ML20141P107
| ML20141P107 | |
| Person / Time | |
|---|---|
| Issue date: | 03/13/1986 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-860307, NUDOCS 8603190014 | |
| Download: ML20141P107 (35) | |
Text
M o
0 March 13, 1986 For:
The Commissioners Fron:
T. A. Rehm, Assistant for Operations, Office of the ED0
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING MARCH 7, 1986 A summary 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
Inspectior. and Enforcement D
Nuclear Regulatory Research E
Executive Legal Director F*
!nternatier.al Programs G
State Programs H
Pesource Management I*
Analysis and Evaluation of Operational Data J*
Small & Disadvantaged Business Utilization & Civil Rights K*
Regicnal Offices L
CRSR Monthly Reports M*
Executive Director for Operations N*
Iten:s Addressed by the Commission 0
Meeting Notices P
Proprietary or Other Sensitive Information (Not for Q
external distribution) 7 x-c
- No input this week.
e603190014 e60313
/
u PDR COMMS NHCC T. A. Reho Asf nt for Operations r
WEEKLYINFOREPT PDR Office of the Executive Director for Operations j
Contact:
T. A. Rehm, ED0 492-7781
HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING MARCH 7, 1986 Comanche Peak Unit 2 Texas Utilities has reported three cases where instrumentation appears to have been willfully damaged. Building management in the Reactor Containment Building identified two cases where a piece of tubing had been cut out of the line. Upon closer examination they found that sections of the instrumentation tubing had been removed. The third case was found by instrumentation workman who were working in the Safeguards Building.
In this case, workers noticed a suspicious looking fitting and upon closer examination they determined that the pressure fitting ferrel had been removed and the nuts had been retightened to hide the missing ferrel. On site security is currently investigating these incidents.
Shoreham Enforcement Action Region I has scheduled an enforcement conference for March 13, 1986 with LILCo to discuss training and qualification problems in the Shoreham radiochemistry department. The problems were identified by an employee chemistry technician and have been verified by regional inspectors. Additional allegations regarding the falsification of cnemistry logs are being investigated.by 01. The Shoreham PM will attend the enforcement conference.
Babcock and Wilcox Volume Reduction Services Facility An environmental assessment has been issued regarding the proposed operation of a Volume Reduction Services Facility by B&W at its site in Parks Township, Pennsylvania.
The facility is designed to receive low-level radioactive waste from utilities and industrial and institutional generators for processing by incineration or high-force compaction.
The assessment supports a Finding of No Significant Impact.
Copies of the Assessment have been sent to the Administrative Judge and parties to the informal proceeding ordered by the Commission.
NFS-Erwin Strike by OCAW members continues. There has been no progress made in resolving differences between the Union and NFS.
The Company has recently advertised for additional salaried workers to augment the current work force.
Mr. Jim Clark was recently assigned to the Erwin site from corporate headquarters in Rockville for an unspecified period of time.
NFS continues to conduct limited operations of the HEU production and scrap recovery operations.
The Union has increased its picketing activities slightly at the site and has circulated a flyer to residents of Unicoi County raising concerns about the plant and suggesting that concerned citizens call the Region II office.
MAP 7
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OFFICE OF ADMINISTRATION Week Ending March 7, 1985 ACMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1985 181 15 Received, 1986 130 31 Granted 102 10 Denied 36 1
Pending 173 35 ACTIONS THIS WEEK Received Kay L. Dove Requests a copy of the proposal submitted by Expert-(86-111)
Ease in response to the SBIR program RFP.
Jim Thomas, Requests a copy of the official Standard Form 50 for NTEU President a former NRC employee.
(86-112)
Michael A. Howman, Requests copies of contracts Nos. NRC-05-85-160 and NUS Corporation NRC-05-84-151.
(86-113)
Joseph M. Varela Requests copies of Mr. Wallace Swan's reports during (86-114) his residency at the Watts Bar nuclear power plant.
Brenda Ravan Requests information on nuclear energy.
(86-115)
Lyle Graber, Requests the enclosures to the November 18, 1985, LER on NUS Corporation Palisades, No. 50-255/85-23.
(86-116)
Charles Barnes Requests copies of certain reccrds from Docket 40-1668; (86-117) 40-6589; 40-7271; and 40-6811.
Charles Barnes Requests copies of the entire docket files for Docket (86-118)
Nos. 40-7251, 40-7484, and 40-2038 and records dated from December 1, 1983, through March 31, 1984, for Docket No. 40-8760.
CONTACT: Donnie H. Grimsley 492-7211 ENCLOSURE A MAR i...J I
i 2
Received, Cont'd Jan Legnitto, Requests copies of all records relating to NRC's use CBS News of outside firms to locate and buy land in Maine (86-119) or any of the other 16 proposed sites for dumping nuclear material.
Shao-Chih Way, Requests a copy of the technical proposal submitted In-Situ, Inc.
by the University of Arizona in response to (86-120)
RFP RS-RES-85-ll4.
James Phalen, Requests (1) records identifying (a) the amount of College of the nuclear fuel reported missing in the U.S. along with Holy Cross the location of these disappearances and (b) the laws (86-121) governing the sale and transport of nuclear fuel; (2) a list of companies licensed to process or transport nuclear fuel; (3) technological material concerning atomic weapons that has been declassified by the Federal Government; and (4) The Los Alamos Primer.
Wendy Parker, Requests copies of records detailing violations of The Montgomery NRC regulations or accidents involving licensees County Sentinel authorized to handle radioactive or byproduct materials (86-1221 in Montgomery County, Maryland, since 1982.
Tim Fitzpatrick, Requests copies of all records related to 01A's completed Thomas Devine, investigation and audit into charges that the NRC staff Goverrment responded improperly to allegations by "whistleblowers" Accountability at the Diablo Canyon nuclear power plant.
Project (86-123)
David R. Ennis, Requests a copy of the transcript of the February 26, NUS Corporation 1985, ACRS Subcommittee meeting on Emergency Core Cooling.
(86-124)
Lyle Graber, Requests copies of the July 24, 1985, and November 26, NUS Corporation 1985, memos from Harold Denton to Willian Dircks on the (86-125)
Davis-Besse event.
Billie P. Garde, Requests all records generated or prepared by Victor Stello Government beginning with his appointment as Acting Executive Accountability Director.
Project (86-126)
Billie P. Garde, Requests all records generated or prepared by Victor Stello Government beginnirg with his appointment as Acting Executive Accountability Director.
Pro,iec t (86-127)
(
MAR 7.3 ENCLOSURE A
3 Received, Cont'd Billie P. Garde, Requests records regarding the Westinghouse Ferro-Government Resonant Transformer problems described in Information Acccuntability Notice 84-84.
Project (86-128)
Billie P. Garde, Pequests records regardi.ng Inspection Report 50-445/
Government 84-39 on the Comanche Peak nuclear power plant.
Accountability Project (86-129)
Diane Curran, Pequests a copy of a letter from Victor Stello to Harmon & Weiss Zinovy V. Reytblatt dated October 15, 1985.
