ML20133H977

Weekly Info Rept for Wk Ending 850726

ML20133H977
Person / Time
Issue date:	07/31/1985
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-850726, NUDOCS 8508090592
Download: ML20133H977 (37)

Text

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July 31, 1985 For: The Commissioners From: T. A. Rehm, Assistant for Operations, Office of the ED0

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING JULY 26, 1985 A summary of key events is included as a convenience to those Commissioners who may prefer a condensed version of this report.

Contents Enclosure Administration A Nuclear Reactor Regulation B Nuclear Material Safety and Safeguards C 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*

Regional Offices L*

CRGR' Monthly Report M*

Executive Director for Operations N*

Items Addressed by the Coninission 0 Meeting Notices P Proprietary or Other Sensitive Information (Not for Q external distribution)

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• No input this week. e

[

/T. A. Rehm, ant for Operations Office of the Executive Director for Operations

Contact:

T. A. Rehm, EDO 492-7781 8508090592 850731 PDR COMMS NRCC WEEKLYINFOREPT PDR

HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING JULY 19, 1985 Arkansas Nuclear One, Units Nos. I and 2 The Arkansas Power & Light Company is currently experiencing a financial strain on their resources as a result of compliance with a recent Order by the Federal Energ)

Regulatory Comission. The Order requires AP&L to support 36% of the cost of the Grand Gulf Nuclear Station. The Arkansas Public Service Commission has refused ta grant AP&L permission for an interim rate increase until their requested rate in-crease can be processed in September. That rate increase could be denied by the PSC, leaving AP&L in a continuing financial strain. AP&L has assured us that this setback should not affect the operation of Arkansas Nuclear One, Units 1 and 2 or the comitments to the NRC. However, AN0-1&2 will be monitored closely for the effects of this recent development.

Diablo Canyon On July 15, 1985 OI:RV received five documents (approx. 11 inch) from GAP that contain further allegations, possibly containing information concerning 01 investi-gations. Region V is currently reviewing the information for specific allegations and for assignment of review responsibility. Dissemination of the information in the documents will be within NRC only on a need-to-know basis until further instructions by 01.

Watts Bar and Belefonte On July 18 and 19, TVA declared a QA stop work order on all Class 1E electrical cable pulling activities at Bellefonte and Watts Bar facilities, respectively.

Fort St. Vrain Restart Fort St. Vrain returned to operation on July 21, 1985, after an outage which began on June 23, 1984, when six of the 37 control rod drive mechanisms (CRDMs) failed to automatically insert their absorber material during a reactor scram. During the outage,, all CRDMs were refurbished, all four Helium circulators were inspected, and numerous PCRV tendons were evaluated.

Selection of U.S. Facilities for Application of IAEA Safeguards The IAEA has advised that they intend to select three new U.S. facilities for the application of full IAEA Safeguards under the US/IAEA Safeguards Agreement.

JUL 2 61985

OFFICE OF ADMINISTRATION Week Ending July 26, 1985 On July 24,1985, the Executive Director for Operations approved a proposed rule which amends 10 CFR Part 9. This rule clarifies and conforms the regulations pertaining to the availability of records to existing case law and reflects long-standing agency practice. In addition, the rule conforms the reproduction costs for Privacy Act records to those currently charged at the NRC's Public Document Room and other NRC offices for publicly available documents.

This notice constitutes notice to the Commission that, in accordance with the rulemaking authority delegated to the EDO, the EDO has signed this proposed rule for publication in the Federal Register.

4 JUL 2 61985 ENCLOSURE A

8 0FFICE OF ADMINISTRATION Week Ending July 26, 1985 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF RE0 VESTS Initial Appeal of Request Initial Decision Carryovers, 1984 179 23 Received, 1985 521 30 Granted 404 24 Denied 99 11 Pending 197 18 ACTIONS THIS WEEK Received Jim Thomas, Requests copies of letters or memoranda between officials NTEU President in the Division of Facilities and Operations Support and (85-509) officials in the Divi; ion of Security relating to theft of NRC equipment.

(An individual Requests documents in the NRC concerning himself, requesting information about himself)

(85-510)

H. Anne Plettinger Requests all records regarding the technical

, (85-511) specifications for River Bend Unit 1.

William R. Gates, Requests a list cf companies, with addresses, which NUMANC0 are licensed to store, handle, or process radioactive (85-512) materials.

John J. McCaffrey, Requests copies of 24 specified documents regarding the New York Public transportation of spent nuclear reactor fuel.

Interest Research Group, Inc.

(85-513)

Allan Jalon, Requests records pertaining to a September 1967 AEC Los Angeles Times investigation of worker exposures to enriched uranium (85-514) during 1966 and 1967 at Atomics International in Canoga Park, California.

Barbara Baker Lim, Requests a copy of the entire document which transmitted Westinghouse " Guidance - Use of Form 4 - Listing of Exposure Periods" Electric Corp, prepared by J. Lieberman.

(85-515) ENCLOSURE A CONTACT: J. M. Felton 492-7211 JUL 2 61985

2 Received, Cont'd Robert T. Simmons Requests biographical data on Herb Livermore, (85-516) Region III Resident Inspector in the early 1980's, and SALP reports for 10 specified plants.

(An individual Requests a copy of an OIA report and other documentation identifying the NRC employee responsible requesting information ) for certain actions reported to 0IA.

(85-517)

David R. Ennis, Requests a copy of the report entitled, " Financial NUS Corporation Implications of Retrospective Premium Assessments,"

(85-518) (NR-AIG-003) by Ron Melicher.

Billie P. Garde, Requests records regarding the staff's review of the Government Quadrex Corporation's analysis of the South Texas Plant, Accountability records the staff relied on in performing the analysis Project of the Quadrex report and records reflecting the facts (85-519) and circumstances under which the staff learned of the Quadrex Report and any evaluation of the same.

(An individual Requests records regarding injuries he sustained while requesting employed by Bechtel at the Salem 1 nuclear power plant information about on January 12, 1985.

himself)

(85-520)

John I Riesland Requests records providing the scheduled dates of new (85-521) fuel shipments vs. the scheduled dates of restart for plants shut down for a refueling outage during the period from January 1, 1980 to January 1, 1985.

Barton A. Smith, APPEAL TO THE EDO for the release of Ms. Vera English's General Electric statements regarding events at the General Electric '

Company facility in North Carolina in March 1984.

(85-A-30-85-303)

Granted Antonio Freire In response to a request for records relating to fuel (85-240) loading and/or low power testing of the Diablo Canyon nuclear power plant; a copy of the damage claim against NRC filed by GPU on December 8, 1980; and a copy of the September 1980 report prepared by AE0D regarding interim equipment and procedures at the Browns Ferry nuclear power plant to detect water in discharge, made available two documents. Infonned the requester that two additional documents subject to this request are already available at the PDR.

