ML20141G260

Weekly Info Rept for Wk Ending 860411

ML20141G260
Person / Time
Issue date:	04/17/1986
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
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WIR-860411, NUDOCS 8604230336
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April 17,1986 For: The Commissioners From: T. A. Rehm, Assistant for Operations, Office of the ED0

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING APRIL 11, 1986 A sumary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.

Contents Enclosure Administration A Nuclear Reactor Regulation B Nuclear Material Safety and Safeguards C Inspection and Enforcement D Nuclear Regulatory 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*

Regi'nal Offices L*

CRGR Moi.%1y Reports M*

Executive D* rector 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.

b A. Rehm Assistant for Operations OCfice of the Executive Director

" for Operations

Contact:

T. A. Rehm, ED0 492-7781 8604230336 860417 PDR COMMS NRCC WEEKLYINFOREPT PDR

HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK UDING APRIL 11, 1986 Fermi-2 The staff was informed by the licensee on the afternoon of April 3rd that there may be a new safety issue at Fermi-2. Specifically, there are 188 embedment plates for supporting safety-related components (e.g., cable trays) whose structural adequacy is in doubt.

The problem first arose in August 1985 when there was a failure during a load test of an embedment supporting a 51-inch bellows in the turbine building. The failure was due to excessive porosity in the weld joining the embedded rod to the plate. About a month ago, the licensee determined that there were 251 more embedments of this type of which 188 are used for a safety-related systems. The licensee has not formally proposed a resolution for this matter because it is still developing its investigative approach. This matter has not been declared a safety issue since no definitive evidence has yet been obtained to indicate that the safety-related embedments have porous welds. The problem is compounded by the fact that there is insufficient room to load test all the potentially affected embedments. Additionally, safety-related components might be damaged in the event of an embedment failure under test load. The licensee believes that this issue will pace its decision on the restart of the Fermi-2 facility.

Wolf Creek .

While preparing to return to operation from a reactor trip caused by operator error related to surveillance in the switch yard, KG&E has detected excessive leakage of the spray bypass valve and has decided to place the reactor in cold shutdown to repair the valve.

While shutdown KG&E will also complete those local leak rate tests, snubber surveillances, and instrument surveillances for which they had requested technical specification extensions and exemptions until the first refueling outage in October.

The outage is currently estimated to last for 15 days.

San Onofre Unit 1

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The San Onofre 1 Restart Report, dated April 8, 1986, has been received by the NRC staff. This comprehensive document (over 400 pages) is intended to address all staff concerns regarding the November 21, 1985 water hamer event. The report has been distributed to Region V, NRR, and IE reviewers along with review plans and schedules which are consistent with the licensee's schedule for restart in early June 1986.

Category I Surface Transportation Although Tri-State Motor Transit Company recently announced that it was withdrawing from the transport of Category I quantities of SSNM, it has agreed to make one more shipment this spring, according to Transnuclear, Inc., the licensee for such shipment. This resolves the immediate problem of assuring the movement of SSNM under export licenses. For the longer range, Transnuclear, Inc., has written to DOE requesting assistance. NRC has also  !

written DOE to offer assistance in resolving this problem.

APR 11 33S I

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! g 0FFICE OF ADMINISTRATION Week Ending April 11, 1986 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1985 181 15 Received, 1986 262 50 Granted 173 14 Denied 50 6 Pending 220 45 ACTIONS THIS WEEK Received Andrew Bedo, Requests a list of licensees in RII engaged in Pipe Nuclear Sources & Inspection, Well Logging, and Radiography operations.

Services, Inc.

(86-248)

Jim Pedro, Requests a copy of Division of Operating Reactor (DOR)

NUS Corporation memorandum #5.

(86-249)

(NRCemployee) Requests records regarding her EE0 matter and other (86-250) specified records.

Susan Bevill, Requests records regarding any complaints, etc., about Balch & Bingham the Farley nuclear power plant or Alabama Power (86-251) Company made by J.L. Smith and NRC responses thereto, and reports regarding the Health Physics inspection of the Farley plant during the week of March 24, 1986.

(NRC employee) Requests records rec.irdin3 an OIA investigation.

(86-252)

Gilbert M. Gaul, Requests for years 1984 and 1985, three categories of The Philadelphia lists of hospitals cited and fined for violations of Inquirer radiation-protection rules and copies of all citations (86-253) and other records which describe the violations.

CONTACT: Donnie H. Grimsley 492-7211 4 ENCLOSURE A l APR 111986

2 Received, Cont'd James T. Lawless, Requests a copy of enclosure 1 to the November 4.1985, The Plain Dealer letter from NRC to the utility on Perry, which was (86-254) denied in NRC's December 26, 1985, response to F01A-85-775 and any additional records since November 18, 1985, concerning allegations about improper work done by Metalweld, Inc., at the Perry nuclear power plant.

Jim Pedro, Requests records reviewed by ACRS related to the statement NUS Corporation in the January 14, 1986, ACRS letter regarding the FDA (86-255) for GESSAR II, "that the design of the SCRAM discharge system has basic deficiencies."

Jim Pedro, Requests a copy of the GESSAR 11 PRA.

NUS Corporation (86-256)

Jim Pedro, Requests a copy of the BWR Owners Group Report issued in NUS Corporation January 1985 regarding USI-45, " Shutdown DHR (86-257) Requirements."

Christopher Govekar Requests a copy of the study released in 1984 on the (86-258) subject of Nuclear Winter.

Tanya K. Bodzin, Requests a copy of the winning proposal submitted with BEMW, Inc., regard to Purchase Order No. DR-86-0653 for NRC Counseling and secretarial training.

Training Associates (86-259)

Jennifer L. Graham, Requests records in the NRC on seven named individuals.

Lewis Kappes Fuller & Eads (86-260)

(NRCemployee) Requests copies of records concerning himself.

(86-261)

Stephanie Murphy, Requests four categories of records regarding NRC Nuclear Information contacts with licensees and Automatic Sprinkler and Resource Corporation of America about operability of 6-inch Service deluge t.nd pre-action fire protection water control (86-262) valves. ,

Granted Steven C. Sholly, In response to a request for summaries and evaluations 5 MHB Technical of Licensee Event Reports from fuel loading to declaration Associates of commercial operation for seven specified nuclear power (85-668) plants, made available 33 records. Informed the requester that additional records subject to this request are already available at the PDR.

ENCLOSURE A APR 1126

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• Received, Cont'd James Phalen, In response to a request for (1) records concerning College of the missing nuclear fuel and the location of these Holy Cross disappearances, (2) laws governing the sale and (86-121) transport of nuclear fuel, (3) list of companies licensed to process or transport nuclear fuel, (4) a description of the type of technological material concerning atomic weapons that has been declassified by the federal government and is available to the general public, and (5) a copy of the Los Alamos Primer, made available three records. Informed the requester that four additional records subject to this request are already available at the PDR. Informed the requester that the NRC does not license nuclear material transport companies. Suggested that he contact the D0D for records on atomic weapons and contact the DOE for a copy of the Los Alamos Primer.

