ML20133Q076
| ML20133Q076 | |
| Person / Time | |
|---|---|
| Issue date: | 10/30/1985 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-851025, NUDOCS 8511010359 | |
| Download: ML20133Q076 (38) | |
Text
f PDL October 30, 1985 For:
The Commissioners From:
T. A. Rehm, Assistant for Operations, Office of the ED0
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING OCTOBER 25, 1985 A sumary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.
Contents Enclosure Administration A
Nuclear Reactor Regulation 8
Nuclear Material Safety and Safeguards C
Inspection and Enforcement D
Nuclear Pegulatory Research E
Executive Legal Director F*
International Programs G
State Programs H
Resource Management 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
Meeting Notices P
Proprietary or Other Sensitive Information (Not for Q
external distribution)
- No input this week.
a
/
]
[T. A. Rehm, nt for Operations Office of the Executive Director for Operations
Contact:
T. A. Rehm, EDO i
492-7781 8511010359 e51030 PDR CONNS NRCC WEEKLYINFOREPT PDR
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.T HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING OCTOBER 25, 1985 Shoreham Emergency Planning On October 18, 1985 the Appeal Board upheld the Licensing Board decisions of April 17, 1985 and August 26, 1985 that the Long Island Lighting Company does not have the legal authority to perform off-site emergency planning functions in the absence of state and local participation. The Board rejected the licensee's pre-emption, i
immateriality, and realism arguments. The licensee is expected to i
appeal this decision to the Comission.
TMI-1 Start Up and Hearings There are two active hearing issues which were part of the THI-1 restart hearings and which the Comission decided did not have to be completed prior to a restart decision. One hearing involved the Dieckamp Mailgram issue and the other was on operator training. Both issues have been decided by the Hearing Board in favor of the licensee and have been appealed by TMIA and the UCS. Oral arguments for the training decision appeal were scheduled for October 24, 1985. However, in a letter dated October 8, 1985, the UCS withdrew its appeal of the Board decision on training and our lawyers have been verbally informed that the UCS will not pursue their appeal of the Dieckama Mailgram decision. Also on October 8, 1985, TMIA in a letter wit 1 drew tts i
appeal of the Dieckamp Mailgram decision. TMIA stated that they still disagreed with the decision but withdrew their appeal due to a lack of funds. Our lawyers also have been verbally informed that TMIA will not pursue their appeal of the training decision either. Oral arguments on the training appeal have been cancelled and the Appeal Board will conduct a sua sponte review. A similar action is expected on the Dieckamp Mailgram appeal.
i, Interaaency Study of State Preparedness for Radiological Emergencies -
NRC is participating in an interagency committee formed by DOT and FEMA to consider and adopt revisions to the Federal Emergency Management Agency (FEMA) report on " Guidance for Developing State and Local Radiological Emergency Response Plans and Preparedness for Transportation Accidents" (FEMA - REP-5).
The report is being revised to reflect comments, suggestions, and recommendations received since its publication in 1983.
A contractor survey and analysis of transportation accidents is nearing completion; the contractor's final report will be used to provide information for an Appendix to the revised report, FEMA-REP-5. Another contractor is conducting a nationwide survey of state and local governs.ent agencies and private industry to learn what training opportunities there are for emergency response personnel and what resources are available for use in planning emergency response programs and in developing the appropriate organization. Analysis of the results of the survey will be given in a final report scheduled for completion in March 1986 and advance information will be taken into account in the revision of the report, FEMA-REP-5.
OCT 2 51985
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OFFICE OF ADMINISTRATION Week Ending October 25, 1985 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1984 179 23 Received, 1985 716 40 Granted 560 29 Denied 165 16 Pending 170 18 ACTIONS THIS WEEK Received Stevi Stephens, Requests all records related to the "Sequoyah Incident" Nuclear Awareness and an incident on or about August 4,1985, at the Wolf Network Creek nuclear power plant.
(85-706)
David S. Palmer, Requests copies of " Evacuation Time Estimates" dated Emergency Response March 3, 1981, and any amendments, updates, appendices Planning &
and addenda, regarding TMI.
Management, Inc.
(85-707)
Bernard M. Savaiko, Requests a list of manufacturers licensed pursuant Department of to 10 CFR 32.14.
Army (85-708)
Kevin Prongay, Requests six categories of records related to a Milberg Weiss mechanical shock arrestor (snubber) failure at the Bershad Specthrie Dresden nuclear power plant on February 10, 1983,
& Lerach and the Pacific Scientific Company, Inc.
(85-709) i John Lapp, Requests a copy of the bid abstract for RFP RS-SECY-Neal R. Gross86-201.
and Co., Inc.
(85-710)
CONTACT:
J. M. Felton 492-7211 00T 2 51985 ENCLOSURE A
2 Received, Cont'd Cindee Virostek Requests copies of 36 specified records regarding B&W's (85-711) facilities in Apollo and Parks Township, Pennsylvania.
Cindee Virostek Requests copies of 38 specified records regarding B&W's (85-712) facilities in Apollo and Parks Township, Pennsylvania.
Charles W. Kelly, Requests copies of all IE Notices for Ma'terial Licensees Core Corporation written since January 1, 1983.
(85-713)
Joseph Cuthbert, Requests a list of awardees for the Phase I SBIR Program Advanced Technology for FY 85.
Center of South-Eastern Pennsylvania (85-714)
Lyle Graber, Requests a copy of an 0IA Report dated March 1984, NUS Corporation entitled, " Performance of CRGR."
(85-715)
Joyce Miller Nelson Requests a copy of SECY-85-279, " Revised Advanced TCP, Inc.
Reactor Policy Statement."
(85-716)
Granted Roanne Sragow, In response to a request for a copy of the current Lack & Sragow design plan (as of February 28,1985) for the McGuire (85-621)
Unit 2 nuclear power plant upper containment building, specifically the area where the rector building fuel handling manipulator crane was located on February 28 at the time of the accident in which an employee was fatally injured, made available a copy of the requested drawing.
Michael R. Deane, In response to a request for copies of (1) SECY-85-208; NUS Corporation (2) procedures used by the Office of Investigations (01)
(85-628) regarding the rights of utility employees; and (3) all minutes from past Regulatory Requirements Review Committee meetings, made available 38 records.
Informed the requester that additional records subject to this request are already available at the PDR. Also, inforned the requester that SECY-85-208 was denied in a previous 1985 FOIA request and that, after review of the paper again, this previous denial stands.
