker Union (0 CAW).
The Union represents the striking workers at the NFS, Erwin, facility.
The meeting was requested by the OCAW in order to obtain information regarding the status of the Nuclear Assurance Corporation (NAC) request for NRC's approval of the purchase of the NFS Erwin, facility and to express its concerns about this transfer.
,m JE 01 w
r i
OFFICE _0_F ADMINISTRATION Week Ending January 31, 1985 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Recuest Initial Decision Carryovers, 1985 181 15 Received, 1986 60 5
Granted 56 1
Denied 13 0
Pending 172 19 ACTIONS HIS WEEK Received Lyle Graber, Requests a printout for the 1985 Power Reactor Sunmary NUS Corpora'. ion of Violations, Infractions, and Deficiencies.
(86-48)
Marvin M. Turkanis, Requests copies of all registrations from the NRC Source Neutron Products, and Device Catalog for the following five firns: Siemens Inc.
Corporation; Toshiba Corporation; General Electric (86-49)
Company; U.S. Nuclear Corporation; and Alpha-Omega Corporation.
William J. Manning Requests a copy of the transcript of the November 19, (85-50) 1981, closed Comission meeting to discuss the suspension of the Diablo Canyon Unit 1 low-power operating license.
Willien Patterson, Requests a copy of FOIA Request No.85-795.
Morgan, Lewis &
Bnckius (86-51)
Edward G. Strit7ky, Requests a cnpy of the 10 mile Emorgency Planning nap for Office of Civil the Maine Yankee nuclear power plant.
Energency Preparedness Lintnin County, Maine (86-52)
Billie P. Garde, Requests all records generated or orepared by Victor Government Stello beginning with his appointment as acting Executive Accountability Director.
Project (8E-53)
CONTACT:
Donnie H. Grimsley 492-7211 ENCLOSLRE A JAN v i 3 33
2 Received, Cont'd Billie P. Garde, Requests all records generated or prepared by Victor Government Stello beginning with his appointment as acting Executive Accountability Di rec to r.
Project (86-54)
Billie P. Garde, Recuests all records generated or prepared by Victor Government Stello beginning with his appointmant as acting Executive Accountability Director.
Project (86-55)
Margaret L. Ryan, Requests records indicating the subjects and questiens Inside NPC upon which the Commission voted by the notation method (86-56) in the first five months of 1985.
Robert G. Todd Requests copies of the entire contents of the FOIA case (86-57) file No.85-848.
Daniel Burnstein, Requests six categories of records regarding the Pilgrim Williams, Jackson, and Maine Yankee nuclear power plants.
& Spero (86-58)
Stevi Stephens, Requests all records in 01 regarding 01 investigations Nuclear Awareness which have occurred and/or been closed within the time Network frame of August 20, 1985, and January 29, 1980, and all (86-59)
Quality First files.
Larry M. Hummel, Requests a list of the names and addresses of Pathfinder organizations licensed to use and store carbon-14 and Laboratories, Inc.
(86-60)
Albert V. Carr, APPEAL TO THE EDO for the release of the denied records Duke Power in NRC's December 26, 1985, partial response to his Company request for records related to and underlying Enforcement (86-A-5-85-5E4)
Actirn No. EA-84-93 regarding the Catawba Nuclear Station.
Granted Steven C. Sholly, In response to a request for (1) records related to the MHB Technical most recent Seabrook 1 Caseload Forecast Panel meeting; Associates (2) the NPC Resident Inspector's Handbnok; (3) all comment (85-769) letters on Draft NUREG-0956, "A Peassessment of the Technical Bases for Estimating Source Terms;" and (4) all records concerning the NRC-sponsored " Risk Methodology Integration and Evaluation Program" at Sandia Laboratories, made available 57 records.
Jack D. Lail, In response to a request for a copy of the response to the The Knoxville News- November 18, 1985, letter from Representative John Dingell Sentinel to NRC Cncirman Palladino and copies of letters dated (86-813) between October ou,1985, and December 6,1985, from the NPC to the Ternesst. Valley Authority, made available
' '*
- 5 one record.
Infrrmed the requester that additional N;' '. 1 records subject to ti,9 request are already available at the PDR.
ENCLOSURE A
3 Granted, Cont'd Janes J. Capone.
In response to a request for the name, address, and United Technologies license number of all NRC byproduct licensees on Packard the magnetic tape which he provided to us, made (85-829) available the requested information on the tape.
Peter F. Riehm, In response to a request for a copy of the Staff KMC, Inc.
Fequirements memorandum dated December 31, 1985, which (86-12) resulted from the Commission's consideration of SECY-85-119, made available the requested record.
Marjorie M. Aamodt In response to a request for a copy of an October 3, (86-13) 1979, memo from R. DeYoung to W. Kreger, " Calculated Off-Site Iodine-131 Air Concentrations from Three Mile Island," made available a copy of the reauested record.
Kathleen F. Tucker, In response to a referral from the DOJ of a request for Health & Energy records relating to claims acainst the government relating Institute to radiation exposure, informed the requester that the NRC (86-24) could not locate any records relating to individuals who may be making claims against the NPC for radiation exposure.
(NRC employee)
In response to requests for records pertaining to herself, (86-28 & 86-30) made available three records.
Howard R. Irwin, In response nto a request for three categories of records Advanced Medical regarding AEC License 34-7225-12 issued to Picker Systems, Inc.
Corporation, informed the requester that the NRC has no (ES-32) records subject to this request.
Williem F. Patterson, In response to a request for a copy of F0IA Request No.
Morgan, Lewis &
85-795, made available a copy of the requested record.
Bockius (86-51)
Denied Cir:dee Virostek, In response to a request for copies of 36 listed reports Kiski Valley or categories of records related to the Babcock and Wiicax Coalition facilities in Apollo and Parks Township, Pennsylvania, (85-711) informed the requester that 22 records are already available at the PDR; six records could not be located; and we have referred seven records to the DOE for review and direct response to her.
Denied portions of one record containing classified information.
(An individual In response to a request for copies of specific on-the-reouesting job radiation exposure procedures for Kelly Air Force information)
Base personnel, made available three records. Denied (80-1) portions of one record, disclosure of which would constitute a clearly unwarranted invasion of personal privacy.
ENCLOSURE A Jid! 3 1 E 5
1 4
Denied, Cont'd Robert R. Sparks, In response to a referral from the OPM of : reevest Herge, Sparks, for copies of form SF-171, Application for Federal Christopher and Enployment, reflecting past employment histories of Biondi certain former employees of the Federal Election (86-14)
Conmission, denied portions of one record, disclosure of which would constitute a clearly unwarranted invasion of personal privacy.
(NRC employee)
In response to a request for two categories of records (86-18) regarding Vacancy Announcement Nr. 86-0336-5, made available three records.
Denied portions of four records, disclosure of which would constitute a clearly unwarranted invasion of personal privacy.
653 ENCLOSURE A Jid4 vi
WEEKLY INFORMATION REPORT DIllSION OF CONTRACTS VEEK ENDING JANUARY 31, 1986 IFB ISSUED IFB No.:
RS-ADM-86-218
Title:
" Furnish and Install an Uninterruptable Power Supply (UPS) System for the NRC Operations Center"
==
Description:==
Contractor shall furnish and install five UPS units to provide continuous power for sensitive computer and telecommunications equipment during interruptions to the electrical power supply.
Period of Performance:
90 days Sponsor: Division of Facilities and Operations Support, Office of Administration Status:
IFB issued on January 24, 1986.
Bids due February 25, 1986.
