ML20132E040

Weekly Info Rept for Wk Ending 850719

ML20132E040
Person / Time
Issue date:	07/24/1985
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-850719, NUDOCS 8508010587
Download: ML20132E040 (38)

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July 24,1985 For: The Comissioners i From: T. A. Rehm, Assistant for Operations, Office of thelfD0 ,

Subject:

WEEKLY INFORMATION REPORT - WEEX ENDING JULY 19, 1985 ,

A sumary of key events is included as a convenience to thos3 Comissioners who may prefer a condensed version of this report.

Contents Enclosure Administration A Nuclear Reactor Regulation . B t.,

Nuclear Material Safety and Safeguards ,

C Inspection and Enforcement f D Nuclear Regulatory Research , E Executive Legal Director F*

International Programs .- G f State Programs 1 H l Resource Management  !*

Analysis and Evaluation of Operational Data , J Small & Disadvantaged Business Utilization & Civil Rights K* /

Regional Offices -

L*

CRGR Monthly Report M* i Executive Director for Operations N*

s Items Addressed by the Comission 0 i '

s Meeting Notices Proprietary or Other Sensitive In' formation (Not for P }'

0 externaldistribution)

• No input this week. ,

M '

k C WEEKLYINF N

EPT PDN

. . e si Office of the Executive Director erations for Operations '

s ,

Contact:

T. A. Rehm. ED0 '

492-7781 ,

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a h* ,

' 'l HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING JULY 19, 1985 e

Rancho Seco Nuclear Generating Station The news media has reported that a local rancher has filed a 9.5 million dollar claim against SMUD for alleged damage to cattle and crops and for loss of property value in connection with discharges of liquid radioactive effluent from Rancho Seco. Earlier the licensee had purchased from the rancher 2 cows that were analyzed by Lawrence Livermore Laboratory (LLL) under contract to the licensee. The results of the analyses found concentrations of 69 pCi/kg and 56 pCi/kg of

, Cesium 137 and 14 pCi/kg and 17 pCi/kg of Cesium 134 in the 2 cows analyzed. Previous analyses of beef by LLL had indicated similar con-(' centrations of these nuclides. The measurable concentrations of Cesium 134 indicate that reactor operation may be a contributor to the presence of Cesium conca?trations in the cattle in the vicinity of the plant.

An adult consuming 110 kg of beef at the reported concentrations,would receive a maximum dose of about 0.8 mrem to the whole body.

Monitored Retrievable Storage (MRS)

Two staff members of NMSS/FC were observers at a MRS Program Review on July 17, 1985 presented by DOE to its peer review panel on the MRS project.

The status of the various elements of the MRS proposal being prepared for Congress were described, including the conceptual designs for the MRS for the proposed sites in Tennessee. Continued work on the MRS Need and Feasibility Report (a preliminary report was issued by DOE in late April when the proposed MRS sites w+ra announced) includes input from a task force of MRS and repository projects' personnel to consider interactions of the integral MRS concept w'th the repository.

The MRS proposal is to be delivered to Congress by January 15, 1986. The

- proposal will be provided to NRC and EPA by December 2, 1985; any comments on the proposal by NRC and EPA are to be submitted to Congress by DOE with the proposal. In addition to the peer panel and DOE staff from Headquarters, Richland and Oak Ridge, DOE contractor personnel from PNL, Westinghous, Golder Associates and Weston were present.

Accident Management Procedures On July 19, 1985, RES and its contractor, INEL, met with TVA corporate management to discuss the possibility of conducting a study of the effectiveness of accident management procedures in reducing risks due to severe accidents. The proposed study would use the recently conpleted

' Brown's Ferry PP.A. Sandia containment event trees and BCL source tems.

TVA management,sppecred receptive and saw some potential advantages in tems of developing cost-effective risk reduction measures and in permitting i the Browns Ferry PRA to be compared with the Peach Bottom surrogate, as a possible approach to the Severe Accident Policy application. One,of the

- principal issues to,b? resolved is the availability of TVA resourdes. Neither RES nor TVA would be willing to conduct the study until there is reasonable assurance that adequate technical support is available.

JUL 101985 4

Q OFFICE OF ADMINISTRATION Week Ending July 19, 1985 ADMINISTRATION OF ThE FREEDOM OF INFORMATION ACT f STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1984 179 23 Received, 1985 508 29 Granted 392 23 Denied 97 11 Pending 198 18 ACTIONS THIS WEEK Received Jim Pedro, Request for a copy of a March 15, 1985, OIA report NUS Corporation regarding the March 11, 1985, Regulatory Reform Task (85-492) Force Report on Backfitting and Licensing.

Jay E. Silberg, Request for copies of SECY-85-80, SECY-85-208, and Shaw, Pittman, the transcripts of any NRC meetings at which these Potts & Trowbridge SECY papers were discussed.

(85-493)

Nina Bell, Request for a list of the nuclear power plants visited Nuclear Information in the course of developing NUREG/CR-3817 and a list and Resource of plants for which written maintenance procedures were Service reviewed and evaluated.

l (85-494)

Michael O'Mealia, Request for a copy of NRC Regulatory Guide 3.

Doc-Search Associates (85-495) l

( Stanley Nowicki, Request for copies of all of the Blue Book (NUREG-0580) j O'Brien - pages for the San Onofre Units 2 and 3 for the years Kreitzberg & 1977, 1978, and 1979.

Associates (85-496) l l Jim Pedro, Request for copies of the papers presented at a 3-day i NUS Corporation workshop on seismic component fragility held at the (85-497) Brookhaven National Laboratory.

CONTACT: J. M. Felton 492-7211 ENCLOSURE A JUL 191985

Received Cont'd Steven Sholly, Request for a copy of a Battelle report referenced in Union of Concerned Chapter 10 of the PRA report on Oconee Unit 3.

Scientists (85-498)

(AnNRCEmployee) Request for copies of all records related to a July 10, (85-499) 1985, memorandum by James G. Keppler.

Gloria L. Miller, Request for a copy of the proposal submitted by Battelle Columbus Westinghouse Corporation in response to RFP Laboratories RS-RES-85-103.

(85-500)

Clyde D. Morell, Request for records reflecting by Region (1) NRC Quality Service contracts for consulting services for 1981 through 1984 Associates Inc. to small business, 8A Setaside, and non-solicited 4

(85-501) emergency awards, (2) contract amounts for contractors l and subcontractors for 1981 to the present, and (3) the project budget for 1985 and 1986 for 8A setaside

and small business contracts.