Charles Barnes In response to a request for a listing of active and (85-643) inactive docket 40 licensees and their locations and all records from March 14, 1985, to the present relating to a Sequoyah Fuels Corporation (SFC) "0" and "Q" Sand ISL Project regarding operational concerns which were relayed to the Uranium Recovery Field Office staff from a former SFC employee, made available two printouts and three OCT 2 51985 ENROSE A L
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Granted, Cont'd James Craig Dodd, In response to a request for copies of records relating Dodd & Helm to operations conducted pursuant to an agreement between (85-672)
Department of Energy and Sandia Corporation and two other specified agreements regarding a " Western Gas Sands Multi-Well Experiment" conducted in Garfield County, Colorado, informed the requester that the NRC has no records subject to this request.
Billie P. Garde, In response to a request for all records relating to Government NRC Inspection Report No. 50-445/85-02 issued on Acccuntability September 11, 1985, regarding the Comanche Peak Steam Project Electric Station, Unit 1, informed the requester that (85-673) the only record subject to this request is already available at the PDR.
Carol P. Barton, In response to a request for a list of data bases, Information including mailing lists, that NRC subscribes to or buys Handling Services from private or public sources, made available a copy of (85-679)
, the requested list.
Denied David Berick, In response to a request for nine categories of records Environmental concerning uranium mill tailings regulations, nade Policy Institute available 135 records. Denied 55 records in their (84-709) entirety and portions of nine records, release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.
Robert Delair, In response to a request for copies of records which Kirkpatrick &
relate to the presence and influence of organized crime Lockhart at the Shoreham nuclear power plant site during (85-248) construction of the plant, made available four records.
Denied one record in its entirety, release of which would tend to inhibit the frank and candid exchange of information in future deliberations and thus would nN oe in the public interest.
Nina Bell, In response to a request for three categories of Nuclear Infornation records regarding cost estimates of backfits to currently and Resource operating power reactors, made available 22 records.
Service Informed the requester that additional records subject to (85-361) this request are already available at the PDR.
Denied one record in its entirety and portions of six records, l
containing predecisional information regarding preliminary consideration of cost analyses of unresolved j
safety issues which were not pursued and finalized, ENCLOSURE A l
OCT 2 51985
4 a
WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING OCTOBER 25, 1985 RFP ISSUED 3
RFP No.: RS-NMS-86-002
^
Title:
"The Need for Spent Fuel Storage Capacity"
==
Description:==
Expertise in determining spent fuel inventory and storage capacity projections through calendar year 2000.
Period of Performance: 21 months Sponsor: Office of Nuclear Material Safety and Safeguards Status: RFP issued on October 24, 1985. Proposals due November 26, 1985.
PROPOSALS UNDER EVALUATION RFP No.: RS-ADM-85-235
Title:
"NRC TransTation Services"
==
Description:==
The contractor will be required to furnish translation services for reports and other related material provided by NRC when issued by a formal work order.
Period of Performance: 2 years i
Sponsor: Office of Administration, Division of Technical Information and Document Control Status: The competitive range has been established and negotiations are scheduled for the week of October 28, 1985.
RFP No.: RS-01E-86-170
Title:
" Assistance for Emergency Response"
==
Description:==
Provide technical, logistical, and administrative assistance for the maintenance and functioning of the NRC Headquarters Operations Center.
Period of Performance:
12 months Sponsor: Office of Inspection and Enforcement Status: RFP closed on September 20, 1985. Proposals forwarded to Source Evaluators for review on October 3, 1985. Competitive range to be established on November 5,1985.
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OCT 2 51285 ENCLOSURE A
i 0FFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending October 25, 1985 Peach Bottom Atomic Power Station, Unit 2 At approximately 9:20 a.m. on the morning of October 17, 1985, Peach Bottom Unit 2 experienced a full reactor scram due to the simultaneous i
failure of all three turbine-driven feedwater aumps. At the time Unit 2 was operating at 100% power and Unit 3 was slutdown and in its refueling outage. The Peach Bottom Station was in the process of participating in its annual emergency exercise with Regional personnel present in the Combined-Unit 2 and 3 control room during the initiation of this scram. The licensee declared an unusual event at 9:21 a.m. and a press release was issued.
With the loss of all three feedwater pumps, reactor water level at Unit i
2 dropped to a lowest recorded value of minus 95 inches. By the time this level had been reached, HPCI, RCIC and auto-isolation (Primary Containment Isolation) had been initiated as designed.
A plus 50 inch reactor water level was achieved by these systems at 9:28 a.m.
Reactor operator response was good during this event as observed by the Regional staff.
At approximately 10: 12 a.m., with the plant maintaining reactor water level with one feedwater pump, the unusual event status was terminated. Peach Bottom Unit 2 is currently in hot standby. The licensee is undertaking its post-trip review and analysis to determine the cause of the simultaneous trip of all three feedwater pumps.
The Region is following this event and its review. The results of the licensee's post-trip review will determine the continued status of Unit 2.
The licensee's review indicates that a faulty ' summing' switch (a part of the feedwater control system) indicated zero feedwater flow resulting in overspeed of all feedwater turbines and subsequently resulting in feedwater turbine trip.
Limerick On October 11, 1985, the staff was advised that the Pennsylvania Commonwealth Court had found in favor of the Philadelphia Electric Company regarding construction of the Point Pleasant Diversion Project (plant supplementary cooling water system) for the Limerick Station.
The Bucks County Court had found in favor of PECo earlier in 1985.
The Commonwealth Court's decision may be further appealed to the Pennsylvania Supreme Court.
l ENCLOSURE B OCT 2 51985 l
On October 17, 1985 the Pennsylvania Public Utility Commission voted 2 to 1 in a non-binding poll to permit continued construction of Limerick Unit 2 subject to a cap on the costs of Unit 2.
Under this arrangement expenses beyond the cap would not be passed on to the consumer. The Comission plans a formal vote on Unit 2 in December,1985. PECo has previously proposed a plan to the PUC to continue with Unit 2 subject to a cost containment cap.
Comanche Peak, Units 1 and 2 Austin B. Scott, Jr. has been named the new vice president - Nuclear Operations for Texas Utilities Generating Company (TUGCO).
Scott, who recently retired as Rear Admiral in the U.S. Navy, is former commander of the submarine force of the U.S. Pacific Fleet. The appointment, announced October 21, 1985, by M. D. Spence, President TUGCO, will be effective November 1, 1985.