IFB UNDER EVALUATION IFB No.:
RS-ADM-86-256
Title:
" Archival Storage"
==
Description:==
The contractor shall provide an environmentally controlled and protected storage area for archival material.
Period of Performance: Two years with an option to extend one additional year.
Sponsor: TIDC/ Office of Administration Status: Bid opening held on January 24, 1986.
RS-CIE-86-155
Title:
" Technical Assistance for Design Inspections"
==
Description:==
The design inspections are intended to provide a close examination of the design process and design implementation for a limited sample of structures, systems or component s for a specific f acility and any of its associated design organizations.
Period of Performance: 36 months Sponsor: Office of Inspection 6 Enforcerent Status: RFP issued on January 29, 1986. Proposals due February 28, 1986.
PROPOSALS UNDER EVALUATION RFP No..
RS-NRR-86-055
Title:
" Assessment and Application of Thermal-Hydraulic Phenomena for Severe Accident Decisions"
==
Description:==
Generic assessment of thermal-hydraulic issues associated with severe accidents, review all LWR designs to determine the specific applicability of resclts of the generic assessment of thermal-hydraulic issues and provide support for implementation of NRC's severe accident policy, review of probabilistic risk assessments and prioritization of generic issues.
Period of Performance:
30 months Sponsor: Office of Nuclear Reactor Regulation Status: Best and Final offers due on February 4, 1986.
ENCLOSURE A JAh 311986
Weekly Information Report Division of Contracts PROPOSALS UNDER EVALUATION (cont'd)
RFP No.:
ole-85-167 title: " General Course in Non-Destructive Examination and Codes"
==
Description:==
The purpose of this project is to provide NRC personnel the detailed technical training in nondestructive examination (NDE) and the applicable codes necessary to enable them to conduct in-depth inspections of NRC licensed facilities under construction or modification to determine ubether or not such facilitie ? N @ nents are constructed properly in accordance with applicable codes and standards.
Period of Performance: Three years Sponsor: Office of Inspection 6 Enforcement Status: Final Evaluation Report received on January 29, 1986.
CONTRACTS AWARDED RFP No.:
RS-ORM-85-335
Title:
" Integrated Library System"
==
Description:==
Software maintenance, support and timesharing. services for the Integrated Library System.
Period of Performance: Two years with cne option year Sponsor: Office of Resource Management Status: Fixed Price Contract No. NRC-33-86-268 awarded to on-Line Computer Systems, Inc., in the amount of $124,287, effective February 1,
1986.
RFP No.:
RS-01E-85-162
Title:
"Techn: cal Assistance in Developing and Implementing Quality Ass trance Initiauives"
==
Description:==
Assist in the development and implementation of revised programs for achieving and assuring the quality of the design, construction, operation and maintenance of nuclear facilities and activities.
These program revisions derive their impetus from conclusions and recommendations identified in the recently completed study of quality assurance mandated by Public Law 97-415 and described in NUREG-1055, " Improving Quality and the Assurance of Quality in the Design and Construction of Nuclear Power Plants" and from subsequent Commission meetings on quality assurance.
Period of Performance: 36 months Sponsor: Office of Inspection 6 Enforcement Status: Cost-Plus-Tixed-Fee / Task Ordering type Contract No. NRC-05-86-162 was awarded to Science Applications International Corporation, McLean, Virginia in the ceiling amount of $1,698,002.00 effective January 24, 1986.
ENCLOSURE A JAN 311956
DIVISION OF ORGANIZATION AND PERSONNEL ITEMS OF INTEREST Week Ending February 1,1986 Comprehensive Negotiations With NTEU Representatives of management and the National Treasury Employees Union (NTEU) commenced renegotiating the existing contract on June 10, 1985.
Failure to reach agreement prompted the parties to seek the assistance of the Federal Mediation and Conciliation Service (FMCS) on January 22 and 23.
FMCS directed the parties to resume bargaining on January 29-30 and to return to FMCS on February 18-21 on all remaining issues.
Any bargaining issues unresolved by close of business February 21 may be referred to the Federal Services Impasse Panel for final and binding resolution.
Unresolved negotiability issues will be referred to the Federal Labor Relations Authority.
JAN 311935 ENCLOSURE A
OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending January 31, 1986 Millstone 3 Millstone 3 began rod withdrawal at 2:50 p.m. on Thursday, January 23, 1986 and achieved initial criticality at 10:00 p.m. that evening.
Termination of Facility Operating License for the Georgia Institute of Technology AGN Training and Research Reactor On January 7,1986, the Office of Nuclear Reactor Regulation issued an Order terminating Operating License No. R-111 for the AGN-201 training reactor at the Georgia Institute of Technology, in Atlante, Georgia.
The AGN-201 reactor was initially licensed to operate at Georgia Tech in 1968 at power levels not to exceed 0.1 watt. This reactor was used in the Institute's educational programs for several years. The nuclear-based research and treining at Georgia Tech continue to be supported by a licensed 5M watt reactor.
Issuance of Renewal of facility Operating License for the Pennsylvania State University Research and Training Reactor On January 27, 1986, the Office of Nuclear Reactor Regulation renewed Facility Operating License No. R-2 for the TRIGA-type research and training reactor (Penn State Breazeale Reactor) at Tennsylvania State University, in University Park, Pennsylvania. The renewal authorizes operation until 2006.
The first Penn State research reactor was licensed to operate in July, 1955 using high-enriched MTR-type fuel. After several years of operation and minor changes, the reactor was mcdified, and licensed in 1965 to operate on low-enriched TRIGA-type fuel, at thermal power levels up to 1 MWatt. The reactor continues to be operated under those same license conditions in the University's nuclear engineering educational program, for botn training and research.
Comanche Peak During a routine review of various licensing documents commencing on January 24, 1986, the staff review found that the construction permit for Unit I had expired on August 1, 1985.
It also appears that the applicant had not made a timely filing for a renewal of the construction permit.
The construction permits had previcusly been extended for Unit I and 2, and Unit 2 is now scheduled to expire on August 1, 1987.
ENCLOSURE B JAN L 1 "
2-This information is preliminary and the applicant and NRC staff are currently examining the extensive licensing record. The ASLB will be notified as appropriate.
JAh 1 e55 ENCLOSURE 3
2_
This information is preliminary and the epplicant and liRC staff are currently examining the extensive licensing record. The ASLB will be notified as appropriate.
ENCLOSURE B JAl; e 1333
NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS FEPORT WEEK ENDING JANUARY 31, 1986 1.
DEFUELING The licensee had intended to perform a video inspection of the void remaining after removing an 8 foot long section of fuel assembly P-4 (refer to Weekly Status Report dated January 27,1966). This will not be feasible, as adjacent rubble has fallen into and ncarly filled the void. A future attempt will be mada to dislodge an intact peripheral assembly, access the void with a camera, and assess the core conditions beneath the rubble pile.
The licensee has increased the actual defueling time from 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per day to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by using three defueling teems instead of two teams per day.
It is expected that next week, the licensee will increase to four teams per day.
A debris bucket hanger has been,nstalled on the shielded work platform that allows an attached debris bucket to follow the platform's rotation. This alleviates the need to reposition the in-use debris bucket each time the platform is rotated.
Four side-loading debris buckets were filled this week. Three of them were filled to an average underwater weight of about 70 lbs with sections of fuel pins. A fourth weighed 500 lbs.
The two new filters installed in the "B" train of the Defueling Water Cleanup Systers (DWCS) have becone plugged af ter a throughput of only 45,000 gallens. The licensee is still studying the problems of biological growth in the reactor coolant system which is believed to be causing the filter plugging.
2.
