ML20138N515
| ML20138N515 | |
| Person / Time | |
|---|---|
| Issue date: | 12/19/1985 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-851213, NUDOCS 8512240041 | |
| Download: ML20138N515 (38) | |
Text
h.
.<.J .
s December 19, 1985 i
For: The Commissioners l
l From: T. A. Rehm. Assistant for Operations, Office of the ED0 l
l
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING DECEMBER 13, 1985 l
! A sunnary 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
! Nuclear Material Safety and Safeguards C Inspection and Enforcement D Nuclear Regulatory Research E Executive Legal Director F*
International Programs G f State Programs H i Resource Management I*
I Analysis and Evaluation of Operational Data J*
Small & Disadvantaged Business Utilization & Civil Rights K*
Regional Offices L CRGR Monthly Report M*
Executive Director for Operations N*
Items Addressed by the Commission 0* i Meeting Notices P Proprietary or Other Sensitive Information (Not for Q
- external distribution) j
~
- No input this week. -
/
,s, ,<
~)
05122 1 851219 ! O b#---
MS NRcc .
u.
T. A. Rehnt,-Assistant for Operations
%gt,y1NFOREPT PDR Office of the Executive Director !
for Operations l t
Contact:
l T. A. Rehm, ED0 I 492-7781 '
. _ _ _.-_~ -- _ _ . - - - - . . . _ - - - - .- - ---
l
, s .
I .
, HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING DECEMBER 13, 1985 Catawba Unit 2 On December 5, 1985. Duke Power Company performed the break-in run of Catawba Unit 2 TDI diesel generator 28. During this test the No. 7 main bearing failed. This bearing was a replacement to the bearing that failed on or about November 20, 1985, during the return to service testing of the 28 diesel. Duke Power attributed the cause of the November 20, 1985, failure to an inadequate support. The cause of the December 5, 1985, failure is attributed to an installation problem, poss.ibly improper alignment. More detailed examination is underway.
The November 20, 1985, caused a one week slip of the fuel load date for Catawba Unit 2, from January 15, 1985, to January 22, 1985. The delay resulting from.the December 5, 1985, failure has not yet been assessed by Duke. -
Trojan At approximately 6:00 p.m. EST on December 9, 1985, during routine preventative maintenance of Emergency Diesel Generator-A, a 16 oz.
ball-peen hammer was found underneath the valve cover. It was found in a position on a ledge where continued operation may have vibrated it into an area where it could damage the generator.
The licensee identified this as a potential act of sabotage when initial investigation found no recent maintenance requiring the use of a ball-peen hammer and that a mechanic who had access to the EGDs had been recently discharged. On December 10, 1985 at approximately 2:00 p.m. EST, NRC-Region V, the FBI, and the Incident Response Center (IRC) were notified.
The licensee has searched and successfully tested both EGD-A and EDG-B and both are currently operable. The plant is currently running at 100%. The licensee is in the process of a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> walk-through of all safety related systems that could easily be tampered with (i.e., valve positioning, cut wires, etc.). Region V has asked to be immediately notified if anything else is found.
1 ImplementationofUS/IAEASafeguardsAgreerg Initial inspections have been successfd% craileted by the IAEA to verify design information from the three ned.y sa*g.- m d facilities (Westinghouse LEU fuel fabricatien and the Salem-1 and Turkey PoTnt-4 reactors). Input data for the preparation of Facility Attachments was collected.
( DEC 131985
, s I -
OFFICE OF ADMINISTRATION Week Ending December 13, 1985 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision
. Carryovers, 1984 179 23 Received, 1985 819 41 Granted 635 31 Denied 182 19 Pending 181 14 ACTIONS THIS WEEK Received Richard A. Cardenas Requests records identifying training required by the (85-796) October 29, 1981, license issued to the Department of the Air Force, Kelly AFB, and the provisions of Title 10 Parts 10 and 19.
Melody Johnson Requests copies of Material Control and Accounting (85-797) Progress Reports filed with the NRC during the period June 1974 - January 1975 pertaining to License SNM-ll74 issued to the Kerr-McGee Cimarron facility.
Jim Pedro, Requests copies of the enclosures to the NRC meeting NUS Corporation summary dated October 9,1985, regarding the October 1, (85-798) 1985, meeting with Philadelphia Electric Company representatives.
Billie P. Garde, Requests all records developed by the Comanche Peak Government harrassment and intimidation panel report issued Accountability November 4, 1985.
Project (85-799)
Billie P. Garde, Requests all records regarding the career progression Government of a named NRC employee.
Acountability Project (85-800)
Billie P. Garde, Requests all records which NRC received from INPO, TVA, Government or any private industry representative regarding a Accountability named NRC employee and the operator training report at Project Beaver Valley.
(85-801)
CONTACT: Donnie H. Grimsley ENCLOSURE A 492-7211 DK ) IS85
.1.
2 Received, Cont'd (NRC employee) Requests records regarding an EE0 matter.
(85-802)
Steven C. Sholly, Requests a copy of Science Applications, Inc., Final MHB Technical Report SAI-354-84-9A, " Containment Event Trees for Associates PWRs and BWRs," dated February 1983.
(85-803)
Steven C. Sholly, Requests copies of ORNL/SAIC Report, "An Evaluation of MHB Technical BWR Over-Pressure Incidents in Low Pressure Systems" Associates of May 1985 and any subsequent versions; NUREG/CR-4135
~ (85-804) of May 1985; and all technical reports prepared by Sandia pursuant to FIN A-1227.
Patty Day, . Requests copies of five specified records referenced NUS Corporation in NUREG-0474.
(85-805)
Patty Day, Requests copies of two specified records regarding NUS Corporation Topical Report NED0-10859.
(85-806)
Billie P. Garde, Requests copies of any requests by ASLBP to establish a Government second docket in the Comanche Peak OL hearing to hear the Accountability issues of harrassment and intimidation which is Project referenced in the March 30, 1984, Fedeal Register notice.
(85-807)
Billie P. Garde, Requests all records related to the overview, regulation, Government and investigation of the adequacy of training of Accountability operators at the Beaver Valley nuclear power plant and Project all subsequent action taken by the NRC about the reported (85-808) problems.
T.P. Bracke, Requests records relating to F01A-85-540.
Combustion Engineering, Inc.
(85-809)
Edward R. DeLouise, Requests a list of names and addresses of licensees City of New Haven located in New Haven, Connecticut.
(85-810)
Betty Weaver, Requests a record indicating the name of the contractor The Industrial and prices paid for each examination outlined in Item Health and Hygiene 1 of RFQ-RI-86-21.
Group, Inc.
(85-811)
George W. Dawes, Requests copies of all records pertaining to Molycorp, Molycorp, Inc. Washington, PA, License No. SMB-1393, for the years (85-812) 1965 through 1985.