Anthony L. Kimmery Request for three categories of records regarding (85-502) Kerr-McGee, and NRC's regulations or radiation exposure and nuclear fuel cycle processing facilities.

Steven C. Sholly, Request for copies of two specified 1984 EG8E reports Union of Concerned on the Bellefonte and Seabrook plants.

Scientists (85-503)

Martin Levy, Request for all records regarding the rules for

- NTEU Chapter 208 obtaining free parking at the Nicholson Lane Building -

(85-504) or all records used in the past by the NRC management in determining the allocation of free parking spaces, and records which have changed the rules.

Richard A. Gaffin, Request for ten categories of documents regarding Miller, Canfield, General Electric's " Reed Report."

Paddock, and Stone (85-505)

(An NRC Employee) Request for three categories of records related to (85-506) Vacancy Announcement No. 85-2103-8.

ENCLOSURE A g

Received Cont'd Linda Smith, Request for a copy of SECY-84-13B, "NRC Integrated S. Levy Program for the Resolution of Steam Generator USI's --

Incorporated Response to Commissioner Coments (Memo from Chilk to (85-507) Dircks dated September 13,1984)."

Lyle Graber, Request for copies of NUREG/BR-0073 (Project Manager's NUS Corporation Handbook) and SECY-85-80.

(85-508)

Granted Lynn Connor, In response to a request for information regarding NRC Information Harold Denton's and Bill Russell's trips to Japan, Service made available eight documents.

(84-279)

Ray Belew, Jr. , In response to a request for copies of records Star-News pertaining to Vera English's allegations regarding Newspapers General Electric Company's facility in Wilmington, (85-176) North Carolina, made available one record. Informed the requester that additional records subject to his request are already located in the PDR.

Arthur F. Green. In response to a request for a copy of NRC license Radiac Research 20-20795-01 issued to HMM Associates in Concord, Corporation Massachusetts, and all available information on the (85-415) license, made available three records. Infomed the requester that five additional records are already available in the PDR.

David R. Ennis, In response to a request for copies of Examination NUS Corporation Results Summary Sheets for eleven listed nuclear (85-442) power plants, made available nine records. Informed the requester that additional records subject to his request are already located in the PDR.

Leonard I. Hellman, In response to a request for a copy of the mailing The Keenan list for IE Information Notices issued by the Division Corporation of Emergency Preparedness and Engineering Response, (85-450) made available the requested mailing labels.

William S. Phillips, In response to a request for a list of waste generators Stock Equipment for 1984, made available the requested computer printout.

Company Infomed the requester that additional records providing (85-459) the desired information are already located in the PDR.

Walter L. Robinson, In response to a request for a copy of a policy directive Walter L. on the Lixiscope, made available the requested record.

Robinson &

Associates (85-471)

ENCLOSURE A JUL 191985

Granted Cont'd James N. Gillman, In response to a request for records containing the Blue Cross and names of all employees, their position titles, grade Blue Shield levels, and work locations, made available one record.

Association Informed the requester that an additinal record is (85-472) available from the Government Priting Office. t Phyllis D. Swecker, In response to a request for a record of financial The Conservative and technical assistance awards made during Fiscal Caucus Foundation, Year 1984 in connection with NRC project grants listed Inc. under Program 77.033 in the " Catalog of Federal (85-474) Domestic Assistance," made available one record.

Donald L. Schlemmer, In response to a referral from the Department of State Government for a disclosure determination on three documents Accountability regarding the Philippine Nuclear Power Plant Unit Project No. 1, made available two documents. Informed the (85-475) requester that the additional record subject to his request is already located at the PDR.

Tom Kalitowski, In response to a request for a current listing of Governor's technical contractors in the earth sciences and Task Force on geohydrology fields that may be available for high-level High-Level radioactive waste disposal work, made available the Radioactive requested record.

Waste (85-479)

Clifford A. Beck, Jr. In response to a request for a copy of the list of free (85-484) NRC publications which is mentioned in NRC's " Citizen's Guide to U.S. Nuclear Regulatory Comission Information,"

made available the requested record.

Jennifer Epps In response to a request for a list of all current NRC (85-488) contracts, made available the requested computer printout.

Denied Bahar Gidwani, In response to a request for information on s:tes in Kidder, Peabody & the U.S. involved in commercial irradiation of n Mical Company instruments, wood and wood flooring, consumer products, (84-705) food and spices, and information on any accident or safety violation of these facilities from 1974 to the present, made available 182 documents. Denied portions of one document, disclosure of which would reveal confidential business proprietary information.

Stevi Stephens, In response to a request for copies of four. categories Nuclear Awareness of documents regarding the Wolf Creek Nuclear Generating Network Plant, made available 55 documents. Informed the (85-161) requester that 12 additional documents are already publicly available at the NRC's Public Document Room.

Denied portions of 27 documents and denied 15 documents JUL 191985 in their entirety pursuant to Exemptions (5), (6), ENCLOSURE A (7)(A),and(7)(C),and(7)(D).

Denied Cont'd Nina Bell, In response to a request for documents pertaining to Nuclear Army Corps of Engineers and NRC analyses of the Information and potential for a debris dam blocking the natural outlet Resource Service of Spirit Lake and affecting the Trojan nuclear power (85-353) plant and the current status of the permanent tunnel the Corps proposed to install, made available 114 documents.

Informed the requester that 21 additional documents are already publicly available at the NRC's Public Document Room. Denied portions of two documents, disclosure of which would constitute a clearly unwarranted invasion of personal privacy.

ENCLOSURE A U 1 9 1985

WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING JULY 19, 1985 PROPOSALS UNDER EVALUATION ,

RFP No.: RS-01E-85-163

Title:

" Emergency Response Data System Requirements Analysis"

Description:

The purpose of this project is to provide the NRC with the information necessary to commence implementation of an Emergency Response Data System (ERDS) capable of providing electronic transmission of a limited data set from any licensed nuclear power plant during an emergency. The Contractor will survey the plants to determine the range of electronic data formats, validation conventions, and update frequencies which must be accommodated by the receiving system at the operations center.