PLANT STATUS The facility remains in long term cold shutdown with th Reactor Coolant System (RCS) vented to the reactor building atmosphere and the reactor vessel head and plenum assembly removed from the reactnr vessel.
The plenum is on its storage stand in the deep end of the fuel transfer canal. A dam has been installed between the deep end shallow ends of the fuel transfer canol. 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). The defueling platform is instelled over the internals indexing fixture.
Calculated reactor decay heat is less than 12 kilowatts.
RCS cooling is by natural heat loss to the reactor builoing ambient atmosphere.
Incore thermocouple readings range from 73'F to 95'F with an averace of 82'F.
J g' ( l ' ~ ' '
~
ENCLOSURE B
The average reactor building temperature is 58"F.
The reactor building airborne activity at the Westinghouse platform is 1.5 E-7 uCi/cc Tr' tium and 5.4 E-11 uCi/cc particulate, predominantly Cesium 137.
Spent Fuel Pool "A" is flooded to a depth of 20 feet. About 6 feet of water is over the fuel canister storage racks.
3.
WASTE _ MANAGEMENT The Submerged Demineralizer System (SDS) and EPICOR II were shutdown this week.
Total volume processed through SDS to date is 3,598,397 gallons, and the total volume processed througn EPICOR II is 2,822,963 gallons.
The "A" train cf the DWCS was started up to filter the RCS at about 6:15 PM, Februe:y 1,1986. About 90 minutes later, the operating pump shutdown automatically due to low water level in the pump well.
The operators noted a slight decrease in RCS level and manually secured the system.
Investigation determined that a hose supplying water from the nump discharge manifold to the filters had ruptured, causing leakage of about 600 gallons of water from the RCS to the fuel transfer canal. The ruptured hose was replaced and the systein restarted. The system response to the hose rupture was as designed, and the casualty caused no radiological hazar(s or uncontained spills. The cause of the hose rupture is under investigation.
4.
RADI0 ACTIVE MATERIAL / WASTE SPIPMENTS Contaminated laundry was sent to Royersford, PA in these quantities in January 1986:
Janua.y 2, 44 (>ims and I box January 7, 42 drums anC 5 boxes January 15, 69 drums January 22, 69 drum!
n'-
es January 28, 67 or s 7xes Combined unit non-compa.
< vT in 16 steel boxes was sent to disposal at Richl&nd, L w
>ry 3.
A Unit 2 shipe_ot of fuel od segments was sent in a shielded cask to Scoville, IP on January 10.
A Unit 1 monthly liquid sample was sent to Rockville, MD for analysis on January 13.
A Unit 2 shipment of a whole body counter radioactive calibration source was. int to Susquehanna Steam Electric Station on Jeruary 14.
A Unit 2 reattor coolent waste sample was sent to Pittsburgh, PA on Jan"ary 10.
A combined unit shipment of radioactive waste in 107 drums was sent to disposal at Richland, WA on Janua'y 24.
jai. 51 dib ENCLOSURE B
. 5.
DOSE REDUCTION / DECONTAMINATION Dettatamination flusing of the 281' annulus area is in progress.
Average general area radiation dose rate is 40 mrem per hour on the 347' level of the reactor building and is 67 mrem per hour on the 305' level of the reactor building. The average do n rate to workers on the defueling work plat crm is 8 mrem per hour.
6.
ENVIRONMENTAL MONITORING US Enviror, mental Protection Agency (EPA) sample analysis results show TMI site liquid effluents to be in accordance with regulatory limits, NRC requirewnts, and the City of Lancaster Agreenvr,t.
TVI wat samples trien by EPA at the plant discharge to the river consism. 'f seven daily composite samples taken from January 11
.a ry 18, 1986. A gamma scan detected no reactor related throur' actiiity.
The Lancaster water sample taken at the water orks intake and ar.alyzed by EPA consisted of a seven day composited sample taken from January 12 through January 18, 1986. A gamma scan detected no reactor resated radioactivity.
The NRC outdoor airborne particulate sampler at the TMI site collected a sample between January 22, and January 29, 1986.
No reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesiwa-137 concentrations to be less than the lower limits of detectability.
7.
FEACTC < BUILDING ACTIVIT1f5 Initial defueling of the reactor core is in progress.
8.
AUXILIARY AND FUEL HANDLING BUILD!NG ACTIVITIES Installation of the balance of DWCS and canister dewatering systen, continued.
Spent Fuei Pool "A" has been flooded to a depth of about 20 feet (about 6 feet above the top of the fuel canister storage racks).
9.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49.
Recovery Operations Plan Change number 31.
SDS Technical Evaluation and System Description Update.
Core Stratification Sanple Safety Evaluation.
refueling Water Clearup Systen Technical Evaluation Report, Revision 7.
Containment Air Control Envelope Technical Evaluation Report, Revision 5.
Solid Waste Facility Technical Evaluation Report.
Reactor Building Sump Criticality Safety Evaluation Report.
JAli31lE6 ENCLOSURE B
. 10 PUBLIC MEETINGS The next meeting of the Advisory Panel is scheduled for February 12, 1986 at the Holiday Inn, 23 South Second Street, Harrisburg, PA from 7:00 PM to 10:00 PM.
At this meeting the Panel will receive a presentatio'1 by the US Department of Energy (DOE) on plans for the shipment of fuel removed from the damaged TMI-2 reactor to a DOE facility for interim storage. The Panel will also receive a status report ce the progress of defueling from GPU Nuclear Corporation. Members of the pt:blic will be given the opportunity to address the Panel.
On January 29, ' 986 in Krshington, D.C., representatives from GPUN and the NRC staff, in separate presentations, provided a briefing on TMI-2 recriticality issues to the Advisory Committee on Reactor Safeguards (ACPS) Subcomittee on Core Performance.
The ACRS full committee will be briefed on February 13. 1986 (3:15 FM - 5:15 PM) at NRC offices at 1717 H Streel, Washington, D.C.
Persons desiring the opportunity to speak before the Advisory Panel are asked to contact Mr. Thomas Snithgall at 717-291-1042 or write to him at 2122 Marietta Avenue, Lancaster, Pennsylvenia 17603.
JAH b 1 i5b0 ENCLOSURE B
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Endino January 31, 1986 Near-Term NRC Actions Under the Nuclear Waste Policy Act (NWPA)
Soction:
121(a) of NWPA:
EPA Final HLW Standards Statu EPA final HLW standards became effective on November 18, 1985, and is being legally challenged by States and environmental groups.
Staff briefed the ACRS on January 15, 1986 on proposed revisions to 10 CFR Part 60 for conformance to EPA standards.
Action:
The proposed revisions to Part 60 are scheduled to be submitted to the Commission in late February 1986.
Section:
141(b) of NWPA:
Comments on MRS Proposal Status:
Staff comments on the MRi proposal were transmitted to the Commission for approval on January 8, 1986 (SECY-86-9).
The Commission was briefed by Mr. Ben Rusche, Director, OCRWM, concerning the MRS proposal on January 23, 1986.
Action:
NRC comments are to be submitted with the proposal to Congress in early February 1986.
Section:
306 of NWPA:
Regulations for Training of Power Plant Personnel.
Status:
The final rulemaking package on Part 55 dealing with simulation training requirements and three associated regulatory guides b--
received ACRS approval.
The final Office review has been complete.
Action:
The final rule is scheduled to be submitted to the CRGR for review on February 12, 1986, and then to the Commission for approval.
Sg: tion:
141(d) of NWPA:
Licensing of MRS Status:
NRC has developed rev. ions to 10 CFR Part 72 to provide the licensing framework for the MRS, should it be authorized by Congress.