ENCLOSURE A JUL 2 61985

3 Nina Bell, In response to a request for documents regarding how NRC Nuclear Information intends to apply the decommissioning rule, when finalized, ar.d Resource to power and non-power reactors which are permanently Service shut down and the effect that the proposed decommissioning (85-359) rule will have on Pacific Gas and Electric's plans to decommission the Humbolt Bay nuclear power plant, made available one document.

Nina Bell, In response to a request for eight categories of Nuclear Information documents regarding seismic design and earthquake and Resource research, made available 96 documents. Informed the Service requester that additional documents subject to this (85-363) request are already available at the PDR.

Jacques Kerdiles, In response to a request for copies of (1) SECY-85-119, Framatome U.S. and (2) a letter from the NRC to Westinghouse or others Representative regarding guidance for review and acceptance of spent (85-420) fuel storage and handling application dated April 14, 1978, and its revision dated January 18, 1979, made available one document. Informed the requester that additional documents subject to this request are already available at the PDR.

Susan L. Hiatt, In response to a request for all records concerning the OCRE Representative meeting between the NRC and the Hydrogen Control Owners (85-464) Group held on May 22, 1985, made available one document.

Frank S. Hamblett, In response to a request for a copy of SECY-85-222, made Newman & available a copy of the requested paper.

Holtzinger, P.C.

(85-470)

Joan A. Estrada, In response to a request for copies of invoices and -

Professional purchase orders for drapery cleaning and the Carpet Service maintenance and repair of venetian blir.ds from August 8, (85-473) 1984, to June 30, 1985, made available a copy of the requested documents.

Richard Condit, In response to a request for records relating to the Government waste disposal practices of the Dow Chemical Company Accountability of Midland, Michigan, made available 12 documents.

Project Informed the requester that additional documents subject (85-483) to this request are already available at the PDR in files for previous F0IA requests.

Desmond J. Byrne, In response to a request for a list of NRC consultant International contracts costing $20,000 or more from the beginning Tourism Research of Fiscal Year 1982 to the present, made available a (85-486) copy of the requested list.

Jim Pedro, In response to a request for papers presented at the BNL NUS Corporation Workshop on Seismic Component Fragility, made available (85-497) 16 documents.

ENCLOSURE A

4 Granted, Cont'd ,

(An individual In response to a request for records about himself, requesting informed the requester that the NRC has no information information about on him in its radiation exposure, document control, or himself) security systen of records.

(85-510)

Denied John Clewett, In response to a request for documents regarding inter-Government views held by three NRC staff members on June 12, 1984, Accountability concerning the Callaway nuclear power plant, made Project available 11 documents. Informed the requester that (84-701) additional documents subject to this request are already available at the PDR. Denied portions of five documents, disclosure of which would disclose the identity of a confidential source. Denied three documents in their entirety containing advice, opinions, and recommendations of the staff. Denied one document in its entirety, disclosure of which would interfere with an enforcement proceeding.

Steve Kohn and In response to a request for information compiled by Richard Condit, and/or for the NRC/AEC regarding the Dow Chemical Government Company of Midland Michigan which was compiled in Accountability order to determine the need to comply with 10 CFR Project Parts 19, 20, 30, 31, 32, 33, 34, 35, 40, 51.4, 51.5, (85-261) 51.6, 51.7, 70, 170, and/or 40 CFR Parts 1500.6, made available 407 documents. Denied portions of 15 documents, disclosure of which would constitute a clearly unwarranted invasion of personal privacy.

Denied portions of three documents which identify procedures for safeguarding licensed special nuclear material at a licensed facility or plant. Denied one document in its entirety containing advice, opinions, and recommendations of the staff.

ENCLOSURE A JUL 2 61985

WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING JULY 26, 1985 IFB ISSUED IFB No.: RS- ASB-85-401

Title:

" Stenographic Reporting Services"

Description:

Provide stenographic reporting services outside the Washington, D.C. metropolitan area.

Period of Perforrrance: 24 months Sponsor: Atomic Safety and Licensing Board Panel Status: IFB issued on July 18, 1985. Bids due August 13, 1985.

RFP ISSUED RFP No. : RS-ADM-85-235

Title:

"NRC Translation 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 Status: RFP issued on July 19, 1985. Proposals due August 19, 1985.

PROPOSAL UNDER EVALUATION RFP No.: RS-NMS-85-008

Title:

" Technical Assistance in Hydrogeology - Project A - Testing"

Description:

The contractor shall provide technical assistance to the NRC in its review of DOE site investigations for a potential High Level Waste (HLW) geologic repository.

Period of Ferformance: 2 years with 3 one-year options Sponsor: Office of Nuclear Material Safety and Safeguards Status: The competitive range has been established and negotiations are scheduled for the week of August 19, 1985. ,

CONTRACTS CLOSED-0UT NRC-03-84-076 John Heywood N RC-02-81 -057 Science Applications Inc.

JUL 2 61985 ENCLOSURE A

0FFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending July 26, 1985 Arkansas Nuclear One, Units Nos. 1 and 2 The Arkansas Power & Light Company is currently experiencing a financial strain on their resources as a result of compliance with a recent Order by the Federal Energy Regulatory Commission. The Order requires AP&L to support 36% of the cost of the Grand Gulf Nuclear Station. Grand Gulf is operated by Mississippi Power and Light Company and owned by Middle South Energies, a subsidiary of Middle South Utilities. AP&L is also a subsidiary of Middle South Utilities. AP&L had originally agreed to accept approximately 20% of the power from Grand Gulf. How-ever, they have since reached an agreement with Middle South Utilities and Middle South Energies that they would not participate in the arrangement. The Arkansas Public Service Commission has refused to grant AP&L permission for an interim rate increase until their requested rate increase can be processed in September. The requested rate increase to be heard in September could be denied by the PSC leaving AP&L in a continuing financial strain. AP&L has assured us that this setback should not affect the operation of Arkansas Nuclear One, Units 1 and 2 or the commitments to the NRC. However, AN0-182 will be monitored closely for the effects of this recent development.

Diablo Canyon On July 15, 1985 OI:RV received five documents (approximately 11 inch) from GAP that contain further allegations, possibly containing information concerning 01 investigations. A copy was provided to Region V and NRR. Region V is currently reviewing the information for specific allegations and for assignment of review responsibility.

Dissemination of the information in the documents will be within NRC only on a need-to-know basis until further instructions by 01.

Watts Bar and Bellefonte On July 18 and July 19, TVA declared a QA stop work order on all Class IE electrical cable pulling activities at Bellefonte and Watts Bar facilities, respectively. The order was issued from the TVA Project Manager's Office under the direction of the Manager of Power and Engineering (Nuclear). Electrical cable installation requirements are addressed by TVA's General Construction Specification, G-38, which is intended to be used for all TVA facilities. The licensee's review of G-38, identified an inadequacy in cable pull tension requirements ENCLOSURE B Jul. 2 61985

, with respect to industry practices, in that the maximum pull forces addressed in the procedure fail to account for side wall pressure exerted on the electrical cable when pulled thru conduit. Cable side wall pressure has been considered as a factor for .:able pulling activities for a number of years. Electrical cable pulling is essentially complete for Watts Bar Unit 1. Also, the licensee is evaluating the applicability of this concern to the Sequoyah units.

