ML20136G430

Weekly Info Rept for Wk Ending 850809

ML20136G430
Person / Time
Issue date:	08/14/1985
From:	Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
WIR-850809, NUDOCS 8508190407
Download: ML20136G430 (30)

Text

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, s August 14, 1985 -

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

Subject:

WEEKLY INFORMATION PEPORT - WEEK ENDING AUGUST 9, 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 Commission 0 Meeting Notices P Proprietary or Other Sensitive Information (Not for Q external distribution)

• No input this week.  % ,

1 T. A. Rehm, assistant for Operations Office of the Executive Director for Operations l

Contact:

T. A. Rehm, EDO 492-7781 8508190407 850814 PDR COMMS NRCC WEEMLYINFOREPT PDR

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• HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING AUGUST 9, 1985 ,

Illinois Proposal for Agreement The staff has received and has under review a draft proposal from Illinois for Agreement State status. The proposal requests authority to regulate byproduct (11(e)(1)), source, less than critical quantities of special nuclear material and low-level radioactive waste disposal. It does not request authority to regulate mill tailings. The effective date requested is July 1, 1986. Following resolution of any staff comments, the State will prepare a final proposal to be submitted by the Governor. OSP would then prepare an assessment of the final proposal for publication in the Federal Register for public coment. There are ahnut 850 NRC materials licenses in Illinois.

SLC Resolution on Nuclear Reform On July 24, 1985, the Southern Legislative Conference (SLC) adopted a resolution on nuclear power and regulatory reform. In the resolution the SLC joins the Southwest Regional Energy Council in supporting reform of the nuclear power plant licensing process including Congressional authorization of an early site approval process, the use of standardized plant design, consolidated hearings, elimination of antitrust reviews in the licensing process and limiting of issues in licensing proceedings. Copies of the resolution are available from OSP.

Exxon Nuclear Company, Inc.

On July 29-August 2,1985, representatives of NMSS/FC accompanied NRC Region V inspectors on an onsite inspection of Exxon Nuclear Company, Inc. fuel fabrica-tion plant in Richland, Washington. The purpose of the site visit was three-fold: 1) to discuss the environmental impacts from the proposed operation of a dry process for the conversion of UFs to UO2; 2) to discuss the upcoming renewal of Exxon's SNM license, and 3) to provide the staff an opportunity to see and evaluate plant operations.

Study of the Design and Installation of Computer-Managed Security Systems In order to meet the requirements of 10 CFR 73.55, " Requirements for Physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage," licensees are increasingly dependent on computer-managed systems to meet their physical security needs in the areas of access control and alarm monitoring / recording. Our inspection program has shown that these systems may be vulnerable to failure in a number of ways that cannot be detected unless detailed technical guidance on selection and use of computers is provided for licensees.

In response to a user need request from NMSS, RES sponsored a study of the design and installation of computer-managed security systems. As a result of this project, Pacific Northwest Laboratories has published in July 1985 the first of two reports, NUREG/CR-4298, titled " Design and Installation of Computer Systems to Meet the Requirements of 10 CFR 73.55." The report provides a technical basis for development of guidance on system design, selection, and installation. The design guidance includes safety and security requirements, design alternatives, computer security, workspace design, and user interface design. The technical basis for guidance is also provided on writing a system specification for procurement, bid review procedures, and site preparation.

AUG 9 1985

OFFICE OF ADMINISTRATION Week Ending August 9, 1985 ADMINISTRATION OF THE FREEDOM 0F INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1984 179 23 Received, 1985 559 31 Granted 431 24 Denied 118 13 Pending 189 17 ACTIONS THIS WEEK Received Cindee Virostek Requests six categories of records regarding specified (85-552) Babcock and Wilcox facilities in Pennsylvania.

Eric R. Smith, Requests copies of the meeting minutes, notes, NUS Corporation transcript and handouts from a July 23-24, 1985, CRGR (85-553) meeting regarding IST/ISI Pump and Valve Programs.

Mozart G. Ratner, Requests copies of 33 specified records regarding the Attorney-At-Law General Electric facility in Wilmington, North Carolina.

(85-554)

Cindee Virostek Requests two categories of records regarding specified (85-555) Babcock and Wilcox facilities in Pennsylvania.

Pamela D. Jones, Requests records regarding contract number NRC-03-82-096 Information awarded to Science Applications, Inc. and contract Handling Services NRC-03-81-130 awarded to Franklin Research Center.

(85-556)

(Individuals Requests copies of the investigation and report in March 1982 on St. John's Regional Health Center regarding requesting information ) an exposure to a radiation implant.

(85-557)

Vincent Clark, Requests copies of the licenses issued to Stocker & Yale, Delta Lighting Inc., of Beverly, Massachusetts.

Corp.

(85-558)

CONTACT: J. M. Felton 492-7211 ENCLOSURE A AUG 01985

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Received, Cont'd Thomas C. Houghton, Requests the " Reactor Operator / Senior Reactor Operator KMC, Inc. Exam Questions and Answer Key" for 11 specified (85-559) examination reports.

Granted Richard E. Webb In response to a request for a copy of the report (85-445) entitled, " Evaluation of Transient Behavior and Small Reactor Coolant System Breaks in the 1977 Fuel Assembly Plant," Volume III, dated May 16, 1979 regarding the Davis-Besse Nuclear Power Station, Unit 1, informed the requester that this report is already available at the PDR.