Action:
The proposed rule on 10 CFR Part 72 was submitted to the Commission (SECY-85-374) on November 15, 1985, for approval which is expected after DOE officially submits the proposal to Congress.
JAN 31 iSE5 ENCLOSURE C
2-Near-Term,' 'E Actions of Interest Early February 1986 - DOE to issue Final Transportation Business Plan.
Early February 1986 - DOE to issue draft Request for Proposals (RFP) for the reactor fuel cask.
Early February 1986 - DOE submits MRS proposal to Congress.
Meetino at DOE Headouarters On January 28, 1986, G. H. Bidinger attended a meeting with DOE and DOE contractor personnel to discuss discrepancies between experiments and calculations for nuclear criticality safety.
The discrepancies are most notable for reflected arrays.
Planned actions for resolution of these problems include specific actions to verify epithermal cross sections and experiments to measure parameters (other than K-effective =1) which can be calculated by the different codes.
Nuclear Fuel Services, Inc. (NFS)
On January 27-28, 1986, members of NMSS and Region II staff met with representatives of NFS (licensee) to discuss NMSS questions and comments related to the review of the NFS application for license renewal.
A; a result of the meeting, it was decided by both parties that a major revision of the NFS application is needed.
On January 28, 1986, members of NMSS, SP, Region II (observer), and ELD staff met with personnel from the Oil, Chemical and Atomic Worker Union (OCAW).
The Union represents the striking workers at the NFS, Erwin, facility.
The meeting was requested by the OCAW in order to obtain information regarding the status of the Nuclear Assurance Corporation (NAC) rcquect for NRC's approval of the purchase of the NFS Erwin, facility and to express iL> concerns about this transfer.
ENCLOSURE C JAN 3 1 SB5
Office of Inspection and Enforcement Items of Interest Week Ending January 31, 1986 1.
The following Sionificant Enforcerent Actions were taken during the part week:
a.
EN 86-03, a Notice of Violation and Proposed Imposition of Civil Penalty in the amour 1 of $1,250 was issued January 28, 1986 to West Virginia University (Morgantown, WV). This action is based en multiple health physics violations which include:
(1) failure to perform bioassays, (2) failure to perform inventories, and (?)
failure to make surveys.
2.
The following IE Preliminary Notifications were issued during the oad week:
a.
PNO-TMI-86-02, GPU Nuclear Corporation (TMI Unit 2), Werker Fa;sts Ta Reactor Building.
b.
PNO-I-86-06, Northeast Nuclear Energy (Millstone Unit 3), Initial Criticality.
c.
PNO-I-86-7, New Hampshire Yankee (Seacrook Unit 1), Discovery of Fake Explosive Device.
d.
PNO-I-86-8, Philadelphia Electric Company (Peach Botton Unit 2),
Unscheduled Shutdown For More Than 48 Hours.
e.
PNO-I-86-09, GPU Nuclear Corporation (TMI Unit 1), Plant Shutdown (Over 48 Hours),
f.
PNO-II 86-09, Nuclear Fuel Services (Erwin, TN), Potential Over-exposure of Workers.
g.
PNO-II-86-10, Virginia Electric & Power Company (Surry Unit 1),
Unscheduled Shutdown Longer Than 48 Hours.
h.
PN0-II-86-11, Carolina Power & Light Company (H. B. Robinson Unit 2),
Loss of Offsite Power Through Startup Electrical Transformer.
i.
PNO-III-86-03As Commonwealth Edison Comoany (Dresden Unit 3), Insula-tion Fire (Update).
j.
PNO-III-86-06, Allied Chemical Company (Metropolis, IL), Uranium Hexafluoride Cylinder Overfill Incident in 1984.
k.
PNO-III-86 -07, Dairyland Power Cooperative (La Crosse), Seal Leakage.
1.
PNO-III-86-08, Detroit Edison Company (Fermi Unit 2), Diesel Generator Firr..
JAN 311956 ENCLOSURE D
. 3.
The following IE Information Notices and IE Bulletins were issued during the past week:
a.
IE Information Notice 86-04, Transient Due to Loss of Power to Integrated Control System at a Pressurized Water Reactor Designed by Babcock & Wilcox, was issued January 31, 1986 to all nuclear power facilities holding an operating license or a construction permit.
b.
IE Information Notice 86-05, Main Steam Safet/ Valve Test Failures and Ring Setting Adjustments, was issued January 31, 1986 to all pressurized-water-reactor facilities holding an operating license or a construction permit.
4 Other Items a.
Technical Training Center (TTC)
The Chairman visited the TTC on the evening of January 30, 1986 and was briefed on TTC operations.
b.
Enforcement Ccnference Director, Enforcement Staff met January 30, 1986 with enforcement coordinators from the regions in Bethesda, MD.
c.
Vendor Program The Vendor Program Branch, Division of Quality Assurance, Vendor, and Technical Training Center, conducted the following inspections this week:
(1) Ger.eral Electric Plant Organization (GENPO), King of Prussia, PA -
identify activities related to nuclear plants that are performed by GENPO, evaluate the adequacy of the ASME IX and XI activities, and review the QA program implementation.
(2) AIRCO, Inc., Cleveland, 015 - review procedures and practices related to the fabrication of welding electrodes in response to a Part 21 report issued by D.C. Cook.
(3) Micro Instrument Corporation, Rochester, NY - review QA program implementation to determine how an incorrect Skir.rer valve was procured and installed in a backup breke system for tiie Auxiliary Building crane at the R. E. Ginna plant.
(4) General Electric, Wilmington, NC - assist 01 in performing an onsite and offisite investigatory effort.
JAN 31163o ENCLOSURE D
. d.
Safety System Functional Inspection (SSFI)
The exit meeting for the Safety System Functional Inspection con-ducted at Arkansas Nuclear One (AND-1) was held with the licensee on January 31, 1986. The emphasis of this inspection was on the emergency feedwater system.
e.
ANSI Subcommittee Meetino Representative of Engineering and Generic Communications Branch (EGCB), Division of Emergency Preparedness and Engineering Response (DEPER) was in Orlando, FL January 29-31 to attend an ANSI Sub-committee meeting.
f.
hon Destructive Examination (NDEl Representative of EGCB, DEPER, was at the EPRI-NDE Center, in Charlotte, NC January 27-28 to participate in a meeting with Utility Tech Advisory Group, EPRI staff, and other NRC staff trembers to review coordination and requalification programs.
JAh 311556 ENCLOSURE D
OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending January 31, 1986 MJItilooD Inteoral Simul? tion Test (MIST)
A Program Management Group (PMG) meeting was held on January 20-22,1986 in Palo Alto, California with the four program sponsors: NRC, Babcock and Wilcox (B&W) Owners Group, B&W, and EPRI. This program includes testing in the MIST facility simulating small break loss of coolant accident (LOCA) and other transients in a B&W reactor geometry.
The objective of this work is to provide data to assess code capability to calculate these transients in B&W reactors. The facility is now in a characterization test phase to calibrate instrumentation and determine actual facility characteristics (volumes, resistances,etc.). This test phase has been extended from the planned 3 months to 4 months due to late installation of the pumps which previously failed to pass acceptance testing. Actual testing is now scheduled to start in May 1986. B&W identified this potential problem only for information and did not recommend ex*,ending the overall program schedule or using funds set aside for testint, problems at this time since the schedule slippage may be recovered during the actual testing.
The PMG also identified a list of 10 potential additional testr to be considered if the contingency tests included in the workscope are not requi md. This list includes a test requested by NRR to study phenomena identified during the analysis of the Davis Besse event.
A report covering the previous Once-Through Integral System (OTIS) test phase is nearly ' complete and should be published within 1-2 months.