(86-130)
Albert V. Carr, APPEAL TO THE ED0 for the release of two denied records Duke Power Company in NRC's January 24, 1986, response to his F0IA request (86-A-14-85-584) regarding Enforcement Action No. EA-84-93 on the Catawba Nuclear Station.
Mozart G. Ratner, APPEAL TO THE ED0 for the release of the denied records Attorney-At-Law regarding a request concerning the General Electric (86-A-15-85-158) Company's facility in Wilmington, North Carolina.
Marya C. Young, APPEAL TO THE ED0 for the lack of response to a request Government for records pertaining to the Region IV audits of Accountability Comanche Peak.
Project (86-A-16-86-81)
Billie P. Garde, APPEAL TO THE ED0 for the lack of response to a request Goverrrent for records regarding the creation of the Contention 5 Accountability and. Harassment and Intimidation Panels.
Project (86-A-17-85-153)
Billie P. Garde, APPEAL TO THE ED0 for the lack of response to a request Government for records regarding the concern / allegation tracking Accountability system for reflecting the status and identification of all Project Comanche Peak allegations.
(86-A-18-85-299)
Billie P. Garde, APPEAL TO THE E00 for the lack of response to a request Government for records regarding all summary raterials provided Accountability to the contention and/or harassment and intimidation Project panels for their assessment of quality assurance / quality (86-A-19-85-312) control at the Comanche Peak nuclear power plant.
ENCLOSURE A MAR
4 Received, Cont'd Billie P. Garde, APPEAL TO THE ED0 for the lack of response to a request Government for all information provided by the alleger identified Accountability in the February 1985 SSER No. 8 having provided Project 300 allegations to the.NRC.
(86-A-20-85-313)
Pillie P. Garde, APPEAL TO THE COMMISSION for the lack of response to a Government request for records regarding NRC Announcement No. 110, Accountability
" Proper Use and Control of Telephone Services," dated Project-November 5,1985.
(86-A-21-86-35)
Billie P. Garde, APPEAL TO THE ED0 for the lack of response to a request Government for records regarding Inspection Report 50-445/85-13 4
Accountability and 50-445/85-09 dated December 24, 1985, on the Comanche Project Peak nuclear power plant.
(86-A-22-86-36)
Billie P. Garde, APPEAL TO THE ED0 for the lack of response to a request Government for records regarding the Quality Assurance Branch " visit" Accountability of TERA offices in Bethesda, Maryland, on October 28 -
Project November 1, 1985.
(86-A-23-86-38)
Billie P. Garde, APPEAL TO THE COMMISSION AND THE ED0 for tha lack of Government response to a request for all records genarated or Accountability prepared by Victor Stello beginnning with his appnintnent Pro.iect as Acting Executive Director.
(86-A-24-86-53)
Rillie P. Garde, APPEAL TO THE COMMISSION AND THE ED0 for the lack of Government response to a request for all records generated or Accountability prepared by Victor Stello beginning with his appointment Proiect as Acting Executive Director.
(86-A-25-86-E4)
Billie P. Garde, APPEAL TO THE COMMISSION AND THE ED0 for the lack of Government response to a request for all records generated or Acccuntability prepared by Victor Stello beginning with his appointment Project as Acting Executive Director.
(86-A-26-86-55)
Billie P. Garde, APPEAL TO THE EDO for the lack of response to a request Government for all records generated or prepared by Victor Stello Accountability beginning with his appointment as Acting Executive Project Director.
(86-A-27-86-80)
Billie P. Garde, APPEAL TO THE ED0 for the lack of response to a request Government for all records generated or prepared by Victor Stello Accountability beginning with his appointment as Acting Executive Project Di rector.
(86-A-28-86-82)
ENCLOSURE A h'M
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4 5
Received, Cont'd Billie P. Garde, APPEAL TO THE COMMISSION for the lack of response to a Government request for records developed in the investigation of all Accountability Equal Employment Opportunity complaints filed by employees Project of the Office of Inspector and Auditor (0IA) against (86-A-29-86-85) employees of OIA.
Billie P. Garde, APPEAL TO THE COMMISSION for the lack of response to a Government request for records relevant to and/or generated in Accountability connection with SECY-85-404, " Unauthorized Disclosure of Project Sensitive Information - Availability of Administrative (86-A-30-86-40)
Sanctions Against NRC Employees and Special Government Employees," dated December 23, 1985.
Laurie Fowler, APPEAL TO THE COMMISSION AND THE ED0 for the lack of Law Offices of response to a request for all records regarding NRC's Brian Spears investigation into the complaints of named individuals (86-A-31-86-43) regarding illegal and improper procedures and practices at the Vogtle nuclear power plant.
Granted Rillie P. Garde, In response to a request for records regardina a named Government NPC employee and the operator training report at Beaver Accountability Valley, made available five records.
Informed the Project requester that additional records subject to this reouest (85-801) are already available at the PDR.
Mary Ann Mathews,
In response to a request for certain information on uranium General Electric shipments for the period January 1985 through December 1985, (86-19) made available a computer printout and tape.
Wanda A. Zwally, In response to a request for copies of the transcripts of University of the Silkwood vs. Kerr-McGee case of September 1977, South Carolina informed the requester that the NRC was not been able to (86-1091 locate transcripts. Suggested that she contact either the U.S. District Court, U.S. Court of Appeals or the U.S.
Supreme Court for copies of the opinions.
Denied Allan Jalon, In response to a request for copies of all records Los Angeles Times pertaining to a September 1967 investigation by the (85-514)
Atomic Energy Connission of worker exposures to enriched uranium during 1966 and 1967 at Atomics International, denied portions of four records, disclosure of which would constitute a clearly unwarranted invasion of personal privacy.
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ENCLOSURE A
6 Denied. Cont'd Billie P. Garde, In response to a' request for all records relevant! to the Government NRC staff's determination of a potential material false Accountability statement on U-Bolt sample, BN 85-077, that was issued Project on August 20, 1985, made available nine records.
Informed (85-614) the requester that additional records subject to this request are already available at the PDP..
Denied three records in their entirety, release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.
James F. Nicolosi, In response to a request for all records for North Hydro Nuclear American Inspection Inc., holder of NRC license No.
Services, Inc.
37-22370-01, concerning NRC's inspections conducted (85-740) in October 1984, January 1985, June 1985, and all subsequent records pertinent to this matter, made available 47 records. Denied 19 records in their entirety, release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process. Denied one record in its entirety, the release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process and constitute a clearly unwarranted invasion of personal privacy.
Denied one record in its entirety, the release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process and reveal confidential business (proprietary) information.
Billie P. Garde, In response to a request for records regarding the career Government progression of a named NRC employee, made available two Accountability records.
Denied portinns of four records, dislosure of Project which would constitute a clearly unwarranted invasion of (85-800) perscnal privacy.