John J. McCaffrey, In response to a request for copies of 24 specified )

New York Public records and related information pertaining to the Interest Research transportation of spent nuclear reactor fuel, made Group available six records. Informed the requester that (85-513) 12 of the records are already available at the PDR; five may be purchased from the NTIS and two may be purchased from the GP0. Also, informed the requester that the NRC could not locate two records.

Barbara Baker Lim, In response to a request for a copy of the entire i Westinghouse record which transmitted the guidance regarding the use Electric Corp. of the NRC Form 4, made available a copy of the requested (85-515) record.

Jeanene C. Ondrik, In response to a request for the last two NRC inspection Nuclear Pharmacy, reports for St. James Hospital in Chicago Heights, Inc. Illinois, made available six records.

(85-524)

Clifford A. Beck In response to a request for copies of 24 specified (85-525) reports and supplements, made available copies of the requested records.

Denied (An individual In response to a request for copies of the investigation and status reports for two complaints he filed with the requesting) information NRC in 1984, made available seven records. Denied 15 (85-429) records in their entirety, release of which would interfere with an ongoing enforcement proceeding and constitute a clearly unwarranted invasion of personal privacy.

ENCLOSURE A UG 9 1985

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l l WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING AUGUST 9,1985 RFP ISSUED .

RFP No.: RS-01E-85-158 l

Title:

" Technical Assistance in Developing and Implementing Programs and Procedures for Inspection of Operating Reactors During Major Outages"

Description:

The objective of this project is to provide technical l assistance to the NRC for activities pertaining to planned i outages of operating reactors. This includes the development )

! of standardized inspection procedures for planned outages l

as well as providing assistance to the regional offices for conducting inspections during planned outages of operating reactors.

Period of Performance: 3 years Sponsor: Office of Inspection and Enforcement Status: RFP issued on August 7, 1985. Proposals due September 10, 1985.

ADMINISTRATIVE MATTER A protest filed by Engineers International, Inc. (EI) under Solicitation No. RS-NMS-85-002 for " Technical Assistance for Design Reviews of High '

Level Nuclear Waste Geologic Repositories" was dismissed by the General Accounting Office on July 31, 1985. El had alleged that its proposal was not given fair and equitable consideration by NRC.

ENCLOSURE A AUG 9 1985

0FFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST .

Week Ending August 9, 1985 Limerick By letter dated July 25, 1985 intervenor Augus Love representing the Graterford Inmates filed a Notice of Appeal from the Licensing Board's Fourth Partial Initial Decision. Mr. Love's Appeal Brief will be filed by August 26, 1985 and the staff's reply is due about 40 days later.

Mr. Love's letter also requested a stay of all proceedings pending resolution of the Appeal. This request was denied by the Appeal Board by an Order dated August 1, 1985.

Arkansas-Nuclear One, Unit No. 1, (ANO-1)

Arkansas Power and Light Company (AP&L) has reduced the steady state power level of ANO-1 in order to maintain the operating level of the "A" Steam Generator (OTSG). This is a reoccurring problem for ANO-1. During the last refueling outage, the OTSGs were cleaned by a process of dynamically shocking the water through the orifices in the tube support plates with bursts of nitrogen at the bottom of the OTSG. This was to remove material which was plugging the orifices. Also the orifices at the bottom of the OTSGs were closed. After startup following the refueling (January 1985) the OTSGs were operating with the water level well below the steam asperation ports into the feedwater downcomer. The OTSG level has been steadily increasing ever since. AMO-1 is currently operating at 99.1% of its authorized power level.

D.C. Cook Steam Generator Tube Leak On Friday, August 2, 1985, while returning to power from a tube plugging outage, the D.C. Cook Unit 2 detected additional primary to secondary

leakage. The Unit had reached 30% power before being shutdown at about 6

00 l p.m. The Unit will be down for at least two weeks for examination and additional tube plugging.

The Unit is approved to operate with environmental qualification extensions until November 30th. The licensee is aware that any extension beyond the I

hovember 30 deadline will require Commission approval according to 1.0 CFR

, 50.49(g).

ENCLOSURE B AUG 9 1985

I Vogtle Units 1 and 2 l A Georgia Pcwer Company representative informed the NRR Project Manager on August 5, 1965 that the company planned to slip the date for commercial operation of Unit 1 from March 1987 to June 1987.

Therefore, fuel load will move fron September 1, 1986 to December 1, 1986.

The schedule slippage is attributed to inability to maintain construction schedules and system turnovers to operation. The schedule

for commercial operation of Vogtle Unit 2 will remain unchanged at September 1988.

- Limerick Unit 1 On August 8, 1985, following a meeting of the Commission, a full power license was issued for the Limerick, Unit 1 plant. The reactor went critical at 7:19 p.m. on August 8. As of 8:05 a.m. on August 9 the reactor is at less than 1% power, 150 psi. The plant staff plans to exceed 5% power sometime later today.

After exceeding 5% of rated power, the plant will be stabilized at 10% of i rated power for a number of basic tests. These include: (1) a reactor vessel water level perturbation to check stability of the feedwater control system; and (2) a primary system pressure perturbation to check stability of the pressure control system (turbine bypass valve).

Diablo Canyon 2 1

Due to delays in the pre-criticality testing, it appears that

criticality will be achieved early the week of August 11, 1985.