Joseph W. Cuthbert, In response to a request for lists of Phase I and II Advanced Technology SBIR awards for 1985, made available copies of the

. Center of South- requested lists.

Eastern Pennsylvania (86-165)

B.S. Dunn, In re:ponse to a request for an itemized listing of fees General Electric charged pursuant to 10 CFR 170.31 and 170.32 for six Company specified 70 dockets, made available six records.

(86-171)

Patty Day, In response to a request for a copy of an April 30, 1985, NUS Corporation memo for Harold Denton from Hugh Thompson re: Policy (86-174) Issue: Extending the Operating Life of Nuclear Power Plants, made available a copy of the requested record.

Joel Levin, In response to a request, on behalf of his client, Nurenberg, Plevin, for records relating to any radiation exposure of Heller & McCarthy her deceased husband while employed at the Pilgrim and Co., L.P.A. Perry nuclear power plants beginning in 1983, made (86-196) available the requested information.

Billie P. Garde, In response to a request for records regarding potential Government sabotage at the Comanche Peak nuclear power plant, made Accountability available three records.

Project (86-208)

James E. Tierney, In response to a request for six categories of records State of Maine related to the siting of high-level radioactive waste 3

(86-221) repositories within the State of Maine, informed the requester that the NRC has no records subject to this request.

EflCLOSURE A APR 11150

4 Granted, Cont'd George R. Holeman, In response to a request for records to and from the NRC Yale University and a former Yale employee, and/or her attorneys, between (86-222) May, 1985, and March 20, 1985, made available two records.

Dennis Melamed In response to a request for a copy of NRC's Information (86-231) Collection Budget for FY 1985 listing by line item the reporting requirements on the private sector and state and local governments by the NRC, made available three records.

Denied Bobby G. Hardwick, In response to a request, on behalf of his client, for McClure, Brannan records concerning his client's exposure to radiation at

& Hardwick the Clinton nuclear power plant, made available 26 (85-763) records. Denied one record in its entirety and portions of two records, 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 and portions of 18 records, release of which would

< constitute a clearly unwarranted invasion of personal privacy. Denied one record in its entirety, release of which would tend to inhibit the frank and candid exchange of information in future deliberations and would interfere with an enforcement proceeding.

Elizabeth A. Mahoney, In response to a request for records concerning inspections, District of letters and citations with regard to the Washington Columbia Nurses' Hospital Center and Capitol Hill Hospital in Washington, Association DC, made available 33 records. Denied one record in its (86-104) entirety containing advice, opinions, and recommendations.

Denied two records in their entirety containing information from a confidential source. Denied portions of three records, release of which would constitute a clearly unwarranted invasion of personal privacy.

Marvin Resnikoff, In response to a request for records related to the Sierra Club disposition of project-generated waste at the DOE Radioactive Waste West Valley Demonstration Project, made available two Campaign records. Denied nine records in their entirety containing (86-152) the advice, opinions, and recomendations of the staff on DOE's draft Environmental Assessment for Disposal of Project Low-Level Waste.

David G. Swanson, In response to a request for a copy of the nonproprietary Applied Science version of the proposal in response to RFP RS-NRR-86-055, Associates, Inc. entitled, " Assessment and Application of Thermal Hydraulic (86-160) Phenomena for Severe Accident Decisions," and a copy of the evaluation by the NRC SEP of the winning proposal, made available one record. 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.

ENCLOSURE A APit 11 "

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5 Denied, Cont'd Albert V. Carr. In response to an APPEAL TO THE ED0 for the release of Duke Power 34 denied records regarding Enforcement Action No. EA-Company 84-93 concerning the Catawba nuclear power plant, (86-A-5-85-584) made available portions of three records. Informed the requester that one record on Appendix J is identical to a record on Appendix M and that one record is outside the scope of his request. Continued to deny the remaining records, release of which would adversely affect the agency's deliberative process.

Margaret L. Ryan, In response to an APPEAL TO THE COMMISSION for the release Inside NRC of the denied notation vote sheets during the first five (86-A-46-85-409) months of 1985, continued to deny these records in their entirety, release of which would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.

1 EllCLOSURE A APR 111986

WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING APRIL 11, 1986 RFP ISSUED RFP No.: RS-01E-86-154

Title:

" Continuity of Government Programs"

Description:

The objective of this project is to identify and select a contractor to provide logistical and administrative support for the maintenance and functioning of the NRC Continuity of Government (C0G) Program.

The contractor will assist in the development of the essential documents and guidance necessary to establish the revised NRC COG Program at both Headquarters and the Regional Offices; and provide support to the NRC for the implementation of the revised COG Program and training of NRC staff.

Period of Performance: Three years Sponsor: Office of Inspection & Enforcement Status: RFP issued on April 3, 1986. Proposals due May 2, 1986.

PROPOSAL UNDER EVALUATION RFP No.: RS-NMS-86-005

Title:

" Technical Assistance in Geophysical Methods for Site Characterization"

Description:

The contractor shall assist the NRC on a task order basis, assessing the adequacy of currently available surveying methods and data analysis

, techniques applicable to site screening and site characterization investigations.

Period of Performance: Three years Sponsor: Office of Nuclear Material Safety and Safeguards Status: RFP closed on April 10, 1986. Proposals forwarded to Source Evaluation Panel for review on April 11, 1986.

ADMINISTRATIVE MATTER As previously reported in the Weekly Information Report for the week ending

.l April 4, 1986, a protest was filed with the Contracting Officer by Hirt Telecom

, Company (Hirt) under Solicitation No. RS-ADM-86-254 for cable installation. Hirt

protested the NRC's decision to reject its bid as nonresponsive and requested that the bid be reconsidered for award. Based on a review of the protester's bid and other relevant facts, the Contracting Officer found that the bid was properly

, rejected as nonresponsive. By letter dated April 9, 1986, the protest was denied.

ENCLOSURE A APR 11 '.536

OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending April 11, 1986 Fermi-2 The staff was informed by the licensee on the afternoon of April 3rd that there may be a new safety issue at Fermi-2. Specifically, there are 188 embedment plates for supporting safety-related components (e.g., cable trays) whose structural adequacy is in doubt.