Scott will direct all nuclear operations at Comanche Peak from offices at the plant.
In addition, Spence announced that James C. Kuykendall, current manager of nuclear operations at Comanche Peak, has been named vice president with broad technical and administrative responsibilities in TUGCO's nuclear organization.
Shoreham Emergency Planning On October 18, 1985 the Appeal Board upheld the Licensing Board decisions of April 17, 1985 and August 26, 1985 that the Long Island Lighting Company does not have the legal authority to perform off-site emergency planning functions in the absence of state and local participation. The Board rejected the licensee's pre-emption, imateriality, and realism arguments. The licensee is expected to appeal this decision to the Comission.
Peach Bottom, Unit 3 Evaluations by the licensee and Regional personnel pinpointed the loss of all three feedwater pumps on October 17 (Unit 3) to a faulty ' total feedwater flow suming unit' which is part of the feedwater level control system. As a result of the failure or malfunctioning of this I
suming unit, a zero feedwater flow was indicated which resulted in overspeed of all feedwater turbines in an attempt to compensate and subsequently resulting in the tripping (overspeed protection) of all three feedwster turbines.
1 A replacement suming unit was installed that same day and testing to the satisfaction of both the licensee and the Region indicated that the system was fully operational with the replacement unit.
ENCLOSURE B W 25 E
i 3-Control rod withdrawal was commenced on October 18 and full power was achieved by Sunday, October 20. The Senior Resident Inspector is following up on the licensee's investigation as to the cause of the summer unit failure.
TMI-l Start Up and Hearings There are two active hearing issues which were part of the THI-l restart hearings and which the Commission decided did not have to be completed prior to a restart decision. One hearing involved the Dieckamp Mailgram issue and the other was on operator training. Both issues have been decided by the Hearing Board in favor of the licensee and have been appealed by TMIA and the UCS.
Oral arguments for the training decision appeal were scheduled for October 24, 1985.
- However, in a letter dated October 8, 1985, the UCS withdrew its appeal of the Board decision on training and our lawyers have been verbally informed that the UCS will not pursue their appeal of the Dieckamp Mailgram decision. Also on October 8, 1985, THIA in a letter withdrew its appeal of the Dieckamp Mailgram decision. TMIA stated that they still disagreed with the decision but withdrew their appeal due to a lack of funds. Our lawyers also have been verbally informed that TMIA will not pursue their appeal of the training decision either. Oral arguments on the training appeal have been cancelled and the Appeal Board will conduct a sua sponte review. A similar action is expected on the Dieckamp Mailgram appeal.
ENCLOSURE B OCT 2 51935
NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT e
WEEK ENDING OCTOBER 25, 1985 1.
PLANT STATUS The facility remains in long term cold shutdown with the Reactor Coolant System (RCS) vented to the reactor building atmosphere and the reactor vessel head and plenum assembly removed 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 oftheplenym).
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 Internal Indexing Fixture in preparation for defueling.
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 72*F to 95*F with an average of 83*F.
The average reactor building temperature is 56*F. The reactor building airborne activity is 4.4 E-8 uCi/cc Tritium and 3.7 E-10 uC1/cc particulate, predominantly Cesium 137.
Spent Fuel Pool "A" is flooded to a depth of 20 feet. About 6 feet of water is over fuel canister storage racks.
2.
WASTE MANAGEMENT The Submerged Demineralizer System (SDS) commenced processing batch 125, Fuel Transfer Canal through Train No.1.
To date a total of 33,940 gallons has been processed.
EPICOR II is temporarily shutdown while changing out liners.
Total volume processed through SDS to date is 3,022,533 gallons, and the total volume processed through EPICOR II is 2,700,737 gallons.
10 CFR 61.55 Exemption approval was given by NRC which authorized the licensee to classify EPICOR II liners containing 1 microcuries l
per cubic centimeter of Strontium 90 as Class A waste.
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ENCLOSURE B
2 3.
DOSE REDUCTION / DECONTAMINATION ACTIVITIES Decontamination activities are continuing on the 281' level of the C
auxiliary building.
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.
Removal of insulation and decontamination of the pressurizer is in progress.
4.
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 j
consisted of seven daily composite samples taken from October 5 i
through October 12, 1985. A gama scan detected no reactor related j
activity.
The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a seven day composited sample taken from October 6 through October 12, 1985. A gama scan detected no 4
reactor related radioactivity.
4 The NRC outdoor airborne particulate sampler at the TMI Site i
collected a sample between October 16 and October 23, 1985. No reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of detectability.
t 5.
DEFUELING OPERATIONS TO BEGIN
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The initial phase of defueling the damaged reactor core at Three 4
Mile Island Unit 2 is scheduled to begin this week. The defueling will involve the use of specially designed tools and equipment and will be perfonned by operators specially trained and licensed by NRC in defueling procedures. This phase of defueling will involve manipulation of the partial fuel assemblies in preparation for i
loading into canisters designed for storage and shipment of the damaged fuel. Shipping of the loaded canisters by rail to the Idaho National Engineering Laboratory is scheduled for next spring.
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REACTOR BUILDING ACTIVITIES 1
Defueling Water Cleanup System (DWCS) preoperational testing and i
modification continued.
Installation of the vacuum defueling system is in progress.
l Work is in progress on the canister positioning system.
Canister handling bridge indexing and load testing is in progress.
l ENCLOSURE B l
~. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _, _ _ _,
3 7.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the DWCS continued. Partial DWCS turnov r for processing RCS during early defueling is expected to be completed in October.
Spent Fuel Pool 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 Requests number 48, 49, and 50.
Recovery Operations Plan Change numbers 29, 31, and 32.
Fuel Canister Technical Evaluation, Revision 1.
Defueling Safety Evaluation.
Application for seismic exemption.
SDS Technical Evaluation and System Description Update.
Core Stratification Sample Safety Evaluation.
Heavy Load H,andling Safety Evaluation Report.
Defueling Water Cleanup System Technical Evaluation Report, Revision 7.
Early Defueling Safety Evaluation Report, Revision 4.
Containment Air Control Envelope Technical Evaluation Report, Revision 5.
9.
PUBLIC MEETING The next meeting of the Advisory Panel is scheduled for 11:00 AM, November 19, 1985, in Washington, DC, before the NRC Commissioners. The next meeting in the THI area is scheduled for December 12, 1985, at the Harrisburg, PA Holiday Inn, 23 South Second Street, Harrisburg, PA, from 7:00 PM to approximately 10:00 PM.