Billie P. Garde, In response to a request for records related to and/or Government generated in connection with NRC Announcement No. 110, Accountability
" Proper Use and Control of Telephone Services," dated Project November 5,1985, and all telephone logs available to the (86-35) agency relevant to the development of the announcement, (86-A-21) made available one record.
Denied 18 records in their entirety, disclosure of which would interfere with an ongoing enforcement proceeding and constitute a clearly unwarranted invasion of personal privacy.
Williar J. Manning In response to a request for a copy of the November 19, (86-50) 1981, transcript of the closed Conmission meeting to discuss the suspension of the Diablo Canyon Unit i low-power operating license, denied this record in its entirety pursuant to Exemption 10 of the Government in
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the Surshine Act because the transcript concerns the initiation of formal agency adjudication.
ENCLOSURE A 7g
7 Denied, Cont'd Steven Aftergood, In response to an APPEAL TO THE COMMISSION for the release Committee to of OIA's " Report to the Commission - Review of NPC's Bridge the Gap Reactor Safeguards Program," April 1983, and " Follow-up (86-A-2-85-577) on Actions Taken on 01A's Report entitled, ' Review of NRC's Reactor Safeguards Program'," memorandum from G.H.
Messenger to the Commission, June 1984, continued to deny these reports in their entirety because these records are critical, self-evaluative reports prepared by the OIA on the NRC's reactor safeguards program.
MAR 7 E66 ENCLOSURE A
WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING MARCH 7, 1986 i
PROPOSALS UNDER EVALUATION r
RFP No.: RS-0IE-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 components for a specific facility and any of its associated design organizations.
Period of Performance: 36 months l
Sponsor: Office of Inspection & Enforcement Status: RFP closed on February 28, 1986. Proposals forwarded to Source Evaluators i
for review on March 3,
!986.
RFP No.:
RS-NMS-86-001
Title:
" Technical Assistance in Environmental and Socioeconomic Assessments"
==
Description:==
Contractor shall provide technical assistance to NRC in the review of DOE programs relating to the development of Environmental Impact Statements.
j Period of Performance: Three years Sponsor: Office of Nuclear Material Safety and Safeguards Status: Negotiations completed on February 27, 1986.
Best and Final offers are due on March II, 1986.
RFP No.:
RS-ADM-86-217
Title:
" Acquisition Training" I
==
Description:==
The contractor shall present the " Acquisition Training" course from materials provided by the NRC to NRC employees responsible for monitoring contractual arrangements.
Period of Performance: Two years Sponsor: Office of Administration l
Status: Best and Final offers received on March 3, 1986 and forwarded to Source Evaluation Panel for review on March 4, 1986.
1 I
CONTRACT AWARDED RFP No.:
RS-NRR-86-055 j
Title:
" Assessment of Application of Thermal-Hydraulic Phenomena for Severe Accident i
Decisions" l
==
Description:==
Generic assessment of thermal-hydraulic issues associated with severe accidents, review all LWR designs to determine the specific applicability of results 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.
I Period of Performance: 30 months i
Sponsor: Office of Nuclear Reactor Regulation Status: A Cost Reimbursement type Contract No. NRC-03-86-055 was awarded to I
the University of California, Santa Barbara, in the amount of $716,056.00 1
effective March 5, 1986.
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ENCLOSURE A MSR 7 12fc i
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0FFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending March 7, 1986 Fermi-2 On February 28, 1986, NRR was informed by a Region III inspector that eleven of the 28 main bearings on the upper cranklines of EDG Nos. 11 and 13 have been visually inspected following the " demonstration" runs l
on these two diesels. While RIII had originally requested visual inspection of 13 main bearings, a compromise was reached to pull only
- 11. All bearings except one were in very good condition. The exception was that for one bearing, there was a metal transfer to the journal. RIII is now considering whether this should be considered as a bearing " failure."
Additionally, the revised "get well" program for the Fermi-2 EDG's was not submitted by DECO on February 28, 1986, as originally planned.
It may be submitted today (March 3) or tomorrow (March 4).
River Bend At 6:49 a.m. CST on March 1, 1986, while at 38* of rated power, the River Bend Station experienced a scram due to low water level. This is the scram for 1985. The low water level was caused by a trip of an electric-driven feedwater pump caused by a voltage transient in a 480 volt feeder transformer in a non-vital circuit. The RCIC systen was manually ir.itiated, but reactor water reached the trip point for the HPCS system prior to full flow on the RCIC system.
The HPCS system was automatically initiated.
The requisite water level was restored and the HPCS systen turned-off within one minute. The reactor was then placed in hot standby.
Several hours after the onset of the event, Gulf States Utilities declared an unusual event.
Region IV is following up.
As of 1:00 p.m. CST, on March 3,1986, River Bend Station was operating at 35% of rated power and certain planned feedwater system tests were being performed.
River Bend Station was restarted on February 26, 1986, after a 10-day outage.
"04 7 I*
ENCLOSURE B 1
l i
- Catawba Unit-2 Initial fuel loading and other activities performed at Catawba Unit 2 foilowing the issuance of the low power license on February 24, 1986, are proceeding on schedule.
On March 1, 1986, Duke Power Company completed loading a full core (193 fuel assemblies) in the reactor vessel, and on March 3, 1986, they completed the installation of the upper internals.
Currently, coupling of the control rod drive shafts and insertion of flux thirrbles are in progress.
Installation of the vessel head is the ne<t major event.
The schedule for initial criticality and operation above 5% power remains unchanged (i.e., April 29, 1986, and May 6, 1986 respectively).
Diablo Canyon Unit 2 Exemption An Exemption has been granted on March 4,1986 for Diablo Canyon Unit 2 regarding the recuirement in 10 CFR 50.46(a)(1) that a plant specific ECCS cooling performance analysis must be performed with an approved code which demonstrates that the peak cladding temperature (PCT) limit of 2200 F in 10 CFR 50.46(b) is not exceeded. The heat transfer characteristics of the Unit 2 steam generators are better and the reactor cperates with a lower Tavg than was assumed in the original analysis, resulting in a PCT that exceeds the 2200 F limit by about 7 F.
The Exemption was granted to allow the licensee to perform the neceosary PCT calculations with an approved code and based on actual plant operation conditions, which are expected to be completed in late August, 1986. The Exemption is based on the heat flux hot channel factor, Fe, being reduced through administrative control, from the value of 2.32 in the Technical Specifications to 2.30 to assure that the calculated PCT does not exceed the 2200 F limit.
Tne operational characteristics of Unit 1 are consistent with the analysis and do not require en exemption.
Conanche Peak Unit 2 Texas Utilities has reported three cases where instrumentation appears to have been willfully damaged.
Building management in the Reactor Containment Building identified two cases where a piece of tubing had been cut out of the line. Upon closer examination they found that sections of the instrumentation tubing had been removed.
The third case was found by instrumentation workman who were working in the Safeguards Building.
In this case, workers noticed a suspicious looking fitting and upon closer examination they determined that the pressure fitting ferrel had been removed and the nuts had been retightened to hide the missing ferrel. On site security is currently investigating these incidents.