The problem first arose in August 1985 when there was a failure during a load test of an embedment supporting a 51-inch bellows in the turbine building. The failure was due to excessive porosity in the weld joining the embedded rod to the plate. About a month ago, the licensee determined that there were 251 more embedments of this type of which 188 are used for a safety-related systems. The licensee has not formally proposed a resolution for this matter because it is still developing its investigative approach. This matter has not been declared a safety issue since no definitive evidence has yet been obtained to indicate that the safety-related embedments have porous welds. The problem is compounded by the fact that there is insufficient room to load test all the potentially affected embedments. Additionally, safety-related components might be damaged in the event of an embedment failure under test load. The licensee believes that this issue will pace its decision on the restart of the Fermi-2 facility.

Peach Bottom Atomic Power Station, Units 2 and 3 On April 3, 1986, the NRC staff was presented with data from Peach Bottom by J. Klapproth of General Electric (GE) on their continuing surveillance program on control blades. These recently collected data indicate the cracking in the sheath to handle weld creviced region on the Peach Bottom blades is more extensive than reported earlier at other plants, e.g., Lacrosse. GE has informed all BWR owners of these findings by letter and by a SIL (Service Information Letter). GE believes that the greater amount of cracking at Peach Bottom was primarily due to differences in configuration of the welds (continuous vs. intermittent and the resulting increases in crevices) and differences in water chemistry. GE is planning to modify the existing shehth design to minimize crevice effects. GE is also planning to inspect additional control rod blades at Peach Bottom as well as Brunswick and Browns Ferry. The staff is following the generic implications of the above information since at least 16 plants have similarly designed control blades. GE will be presenting the additional Peach Bottom data as well as their surveillance recommendations to the staff in late April.

ENCLOSURE B pg

Monticello High Energy Line Break Analysis As part of an ongoing routine check of plant design, Northern States Power Company discovered that a feedwater line break in the pipe chase area adjacent to the Division 2 motor-control center in the turbine building was never formally analyzed and informed the staff on March 27, 1986. On April 4, the licensee informed the staff that further analysis has shown that a full quillotine break will over-pressurize the pipe chase room and the resulting jet impingement forces will damage two walls. The licensee has infonned the staff that damage

. to the Division 2 motor control center and Division 1 cables in the pipe chase will effect the plant's ECCS capability to function if needed.

The plant is at about 70% power and is in a coast down mode for cycle 12 refueling which is expected to start on April 30, 1986. The licensee has completed a fracture mechanic analysis for the feedwater system and concluded that based on dynamic analysis and reliance on

" leak before break" that a quillotine pipe break in this area is highly unlikely. The licensee will monitor this rocm for any leakage twice per shift and will shutdown the plant if any leakage is detected in that area.

i During the conference call on April 5,1986, the licensee informed the staff that a detailed safety evaluation and justification for operation to April 30, 1986 will be available for staff review by April 9, 1986.

Perry

A prehearing conference call was held on April 3, 1986 with the ASLAB during which time the schedule was established for the hearing. The object of the hearing will be to determine whether the concerns raised by the intervenor (Ohio Citizens for Responsible Energy or OCRE) should be admitted as a new contention for litigation. OCRE has alleged, as a result of the January 31, 1986, Ohio Earthquake, that the Perry plant's seismic design is inadequate, and that the plant is located on or near a " capable fault." The hearing will begin on Monday, May 12, 1986, at the Mentor City Council Chambers in Mentor, Ohio.

j As a separate matter, the staff has been advised by the Perry Plant Manager that Perry's fuel loading is behind schedule and is now

] projected to be completed by April 20, 1986. The delay is attributed

to CEI's "go-slow approach" and not due to any problems with fuel loading operations. As of Friday, April 4, 1986, approximately 200 fuel assemblies have been installed out of a total of 748 fuel assemblies. (CEI has the capability of loading 50 assemblies per day). Initial criticality is currently targeted for April 28, 1986.

1 EHCLOSURE B APR 111956

North Anna Power Station, Unit No. 1 and 2 A meeting was held on April 7, 1986, with the Virginia Electric and Power Company (the licensee), representatives of the Westinghouse Owners Group (WOG), and the NRC staff regarding Reactor Trip Breaker testing. The purpose of the meeting was to discuss the licensee's proposed maintenance program which would reduce the number of breaker cycles by 67.5% while continuing to satisfy WOG maintenance. The proposed program would reduce the amount of handling on the breaker, reduce the amount of wear on the breaker parts, and increase the effectiveness of lubrication for DB 50 Reactor Trip Switch Gear by reducing breaker testing. The licensee's proposed changes do not affect present or proposed Technical Specification Requirements. The licensee's proposed program will be provided in a supplemental response to Generic Letter 83-28 which will address proposed periodic maintenance and testing for 12-month intervals. For other Westinghouse plants, this matter will be handled on a generic basis with the WOG.

Wolf Creek While preparing to return to operation from a reactor trip caused by operator error related to surveillance in the switch yard, KG&E has detected excessive leakage of the spray bypass valve and has decided to place the reactor in cold shutdown to repair the valve.

While shutdown KG&E will also complete those local leak rate tests, snubber surveillances, and instrument surveillances for which they had requested technical specification extensions and exemptions until the first refueling outage in October.

The outage is currently estimated to last for 15 days.

San Onofre Unit 1 The San Onofre 1 Restart Report, dated April 8, 1986, has been received by the NRC staff. Thiscomprehensivedocument(over400pages)is intended to address all staff concerns regarding the November 21, 1985 water hammer event. The report has been distributed to Region V, NRR, and IE reviewers along with review plans and schedules which are consistent with the licensee's schedule for restart in early June 1986.

Callaway The first refueling outage at Callaway has been completed and the reactor is holding in mode 5 while cleaning bp primary coolant system chemistry. Entry into mode 2 is currently schaduled for April 12. If achieved this will be a 43 day refueling outage.

During the outage, Union Electric (UE) has examined the tubes in two steam generators. No tubes required plugging and only 15-20 tubes in ENCLOSURE B each generator exceeded the 20 mil reporting threshold, with no indications greater than 38 mils deep.

APR 111986

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UE has satisfied all License conditions related to return to operation from the first refueling outage. Amendment 15 to the Callaway license i

authorizing the use of Westinghouse oltimized fuel assemblies and the reload 1 analysis was issued on April 8, 1986.

Grand Gulf, Unit 1 The plant was manually scrammed from 60% of rated power on April 7, 1986, because one of the safety relief valves remained open for more than two minutes (stuck open relief valve). The low-low set points on six safety relief valves were being calibrated when one of the valves opened and remained open, as determined by a temperature increase at the discharge pipe and a decrease in the electrical power output by about ten percent (70 MW). In accordance with the Technical Specifications, the reactor was manually scramed when the valve failed to re-close within two minutes. Closure of the valve was achieved about 15 minutes after the reactor scram. An unusual event was declared and then terminated af ter 23 minutes.