Period of Performance: One year Sponsor: Office of Inspection and Enforcement Status: RFP closed on July 12, 1985. Proposals forwarded to Source Evaluators for review on July 15, 1985. Competitive range to be established on August 21, 1985.

RFP No.: RES-85-106

Title:

Piedmont Seismic Reflection Study

Description:

Select a specific seismological problem related to the Southern Piedmont, design a program of seismic reflection and other geographical investigations, execute the program & interpret the resulting data. The information gathered is to be used to advance the state of knowledge on possible causes of seismicity in the Piedmont of Virginia and the Carolinas, particularly with respect to structure at hypocentral depths.

Period of Performance: 2 years with additional one year option Sponsor: Office of Nuclear Regulatory Research Status: Best and Final offers received on July 17, 1985 and forwarded to Source Evaluators for review on July 17, 1985.

RFP No. : NMS-85-007

Title:

" Facility Systems Analysis Support"

Description:

Provide technical support in the form of reports, analytical, and engineering expertise to fully implement the regulatory effectiveness review program for all power plants.

Period of Performance: 24 months Sponsor: Office of Nuclear Material Safety and Safeguards Status: Best and Final offers received on July 17, 1985, and forwarded to Source Evaluation Panel for review on July 18, 1985.

ENCLOSURE A JUL 191985 l

Division of Contracts Weekly Information Report CONTRACT AWARDED RFP No. : ADM-85-234

Title:

" Photographic Reproduction Services"

Description:

Provide processing and printing of negatives and production of slides.

Period of Performance: 24 months Sponsor: Office of Administration Status: Fixed Price Requirements contract awarded to SBA/ Domus Design Studios in the amount of $59,166.25 effective July 2,1985. This firm has been certified by the Small Business Administration as a socially and economically disadvantaged firm eligible for noncompetitive awards under that agency's 8(a) program.

CONTRACTS CLOSED-00T NRC-04-79-203 ANCO NRC-03-82-ll2 Department of Commerce NRC-03-79-167 Army-Corp of Engineers ADMINISTRATIVE MATTER Two protests were received on June 28, 1985, under IFB No. RS-ADM-85-252 for "Micrographic Services of Source Drawing Documents." The first protest was filed with SBA and the second protest was filed with GA0.

This solicitation was totally set aside for small business participation.

Both protestors allege that the apparent low bidder is ineligible for award as he does not qualify as a small business under the applicable size standard.

On July 9,1985, verification of the apparent low bidder's status as a large business concern was received. Accordingly, the bid was rejected as nonresponsive to the small business provision of the solicitation.

Both protestors have withdrawn their protests as the apparent low bidder was determined to be ineligible for award.

t l l ENCLOSURE A i JUL 191985 l l

0FFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending July 19, 1985 Waterford 3 On July 11, 1985, the Atomic Safety and Licensing Appeal Board issued ALAB 812. This order denied the Joint Intervenor's November 8,1984 motion to reopen the record for Waterford 3 concerning QA, management integrity and NRC resolution of allegations in all respects save where the issues related to ongoing OI investigations. To that extent, the motion was referred to the Commission. This motion was the last matter pending before the Appeal Board in the Waterford operating license proceeding.

Shoreham OnJgly 10, 1985, while the Shoreham plant was operating at 2% power (360 F and 140 psig), the licensee decided to purge the containment so as to reduce the high concentration of carbon monoxide (approximately 75 ppm) in order to permit personnel entry for maintenance. The operator mistakenly opened the 18-inch primary containment purge valves, which is a Technical Specification violation, instead of the smaller (4 to 6 inch) purge valves. The Technical Specifications require these 18-inch valves to be sealed closed during operating Modes 1, 2, and 3.

The Limiting Condition for operation, however, requires that if these

, valves are opened, they must be closed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. These 18-inch valves remained open for a little over two hours. ~

Rancho Seco Nuclear Generating Station The news media has reported that a local rancher has filed a 9.5 million dollar claim against SMUD for alleged damage to cattle and crops and for loss of property value in connection with discharges of liquid radioactive effluent from Rancho Seco. Earlier the licensee had purchased from the rancher 2 cows that were analyzed by Lawrence Livermore Laboratory (LLL) under contract to the licensee. The results of the analyses found concentrations of 69 pCi/kg and 56 pCi/kg of Cesium 137 and 14 pCi/kg and 17 pCi/kg of Cesium 134 in the 2 cows analyzed. Previous analyses of beef by LLL had indicated similar con-centrations of these nuclides. The measurable concentrations of Cesium 134 indicate that reactor operation may be a contributor to the presence of Cesium concentrations in the cattle in the vicinity of the plant.

An adult consuming 110 kg of beef at the reported concentrations would receive a maximum dose of about 0.8 mrem to the whole body.

• ENCLOSURE B JUL 191985

Rescission of February 11, 1980 Orders for the Indian Point Nuclear Generating Unit Nos. 2 and 3 On February 11, 1980, certain interim measures were imposed by Order on Consolidated Edison and the Power Authority of the State of New York that were intended to significantly increase the level of safety at the Indian Point Station. Following five years of special proceedings the Commission decided the February Order did not significantly increase the safety as intended. Therefore, on July 5,1985, the February 11, 1980 Orders for the Indian Point Nuclear Generating Unit Nos. 2 and 3 were rescinded in accordance with Commission's Decision CLI-85-06 dated May 7,1985 for all items not required to meet generic concerns or other licensing commitments for the Indian Point Units.

Fermi-2 Operating License NPF 43 for Fermi-2 was issued to Detroit Edison Company on July 15, 1985. The license authorizes operation at reactor core power levels of 3292 megawatts thermal (100% power).

Completion of power ascension testing and subsequent commercial operation is currently scheduled for late 1985.

Wolf Creek At 11:00 p.m. on July 15, 1985 Kansas Gas & Electric completed the start up testing required at 50% power and carried out a successful shutdown from outside of the control room.

The schedule for the remaining start up testing program is as follows:

75% power tests 7/17 - 7/24 90% power tests 7/24 - 7/29

. 100% power tests 7/29 - 8/16 The fuel load and low power license was issued on March 11, 1985 and the full power license was issued on June 4,1985.