ENCLOSURE B K4 7 !-
l-
. Millstone 3 j
Millstone 3 began heatup on Friday, February 28, 1986, after a seven day shutdown to replace demineralizer webbing.
Several problems were experienced during the heatup, and as a result, the licensee put startup preparation on hold until corrective actions are identified and completed. The unit is now in Mode 3.
Problems experienced during heatup included 1 safety injection resulting from low primary system pressure (P-11 interlock); I safety injection resulting from low main steam pressure following reset of mair; steam isolation; and, identification of an RHR hot leg recirculation valve which was shut and should have been locked open.
i A meeting with the utility has been scheduled for 1:15 p.m. on Thursday, March 13, 1986, in Region I to discuss recent operating experience.
Shcrehan Enfnrcement Action Region I has scheduled an enforcement conference for March 13, 1986 with LILCo to discuss training and qualification problems in the Shcreham radiochemistry department. The problems were identified by an employee chemistry technician and have been verified by regional inspectors. Additional allegations regarding the falsification of chemistry logs are being investigated by 01. The Shoreham PM will attend the enforcement conference.
River Bend On l' arch 5,1986, River Bend Station exceeded 50% of rated power for the first time since receiving full power authorization.
t During a site visit near the end of January 1986, we discussed certair.
problems associated with the operation of the River Bend Station's i
feedwater system. Since that time, the license 2 has taken the follcwing corrective actions:
- Mitigated flow induced high frequency vibrations by rerouting certain piping in the condensate recirculation system.
Replaced piping downstream of the feedwater recirculation valve in the feedwater mini-flow line with erosion resistant stainless steel piping of larger diameter.
- Surface hardened a plug and cage assembly on the motor operated feedwater regulation valves to prevent galling.
Based on its judgement that the feedwater system is operating smoothly, ENCLOSURE B l
the licensee has moved above 35% of rated power and plans further start-up testing at the 55% power plateau.
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NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT WEEK ENDING MARCH 7, 1986 1.
DEFUELING As of March 10, 1986, 21 defueling canisters have been transferred from the reactor vessel to the spent fuel pool storage racks. Total weight of fuel debris and structural material transferred out of the reactor vessel is about 18,960 lbs. The estimated total weight of fuel debris and structural materials originally in the reactor vessei after the accident was 308,000 lbs.
Defueling by pick-and-place with a spade-bucket tool centinued.
l Visibility in the reactor vessel continues to be poor because of biologic growths. The organic growth in the RCS has progressed to the point where a self-sustaining community exists. The growths vary from algae in suspension through fungi and bacteria to aerobic and anaerobic organisms in the lower vessel. The licensee continues to study the problem with the assistance of outside experts in the field. A long tern treatment plan is not expected for several weeks.
2.
PLANT STATUS The reactor remains in long term cold shutdown, vented to atmosphere.
The reactor vessel head is in storage on the 347' elevation. The plenum is on its storage stand in the deep end of the fuel transfer canal. A dam is installed between the deep and shallow ends of the transfer canal, permitting a 20 foot depth (about 5 feet over the top of the plenum).
Reactor Coolant System (RCS) cooling is by natural heat loss to the reactor building atmosphere.
Calculated reactor decay heat is 10.7 kilowatts.
Incore thermocouple readings range from 72 F to 95 F, averaging 83 F.
The average reactor building temperature is 55 F.
The reactor i
buildirg airborne activity at the defueling platform is 9.5 j
E-8 uCi/cc Tritium and 5.4 E-11 UCi/cc particulates, predominately l
The reactor vessel and modified internals indexing fixture are flooded to the 327'6" elevation which is 151 feet above the core region top. The defueling platform is mounted above the internals indexing fixture.
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7 1966 ENCLOSURE B n.
2 3.
WASTE MANAGEMENT The Submerged Demineralizer System (SDS) completed processing batch 127, Fuel Transfer Canal Recycle through both trains.
(202,658 gallons)
SDS commenced processing batch 128, neutralizer tanks through train number 2.
EPICOR II remained shutdown.
Total volume processed through SDS to date is 3,812,680 gallons, and the total volume processed through EPICOR II is 2,822,963 gallons.
4.
ENVIRONMENTAL MONITORING 1
US Environmental Protection Agency (EPA) sample analysis results show TNI site liquid effluents to be in accordance with regulatory a
linits, 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 February 15 through February 22, 1986. A gamma scan detected no reactor related activity.
The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a seven day composited sample taken from February 16 through February 22, 1986. A gamma scan detected no reactor related radioactivity.
The NRC outdoor airborne particulate sampler at the TMI site t
collected a sample between February 26, and March 5,1986. No reactor related radicactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.
5.
REACTOR BUILDING ACTIVITIES Initial defueling of the reactor core is in progress.
6.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES i
Installation of the balance of Defueling Water Cleanup Systen (DWCS) i contir,ued.
Preparations are being made for decontamination in the Seal Injection Room, 281' auxiliary building.
Kelly vacuuming of the 281' elevation fuel handling building i
continued.
4 Startup testing of the canister dewatering system has stopped and j
systen responsibility returned to engineering.
2 7.
NRC EVALUATIONS IN PROGRESS Technical Specification Change Request number 49.
Recovery Operations Plan Change number 31.
SDS Technical Evaluation and System Description Update.
W) 7 f366 ENCLOSURE B J
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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.
Reactor Building Sump Criticality Safety Evaluation Report.
TMI-2 Temporary Reactor Vessel Filtration System Safety Evaluation i
Report, Revision 1.
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7 1966 i
ENCLOSURE B
0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending March 7, 1986 Near-Term NRC Actions Under the Nuclear Waste Policy Act (NWPA)
Section:
121(a) of NWPA:
EPA Final HLW Standards Status:
Staff briefed the ACRS on January 15, 1986, and NMSS Director on February 21, 1986 on proposed revisions to 10 CFR Part 60 for conformance to EPA HLW standards (40 CFR Part 191).
i Action:
The proposed Federal Register notice of revisions to Part 60 is scheduled to be submitted to the Commission in early March 1986, for approval and publication.
Section:
114(e) of NWPA:
Project Decision Schedule Status:
DOE issued the draft Project Decision Schedule (PDS) on July 18, 1985 for comment.
NRC transmitted formal comments to DOE on October 24, 1985.
Action:
NRC and DOE staffs have been meeting to resolve NRC comments on the draft PDS.
DOE is now scheduled to issue the final PDS in March 1986.
Section:
141(d) of NWPA:
Licensing of MRS Status:
NRC has developed revisions to 10 CFR Part 72 to provide the licensing framework for the MRS, should it be authorized by Congress, i
Action:
The proposed rule on 10 CFR Part 72 was submitted to the Commission (SECY-85-374) on November 15, 1935 and is awaiting Commission approval.
Section:
141(b) of NWPA:
Comments on MRS Proposal Status:
Staff comments on the MRS proposal (SECY-86-9) were approved by the Commission on February 5, 1986, and transmitted to 00E.