The plant will remain shut down for about four days to replace a leaking recirculation pump seal. The cause of the opening of the relief valve and its failure to re-close are being investigated.

Oconee Unit 1 Oconee Unit 1 is presently in a refueling outage and Duke Power Company has been performing inservice inspection (ISI) on the unit. The ISI was done by using the ultrasonic testing (UT) method. Twenty-two indications have been found on the reactor vessel (specifically, the reactor vessel flange weld) and they have been classified by Duke as either acceptable or unacceptable by using the criteria in the ASME Code. Thirteen indications have been classified as unacceptable; the largest is estimated to be 6.4 inches long in the radial direction.

Duke had performed the Unit 1 10-year ISI in 1983 and no such indications were found.

Duke has compared these indications to the original radiographs taken after fabrication, and the indications did not show on the radiographs. A major consideration is whether the indications are resulting from differences in examination techniques used in previous and base line examinations or whether the indications are service related. The licensee has performed fracture mechanics analyses of the indications.

The staff met with Duke in Region II on April 8 and discussed the results of the inspection and analyses. The need for any additional inspection, corrective action and any generic implications are being considered by the staff.

Unit 1 is scheduled to start up April 24.

ENCLOSURE B The other 2 Oconee units continue to operate at 100% power.

APR 111986

NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT WEEK ENDING APRIL 11, 1986

1. DEFUELING

- As of April 13, 1986, a total of 42 defueling canisters have been loaded with fuel debris and t.ansferred to the canister storage racks in the fuel building. The total weight of debris transferred out of the reactor vessel is 47,500 lbs.

Fuel debris in the form of small loose rubble which is amenable to

" pick and place" defueling using a spade-bucket tool has been substantially depleted. The remaining loose rubble consists mainly of either fine debris, or pieces that would require some sizing operation before they can be placed into defueling canistr.rs. Both vacuum defueling of the fine debris and sizing operations (e.g.,

cutting, shredding or separating) would require good underwater visibility which is not available due to the biologic growth. The licensee has halted the defueling operation to implement a micro-organism treatment and control program.

- Preparations are in progress to begin a program designed to kill the biological contamination in the reactor coolant system (RCS). The program includes manual brushing and hydrolazing to remove the

adherent growth from the surfaces inside the reactor vessel, circulating the RCS water through a high pressure pump, and filtering the pump effluent through a diatomaceous earth filter to remove the dead organisms. Laboratory and pilot scale testing have demonstrated that the rapid pressurization and depressurization that occurs when the water passes through a high pressure positive displacement pump is effective in destroying most of the organisms and that the remaining biological debris is readily filterable. The entire operation is expected to take about one week.

2. PLANT STATUS

- The reactor remains in long term cold shutdown, vented to atmosphere. Core cooling is by ratural heat loss to ambient building atmosphere. The average of the incore thermocouple average is 79 F.

- The airborne radioactivity on the defueling platform is about 1.7 E-7 uCi/cc Tritium and 3.2 E-11 oCi/cc Cesium-137. The platform is mounted above the modified internals indexing fixture which is mounted on the reactor vessel fitnge. These provide water coverage of 151 feet over the core region. This water level is about 5 feet over the top of any debris canisters in the reactor vessel.

3. WASTE MANAGEMENT

- The Submerged Demineralizer System (SDS) is shutdown. SDS total processed to date is 3,885,859 gallons.

1 EPICOR II was in temporary shutdown this week. EPICOR II total processed to date is 2,854,371.

ENCLOSURE B APR 111993

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 (includes TMI-1 and TMI-2) to the river consisted of 14 daily composite  ;

samples taken from March 22 - 29, 1986. A gamma scan detected no reactor related activity above the lower limit detectability. Trace indications of Iodine-131 may be present but not in sufficient quantities to be quantified or clearly identified.

The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a seven day composited sample taken from March 22 - 29, 1986. A gamma scan detected no reactor related radioactivity.

The NRC outdoor airborne particulate sampler at the TMI site collected a sample between April 3 - 10, 1986. No reactor related radioactivity was detected. Analysis showed Iodine-131 and l Cesium-137 concentrations to be less than the lower limits of detectability.

5. AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Scabbling and painting of the floors in the neutralizer tar.k rooms were done this week.

Scabbling and painting of the floors in the mini-decay heat pump room area were done.

About 90% of the general area floor in the 281' elevation fuel handling building has been released for street clothing access.

6. RADI0 ACTIVE PATERIAL SHIPMENTS Laundry - Contaminated laundry was sent from TMI site to Royersford, PA on these dates:

March 4 - 92 drums and 2 boxes March 11 - 86 drums and 5 boxes March 18 - 78 drums and 5 boxes March 25 - 130 drums and 3 boxes March 31 - 107 drums and 4 boxes Samples - Unit 2 reactor building basement concrete core bore samples were sent to Scoville, ID for research analysis on March 14, 1986.

Waste - A combined unit shipment of 72 drums and 6 boxes of waste were sent to Richland, WA for burial on March 17, 1986.

Samples - Unit 2 samples of air inside the reactor building were sent to Pittsburgh, PA for analysis on March 13, 1986.

APR 111986 ENCLOSUR' B

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. 7. NRC EVALUATIONS IN PROGRESS

- Technical Specification Change Request number 49, and 51.

Recovery Operations Plan Change number 31, 33, 35, and 36.

- Core Stratification Safety Evaluation.

- Solid Waste Facility Technical Evaluation Report.

l - Reactor Building Sump Criticality Safety Evaluation Report.

TMI-2 Temporary Reactor Vessel Filtration System Safety Evaluation Report, Revision 1.

Underhead High Pressure Decon Safety Evaluation Report.

- Hydraulic Shredder Safety Evaluation Report.

Canister Handling and Preparation for Shipment Safety Evaluation Report.

Defueling Canister Technical Evaluation Report, Revision 2.

Penetration 536 Modification Safety Evaluation Report

8. PUBLIC MEETING On the evening of April 10, 1986, the Advisory Panel for the Decontamination of Three Mile Island Unit 2 held a public meeting at the Holiday Inn, Center City, Harrisburg, PA.

At this meeting the Panel received a briefing by T. Demitt, Deputy Director, TMI-2, on the status cf defueling. The Panel expressed interest on the issue of micro-aiological growths in the reactor coolant system. The licensee described the extent of the problem and presented their plans for controlled growth of the micro-organisms.

}

The NRC staff provided a status report on regulatory issues related to r

TMI-2. This included a brief summary of the NRC Advisory Comittee for Reactor Safeguards conclusions on the potential for recriticality during defueling.

The Panel also received comment from members of the public. The next meeting of the Advisory Panel is scheduled for June 11, 1986 from 7:00 PM to 10:00 PM at the Holiday Inn, Center City. Harrisburg, PA.