Beaver Valley 2

! On June 6, 1985 we issued a final draft Safety Evaluation Report in j

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order that the applicant could provide additional information to close open issues. Since we have not received either a schedule for information submittals or the submittals, we advised the applicant, on August 2, 1985 that the delay will most likely result in a delay in his desired ACRS meeting.

ENCLOSURE B AUG 9 1985 1

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Fermi-2 The Fermi-2 facility will pull rods and go critical again late on August 8th after having been shutdown for about two weeks. Though the full power license was issued on July 15, 1985 after Concission authorization on July 10, 1985, Region III issued a Confirmatory Action Letter (CAL) dated July 16, 1985, limiting Fermi-2 to power levels no greater than five percent. Other mechanical (e.g., the south main feedwater pump) and procedural problems also limited operations at the facility. Testing of the HPCI and RCIC systems and of the north feedwater pump will require about two weeks before the plant will be ready to exceed five percent power. Region III may be able to reach a decision on DECO's response to the CAL in the same time frame.

The damaged steam turbine of the south feedwater pump has been shipped to DeLaval's factory in New Jersey for repair. This repair should be completed in about 2 to 3 months from now (i.e., about the end of October 1985); without this pump, the plant cannot exceed 50% power.

Assuming the plant is ready to exceed 5% power by late August, the startup test program would also limit the plant below 50% power until after the scheduled shutdown for about one month starting at the end of October 1985.

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AUG 9 1985 ENCLOSURE B i

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a NRC TMI PROGRAM OFFICE WEEKLY STATUS REPORT WEEK ENDING AUGUST 9, 1985 -

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

The plenum is on its storage stand in the deep end of the fuel transfer canal. A dam has been installed between the deep and shallow ends of the fuel transfer canal. The deep end is filled with water to a depth of about 20 feet (about 5 feet above the top 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 70*F to 91*F with an average of 80*F. Average cold leg temperature is 56*F.

The average reactor building temperature is 59*F. The reactor building airborne activity is 2.2 E-8 uCi/cc Tritium and 4.1 E-9 uC1/cc particulate, predominantly Cesium 137.

2. WASTE MANAGEMENT The Submerged Demineralizer System (SDS) and EPICOR II were shutdown this period.

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 AUG 9 1985 l

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

Average general area radiation dose rate is 40 mrem per hour on the 347' level of the reactor building and is 67 mrem per hour on the 305' level of the reactor building.

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 20, to July 27, 1985. Gamma scans detected no reactor related radioactivity.

The Lancaster water sample taken at the water works intake and arlalyzed by the US Environmental Protection Agency consists of a seven day composite sample taken from July 31 to August 8,1985. A gama scan detected no reactor related radioactivity.

The NRC outdoor airborne particulate sampler at the TMI Site collected a sample between July 31, and August 8, 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 Installation of the rotating work platform and service platform (over the reactor vessel) has been completed.

Equipment was staged into the reactor building and installation is almost complete on the cable management system.

Installation of the reactor building service platform jib cranes was completed.

Loop calibration of Defueling Water Cleanup System (DWCS) instrumentation and final preparations for system preoperational testing continued this week.

Installation of tool racks for defueling tools has begun.

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 of four fuel canister racks are on site with further deliveries scheduled through August.

ENCLOSURE B AUG 91985 l

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7. SUSPENSION OF WASTE BURIAL IN WASHINGTON STATE On August 6, 1985 the State of Washington, Department of Social and Health Services notified NRC TMIPO of the suspension of GPU Nuclear's Three Mile Island Nuclear Station pennit to ship radioactive waste to U.

S. Ecology's Hanford Waste Management Facility at Richland, Washington.

The State action was taken as a result of a radioactive waste shipment of 104 barrels, dispatched from TMI on July 18, and received at the U. S.

Ecology site on July 23, 1985. Contrary to NRC and Washington State requirements, three barrels were incorrectly classified, labeled and certified by GPUN. The three barrels exceed the 10 CFR 61.55 requirementsforClassAwastecontainingstrontium-90(>.04uC1/cc)and should have been classified and handled as Class B waste. Class B waste must be segregated from Class A waste and meet stability requirements to Class A waste.

which do not apply (DOT) shipping requirements.All of Transportation The threeofbarrels the barrels will bemet Depar segregated from the balance of the shipment. The 101 Class A barrels will be buried, and the three Class B barrels will be returned to TMI.

No further shipments will be permitted until approval is received from the State. Among the requirements for reinstatement of burial privileSes is a description of the Quality Assurance program to be applied to radioactive waste shipments made from the TMI site which will prevent future violations of shipping and classification requirements.

8. NRC EVALUATIONS IN PROGRESS Technical Specification Change Requests numbers 48, 49, and 50.

Recovery Operations Plan Change numbers 29, 31, 32, and 34 Fuel Canister Technical Evaluation.

Fuel Handling Senior Reactor Operator Training Program .

- Defueling Safety Evaluation.

Application for seismic exemption.

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

10. 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 AUG 9 1985

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0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest l

Week Ending August 9, 1985

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NRC/ DOT Sponsored Seminar on Spent Fuel Transportation for States, Local l Governments and Indian Tribes The NRC/D0T Seminar on Spent Fuel Transportation in Chicago on July 31 through August 2,1985, drew a peak attendance of 275, about twice the number originally expected. Representatives of the States, local governments and Indian tribes l were represented. The half-day tour of the General Electric spent fuel storage  !

facilities at Morris, Illinois, was attended and especially well received by the 157 participants. The tour included exhibits of the IF-300 rail shipping casks, the NRC Region III field inspection and radiological monitoring van, the Illinois Department of Nuclear Safsty Inspection and Radiological monitoring van, the Illinois hazardous materials highway patrol car for initial response to highway accidents, the Burns Security escort vehicle which has accompanied  !

certain spent fuel shipments, and the Northern States Power escort vehicle which accompanies all of their spent fuel shipments. All exhibits were manned by their regular staff who explained the capabilities and use of the vehicles.