Persons desiring the opportunity to speak before the Panel are asked to contact Mr. Thomas Smithgall at 717-291-1042 or write to him at 2122 Marietta Avenue, Lancaster, Pennsylvania 17603.
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OCT 2 51985 ENCLOSURE B l
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OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending October 25, 1985 Near Term NRC Actions Under the Nuclear Waste Policy Act 1983 Section: 114(f) of NWPA:
Preliminary Determination of Site Suitability Action:
T'1e Comission met with representatives of States and Tribes on Friday, September 6, 1985 to receive their views on DOE's timing of the preliminary determination.
The Comission then requested OGC to examine whether NRC is legally required by NWPA to take any action now in response to the current DOE position on the timing of the preliminary determination.
In a memo to the Comission on September 24, OGC advised that the Comission had no need to act now, but should not remain silent on the issue.
Status:
The Commission response to the OGC recommendation and to SECY-85-237 requests that staff prepare, for Comission review, an appropriate statement to be issued to restate the Comission's concurrence decision on the DOE Siting Guidelines.
Two Comissioners disagreed with this action.
Section:
114(e) of NWPA:
Project Decision Schedule Coments Action:
DOE had requested coments on the draft PDS by September 13, 1985.
The Comission voted to approve the PDS coments on September 19, 1985.
The final edited version was submitted to SECY on October 16, 1985 for transmittal to DOE.
Status:
The PDS comments are being edited at the Commission to include the Commission decision (with two Comissioners disagreeing) on 114(f).
The comments will then be transmitted to DOE.
Section:
301 of NWPA:
DOE Mission Plan Action:
NRC testified concerning the final Mission Plan before both houses of Congress in early September.
i ENCLOSURE C CCT 2 51985
-g-Status:
NRC has been invited to testify on November 6, 1985 before the House Subcommittee on Energy Research and Production concerning the implementation of NWPA and also the Mission Plan, among other topics.
NRC is also scheduled to testify before the Senate Subcommittee on Nuclear Regulation on October 29, 1985.
Interagency Study of State Preparedness for Radiological Emergencies NRC is participating in an interagency committee formed by DOT and FEMA to consider and adopt revisions to the Federal Emergency Management Agency (FEMA)
^
report on " Guidance for Developing State and Local Radiological Emergency Response Plans and Preparedness for Transportation Accidents" (FEMA - REP-5).
The report is being revised to reflect commen,ts, suggestions, and i
recommendations received since its publication in 1983.
A contractor survey and analysis of transportation accidents is nearing completion; the contractor's final report will be used to provide information for an Appendix to the revised report, FEMA-REP-5.
Another contractor is conducting a nationwide survey of state and local government agencies and private industry to learn what training opportunities there are for emergency response personnel and what resources are available for use in planning emergency response programs and in developing the appropriate organization.
Analysis of the results of the survey will be given in a final report scheduled for completion in March 1986 and advance information will be taken into account in the revision of the report, FEMA-REP-5.
Kerr-McGee (West Chicago)
FC staff members traveled to the Chicago area to discuss preparation for the Kress Creek hearing with ELD and Region III personnel and to review the status of the ANL work on preparation of the supplemental EIS.
NFS-Erwin Strike by OCAW members continues.
There has been some negotiating between the Union and NFS within the last two weeks but no resolution has been reached.
NFS is conducting limited operations of the HEU production, scrap recovery and R&D facilities.
No problems with site operations have arisen to date.
B&W Apollo On October 18, a representative of the Babcock & Wilcox Company, Apollo, PA met with Safeguards personnel to discuss the possibility of reducing safeguards requirements at the Apollo and Leechburg facilities because of reduced quantities of possessed SNM. A follow-up meeting is tentatively planned for October 24 to discuss details of the reduced safeguards program.
l ENCLOSURE C OCT 2 51985
OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending October 25, 1985 1.
The following Significant Enforcement Actions were taken during the past week:
a.
EN 85-14A, Revised Order Modifying License was issued October 18, 1985 to Nuclear Fuel Services, Incorporated (Erwin, TN). The licensee responded to the Order Modifying License (EN 85-14, dated February 15,1985) in letters from their corporate office and plant, both dated May 22, 1985. A meeting between NRC representatives and NFS staff was held on April 1, 1985. During this meeting NFS expressed a desire to modify, and in some cases, clarify the proposed license conditions. NRC and NFS agreed that NFS would submit suggested changes.
These suggestions were transmitted in a licensee letter dated April 22, 1985. NRC met again with NFS on October 11, 1985 and reached final agreement on the terms of the Order.
b.
EN 85-70, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $50,000 was issued October 22, 1985 to VermontNuclearPowerCorporation(VermontYankee). This action is based on a radiological incident in which a Chemistry-Health Physics technician received an unplanned radiation exposure of approximately 1.3 rem to the whole body while performing a survey where the radia-l tion levels were 1000 R/hr.
c.
EN 85-72, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $50,000 was issued October 21, 1985 to Boston Edison Company (Pilgrim). This action is based on multiple examples of openings in vital area barriers.
d.
EN 85-73, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $8,000 was issued on October 23, 1985 to Pathfinder Mines Corporation (Allentown, PA). This action is based on several violations resulting from the unauthorized construction of three uranium heap leach piles. One of the violations involves the failure to comply with EPA standards for uranium mill tailings.
i Under the Atomic Energy Act, the NRC has the authority to enforce these standards.
2.
The following IE Preliminary Notifications were issued during the past week:
a.
PNS-I-85-14, Combustion Engineering, Inc. (Windsor, CT), Inymtory Difference in Excess of Limit of Error.
OCT 2 51985 l
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i b.
PN0-I-85-81, Beth Israel Hospital (New York, NY), Lost Cesium-137 Source.
c.
PN0-I-85-82, Niagara Mohawk Power Corporation (Nine Mile Point Unit 2), Electrical Breaker Explosion.
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d.
PNO-II-85-96, Duke Power Cnmpany (Catawba Unit 1), Shutdown in Excess of 48 Hours.
i e.
PNO-II-85-97, Florida Power and Light Company (Turkey Point Unit 3),
Shutdown in Excess of 48 Hours.
f.
PN0-II-85-98, Tennessee Valley Authority (Watts Bar Units 1 & 2),
Bomb Threat.
g.
PNO-II-85-99, Georgia Power Company (Vogtle Units 1 & 2), Bomb Threat Against Individual Worker, h.