AFR 111986 ENCLOSURE B

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OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending April 11, 1986 Near-Term NRC Actions Under the 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).

Action: The proposed Federal Register notice of revisions to Part 60 f

(SECY-86-92) was submitted to the Commission in late March 1986 for approval and publication by late April 1986.

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: DOE published a Notice of Availability of the PDS in the Federal Register (51 FR 11466) on Thursday, April 3,1986.

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.

Action. The proposed rule on 10 CFR Part 72 was submitted to the Commission (SECY-85-374) on November 15, 1985, and a supplen.ent (SECY-85-374A) concerning State / Tribal involvement was submitted to the Commission on March 14, 1986. Both papers are currently awaiting Commission approval.

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 with and provide technical assistance to non-nuclear weapon states l in the field of spent fuel storage and disposal. l ENCLOSURE C APR 11 ;?SS

. T

-2 Action: The third annual joint update was published in the Federal Register (51 FR 11463) on April 3, 1986.

Secticn: 306 of NWPA: Regulations for Training of Power Plant Personnel Status: The final rulemaking on Part 55 and three associated regulatory guides received ACRS approval in December 1985, and final Office review has been completed.

Action: The final rule was submitted for review to the CRGR on February 26, 1986, which recommended several modifications. The edited final rule was approved by the CRGR on March 19, 1986. The final rulemaking package is expected to go to the Commission in April 1986.

Near-Term DOE Actions of Interest March 1986 - DOE submitted Annual Report to Congress (Section 304)

April 1986 - DOE to submit Fee Adequacy Report to Congress (Section 302)

April 1986 - DOE to issue Final Project Decision Schedule (PDS)

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 - DOE to issue Final Transportation Institutional Plan April 1986 - Secretary makes a Preliminary Determination on site suitability for a repository April 1986 - Issue Notice of Proposed Rulemaking for Defense Waste fee.

Draft Environmental Impact Statement (DEIS) Re Disposal of Hanford Defense High-Level, Transuranic and Tank Wastes On April 8,1986, the NRC received a draft environmental impact statement (DEIS) prepared by the U.S. Department of Energy entitled " Disposal of Hanford i

Defense High-Level, Transuranic and Tank Wastes" (DOE /EIS-0113, March 1986).

The DEIS has been distributed to interested Federal and State agencies as well as others who have an interest in this activity. DOE will be conducting workshops in the Washington /0regon area to answer questions on the technical content of the DEIS. Comments are being requested by August 9, 1986. The l

ENCLOSURE C APR 11 i?;9 i--

DEIS addresses the selection and implementation of final disposal actions for radioactive wastes located at the Hanford site in Richland, Washington. Among the alternatives considered in the DEIS are (1) "in place stabilization" where the waste is left in the tanks but is isolated by protective and natural barriers; (2) removal of the waste from the tanks and ultimate disposal in a geologic repository; and (3) a reference alternative which combines features of both the geologic disposal and in place stabilization alternatives. The staff plans to review the DEIS only to the extent needed to determine its impact on our statutory responsibilities and how DOE's decisions on the Hanford wastes might affect our resource needs (i.e., additional licensing reviews, development of new regulations, etc.)

Babcock & Wilcox (B&W) Volume Reduction Services Facility The staff has issued its Safety Evaluation Report (SER) on 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 nuclear utilities and industrial and institutional organizations for processing by incineration or high-force compaction. The treated wastes would be packaged for shipment to commercial disposal sites or returned to the waste generators. The staff's Environmental Assessment and proposed Finding of No Significant Impact on the project were issued in, March. Copies of the staff's documents were sent to the Administrative Judge

( and parties to the informal proceeding ordered by the Commission.

l Duquesne Light Company, Beaver Valley Power Station, Unit 2 On April 9, 1986, Duquesne Light Company was issued Materials License No.

SNM-1954 for Beaver Valley Power Station, Unit 2, authorizing the receipt, possession, inspection, and storage of uranium enriched in the U-235 isotope in fuel assemblies. The license also authorizes the receipt, possession, inspection, and use of other radioactive materials in the form of flux mapping moveable incore detectors, neutron detector systems, primary source rods, and various detectors and monitors and their related calibration and check sources.

All materials are for eventual use at the Beaver Valley Power Station, Unit 2.

l l Category I Surface Transportation Although Tri-State Motor Transit Company recently announced that it was withdrawing from the transport of Category I quantities of SSNM, it has agreed to make one more shipment this spring, according to Transnuclear, Inc., the licensee for such shipment. This resolves the immediate problem of assuring the movement of SSNM under export licenses. For the longer range, Transnuclear, Inc., has written to DOE requesting assistance. NRC has also written DOE to offer assistance in resolving this problem.

ENCLOSURE C

,. APR 111983

NFS-Erwin On March 30, 1986, the strike at NFS-Erwin was settled. A meeting was held by NMSS, IE, and ELD with NFS corporate management on April 4 concerning plans to conduct a special inventory before resuming full operations. The Division of Safeguards issued some license conditions concerning the special inventory on April 8. Also on April 8, NRC received some information from NFS concerning its overall plans for the return of its plant to normal operations.

Safeguards Regulatory Effectiveness Review (RER)

On April 4,1986, an NRC team, assisted by Army Special Forces personnel, completed a Regulatcry Effectiveness Review at the Duane Arnold Energy Center, Iowa.

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ENCLOSURE C APR 11 SE5 1

f Office of Inspection and Enforcement Items of Interest Week Ending April 11, 1986

1. The following Significant Enforcement Actions were taken during the past week:

EN 86-17, a Notice of Violation and Proposed Imposition of Civil Penalties was issued on April 7, 1986 to Pittsburgh Testing Laboratory (Pittsburgh, PA) in the amount of $58,000. This action was based on an inspection and investigation in which numerous violations of NRC requirements were identified.

2. The following IE Preliminary Notifications were issued during the past week:

a. PNO-I-86-26, Boston Edison Company (Pilgrim), Plant Shutdown for More Than 48 Hours.

b. PN0-II-86-26, Department of the Army (Fort Knox, KY) - Possible Overexposure of Two Individuals.

c. PNO-II-86-27, Mississippi Power and Light Company (Grand Gulf Unit 1), Unscheduled Shutdown Greater Than 48 Hours.

d. PNO-III-86-33, Toledo Edison Company (Davis Besse) - Security Guard Admits Bomb Hoax.

e. PNO-III-86-34, Consumers Power Company (Midland), Proposed Conversion of Midland to Natural Gas.

f. PNO-IV-86-10, Public Service Company of Colorado (Ft. St. Vrain),

Offsite Rdioactivity Release.

g. PNO-IV-86-11, Kansas Gas & Electric Company (Wolf Creek), Shutdown Greater Than 48 Hours.