Exxon Nuclear Company, Inc.

On July 29-August 2, 1985, representatives of NMSS/FC accompanied NRC Region V r inspectors on an onsite inspection of Exxon Nuclear Company, Inc. fuel fabrica- i tion plant in Richland, Washington. The purpose of the site visit was three-fold: 1) to discuss the environmental impacts from the proposed operation of 1 a dry process for the conversion of UFs to UO2 ; 2) to discuss the upcoming renewal of Exxon's SNM license, and 3) to provide the staff an opportunity to see and evaluate plant operations.

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NEAR TERM NRC ACTIONS UNDER THE NUCLEAR WASTE POLICY ACT

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Section: 114(e) of NWPA Action: NRC received the DOE draft Project Decision Schedule'on July 18, 1985.

Status: NRC comments on the draft PDS are due to 00E on September 13, 1985. NRC staff are currently preparing the proposed response for the Commission to transmit to 00E.

Section: 121(a)ofNWPA Action: EPA plans to issue its final high-level waste standards on August 15, 1985.

Status: When EPA issues the final standards, NRC regulations and criteria (10 CFR Part 60) must be revised by the Commission to meet the standards.

Section: 117(a)ofNWPA Action: NRC must provide timely and complete information to States and Tribes concerning the High-Level Waste Repository Program.

Status: NRC staff has been meeting with State and Tribal officials to discuss their involvement in NRC's NWPA actions, so that it can be factored into NRC's connents on the draft Project Decision Schedule.

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ENCLOSURE C AUG 9 1985

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0FFICE OF INSPECTION AND ENFORCEMENT Items of Interest Week Ending August 9, 1985

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

a. EN 85-06A, Imposition of Civil Penalties in the amount of $5,000 was issuedAugust7,1985toNorthAmericanInspection,Inc.(Bethlehem, PA). The licensee responded to the Notice in letters dated February 21, 26 and April 10, 1985. After careful consideration of the licensee's response, the staff has concluded that the violations did occur as set forth in the Notice of Violation and Proposed Imposition of Civil Penalties (EN 85-06, dated February 1, 1985).

This action was based on 12 violations which were characterized in the aggregate as a Severity Level III problem.

b. EN 85-53, a Notice of Violation and Proposed Imposition of Civil Penalty in the amount of $2,500 was issued August 8, 1985 to Syncor International (Sylmar,CA). This action involves licensed material being left unattended and unsecured in unlocked vehicles with the keys in the ignition and the motor running.

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

a. PNO-TMI-85-06,GPUNuclearCorporation(TMIUnit2),Suspensionof Waste Burial in Washington State.

b. PNO-I-85-54. Boston University (Boston, MA), Flooded Radioactive Material Storage Area.

c. PNO-I-85-55,MaineYankeeAtomicPowerCompany(MaineYankee),

Mispositioned Instrumentation Valves,

d. PNO-II-85-75. Virginia Electric and Power Company (North Anna Unit 1),UnscheduledShutdownGreaterThan48 Hours.

e. PNO-II-85-76. Florida Power and Light Company (St. Lucie Unit 2),

Power Loss to Engineered Safeguards Instrumentation Train.

f. PNO-III-85-28D,J.C.Haynes(Newark,OH),ArrestforUnlawfull Possession of Radioactive Material (Final Update).

g. PNO-III-85-63A,DetroitEdison(FermiUnit1),ShutdowntoRepair FeedwaterPump(Update). ,

h. PNO-III-85-68, Comonwealth Edison (LaSalle Unit 2), Shutdown to Investigate Localized High Drywell Temperatures.

1. PNO-!!!-85-69, John Mathes and Associates (Columbia. IL), Stolen Moisture Density Gauge.

AUG 0 1985 ENCLOSURE D

-2 J. PNO-III-85-70. Detroit Edison Company (Fermi Unit 2), County Board of Consnissioners Request Investigation of Utility and NRC.

k. PNO-IV-85-38,GulfStatesUtilities(RiverBend),Detectionof Concealed Weapon.

1. PN0-IV-85-39, Western Stress Corrpany (Evanston, WY), Apparent Over-exposure of Two Radiographers.

m. PNO-IV-85-39A,WesternStressCompany(Evanston,WY), Apparent Overexposure of Two Radiographers (Update).

n. PNO-IV-85-39B, Western States Company Evanston,WY),ApparentOver-exposureofTwoRadiographers(Update)(.

o. PNO-IV-85-39C,WesternStatesCompany(Evanston,WY),Overexposureof TwoRadiographers(Update),

p. PNO-V-85-51, Pacific Gas & Electric Company (Diablo Canyon Units 1 & 1),

Earthquakes.

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

a. IE Information Notice 85-66, Discrepancies Between As-Built Construc-tion Drawings and Equipment Installations was issued August 7, 1985 to all nuclear power reactor facilities holding an operating license or a construction permit,

b. IE Information Notice 85-67, Valve-Shaft-to-Actuator Key May Fall Out of Place When Mounted Below Horizontal Axis was issued August 8, 1985 to all nuclear power reactor facilities holding an operating license or a construction permit.