ENCLOSURE A i
DEC 131985
3 Received, Cont'd Jack Lail, Requests copies of NRC's response to the November 18, The Knoxville 1985, letter from Rep. John Dingell to Chairman News-Sentinel Palladino and all letters dated between October 30, (85-813) 1985, and December 6, 1985, to TVA from the Commissioners, the EDO, IE, and NRR.
Marvin M. Turkanis, Requests copies of all records dealing with a complaint Neutron Products or notification by Siemens Corporation against Neutron Inc. Products regarding its performance on a Siemens' (85-814) teletherapy unit at Metropolitan Hospital, San Juan, Puerto Rico.
Janet G. Aldrich, Requests, on behalf of an NRC employee, records Polydoroff and regarding an EE0 matter and a security file violation.
Miller, P.C.
(85-815)-
(NRC employee) Requests three categories of records regarding a (85-816) security file violation.
(NRCemployee) Requests three categories of records regarding a (85-817) security file violation.
(An individual Requests records regarding himself.
requesting records about himself)
(85-818)
Charles Barnes Requests copies of all facility docket file records (85-819) maintained in Docket 40-6175, Kerr-McGee Oil Industries, which have been retired.
Granted Zinovy V. Reytblatt, In response to a request for four categories of records Illinois Institute related to leak rate testing, made available one record.
of Technology Informed the requester that one additional record (85-724) subject to this request is already available at the PDR.
John Harrison, In response to a request for records providing, by year The Columbian from 1975 through October 1985, for all irradiated fuel (85-731) shipments entering the United States via the ports in Oregon and Washington, the date, port, amount, and model of cask used, informed the requester that the NRC has no records subject to this request.
Blair Childs, In response to a request for a list of NRC Senior Senior Executives Executive Service (SES) employees, made available a Association copy of the requested list.
(85-768)
ENCLOSURE A DEC 101985 l
L
4
. Granted, Cont'd (NRCemployee) In response to a request for copies of records (85-783) pertaining to the selection under Vacancy Announcement No. 84-2556-4, informed the requester that the vacancy announcement was cancelled.
Dave Skripol, In response to a request for a listing of the Fenn Manufacturing organizations licensed to machine Magnesium-Thorium, (85-785) made available a copy of the requested list.
(Anindividual In response to a request for records pertaining to requesting herself that are maintained by the NRC, informed the information about requester that the NRC has no records pertaining to herself) her in its radiation exposure, document control, or (85-792) security systems of records.
Denied -
None ENCLOSURE A DEC 131985
U L WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS
- WEEK ENDING DECEMBER 13, 1985
'RFP ISSUED RFP No.: RS-ADM-86-217
Title:
" Acquisition Training"
Description:
The contractor shall present " Acquisition Training" to NRC technical employees responsible for monitoring contractual arrangements.
Course materials will be provided by the NRC.
Period of Performance: Two years Sponsor: Office of Administration Status: RFP issued on December 3, 1985. Proposals due January 3, 1986.
PROPOSALS UNDER_ EVALUATION RFP No.: RS-ORM-85-336
Title:
"ADP Information Technology Support Center"
Description:
End-user computing support services for users of NRC microcomputers and NRC users of the NIH computer facility.
Period of Performance: Two years Sponsor: Office of Resource Management Status: RFP closed on December 6, 1985. Proposals forwarded to Source Evaluation i Panel for review on December 9, 1985.
RFP No.: RS-ORM-85-335
Title:
" Integrated Library System"
Description:
Sof tware maintenance support and timesharing services for the ;
Integrated Library System. {
Period of Performance: Two years with one option year.
Sponsor: Office of Resource Management -
7 Status: RFP closed on December 10, 1985. Proposals forwarded to Source Evaluation Panel for review on December 10, 1985. :
RFP No.: RS-SDB-85-387 j
Title:
" Development of Business Opportunities for High Technology Small Business Firms with the U.S. NRC" :
[
Description:
The contractor shall analyze the nature of the prime contract and (
subcontract market within the nuclear arena to establish a comprehensive ;
listing of small business firms, including 8(a) firms, capable of ;
performing NRC's technical requirements. [
Period of Performance: One year I Sponsor: Office of Small and Disadvantaged Business Utilization / Civil Rights ;
Status: The competitive range has been established and negotiations are scheduled for the week of December 16, 1985.
I t
I r
ENCLOSURE A
, DEC 1 L E85 L
Weekly Information Report Division of Contracts RFP No.: RS-0IE-85-156
Title:
" Technical Assistance in Developing and Implementing Programs and Procedures for Reactors Requiring Special Inspection Resources"
Description:
The objective of this project is to provide technical assistance to i the NRC for activities pertaining to problem reactors during construction and operation, including development of an NRC program that standardizes inspection procedures for significant problem areas and emergency outages, and assisting in inspections.
Period of Performance: Three years Sponsor: Office of Inspection & Enforcement 2 Status: Best and Final offers are due on December 30, 1985.
RFP No.: RS-0IE-85-167
Title:
" General Course in Non-Destructive Examination Technology and Codes" l
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 inspection of NRC licensed facilities under construction or modification to determine whether or not such facilities and components are constructed properly in accordance with applicable codes and standards.
Period of Performance: Three years Sponsor: Office of Inspection & Enforcement
'sta tus : Best and Final offers received en December 9, 1985, and forwarded to j Source Evaluators for review on December 10, 1985.
1 i
)
i i
9 t
i -
l ENCLOSURE A '
DEC 131985
. , 1 -
, OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST' Week Ending December 13, 1985 Grand Gulf, Unit 1 The licensee has issued an interim report on the cracks found on the i
outside surface of a cross-shaped fitting in the recirculation piping.
The cross (24-inch fitting) connects diameter the recirculation to the jet pump ring supply pump headerdischarge (16-inch pipe diameter). 'These cracks were found after the induction heating stress improvement (IHSI) process was applied to the recirculation piping 1
welds. .
These cracks have been found to be surface cracks that were caused by the special forging process used for these fittings. The effect of the IHSI process was to open the cracks somewhat; however, IHSI did not cause the cracking. The Engineering Branch, DBL is pursuing a generic inquiry to determine if fittings made by this special forging process were used in other BWRs.
The response to this generic inquiry is not considered to be urgent because the depth of the cracks compared to the cross fitting's wall thickness is small enough that piping integrity is not significantly ;
affected. The licensee has determined that the special forging process '
used for the cross fittings is unique and therefore other forged fittings at Grand Gulf, Unit 1 are not likely to have similar cracks in :
them.
Catawba Unit 2 f
On December 5,1985, Duke Power Company performed the break-in run of '
Catawba Unit 2 TDI diesel generator 28. During this test the No. 7 main bearing failed. This bearing was a replacement to the bearing that failed on or about November 20, 1985, during the return to service L
testing of the 2B diesel. Duke Power attributed the cause of the '
November 20, 1985, failure to an inadequate support. The cause of the December 5,1985, failure is attributed to an installation problem, possibly improper alignment. More detailed examination is underway. '
The November 20, 1985, caused a one week slip of the fuel load date for Catawba Unit 2, from January 15, 1985, to January 22, 1985. The delay resulting from the December 5,1985, failure has not yet been assessed by Duke.