Fort St. Vrain Restart Fort St. Vrain returned to operation on July 21, 1985, after an outage which began on June 23, 1984, when six of the 37 control rod drive mechanisms (CRDMs) failed to automatically insert their absorber material during a reactor scram. During the outage, all CRDMs were refurbished, all four Helium circulators were inspected, and numerous PCRV tendons were evaluated.

The return to operation was authorized by a July 19, 1985 Confirmatory Action Letter which allows operations up to 15% power pending certification that the facility is in compliance with 10 CFR 50.49 (EQ).

Additionally, numerous licensee commitments related to CRDMs, water ingress, conduct of operations, Technical Specifications, and fire protection were confirmed.

The plant is presently (7/22/85 a.m.) critical and performing startup testing.

Waterford LP&L's Waterford 3 is presently in Mode 5 (cold shutdown) in day 6 of a projected 26-day outage. This outage began at 3:45 a.m. on July 18, 1985 with a turbine trip due to high vibration. The plant was in the process of returning to power after an interruption of the 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> warranty run (malfunction of digital electrical hydraulic control system). The know damage to date includes the exciter and the third stage of the low pressure turbine. The exciter has been shipped to Westinghouse for repair / replacement and a spare low pressure rotor assembly is presently being prepared for installation. Further investigation of root cause and inspection for additional damage are in progress.

Turkey Point Unit 3 While operating at 100% power on July 21, 1985, the reactor tripped at 11:41 p.m. due to turbine trip. The exact cause is unknown but a lightning strike occurred in the area at that time.

ENCLOSURE B JUL 2 61985

. o Approximately one hour later, all three (A, B & C) auxiliary feedwater (AFW) pumps auto-started due to low-low level in steam generator 38.

The low-low level was caused by failure of the normal feedwater train bypass valve to open when demanded by the operator. Auxiliary feedwater pumps A & C tripped on mechanical overspeed (cause of overspeed to be determined). The B pump was able to maintain water level. Within I hour, the A, C pumps were successfully tested and considered operable.

At 4:00 a.m. on 7/22/85 (plant in hot shutdown), all three AFW pumps successfully auto-started due to main feedwater pump trip caused by high level in the 3C steam generator. The level increase was caused by a closed but leaking FW bypass regulating valve.

At 6:04 a.m. on 7/22/85, plant cooldown from hot shutdown to cold shutdown was effected for repair of an AFW control valve.

Limerick On July 22, 1985 the Board issued its Fourth Partial Initial Decision (PID) in the Limerick proceeding. This PID finds that the emergency response plan for the State Correctional Institute at Graterford meets the requirements of 10 CFR 50.47 and Appendix E as well as the criteria of NUREG-0654, and provides reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency.

Oconee Nuclear Station, Unit 1 Duke Power Company informed the staff on July 23, 1985 that a DC breaker responded slowly during the monthly on-line surveillance test. The breaker tripped in 1738 milliseconds and the acceptance criteria requires a response time within 80 milliseconds.

Oconee Unit I continues to operate at 100% power. Duke says the faulty breaker was replaced with a spare and they are in the process of testing the other reactor trip breakers in Unit 1.

A similar event occurred at Oconee Unit 1 on April 30, 1985 when a DC breaker tested slowly with a 1530 millisecond response time. Duke had found the cause to be a paint chip interferring with the undervoltage trip attachment.

ENCLOSURE B JUL 2 61985

Turkey Point Units 3 & 4 In accordance with 10 CFR 21, Florida Power and Light Company notified the NRC by telephone of a design deficiency relating to Turkey Point Plant, Units 3 and 4, Main Steam Isolation Valves (MSIV). Turkey Point Plant uses MSIVs in conjunction with Main Steam Check Valves to isolate the steam generators from the ste<tm header. The MSIVs have a trip feature designed to prevent steam flow from the steam generator to the header. The criterion for the trip feature, identified in FSAR Section 14.2.5, is that the MSIVs close in less than 5 seconds under no steam flow conditions.

Tests performed by the licensee indicates that MSIV closure is not assured if instrument air is unavailable and no steam or low steam flow exists.

The licensee has implemented the compensatory measures until modifications are implemented which will assure the closure times assumed in the accident analysis are valid. The compensatory measures are:

Backup diesel air compressor available

- Cross ties to the fossil units service air

- Procedures requiring plant shutdown on loss of plant air The licensee will provide a followup written submittal. The staff is assessing the information provided and possible generic implications.

Palo Verde Unit 1 ,

The staff was informed on July 24, 1985 that Unit I was required to shutdown in accordance with Technical Specification 3.4.5.2 because of an unidentified leakage rated slightly in the reactor coolant system.

This is a second occurrence for this event. On July 11, 1985, an unidentified leakage rate of 1.2 gpm was determined. On July 12, 198!.,

the licensee's request for a one time only change to Technical Specification 3.4.5.2 was granted, which allowed an additional 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to find the leakage pathway before proceeding to cold shutdown.

l

! ENCLOSURE B JUL 2 G 1985

NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT WEEK ENDING JULY 26, 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.

- The reactor vessel plenum has been removed from the reactor vessel and placed on its storage stand in the deep end of the fuel transfer canal. A dam has been installed between the deep and shallow ends of the fuel transfer canal. The deep end is filled with water to a depth of about 20 feet (about 5 feet above the top of the plenum).

The modified internals indexing fixture is installed on the reactor vessel flange and is flooded to elevation 327 'eet 6 inches (151 feet above the top of the core region).

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 71*F to 91*F with an average of 81*F. Average cold leg temperature is 58*F.

The average reactor building temperature is 59*F. The reactor building airborne activity is 7.4 E-9 uC1/cc Tritiun 4.1 E-10 uCi/cc particulate, predominantly Cesium 137,

2. WASTE MANAGEMENT The Submerged Demineralizer System (SDS) processed batch 5123 consisting of 50,028 gallons from the "C" reactor coolant bleed

~

tank. EPICOR II completed processing batch 264 consisting of 10,831 gallons from SDS tank 18.

Total volume processed through SDS to date is 2,963,375 gallons, and the total volume processed through EPICOR II is 2,547,671 gallons.

ENCLOSURE B.

JUL 2 61985

2

3. DOSE REDUCTION / DECONTAMINATION ACTIVITIES Decontamination activities are continuing on the 281' level of the Auxiliary Building.