4. Other Items

a. Senior Maragement Meeting Director, IE met with the Chief Executive Officer of Omaha Public Power District concerning the outage inspection program for Fort Calhoun on August 9, 1985.

b. Deputy Director Division of Inspection Programs The new Deputy Director, Division of Inspection Programs reported for duty this week.

ENCLOSURE D AUG 9 1985

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c. Emergency Preparedness i On August 1, 1985 representatives of the Emergency Preparedness Branch, Division of Emergency Preparedness and Engineering Response participated in a meeting in Region I with representatives of North-east Utilities to discuss emergency preparedness matters related to licensing of Millstone Unit 3.

d. Public Hearing Chief, Reactor Construction Programs Branch, Division of Quality Assurance, Vendor, and Technical Training Center Programs partici-pated in the public hearing for the South Texas Plant in Houston, TX this week,

e. Regulatory Guide 1.28. Rev. 3 Quality Assurance Program Requirements (Design and Construction)

Regulatory Guide 1.28, Revision 3, " Quality Assurance Program Require-ments (Design and Construction) " was released for issuance this week. Regulatory Guide 1.28 Revision 3 was developed by the Quality Assurance Branch staff and it endorses ANSI /ASME NQA-1-1983 and the j

NQA-la-1983 Addenda,

f. Haddam Neck Design Review ,

A representative of the Quality Assurance Branch, Division of Quality Assurance, Vendor, and Technical Training Center Programs, visited the Haddam Neck Nuclear Power Plant site on August 6 and 7, 1985 to discuss Haddam Neck design reviews,

g. Engineering Assurance On August 5, 1985, the Quality Assurance Branch received a report from Niagara Mohawk Power Corporation conveying the results of phase 3

one of its program for completion of Engineering Assurance in-depth audits from Nine Mile Point 2. Representatives of the Quality Assurance Branch will visit Stone & Webster offices in Cherry Hill, New Jersey the week of August 12, 1985 to inspect implementation.

h. Vendor Program The following vendor inspection was conducted this week:

Air Balance, Inc., Wrens, Georgia, to determine if the failure of fire dampers to close under certain flow conditions, as reported by Ruskin Manufacturing Company, apply to Air Balance supplied dampers and to obtain information in regard to possible generic fire darper issues.

AUG 0 1985 ENCLOSURE D

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1. Incident Response (1) The Incident Response Branch Chief, Division of Emergency Preparedness and Engineering Response conducted a tour of the NRC Operations Center for members of the ACRS on August 7, 1985.

This tour discussed the agency's incident response program.

t (2) The Incident Response Branch Chief and a staff member met with the Federal Radiological Preparedness Coordinating Committee, Subcommittee on Response to discuss planning issues for the FY 87 Federal Field Exercise.

J. Mini-Perfomance Appraisal Team (PAT) Inspections Three mini-PAT inspections are scheduled for the following plants:

D.C. Cook - August 19-28 Fort St. Vrain - August 19-28 Browns Ferry - August 26-30

k. CRGR Visit To Monticello Director, Division of Emergency Preparedness and Engineering Response will participate in a CRGR visit to the Monticello Nuclear Power Plant on August 12-14, 1985.

1. Resident Inspector Safeguards Training Representatives of Reactor Operation Programs Branch, Division of Inspection Programs presented Resident Inspector Safeguards Training on August 6,1995 at the Region III resident inssector counterpart meeting. Representatives also participated in tie NMSS RER at Fort St. Vrain August 7-11, 1985.

m. Construction Appraisal Team (CAT) Inspection Representative of Reactor Construction Programs Branch, Division of Inspection Programs was at Byron Unit 2 site August 8, 1985 to pre-

! pare for the upcoming CAT inspection to be performed August 19-30 l and September 9-20, 1985.

n. Enforcement Conference Representative of Enforcement Staff was in Region !! this. week for l an enforcement conference on Grand Gulf.

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OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest .

Week Ending August 9, 1985 ROSA-IV The ROSA-IV system performs large-scale thermal hydraulic tests under a cooperative program with NRC. The test results are used to verify scaling parameters in NRC regulatory safety analysis codes.

The ROSA-IV program is on schedule. The Large-Scale Test Facility (LSTF) is now fully operational. Since the comissioning of LSTF, three small cold-leg break tests have been completed. The data obtained from these tests are being processed and qualifico. Two sets of unqualified data plots have been received by the NRC, the Los Alamos National Laboratory (LANL)andEGAGIdaho, Incorporated (EGAG). These are: (1)2.5 percent cold-leg br<.ak test (SB-LC-01), and (2) 5 percent cold-leg break test (SB-CL-05). The 5 percent test was configured to simulate a Japanese pressurizedwaterreactor(PWR). The purpose of this test was to study the effect of liquid holdup in a steam generator and the resulting core level depression. Based on preliminary data plots, there was liquid holdup in the upside of the steam generator U-tubes and brief core uncovery. The maximum heater rod temperature observed was 680K. Further analysis and evaluation of these test results will be performed by the Japan Atomic Energy Research Institute (JAERI). The qualified data will be provided later by JAERI to LANL and EG&G for code assessment.

The final RELAPS/ MOD 2 input deck to simulate LSTF was completed by EG8G and sent to JAERI and LANL for use. LANL is developing a TRAC-PF1/ MODI input deck to simulate LSTF.

