Text

Weekly Info Rept for Wk Ending 851227
	ML20141E721
Person / Time
Issue date:	01/02/1986
From:	Rehm T; NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:	;
References
	WIR-851227, NUDOCS 8601080293
	Download: ML20141E721 (26)
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January 2, 1986 For: The Commissioners From: T. A. Rehm, Assistant for Operations, Office of the ED0

Subject:

WEEKLY INFORMATION REPORT - WEEK ENDING DECEMBER 27, 1985 A sunnary 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. ~'

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/ T.].A.lRehm, Assistant gk

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for Operations Office of the Executive Director for Operations

Contact:

T. A. Rehm, ED0 -

492-7781 8601080293 e60102 PDR COMMS NRCC WEEST1 N T

HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING DECEMBER 27, 1985 Salem Unit No.1 and Turkey point Unit No. 4 Salem Unit No. 1 and Turkey Point Unit No. 4 have been selected by the Inter-national Atonic Energy Agency (IAEA) under Article 39(b) of the US/IAEA Safe-guards Agreement for the application of IAEA safeguards, effective January 1, 1986. These facilities will be subject to-IAEA safeguards reporting and inspection requirements. The objective of the inspection is to permit the IAEA to verify that source and special nuclear materials are not withdrawn from the facilities.

Rancho Seco Nuclear Generating Station Unusual Event The Rancho Seco Nuclear Generating Station is in hot shutdown for repair of a leaking valve in the pressurizer liquid sample line. At 7:34 p.m. (EST) on December 22, 1985, with the unit at 97% power, unidentified leakage of an estimated 3-4 gpm was observed from the reactor coolant system (RCS). An Unusual Event was declared at 7:42 p.m. The source of the leakage was deter-mined to be from'a valve in the pressurizer liquid sample line (containment isolation valve SFV-70001.

The event (i.e., leakage)) lasted approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 20 minutes, and the total RCS inventory leaked was estimated by the licensee to be roughly 1640 gallons. Maintenance personnel are currently repacking the valve and reactor startup is anticipated upon completion of this effort.

ArkansasNuclearOne, Unit 1_(AN0-1)

A safety system functional inspection by IE personnel will be performed at ANO-1 from January 6, 1986, to January 31, 1986. An exit meeting with the licensee is anticipated for January 31, 1986. The inspection will consist of a detailed review of the ANO-1 emergency feedwater system. The objective of the inspection is to assess the operational readiness of the emergency feedwater (EFW) system.

The inspection will b~e of a format similar to that which was performed at Turkey Point and Pilgrim. It is a fallout of the Davis-Besse event, and it was requested by the EDO.

NFS-Erwin Stri ke by OCAW members continues. There has been almost no negotiating between the Union and NFS within the last 3 months, so resolution of the differences between the parties is not expected in the near term. NFS is conducting limited operations of the HEU production, scrap recovery, and R&D facilities.

DEC 2 71985 m

OFFICE OF ADMINISTRATION Week Ending December 27, 1985 ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of Request Initial Decision Carryovers, 1984 179 23 Received, 1985 847 41 Granted 654 32 Denied 188 19 Pending 184 13 ACTIONS THIS WEEK Received Dudley Pierson, Requests copies of 01's report on the July 2,1985, The Detroit News inadvertent criticality incident at- the Fermi 2 nuclear .

(85-834) power plant and the potential coverup by the utility officials or NRC staff and all 01 communications to utility officials, specifically Chairman W. McCarthy, regarding the incident.

Lindsay Audin Requests copies.of all records received by NRC in '

(85-835) response' to Mr. C. MacDonald's February 24, 1984, inquiry to Mr. J.P.T. Martin of the Central Electricity Generating Board of Great Britain.

W.S. S_ chum, Requests copies of the latest IE Manual, Volume XI, Quality Technology Interpretations Section, and current NRC policy, guidance, Company or interpretation regarding the use, completion, or (85-836) processing of licensee reports required by 10 CFR 50.55(e).

(NRCemployee)- Requests records relating to his security clearance and (85-837) an 01A investigation.

(NRCemployee) Requests copies of specific records.

(85-838)

Doris C. Bryan, Requests copies of F01A-85-749, F01A-85-750, and Texas Nuclear printouts identical to those provided under those two (85-839) F0IA requests.

Jack F. Crawford, Requests a list of all nuclear power plants in Mandex, Inc.. the US.