ENCLOSURE B DEC 1 E35 *
. ,m -... . , - - . , _ - - _ .
-e _ _ .
Rancho Seco Nuclear Generating Station Reactor Trip The Rancho Seco Nuclear Generating Station is in hot shutdown following an inadvertant reactor trip from 91% power at 5:11 p.m., PST on December 5, 1985. The reactor trip resulted from an operator error during the transfer of ICS control from manual to automatic. An improper demand setting on a controller caused feedwater flow to increase when automatic control was selected. The operator switched back to manual control when the increased feedwater flow was noted.
The "A" feedwater flow indicator stuck in the high flow position. The operator continued to manually decrease "A" feed flow while focusing on the faulty flos indicator. The "A" steam generator level decreased, causing overheating in the primary system. The reactor tripped on overpressure.
All major systems functioned normally during the shutdown. The licensee is performing an evaluation of the plant response and expects to commence restart during the week of December 12, 1985.
Crystal River 3 - Additional AFW Actuations On December 3, 1985, CR-3 tripped fron 93% power due to loss of the 6.9KY bus supplying two of the four reactor coolant pumps. A presumed pressure spike in the steam generators caused a spurious EFIC trip and AFW initiation. The operators secured MFW and allowed AFW to run. It controlled as expected for 20 minutes until it was secured and MFW reinitiated.
The following is based on very preliminary information. During the evening of December 7,1985 with the unit in Mode 3 after the above bus failure, a vital bus feeding the EFIC system lost power during attempts to improve the functioning of vital bus transfer switches. This results in a one-half EFIC trip upon repowering. Continued testing introduced another half-trip and AFW was initiated. "B" steam generator feedwater and all MSIVs were isolated. Primary pressure and temperature were controlled using steam generator blowdown lines. MFW was restored within 10 minutes and the MSIVs opened within one hour.
Subsequently, early Monday morning, the plant was restarted.
3 NRC staff expressed concern about the possibility of a similar event at power, which might preclude all AFW in the event of failure of the motor-driven AFW loop. FPC was asked to explain this transient and the restart decision during the meeting scheduled for yesterday, December 10,1985, at 1:00 p.m.
ENCLOSURE B DEL 1 e 1985
f Palo Verde Unit 1 Palo Verde Unit I achieved the 100% power level for the first time at about 6:00 p.m. on December 10, 1985. Several hours later, the plant underwent a controlled shutdown due to leaking tubes in the condenser.
Examination of the condenser revealed one sheared tube and another leaking tube. Repairs are underway. The plant is currently in Mode 2 at essentially zero power.
Palo Verde Unit-2 A low power license was issued to Palo Verde Unit 2 on the evening of December 9,'1985. Initial fuel loading commenced just before midnight on December 11, 1985.
Trojan At approximately 6:00 p.m. EST on December 9, 1985, during routine preventative maintenance of Emergency Diesel Generator-A, a 16 oz.
ball-peen hammer was found underneath the valve cover. It was found in a position on a ledge where continued operation may have vibrated it into an area where it could damage the generator.
The licensee identified this as a potential act of sabotage when initial investigation found no recent maintenance requiring the use of a ball-peen hammer and that a mechanic who had access to the EGDs had
, been recently discharged. On December 10, 1985 at approximately 2:00 p.m. EST, NRC-Region V, the FBI, and the Incident Response Center (IRC) were notified.
The licensee has searched and successfully tested both EGD-A and EDG-B and both are currently operable. The plant is currently running at 100%. The licensee is in the process of a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> walk-through of all safety related systems that could easily be tampered with (i.e., valve positioning,cutwires,etc.). Region V has asked to be immediately notified if anything else is found.
ENCLOSURE B DEC 131985 L
i I
NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT WEEK ENDING DECEMBER 13, 1985
- 1. DEFUELING
- On December 11, 1985, the licensee completed filling the first fuel canister. It was filled with approximately 350 lbs. of debris consisting
. of about 12 pieces of fuel assembly end-fittings, control rod spiders, and small pieces of partial fuel assemblies. The exact weight of the loaded debris will be measured when the canister is closed, dewatered, -
and readied for transfer out of the reactor vessel. Filling of the !
second fuel canister was completed on the morning of December 14. It '
contains about 9 end-fittings and pieces of partial fuel assemblies. ,
Filling of the third fuel canister began on December 14. At about !
7:30 PM on December 14, with the canister about half-filled, an '
end-fitting was inserted into the canister and appeared to jam before being fully lowered into the canister. Operators attempted ,
unsuccessfully to tap the stuck end-fitting into the canister with a long !
handled tool. They then attempted to remove the end-fitting by grappling !
it with a J-hook attached to the one ton jib crane. When lifting with #
the crane, the canister positioning system (CPS) canister sleeve apparently became unlatched, the canister and sleeve lifted out of the CPS and dropped about li feet to the debris pile. On December 15, after special training for the evolution, the canister and sleeve were retrieved using the 5 ton service crane and was successfully reinstalled in the CPS. Preliminary video survey showed no damage to the canister, the sleeve, or the CPS. However, load cells on the 5 ton service crane indicated a dead weight of the canister and sleeve of about 2200 lbs.
Thus, the one ton rating of the jib crane may have been exceeded. The jib crane (one of two) has been removed from service. This event is under review by the licensee and the NRC staff to assess any damage to ,
the CPS and corrective actions to prevent future recurrence.
l t
A video survey of the core has determined that there are about 40 standing peripheral fuel assemblies with their end-fittings attached. About 40 to 50 single end-fittings were seen in the ;
debris bed. The remainder of the 177 end-fittings are either fused l together in aggregates of 2 to 4 or are hidden from view under other debris. The licensee does not believe that the presence of the ,
fused end-fittings will hinder access for the vacuum defueling test.
DEC 1F G85 ENCLOSURE B O
- The licensee expects to test the vacuum defueling system in'the reactor vessel in early January 1986,
- 2. 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 from the reactor
. 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 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). The defueling platform is installed over the internals indexing fixture.
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 68*F to 93 F with an average of 82.5'F.
The average reactor building temperature is 57'F. The reactor building airborne activity at the Westinghouse platform is 6.2 E-8 uCi/cc Tritium and 2.6 E-10 uti/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 "B" train of the DWCS reactor vessel filtrei. ion system was operated at reduced flow intermittent as needed to maintain RCS clarity for defueling operations. The licensee is still studying the DWCS filter fouling problems and is planning to conduct tests to evaluate the use of filter precoat materials to alleviate the problem.
- SubmergedDemineralizerSystem(SDS)istemporarilyshutdown.
EPICOR II is temporarily shutdown while changing out liners.
Total volume processed through SDS to date is 3,598,397 gallons, and the total volume processed through EPICOR II is 2,700,737 gallons.
- 4. DOSE REDUCTION / DECONTAMINATION ACTIVITIES
?