PNO-II-85-100, Virginia Electric and Power Company (North Anna Unit 1), Loss of Cooling Water to Reactor Coolant Pump Motor.
1.
PNO-III-85-89(dtd 10/18/85), Consumers Power Company (Palisades),
Shutdown for RHR Valve Repair.
j.
PNO-III-85-91, Dairyland Power Cooperative (Lacrosse), Loss of Off-Site Power.
i k.
PNO-III-85-92, Dairyland Power Cooperative (Lacrosse), Shutdown Because of Higher Than Expected Neutron Flux During Startup.
1.
PNO-III-85-92A, Dairyland Power Cooperative (Lacrosse), Shutdown Because of Higher Than Expected Neutron Flux During Startup (Update).
3.
The following IE Information Notice was issued during the past week:
I i
a.
IE Information Notice 85-82, Diesel Generator Differential Protec-tion Relay Not Seismically Qualified, was issued October 18, 1985 to all nuclear power reactor facilities holding an operating license or a construction permit.
4.
Other Items a.
Edison Electric Institute Conference Director, IE was in Chicago, IL on October 22, 1985 to be the luncheon speaker at the Edison Electric Institute's Conference on Effective Drug and Alchol/ Fitness for Duty Policy Implementation.
b.
Safety System Functional Inspection (1) Director, Division of Inspection Programs (DI) and representa-tives of Operating Reactor Programs Branch, DI were in Region II October 23, 1985 to meet with representatives of Florida Power and Light Comapny regarding the recent safety system functional i
inspection conducted at Turkey Point.
ENCLOSURE D l
i
(2) An inspecticn of selected safety systems at the Pilgrim plant commenced on October 22, 1985. The inspection effort is expected to conclude on November 22, 1985. The inspection will be similar to the recently completed safety system functional inspection at Turkey Point, and like the Turkey Point inspection, will be conducted by members of the Performance Appraisal Section, Operating Reactors Program Branch, DI, the Region, NRR, and NRC contractors.
c.
Watts Bar Employee Response Team Inspection Deputy Director and representatives of the Division of Inspection Programs continued the Employee Response Team Inspection at Watts Bar this week.
Representatives of NRR and the Region also partici-pated.
d.
Construction Appraisal Team (CAT) Inspection 2
The Construction Appraisal Team (CAT) inspection began this week at the South Texas Nuclear Plant. The inspection is scheduled for October 21 through November 1, and November 11 through 22, 1985.
e.
Vendor Program Activities (1) The Vendor Program Branch, Division of Quality Assurance, Vendor, and Technical Training Programs (DQAVT), conducted the following inspections this week:
(a) Virginia Electric Power Company, Surry Nuclear Power Station - to review the vendor-utility information inter-face and facility modifications made in response to vendor information.
(b) Dietrich Standard Company - to review the Fort Calhoun outage inspection requirements imposed on component cooling water flow elements.
(c) Cooper Energy Service, Cooper-Bessemer Diesel Generator - to review vendor activities related to faulty RPM indicators l
caused by installation of an alarm circuit component that is incompatiable with the engine control circuitry, i
(2) The Chief. Vendor Program Branch, DQAVT, was at TVA this week to meet with TVA representatives and discuss 50.54(f) responses.
f.
Emergency Preparedness (1) A representative of the Emergency Preparedness Branch, Division of Emergency Preparedness and Engineering Response (DEPFR) assisted Region III in observing an exercise at Robisor this week.
ENCLOSURE D OCT 2 51985 l
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4 (2) Representatives of the Emergency Preparedness Branch, DEPER pro-vided a briefing to the Committee to Review Generic Requirements i
(CRGR) on Offsite Emergency Medical Services this week.
(3) Representatives of the Emergency Preparedness Branch, CEPER and a representative of the Operating Reactor Programs Branch, Division of Inspection, completed an emergency preparedness assess-i ment of Region V in connection with the Trojan emergency pre-
)
paredness exercise this week.
I g.
Relocation Tabletop Exercise (RTE)
I On October 21, 1985, a Relocation Tabletop Exercise (RTE) working group session was held in Philadelphia, PA to finalize planning for the December exercise.
Participants included members from the Incident Response Branch, DEPER, FEMA and their contractor, EPA and D0E.
i h.
Incident Response J
(1) On October 22, 1985, representatives of the Incident Response Branch, DEPER, participated, in a limited manner, in an exercise with Region III and Kewaunee.
(2) Da October 23, 1985, a representative of the Incident Response Branch, DEPER, attended a briefing session prior to the start of the REX 86 ALPHA, a joint military / civilian preparedness exercise involving essentially all federal agencies to some extent. NRC's participation was minor.
ll 1.
Quality Assurance I
(1) Representatives of the Quality Assurance Branch, DQAVT conducted an inspection of the corrective actions undertaken by the Hope Creek project as a result of IDVP findings at the Bechtel offices l
in San Francisco October 22-25, 1985.
(2) Representatives of the Quality Assurance Branch, DQAVT conducted an inspection of the Comanche Peak project Quality Assurance l
I l
Program at Region IV offices and the site October 21-25, 1985.
i j.
Enforcement Conference j
l Representative of the Enforcement Staff was in Region II this week l
for an enforcement conference on North Anna and Surry.
ENCLOSURE D OCT 2 51985
k.
Security Representative of the Operating Reactor Program Branch, DI, was invited by NAVSEASYSCOM to attend a meeting at the Capitol building October 23, 1985 to provide initial input regarding revisti g MIL-STD-MIL-P-43607 entitled, "High Security Padlock, L:.
Jperated."
The representative also assessed a new security padloce for appli-cability to the nuclear industry. Representatives from DNA and the Department of Army also attended.
1.
EPRI NDE Center Representative of Engineering and Generic Communications Branch, Division of Emergency Preparedness and Engineering Response was at the EPRI NDE Center, Charlotte, NC this week to monitor qualification tests of SWRI and Combustion Engineering Automated UT System.
ENCLOSURE D OCT 2 51935
OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending October 25, 1985 Semiscale A sumary of all small-break loss-of-coolant accident (LOCA) experiments performed in Semiscale from 1979 through 1984 has been issued as NUREG/CR-4393. Three different types of small breaks have been studied, i.e., pipe breaks, steam generator tube ruptbre (SGTR), and stuck-open pressurizer power operated relief valve. Other experimental variables evaluated in the report are break size, break location, core by(pass flow, primary coolant pump operation, emergency core cooling system ECCS) operation and design, compounding failures, and operator recovery procedures. The purpose of the report is to consolidate the knowledge gained from this extensive series of tests for use in code development and code assessment and to increase staff understanding when dealing with small-break LOCA safety and regulatory issues.