Average general area radiation dose rate is 36 mrem per hour on the 347' level of the reactor building and is 160 mrem per hour on the 305' level of the reactor building.

4. ENVIRONMENTAL MONITORING 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 the US Environmental Protection Agency at the plant discharge to the river consisted of seven daily composite samples taken from July 6, to July 13, 1985. Gamma scans detected no reactor related radioactivity for the July 6 through 12 samples.

The July 13 gamma scan result was 3 E-9 uCi/cc.

The Lancaster water samples taken at the water works intake and _

analyzed by the US Environmental Protection Agency consisted of seven day composite samples taken from July 14 to July 28, 1985. A gamma scan detected no reactor related radioactivity.

The NRC outdoor airborne particulate sampler at the TMI Site collected a sample between July 18, and July 25, 1985. No reactor related radioactivity was detected. Analysis showed I-131 and Cs-137 ccncentrations to be less than the lower limits of detectability.

5. REACTOR BUILDING ACTIVITIES Additional characterization of the reactor vessel lower head was performeo during the week of July 21, 1985. Inspection of an area in the last quandrant to be characterized (North side of vessel) indicated that the rubble bed is somewhat more shallow in this area than at points inspected in the other three quadrants. Because of the shallowness, samples were not obtained at this location. A water jet directed at the debris cratered the debris bed. This activity as well as probing of the bed indicates that this portion of the bed may consist of non-aglomerated rubble. Also, radiation level measurements of debris bed samples taken from a location at the X axis (West side of vessel) indicate that the material sample contains a much smaller concentration of radioactive material than expected.

Substantial progress on assembling the rotating defueling platform in the reactor building was made during the week.

ENCLOSURE B Jul 2 61985

3

6. AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Installation of the DWCS continued. Partial DWCS turnover for processing RCS during early defueling is scheduled to be completed in late August.

The first fuel canister rack is on site with further deliveries scheduled through August.

7. NRC EVALUATIONS IN PROGRESS Defueling Water Cleanup System Technical Evaluation (including Revision 6)

Technical Specification Change Requests numbers 46, 48, 49, and 50 Recovery Operations Plan Change numbers 27, 29, 31, and 32 Fuel Canister Technical Evaluation Fuel Handling Senior Reactor Operator Training Program Defueling Safety Evaluation Application for seismic exemption The NRC Vendor Programs Branch performed an inspection at the NuclearEnergyServices(NES)facilityinGreensboro, North Carolina, where the fuel storage canisters, fuel storage racks, and fuel canister transfer shields are being fabricated. The inspection examined construction activities and included a review of the implementation of the quality assurance program at NES. The inspection findings are undergoing NRC management review and the final inspection report will be issued next week.

8. PROJECTED SCHEDULE OF FUTURE EVENTS Start of Defueling: October 1985

9. .PUBLIC MEETING The next meeting of the Advisory Panel for the Decontamination of Three Mile Island Unit 2 is scheduled for September 1985 at a location in Annapolis, Maryland, the specific date and location will be identified later.

ENCLOSURE B JUL 2 61985

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s

O OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending July 26, 1985 Near Term NRC Actions Under the Nuclear Waste Policy Act (NWPA)

Section: 114(e) of NWPA Action: NRC transmitted comments to DOE on the preliminary draft Project Decision Schedule on March 4, 1985.

Status: DOE submitted the draft PDS to NRC on July 18, 1985. Review and comments are due by September 13, 1985. The final PDS is expected in November, 1985.

Section: 301 of NWPA Action: The final DOE Mission Plan was submitted to Congress on July 9, 1985. As required by NWPA, DOE published responses to NRC objections in the Federal Register on July 12, 1985 (50 FR 28446).

Status: Ben Rusche, Director, Office of Civilian Radioactive Waste Management at DOE will meet with the Commission on July 29, 1985 at ,

2:00 p.m. to discuss NRC's views of the Mission Plan.

Duke Power Company On July 10, 1985, Duke Power Company was issued Materials License No. SNM-3949 for the Catawba Nuclear Station, Unit 2, authorizing the receipt, possession, inspection, and storage of uranium enriched in the U-235 isotope contained in fuel assemblies in their shipping containers, in the New Fuel Storage Vault, and in the Spent Fuel Storage Facility. In addition, the license authorizes the receipt, possession, inspection, storage, and use of a Pu-Be neutron source and storage U-235 fission chambers.

Selection of U.S. Facilities for Application of IAEA Safeguards The IAEA has advised that they intend to select three new U.S. facilities for the application of full IAEA Safeguards under the US/IAEA Safeguards Agreement.

The three facilities are:

1. Westinghouse LEU Fuel Fabrication facility

2. Turkey Point #4 PWR power reactor

3. Salem #2 PWR power reactor ENCLOSURE C JUL 2 61985 I

. o 0FFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending July 26, 1985

1. The following Significant Enforcement Action was taken during the past week:

a. EN 85-52, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $150,000 was issued July 22, 1985 to Tennessee Valley Authority (Browns Ferry Units 1, 2 and 3). This action is based on two violations that were identified as a result of a special safety inspection conducted to review the reactor vessel water level indication anomalies that occurred during a Unit 3 startup.

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

a. PN0-I-85-52, General Public Utility Nuclear Corporation (0yster Creek), Reactor Shutdown Due to a Degraded Energency Service Water System.

b. PNO-II-85-68, Duke Power Company (0conee Units 1, 2, & 3), Threaten-ing Telephone Calls,

c. PNO-II-85-69, Tennessee Valley Authority (Bellefonte Units 1 & 2; Watts Bar Units 1 & 2), Stop-Work Order on Electrical Cable Installa- 1 tion.

d. PN0-II-85-70, Florida Power and Light Company (St. Lucie Units 1 & 2; Turkey Point Units 3 & 4; Crystal River Unit 3), Actions in Response to Tropical Storm " Bob."

e. 'PN0-II-85-70A, Florida Power and Light Company (St. Lucie Units 1 &

2); Georgia Power Company (Hatch Units 1 & 2); Carolina Power and Light Company (Brunswick Units 1 & 2); and General Electric Company (Wilmington, NC), Actions in Response to Tropical Storm " Bob."

(Update)

f. PN0-II-85-71, Georgia Power Company (Hatch Unit 1), Unscheduled Shutdown Greater Than 48 Hours.

g. PNO-III-85-228, Iowa Electric Light and Power Company (Duane Arnold),

Through-The-Wall Crack in Recirculation Piping (Update).

h. PN0-III-85-61, Commonwealth Edison Company (Byron Unit 1), Lightening Strike Affects Instrumentation, Components.

1. PNO-III-85-62, Commonwealth Edison (LaSalle), CAL Issued Because of Faulty Installation.  !

j. PN0-III-85-63, Detroit Edison Company (Fermi Unit 2), Shutdown to l Repair Feedwater Plant. ENCLOSURE D l JUL 2 61985 l l

k. PN0-III-85-64, Wisconsin Electric Power (Point Beach Unit 1), Loss of Power to Safeguard Buses.