3h 31 sS5 ENCLOSURE E
. Results from Hydrogen Testino in the FLAME Facility with ice Condenser Upoer Plenum Simulated Obstacles A recent test in the FLAME facility was conducted and 1/2 scale air handling units were placed in the channel to simulate the ice condenser upper plenum environment.
For this 28.5% hydrogen mixture, a transition from deflagration to detonation (DDT) was observed at about 8 meters down the channel (30 meters long) with a peak over pressure of 220 psi and with flame speeds up to 700 m/s prior to detonation. These results suggest that if a stoichometric mixture exists in the ice condenser upper plenum and if it is ignited, then transition from deflagration to detonation will occur.
These conclusions have been confirmed by a series of 12 small scale tests (mini-FLAME) in which the hydrogen concentration, top venting and channel obstacles were var,ied in a systematic way. To investigate the lower limit of DDT for the it'e condenser upper plenum two more tests are planned. The first test will have a 16% hydrogen concentrati6n test with simple cbstacles and 50% venting and. the second test will have 181 hydrogen concentration with 50% venting ard ice condenser upper plenum simulated cbstacles. These tests are expected to complete the experiments planned for the FLAME facility. The results provide confirmation of issues remaining from the Hydrogen Rule for Ice Condenser PWRs.
Steady-State Fuel Perforrance The FRAPCON-2 computer code was developed by RES for NRR for their review of core reload licensing applications and for audit of codes submitted by reactor fuel vendors.
A typical question raised by NRR during review regards whether the fission gas release to the gap and the consequent rod pressure at er.c of life may cause unacceptable cladding deformation. The FRAPCON code is able to provide answers to such questions.
The final code version has been used to generate fuel performance predictions for selected rods of an evaluated power reactor data sample.
Rod design, operational, and perforrance data were obtained from the EPRI Fuel Performance Data Base.
A report has been issued (NUREG/CR-3741 Vol. 2) which presents comparisons between neesured and calculated fuel and cladding deformation, fission gas release, internal rod pressure, gas ccmposition, and cladding corrosion.
Interpretations are made relative to code error magnitudes, distributions, and trends versus rod design and operations parameters. The results indicate that FRAPCON-2 (VIM 5) is an improved code having adequate capability for best estimate analysis of moderate duty fuel rod performance, up to average buraups of at least 40,000 MWD /MTM.
ENCLOSURE E J AN 31.--coo
. Electronic Transmission of Termination Data 10 CFR 20.408 requires cert n types of NRC licensees to submit personnel identification and exposurt information to the NRC when any individual monitored for radiation dose completes his assignment or period of employment at the licensee's facility. The NRC now receives about 120,000 termination reports each year, 95% of which are for nuclear power plant workers.
The receipt of termination information on paper requires that they be manually processed and entered into the hRC's computerized data system, the Radiation Exposure Information Reporting System (REIRS).
One of the steps being taken to reduce NRC resources expended on the processing of the termination data is to establish a procedure whereby licensees may submit the data on magnetic tape.
In order to make the procedure as efficient as possible, a standard file layout for the data is being developed.
NRC staff have drafted a layout and have transmitted it to the nuclear utilities for their review and comments. More than half of the utilities maintain worker exposure information in a computer system, and it is anticipated that this will encourage them to begin submitting the termination data electronically via magnetic tape or direct linkup.
B. Brooks 42-74577 Results of Public Meetinas on Uranium On December 3-4, 1985, Public Meetings on Ultra-sensitive Bioassay Techniques and Nephrotoxicity of Uranium were held by ine staff at the GSA Auditorium in k'ashington, DC. Approximately sixty people attend:td the bioassay meeting, while 30 were present for the nephrotoxicity meeting. Based on the results of animal experiments, it appears that the limit used for uranium in the kidney may be too high, possibly by a factor of five for soluble u.anium compounds.
It may thus be necessary to lower the NRC limit on the intake of soluble uranium compounds.
If this limit were to be reduced, information gathered at the meeting indicates that a number of practical techniques exist for the measurement of urinary uranium concentrations at sufficiently low levels for determining compliance with lower intake standards.
R. B. Neel 42-74559 a mi 3 1 1935 ENCLOSURE E
. Transfer of UT Technology to Industry An agreement was signed between Battelle Pacific Northwest Laboratory (PNL) ~
and Canbustion Engineering Inc. (CE) on Janua ry 23, 1986, following '
concurrence by NRO, for CE's participation in the NRC's safety research prcgrcm on the 1 valuation and application of an advanced nondestructive exemination technique for inservice inspection of reactor primary system crponents (piping, vessel, cozzles, etc.).
The technique has been named (SAFT-UT) which stands for synthetic aperture focusing techn%ue for ultrasonic testing.
SA"T-UT research was started a decade ago in response to the need for a rnfor icnrovament in the currently practiced techniques for detection and chtracterization of flaws.
The SAFT-UT technology uses the phase and amplitud2 information of signals and the search unit position to fom a highly accurate 3
dimensional image of flaws in components.
The m nhodology was developed and the feasibility established at the University of Ilichigan; work continued to evaluate the technique for flaw sizing c3pability at Southwest Research Institute, and currently work is in prograss at PNL to evaluate, validate and obtain acceptance of SAFT-UT ror actual inservice insp3ction of nuclear power reactors for reliable d?tection and accurate characterization of flaws.
In conjunction with this field impletentation work, the PNL team developed, in 1984, improved prncedures for inspection of intergranular stress corrosion cracking in stainless steel piping and perfomed inservice inspections at two reactor sites of selected stainless steel pipes.
The inspections, conducted at the rea,e::st of !!r,R, used SAFT-UT in a third party role to aid in resolving inspction inconsistencies between several different UT inservice in3rection results for intergranular stress corrosion crecking in boiling mer rcector piping at Dresden 3 and Vemont Yankee reactors.
SAFT-UT prW.rced high resolution images which were easy to interpret and helped to assess tha true state of cracking.
The participation of CE in the SAFT-UT research program is of benefit to f,RC since CE will supply a) invaluable field ex for final b)perience vt.lidation and crplication of the SAFT-UT systen, flawed samples for vali(ation testing, c) technical manpower to work directly with the PHL staff to auTant the research and d) $250,000 to the research program at T D.,
- Stt importantly, CE will work closely with PNL to gain experience and to learn the proper use and application of SAFT-UT; CE will also build, with P!:L 's help, their own 5 AFT-UT system for field inspection work, per.~orn their own additional system application research and will use S!tFT-UT for cermrcial field inservice inspections.
This will mean that the final stage of development of advanced UT technology, the transfer te industrial practice, will be conducted effectively, and be employed in the field to gain wide spread industrial use for more accurate inspections of nuclear power reactors.
JAN 31 EE5 ENCLOSURE E
. RES Rulemaking Activities Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors (Part 50) (Appendix J)
The proposed rule would update and revise the 1973 criteria for preoperational and periodic pressure testing for leakage of primary and secondary containment boundaries of water-cooled power reactors. The revision i: needed to resolve continuing conflicts between licentees and NRC inspectors over interpretations, current regulstory practice which is no longer being reflected accurately by the existing rule, and endorsement in the existing regulation of an obsolete national standard that was replaced in 1981.
Tne proposed rulemaking package, including a backfit rule analysis (coordinated with ELD), was sent to the Office of the Director, RES, for concurrence on January 22, 1986. The backfit rule analysis included in the rulemaking package has been concurred in by a Senior Regulations Attorney in ELD.