)
l Action:
NRC comments were to be submitted with the proposal to Congress on February 7, 1986.
However, a permanent injunction issued for the State of Tennessee has indefinitely delayed the submission of the MRS proposal to Congress.
DOE has filed an sppeal before the 6th Circuit Court of Appeals to the U.S. District Court decision.
ENCLOSURE C
?
7 136c
Section:
223 of NWPA:
Joint Notice of Technical Assistance Status:
NRC and DOE must update annually a joint notice in the Federal Register stating that the United States is prepared to cooperate and provide technical assistance to non-nuclear weapon states in the field of spent fuel storage and disposal.
Action:
The third annual joint update is currently being prepared for publication in early April 1986.
Near-Term DOE Actions of Interest March 1986 - DOE to submit Fee Adequacy Report to Congress (Section 302) 3 March 1986 - DOE to submit Annual Report to Congress (Section 304)
March 1986 - 00E to issue Final Project Decision Schedule (PDS)
(Section 114(d))
April 1986 - DOE to issue final five Environmental Assessments for first repository.
April 1986 - DOE to nominate and recommend candidate sites for site characterization.
April 1986 - 00E to issue Final Transportation Institutional Plan.
Meetings with International Visitors During the week of February 24, Waste Management Division personnel met with four European visitors to the United States.
The visitors were Rudolph Rometsch, President of NAGRA, of Switzerland; Paul deJorghe, recent Chairman of the Radioactive Waste Management Committee (RWMC) of NEA; Jean-Pierre Olivier, Secretary to the RWMC and Joszeph Hirling, Head of the Wasta Management Section of IAEA.
Discussions focused on ongoing low-level waste activities and potential future international cooperation.
NRC Receives Draft DOE Transportation Institutional Plan 00E has forwarded a revised draft of its Transportation Institutional Plan to NMSS for review and comment.
DOE developed the 180 page plan to " lay the foundation for interaction among all interested parties for the purpose of identifying and resolving issues of concern." Copies of the plan are being distributed to other offices for review by March 18, 1986.
DOE intends to publish the final Transportation Institutional Plan in April 1986.
MAR 7 1986 ENCLOSURE C t
7-~-
_y
Combustion Enoineering, Windsor, Connecticut On March 5, 1986, representatives of Combustion Engineering and a representative of American Nuclear Insurers, met with representatives of NMSS to discuss methods of analysis for determining the maximum water mist density from sprinklers at the Combustion Engineering Windsor Facility.
Methods for evaluating the nuclear criticality safety of arrays of fuel assemblies under maximum credible and optimum mist densities were also discussed.
Nuclear Assurance Corporation By letter dated February 28, 1986, Mr. Paul F. Schutt, President of Nuclear Assurance Corporation (NAC) withdrew his request for NRC approval of NAC's acquisition of the stock of Nuclear Fuel Services, Inc.
Babcock and Wilcox Volume Reduction Services Facility An environmental assessment has been issued regarding the proposed operation of a Volume Reduction Services Facility by B&W at its site in Parks Township, Pennsylvania.
The facility is designed to receive low-level radioactive waste from utilities and industrial and institutional generators for processing by incineration or high-force compaction.
The assessment supports a Finding of No Significant Impact.
Copies of the Assessment have been sent to the Administrative Judge and parties to the informal proceeding ordered by the Commission.
NFS-Erwin Strike by OCAW members continues.
There has been no progress made in resolving differences between the Union and NFS.
The Company has recently advertised for additional salaried workers to augment the current work force.
Mr. Jim Clark was recently assigned to the Erwin site from corporate headquarters in Rockville for an unspecified period of time.
NFS continues to conduct limited operations of the HEU production and scrap recovery operations.
The Union has increased its picketing activities slightly at the site and has circulated a flyer to residents of Unicoi County raising concerns about the plant and suggesting that concerned citizens call the Region II office.
l MAR 7 266 ENCLOSUPE C
Office of Inspection and Enforcement Items of Interest Week Ending March 7, 1986 1.
The following Significant Enforcement Actions were taken during the past week:
a.
EN-85-54A, an Order Imposing Civil Penalty was issued on March 4, 1986 to GPU Nuclear Corporation (TMI Unit 2) in the amount of-
$64,000. This action is based on a violation involving acts of I
discrimination against a contractor employee for raising safety concerns associated with the TMI-2 polar crane refurbishment in 1983.
b.
EN 86-08, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $25,000 was issued February 28, 1986 to Duke Power Company (0conee). This action is based on multiple examples of openings in a vital area barrier.
c.
EN 86-09, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $50,000 was issued on March 3, 1986 to Portland General Electric Company (Trojan). This action is based on an apparent breakdown in the licensee's quality assurance program.
d.
EN 86-10, a Notice of Violation and Proposed Imposition of Civil Penalty was issued on March 5, 1986 to Commonwealth Edison Company (Byron) in the amount of $50,000. This action is based on a breach of a vital area barrier.
e.
EN 86-11, an Order Suspending License, Effective Immediately was issued on March 3, 1986 to Radiation Technology, Inc. (Rockaway, NJ).
This action is based on licensee personnel repeatedly bypassing required safety interlocks on an irradiation cell.
2.
The following IE Preliminary Notifications were issued during the past week:
a.
PNO-II-86-19, Georgia Power Company (Vogtle Unit 1), Accidental Construction Fatality.
b.
PNO-II-86-20, Virginia Electric & Power Company (North Anna Unit 2),
Degradation of Diesel Generator Bushings.
c.
PNO-III-86-17, Commonwealth Edison Company (Quad Cities Unit 2),
Shutdown to Repair HPCI.
d.
PN0-IV-86-07, Gulf States Utilities (River Bend), Reactor Trip and Momentary Safety Injection.
e.
PNO-IV-86-08, Todd Shipyards (Galveston, TX). Damage to Radioactive Materials Container Onboard Ship.
f.
PN0-V-86-09, Southern California Edison (San Onofre Unit 3), Pressure Boundary Leakage.
up
,, y ENCLOSURE D
2 3.
The following IE Information Notices and IE Bulletins were issued during the past week:
1 None.
4.
Other Items a.
Senior Management Meetings i
(1) The Director, IE and Director, Division of Inspection Programs participated in a meeting at the Institute for Nuclear Power Operations (INP0) in Atlanta, GA this week.
(2) The Deputy Director, IE participated in the management meeting of the Systematic Assessment of Licensee Performance (SALP) of the Pilgrim facility at Plymouth, MA this week.
(3) The Director, Division of Emergency Preparedness and Engineering Response participated in the Operational Readiness Review of Startup Testing this week for the Palo Verde Unit 2 facility in Phoenix, AZ.
b.
Incident Response (1) The Chief, Incident Response Branch, Division of Emergency Preparedness and Engineering Response (DEPER) participated and presented a paper at the INP0 Emergency Preparedness and Emergency Communications Workshop in Atlanta, GA.