1. PN0-IV-85-35, Louisiana Power and Light Company (Waterford 3), High Vibration in Turine.

m. PN0-IV-85-35A, Louisiana Power & Light Company (Waterford 3), High Vibration in Main Turbine (Followup Report).

n. PN0-IV-85-36, Nebraska Public Power District (Cooper), Loss of Instrumentation on the Meteorological Tower.

o. PN0-IV-85-37, Public Service of Colorado (Fort St. Vrain), Authori-zation to Return the Fort St. Vrain Plant to Operation.

p. PN0-IV-85-37A, Public Service of Colorado (Fort St. Vrain), Return to Operation After a Prolonger Shutdown (Update).

q. PN0-V-85-45A, Department of the Navy, Naval Ocean Systems Center (San Diego, CA) Update--Contamination of Three Laboratories.

r. PN0-V-85-45B, Department of the Navy, Naval Ocean Systems Center (San Diego, CA), Update--Contamination of Three Laboratories.

s. PNO-V-85-46, Fortland General Electric Company (Trojan), Reactor Trip and Subsequent Shutdown for Greater Than 48 Hours,

t. PNO-V-85-47, Pacific Gas and Electric Company (Diablo Canyon Unit 2),

Heatup Sequence in Preparation for Criticality Interrupted. ,

u. PNO-V-85-48, Palo Verde Nuclear Generating Station (Unit 1), Extended Plant Outage.

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

a. IE Information Notice 85-61, Misadministrations to Patients Under-going Thyroid Scans was issued July 22, 1985 to licensees authorized to use by-product material for human applications,

b. IE Information Notice 85-62, Backup Telephone Numbers to the NRC Operations Center was issued July 23, 1985 to all nuclear power reactor facilities holding an operating license or a construction permit.

c. IE Information Notice 85-63, Potential for Comon-Mode Failure of Standby Gas Treatment System on Loss of Offsite Power was issued July 25, 1985 to all nuclear power reactor facilities holding on operating license or a construction permit.

ENCLOSURE D JUL 2 61985

4. Other Items

a. Outage Trial Inspection Program Representatives of the Division of Inspection Programs met with regional personnel at Region IV on July 25 and at Region III on July 26 to discuss the outage inspection trial program which will be conducted during upcoming outages at the Fort Calhoun and Dresden 3 plants.

b. Incident Response (1) On July 23 and 24 technical training drills for the Reactor Safety Team and Protective Measures Team were conducted in the Operations Center using the Bookhaven Nuclear Plant Analyzer for BWRs.

(2) On July 25, Chief and representatives of the Incident Response Branch, Division of Emergency Preparedness and Engineering Response attended a site meeting at Beaver Valley with licensee representatives, other federal representatives and the state to discuss the Relocation Tabletop Exercise (RTE).

(3) A representative of the Incident Response Brar.ch attended an EPA briefing on the National Science Foundation oroject for communicating risk and risk management decisions en July 25, 1985. This project is sponsored by the Office of Science and Technology Policy.

c. Emergency Response / Preparedness (1) IE staff memebfrs attended a meeting with FEMA representatives on July 23,'1985 to discuss the current status of the ongoing rulemaking regarding consideration of the complicating effects of natural phenomena on emergency response.

(2) A representative of the Emergency Preparedness Branch, Division of Emegency Preparedness and Engineering Response participated in the observation of the Watts Bar full-participation emergency preparedness exercise this week.

(3) A representative of the Emergency Preparedness Branch partici-pated in the preoperational inspection of emergency planning at Millstone Unit 3 this week.

l ENCLOSURE D JUL 2 61985

d. Vendor Program The following Vendor Program inspections were conducted this week: '

(1) Point Beach Units 1 and 2, Two Rivers, WI. This inspection was conducted to review licensee equipment qualification program implementation as required by 10 CFR 50.49.

(2) Technology for Energy Corporation, Knoxville, TN. This inspec-tion was conducted to review information concerning the quali-fied life of acoustic monitors and review implementation of the QA program.

(3) Engineering Assurance This week, representatives of the Division of Quality Assurance, Vendor, and Technical Training Center Programs, conducted an implementation inspection for the South Texas Project Engineering Assurance Program at Stone & Webster offices in Boston and at Ebasco, NY for followup on Harris IDI inspection findings.

JUL 2 61985

0FFICE OF NUCLEAR REGULATORY PESEARCH Items of Interest

. Week Ending July 26, 1985 Semiscale During this week, the first 600 seconds of the Semiscale Test S-FS-6 was successfully rerun. During the original test, performed on May 22, 1984, the thennocouple triplets used to measure heat transfer from the primary to secondary coolant across the steam generator tubes were incorrectly calibrated, thus resulting in unacceptably large uncertainties in heat transfer response.

Since obtaining steam generator heat transfer data during this period for assessment of NRC's analysis methods was the principal objective for this test, the test was rerun at this time with properly calibrated thennocouples. Test S-FS-6 models a 100 percent break in the feedwater line of a Combustion Engineering (CE) System 80 type reactor. This accident was chosen because very conservation analyses by the vendor indicated the potential for high primary system pressure during these transients. Data from this test will be used to assess NRC's best estimate codes (TRAC and RELAP5).

ROSA-IV Since the connissioning of the Japanese ROSA-IV Large-Scale Test Facility (LSTF), two small break tests have been conducted. The first test, SB-CL-01, was conducted on May 30-31, 1985. This is a 2.5 percent cold-leg break test.

The purpose of this test was to study the effect of break orientation. The second test, SB-CL-05, was conducted on June 26-27, 1985. This is a ,

5.0 percent cold-leg break test with 0.5 percent total bypass flow from upper head and hot-leg to the upper downcomer region. The purpose of this test was to study the effect of liquid holdup in a steam generator and the resulting .

core level depression. This test will improve our understanding of li holdup phe'nomenon during a small-break loss-of-coolant accident (LOCA) . The quid liquid holdup phenomenon is an important licensing and safety issue.

Model Boiler-2 (M8-2)

MB-2 data is used to validate steam generator models in NRC's licensing safety

. analysis codes TRAC and RELAP. The cxamination of loss of feed data has been completed. Thermocouple data in the tube bundle were examined for consistency and found to be excellent, thus giving a high degree of confidence in the ability to extract heat transfer coefficients from loss of feed data. Those coefficients will be available when the data analysis report is published in October 1985. This is a joint program amon9 NRC, the Electric Power Research Institute (EPRI), Westinghouse Electric Corporation (W), and the Central Electricity Generating Board (United Kingdom) (CEGB).