Decontamination activities are continuing on the 281' level of the auxiliary building. Scabbling of reactor coolant bleed tank cubicles is completed.
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.
DEC 131985 ENCLOSURE B
Decontamination of the "A" D-ring is in progress.
Preparations are in progress to Kelly-Vac the auxiliary building elevator pit and the underside of the elevator car.
- 5. ENVIRONMENTAL MONITORING US Environmental Protection Agency (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 EPA at the plant discharge to the river consisted of seven daily composite samples taken from November 23 through November 30, 1985. A gamma scan detected no reactor related activity.
The-Lancaster water sample taken at the water works intake and a'nalyzed by EPA consisted of a seven day composited sample taken
, from November 24 through November 30, 1985. A gamma scan detected no reactor related radioactivity.
No sample was collected by the NRC outdoor airborne particulate sampler at the TMI Site during this period due to personnel error in sanpler operations. A thorough review of plant strip chart recorders by NRC personnel determined that there were no abnormal releases of radioactivity from the site. ;
- 6. REACTOR BUILDING ACTIVITIES i The initial phase of defueling the reactor core is in progress. [
Installation of the vacuum defueling system is in progress. ;
The pressurizer manway cover has been removed, the access port ,
shielded, and TLD's and cameras lowered into the pressurizer.
Preliminary video and TLD surveys indicated that there is little i fuel d sition in the pressurizer. Further examination is in
- 7. AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the balance of DWCS continued.
Spent Fuel Pool "A" has been flooded to a depth of about 20 feet (about 6 feet above the top of the fuel canister storage racks).
- 8. 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 Sample Safety Evaluation.
Defueling Water Cleanup System Technical Evaluation Report, Revision 7.
Containment Air Control Envelope Technical Evaluation Report, Revision 5.
Solid Waste Facility Technical Evaluation Report.
ENCLOSURE B DEC 12 '.935
- . . ~ .
. 9. PUBLIC t'EETINGS The Advisory Panel for the Decontamination of Three Mile Island Unit 2 met on December 12, 1985. At the meeting the panel heard a presentation 4
by Mr. and Mrs. Aamodt on health effects in the area surrounding the Three Mile Island (TMI) facility. The Aamodts criticized the Pennsylvania State Department of Health and its recent study of cancer incidence around TMI.
- The panel also received briefings from GPUN on progress of the cleanup and from the NRC staff on the status of regulatory activities. Members of the public were afforded an opportunity to comment on cleanup related issues.
The ne'xt meeting of the panel is scheduled for February 12, 1986 in the Harrisburg area from 7:00 p.m. to 10:00 p.m. at a place to be determined.
1 I
i
?
L J k
?
i i
! I i ,
a ENCLOSURE B l l DEC l' 1035
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending December 13, 1985 Near-Term NRC Actions Under the Nuclear Waste Policy Act (NWPA)
Section: 114(e) of NWPA: Project Decision Schedule (PDS)
Status: The draft PDS was issued by DOE on July 18, 1985. The final PDS had been scheduled for a December 1985 release.
Action: Current DOE schedule for the final PDS is late February 1986.
Section: 114(e) of NWPA: Requirements under draft PDS Status: In the draft PDS, DOE requested that affected Federal agencies review Section 10 - Compliance with Federal Statutes, Regulations, and Permits, and submit, a report to DOE by January 1, 1986.
Action: The requested report has been prepared by ELD and is currently under review by NMSS for submittal to DOE.
Section: 137 of NWPA: Transportation of HLW Status: DOE issued the draft Transportation Business Plan in August 1985, and the draft Transportation Institutional Plan in September 1985.
Action: The final Transportation Business Plan is expected in December 1985, and the final Transportation Institutional Plan in April 1986.
Section: 141 of NWPA: Submittal of MRS Proposal Status: Submittal by DOE to the Comission of the MRS facility proposal is expected by December 16, 1985 (previous schedules stated December 2). The delay is related to DOE consideration of comments by Tennessee State review groups on the proposed MRS.
Action: NRC staff will review the MRS proposal and provide comments to the Commission for approval and transmittal to 00E. NRC's comments will be submitted with the MRS proposal to Congress.
ENCLOSURE C DEC 131985
Oak Ridge Associated Universities On December 6 and 7,1985, a member of the FC staff acommpanied Oak Ridge Associated Universities on a confirmatory survey of property formerly utilized by Cabot Corporation, Kawecki-Berylco Division, for the aluminathermic production of tantalum and columbium from source material. The survey is scheduled to be completed by December 13, 1985.
Material Licensing and Inspection Workshop This workshop was hosted by Region IV on December 4-6, 1985. The first day, dedicated to inspection matters, was moderated by Len Cobb, IE. The remaining time dealt with material licensing matters and was moderated by Vandy L.
Miller, NHS$.. The workshop was well attended by the Regions, and the consensus was: 1) that it had proved to be very beneficial to both matorial licensing reviewers and inspection personnel, and 2) that is should be continued on an annual basis.
NFS-Erwin Strike by OCAW members continues. There has been some negotiating between the Union and NFS within the last eight weeks but no resolution has been reached.
NFS is conducting limited operations of the HEU production, scrap recovery and R&D facilities. No problem with site operations has arisen to date.
Implementation of US/IAEA Safeguards Agreement Initial inspections have been successfully completed by the IAEA to verify design information from the three newly selected facilities (Westinghouse LEU fuel fabrication and the Salem-1 and Turkey Point-4 reactors). Input data for the preparation of Facility Attachments was collected.
ENCLOSURE C DEC I E 1E5
Items of Interest Week Ending December 13, 1985
- 1. The following Significant Enforcement Actions were taken during the past week:
None.
- 2. . The following IE Preliminary Notifications were issued during the past week:
- a. IIT-85-2C, Southern California Edison Company (San Onofre Unit 1),
Status Report From NRC Incident Investigation Team.
- b. IIT-85-20, Southern California Edison Company (San Onofre Unit 1),
Status Report From NRC Incident Investigation Team.
- c. PNO-II-85-115, Duke Power Company (Catawba Unit 2), Transamerica Delaval Diesel Generator Bearing Failures.
- d. PNO-II-85-116, Duke Power Company (McGuire Unit 2), Unscheduled Shutdown Longer Than 48 Hours,
- e. PNO-II-85-117, Nuclear Fuel Services (Erwin, TN), Media Interest in Picket Line Incident.
- f. PNO-IV-85-61, Arkansas Power and Light Company (Arkansas Nuclear One, Unit 2), Outage Greater Than Two Days.
- g. PN0-IV-85-60A,BasinIndustrialX-Ray,Inc.(Midland,TX),
RadiographySourceDisconnectResultingInAr, Overexposure (Update).
- h. PNO-IV-85-63, Louisiana Power & Light Company (Waterford 3),
Inadvertent Reactor Trip From 100% Power.
- 1. PNS-V-85-06, Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant), Narcotics Arrests By San Luis Obispo County Narcotics Task Forca.