3. The following IE Information Notices and IE Bulletins were issued during the past week:

a. IE Information Notice No. 86-23, Excessive Skin Exposures Due to Contamination With Hot Particles, was issued April 9, 1986 to all nuclear power reactor facilities holding an operating license or a construction permit.

b. IE Informtion Notice No. 86-24, Respirator Users Notice: Increased Inspection Frequency for Certain Self-Contained Breathing Apparatus Air Cylinders, was issued April 11, 1986 to all nuclear power reactor facilities holding an operating license or a construction permit, research and test reactor facilities, fuel cycle licensees, and Priority 1 material licensees.

ENCLOSURE D APR 111986 i

c. IE Information Notice No. 86-25, Traceability and Material Control of Material and Equipment, Particularly Fasteners was issued on April 11, 1986 to all nuclear power reactor facilities holding an operating license or a construction permit.

4. Other Items

a. Civil Penalties Paid (1) Comonwealth Edison (Byron) in the amount of $50,000 for viola-tions involving failure to control access to a vital area (EN 86-18).

(2) Portland General Electric (Trojan) in the amount of $50,000 for violations involving breakdown in the licensee's quality assurance program.

b. Operations Center On April 8,1986, Headquarters participated in a limited manner in two drills; one with Region I and Susquehanna and the other with Region III and LaSalle. Participation included a partial Reactor Safety Team, Protective Measures Team and a simulated Executive Team for each drill.

c. Vendor Program (1) The Vendor Program Branch, Division of Quality Assurance, Vendor, and Technical Training Center Programs met with SMC O'Donnell, a new comercial contractor. ,

(2) A member of the Vendor Program Branch assisted ASME in conducting an audit of the National Board of Boiler and Pressure Vessel Inspectors activities as part of the overall audit of the ASME Accreditation Program in conjunction with the U.S. Coast Guard,

d. Quality Assurance The N'RC approved a QA Topical Report for General Nuclear Systems, Inc. which included provisions for NRC acceptance of inspections done by Gennan TUV organizations as substitutes for U.S.-based inspections. This was made possicle after an NRC review of inspec-tien methodologies established equivalence with U.S. Appendix B requiraments and an exchange of correspondence between the ED0 and the Gerran government competent authority.

e. Regional Assessment Members of the Incident Response Branch and Emergency Preparedness Branch are participating in the joint IE assessments of Regions I and III being performed in conjunction with the Susquehanna and LaSalle emergency preparedness eercises.

ENCLOSURE D APR 111983 ,

l

f. Incident Response On April 10, 1986, the Incident Response Branch Chief and staff members will meet with the state of Illinois to discuss their emergency response capabilities and tFe Illinois nuclear data link.

Preplanning for the next Federal Field Exercise will also be discussed.

g. Emergency Preparedness Emergency preparedness exercise reports prepared by FEMA for San Onofre, Calvert Cliffs, and Surry were forwarded by IE to the Regions for appropriate action. While there were no deficiencies in offsite preparedness observed during the exercises, FEMA did identify areas requiring corrective action and areas recommended for improvement.

h. Generic Issues The Rancho Seco batteries were found to be degraded by a problem that affects their seismic qualification. Substantial amounts of material have been lost due to erosion or corrosion of the hooks that support the plates and fasten them to the bus bars in the top internal portion of the cells. This appears to be a problem that may arise rapidly on certain batteries after 15 years of age. As soon as possible, the staff will attempt to define the problem and issue an information notice,

i. Meetings - Conferences of Note Staff member, Vendor Program Branch met with NRR and the NSSS Owners' Groups regarding their activities in response to the SONGS-1 water hammer and check valve event of November 1985.

j. TVA Activities Staff member, Vendor Program Branch assisted Region II and Office of Investigations activities this week.

k. Transportation Staff member, Safeguards and Matarials Programs Branch conducted a training session on transport of radioactive material during the USAF Health Physics Symposium this week.

ENCLOSURE D APR 111?ES

OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending April ll,1986 t

Cooperative Nuclear Plant Analyzer Program between USNRC and Energieonderzoek Centrum Nederland (ECN)

On April 4,1986 a meeting was held between the Dutch representative Karl Brinkmann and RES representatives (J. Cortez, F. Odar, R. VanHouten) to discuss a cooperative program on the Nuclear Plant Analyzer (NPA). A clause in the research agreement between the USNRC and ECN gives ECN an option to participate in the NPA development during the next four years. It was agreed that a representative of ECN will join the INEL team during the first year for training on the NPA system. He will also model Dutch plants. In the remaining three years ECN will participate in the program if the USNRC establishes a program for development of the NPA on a minicomputer. The ECN will make a monetary contribution to the program.

EBR II Inherent Safety Demonstration Tests On April 3,1986, Argonne National Laboratsry successfully performed two safety shutdown demonstration tests at the Experimental Breeder Reactor II (EBR II) facility in Idaho. The two tests were a Loss of Flow Test Without Scram (LOFWS) and a Loss of Heat Sink Without Scram (LOHSWS).

Both the LOFWS and LOHSWS tests were initiated with the reactor operating at 60 MWt (about full power), sodium inlet temperature at 650 F, and sodium outlet temperature at approximately 840 F. Once the tests were initiated, no operator actions were taken.

The loss of flow test was initiated by securing the primary coolant and intermediate loop pumps. Over the first 40 seconds the reactor coolant outlet temperature increased about 300*F causing a passive power ren ction due to thermal expansion of the core, sodium coolant, and control rods. Over the next 150 seconds, the reactor outlet temperature decreased to a value slightly higher than that at the initial condition. Although the test was terminated prior to steady state conditions, the reactor would eventually be critical at a very low power level with the bulk sodium temperature being 10-15*F higher than at the beginning of the test. Reactor cooling would continue to be by natural circulation with a AT near the initial conditions at the beginning of the test.

ENCLOSURE E APR 111985

2-The loss of heat sink test was initiated by securing the intermediate loop pump and applying a reverse flow to eliminate' natural convection flow and effectively eliminating the secondary heat sink. The primary pumps were left running at full flow. Upon loss of the heat sink, all energy was dissipated into the primary bulk sodium pool causing the reactor coolant inlet temperature to rise. This resulted in a passive shutdown of the reactor due primarily to the thermal expansion of the core and its support structure. The reactor inlet temperature increased by approximately 80'F. As reactor power decreased, the reactor-outlet coolant temperature also decreased. At the conclusion of the test the reactor was critical at a very low power level with the primary coolant pumps running, and the primary bulk _ sodium temperature approximately 80*F higher than at the start of the test.

These tests demonstrated the passive shutdown of the reactor. It appeared as though the plant could remain in the post test low power conditions indefinitely without any operator action needed. NRC was invited to observe the test. The RES representative in Idaho attended.