Model Boiler-2 (MB-2) Program Management Group Meeting (PMG)
The MB-2, a steam generator test program, operated jointly by Westinghouse, EPRI, and NRC, is being conducted to study heat transfer during small breaks, tube rupture events, and other system transients.
The MB-2 data is used to validate steam generator models in NRC's licensing safety 4
analysis codes TRAC and RELAP.
The PMG met in Knutspor, United Kingdom (U.K.) on October 1-2, 1985, to discuss program schedules and costs and to review the final Phase-I and Phase-II results. Agreement was reached on scope and preparation of the final report. The final draft of the Phase-II report is scheduled to be submitted to the PMG for comments by January 15, 1986. The schedule for the Phase-I report will be finalized by next week.
I 1
The highlights of the technical presentation were that for steam line break, considerable carryover (20 percent) could take place. This has a mitigating effect on external shock; the exact amount, however, would have to be determined by a systea code such as RELAP.
For SGTR, the results show that carryover is very small (generally less than 0.01 percent), even when the primary separators are flooded.
It appears that the carryover is extremely sensitive to changes in water level. Thus, each cycling of the i
I relief valve results in very small, but finite, bursts of primsry liquid into the steam line. Calculations must be performed to determine whether the integrated amount of liquid carryover is significent, if the valve cycles at high frequencies during recovery from SGTR.
OCT 2 51985 ENCLOSURE E
~ _ - _ _. _ - _ _ _ -
m
-2 Effect of Radiation on Fission Product Chemistry Sandia National Laboratory has recently completed a scoping study on the effect of radiation on high temperature fission product chemistry. The study was conducted to determine the possible destabilizing effect of radiation on fission product chemical fonns. Experiments were conducted at approximately 1000C in a stainless steel pipe, part gf which was exposed to a relatively 6
small radiation field (130,000 curie Co source). Cs1 or AgI vapors were passed through the pipe along with steam. The results indicated a nearly complete dissociation of Cs! and Agl. Csl was found to be retained in the stainless steel apparatus while iodine travelled downstream and was collected in the condensate tank. Further analysis of the experimental findings is underway.
Implications of this effect on severe accident source term is uncertain at present since the chemical form of iodine and its reactive properties under these conditions have not been determined. However, follow-on work is planned and will be defined when commenu are received from the on-going peer review.
OCT 2 51985 ENCLOSURE E
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l ITEMS 0F INTEREST 0FFICE OF INTERNATIONAL PROGRAMS
{
WEEK ENDING OCTOBER 25, 1985 International Meetings The following in L national meeting notices supplement those previously i
announced:
November 13-15, 1985, Toronto, Canada - IAEA Consultants Meeting on Application of Basic Safety Standard Dose Limitation System to Operational Radiation Protection I
December 9-11, 1985, Vienna, Austria - IAEA Advisory Group Meeting on j
Planning a Prograrvne on New Concepts of Light Water Reactors j
January 13-17, 1986, Vienna, Austria - IAEA INTOR Specialists' Meeting on Tokamak Concept Innovations January 28-30, 1986, Budapest, Hungary - IAEA Specialists Meeting on Load and Time Dependent Material Performance, other than Irradiation Effects April 15-1/, 1986, Tokyo, Japan - Second International lopical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations September 1-5, 1986, Vienna, Austria - IAEA International Symposium on Radiotherapy in Developing Countries - Present Status and Future Trends November 10-14, 1986 Vienna, Austria - IAEA International Symposium on Nuclear Material Safeguards.
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00T 2 51985 ENCLOSURE G l
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OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDIl4G OCTOBER 25, 1985 Training Course for State Personnel A one-week course in well logging for State personnel will be presented in Houston, Texas, the week of riovember 4-8, 1985.
l OCT 2 51985 EflCLOSURE H
0FFICE OF RESOURCE MANAGEMENT Items Of Interest Week Ending October 25, 1985 Change in Divisor for Calculation of Employees' Pay Effective with salaries to be paid on November 5, 1985, the agency's payroll system has been modified to compute the hourly rates of pay for annual-salary employees by dividing their annual rate of pay by 2080 hours0.0241 days <br />0.578 hours <br />0.00344 weeks <br />7.9144e-4 months <br /> rather than 2087 hours0.0242 days <br />0.58 hours <br />0.00345 weeks <br />7.941035e-4 months <br />. This will result in a slight increase in pay to each employee.
Public Law 97-253, the Omnibus Budget Reconciliation Act of 1982, had estab-lished the requirement for the 2087 divisor, with an effective expiration date of October 12, 1985..The Congress has yet to extend the requirement for the 2087 divisor.
Bulletin 0904-1, " Policy and Procedures for Acquiring Microcomputer Equipment, j
Software, and Softwar. Services" On October 15, 1985, Bulletin 0904-1, " Policy and Procedures for Acquiring Microcomputer Equipment, Software, and Support Services" was implemented.
This bulletin provides for the timely delivery of microcomputer equipment, software, and support services in order to take advantage of the potential benefits while maintaining controls necessary to promote efficient, cost effective use of the technology.
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i ENCLOSURE I i
1 OCT 2 51995
(
REGION III STATUSREPOPJ DAVIS-BESSE LOSS OF FEEDWATER EVENT OCTOBER 25, 1985 Plant Status h
The plant remains in cold shutdown. The circulating water canal is drained.
Decay hcat removal loop No. 1 is drained for maintenance. Emergency Diesel Generator No.1 is inoperable due to an inoperable ventilation damper. The diesel firewater pump is inoperable due to a coolant problem and the jockey firewater pump (non-TS) is inoperable due to a damaged motor.
A.
EQUIPMENT STATUS (F0LLOWS TABLE 5.1 IN NUREG 1154)
ITEM TROUBLE SHOOTING / ROOT CAUSE DETERMINATION ACTIVITIES RIII ACTIONS
- 1. Main Feedwater Root cause determined to be
- Complete, l
Turbine component failure in speed control Inspection circuit. Revised report issued Report 85025.**
08/30/85 4
- 2. Closure of Root cause determined to be circuit
- Complete, j
MSIVs was overly sensitive to momentary IR 85025.**
i system perturbation.