- j. PNS-V-85-07, Portland General Electric Company (Trojan Nuclear Power Plant),PossibleSabotage.
- k. PNO-V-85-84, Department of the Navy (Naval Regional Medical Center, SanDiego,CA),TeletherapySourceRetractionMalfunction.
- 1. PNO-V-85-85, Southern California Edison Company (San Onofre Unit 2),
Reactor Trip and Safety Injection System Actuation.
ENCLOSURE D t None l
DEC 13 IW>
2
- 4. Other Items
- a. Civil Penalties Paid (1) EA 85-114 issued December 9, 1985 to Commonwealth Edison (LaSalle),$37,500.
(2) EA 85-98 issued December 10, 1985 to Metro Health Center (Erie, PA),$3,750.
(3) EA 85-116 issued December 10, 1985 to Quality Assurance Testing (LaFox,IL),$500,
- b. ASME National Board Meeting Deputy Director and Chief, Vendor Program Branch, Division of Quality Assurance, Vendor, and Technical Training Center, attended ASME's National Board meeting on December 10 in Columbus, OH.
- c. FEMA Exercise Director, Division of Emergency Preparedness and Engineering Response, the Chief and representatives of that Division's Incident Response Branch and Region I representatives attended FEMA's relocation tabletop exercise on December 10,11 in Emitsburg, MD.
- d. INPO Evaluation Programs Director and Deputy Director, Division of Inspection Programs, visited INPO (Atlanta) on December 11 for a periodic briefing on INP0's evaluation programs.
- e. Emergency Preparedness Seminars Incident Response Branch, Division of Emergency Preparedness and Engineering Response, sponsored seminars presented by Babcock and Wilcox on December 11 and 12. Subjects included degraded core scenarios and emergency operating procedures.
- f. Franklin Research Center Meeting Representatives of the Engineering and Generic Comunications Branch, Division of Emergency Preparedness and Engineering Response,and of Region III met with Franklin Research Center (Philadelphia) on December 12 to discuss analysis of Fermi Unit 2 diesel bearing failures.
ENCLOSURE D DEC 1?1935
3
- g. Inspection Accompaniment A representative of the Safeguards and Materials Program Branch, Division of Inspection, accompanied inspection at Combustion
! Engineering's Windsor, Connecticut Fuel Facility. Another repre-4 sentative of that Branch accompanied Region I's materials licensee inspections in the Baltimore-Washington, DC area as part of regional assessment efforts. A representative of the Operating Reactors Pro-gram Branch, accompanied a physical security inspection at Kewaunee.
A representative of the Emergency Preparedness Branch, Division of Emergency Preparedness and Engineering Response, participated in the Emergency Preparedness preoperational appraisal at Seabrook.
- h. IAEA Meeting A representative of the Safeguards and Materials Program Branch, Division of Inspection, participated in an IAEA Advisory Group Meeting (Vienna, Austria) to draft an IAEA document: " Systematic Operational Radiation Protection Appraisal Techniques," This document is to be issued in early 1987.
I 1
I i
i ENCLOSURE D DEC1L1505 i
l
O OFFICE OF NUCLEAR REGULATORY RESEARCH
^
Items of Interest
. Week Ending December 13, 1985 High Pressure Streaming Test High Pressure Streaming Test No. 8 (HIPS-8C) was successfully conducted on November 1985 at Sandia National Laboratories, Albuquerque, NM. The purpose of this test was to investigate the potential for debris to be dispersed from the reactor cavity via the annular gap between the reactor pressure vessel and the cavity wall., In many plants tFir path provides a direct access to the upper containment dome region.
The experiment apparatus is based on a 1/10 linear scaling of the Zion nuclear plant cavity. The width of the resulting gap is 1.3 to 1.4 cm. The test apparatus was placed in an interaction chamber, but the instrument tube exit was outside the enclosure so that only the mass escaping through the annular gap would be collected. Carbon dioxide gas was used to pressurize the thermite melt at 3.2 MPa initially.
The test results indicate that a substantial amount of the melt was dispersed through the annular gap. The mass collected from within the enclosure represents about 25% of the ejected melt. This amount is close to the ratio of the gap to the total flow areas out of the cavity. The dispersal mechanism '
appears to be melt entrainment in a high speed gas flow.
Source Term Code Package The Source Term Code Package (STCP) is a streamlined version of the suite of codes used by Battelle in BMI-2104. The Code Package is currently being used by Battelle to calculate source terms for about 25 accident sequences in the NRC's risk rebaselining program (SARP). As part of a quality assurance verification program, the Code Package has recently been installed by Brookhaven on the BNL computer system where both the coding of STCP and the numerical calculations for SARP are being checked. The Code Package is now operational on the BNL CDC-7600 and a number of test problems have been conducted. Various errors and problems have been uncovered and resolved by BNL. This information has been provided to and used by BCL, Problems remain but it is not yet known whether the problems are in the code itself or in the method of segmenting the code to fit on '
the BNL computer. Audit calculations for several of the risk rebaselining sequences will be initiated a soon as coding and segmentation problems are resolved.
ENCLOSURE E DEC 131985
RELAP5/M002 Code The RELAP5/M002 code is used to analyze thermal hydraulic phenomena occurring in the reactor system when a system transient occurs. The Idaho National Engineering Laboratory (INEL) has published a report entitled "RELAP5/M002-User Guidelines" (NUREG/CR-4312). The report will be available to NRR, NRC contractors, and international partners under the
, International Code Assessment Program and all other U.S. users.
Iodine Release Following Steam Generator Tube Rupture (SGTR)
A meeting.was held on December 4, 1985 at the Oak Ridge National
~
Laboratory to discuss the recent experimental data on iodine partition coefficients under conditions simulating the SGTR environment.
Representatives from NRC,.ORNL, Science Applications Incorporated, and the Electric Power Research Institute (EPRI) attended the meeting.
The experimental data shows a strong effect of boric acid concentrations on iodine volatility. A test matrix which would extend these results to a wide range of conditions has been acreed upon. EPRI will be following these experiments closely because the data generated is required for the iodine release model which they are currently developing. The difficulties of measuring iodine species during reactor operations have also been discussed in connection with plans to obtain such data in several reactors.
Meeting of the Coordinating Ccmittee for LLW Disposal Technology The Coordinating Committee for LLW Disposal Technology met on Thursday, December 5, 1985, in Palo Alto, California. In attendarce were representatives from: the States of Illincis, hew York, Pennsylvania, and Texas; EPRI; EG&G; Idaho;andRogersandAssociations(RAE). The meeting was chaired by Dr. G.
Hill of the Southern States Energy Board, and the NRC was represented by Dr. F. A. Costanzi, RES.
The meeting began with a presentation by RAE on the status of their work on LLW disposal alteratives to shallow lar.d burial (SLB). RAE has completed the classification of various LLW disposal technologies and has begun eval . ting the engineering requirements and costs of each. This EPRI-sponsored work by RAE cocpliments the work being conducted for RES by EGSG, Idaho, on safety dcsign and performance of engineered enhancement / alternatives to SLB. Both efforts should be completed in the Spring of 19P6.