Crack Arrest Workshop The Second Annual NRC/EPRI/NBS Crack Arrest Workshop will be held at NBS Gaithersburg on Thursday and Friday, April 10th and lith,1986. The foremost, international experts in the field of dynamic fracture will participate and make presentations. Heavy emphasis will be placed on the recent results of the NRC/HSST/NBS Wide-plate tests results and on the recent developments in the viscoplastic fracture mechanicsTesearch effort being directed by ORNL through the HSST Program. This work will present the state-of-the-art for crack arrest and in particular the definitive role played by the NRC research.

Contact:

M. Vagins Publication to be Issued in the Near Future

Title:

Draft Regulatory Guide - Containment System Leakage Tosting

Description:

Endorsement of ANSI /ANS 56.8, " Containment System Leakage Testing Requirements".

Contact:

G. Arndt 443-7893 \ '

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APR- 11 1995 ENCLOSURQE

. RES Rulemaking Activities Modifications to GDC 4 Requirements for Protection Against Postulated Pipe Ruptures (Part 50)

The proposed rules 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 final limited scope rule is scheduled to be published in the Federal Register this week. The proposed broad scope rulemaking package is at the ED0's office for signature before being sent to the Commission for vote.

Emergency Preparedness for Fuel Cycle and Other Radioactive Materials Licensees (Parts 30, 40, 70)

In 1981 the NRC issued orders to certain fuel cycle and other radioactive material licensees requiring them to submit comprehensive onsite radiological emergency plans. Rulemaking was initiated on August 3, 1981, for codification of those orders.

The Acting ED0 signed SECY-86-99 on March 25, 1986, and forwarded it to the Commission. At IE's request, the ED0's office changed the recommendation to ask the Commission to defer action until a " Regulatory Gap Analysis" had been submitted. The expected submission date is now April 30, 1986.

Severe Accident Risk Assessnent The RES staff and supporting contractors are currently engaged in the reevalua-tion of the risk of six reference LWRs. This reevaluation is currently being .

used to support NRR's review of IDCOR submittals. In addition, it will support the staff repprt NUREG-1150, which is intended to provide guidance to decision-makers as to the appropriate role of information on core melt frequency, containment performance, source terms, and risk in making severe accident decisions.

A RES/ contractor meeting was held at Sandia National Laboratories on April 2-3, 1986, to discuss the uncertainty analyses for the reference plant studies. RES will brief CRGR on the status of NL' REG-1150 and its supporting analyses on April 10, 1986.

The staff has been informed by an April 2,1986, SECY to ED0 memorandum to the effect that the schedule for NUREG-1150 delivery is firm at September 30, 1986.

APR 111986 ENCLOSURE E e ge

ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING APRIL 11, 1986 Brazilian Visit On Monday representatives from IP and SP met with Dr. Rex Nazare.

Chairman of the Brazilian National Nuclear Energy Comission (CNEN), to discuss the current status of the Price-Anderson Act. This meeting was one of a series of discussions Dr. Rex held in Washington at the State Department.

Foreign Trip Reports J. Muscara, MEB, RES November 4-8, 1985; Visited France:

Mr. Muscara participated in and chaired the Technical Advisory Group (TAG) meeting for the Steam Generator Group Program held in Cadarache. l The visit consisted of tours and discussions of Framatome's maintenance '

and development center including services and NDE activities, status of steam generator activities in France (EdF), PNL presentations on program progress and results and the closed TAG meeting.

Guy H. Cunningham III, Executive Legal Director March 10-11,1986; Visited France:

Mr. Cunningham attended the meeting of the Restricted Working Group on Decomissioning of Nuclear Installations of the Group of Governmental Experts on Third Party Liability in the Field of Nuclear Energy, NEA, Paris. The discussions at the meeting were centered on a paper presented by the Italians. The technical people recomended a further meeting of the Restricted Working Group in the fall.

R. A. Lorenz, ORNL March 11-12, 1986; Visited France:

The traveler represented the NRC at the seventh meeting of the OECD-sponsored Group of Experts on the Source Term (GREST) held in Paris. The purpose of the meeting was to review drafts of papers to be submitted in June to the Principal Working Group 4 (PWG4).

ENCLOSURE G APR 111986

l

. 1 0FFICE OF STATE PRDGRAMS ITEMS OF INTEREST i WEEK ENDING APRIL 11, 1986  !

Large Irradiator Radiation Safety Workshop The American Board of Health Physics has granted 2 Continuing Education Credits for the "Large Irradiator Radiation Workshop sponsored by OSP in September 1985. The Proceedings of this Workshop are now available as NUREG/CP-0073."

Price-Anderson Meeting at State Department On April 7,1986, at the State Department, Jerome Saltzman, OSP, participated in a discussion of the Price-Anderson Act with Dr. Rex Nazar,es, Director of the Brazilian National Commission on Nuclear Energy, and his associates.

Aopalachian Low-Level Radioactive Waste Compact Maryland enacted the Appalachian States Low-Level Radioactive Waste Compact on April 8,1986, and at the same time repealed the Northeast Interstate Low-Level Radioactive Waste Management Compact, following the recent example of Delaware. Membership in the Appalachian Compact comprises Pennsylvania, West Virginia, Delaware and Maryland. New Jersey and Connecticut are the only two members that remain in the Northeast Compact.

Western Low-Level Radioactive Waste Disposal Compact Governor Babbitt of Arizona signed on Aoril 3,1986, the " Western Low-Level Radioactive Waste Disposal Compact," (S.B. 1438). Earlier, Governor Janklow of Scatn Dakota signed legislation on March 29, 1986, S.B. 293, which enacts the same compact. North Dakota has this compact under review and is comparing it to the Rocky Mountain Compact in which it will become eligible effective

, July 1, 1986.

4 ENCLOSURE H APR 111986

ITEMS ADDRESSED BY THE C0911SSION' ' WEEK ENDING APRIL'11,1986 A. STAFF REQUIREMENTS ~ ~ ADVISORY ~ COMMITTEE'ON REACTOR SAFEGUARDS'(ACRS) MEETING ON SAFETY GOALS, 10:00 A.M., FRIDAY, MARCH 28,1986. COM11SSIONERS' CONFERENCE R00H, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to R. Fraley dated 4/7/86 The Commission met with members of the Advisory Committee on Reactor Safeguards (ACRS) to discuss the policy statement on safety goals for the operation of nuclear power plants.

Chairman Palladino requested ACRS comments on the March 24 i memorandum from V. Stello to the Commission on safety goals.

(ACRS) (SECY Suspense: 4/18/86)

_. Commissioner Zech requested the ACRS to provide a mark-up of the proposed safety goal policy clearly indicating where individual ACRS members agree with the policy and where they disagree, and the wording the individuals would propose to modify the policy.