Bilateral Thermal Hydraulics Agreement Concluded with Belgium An agreement on thermal hydraulics research between the NRC and Tractionel of Belgium has been signed by both parties. Tractionel is an engineering company supporting the Belgium utility and its four generating units at Doel. As part of the 5-year agreement, the NRC will provide the RELAPS/ MOD 2 code in exchange for 15 assessment calculations to be performed by Tractionel. Data from the Doel power plants will provide the basis for the calculations. Tractionel has gained experience with RELAP through use of earlier versions of the code, including RELAPS/M001. The information to be generated by Tractionel will assist the NRC's effort to define the code accuracy and uncertainty for best estimate analysis of plant transients.

E m 0S E E AUG 0 1985

Use of Nuclear Plant Analyzer (NPA) for Davis-Besse Transient NRR has made preliminary use of the NPA with the mainframe Idaho National Engineering Laboratory (INEL) computer to analyze the Davis-Besse transient. On July 21, 1985 a severe thunderstorm knocked out the operation of the INEL computer. Subsequent efforts by INEL and Control Da'ta Corporation (CDC) did not restore full operational capability. When it was restored, it turned out to be highly unreliable. Thus, NRR was unable to complete their planned analyses of the Davis-Besse transient.

In order to resolve the computer hardware problems, INEL is making the following changes,

a. Tapeanddiskerrorrecoverycapabilityforthecomputer(N05) system was tested and installed at INEL by August 1, 1985.

b. Replacement of six 885 Disk Drive HDs will be completed by

, August 10, 1985.

c. The disk system is being refurbished. The system will be reconfigurated to handle file transfers at a higher rate,

d. An 80 KVA " ride through" motor generator will be installed on site by November, 1985 to stabilize the power on CYBER 176 (201).

e. Two additional disk drives and controllers have been ordered.

This will provide additional file paths.

f In addition, CDC has placed INEL on a Critical Site Status so that all i

problems can be quickly identified. It is expected that the reliability of the system will be enhanced by November 1985 when the installation of the motor generator will be completed.

Calibration of Instruments Used for the Dosimetry of Beta Radiation In connection with a project funded jointly by the National Bureau of Standards (NBS) and the Nuclear Regulatory Conrnission, NBS has developed a >

! facility to calibrate beta sources and transfer instruments sent to NBS by j l commercial calibration services or by NRC licensees. After return to the  ;

sender, the transfer instrument or sources may then be used for the on-site calibration of radiation protection instruments. The standard beta sources that are currently available at the NBS facility for this calibration service l are: Strontium 90, Thallium-204 and Promethium-147. The results of this NBS study have been published as NUREG/CR-4266, " Standard Beta-Particle and Monoenergetic Electron Sources for the Calibration of Bota-Radiation Protection Instrumentation." The purpose of this work was to improve the  ;

accuracy of radiation surveys that licensees are required to perform for the NRC. NUREG/CP-0050, " Proceedings of the International Beta-Dosin,etry  :

Sympostun",1983, has shown that present beta measurements may be in error by  ;

, as much as a factor of 100 if the dependence on beta energy, source-detector l l geometry, mixed radiation fields and environmental conditions is not properly I

factored into the measurement. ENCLOSURE E AUG 91985 L

Meeting Of ASTM C-26 Subcommittee On Nuclear Waste Mar.agement ,

The ASTM C-26.07 subcomittee on Nuclear Waste Management met on July 30-31 at Danvers, MA. Dr. Kyo S. Kim of the Waste Management Branch, Division of Radiation Programs and Earth Sciences is the RES liaison with the subcommittee and attended this meeting. Status reports by four task groups of the subcomittee were given. Two task groups reported that adoption of two Materials Characterization Center (MCC) test methods is nearly complete, and that the subcomittee should be able to recomend adoption of MCC-1, " Static Leach Testing" and MCC-11. " Splitting Tensile Strength Method" as ASTM standards by the end of the calendar year. In addition, it was reported that work is proceeding on development of an ASTM standard on radiolytic generation of gas in low level radioactive wastes, and a standard on low level waste leaching tests. Publication by ASTM of standards on these subjects will facilitate NRC review of licensed disposal of both high level and low level radioactive wastes by providing methods which have been reviewed and endorsed by the technical comunity for assessing the performance of waste forms.

The next meeting of the subcommitte will be in January.

Study of the Design and Installation of Computer-Managed Security Systems In order to meet the requirements of 10 CFR 73.55, " Requirements for Physical Protection of Licensed Activities in Nuclear Power Reactors Against Radiological Sabotage," licensees are increasingly dependent on computer-managed systems to mett their physical security needs in the areas of access control and alarm monitoring / recording. Our inspection program has shown that these systems may be vulnerable to failure in a number of ways that cannot be detected unless detailed technical guidance on selection and use of computers is provided for licensees.

In response to a user need request from NMSS, RES sponsored a study of the -

design and installation of computer-managed security systems. As a result of this project, Pacific Northwest Laboratories has published in July 1985 the first of two reports, NUREG/CR-4298, titled " Design and Installation of Computer Systems to Heet the Requirements of 10 CFR 73.55." The report provides a technical basis for development of guidance on system design, selection, and installation. The design guidance includes safety and security requirements, design alternatives, computer security, workspace design, and user interface design. The technical basis for guidance is also provided on writing a system specification for procurement, bid review procedures, and site preparation.