ENCLOSURE E l

, Meeting of Coordinating Committee for LLW Disoosal Technologies NRC/RES personnel recently participated in the second meeting of the Coordinating Committee for LLW Disposal Technologies, an ad hoc group formed to coordinate LLW research among various Federal agencies (NRC, DOE, USGS, EPA), industry (EPRI), and States. Committee members report on ongoing and planned LLW research activities in their organizations and serve as a means of conveying research results from the other organizations back to their own organizations. The Committee is serving to focus research on actual, specific problems being encountered by the States. The Committee is meeting approximately quarterly.

Fifth Annual American Statistical Association Conference on Radiation and Health The Fifth Annual American Statistical Conference on Radiation and Health, which was supported by NRC and DOE, was held at Berkeley Springs, West Virginia, July 8-12, 1985. Topics covered at the meeting included the revision of dosimetry for the Atomic Bomb Survivors, the impact of dose measurement error on radioepidemiologic studies, the radioepidemiologic tables (probability of causation) and several presentations on ongoing radioepidemiologic studies. Dr. Michael Ginevan, HEB/DRPES/RES, chaired a session on " Relationship of Cancer Incidence to Terrestrial Radiation and Population Density: Connecticut, 1935-1974."

International Conference on Nuclear Reactor Decomissioning Planning The International Conference on Nuclear Reactor Decomissioning Planning sponsored by the NRC and hosted by the NRC subcontractor, United Nuclear Corporation, was held in Bethesda July 15 through July 18. The Conference was attended by representatives of industry and agencies, state and federal, and international experts with decomissioning responsibility and experience.

Duriag the conference 36 papers were presented in major areas of interest that could impact on the rule on planning: Decomissioning Philosophy and Guidance, funding of Decomissioning Projects, Decorsnissioning Plans and Evperience, Minsgemnt of Decomissioning Waste, and Engineering Problems.

ENRM E JU. 2 6 1985

Among the areas discussed, major points of concern were: (1) how actual l cxperience can be factored into planning; (2) when will generic guidance on residual radioactivity levels for decomissioning be available including levels for possible recycle; (3) how to handle decomissioning waste in terms

- of storage accommodation, characterization, consistency and waste form as well as recycle of deconunissioning materials within and outside of the nuclear industry; (4) the need for the development of regulations and guidance explicitly pertaining to decomissioning; (5) what are the best methods for estiw. ting cost and additionally, for the USA, what funding packages constitute a proper inplementation of reasonable assurance; and (6) how acceptable is entombmont as a decomissioning alternative.

About 175 people attendeu the Conference including those from England, Crnada, Tain n, Italy, France, Federal Republic of Germany, Israel, Japan, Smfen, Belgium, and a representative from the Internatiunal Atomic Energy Agency. Connnts from the attendeed were that the quality and breadth of meterial presented was imprssive, leading to an interesting and useful meeting.

Ccn'erence proceedings (NUREG/CP-0068) will be available in 3 to 4 months.

Seminar on Recent Major Earthquake in Chile The Earthquake Engineering Research Institute held a seminar on the March 3, 1985 magnitude 7.8 earthquake in Chile at the U.S. Geological Survey Auditorium in Reston, Virginia, on July 18 and 19. The agenda included a presentation on the geology and seismicity of the region, basic seismological field observations, geotechnical effects such as liquefaction and damn failures, basic seismological field observations, strong motion records of the main shock and aftershocks, performance of residential, industrial structures, bridges, and socioeconomic observations. Discussions were held on the improvement of existing design codes and construction practices.

MIT.I/NUpEC Discussions i

RES is continuing discussions with the Japanese Ministry of International Trade and Industry (MITI) and the Nuclear Power Engineering Test Center (NUPEC) regarding possible participation in high level vibration experiments 4

on the T6dotsu snaker table. The Tadotsu facility, located on the island of Shikoku, is the world's largest shaker table (15m x 15m, 3000 ton force).

RES is interested in participating in the extension of a planned experiment on a 1/3 scale PWR coolant loop into the inelastic range. Data from this experiment would be used to validate simplified nonlinear computer codes used in margins studies beyond the design basis.

ENCLOSURE E JUL 2 61985

-- -. - - - -- --- ==

- - - . , . . _ _ - , -m %

EPRI has expressed interest in participating, in concert with RES, in these experiments.

that is mutually beneficial to all parties.RES is working closely with EPRI to j dev i

- Officials from MITI and NUPEC will visit the NRC and EPRI during the week of August 5 to discuss the possibility of a cooperative effort on the Tadotsu shaker table experiments.

The MITI and NUPEC officials will also visit the Brookhaven National Laboratory (the NRC contractor for this effort) on August I to discuss the technical aspects of the proposed experiment.

Hydrogen Combustion FLAME Acceleration Tests The FLAME (Flame Acceleration Measurements and Experiments) facility at Sandia National Laboratories was designed to study hydrogen combustion problems relevant to reactor safety. These are accelerated flames and transition to detonation. Test Series I investigated the effect of transverse venting on flame acceleration and transition to detonation. On June 28, 1985, the first test of Series II was conducted at the FLAME facility channel in which obstacles were used to promote flame acceleration. The results were signifi-cantly different from the clean channel (no obstacles) tests.

The effect of obstacles on the flame speeds and overpressures was significant.

For 15% hydrogen in FLAME without obstacles and with no top venting, the overpressure was about 10 kPa (1.5 psig) and the equivalent planar flame speed was about 60 m/s. In the latest test with obstacles, the peak overpressure was I

about 600 kPa (90 psig), and the equivalent planer flame speed was over 500 m/s.

The remaining tests in this series are planned to determine the interactive relationships between obstacles and transverse venting on flame acceleration.

l -Flame acceleration causes significant increases in overpressure and the -

I pret,eoility for transition from deflagration to detonation. Upon completion of this final series in February 1986 it is expected that an adequate data base will exist to quantify the effects of flame acceleration. This data is needed to resolve and bring closure to flame acceleration issues remaining for BWR-MARK III and PWR Ice Condenser Plants.

ENCLOSURE E JUL 2 61985

International Conference on Nuclear Plant Aging, Availability Factor and l

Reliability Analysis - San Diego, CA, July 8-12, 1985 l

I

• NRC staff actively participated in the International Conference on Nuclear Plant Aging, Availability Factor and Reliability Analysis in San Diego, July 8-12, 1985. Over 300 delegates attended the conferehce with significant pa'rticipation from foreign countries. At the conference, the major topic of discussion by the NSSS vendors was centered around " Plant Life Extension" while the utilities' interest was in programs directed at improvements in " Plant Availability" and " Plant Capacity Factor." .

( Chairman Palladino in his keynote address entitled, " Forty Years--What Then?" .

focused on the imediacy of plant aging issues and on the prospects for extending plant operation beyond forty years. The Chainran emphasized the need for aging research for regulatory readiness to assess license renewals and discussed the relationship of safety, aging, availability and reliability. He cited specific examples of many possible actions that the industry might take on its own initiative to facilitate license renewals and outlined the importance of research, experiments and learning from operating experiences.