Farley 1/2 Tendon Anchor Replacements This is a status update of prior Highlights issued on February 22 and 27, and April 18, 1985 relating to failures of containment tendon anchors at Farley 2 and subsequent cracks found on Unit I lower vertical anchor heads. Action to date includes:

(1) Report of the first tendon failure on Unit 2 was made by Alabama Power Company on January 28, 1985. One vertical tendon was found detensioned during surveillance tests of the containment building.

Two other anchors were found in a partially failed condition.

ENCLOSURE B JUL 191995

(2) Restoration on Unit 2 was completed on April 16, 1985. In addition to the three failed anchors, seventeen anchors failed magnetic partical tests and were replaced.  ;

(3) Inspections started on Unit I during the refueling outage on April 5, 1985. Six anchors failed magnetic particle tests and were replaced. Restoration on Unit I was completed on June 10, 1985.

The following tabulates the completed tendon anchor inspections and/or replacements on Unit 1 and Unit 2:

Tendon Total Unit 1 Unit 2 Type Each Unit Inspected Replaced Inspected Replaced Vertical 130 130 6 130 20 Hoop 135/134* 28 0 73 0 Dome 93 29 0 46 0

• Unit 2 has one less hoop tendon.

VEPC0 Quality Work Crew Concept Surry and North Anna Power Plants On July 16, 1985, VEPC0 presented a new concept for maintenance related work to be implemented at the Surry and North Anna Power Stations. The purpose of the " quality work crew concept" is to provide the work conditions where high quality maintenance is safely performed by craftsman (mechanics, electricians, etc.) without the involvement of additional support staff or follow-up inspection. The goal of the program is to: (1) increase quality of work, (2) increase productivity, (3) decrease radiation exposure, and (4) improve the morale and employee satisfaction of the trade craft employees.

The Quality Maintenance Team will perform its own inspections (not the team member performing the work). Also, the team performs its own radiological control function. Team members will receive advanced radiation worker training. In essence - quality is built in - not inspected in.

A pilot crew comprising a mechanical foreman and six mechanics will initiate the new concept at the Surry facility during the Sumer (1985) and in the Fall (1985) at the North Anna facility. The concept is new to the nuclear industry in the U.S. In addition, VEPC0 is sending the pilot crew to Japan to observe at first hand maintenance at Japanese nuclear facilities which is similar to VEPC0's new concept.

• ENCLOSURE B JUL 191985

Turkey Point Plant Units 1 & 4 By memorandum dated March 22, 1985, the Executive Legal Director informed the Directors of NRR, IE and NMSS of the Supreme Court's decision in Case No.83-703, Florida Power and Light Co. vs. Lorion (March 20, 1985). The case was tTi result of a Section 2.205 petition denial by Harold Denton in 1981. The District of Columbia Court of Appeals had decided that it lacked jurisdiction to review the Section 2.206 denial. Details of the Supreme Courts decision and impacts are provided in the above referenced memorandum.

By Order dated July 12, 1985, the District of Columbia Court of Appeals indicated that the case had been remanded to them by the Supreme Court and the merits of the petition for review remain to be addressed by the Court of Appeals. The Order indicated that supplemental briefs shall be filed as follows:

Petitioner's brief (Lorion) August 6, 1985 Respondent's brief (NRC) September 3,1985 Intervenor's brief (FPL) September 18, 1985 Petitioner's reply brief (Lorion) September 30, 1985 Joint appendix, if necessary October 10, 1985 The case initially addressed steam generator and Pressurized Thermal Shock (PTS) concerns. The steam generators are a moot issue due to having been replaced. The supplemental briefs will address the PTS Concerns.

Three Mile Island - Unit 2 GPU Nuclear Corporation announced on July 17, 1985, that the schedule (September 1985) for commencement of defueling of the THI-2 reactor has slipped by several weeks. The licensee does not expect to start defueling until October 1985. The schedule slippage is due to delays in the delivery of fuel storage canisters, fuel storage racks, and canister handling equipment from Nuclear Energy Services, the equipment supplier. The delay is the result of deficiencies in the vendor's implementation of their quality assurance program. The deficiencies were identified by NRC Vendor Programs Branch inspection and by GPU Nuclear and Bechtel audits of the vendor. A QA hold has been placed on the equipment pending resolution of the deficiencies.

Limerick On 7/17/85 ASLB hearings on two issues concerning emergency planning evacuation for the inmates at the State Correctional Institute at Graterford (8 miles from Limerick) were concluded and proposed findings were filed. A decision by the Board is expected in the near future.

ENCLOSURE B JUL 191985

- On 7/16/85 the staff was informed that administrative law judges for the Pennslyvania PUC had advised the PUC that construction of Unit 2 should not be continued beyond its present 30% complete. A decision by the PUC is not expected for 3 to 6 months.

Beaver Valley Unit No. 1 On July 17, 1985, while performing the required monthly surveillance tests on Diesel Generator (DG) No.1, operators discovered that it can only deliver 390kw. (Technical-Specification requires that it can be loaded to greater than 1425kw, and it is designed to deliver 2850kw.)

Upon investigation, it was discovered that the power limit switch in the governor has been set at 3 instead of 10, which would correspond to the maximum possible power of 2850kw.

The DG room is a security area. The last DG test was performed on June 19, 1985. Thus, the No. 1 DG could have been in a degraded mode of readiness for as much as a month. License personnel are continuing with their investigation of this matter, but at this time the cause of the problem cannot be ascertained. No additional information is available.

All information is based on conversations with Region I, ORAB and licensee personnel.

l

,l ENCLOSURE B JUL 191985 1

NRC TMI PROGRAM 0FFICE WEEKLY STATUS REPORT WEEK ENDING JULY 19, 1985

1. PLANT STATUS

- The facility remains in long term cold shutdown with the Reactor Ccolant System (RCS) vented to the reactor building atmosphere and the reactor vessel head and plenum assembly removed. .

The reactcr 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 feet 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 92 F with an average of 81*F. Average cold leg temperature is 60*F.

The average reactor building temperature is 60"F. The reactor building airborne activity is 2.3 E-7 uCi/cc tritium, and 1.5 E-10 uti/cc particulate, predominantly cesium 137.

2.' WASTE MANAGEMENT The Submerged Demineralizer System (SDS) commenced processing batch S123 consisting of 25,745 gallons from the "C" reactor coolant bleed i

tank. EPICOR 11 completed processing batch 260 consisting of 5,324

gallons from SDS tank 1B.