Revised report issued 09/07/85.
t
- 3. Steam Safeties Defective electronic module in ICS
- Complete, i
Atmos. Vents likely cause of problem with IR 85025.**
l atmosphere vent valves. Revised i
report issued 10/03/85. MSSV test results being evaluated.
{
- 4. Aux. Feedwater Root cause was condensation in long Complete, see Turbine.
steam inlet lines. Revised report IR 85022 and l
issued 09/16/85.
IR 85030.
i
- 5. AFW Containment Root causes were incorrect torque Complete, see Isolation Valves switch bypass swftch settings and IR 85022 and inadequate test and maintenance IR 85030.
procedures. Revised report issued l
08/29/85.
l
- 6. Steam Supply Root causes were incorrect torque Complete, see Valve to AFPT switch bypass switch settings and IR 85022 and No. 1 inadequate test and maintenance IR 85030, procedures. Revised report issued 09/09/85.
ENCLOSURE L DCT 2 51985 l
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TROUBLE SHOOTING / ROOT CAUSE ITEM DETERMINATION ACTIVITIES RIII ACTIONS Ij'
- 7. Source Range NI Root cause of NI-2 failure was a
- Complete, i
defective containment cable IR 85025.
i penetration module. Revised report for NI-2 issued 9/19/85. Root cause of NI-I failure was a bad connection between detector and cable.
Revised report on NI-1 issued 09/16/85.
i
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- 8. PORV Root cause not determined. Report
- Complete, issued 08/23/85.
IER 85025.**
i
- 9. S/U Feedwater The valve func*.ioned correctly Complete.
Valve during the June 9 e' vent. Revised IER 85025.**
i report issued 08/29/85.
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- 10. Recovery of Root causes were inadequate training Complete, see AFP Turbine and procedures. Revised report IER 85030, issued 08/30/85.
- 11. AFP No. 1 Root cause determined to be excessive Complete, Suction Transfer pressure drop across common strainer IER 85025.**
caused by transient flow variations.
Revised report issued 09/17/85.
i 1
- 12. Turbine Turning j
Gear *
- 13. Control Room HVAC*
I
- 14. Turbine Bypass Root cause was water hammer.
Complete, see Valve Revised report issued 08/29/85.
IER 85022.
l
- Status not maintained on this item since this type failure occurred previously and do not appear to be unique to this event.
- Inspection Report 85025 in draft will be issued in approximately 2 weeks.
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ENCLOSURE L OCT 2 51985 2
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B.[RegionIIISTAFFACTIONSASASSIGNEDBYW.DIRCKSMEMO0FAUGUST9,1985
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Item: Adequacy of the licensee's management and maintenance activities ACTION STATUS /COPMENTS (b) Evaluate and take action on the Region III is observing maintenance activities and evaluating j
licensee's response to findings LER's; DVR's and other items as they relate to the control of concerning management practices maintenance. A maintenance survey team inspection conducted (e.g., control of maintenance on September 16-20, 1985 confinned previous concerns identified programs and post-trip reviews).
by Region III. A followup team inspection is planned for early 1986. DRP in 90njunction will DRS will assess management practices during inspection.
6.
Item: Reliability of the AFW containment isolation valves and other safety-related valves ACTION STATUS /COPMENTS (a) Monitor the licensee's trouble-Trouble s coting activities related to containment isolation shooting activities valves AF599 and AF608 are complete. Regicn III specialist are evaluating and monitoring MOVATS testing on other safety-related motor operated valves. About 50% of 166 valves have been completed.
l 1
(e) Detennine that the procedures for Limitorque operators for valves AF599 and AF608 have been adjustments of the AFW isolation adjusted and the valves have been tested under dp conditions.
- l valves such as torque switch bypass Confirmatory testing will be perfonned during startup.
switches are clear and proper, and that associated training programs are 1
adequate. Confina that adjustment settings are consistent with plant j
procedures.
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Item: Adequacy of emergency notifications ACTION 3 STATUS /COPMENTS m
IR (a) Verify the adequacy of the licensee's Investigation of the adequacy of the licensee's procedures procedures and training for the report-and training for the reporting of events to the NRC ing of events to the NRC Operations Operations Center has been completed. One violation of NRC Center.
requirements was found.
Inspection results are documented in Inspection Reports 8023 and 85034.
8.
Item: Reliability of AFW pump turbines ACTION STATUS /C0tWENTS (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 testing 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.
basis events.
(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.
9.
Item: Reliability of the PORV ACTION STATUS /COPMENTS (a) Monitor the licensee's trouble-Troubleshooting activities have been completed. Confirmatory shooting activities testing will be conducted at operating temperature and pressure. Additional research test data has not been provided mg to the licensee.
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Item:
Resolution of equipment deficiencies ACTION STATUS / COMMENTS m3 (a) Monitor the licensee's trouble-See Table A.
Table A will be eliminated in subsequent status shooting activities reports because all the Region III activities relative to troubleshooting / root cause activities have been completed.
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Other Activities The new electric motor driven startup feedwater pump (SUFP) is in place.
Installation of pipe and valves is about 80% complete. Conduit installation, cable pulling and wire termination is in progress. The old SUFP has been electrically disconnected and it's discharge piping is no longer connected to the feedwater system.
Evaluations and inspections of safety system piping supports are continuing.
Nonconformance Reports (NCRs) have been written against 1301 of 1433 pipe supports inspected so far. The licensee's engineering department has received 1170 NCRs for evaluation.
Rework is required on 74 of the 560 supports that have been evaluated. There are 16 licensee inspection teams on this project.
M0 VATS testing continues on the 166 safety-related motor-operated valves on site. Eighty one valves have been tested, a few of these will require retesting.
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OCT 2 51985 6
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ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING OCTOBER 25, 1985 A.
STAFF REQUIREMENTS - DISCUSSION OF PLANT ISSUES WITH REGIONAL ADMINISTRATORS, 2:00 P.M., TUESDAY, OCTOBER 1, 1985, COMMISSIONERS' CONFERENCLcROOM, D.C.
OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to W. Dircks dated 10/21/85 The Commission met with staff and regional administrators from Regions IV and V to discuss plant safety issues and other items.
Region IV was requested to provide data to the Commission on the number of active uranium recovery mill licenses.
(Subsequently, by memorandum to the EDO dated October 4,
- 1985, Region IV provided information on the status of uranium mills licensed by NRC, as well as those in agreement states.)
Region IV was also requested to provide to the Commission details on the Region's oversight responsibility for inactive mills that are currently licensed.