He further stated that the industry's effort to understand and counter the effects of aging, to improve reliability. to reduce outages, and to lengther.

the life of components will contribut'e significantly to the future designs of nuclear power plants.

In the plenary session, following the Chairman's keynote address, G. A.

Arlotto, Director, DET, RES. delivered a speech entitled, " Understanding Aging

- A Key to Ensuring Safety." In his speech. Arlotto referred to the NRC's Policy and Planning Guidance (PPG) Document and stated how the PPG influences and provides guidance in the development of hardware- and technology- oriented research programs. He reiterated the high priority that the Comission places on operating reactors and discussed how a better understanding of aging would help the industry foresee potential safety problems and take appropriate action.

Arlotto's speech cited plant experiences with aging exemplified by pressure vessel embrittlement, degradation nf reactor coolant pressure boundary

, components (including steam generator tubings), and BWR piping. He reviewed how the results of preplanned research programs contributed to resolve some major aging-related issues assuring safety without incurring high costs that would have resulted from unnecessary plant shutdowns.

Arlotto then discussed the Nuclear Plant Aging Research Program and invited -

participation from all in the nuclear power plant comunity--within and outside the U.S. He concluded his speech by identifying the spin-off benefits of the aging research program which included new designs is, the evaluation of "mothballing" and de-mothballing" plants that are pre:. mtly inactive, plant lifetime extensions, and in establishing credibility ot ome equipment l qualification techniques. +

ENCLOSURE E JUL 2 61985

ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING JULY 26, 1985 l

l International Visitor On Thursday Mr. Riccardo Mueller of the Swiss Nuclear Safety Directorate, accompanied by Dr. Christian Risch, Science and Technology Counselor at the Swiss Embassy in Washington, visited IP to discuss fuel exports to Switzerland and different options related to Swiss participation in NRC's severe accident research program. J. Cortez, RES, participated in the discussion.

Visit of John Negroponte Ambassador John Negroponte, the designated Assistant Secretary of State l for Oceans and International Environmental and Scientific Affairs, met  !

with Chairman Palladino, Commissioner Bernthal, ED0 Dircks, and IP Director Shea on July 10. Ambassador James Malone, who has been serving l as OES Assistant Secretary, has been nominated to become U.S. Ambassador '

to Belize.

t t .

t ENCLOSURE G JUL 2 61985

OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING JULY 26, 1985 Indemnification of Spent Reactor Fuel at a Distant Reactor Location Duke Power Company has requested Commission authorization permitting Duke to store spent fuel discharged from its Oconee Units 1, 2 and 3 at its McGuire Unit 2 reactor. Duke is seeking Price-Anderson indemnity protection for all such storage of spent fuel at the distant reactor location. The Commission has decided to exercise its discretionary statutory authority under the Price-Anderson Act and extend Government indemnity to the storage of Oconee spent fuel at McGuire Unit 2. Absent this action by the Commission, this spent reactor fuel would not have been covered by Government indemnity in the event of a nuclear accident at the site where this spent fuel was stored and where the reactors involved have the same licensee.

Status of Low-Level Radioac'tive Waste Compacts Attached is a table of the legislative status of low-level radioactive waste compacts being negotiated under the Low-Level Radioactive Waste Policy Act of 1980.

e ENCLOSURE H JUL 2 61985

h INTERSTATE LOW-LEVEL RADI0 ACTIVE WASTE COMPACTS N LEGISLATIVE STATUS AS OF JULY 24, 1985 ,

a E Northwest Central Midwest Southeast Northeast Appalachian (S.356 (S. 655 (S. 899 (S. 44 H.R. 862) H.R. 1046) H.R. 2635) H.R. 1267)

Alaska - e Arkansas - e Indiana - e Alabama - e Connecticut - e Pennsylvania -i (1)

Hawaii - e Kansas - e Iowa - e Florida - e Delaware - e West Virginia - e Idaho - e Louisiana - e Michigan - e Georgia - e Maryland - e Montana - e Nebraska - e Minnesota - e Mississippi - e New Jersey - e Oregon - e Oklahoma - e Missouri - e North Carolina - e Washington, DC - p Utah - e North Dakota - p South Carolina - e Washington - e Ohio - e Tennessee - e Wisconsin - e Virginia - e Western Rocky Mountain Central - Midwest Dakota Unaffiliated States (S. 442 , (S. 802 H.R. 2702) H.R. 2062)

Arizona - e Colorado - e Illinois - e North Dakota - e Maine California - 1 Nevada - e Kentucky - x South Dakota - e (3) Massachusetts New Mexico - e New Hampshire

, North Dakota - e (4) NewYork(2)

Wyoming - e Rhode Island Texas (2)

Puerto Rico Ky Vemont Notes: Virgin Islands e - Enacted 1 - Introduced (1) Other eligible States are p - Has petitioned to join MD and DE.

x - Signed by Executive Order (2) Texas and New York are actively planning a site of their own.

9 (3) Also requires voter approval P in November 1985. ,

8 (4) Voted in as eligible by the Board E Prepared by Office of State Programs, NRC

] (301) 492-9880

OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEM 0F INTEREST WEEK ENDING JULY 26, 1985

AE0D Report on Medical Misadministrations for 1984 (AE0D/N503)

AEOD published a rev.iew of medical misadministration reports received in 1984. We found that the number of diagnostic misadministrations reported (412) was about the same as that reported in previous years and that the number of therapy misadministrations was higher than the number reported in both 1982 and 1983, but was comparable to that reported in 1981. We observed that two of the diagnostic misadministrations involved administra-tion of therapy doses to patients. These two diagnostic misadministrations were determined to be abnormal occurrences.

4 ENCLOSURE J JUL 2 ,61985

9 ITEMS ADDRESSED BY THE COPNISSION - WEEK ENDING JULY 26, 1985 A. STAFF REQUIREMENTS - PERIODIC MEETING WITH ADVISORY COMMITTEE ON REACTOR SAFEGUARDS (ACRS), 9:30 A.M., THURSDAY, JULY 11, 1985, COPNISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to Record dated 7/23/85 The Commission met with members of the Advisory Committee on Reactor Safeguards (ACRS) . The principal topics'for the meeting were "ACRS activities related to consideration of seismic events in emergency planning" and " safety goals."

Individual Commissioners had comments and questions for the ACRS members. However, no Commission requirements were issued at this meeting.