(2) An Incident Response Branch (DEPER) staff member attended an interagency meeting at FEMA to review a draft of the Relocation Tabeltop Exercise (RTE) After-Action Report.
c.
Quality Assurance (1) An inspection was conducted this week at Crane Company, Warrington, PA to review QA records pertaining to the manufacture of swing-type check valves and spare parts, and pertinent items (e.g., design changes, recommended maintenance prograrcs, failure data) related to nuclear check valves manufactured by Crane.
(2) A member of the Quality Assurance Branch, Division of Quality Assurance, Vendor, and Technical Training Programs, participated in a meeting at the Comanche Peak site at the request of Region IV to discuss electrical penetration deficiencies.
d.
Regulatory Effectiveness Review (RER)
A member of the Operating Reactors Program Branch, Division of Inspection, participated with NMSS staff on an RER of the Virgil Summer facility this week.
ENCLOSURE D
~
4 2
3 e.
TVA Activities A team from the Quality Assurance Branch, Division of Quality Assurance, Vendor, and Technical Training Programs, and consultants were at the Sequoyah site this week inspecting the Gilbert / Commonwealth design control review.
f.
Interagency Activities The next Federal Field Exercise is to be conducted in conjunction with the Zion facility and is scheduled for June 1987. FEMA and NRC headquarters and regions met with Commonwealth Edison, Illinois and Wisconsin to discuss the planning schedule, coordination, and level of participation.
l g.
Meetings - Conferences of Note A member of the Safeguards & Materials Programs Branch, Division of Inspection, presented a paper at the Waste-Management '86 Conference in Tuson, AZ this week.
I
\\
MAa 7 f986 ENCLOSURE D
OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending March 7, 1986 Containment Aerosol Experiments Oak Ridge National Laboratory (ORNL) has completed a series of five iron aerosol tests in the Aerosol-Moisture Interaction Test (AMIT) Vessel. The AMIT tests are designed to:
investigate the effects of humidity level on the physical characteristics of aerosols of interest in LWR accident sequences, determine the humidity level at which agglomerated aerosols change from chain-like to spherical in shape, and provide aerosol particle shape factor data for development of aerosol behavior codes.
For relative humidity levels of 92% and below the iron aerosols are chain-like agglomerates. For relative humidity levels of 95% and above the iron aerosols are spherical agglomerates.
Analysis of the test data is in progress for estimation of the aerosol dynamic shape factors.
The next series of AMIT tests will be on concrete aerosols.
The AMIT tests are part of an effort to assess existing aerosol analytical models and codes against experimental results. The resultant codes are used to predict the radioactive source term and sensitivity studies have shown that uncertainties in the aerosol shape factor produce a significant uncertainty in the amount of radioactive materials released in accident sequences in which containment failure occurs several hours after core melt.
RELAP5 The RELAP5 code is a thermal hydraulic system transient code having capabili-ties for calculating large or small break LOCAs as well as various non-LOCA transients in Pressurized Water Reactors (PWRs). A frozen version of RELAP5/ MOD 2 (Cycle 36) has been released for independent assessment and various applications. The RELAPS/ MOD 2 Users Manual (Volumes 1 and 2) was published and distributed to authorized recipients on December 4,1985.
A design and implementation plan for RELAP5 self-initialization was completed on December 20, 1985. Test decks for H.B. Robinson and GERDA (straight-tube steam generator facility) were obtained for testing various self-initialization options.
The H.B. Robinson deck was run at steady-state 100% power. Work is now in progress to decrease power to 80% and reach a new steady-state. Work will soon begin on the GERDA deck (which has application to B&W plants) to produce similar steady-state results.
Completion of these runs will verify j
applicability of the two-step numerics and steady-state options.
1 I
ENCLOSURE E y.
7 gg
. TRAC-B F1 The TRAC-BF1 code is a thermal hydraulic system transient code having capabi-lities for caiculating large or small break LOCAs as well as various system transients in Boiling Water Reactors (BWRs). This code is currently under developmental assessment.
It is expected that the frozen version of TRAC-BF1 will be issued by June 15, 1986 for independent assessment.
To date all the deficiencies identified in the TRAC-BF1 program plan have been eliminated or mitigated.
In addition, other corrections, improvements, and user conveniences have been incorporated. TRAC-BFI was also modified for execution on the CRAY computer. A plan has been developed for conversion of the code to execute on IBM computers.
The Rig of Safety Assessment ROSA-IV The ROSA-IV program is on schedule.
In this program the Japan Atomic Energy Research Institute (JAERI) conducts small-break LOCA and non-LOCA transient tests and provides these test data to the NRC for assessment and improvement of.
the NRC safety analysis codes.
On January 23, 1986, the experiment SB-CL-06 was conducted in the ROSA-IV Large Scale Test Facility (LSTF). The SB-CL-06 is a 5 percent cold leg break LOCA test, a counterpart test of the Semiscale S-LH-1 liquid holdup test. The preliminary results showed that there was no core uncovery and no core heatup as observed in previous tests. The liquid holdup and/or core level depression phenomena will be further investigated by JAERI. The test SB-CL-07, also a 5 percent cold leg break LOCA, will be conducted in early March. This test is similar to SB-CL-05 (1.8 percent bypass flow) except the vent valve between the downcomer and upper plenum will be opened to release the vapor generated in the core.
Numerous JAERI two-phase flow instruments are being installed in LSTF. These include traversing pitot tube, single and three beam gamma der:sitometers, and drag transducers. Most of the key locations in LSTF are now being fully ins trumented. The LSTF data acquisition capacity has been increased from 2000 to 2512 channels.
l Y,AR 7 198f ENCLOSURE E
. Multiloop Integral System Test (MIST Program The MIST facility is an integral test facility designed to simulate thermal hydraulic aspects of transients in reactors of the Babcock and Wilcox (B&W) design. The data will be used in assessing code capability.
During testing, gamma densitometers will be used to obtain void fraction data at various loca-tions of the loop.
Inspection of the gamma densitometer beryllium thimbles for corrosion was performed on February 12, 1986. The purpose was to examine the condition of the beryllium windows exposed to high pressure and temperature for roughly six weeks prior to the inspection. The preliminary determination of the integrity of the beryllium windows is important because they are part of the primary pressure boundary. A video borescope was inserted into the piping to examine the inner pipe beryllium thimble surfaces. The inspection revealed a substance had plated onto the thimbles and was observed to be breaking up.
Some of the substance was retrieved and analyzed under electron microscope and was found to be silica which had plated out on the beryllium thimbles.
The silica is expected to dissolve when the loop is refilled.
- Hence, characterization testings of the MIST facility will continue as scheduled with composite testing commencing in May, 1986.
Waste Management Research On February 27, 1986, Dr. Y. Wadachi and Mr. M. Namura of the Japan Atomic Energy Research Institute (JAERI) visited with staff of the Waste Management Branch of the Office of Research. Dr. Wadachi is the General Manager of JAERI's low Level Waste Management Laboratory, and Mr. Namura is the Deputy General Manager, Waste Safety Test Facility (WASTEF) Operations Division.