ENCLOSURE E JAN 31 3D
. Publications to be Issued in the Near Future
Title:
Design and Fabrication Code Case Acceptability. ASME Section III, Division I (R.G.1.84, Rev. 24)
Descriotion: The guide on Design and Fabrication Code Case Acceptability has been revised to include new code cases, annulled code cases, revised code cases, reaffirmed code cases and reinstated code cases, subsequent to issuance of R-23 of the guide.
Con ta ct:
E. O. Woolridge 443-7917
Title:
Materials Code Case Acceptability, ASME Section III, Division I (R. G.1.85, Rev. 24)
==
Description:==
The guide on Materials Code Case Acceptability has been revised to include new code cases, revised code cases, reaffirmed code cases, reinstated code cases and annulled code cases subsequent to issuance of R-23 of the guide.
Conta ct:
E. O. Woolridge 443-7917
Title:
General Guidance for Designing, Testing, Operating, and Maintaining Emission Control Devices at Uranium Mills (Division 3 Reg. Guide)
==
Description:==
This guide provides guidance for design, testing, operating, and maintaining emission control devices at uranium mills to assure their reliability of performance.
Contact:
M. S. Weinstein 443-7666 JAN 31 Ik3 ENCLOSURE E
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PP0GPAMS WEEK ENDING JANUARY 31, 1986 International Meetings The following international meeting notices supplenent those previously announced:
February 27-28, 1986, Vienna, Austria - Consultants Group Meeting on "Operatirg Procedures for Abnormal Conditions in Nuclear Power Plants" Marcii 4-5, 1986, Vienna, Austria - Consultants Meeting to Define Detailed Scope and Objectives of the IAEA's Technical Committee Meeting on " Gas-Cooled Reactors and Their Applications," to be held in October 1986 in Vienna April 7-10, 1986, Vienna, Austria - Intercomparison Study of Personnel Dosineters Applied in Occupational Personnel Fonitoring in Member States April 21-26, 1986, Kuala Lumpur, Malaysia - Regional Overview Course on Pegulatory Aspects of Radiation and Nuclear Safety May 5-9, 1986, Vienna, Austria - Technical Conmittee Meeting on
" Identification of Failure Secuences Sensitive to Human Error" May 12-16, 1986, Vienna, Austria - Advisory Group Meeting to Assist IAEA Secretariat in the " Preparation of a Guidebook on Research and Development Support for Nuclear Power" May 12-16, 1986, Vienna, Austria - Technical Committee Meeting
" Assessment of Occupatior.al Exposure to External Irradiation for Monitoring Purposes" Foreien Visitors On Monday Jean Bussac, Deputy Director, accompanied by Andre Schmidt, French CEA Institute of Protection and Nuclear Safety, met with RES and NMSS for a general exchange of views on nuclear safety and waste r.anagement research, a review of the status of current projects, and a discussion concerning proposed cooperation.
Following a two-week schedule of neetings and site visits to LASL, SNL, and ORNL to review current projects, Mr. Schmidt will return to NRC on Monday, February 10 for a half-day review of their laboratory visits.
On Friday Roland Naegelin, Director of the Swiss Federal fluclear Safety Inspectorate, met with IP, NRR, and RES representatives. There was an extensive exchange of questions and information on current reactor licensing issues in the U.S. and Switzerland.
ENCLOSURE G JAN 31 h'
0FFICE OF RESOURCE MANAGEMENT Item Of Interest Week Ending January 31, 1986 FY 1987 Eudget The " Green Book" - FY 1987 budget submission was provided to OMB in draft.
Guidance, received from the Commission, was incorporated into the final version and sent to the printer.
It will be available early next week for submission to Congress.
ENCLOSURE I JAN 31:EC5
OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEMS OF INTEREST Week Endina January 31, 1986 The current AEOD Trends and Pan.
Program Plan was issued January 30, 1986. This plan revises and e a
, AE0D/P402, Trends and Patterns Program Plan FY 1984 - FY 1986, which was distributed in March 1984.
Our experience in carrying out the original plan and changes in reporting requirements have been reflected through changes in the content of the Program. A principal change from our original approach is rather than sweep through the LER data base in a general way at the event level and component level, we intend to foct.s more directly on analysis at the event level, i.e.,
reactor trips, ESF actuations, system unavailabilities, and technical specification violations, and to cover these subjects in greater detail in yearly reports. This approach is more suited to making use of the detailed information provided in LERs after implementation of the LER Reporting Rule, 10 CFR 50.73, in January 1984. Also, trend and pattern analysis of component level data will be performed using NPRDS data, again consistent with the de-emphasis of individual component failures in post-1983 LER data and improvements in the NPRDS.
ENCLOSURE J JAa, 5 1,e,c,o,
0FFICE OF SMALL AND DISADVANTAGED BUSINESS UTILIZATION / CIVIL RIGHTS Item of Iterest Week Ending January 31, 1986 Small and Disadvantaged Business Utilization Procram On Friday, January 24, 1986, Atlanta University hosted an NRC sponsored symposium for twenty-five (25) Historically Black Colleges and Universities (HBCUs).
Dr. J. Nelson Grace and Theresa Spearman from Region II, as well as Von Deloatch from OSDBU/CR participated in the program for NRC. The technical presenters were Robert J. Sorenson and Walter J. Apley from Battelle Pacific Northwest Laboratories. They discussed such subjects as technology transfer and the U.S. Nuclear Power Industry, including a range of topics from nuclear power development, energy processes and safety in the U.S. to the r.uclear industry future perronnel demands.
This was followed by a question and answer session and identification of potential areas for follow-up efforts.
ENCLOSURE K JA!i 31 EE3
REGION !!!
STATUS REPORT DAVIS-BESSE LOSS OF FEEDWATER EVENT JANUARY 31, 1986 Plant Status The plant remains in cold shutdown. Troubleshooting of the safety features actuationsystem(SFAS)iscontinuing. Troubleshooting completed so far has revealed that the blocking circuit does not function properly for one of two SFAS actuated barated water storage tank suction valves. The problem appears to be the result of improper circuit design..
Restart Activities A NRR maintenance survey inspection wf!1 be on site February 18-21 to
++
followup on previous findings and to evaluate the licensee's actions concerning r.anagement practices as they relate to the maintenance 6rea.
MOVATS testing, environmental qualification work and other maintenance
++
activities continue on the 167 safety-related motor-operated valves onsite.
The licensee has completed all work on forty eight valves and returned them to service. The licensee is repairing and testing valve motor operators continuously with three overlapping ten-hour snifts.
The NRC test review team continues to provide weekly coverage of licensee
++
testing activities.
Testing of the motor-driven feed pump has been completed satisfactorily at cold shutdown conditions. Additional testing is scheduled for hot standby. An operational retest of the fire and radiation alarms was also completed following repair.
Repairs and testing of the Incore Monitoring system is continuing.
Live transfer of the 480v switchgear is scheduled later this week.
Further system testing awaits completion.of equipment rodifications..
_0ther Activities Inspecticns of safety system piping supports in the auxiliary building are continuing. Evaluation of the nonconformances (NCR) found on supports in containment is in progress.1 Of the support NCRs requiring disposition prior to restart, eighteen remain to be dispositioned.
The licensee is continuing to investigate the cause of the restricted flow of water from Lake Erie to the plant that occurred in December,1985. The investigation is being hampered by lake ice conditions.
The flow has returned to normal.
ENCLOSURE L JAN 311E55
The licensee's inspection and review of items requiring environmental qualification continues to identify components that require repair,
++
replacement, or further engineering evaluation.
Last week it appeared that the post-accident containment radiation monitoring instruments were not environmentally qualified.
This conclusion was based on a review of records.
Inspection of the actual installation revealed that the component that was thought to be unqualified was environmentally qualified and the records were incorrect.