(Region IV)
(SECY Suspense:
11/8/85)
Region IV was further requested to provide the Commission with an information paper on the Brown and Root litigation settlement that highlights the plan of the Region with respect to auditing the review of documents being performed by the parties.
The paper should also include an estimate of the sample size, factors that would lead the Region to conclude that the review process is working well and a description of the monitoring role the Region would have after completion of its audit.
(Region IV)
(SECY Suspense:
11/8/85)
The Commission asked the EDO to examine the management scheme employed at River Bend, in which a work control group of knowledgeable operations, maintenance, construction and engi-neering personnel is formed to examine and analyze a work control activity before it is implemented, in order to deter-mine the feasibility of applying this management technique to other operating plants.
(NRR)
(SECY Suspense:
11/8/85)
The Commission requested that the staff put together a paper that would outline an expanded approach to regulating operating plants.
(NRR)
(SECY Suspense:
11/8/85)
Chairman Palladino suggested that at the agenda planning session on October 3, 1985, that the Commission consider setting a meeting date with INPO or INPO and staff to discuss plant maintenance and training programs.
(Subsequently, at agenda planning on October 3, a meeting was tentatively scheduled for mid-December.)
ENCLOSURE 0 OCT 2 51985
A.
CONTINUED The staff, in response to a question by Commissione8 Asselstine on the Mexican earthquake, advised the Commission that staff personnel were traveling to Mexico to examine the effects of the earthquake and would provide an analysis to the Commission within six months.
(NRR)
(SECY Suspense:
4/30/86)
B.
STAFF REQUIREMENTS - PERIODIC MEETING WITH ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS), 10:30 A.M., OCTOBER 10, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to W. Dircks, H. E. Plaine and R. Fraley dated 10/21/85 The Commission met with members of the Advisory Committee on Reactors Safeguards (ACRS) to discuss the standards proposed by the Environmental Protection Agency (EPA) for the disposal of high-level radioactive waste.
The Commission requested that the ACRS provide expanded written comments on the EPA proposed standards to the Commission as soon as possible.
(ACRS)
The Commission decided to schedule a meeting with the staff to discuss the technical aspects of the proposed EPA standards as well as cptions the Commission can exercise prior to the i
promulgation of the standards, should the Commission disagree with EPA's approach.
Chairman Palladino requested that members i
of the ACRS be present at such meeting and instructed OGC to provide an analysis of the options available to the Commission.
Chairman Palladino further instructed the staff to respond to t
the expanded ACRS comments.
(Subsequently, at the agenda planning session of October 10, 1985, a meeting was scheduled for October 21, 1985, to discuss with staff the proposed EPA standards.)
- Commissioner Asselstine was not present.
l OCT 2 51985 ENCLOSURE 0
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to IS NRR MEETING NOTICES *
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OCTOBER 25, 1985 DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 10/28/85 50-213/245 Northeast Util.
To discuss and review plant Northeast Utilities F. Akstulewicz 1:00 pm Berlin, CT modifications made at Millstone 1 10/29/85 Millstone 1 Site and Haddam Neck in response to 9:00 am Waterford, CT IE Bulletin on Masonry Wall Design 10/29/85 Haddam Neck i
1:00 pm East Hampton, CT 10/30/85 Northeast Util.
9:00 am 10/29/85 50-259/260/ MNBB-6507 To discuss TVA's program to TVA R. Clark 1:00 pm 296 Bethesda environmentally qualify cable at Browns Ferry 10/29/85 50-267 MNBB-6507 To discuss schedule extension Public Serv. Co.
K. Heitner 9:00 am Bethesda to the Equipment Qualification of Colorado Rule for Ft. St. Vrain 10/30-31/85 50-382 87th Floor Discuss confirmatory analyses Louisiana Power &
J. Wilson 8:30 am 2 Word Trade Ctr for common foundation basemat Light Co.
New York, NY at Waterford 3 BNL EBASCO 10/31/85 50-302 P-422 To discuss NRC concerns re-Florida Power Corp.
H. Silver 1:00 pm Bethesda garding review of GOC-4 exemption request for RCP restraints O Capies 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
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NRR MEETING NOTICES *
!N DOCKET APPLICANT /
DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 11/4-5/85 50-275/323 P-110 Discuss Inservice Testing Pacific Gas & Elec H. Schierling 9:00 am Bethesda (Diablo Canyon) 11/6/85 P-422 Technical Specification NRC Personnel R. Emch 9:00 am Bethesda Improvement Project 11/6-7/85 50-275/323 AR-5033 Discuss status of licensee's pacific Gas & Elec.
H. Schierling 9:00 am Bethesda Detailed Control Room Design Review 11/7/85 50-440 Perry Site To determine readiness for Cleveland Elec. Ill.
J. Stefano 9:00 am Perry, Ohio a low power operating Co.
license Copics 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.
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ro en hk NMSS MEETING NOTICES FOR WEEK ENDING: 10/25 Division of Fuel Cycle and Material Safety ATTENDEES /
DOCKET DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 10/31/85 Willste Pre-application meeting for Reps of G'NS MacDonald Room 106 Castor V-21.
Reps of GNSI 9:00-12:00 N C. MacDonald (FC)
R. Chappell (FC)
R. Odegaarden (FC) 11/4-15/85 San To attend ANS, Conduct Nuclear G. Bidinger (FC) -
Bidinger Francisco, Criticality Safety Meeting Visit CA and LBNL
- Richland, WA Discuss Dry UF6 Process and accompany inspector at Exxon.
DIVISION OF WASTE MANAGEMENT None DIVISION OF SAFEGUARDS None O
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RES MEETING NOTICES October 25, 1985 DOCKET ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 11/6-7/85 NL To review draf t report NUREG/CP,-4349, Schunnan, INEL Au 9:00-4:00 Methods for Evaluating Alternative Bongarra, NRR Techniques &nd Formats for Presenting Goodman, NRR t
3 Procedures in NPPs i
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c.n RII MEETING NOTICE DOCKET ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 11/01/85 Homestead, FL Site Familiarization Comissioner Bernthal, Walker of Turkey Point Facility his assistant, and R.
Walker i
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REGION III MEETING NOTICES WEEK ENDING:
October 25, 1985 00CKET ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 11/13/85 50-315 Glen Ellyn, IL Enforcement Conf.
Aner.Elec. Power J.G. Keppler 10 a.m 50-316 D.C. Cook J.G. Keppler & staff 1
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