ENCLOSURE E DEC 131985
o .
During the course of discussion it was observed that some alternatives might result in higher occupational exposure than others. This may be especially true for alternatives designed for ready retrieval of wastes. In any case, it was noted that occupational exposure is an issue that needs to be factored into design requirements and costs for any LLW disposal technology.
A brief discussion was held on the state of modeling performance of SLB alteratives. It was the general consensus that the modeling of the engineering, per se, has not been done, and that devclopnent of such models is needed for performance to be properly considered in selecting from the various i technologies for LLW disposal.
The next meeting of the committee is tentatively set for late April at EG8G, Idaho.
A i
l i
EflCLOSURE E ;
i I
_w. .
-4 RES Rulemaking Activities Severe Accident Risk Assessment The RES staff and supporting contractors are currently engaged in the reevalua-tion of the risk of six reference LWRs. This reevaluation is currently being used to support NRR's review of IDCOR submittals. In addition, it will support the. staff report NUREG-1150, which is intended to provide guidance to decision-makers as to the appropriate role of information on core melt frequency, containment performance, source terms, and risk in making severe accident decisions.
A briefing of' office management was held on December 9,1985, and was well received. The briefing included the approach and the results to date for Surry, Peach Botton, and Sequoyah. The Deputy Director, NRR, requested routine updates, particularly on Sequoyah. The next briefing will probably be held in late January.
Also on December 9,1985, IDCOR was briefed on the uncertainty analyses being done for NUREG-1150. They expressed interest in major phenomenological issues important to risk (providing such information as core-concrete on the inter-action and direct heating) and requested to be advised as to our assessment of the principal parameters influencing the risk assessments. The Director, DSRO, NRR, expressed great interest in having NRR become significantly involved in 4
the assessment of several of the issues.
Schedules for the individual plant assessments continue to slip somewhat, principally due to the receipt of quality assurance (QA) and quality control (QC) comments. Such comments will substantially improve the quality and credibility of the work, however; and the schedule for NUREG-1150 remains unaffected at the present time.
Risk Effectiveness of LWR Regulatory Requirements The purpose of this program is to identify existing regulatory requirements that have marginal importance to safety, and to make recommendations to the EDO whether to eliminate or modify these requirements.
AmeetingbetweenDRA0/RESstaffandcontractor(PNL)staffisscheduledduring the week of December 16, 1985, at PNL in Richland, Washington, to discuss resolution of staff coments on PNL's two draft reports. Program plans for FY 1986 work will also be discussed at the forthcoming meeting. Based on
. advice from Program Advisory Group and Research Review Group members, the following five regulatory areas were tentatively selected for assessment in FY 1386: (1) reactor vessel level indicating system, (2) post-accident system, (3) impregnated charcoal filters in effluent treatment sampling system. (4) combustible gas control system, and (5) turbine missiles.
ENCLOSURE E DEC 13 iS85
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING DECEMBER 13, 1985 j OECD Vacancy A vacancy notice for an A2/A3 Energy Statistician / Analyst in the Energy Statistics Division of the Office of Information and Emergency Systems
. Operations at the Organization for Economic Cooperation and Development (OECD) headquarters in Paris, France has been posted on NRC bulletin boards.
~
International Meetings The following international meeting notices supplement those previously announced:
January 20-24, 1986, Manila, The Philippines - IAEA Seminar on Quality Assurance for the Operation of Nuclear Power Plants January 20-24, 1986, Vienna, Austria - Joint IAEA-European Comunity Consultants' Meeting on Hydrogen Issues Related to Nuclear Reactor Safety ,
February 19-21, 1986, Karlsruhe, FRG - IAEA Consultants' Meeting on Nuclear Techniques for Analysis of Environmental Samples April 7-11, 1986, Vienna, Austria - IAEA Technical Comittee Meeting on !
Advances in Uranium Refining and Conversion ;
April 14-18, 1986, Rome, Italy - IAEA Technical Comittee Meeting on ,
! mobilization of Low and Intermediate Level Radioactive Waste with Polymers ;
International Visitors On Tk;" day Mr. Nicholaas Guus Ketting (President) and Mr. f#it Aart Leendert van Hoek (Member) of the Board of Managing 4
Directors c' the Dutch Electricity Generation Board (SEP) visited NRC in connection with the planned future expansion of their nuclear power program. EDO W. Dircks, DEDR0GR V. Stello, D. Eisenhut of NRR, and ,
J. Shea and H. Schechter of IP participated in the meeting. The '
visitnrs were interested in learning the views of senior NRC officials on key managerial / organizational approaches that utilities should bear in mind to enable them to select, construct, and operate from two to j four new nuclear power plants. Other stops on the visitors' itinerary included DOE, several U.S. utilities, and Harvard University's Kennedy School of Government.
ENCLOSURE G
- DEC 131985 !
0FFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING DECEMBER 13. 1985 Exercise Relocation of People from Around a Nuclear Power Plant Ira Dinitz, OSP, participated in a Relocation Tabletop Exercist (RTE) at the Emergency Management Institute in Emmitsburg, Maryland, on December 10,1985.
The RTE focused on a broad range of relocation, reentry, and recovery issues which conceivably could emanate from the consequences of an offsite release of radiation. Representatives of the nuclear liability insurance pools also participated in this exercise.
Price-Anderson Panel Jerome Saltzman, OSP, joined representatives of DOE, nuclear utilities and public interest groups in a discussion of the progress of Price-Anderson legislation at a December 12, 1985, meeting in Washington, D.C. of the National Conference of State Legislatures' State-Federal Assembly.
ENCLOSURE H DEC 101395
f 4
i i.
REGION III I STATUS REPORT .;
A f
. DAVIS-BESSE LOSS OF FEEDWATER EVENT l DECEMBER 12, 1985 i i
[
Plant Status I v
The plant remains in cold shutdown. The circulating water canal is drained. '
Decay heat loop No. 2 is out of service for maintenance. j f
i l
l t i
i -
4 ,
f, i
I i
i i !
h i
i i
t
+
i i i'
l !
t i i i t i :
i ENCLOSURE L f
DEC 131935 !
1 i
I
??,
c .
W eo Region III STAFF ACTIONS AS ASSIGNED BY W. DIRCKS MEMO 0F AUGUST 5,1985 '
{
- 1. Item: Adequacy of the licensee's management and maintenance activities ACTION STATUS / COMMENTS l
(b) Evaluate and take action on the Region III is observing maintenance activities and licensee's response to findings evaluating LER's, DVR's and other items as they relate to l
concerning management practices the control of maintenance. A maintenance survey team l
(e.g., control of maintenance inspection conducted on September 16-20, 1985 confirmed l programs and post-trip reviews). previous concerns identified by Region III. An IE/NRP inspection team will assess maintenance and management practices prior to restart. This inspection is currently planned for mid-January 1986.