2 Total volume processed through SDS to date is 2,939,092 gallons, and the total volume processed through EPICOR II is 2,505,311 gallons.

< ENCLOSURE B JUL 191985

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 Agreerent.

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 June 29, to July 6, 1985. Gamma scans detected no reactor related radioactivity.

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 June 30, to July 6, 1985 and July 7 to July 13, 1985. A gamma scan detected no reactor related radioactivity.

The NRC outdoor airborne particulate sampler at the TMI Site collected a sample between July 11, and July 18, 1985. No reactor related radioactivity was detected. Analysis showed I-131 and Cs-137 concentrations to be less than the lower limits of detectability.

5. REACTOR BUILDING ACTIVITIES Additional characterization of the reactor vessel lower head was performed during the week of July 14, 1985. The characterization '

included: water sampling in the lower head and annulus regions to compare chemical properties for homogeniety, additional video inspections in two icwer head quadrants which had not been examined previously, and sampling of debris in the lower head. The scheduled activities were completed in one of the two quadrants and the analysis of results is in progress. Solid debris samples will be sent to the INEL (Idaho National Engineering Laboratory) for study.

Inspection of the second quadrant is scheduled to start Monday, July

. 22, 1985.

Preliminary data indicates that boron concentrations, as well as other chemical and physical water properties in the lower head area, are consistent with those elsewhere in the vessel and that the ruoble bed in the newly viewed area generally consists of smaller particles than previously seen in other areas.

ENCLOSURE B JUL 191965

3 Next week, reactor defueling preparations will dominate the scheduled activities in the reactor building. The defueling platform will be assembled and installed above the internals indexing fixture in conjunction with the trolley on the dabris canister transfer bridge. The starting date for initial defueling has been revised from September to October 1985.

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.

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 Nuclear Energy Services (NES) facility in Greensboro, North Carolina, where the fuel storage canisters, fuel. storage racks, and fuel canister transfer shields are being fabricated. The inspection examined construction activit~ies 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 used in a few weeks.

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

9. PUBLIC MEETING On July 18, 1985, the Advisory Parel for the Decontamination of Three Mile Island Unit 2 held a public meeting at the Public Safety Building in Lancaster, Pa. The Panel received a status report on the cleanup by GPU Nuclear Corporation, including an announcement that the scheduled commencement of defueling has been changed from September 1985 to October 1985 due to equipment procurement and delivery delays.

Dr. William Travers, Deputy Program Director, TMIPO, NRR, provided a status report on NRC activities required to be completed. prior to the commencement of defueling. Dr. William Kirk, Director, TMI ENCLOSURE B JUL 191985

/.

4 Field Station, EPA, described the upgraded aquatic radiological monitoring program in the vicinity of the TMI site; and Mr. Frank Congel, Chief, Radiological Assessment Branch, NRC, summarized the results of a staff review of health effects studies conducted in the vicinity of TMI-2 as a result of the f: arch 1979 accident. The next meeting of the Advisory Panel is scheduled for September 1985 at a location in Annapolis, Maryland, to be identified later.

0 S

e ENCLOSURE B JUL 191985

OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending July 12, 1985 Near Term NRC Actions Under the Nuclear Waste Policy Act Section: 114(e) of NWPA Action: NRC transmitted comments to DOE on the preliminary draft Project Decision Scheudle on March 4, 1985.

Status: NRC is expecting to receive the DOE draft PDS by July 19, 1985.

Review and comments are due by September 13, 1985. The final PDS is expected in November, 1985.

Section: 301 of NWPA Action: NRC submitted 21 objections plus comments on the DOE draft Mission Plan on July 31, 1984.

Status: The final 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), stating that they (D0E) "did not revise the Mission Plan to meet the NRC objection concerning the timing of the preliminary determination, objection number five," and reasons why. The Mission Plan has created much Congressional interest. Ben Rusche, Director, Office of Civilian Radioactive Waste Management at DOE will meet with the Commission on July 29, 1985 to discuss NRC's view of the Mission Plan.

Monitored Retrievable Storage (MRS)

Two staff members of NMSS/FC were observers at a MRS Program Review on July 17,1985 presented by DOE to its peer review panel on the MRS project.

The status of the various elements of the MRS proposal being prepared for Congress were described, including the conceptual designs for the MRS for the proposed sites in Tennessee. Continued work on the MRS Need and Feasibility Report (a preliminary report was issued by DOE in late April when the proposed MRS sites were announced) includes input from a task force of MRS and repository projects' personnel to consider interactions of the integral MRS concept with the repository.

NCLOSURE C JUL 101985

The MRS proposal is to be delivered to Congress by January 15, 1986. The proposal will be provided to NRC and EPA by December 2, 1985; any comments on the proposal by NRC and EPA are to be submitted to Congress by DOE with the proposal. In addition to the peer panel and DOE staff from Headquarters, Richland and Oak Ridge, DOE contractor personnel from PNL, Westinghous, Golder Associates and Weston were present.

Nuclear Fuel Services (NFS)

On July 16, 1985, a meeting was held with representatives from NMSS, Region II, and NFS. The meeting was requested by NFS to present a revised plan for starting up additional operations using salaried personnel.

Update on Chicago Seminar on Spent Nuclear Fuel Transportation The NRC and the Department of Transportation are jointly sponsoring a seminar for State officials who have been designated to handle spent fuel transportation matters. The seminar will be held in Chicago from July 31 through August 2, with representatives from the 48 contiguous states plus the District of Columbia. In addition to the State's designated representative, for whom NRC is paying travel costs, most states are sending additional delegates at their own expense. A number of State legislators will be attending. The meeting was recently announced in the Federal Register (50 FR 27867), and to date, the responses from the states and others indicates a total attendance of 250 to 300.

The seminar agenda, which is being put into final form this week, emphasizes topics dealing with the division of responsibilities between Federal agencies, with the description of regulatory requirements, and with the discussion of

_ issues of particular interest to state and local governments and to Indian tribes.

ENCLOSURE C JUL 191985

OFFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending July 19, 1985

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

week:

a. EN 85-51, a Notice of Violation and Proposed Imposition of Civil in the amount of $100,000 was issued July 12, 1985 to Toledo Penalty Edison (Davis-Besse). This action is based upon three violations.