Their visit was part of the NRC/JAERI activities under a research cooperation agreement in the area of waste management research. They made brief presentations on their hot cell facilities (WASTEF) for high level waste management materials research and on their low level waste research activities.
Details of work being done by JAERI under the cooperation agreement were discussed and RES staff provided background information for the next leg of their trip, which were visits to review NRC waste management research related to the cooperation agreement at BCL, INEL and PNL.
While at PNL, final arrangements were made for the 12 month stay of Dr. Ohnuki of JAERI at PNL, where he will work on an NRC low level waste site modelling project.
Dr Wadachi and Mr. Namura were accompanied on their visits to the laboratories by Dr. Kyo S. Kin of the NRC/RES Staff.
sR 7198f ENCLOSURE E l
_4-RES RULEMAKING ACTIVITIES Broad Scope Modification of GDC 4 Requirements for Protection Against Dynamic Effects of Postulated Pipe Rupture (Part 50)
The proposed rule would permit licensees and applicants to use newly developed analytical methods involving widely accepted advanced fracture mechanics theories for determining that certain pipe ruptures need not be treated in the design basis for dynamic effects. The revised requirements would permit the removal of counter productive hardware, such as pipe whip restraints and jet impingement barriers, from operating plants, plants under construction and future designs.
The Broad Scope Rule was presented to the ACRS Subcommittee on Metal Components on February 27, 1986. Comments were favorable from all sources and a positive recommendation from the ACRS full committee is expected on March 13, 1986.
Licenses and Radiation Safety Requirements for Well Logging Operations (Part 39)
The proposed rule would establish specific radiation safety requirements applicable to licensees who perform operations such as well logging, mineral logging, radioactive markers, and subsurface use of radioactive materials in tracer studies.
The proposed rule is necessary because current NRC regulations address these operations in a general way without providing the specific guidance necessary to ensure that these operations are performed safely.
A draf t final rule was distributed for division review on January 8,1986, and staff comments have been received. The draft rule was sent by SP to Agreement States for their review.
State comments are due by March 14, 1986.
Emergency Preparedness for Fuel Cycle and Other Radioactive Materials Licensees (Parts 30, 40, 70) i In 1981 the NRC issued orders to certain fuel cycle and other radioactive I
material licensees requiring them to submit comprehensive onsite radiological emergency plans.
Rulemaking was initiated on August 3, 1981, for codification of those orders.
On February 7, 1986, the Director, RES, sent a revised rulemaking package to the Acting EDO for his signature.
IE sent the package to FEMA for reconcurrence and requested that the Acting EDO hold the package until this reconcurrence is obtained.
On February 20, 1986, representatives from IE and RES met with FEMA staff to discuss the rule.
On February 24, 1986, RES received changes in the rule, requested by FEMA staff.
FEMA wanted more consideration of chemical toxicity.
On March 5,1986, a reworded rule meeting FEMA's satisfaction was prepared and will be sent to the Acting ED0 after obtaining office concurrences.
Jt 7 198i ENCLOSURE E
s
/
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS VEEK ENDING MARCH 7, 1986 NRC Technical Cooperation With Ecypt-The latest in a series of IAEA-sponsored nuclear safety workshops, carried out with NRC assistance, was held in Cairo, Egypt from January 26 to February 14 Four NRC lecturers participated in this workshop which focused on environmental impact assessments of nuclear power plants.
Egyptian senior nuclear officials, speaking at the opening session, stressed the important contribution which is being made by the U.S., and in particular the NRC, in trainin.g and preparing Egyptian staff members to perform their safety ano regulatory functions.
IAEA Seismic Meetino in the USSR NPC staff nerbers fron NRR and RES will participate in an IAEA meeting on earthauake ground motion and the evaluation of anti-seismic design features of nuclear facilities being held in Moscow, llSSR, from March 26-28, 1986.
ENCLOSURE G MAR 7 586
OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING MARCH 7, 1986 Orientation Meeting for Iowa SP and Region III staff will meet with the Iowa radiation control program staff, March 11-12, 1986, to review their progress in implementing their Section 274b Agreement program. The program became effective January 1, 1986.
Training Course During the week of March 17-21, 1986, twenty State radiation control personnel will participate in the course entitled "The Medical Use of Radionuclides" at the Oak Ridge Associated Universities, Oak Ridge, Tennessee, l
ENCLOSURE H yAR 7 E86
REGION III STATUS REPORT DAVIS-BESSE LOSS OF FEEDWATER EVENT MARCH 7, 1986 Plant Status The plant remains in cold shutdown.
Restart Activities A NRR maintenance survey inspection team will be on site March 24-28 to follow up on previous findings and to evaluate the licensee's actions concernica management practices as they relate to the maintenance area.
MOVATS testing, environmental qualification work and other maintenance
++
activities continue on the 167 safety-related motor-operated valves onsite.
The licensee has completed all planned work on seventy eight valves and returned them to service. The licensee is repairing and testing valve motor operators continuously with three overlapping ten-hour shifts.
The NRC test review team continues to provide weekly coverage of licensee
++
testing activities. The licensee has completed their review of the systems important to safe plant operations and the testing requirements associated with each. This review has identified a test program consisting of 245 tests of which 32 will be performed following criticality.
This program consists of 142 existing or modified surveillance tests and 103 new test procedures. Eleven tests were performed last week and 54 tests have been performed to date.
Other Activities Inspections of safety system piping supports in the auxiliary building are ++
continuing. Evaluation of the nonconformances (NCR) found on supports in containment is in progress. Of the support NCRs requiring disposition prinr to restart, eighteen remain to be dispositioned.
The licensee's identification, repair, replacement and engineering
++
review of items requiring environmental qualification (EQ) is continuing.
Last week inspectors from Region III and headquarters, assisted by contract personnel, performed an EQ audit.
While no significant deficiencies were identified, a subsequent inspection is planned prior to restart.
Licensee Activities The licensee's Board of Directors Operations Committee will be onsite next ++
week to attend the weekly staff meeting.
MAR 7 M66 ENCLOSURE L i
-. E.
~..
C.
STAFF RE0VIREMENTS - BRIEFING BY INCIDENT INVESTIGATION TEAM ON STATUS OF RANCHO SECO. TUESDAY. FEBRUARY 25. 1986. COMMISSIONERS' CONFFRENCE ROOM.
1 D.C. 0FFICE (OPEN TO PUBLIC ATTENDANCE) Memn SECY to V. Stello dated 3/6/R6 The Commission
- met to be briefed by staff on the loss of DC power in the integrated control system (ICS) event which occurred at the Rancho Seco Nuclear Power Plant on December 26, 1985.
Chairman Palladino requested information on whether or not the Rancho Seco plant has a reactor water level indicator.
(NRR)
(SECY Suspense:
3/14/86)
Chairman Palladino also requested the staff to respond on why the emergency feedwater initiation and control (EFIC) system has not been installed at Rancho Seco.