B. STAFF REQUIREMENTS MEMORANDUM - AFFIRMATION / DISCUSSION AND V0TE.11:30 A.M., THURSDAY, JdLY 11, 1985, COPNISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to H. H. E. Plaine dated 7/24/85 I. SECY-85-214 - Denial of Request for Rulemaking to Amend 10 CFR 7.9 The Commission, by a 4-0 vote, approved a Federal Register Notice denying a petition for rulemaking that proposed that the Commission amend 10 CFR 7.9 to allow appeals of closing ACRS meetings directly to the Commissioners. ,

You should forward the Federal Register Notice to the Secretary for signature and publication. ,

(OGC) (SECY Suspense: 7/31/85) 4 l l l

4 ENCLOSURE 0 JUL 2 61985

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E os NRR MEETING NOTICES * '

. c3 JULY 26, 1985 5

w DOCKET APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 7/29-30/85 50-416 Grand Gulf Site Discuss outage planning and Mississippi Power & L. Kintner Claiborne Cty., licensing actions at Grand Light Co.

Mississippi Gulf 1 7/30/85 50-309 P-110 To discuss Generic Fuel Loads Maine Yankee Atomic P. Sears Bethesda for Maine Yankee 7/30/85 50-440 Landow-208 To discuss changes to Chapt. 12 Cleveland Elec. Ill. J. Stefano 10:30 am 50-441 Bethesda of Perry FSAR 7/31/85 50-458 P-1000 To discuss staff comments on Gulf States Utilities S. Stern 10:00 cm Bethesda hydrogen control-degraded core for River Bend 7/31/85 AR-5033 Emergency Procedure Guidelines Combustion Eng. T. Greene 9:30 a2 Bethesda Owners Group l7/31/85 50-219 Oyster Creek To discuss status of licensing GPU Nuclear J. Donohew 10:30 am Site actions for the plant PLEASE BE ADVISED THAT DAILY RECORDING CAN BE HEARD ON 492-7166

• Ccpies 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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• u DOCKET APPLICANT /

DATE/ TIME NUMBER LOCATION -

PURPOSE ATTENDEES NRR CONTACT 7/31/85 50-305 Wisconsin Public To discuss integrated Wisconsin Public Serv. M. Fairtile 1;30 pm Serv. Corp. scheduling for Kewaunee Green Bay, Wisc.

-7/31/85 50-305 Essex Corp. Audit of Implementation Florida Power & Light D. Mcdonald 10:00 am 50-251 Alexandria, VA Methodology for Task Analysis ESSEX Upgrade Program-Turkey Point 8/1/85 50-354 P-118 To discuss proposed compression Public Service D. Wagner 9:00 cm Bethesda of Hope Creek Power Ascension Elec. & Gas Program ,

8/1/85 50-325/324 P-114 To discuss Brunswick Integrated Carolina Power & M. Grotenhuis 1:00 pm Bethesda Schedule Light Co.

8/6/85 P-422 Quarterly Meeting of EPRI Light EPRI D. Moran 1:30 pm Bethesda Water Reactor Steering AIF Committee 8/7/85 Room 144 To discuss status of licensing Niagara Mohawk Power M. Haughey 10:00 am Phillips Bldg. issues for Nine Mile Point 2 Bethesda 8/8/85 50-387/388 P-114 To discuss development of Pennsylvania Power M. Campagnone 10:30 am Bethesda transient analysis and core & Light Co.

PLEASE BE ADVISED THAT DAILY RECORDING CAN BE HEARD ON 492-7166

• Ccpies 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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r-co NMSS MEETING NOTICES e>

DIVISION OF WASTE MANAGEMENT July 24,1985 u

DOCKET ATTENDEES /

DATE/ TIME NUMBER LOCATION PURPOSE APPLICATION NRC CONTACT August 5-8 Austin, Texas Permian Basin Core ~ RJohnson ,WM RJohnson, WMRP Texas Bureau of Examination

• JTrapp,WM JTrapp, WMGT Economic Geology RLee WM Offices FWRoss WM WKelly,WM JPearring,WM DHedges ,WM EZurflueh,RES CHackbarth,RES GJacobs,0RNL

~

RWilliams, WA -

GWinter WA DBerry e' LMcKeague,LLL DCarpenter,LLL JImse,Weston

, BCummings,El i JDaemen ,El i

j *To familiarize the NRC staff with the data and data interpretations available to the DOE through TBEG, SWEC, and ONWI to support the preliminary conceptual models of the geologic conditions and processes in the fields of geology, hydrology and geochemistry in the area of the proposed high-level waste sites. Determine subject areas in which further interactions between DOE and NRC should be undertaken.

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c_ NHSS MEETING NOTICES

c5 , FOR WEEK ENDillG: 7/26/85

c. Division of TucI Cycle and Material Safety e, ,

as DOCKET , ATTENDEES /

DA$t/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 4 .

i 7/30-8/2/85 Chicago, IL Participate in NRC/ DOT Spent Nuclear Reps of D0T Cunningham/

Fuel Transportation Seminar. and States Cook J. Davis (NMSS)

R. Cunningham (FC)

L. Rouse (FC)

J. Cook (FC)

C. MacDonald (FC)

B. Thompson (FC) .

R. Odegaarden (FC) 7/29-7/30/85 70-143 Atlanta, GA Meeting with NFS and Region II. Reps of NFS and Soong Region II

! A. L. Soong (FC) 7/29-7/31/85 40-2061 Champagne, Meeting with ANL and State personnel Reps of ANL and IL to discuss information on geology and State 2

Kerr-McGee EIS. M. Horn (FC)

W. Nixon (FC) 7/29-8/2/85 70-1257 Richland, Environmental review for license WA amendment and accompany inspector Reps of Exxon Shum for onsite visit of Exxon plant. and Region E. Shum (FC)

K. Kodali (FC)

DIVISION OF SAFEGUARDS j None 1

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m DOCKET LOCATION ATTENDEES /

DATE/ TIME NUMBER PURPOSE APPLICANT NRC CONTACT' 8/5-8/85 Las Vegas, NV ' ASA Comittee on Nuclear Abramson Abramson Regulatory Research Joint Statistical Meeting P

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E r-3 to RII MEETING NOTICE G5 DOCKET ATTENDEES /

DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 7/29/85 RII Office Management Meeting Licensee, Regional Stohr 1:30 pm Nuclear Fuel Services, Inc. Administrator and to dicuss recent enforce- Selected HQs & RII ment actions Staff Members 7/30/85 Jackson, MS Meeting with representa- Licensee, Regional Walker 1:00 pm tives of MP&L for a Administrator and presentation of the Grand selected RII staff Gulf SALP report members 8/2/85 Chattanooga, Tour of TVA Corp. Office, Commissioner Bernthal, Walker Tennessee TVA Trng. Ctr., and members of his staff, Sequoyah Nuclear Facility and selected RII Staff members E

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o> REGION III MEETING NOTICES G5 0 * '

WEEK ENDING: Jtily 26,1985 DOCKET ATTENDEES /

DATE/ TIME NUPBER LOCATION PURPOSE APPLICANT NRC CONTACT

/6-7/85 No. Aurora, IL Resident Seminar Resident Inspectors J.G. Keppler & staff J.G. Keppler 5

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