Specifications.
These instruments are required by the Technical.
tketings On February 5,1986,'the Babtbck and'Vilcox owners group will meet with the NRC in Washington to discuss their activities in response to the December event at Rancho Seco and the June event at Davis-Besse.
On February 6,1986, the ACRS will meet with the NRC staff and Toledo Edison in Washington tc discuss the safety evaluatuon report on and the status of activities being conducted in response to the June event.
EUCLOSURE L JAF 311955 2
4 ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING 1/31/86 A.
STAFF REQUIREMENTS - DISCUSSION OF REVISIONS TO NRC SUNSHINE ACT REGULATIONS, 1_0:00 A.M., FRIDAY, JANUARY 17, 1936, COMMIS3IONERS' CONFERENCE R00M, D.C.
OFFICE (OPEN TO PUBLIC ATTENDANCE Memo SECY to RECORD dated 1/24/86 The Co=ission met with the Of fice of the General Counsel to discuss the draft final " Sunshine Act Rule" (SECY-85-67A).
The Co=ission agreed to withhcid final action on SECY-BS-67A until the Administrative Law Section of the American Bar Association has issued its findings on the rule and the Office of the General Counsel has briefed the Commission on the findings of the ABA.
Chairman Palladino requested that the Commissioners revise their vote sheets on SECY-S5-67A, if necessary, as per the discussion and provide them to the Office of the Secretary.
B.
STAFF REQUIREMENTS - BRIEFING BY DOE ON MONITORED RETRIEVABLE STORAGE, 2:00 P.M., THURSDAY, JANUARY 23, 1986, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE OPEN TO PUBLIC ATTENDANCE Memo SECY to RECORD deted 1/30/86 The Co=ission was briefed by Ben Rusche, Director, Office of Civilian Radioactive Waste Management, U.S. Department of Energy (DOE) and Keith Klein, Deputy Associate Director for Storage and Transportation Systems, Office of Civilian Radio-active Yaste Management, DOE on a proposal for constructing and operating a facility for monitored retrievable storage (MRS).
Chaincan Palladino requested that Commissioners vote as soon as possible on SECY-86-9.
ENCLOSURE O JAN 311955
2 C.
STAFF REQUIREMENTS - BRIEFING ON STATUS OF REPORT OF TASK FORCE ON TECHNICAL SPECIFICATIONS, 2:00 P.M., TUESDAY, JANUARY 21,1986, C0!iMISS10NERS' CONFERENCE ROOM, D.C. OFFICE OPEN TO PUBLIC ATTENDANCE) Meno SECY to V. Stello and H. E. Plaine dated 1/30/86 The Co=ission met to be briefed by staf f on staf f's "Recommen-dations for Improving Technical Specifications" (SECY-86-10).
Comissioner Asselstine requested that the Of fice of the General Counsel examine the bases for enforcement of technical specifications requirements as opposed to alternative tools for implementing regulatory requirements such as Final Safety Analysis Report (FSAR) commitments.
(OGC)
(SECY Suspense:
2/14/86)
Commissioner Asselstine requested that the staff provide a written comparison of which items would be regulated under technical specification requirements and what kinds of items would come under alternatives such as FSARs for the Wolf Creek plant.
(NRR)
(SECY Suspense:
1/31/86)
Commissioner Zech noted that he has asked the staff to look into the need for all of the surveillance testing and maintenance required during power operation.
Chairman Palladino suggested that, per staff's recommendation, the Atomic Industrial Forum (AIF) be invited to brief the Commission on technical specifications improvements.
(Subsequently, a briefing by AIF was tentatively scheduled for Tuesday, February 11, 1986.)
Chairman Palladino requested that Commissioners forward to the staff any further questions the might have on SECY-86-10.
(OCM)
JAfi 3113E5 ENCLOSURE 0
3 D.
STAFF REQUIREMENTS - AFFIRMTION/ DISCUSSION AND VOTE, 3:30 P.M., THURSDAY, JANUARY 23, 1986, C0!NISS10NERS' CONFERENCE ROOM, D.C. OFFICE OPEN TO PUBLIC ATTENDANCE) Memo SECY to V. Stello cated 1/30/86 I.
SECY-85-209A - Final Regulttiens on No Significant Hazards Consideration (The " Shelly Amendment")
The Commission by a 4-1 vote approved final regulations imple-renting the Sholly Amendment providing for requested operating license amendments involving no significant hazards consid-erations before the conduct of any hearing.
Co=issioner Asselstine disapproved t'rie final rule and provided separate views (attached) to be published with the Federal Register Notice.
The Co=ission also agreed that the Federal Register notice should be modified in accordance with points 2, 3,
and 4 of the January 9, 1986 OGC memo (attached).
You should revise the Federal Register Notice as noted, review it for any necessary editorial corrections and return it for signature and publication.
(EDO)
(SECY Suspense:
2/24/86)
The Cc=ission also agreed that if the staff believes legis-lation changes to Section 189a of the Atomic Energy Act are needed a recommendation should be made to the Commission.
Attachments: (.506 Gehd.ed As stated JAN 311936 ENCLOSURE O
E a-to NRR MEETING NOTICES *
((,
JANUARY 31, 1986
=
o>
DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 2/4/86 50-259 P-110 Discuss TVA's program to TVA & GE R. Clark 9:00 a.m.
50-260 Phillips Bldg.
environmentally qualify cable at 50-296 Browns Ferry.
2/4/86 50-029 Yankee Nuclear Discuss staff comments on the Yankee Atomic J. Clifford 12:00 p.m Power Station licensee's PRA associated with Electric Co.
Rowe, MASS.
SEP Topic III - 2; Winds and Tornadoes.
2/5-6/86 YAEC Corporate 8:30 a.m.
Of fices Framingham, MASS.
2/5/86 50-280 P-110 Discuss the Integrated VEPC0 T. Chan 10:00 a.m.
50-281 Phillips Bldg.
Implementation Schedule Surry &
50-338 North Anna 50-339 2/5/86 50-395 V.C. Site To tour the site and corporate South Carolina J. Hopkins 8:00 a.m.
Jenkinsville, S.C. headquarters.
Electric & Gas Co.
Corporate Hdq.
Columbia, S.C.
2/6/86 50-443 Seabrook Site 10 CFR 73.55 confirmatory security Seabrook Nuclear V. Nerses 8:30 a.m.g 50-444 Seabrook, N.H.
site visit and meeting.
Power Station P8 5
m u
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
E 2-eo NRR MEETING NOTICES
- ni 0$
JANUARY 31, 1986 DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 2/5/86 P-118 Overview of B&W Owners Group B&W Owners Group W. Paulson 10:00 a.m.
Phillips Bldg.
Activities.
1:15 p.m.
Discussion of the B&W Owners Group program with regard to the Dec. 26 Rencho Seco event and the Davis-Besse June 6, 1985 event.
2/12/86 bO-305 Room 5033 Discussion of licensee's Detailed Kewaunee Nuclear M. Fairtile 8:30 a.m.
Air Rights Bldg. Control Room Design Review Summary Power Plant Report.
2/12/86 50-321 Edwin I. Hatch Discuss the GPC plans related to Georgia Power Cc.
G. Riverbark 2:00 p.m.
50-366 Nuclear Plant Hatch Unit 1 and 2 and the status Baxley, Georgia of Hatch 1 and 2 licensing activities.
2/12/86 50-219 Room P-114 Discuss the draft integrated GPUNC J. Donohew 1:30 p.m.
Phillips Bldg.
schedule for Oyster Creek (Generic Letter 85-07 dated May 2, 1985).