ENCLOSURE E AUG 9 1985 i

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4-Recently Issued Publications

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Reg. Guide 1.28 Rev. 3. " Quality Assurance Program Requirements (Design and Construction)(Task RS 002-5).

NVREG-0956, " Reassessment of the Technical Bases for Estimating Source Terms," was printed this week and is available for distribution. This document provides the NRC staff assessment on the science and engineering associated with the phenomena that occur during and after a spectrum of core damage events. The report is the culmination of several years' work by the NRC and its contractors on the reassessment of the radionuclide releases associated with severe accidents in light water reactors. It represents an important first step in the consideration of safety issues for accidents more severe than the design basis. The report has been issued for public comment and comments have been invited on all phases of the science and engineering and on the staff's conclusions and recommendations.

AUG 0 1985 ENCLOSURE E

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l-1 ITEMS OF INTEREST j OFFICE OF INTERNATIONAL PROGRAMS l l

WEEK ENDING AUGUST 9, 1985 l

r International Meetings .

j The following international meeting notices supplement those previously I announced: }

September 3-20, 1985 Bristol, UK - IAEA Interregional Training Course on the l Uses of Probabilistic Safety Assessment (PSA) in Decision Making - Managerial .

Perspectives  ;

t October 7-11, 1985, Vienna, Austria - IAEA Advisory Group Meeting to Prepare a Safety Series Document on The Application of the Principles of Radiation Protection to Sources of Potential Exposure, with Special Reference to Radio-active Waste Repositories

IAEA Vacancy Notices I l . l The following six International Atomic Energy Agency vacancy notices for i positions at its headquarters in Vienna, Austria are posted on NRC bulletin i boards

l P-3 Physicist, INIS Section, Division of Scientific and Technical l Information, Department of Nuclear Energy and Safety P-5 Head, Vienna International Center Library, Division of Scientific and Technical Information, Department of Nuclear  ;

Energy and Safety  :

0-1 Director, Division of Public Information, Department of Administration ,

1 P-5 Head, Conference Service Section, Divisior of External Relations, Department of Administration P-4 Risk Studies Coordinator, Reliability and Risk Assessment Unit, Division of Nuclear Safety, Department of Nuclear Energy and Safety l P-4 Nuclear Engineer, Advanced Nuclear Power Technology Section, Division of Nuclear Power, Department of Nuclear Energy and  !

Safety l J

Foreign Visitors  !

On Monday and Tuesday Mr. Reuven Greenberg of the Licensing Division of the

, Israeli Atomic Energy Comission met staff members of the NRR Divisions of Systems Integration, Safety Technology, and Human Factors Safety to discuss

(

' the reliability of computer software in the performance of safety-related tasks.

l ENCLOSURE G AUG 01985

t OFFICE OF STATE PROGRAMS ITEMS OF INTEREST I WEEK ENDING AUGUST 9, 1985 l l Training Course for State Personnel l

During the week of August 19-23, 1985, sixteen State radiation control personnel l

, will attend the courso entitled " Safety Aspects of Industrial Radiography for l l State Regulatory Personnel" at Gamma Industries in Baton Rouge, Louisiana, r Followup Review of California Program l A followup review of the California radiation control program will be conducted l August 19-23, 1985.

l Illinois Proposal for Agreement

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l The staff has received and has under review a draft proposal fro 1 Illinois for l Agreement State status. The proposal requests authority to regulate byproduct l (11(e)(1)), source, less than critical quantities of special nuclear material l and low-level radioactive waste disposal. It does not request authority to regulate mill tailings. The effective date requested is July 1, 1986. Following t

resolution of any staff comments, the State will prepare a final proposal to be submitted by the Governor. OSP would then prepare an assessment of the final

, proposal for publication in the Federal Register for public comment. There are about 850 NRC materials licenses in Illinois, l

SLC Resolution on Nuclear Reform On July 24, 1985, the Southern Legislative Conference (SLC) adopted a resolution l on nuclear power and regulatory reform. In the resolution the SLC joins the i

Southwest Regional Energy Council in supporting reform of the nuclear power .

plant licensing process including Congressional authorization of an early site approval process, the use of standardized plant design, consolidated hearings, ,

elimination of antitrust reviews in the licensing process and limiting of issues  !

l in licensing proceedings. Copies of the resolution are available from OSP.

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I g g ggg ENCLOSURE H 1

OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ITEM OF INTEREST WEEK ENDING AUGUST 9, 1985 In a memorandum dated August 5, 1985, the EDO assigned responsibility for generic and plant-specific actions resulting from the NRC Team's investigation of the Davis-Besse event (documented in NUREG-1154). The Directors of NRR, IE, RES, AE00, and the Regional Administrator, RIII, were requested to deter-mine the actions necessary to resolve the items in their area of responsibility and, where appropriate, to identify additional staff actions or revisions as the understanding of this event is refined.

The EDO also requested each office to conduct an in-depth reappraisal of the effectiveness of their programs based upon the lessons of the Davis-Besse event and to propose actions to make NRC programs more effective.

It was noted that the actions for restart of Davis-Besse would be handled in a separate manner.