- 6. Item: Reliability of the AFW containment isclation valves and other safety-related valves l ACTION STATUS / COMMENTS (a) Monitor the licensee's trouble- Troubleshooting activities related to containment isolation shooting activities valves AF599 and AF608 are complete. Region III specialists are evaluating and monitoring M0 VATS testing on other safety-related motor operated valves. Of a total of 167 valves, 99 have been completed including valves requiring retest.
(e) Determine that the procedures for Limitorque operators for valves AF599 and AF608 have been l adjusted and the valves have been tested under dp i adjustments of the AFW isolation valves such as torque switch bypass conditions. Procedure reviews and evaluations of the switches are clear and proper, and training program will be completed prior to restart.
that associated training programs are Confirmatory testing will be performed during startup, adequate. Confirm that adjustment y, settings are consistent with plant
=; procedures.
Es E
a r-2
ES Item: Reliability of AFW pump turbines
(( 8. ,
ACTION STATUS / COMMENTS (a) Monitor the licensee's trouble- Troubleshooting activities are complete. Region III shooting activities including will monitor confirmatory testing during plant startup possible hot plant operation to as part of startup test activities.
confirm failure mode.
(d) Verify that the AFW system has been Results of test review group meetings have culminated adequately tested to confirm system in the development of a charter outlining test review group configuration involved with design responsibilities and activities. AFW testing will be basis events. included as part of the testing review team effort.
(e) Review the implementation of the The licensee is developing a training program on resetting operator training program to assure of the trip throttle valve. This training will include proper operator actions, such as resetting of trip mechanism at operating conditions, resetting of trip throttle valve. therefore, the training will be completed during plant restart.
E P
o C
A r-3
I .
i R
- 9. Item: Reliability of the PORY w .
$ ACTION STATUS /COMENTS 18 (a) Monitor the licensee's trouble- Troubleshooting activities have been completed. i shooting activities. Confirmatory testing 'will be conducted at operating temperature and pressure. Testing of an equivalent valve
' indicated a lower flow condition than expected. Testing of
' a modified PORY completed at the Marshall Steam Station j facility on November 15, 1985, demonstrated an acceptable
- flow rate.
i i
l l I
T 9
P 8
15 m
F 4
4 s . . - _ . . - ._ _ _ _ _ _ _ - _ . . _ ~ . _ _ . _ . - - _ _ . _ _ . _ _ - - - -- .
Other Activities Installation of the new electric motor driven startup feedwater pump is ++
complete. Testing of he motor (uncoupled from the pump) was completed on November 14, 1985.
Evaluations and inspections of safety system piping supports are complete. ++
Nonconformance Reports (NCRs) have been written against 2152 of 2425 pipe supports inspected so far. Rework is required on 195 of the 873 supports that have had NCRs dispositioned (earlier status reports had reported the number evaluated, an interim stage of the disposition process) by the licensee's staff.
NOVkTStestingcontinuesonthe167 safety-relatedmotor-operatedvalves ++
onsite. The licensee has completed 99 valves including valves requiring retest due to maintenance activities. The licensee is repairing and testing valve motor operators continuously with three overlapping ten-hour shifts.
The service water structure will require ventilation improvements before ++
startup. This modification work may be a critical path item. The licensee has not yet pertormed testing required to allow completion of the design of the ventilation improvements.
The NRC test review team continues to provide weekly coverage of licensee ++
testing activities. Presently, there are very few tests ready for performance.
The testing schedule has been delayed due to the implementation of Facility Change Requests (FCRs) and is expected to accelerate by the end of December.
In the meantime, the test review team is focusing on the review of individual test procedures. The licensee has recently completed and approved a System Review Package for each system under review. The licensee's schedule presently indicates that the test program will be complete by February 2,1986.
Planned Meetings Comission meeting to discuss status of Davis Besse restart activities on December 18, 1985.
I ENCLOSURE L 5
DEC 19195 L -
ITEMS ADDRESSED BY THE' COMMISSION -' WEEK ENDING DECEMBER 13, 1985 A. STAFF REQUIREMENTS ' PERIODIC' MEETING WITH' ADVISORY PANEL ON DECONTAMINATION i 0F TMI-2, 11:00 A.M., TUESDAY, NOVEMBER 19, 1985, C0ff1ISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCF) Memo SECY to W. J. Dircks and R. Fraley dated 12/11/85 l The Commission met with the Advisory Panel for the Decontam-ination of TMI-2 to obtain the Panel's views on the cleanup activities at TMI-2 and related matters.
The Commission directed the ACRS to review measures being implemented by GPUNC to preclude the possibility of recriti-cality during the TMI-2 defueling. The NRC staff is to provide the issue.-
ACRS with information on the staff's evaluation of this (TMIPO/ACRS) (SECY Suspense: 3/15/86)
The Commission directed the staff to prepara an analysis of the schedule slippage in the cleanup operation at TMI-2 during the period from July 1985 to October 1985. The analysis should examine the causes of the scheduling slip, the effect of the l
delay on the overall cleanup schedule and any steps the licensee has taken, as a result of the delay, to assure future compliance with the schedule.
(TMIPO) (SECY Suspense: 2/14/86)
B. STAFF REQUIREMENTS MEMORANDUM - AFFIRMATION / DISCUSSION AND VOTE, 2:00 P.M.,
- WEDNESDAY, DECEMBER 4, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to H. H. E. Plaine dated 12/12/85
- I. SECY-85-332A - Revised Braidwood Order l
' The Commission, by a 4-1 vote,* approved an order requiring the applicant and staff to provide answers to Commission questions prior to a consideration by the Commission of the applicant's request that the Commission: (1) grant an exemption from 10 CFR S 2.786 (b) (1) ; and (2) take review of ALAB-817, in which the Appeal Board denied the applicant's request that it review l
whether the Licensing Board committed procedural errors in the conduct of the Braidwood operating license proceedings.
l Cormnissioner Roberts provided addition views to be attached to the order, Commissioner Asselstine disapproved and provided separate views.
i (Subsequently, on December 5, 1985 the Secretary signed the f order.)