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

a. PNO-I-85-49, Vermont Yankee Nuclear Power (Vermont Yankee), Informational Picket.

b. PN0-I-85-50, Northeast Utilities (Millstone Unit 2), Unplanned Reactor Scram.

c. PN0-I-85-51, Duquesne Light Company (Beaver Valley, Unit 1), Potential Tampering with Diesel Generator,

d. PN0-II-85-66, U.S. Pipe and Foundry Company (Bessemer, AL), Contami-nation Detected in Scrap Area.

e. PNO-II-85-67, Duke Power Company (McGuire Unit 2), Unscheduled Shutdown Longer Than 48 Hours.

f. PNO-II-85-58A, Detroit Edison (Fermi Unit 2), Inadvertent Criticality (Update).

g. PN0-III-85-56, Department of Army (Rock Island IL), Fire in South Korea Involving U.S. Army Weapons Sights Containing Promethium 147.

h. PN0-III-85-57, Wisconsin Electric Power (Point Beach), Discharge of Firearm by Security Officer.

i. PNO-III-85-58, Detroit Edison Company (Fermi Unit 2), Inadvertant Criticality.

j. PNO-III-85-58A, Detroit Edison (Fermi Unit 2), Inadvertent Criticality (Update).

k. PN0-III-85-59, American Electric Power Company, Indiana Michigan Electric Company (D.C. Cook Unit 2), Shutdown to Investigate Steam Generator Tube Leakage.

1. PN0-III-85-60, Commonwealth Edison Company (LaSalle Unit 1), Shutdown for Valve Maintenance.

ENCLOSURE D JUL 191985 1

m. PN0-IV-85-31, Kansas City Gas and Electric Company (Wolf Creek),

Update to PN of July 11, 1985 - Feedwater Control Problems.

n. PN0-IV-85-32, McClellan Engineers, Inc. (Little Rock, AK), Theft or Loss of Radioactive Material.

o. PNO-IV-85-33, Arkansas Power and Light Company (Arkansas Nuclear One), Arkansas Power and Light Funding of Grand Gulf,

p. PNO-IV-85-34, Nebraska Public Power District (Cooper), Hospitalization of On-Coming Shift Supervisor.

q. PNO-V-85-44, Exxon Nuclear Company Inc. (Richland, WA), State of Washington Suspension of Exxon Nuclear Company's Permit for Radio-active Waste Burial.

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

s. PNS-V-85-03, GA Technologies, Inc. (San Diego, CA), Missing Security Detector Check Source.

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

a. IE Information Notice 85-53, Performance of NRC-Licensed Individuals While on Duty was issued July 12, 1985 to all nuclear power reactor facilities holding an operating license or a construction permit.

b. IE Information Notice 85-54, Teletherapy Unit Malfunction was issued .

July 15, 1985 to all licensees authorized to use teletherapy units.

c. IE Information Notice 85-55, Revised Emergency Exercise Frequency Rule was issued July 15, 1985 to all nuclear power reactor facilities holding an operating license or a construction permit.

d. IE Information Notice 85-56, Inadequate Environment Control for Components and Systems in Extended Storage or Layup was issued July 15, 1985 to all nuclear power reactor facilities helding an operating license or a construction permit.

e. IE Information Notice 85-57, Lost Iridium-192 Source Resulting in the Death of Eight Persons in Morocco was issued July 16, 1935 to all licensees that possess, use and manufacture radiographic exposure devices with sealed radiation sources.

f. IE Information Notice 85-58, Failure of a General Electric Type AK-2-25 Reactor Trip Breaker was issued July 17, 1985 to all nuclear power reactor facilities designed by Babcock and Wilcox Company, and Combustion Engineering, and holding an operating license or con-struction permit.

ENCLOSURE D JUL 191985

g. IE Information Notice 85-59, Valve Stem Corrosion Failure was issued July 17, 1985 to all nuclear power reactor facilities holding an operating license or construction permit.

h. IE Information Notice 85-60, Defective Negative-Pressure, Air-Purifying Full Facepiece Respirators was issued July 17, 1985 to all nuclear power reactor facilities holding an operating license or a construction permit, research and test reactors, fuel facilities, and certain material licensees.

4. Other Items

a. Seminar - Maintenance and Modification Activities on Operating Plants Director, IE was in Tarrytown, NY on July 17, 1985 to participate in a utility seminar focusing on maintenance and modification activities in operating plants.

b. Resident Meeting Branch Chief and a representative of the Operating Reactors Programs Branch, Division of Inspection Programs, participated in a Region V Resident meeting July 15-19, 1985.

c. Regional Assessment A representative of the Safeguards and Materials Programs Branch, Division of Inspection Programs, was on an assessment inspection this week of uranium mills at Casper and Riverton, WY, accompanying a Region IV inspector and at the Denver Office.

d. Employee Concerns Program A representative of the Reactor Construction Programs Branch, Division of Inspection Programs, assisted Region II and NRR in the review of Employee Concerns Programs at TVA's Watts Bar site during July 15-19, 1985.

e. Civil Penalties Paid On July 11, 1985, payment in the amount of $50,000 was received from Duke Power Company (McGuire) for enforcement action (EA 84-130) relating to a violation involving an inoperable upper head injection system.

ENCLOSURE D JUL 191985

t

f. FEMA Workshop Representatives of the Incident Response Branch, Division of Emergency Preparedness and Engineering Response, served as instructors to the FEMA Workshop on Emergency Response held in Emmitsburg, MD on July 15-17, 1985.

g. Reactor Operation Events Meeting Representatives of the Engineering Generic Communications Branch, Division of Engineering Preparedness and Engineering Response, participated in a meeting on reactor operational events with INP0.

The meeting was held in Atlanta on July 18, 1985. The EGCB personnel presented data on HPCI and RCIC system reliability.

h. Program Development In the area of program development, four inspection procedures (IPs) from the 2515 program (operating reactors) were sent for issuance.

Two of these IPs deal with inspection of equipment calibration and calibration of measuring and test equipment. The remaining two deal with preparation for refueling and refueling activities. The latter two IPs were significantly revised to emphasize the inspec-tion of the licensee's controls for the conduct of refueling operations, establishing and maintaining plant conditions for refueling; and implementation of these controls.

i. J. C. Haynes Chief. Safeguards Materials Programs Branch, Division of Inspection Programs, accompanied Region III staff on a visit to J. C. Haynes Company in Columbus, OH, July 18, 19, 1985.

j. INP0 Representatives of Engineering and Generic Communications Branch, Division of Emergency Preparedness and Engineering Response, parti-cipated in a meeting on reactor operational events with INP0 in Atlanta, GA on July 18, 1985. Report data on HPCI and RCIC systems reliability was presented by these personnel.