E o
E E
M Copies of summaries of these meetings will be made publicly available and placed in the respective der.ket file (s) in the NRC and local public document rooms
E NMSS MEETING NOTICES FOR WEEK ENDING: 1/31/86 Division of Fuci Cycle and Material Safety
'8, DOCKET ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 2/5/86 Willste Meeting with American Nuclear Reps fm ANI, Loysen Insurers (ANI) to discuss fire NRR & FC protection of mobile radwaste incinera tors.
2/10/86 71-6639 Willste Discuss Model MH-1A.
Reps of 00:
Odegaarden 9:00-11:00 Room 829 R. Odegaarden (FC)
H. Lee (FC)
B. Lake (FC)
C. MacDonald (FC) 2/18-21/86 Project West To discuss various topics on T. Clark (FC)
Clark M-32
- Valley, the solidification of high-1cvel N. Davison (FC)
NY waste at West Valley.
Reps of West Valley 2/11-14/86 Las Vegas, To attend meeting of the Nondes-D. Chape11 (TC)
Chape11 NV tructive Testing Management B. Carrico (FC)
Association.
Division of W3ste Management 2/5-7 Colorado State Univ.
Meeting on Geotechnical and MFliegel MFliegel Geohydrolic Aspects of WM 5 WMGT s ta f f 2/10 Savannah, GA A5ME/EPRI Radwaste Workshop TCJohnson TCJohnson 2/10-12 Washington, DC Nat'l Council of Ameitan CRussell CRussell Indians Executive Council Meeting SWeissberg, SP 2/27-3/1 State of Illinois int'l Symposium on Alternative RBrowning RJStanner g
Chicago, 111 LLW Technologies RJStarmer P
S CM Division of Safeguards m
None
$2 e.3 January 31, 1986 sa
[h),
OSP MEETING NOTICES DATE/ TIME LOCATION PURPOSE ATTENDEES NRC CONTACT 2/10/86 Montgomery, AL Meeting with State Health Dr. Myers, AL R. Trojanowski Dept. Officials on Agree-Dr. Fox and ment State Program and AL Staff Nov. 85 EP Drill at N. Grace, RII Browns Ferry W. Kerr, OSP R. Trojanowski, RII E
P S
E m
"U
EDO PAPERS TO THE COMMISSION WEEK ENDING JANUARY 31, 1986 1.
SECY 86 SECY 85-163/163A - Station Blackout, Unresolved Safety Issue (USI) A-44 (1-2.8-86)
To provide the Commission with the staff's backfit analysis for the proposed rule on Station Blackout.
2.
SECY 56 Response of GPU Nuclear Corporation (TMI) to Proposed Civil Penalt/ for Discrmination (EA 84-137)
(1-29-86)
To advise the Conmission of the staff's intention to issue an order imoosing civil monetary penalty to GPU.
3.
SECY E6 Response of Mississippi Power and Licht Company (Grand Gulf) to Proposed Civil Penalty for Material False Statements recarding Technical Specifications (EA 84-75)
(1-29-86)
To obtain Conmission apcroval to issue an order imposing part of the civil penalty proposed in the Notice of Violation and Proposed Imposition of Civil Penalties issued on March 21, 1985 to Mississippi Power and Light Company (MP&L) regarding naterial false statements (MFS) involving Grand Gulf's Technical Specifications.
4.
SECY 86 33 - Preliminary Report on the Safeouards Doerational Data Analysis Systen (1-29-E6)
To describe to the Conmission the NMSS Safeguards Operational Data Analysis System and its planned uses.
5.
SECY 86 Materiai False Statements (1-30-86)
To provide a revised proposal on material false statements 6.
SECY 86 Nuclear Plant Reliability Data (hPRD) System (1-30-86)
To provide the Comissioners with information on the current status of the NPRD System.
7.
51CY 86-1 A - Status of Staff Actions P.egarding TVA (1-31-86)
To provide the Conmission with a status report on staff activities in response to issues associated with TVA. This is the second status report on this topic.
JAN 31 So ENCLOSURE Q
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AECL-8592 PODSIPS A COMPUTER PRCGRAM FOR THE EVALUr. TION OF POINT-DEFECT O'
PROPERTIES IP1 METALS AECL-8400 LOCA SIMULATION TESTS IN THE RD-12 LOOF HITH MULTIPLE HEAT CHANNELS AECL-8403 REMOVAL Of 10D0iiTH4NE FROM AIR USING A PILOT-SCALE CORONA DISCHARGE SCRUDBER FRANCE:
CEA INFORMATION tl0TES, NO. 12. DECEMBER 19858
- 29TH IAEA GENERAL CONFERENCE, VIENHA, SEPTEMBER 23-29, 1985
- COST OF ELECTRICITY FRODUCTION FROM THERMAL, NUCLEAR-OR CDAL-50UFr,t3 SN NO. 47 BULLETIN OF NUCLEAR INSTAILATIOi!S SAFETY - SEPTEMBER-0CTOBER 1985 EdF f0'lillLY GENERAL RE3ULTS OF FRENCH NUCLEAR P0HER PLANTSNM - DECEMBER 1985 JAPAN JAIF ATL'MS IN JAPAN, OCTOBER AND NOVEMBER 1985MM UNITED KINGDON:
SRD M 227 TRIT 0X - A COMFUTER PROGRAM TO ESTIMATE COMMITTED DOSES IN THE VICINITY OF BUILDING 3 AFTER RELEASING 1RITIUM OXIDE - PROPRIETARY M Cat EUR 9708 EN PROCEEDINGS OF THE 1984 INTERNATIONAL CONFERENCE ON PLASMA PHYSICS LAUSANNE, JUNE 27-JULY 3, 1984 EUR 9772 EN EC STATIC HIGH-TEMPERATURE LEACH TEST EUR 9876 EH RATCHETTING IN Ti1E CREEP RANGE EUR 9961 FR STORAGE OF RADIDACTIVE HASTES IN GRANITIC ENVIRONMEN',
EUR 9980 EN THE EFF ECTS OF BUILDINGS ON LOH-LEVEL ATMOSPHERIC DISCHARGES EUR 9992 FR EXPERIMENTAL PROGRAM F3R THE S'ORAGE OF SPENT FUEL - PHASE 12 g
RELIABILITY STUDY
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EUR 10107 EN SURVEY OF EXISTING LITERATURE IN THE FIELD OF SHOCK-ABOURBI;10 MATERIALS HITH A '"IEH TO SUBSEQUENT ADAPTATION OF PLASTIC t,
DEFORMATION CODES - PHASE 1 EUR 10118 EN QUALIFICATION, TRAINING, LICENSING AND RETRAINING OF OPERATING SHIFT PERSONNEL IN NUC8 EAR POWER PLANTS EUR 10126 EN COMPARISDN OF MATERIAL PROPERTY SPETIFICATIONS OF AUSTENITIC SIEELS IN FAST BREEDER PEACTOR TECHNOL06.
EUR 10190 IT THERMAL BEHAVIOR OF THE CLAY FORMATIONS ISSN 0014-2352 EURO ABSTRACTS, VOL. 23, NO. 9, SEPTEMBER 1985 DECD/NCA :
NEA EPIDEMI010GICAL ST!JDIES OF GROUPS HITH CCCUPATIONAL EXPOSURE TO RADiATIDHMM, PARIS 1985 IRS NO. 597 LOVIISA, FINLAND - UNIDENTIFIED RISK OF TOTAL LOSS OF P0HER IN CASE OF A MAIN TRANSFORMER FIREMM - PROPRIETARY M DELEl*D FROM PCR COPY MM INDItaTES THE DOCUMENTS ARE IN ENGLISH E
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