AUG 9 1985 ENCLOSURE J

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0FFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS WEEK ENDING AUGUST 9, 1985 Proposed Rule Signed by EDO j On August 6,1985, the Executive Director for Operations approved a proposed l rule that would amend 10 CFR Part 73, " Physical Protection of Plants and l Materials" to improve the clarity and effectiveness of the present require-i monts for the reporting of safeguards events of Section 73.71. The proposed i

rule also contains conforming amendments to 10 CFR Parts 70, 72, 73 and 74,

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

I I

e go 91985 ENCLOSURE N i

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ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING AUGUST 9, 1985 A. STAFF REQUIREMENTS - BRIEFING ON DAVIS-BESSE 1:30 P.M., WEDNESDAY, JULY 24, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to W. J. Dircks dated 8/7/85 The Commission met to be briefed by staff on the June 9, 1985 loss of main and auxiliary feedwater event at the Davis-Besse Nuclear Power Station Unit 1.

The EDO indicated that the investigative team would be preparing the lessons learned regarding the process used in carrying out the investigation.

(EDO)/AE00 Chairman Palladino indicated that a follow-on meeting to discuss implementation of the investigative team's conclusions may be. scheduled and requested the Office of the Secretary to propose a tuitable date at a future agenda planning session.

(SECY)

ENCLOSURE 0 AUG 0 1985

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AUGUST 9, 1985 000ET . APPLICANT /

DATE/TI*E ItseER LOCATION PURPOSE ATTEISEES NRR CONTACT 8/12/85 50-309 P-110 To discuss generic fuel leads Maine Yankee Atomic P. Sears 1:00 pe Bethesda for Itaine Yankee S/13/95 50-387/388 5088-6507 To discuss possible NBC review Pennsylvania Power & M. J. Campagnone 10.30 am Bethesda of S=-- _ trc's completed PGA Light 8/13-15/95 50-423 Millstone 3 Site Enviremental Qualification of Isortheast Utilities E. Doolittle Waterford, Conn. Electrical Emipment Site Audit EGac 8/14/85 50-346 P-110 Biscuss Toledo Edison Co. Toledo Edison Co. A. De Agazio 0:00 am Bethesda planned actions relative to June 9th evant at Davis-tesse 8/15/85 50-454 P-114 To discuss progress of review Brookhaven Matl. Lab. L. 01shan 9-00 am 50-455 Sethesda of Syron LCD Relamation Program 8/15/85 50-498 P-118 NRC staff review of Quellffed Houston Lighting & N. Kadadi 9:00 am 50-499 Bethesda Display Processing system Power Co.

Bechtel Westinghouse PLEASE K ADWISED THAT DAILY RECORDING CAII K IEAAD ON 492-7166

• Copies of sammerles of these meetings wl11 be made publicly available and placed in the respective docket flie(s) in the NRC and local public document roses. -

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t Dloision of Fuel Cyc12 and platerial Safety ,

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c SOCKET ATTENBEES/

BATE / TIE $ IENGER LOEATION PtmPOSE APPLICANT NRC CONTACT "a",

8/12/85 9:00-3:00 ,

Willste 81dg. Pre-application meeting for R. H. Odegaarden. FC Odegaarden I Silver Spring West Valley Storage /Transp., C. E. M cDonald, FC ,

Casks.

C. R. k rotta FC H. Lee,FC D. Huang, FC E. Easton, FC  ;

W. H. Lake FC "

Representatives of DOE, l Transnuclear and Consultants. ,

8/14/85 70-364 5th Floor Conf. To discuss waste burial area P. Loysen FC Loysen ,

Room, W111ste at Parks Tounship (Babcock L. C. Rouse, FC Building SS and Wilcox) F. Sturz, FC J. Roth, RI M. Austin, 88M  ;

D. Sgarlata, 88W J. Berger, ORAU  !

8/14-16/85 Lane Geneva, Working Group Participation J. P. Roberts FC Roberts Wisconsin in ANS-57.7 Reconfirmation Representatives of  ;

Meeting. ,

Battelle Pacific l Northwest Labs. l l

8/20/85 71-9200 5th Floor Conf. Discuss TMI canisters for use R. H. Odegaarden. FC Odegaarden '

10:00-2:00 Room. Willste in Model No. 125-8 Cask. C. R. Chappell, FC -

i 81dg., SS C. R. k rotta FC C. E. Mcdonald, FC t Representatives of NUPAC, GPU Nuclear -

and B&W 8/29/85 72-3 H. B. Robinson Site visit to Carolina Power F. Sturz, FC Sturz g site near & Light Campany's H. B. E. Pentecost NRC p Hartsville, SC Robinson site to discuss J. Kozyra, et al, S Environmental Assessnent of CP&L E _

Independent Fuel Storage '

Installation.

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OSP M ETIIE NOTICES August 9, 1985 k DATE/ TIE LOCATION PURPOSE ATTENDEES NRC CONTACT 8/15-16/85 Albuquerque,N.M. Attend meeting of -

Indian Committee SWeissberg National Indian Nuclear Members; DOE; ,

Waste Review Cossaittee S. Weissberg, OSP 8/21/85 Ricimond, Virginia Discuss Agreement State Dr. R. Stroube. Asst. DNussbaumer 10AM Program and MOU on Health Commissioner Inspection of Waste and Staff; Packaging and R. Trojanowski, R II; Transportation D. Nussbaumer, OSP  ;

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= RII E ETING NOTICE E

DOCKET '

ATTENDEES /

LOCATION PURPOSE APPLICANT NRC CONTACT DATE/ TIME NLMBER 8/15/85 Southport, NC Presentation of Operator Licensee, Regional Gibson 11:30 a.m. (Brunswick License Certificates Administrator and, Site) Selected RII Staff Members P

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