DEC 131985 ENCLOSURE 0
l B. CONTINUED
- Section 2'01 of the Energy Reorganization Act, 42 U.S.C. S 5841, provides that action of the Commission shall be deter-mined by a " majority vote of the members present." Commissioner i
Roberts was not present when this item vas affirmed. Accor-dingly, the formal vote of the Commission was 3-1 in favor of the decision. Commissioner Roberts, however, had previously I indicated that he would approve this paper and had he been present he would have affirmed his prior vote. ,
! l l
l
\
i i
l l
ENCLOSURE 0 DEC 131985 I _ _ . _ _ . . . . . ~ . - . _ . - . _ . . _ _ _ - _ _
1
~
i
! Mo .-
R} NRR MEETING NOTICES
- ov DECEMBER 13, 1985 j DOCKET APPLICANT /
j DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 1
1 12/16/85 50-244 P-114 Discuss the licensee's Rochester Gas C. Miller l 1:00 pm Bethesda licensee's proposed use of & Electric Corp.
j the C.E. method of Steam R. E. Ginna j Generator Tube Steering
! 12/16/85 50-461 416B Discuss Clinton's proposed Illinois Power Com. B. Siegel l 1:30 pm Bethesda accelerated power assention Clinton Power Station
- test program i
12/16/85 50-269 Oconee,'S.C. Meeting with Duke Power on Oconee Nuclear Station H. Nicolaras j 7:30 am. 50-270 Post-Accreditation Training
- 50-287 at the Oconee Nuclear Station j Units 1, 2 and 3 l 12/16/85 50-410 .Nine, Mile Point h eting with Niagara Mohawk Nine Mile Point Unit 2 M. Haughey
- Unit 2 Site Power Corp. on Nine Mile Point l Scriba, N.Y. 2 (NMP-2) i
{ 12/16/85 50-442 Seabrook Station Seabrook Technical Specification PSC of New Hampshire V. Nerses
! 8:00 am 50-444 Seabrook, N.H. Meeting Seabrook Nuclear Power l
! Station l
t l
- Copies of sunanaries of these meetings will be made publicly available and placed in the respective docket file (s)
! in the NRC and local public document rooms
! 9 l ?
- a l .
E T
l 1
- _ . . . - - . _ . . . - . ~ - . - - , _ . _ . - - - - _ - - . - - - _ _ - - . - . - - - . . - - - . . .-. , - _ - - - - = . - - - . , - - - . - - - - - - - _ _ _ . . - - _ _ - - __ -- -
i l -
! c, -
h % .
l
! w -
1 c .,
l y NRR MEETING NOTICES
- DECEMBER 13, 1985 DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT j 12/17/85 50-289 TMI-1 Training Meeting with GPU Nuclear GPU Nuclear J. Thoma j 10:00 am Center Corporation Corporation
! Middletown, PA
)
j 12/17/85 P-422(12/17) Meeting with BWR Owners BWR Owners M. W. Hodges 4 8:30 am P-118 (12/18) Concerning Rev. 4 to NRR Staff l Emergency Procedure Guidelines
! 12/17/85 50-440 P-412 Meeting with Cleveland Electric NRC Staff J. Stefano j 11:00 am Bethesda Illuminating Co. re: Perry NRC Region III j
Nuclear Power Plant Unit 1 CEI i
l 12/17/85 50-445 Sheraton Hotel Meeting with Texas Utilities Texas Utilities A. Vietti-Cook j 1:30 pm 50-446 Arlington, Texas Comanche Peak
> Units 1 and 2 I
12/17/85 50-410 Nine Mile Point Meeting with Niagara Mohawk B. G. Hooten M. Haughey Unit 2 Site Power Corp. on Nine Mile Point Nine Mile Point Scriba, N.Y. 2 (NMP-2) Nuclear Station 12/17/85 50-244 314-A To discuss the licensee's Rochester Gas & Elect. C. Miller l 9:00 am Bethesda Containment Purge and Vent R. E. Ginna Technical Specification req.
12/18/85 50-335 P-422 To discuss the discontinuity Florida Power & D. Sells !
2:00 pm 50-389 Bethesda in the security perimeter at Light Co.
j y the intake canal
! 6
- E l A i' l Copies 07 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.
l l i L _ _. _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _
I
a .-
- f c)
- 1 y
- f .3 h NRR MEETING NOTICES
- DECEMBER 13, 1985 DOCKET APPLICANT /
j DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT i
l 12/19/85 50-390 P-118 Meeting with TVA - Welding TVA W. Long
{ 1:00 pm 50-391 Bethesda Issues 1
l.'
12/19/85 50-369 6507 MNBB Discuss technical analyses in Duke Power D. Hood 10:30 am 50-370 Bethesda support of deletion of UHI
- system at McGuire provided by Duke Power Company's letter of May 9, Oct 2 and Oct 14, 1985 12/19/85 50-280 P-114 To discuss GDC-4 partial VEPC0 T. Chan 9
- 00 am 50-281 Bethesda exemption requests 12/19/85 50-315 Westinghouse Ofc. Discuss the basis for and IMEC/AEP D. Wigginton L 10:00 am. 50-316 4901 Fairmont Ave. acceptable provisions of I
Bethesda Technical Specifications of Appendix R i
[ 12/20/85 50-400 QUATEL Office To discuss detailed control CP&L B. Buckley 10:30 am (12th Floor) . room design review issues l Landow Bldg.
Bethesda 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 1
, P i 8 l
E m
"U
NHSS MEETING NOTICES '
S"?
FOR WEEK ENDING: 12/13/85
'i l
Divisitn of fuel Cycle and Mat: rial Safoty -
.s ,
$$ DOCKET ATTENDEES /
['j DATE/ TIME NUISER LOCATION PURPOSE APPLICANT NRC CONTACT 12/13/85 Willste Discuss basket for Model No'. TN-BRP R. Odegaarden (FC) Odegaarden cask with Transnuclear, Inc. , and C. Chappell (FC)
LLL. C. MacDonald (FC) 12/16/85 Willste Discuss Put 71 Requirements for R. Odegaarden (FC) Odegaarden Spent Fuel Casks with Combustion C. MacDonald (FC)
Engineering (Bill Buens). H. Lee (FC) 12/17-19/85 . West To meet with DOE and NRC subcontractor NRC/ DOE Staff Norra Davison Valley, NY at West Valley site for demonstration
, of fuel consolidation and a gas
- chromatograph. ,
1 Division of Waste Management j 12/16-17/85 Chicago, II. 2nd Annual Illinois Depan'aent of R. E. Browning (WM) R. E. Browning i Nuclear Safety LLW Generators
! Conference.
I I
} Division of Safeguards None.
1 .
m i R i 5
? E A
o 1
i
i pg Decemb:r 13, 1985 ;
c3 ,
$$ RII MEETING NOTICE 15 i DOCKET ATTENDEES /
NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT i DATE/ TIME i
12/16/85 RII Office SALP Board Meeting Selected RII Staff Walker 1:00 pm CP&L - Robinson Facility Members 12/17/85 RII Office SALP Board Meeting Same as above Walker 8:30 am CP&L - Brunswick and Shearon Harris Facilities 12/18/85 RII Office Enforcement Conference Licensee representatives Walker 10:00 am VEPC0 - North Anna Station Regional Administrator and selected RII Staff Members 12/19/85 Knoxville, TN Meeting with TVA management Commissioner Asselstine Walker and Nuclear Safety Review and two staff members, Staff and at the Watts Bar Licensee and NSRS staff site to meet with a TVA members and two RII staff contractor on employee members concerns 12/19/85 Spring City, TN Meeting with TVA Watts Commissioner Asselstine Walker Bar management and two staff members, Licensee staff members, and Selected RII Staff Members s
P S? ,
Ei m
T