N OM D JUL 191985

.s. . .. -. .. . . ..

OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending July 19, 1985 RELAPS/SCDAP Integration and Applications RELAPS/SCDAP is an integrated code in which the RELAP5 thermal-hydraulic code is dynamically linked with the SCDAP severe core damage analysis code. The TRAP-MELT code for fission product transport and deposition is included in RELAP5/SCDAP as a module. RELAPS/SCDAP is designed for simulating severe '

accidents prior to vessel failure in the reactor coolant system of an LWR. The PWR portion of the code is operational and is currently running on a CRAY machine in Albuquerque, New Mexico. The BWR portion of the code will be com-pleted by September 1986. INEL will continue code assessment and subsequent improvement in 1986. RELAP O/SCDAP was r6,cently used to make a pretest prediction for the LOFT FP-2 test in which the center fuel bundle was intentionally damage with fuel rod temperature exceeding the clad melting point (around 3500*F). The code predicted the time-dependent peak clad temperature in the center fuel bundle as well as in the peripheral fuel bundles.

Implementation of the MELPROG Code by the United Kingdom The MOD 0 version of the new MELPROG mechanistic in-vessel core-melt progression code has been implemented by the United Kingdom Atomic Energy Authority staff at Winfrith on the CRAY facility at Harwell under our bilateral agreement in the international Severe Fuel Damage research program. The Winfrith and Culham staffs are testing the code and plan to proceed with analysis of the results of the melt progression experiment DF-1 and DF-2 performed in the ACRR test reactor. The MELPROG code is also being used in analysis for Phase-2 of the containment study _for the Sizewell B inquiry. The U.K. application and ,

assessment of the mechanistic SCDAP fuel damage code has proved to be the most '

thorough, independent review that the code has received, and has proved invaluable. The U.K. application and assessment of MELPROG should prove equally valuable.

Recently Issued Publication Draft Regulatory Guide and Value/ Impact Statement: Criticality Safety for Handling, Storing, and Transporting LWR Fuel Outside Reactors, Task CE-407-4.

Comments requested by September 20, 1985.

Contact:

M. W. Weinstein (301)443-7666.

l ENCLOSURE E JUL 191985 1

• Accident Management Procedures On July 19, 1985, RES and its contractor, INEL, met with TVA corporate management to discuss the possibility of conducting a study of the effectiveness of accident management procedures in reducing risks due to severe accidents. The proposed study would use the recently completed Brown's Ferry PRA, Sandia containment event trees and BCL source terms.

TVA management appeared receptive and saw some potential advantages in terms of developing cost-effective risk reduction measures and in permitting the Browns Ferry PRA to be compared with the Peach Bottom surrogate, as a possible approach to the Severe Accident Policy application. One of the principal issues to be resolved is the availability of TVA resources. Ne .ne r RES nor TVA would be willing to conduct the study until there is reasonable assurance that adequate technical support is available.

ENCLOSURE E

ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING JULY 19, 1085 International Meetinos The following international meeting notices supplement those previously announced:

Septenber 30-October 4, 1935, Vienna, Austria - IAEA Technical Committee Meeting on Probabilistic Risk Analysis of Engineered Safety Systems.

November 11-15, 1985, Karlsruhe, FRG - IAEA Technical Committee on Fuel Rod Internal Chemistry and Fission Products Behavior.

April 14-18, 1986, Vienna, Austria - IAEA Seminar on Supporting Industrial Infrastructure Requirements and Development for Nuclear Power.

International Visitors On Monday Madeleine Conte, Chief, Generic Issues Branch, Institute of Pro-tection and Nuclear Safety (IPSN) within the French Atomic Energy Commission (CEA), met with William Morris and Jit Vora, RES, to discuss NRC's research program on nuclear plant aging and possible CEA participation in the program.

On Thursday and Friday Bernard Fourest, Chief, Operating Experience Branch, IPSN, CEA, and three other IPSN representatives, met with Jack Heltemes and members of AE0D, IE, NRR, and IP to discuss recent reactor incidents.

1

-0FFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING JULY 19, 1985 Financing of Decommissioning On July 16, 1985, Robert. Wood (OSP) spoke before the International Nuclear Reactor Decommissioning Planning Conference in Bethesda, Maryland, on

" Financial Aspects of the NRC's Proposed Decommissioning Regulations."

jgt 1 g 1009 ENCLOSURE H

.7 4 p t- 5 0FFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEM 0F INTEREST , ,

WEEK ENDING JULY 19, 1985 I

, On July 18, a routine technical exchange meeting between NRC and INP0 was held at the INP0 offices in Atlanta. Three representatives from AE00, two '

i from IE, and one from NRR were in attendance from the NRC. The topics '

discussed included LaSalle pump house flooding, internal flooding of power plant buildings, HPCI/RCIC problems, Davis-Besse loss of all feedwater, Hatch control room water intrusion, loss of RHR case study, Westinghouse , 4 seal table problems, and reactor scram history.

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ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING JULY 19, 1985 N s k ,\

A. STAFF REQUIREMENTS -- DISCUSSION /POSSIBLE V0TE ON FULL POWER OPERATING LICENSE FOR FERMI-2, 2:30 P.M., WEDNESDAY, JULY 10, 1985, COMISSIONERS' CONFERENCE ROOM, DC 0FFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to William J. Dircks dated 7/18/85 The! Commission met with staff to discuss whether or not to s, grant a full power operating license to Enrico Fermi Atomic Power Plant, Unit 2.

The following persons made oral presentations to the Commis-sion during the meeting:

Sister Barbara Bacci Servants of the Immaculate Heart of Mary Congregation J,ennifer Puntenney Safe Energy Coalition of Michigan Jphn Eckert, Director of Civil Preparedness MCnroe County Richard Petticrew, Chairman Monroe County Commission Walter McCarthy, Chairman of the Board Detroit Edison Company Charles Heidel, President Detroit Edison Company Wayne Jens, Vice President-Nuclear Operations Detroit Edison Company The Commission voted full power 4-0*for to authorize the Atomic staff to Power issue a Plant, Unitoperating 2 license Enrico Fermi

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• Commissioner Roberts had not yet been sworn in for his second term and therefore was not in attendance at this meeting.