Commissioner Bernthal requested information on the significance of the EFIC system in terms of overall plant safety.
(NRR)
(SECY Suspense:
3/14/86)
Chairman Palladino requested the staff to provide the following:
1.
schedule for follow-up plan; 2.
schedule for staff recommendations on corrective action; 3.
schedule for staff assessment as to why plant modifications which should have been done were not done; 4.
status of. confirmatory orders or lerters requiring the plant to remain shut down until NRC is satisfied that corrective actions are completed; and 5.
information on whether the licensee is planning a submittal for the Commission and, if so, when.
l, (NRR)
(SECY Suspense:
3/14/86)
Chairman Palladino indicated that a follow-on meeting with l
staff and, possibly, a meeting with the Sacramento Municipal Utility District (SMUD) would be scheduled following receipt of staff's follow-up plan.
- Commissioner Roberts was not present.
tiAh 71%6 ENCLOSURE O
ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING MARCH 7, 1986
\\
A.
STAFF REQUIREMENTS - STAFF BRIEFING ON INTEGRATED SAFETY ASSESSMENT PROGRAM, 2:00 P.M., WEDNESDAY, FEBRUARY 19, 1986, COMMISSIONERS' CONFERENCE ROOM, D.C.
OFFICE (OPEN TO PUBLIC ATTENDANCE) Merao SECY to V. Stello dated 3/3/86 The Commission met with the staff to discuss the status of the Integrated Safety Assessment Program, ISAP, for operating nuclear power plants.
Commissioner Asselstine requested the staff to identify the fees collected from the plants involved in the ISAP pilot program that are related to the program and consider cost recovery possibilities for future ISAP activities.
(NRR)
(SECY Suspense:
3/31/86)
The staff promised to provide an analysis of ISAP to the Commission by Fall, 1986.
(NRR)
(SECY Suspense:
9/30/86)
The staff further promised to provide an annual report to the
~
Commission that includes a discussion of the present NRC resources utilized in ISAP and a projection of completion of the ISAP as applied to Haddam Neck and Millstone 1, the plants involved in the pilot program.*
(NRR)
(SECY Suspense:
3/31/86)
B.
STAFF REQUIREMENTS - DISCUSSION OF DOE HIGH LEVEL WASTE PROGRAM, 10:00 A.M.,
THURSDAY, FEBRUARY 27, 1986, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to RECORD dated 3/6/86 The Commission met to be briefed by Mr. Ben Rusche, Director, Office of Civilian Radioactive Waste Management, U.S. Department of Energy, on the status of the high level waste program.
There were no requirements at this meeting.
NAit 7 1986 ENCLOSURE 0
E
- =
NRR MEETING MOTICES*
3 MARCH 7, 1986 I
i DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 3/10/86 50-289 Room 6507 Discuss in detail the final report GPUN - TMI-1 J. Thoma 1
10:00 a.m.
MNBB submitted by GPUN concerning long term corrosion program conducted by the TMI-1 OTSG.
3/10/86 50-317 poem P-422 Resolve differences between BG&E BG&E D. Jaffe 9:00 a.m.
50-318 Phillips Bldg.
and NRC staff positions on reactor coolant system, high point vents, j
and Technical Specifications.
3/10/86 50-354 PSE&G T.C.
Determine the readiness of Hope PSE&G D. Wagner 4:30 p.m.
Salem, N.J.
Creek for a low-power operating license.
3/11/86 50-354 Hope Creek Site Same as above re PSE&G T.C.
PSE&G D. Wagner 8:00 a.m.
Lower Alloways Creek, N.J.
1 3/12/86 50-395 Room 114 Discuss V.C. Summer fire South Carolina J. Hopkins 10:30 a.m.
Phillips Bldg.
protection with regard to Tc Electric & Gas Co.
indication and schedule.
3/11-12/86 50-275 Room P-118 Discuss the status of the Long PG&E H. Schierling 4
8:30 a.m.
50-332 Phillips Bldg.
Term Seismic Program (LTSP).
Also discussion will include the results of the PG&E scoping study.
3/13/86 h!
50-267 NRC Region IV Discuss LC0 4.1.9 of Fort PSC K. Heitner 8:30 a.m. Es Parkway Central St. Vrain (FSV) Technical El Plaza Building Specifications (TS).
]
??
Arlington, TX.
l m
Copies of summaries of these meetings will be made publicly avai.lable and placed in the respective docket file (s) o in the NRC and local public document rooms
l 1
i x
E i
NRR PEETING NOTICES
- I MARCH 7, 1986 DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT j
3/20/86 50-213 Landow Bldg.
Discuss the utilities plans NU F. Akstulewicz 9:30 a.m.
7910 Woodmont Ave.
to perform reload analyses Suite 208 within NU for the operating Bethesda, MD PWR's.
i 3/20/86 50-219 Room P-118 Discuss the licensee's request GPUN J. Donohew 9:30 a.m.
Phillips Bldg.
dated September 24, 1985, to cancel the replacement of the large containment purge / vent valves in the Cycle 11R outage.
i i
l 2
i E
i P8 Si m
m l
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 l
4
)
1:
NMSS MEETING WOTICES FOR WEEK ENDING:
3/7/86 Division of Fuel Cycle and Material Safety M
DOCKET ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 3/10/86 71-5796 Willste Discuss pending application and NRC H. Irvin (AMS)
Odegaarden 1:00-3:00 5th floor deficiency letter with Advanced R. Odegaarden (FC) conf room Medical Systems.
H. Lee (FC) i j
3/11/86 40-2061
- Argonne, To discuss supplement to Kerr-M. Horn (FC)
Horn e
IL McGee's FES.
G. LaRoche (FC) 3/11-12/86 40-3392 Glen
" Enforcement Conference" to discuss D. Cool (FC)
Cool Ellyn, IL NRC findings during a recent special Region III Reps l
inspection of uranium hexafluoride operations (Allied Corporation).
i 3/17-20/86
- Richmond, To attend DOE seminar on transporta-M. Lauer (FC)
Lauer VA tion regulation review.
3/18-20/86 King of Conduct the National Program Review D. Chapell (FC)
Chapell i
- Prussia, of Region I decentralized material
{
PA licensing activities, i
i 3/21/86
- Bethesda, Present lecture on NRC's current P. Vacca (FC)
Vacca 9:00-11:00 MD policies and practices in medical licensing at the Naval Medical l
Corrmand.
l Division of Waste Management j
None i
I I
t Division of Safeguards j
Hone s
A i
v i
l 4
E 20 March 7, 1986 RII MEETING NOTICE DOCKET ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 3/11/86 RII Office Carolina Fcwer & Light Licensee and Selected Gibson 12:30 p.m.
Co. management meeting RII Staff Members to discuss the loss of power that occurred at the Robinson facility on 1/28/86.
3/14/86 RII Office Duke Power Company Licensee and Selected Grace 10:30 a.m.
management meeting to RII Staff Mcmbers discuss problems associated with the Service Water System at the McGuire Nuclear Station.
E P
S E
m 73
.