(ACRS) (SECY Suspense: 4/18/86)

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Commissioner Bernthal suggested that the Commission continue the discussion with the ACRS at a meeting in the near future.

(Subsequently, a follow-on meeting was tentatively scheduled for Thursday, May 8, 1986, at 2:00 p.m.)

i Chairman Palladino requested the Office of the Secretary to provide the ACRS with copies of the March 24 memorandum from V.

Stello to the Commission on safety goals.

i (Subsequently, on Friday, March 24, the SECY office provided

the ACRS with copies of the document.)

APR 111986 ENCLOSURE 0

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s NRR MEETING NOTICES *

• APRIL 11, 1986 GS DOCKET APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 4/17/86 -

Ford Bldg. Discuss possible adjustments to AIF E. Butcher 1:00 p.m. AIF Conf. Room the Technical Specifications 7101 Wis. Ave. proposed criteria based on trial Bethesda, Md. application of criteria to Wolf Creek and Limerick Technical

) Specifications.

4/21/86 -

Room P-118 Brief P,noject Directors and TSCB:NRR E. Butcher 10:30 a.m. Phillips Bldg. Projec?T1anagers on the NRC Technical Specifications Improvement Program Plan.

4/22/86 -

Room P-110 Hear and discuss licensee's MP&L L. Kintner 1:30 p.m. Phillips Bldg. plans for the first refueling outage.

4/24/86 50-267 Fort St. Vrain Discuss (1) PCRV tendon PSC C. Hinson 1:00 p.m. Visitor Center surveillance; (2) integrated Platteville, Col. leak rate testing; (3) graphite fuel block crack surveillance; and (4) Building 10, at the Fort St. Vrain Nuclear Generating Station.

4/24/86 50-315 D.C. Cook Site Discuss the site organization and IMEC D. Wigginton 1:00 p.m. 50-316 Stevensville, plant management issues in regards m

Michigan to meeting regulatory requirements p and technical specifications.

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• ACopies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) oin the NRC and local public document rooms

2 -

, NRR MEETING NOTICES

• APRIL 11, 1986 in CD DOCKET APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 4/24/86 50-219 ' Room P-114 Discuss the draft Technical GPUN J. Donohew 9:30 a.m. Phillips Bldg. Evaluation Report on ISPAR

Section 4.11 issued by the staff on January 9,1986.

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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 i

~

, NMSS MEETING NOTICES .

@ Division of Fuel Cycle and Material Safety FOR WEEK ENDING: 04/11/86 i g r .

m DOCKET ATTENDEES /

n; DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 04/8-10/86 Seattle, WA Present a paper at the Third JRoberts, FCAF JRoberts International Symposium on Representatives of Spent Fuel Storage Technology Battelle PNL, ,

industry and

• technical groups. -

4/11/86 Ocean City, Attend Mid-Atlantic Nuclear VMiller, FCML VMiller 1 le Medicine Conference Workshop IMcElroy, FCML l on Medical Licensing.

4/15/86 72-3 Hartsville, Meeting and visit to discuss JRoberts, FCAF JRoberts NC ISFSI application w/ Carolina FSturz, FCAF -

Power and Light at H. 8. JSchneider,' FCAF '

Robinson site. JCounts. IE Representatives of CP&L 4/19-26/86 Vienna, To participate as U.S. Expert DCool FCUF DCool Austria in IAEA Advisory Group.

4/21-23/86 West Valley, To discuss DOE development of ATClark, FCAF ATClark NY confinement barriers and instal- NDavison, FCAF 1ation in supernatant treatment system.

4/22/86 40-2061 Glen Ellyn, To discuss the Kress Creek Hearing MLHorn, FCUF MLHorn Illinois with Region III staff.

4/27/86- Knoxville, To participate in DOE sponsored NKetzlach, FCUF NKatzlach 5/2/86 TN workshops and Nuclear Criticality Technology and Safety Conf.

k 4/28/86- 40-2061 Chicago. To participate in Hearing on DAcool FCUF MLHorn

G 5/2/86 Illinois Kress Creek (Kerr-McGee) EYShum FCUF g MLHorn, FCUF A 5/5-7/86 40-2061 Chicago. To participate in Hearing'&n - DACool, FCUF MLHorn

o Illinois Kress Creek (Kerr-McGee) MLHorn FCUF

, DIVISION OF WASTE MANAGEMENT ,

DATE LOCATION PURPOSE

[ ATTENDEES CONTACT -

N April 23, 1986 NRC, Willste Bldg. EA Site Ranking Methodology Walker Walker

• Silver Spring, MD Briefing ISIRP staff DOE staff ,

DIVISION OF SAFEGUARDS None

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. o OSP MEETING NOTICES April 11,1986 DATE/ TIME LOCATION PURPOSE ATTENDEES NRC CONTACT H

4/22-23/86 Region II, Atlanta Regional SLO Meeting. Region II Governor- MLandau, OSP

$k To discuss subjects of appointed State RTrojanowski, mutual regulatory Liaison Officers; Reg. II interest with Governor- NRC, HQ and Region appointed State Liaison s caff.

Officers.

5/1/86 Hyatt Regency, Workshop co-sponsored by Legislators from most MLandau, OSP Washington, D.C. NRC and the Natl. Conf. States in the U.S. who of State Legislatures to are members of their educate legislators on a State energy or natural wide spectrum of nuclear resources committees, waste issues including NRC staff, radioactive waste disposal, transportation of waste and decommissioning.

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April 11, 1986

3 RII MEETING NOTICE

(( DOCKET NUMBER LOCATION PURPOSE ATTENDEES /

APPLICANT NRC CONTACT gg DATE/ TIME 04/14/86 Southport, NC Presentation of Operator Regional Administrator Grace pm Licensing Certificates 12:30 pm RII Office Meeting with Georgia Licensee and Selected Walker Power Company to discuss Region II Staff Members electrical modules on the Vogtle Readiness Review Program 04/15/86 RII Office Meeting with Florida Power Same as above Walker Company to discuss design 1:00 pm basis reconstitution at Turkey Point 04/16/86 RII Office Meeting with the Senior R. Conway and Grace 11:00 am Vice President-Nuclear Power Regional Administrator of Georgia Power Company to discuss Vogtle issues 04/18/86 RII Office Meeting with Duke Power Licensee and Selected Walker 10:00 am Company to discuss Oconee Region II Staff Members Reactor Vessel UT indications 04/23/86 RII Office Duke Power Company SALP Licensee and Selected Walker 8:30 am Meeting RII Staff Members 04/30/86 Waynesboro, GA Vogtle Full Scale Emergency Participation by HQs Grace Exercise and Regional staff members E

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