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ENCLOSURE 0 t

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r-NRR MEETING NOTICES *

(( JULY 19, 1985 u

DOCKET APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 7/23/85 50-254 P-422 To discuss pipe replacement Commonwealth Edison R. Bevan 11:00 am 50-265 Bethesda program for Quad Cities 1&2 7/23/85 50-249 P-422 To discuss details of reactor Commonwealth Edison R. Gilbert 9:00 am Bethesda coolant system piping replace-ment program for Dresden 3 7/23-25/85 50-413 Catawba Site Site Visit Duke Power Co. K. Jabbour 8:30 cm 50-414 York Cty, SC 7/24-25/85 50-395 P-114 To discuss the licensee's So. Carolina Elec. J. Hopkins 9:00 am Bethesda recent reanalysis of fire & Gas.

protection capability for V. C. Summer 7/25/85 P-422 Quarterly Meeting of the EPRI Electric Power D. Moran 1:30 pm Bethesda Light Water Reactor Steering Research Inst.

Committee and NRC Policy AIF

. Committee to assess progress

1. and provide guidance for the l EPRI LWR Standardized Plant i Design Evaluation Program l 7/25/85- - 50-250 MNBB-6110 Discussions related to method- Florida Power & D. Mcdonald 1:30 pm 50-251 Bethesda ologies and processes used Light for establishing priorities (Turkey Point) l . n, . and schedules z

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

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

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$on DOCKET APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 7/26/85 P-422 To discuss results of revised Westinghouse D. Moran 9:00 am Bethesda Methodology for Generic Analysis related to " Westinghouse Long Term Ice Condenser Containment Code" 7/30/85 50-309 P-110 To discuss Generic Fuel Loads Maine Yankee Atomic P. Sears Bethesda for Maine Yankee 7/31/85 50-219 Oyster Creek To discuss status of licensing GPU Nuclear J. Donohew 10:30 am Site actions for the plant 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 PLEASE BE ADVISED THAT DAILY RECORDING CAN BE HEARD ON 492-7166 i

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

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. N ING: 7/19[85 Divisi:n of fuel Cycle and Matt;rini S*.faty c_

E DOCKET ATTENDEES /

NRC CONTACT NjMIER LOCATION PURPOSE APPLICANT DATE/ TIME E

• 7/26/85 71-9200 Willste To discuss TMI Cask. Reps of NUPAC, Odegaarden 8:15-5:00 4th floor DOE, EG&G conf room C. MacDonald (FC)

. R. Chappell (FC)

C. Williams (FC)

C. Marotta (FC)

E. Easton (FC) -

W. Lake (FC)

R. Odegaarden (FC) 7/29/85 71-6601 Willste Discuss license amendment with Reps of Chem Nuclear Odegaarden 10:00-1:00 Chem-Nuclear. R. Odegaarden (FC) -

C. Williams (FC)

H. Lee (FC) 7/30-8/2 Chicago,. Participate in NRC/ DOT Spent Nuclear Reps of D0T, States Cook /Cunningham IL Fuel Transportation Seminar. R. Cunningham (FC)

J. Cook (FC)

C. MacDonald (FC)

W. Thompson (FC)

. L. Rouse (FC) e N

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, D_IVISION OF WASTE MANAGEMENT July 18,1985 m,

w DOCKET ATTENDEES /

DATE/ TIME NUMBER LOCATION PURPOSE AP'LICATION P NRC CONTACT July 31,1985 DOE HQ, Forrestal To discuss and clarify JPearring, WM MDunkleman, WMRP Bldg. Rm. 4E069 DOE positions on NTanious WM Washington, D.C. retrievability and JGreeves, WM retrieval and to reach HMiller, WM agreement where possible JDaemen, SNL KWahi, SNL SBhattachanya, EI TRajaraam, El RCummings, DOE

... MFrei, DOE JRhoderick, DOE VLowery, DOE DOE Project Personnel DIVISION OF SAFEGUARDS None G

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$$ DOCKET ATTENDEES /

!k DATE/ TIME NUMBER LOCATIDN PURPOSE APPLICANT NRC CONTACT 7/28-d/1 Danvers, t%SS. AST!1 C-26 Committee on the Frattali Frattali Nuclear Fuel Cycle Meeting 8/3-8/85 Las Vegas, NV 1. Meet with Carl Bennett re Abramson Abramson statistical handbook.

2. ASA Committee on Nuclear Regulatory Research

3. Deliver paper at joint statistical meetings 4

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- OSP MEETING NOTICES July 19, 1985 eo Nm DATE/ TIME LOCATION PURPOSE ATTENDEES NRC CONTACT 7/26/85 Indianapolis, Meet with Indiana Ind. Advisory WKerr Indiana Board of Health Committee and Dept.

Advisory Committee of Health Staff; W. Kerr, OSP; R. Lickus, Reg. III.

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"' RII MEETING NOTICE DOCKET ATTENDEES /

PURPOSE APPLICANT NRC CONTACT DATE/ TIME NUMBER LOCATION RII Office Meeting with Carolina Licensee and members Gibson .

07/23/85 of the DRP and DRS 10:00 am Power and Light Company representatives to discuss Divisions Licensed Operator Identi-fication Program for Shearon Harris RII Office SALP Board Meeting - Selected RII and NRR Walker 07/24/85 staff members 8:30 am Browns Ferry & Sequoyah facilities 07/24-25/85 RII Office EE0 Forum All RII employees and Grace 9:00 am W. Kerr and E. Tucker with OSDBUCR:HQ 07/25-26/85 Spring City, Watts Bar Full Scale Selected RII Staff Stohr Tennessee Emergency Exercise Members P

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• July 19, 1985 WEEK ENDING:

DOCKET ATTENDEES /

DATE/ TIME lamber LOCATION .

PtRPOSE APPLICANT WRC CONTACT 7/30/85 53-454 Byron, IL Management Ptg. Co w nwealth Edison 50-455 Syron Plant J.G. Keppler & staff J.G. Keppler 8/6,7/85 N . Aurora, IL Resident Seminar Resident Inspectors RIII technical staff O!

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