(85-840)

CONTACT: Donnie H. Grimsley 492-7211 ENCLOSURE A DEC E~ E85

s 2

. Received, Cont'd Alan C. Brown, Requests all records used in or related to training l Miller & Chevalier related to radiation protection, including training l (85-841) used by regional offices for inspectors for work at fuel cycle facilities, records relating to testing techniques, and records relating to Reg. Guide 8.27.

John D. Trotter, Requests a copy of NUREG-1109, " Regulatory Analysis NUS Corporation for the Resolution of A-44."

(85-842)

Garth Wilson, Requests access to records concerning D0E.'s Vitro The Argee UMTRA Project.

Corporation (85-843)

Ellyn R. Weiss, Requests copies of all answers provided by the GPU Harmon & Weiss Nuclear Corporation to questions propounded by NRC (85-844) staff as an attachment to inspection report No. 50-289/

85-26.

Hossein F. Sadid Requests blank copies of draft inspection report forms (85-845) used for medical, industrial, and academic purposes.

Teresa S. Barnhart, Requests six categories of records regarding Vacancy .

NTEU-Steward Announcement No. 86-03365.

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(85-846)

(NRCemployee) Requests a ' copy of her security file.

(85-847)

Granted Billie P. Garde. In response to a request for all records to date related Government to the Loss-of-Load Test incident at the Palo Verde Accountability nuclear power plant discussed in NRC's October 2, 1985, Project letter to the utility, made available 22 records.

(85-696) Informed the requester that additional records subject to this request are already available at the PDR.

John Lapp, In response to a request for the names and prices for all Neal R. Gross and 'submitters of proposals in response to Request for Company,.Inc. Proposal No. RS-SEC-86-201 entitled " Stenographic (85-710) Reporting Services," made available one record.

Marvin M. Turkanis, In response to a request for a copy of all records Neutron Products, dealing with a complatit and/or notification by Siemens Inc. Corporation against Neutron Products regarding its (85-814) performance on a Siemens' teletherapy unit at Metropolitan Hospital, San Juan, Puerto Rico, made available five records.

ENCLOSURE A

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Grante'd, Cont'd Charles Barnes In response to a request for. copies of all facility (85-819) docket file records maintained in Docket 40-6175-SUB-143, which have been retired, made available 25 records.

Cindee Virostek, In response to a request for three specified records Kiski Valley .egarding the Nuclear Materials Equipment Corporation Coalition facility in Apollo, Pennsylvania, informed the requester (84-825) that we have referred these records to the DOE for a disclosure determination and direct response to her.

Denied James T. Lawless, In response to a request for access to Enclosure 1 of The Plain Dealer the November 4,1985, letter from Charles E. Norelius, (85-775) NRC, to Murray R. Edelman, The Cleveland Electric Illuminating Company, concerning allegations about improper work done by Metalweld, Inc., at the Perry nuclear power plant, denied the requested enclosure because disclosure of the information would interfere with an ongoing investigation.

Jim Pedro, In response to a request for enclosures to an NRC meeting NUS Corporation summary with Philadelphia Electric Company held on (85-798) October 1, 1985, regarding cracking in the re-circulation outlet safe ends, made available one record.

Denied portions of one record containing confidential business (proprietary) information.

ENCLOSURE A DEC 2 285

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WEEKLY INFORMATION REPORT DIVISION OF CONTRACTS WEEK ENDING DECEMBER 27, 1985 IFB ISSUED IFB No.: ADM-86-256

Title:

" Archival Storage" .

Description:

-The contractor shall provide an environmentally controlled and protected storage area for archival material.

Period of Performance: Two years Sponsor: Office of' Administration i

Status: IFB issued December 23, 1985. Bids due on January 22, 1986.

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ENCLOSURE A i DEC 2 " i??5 l

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OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending December 27, 1985 River Bend Station As part of its. power ascension program for the River Bend Station, the licensee initiated a planned outage and a loss of offsite power test on December 7, 1985.

River Bend subsequently returned to power on December 15, 1985, and expects to exceed 5% of rated power on December 20, 1985. The licensee plans to conduct additional tests at 20% of rated power on or about December 23, 1985, and then raise the power level 25% rated power.

Region IV reports that the offsite power-testing appears to have been successful. The staff expects to review the test results upon completion of the licensee's internal review.-

Gulf States Utilities received its low power license for River Bend on August 29, 1985, and exceeded 5% rated power for the first time on November 25, 1985. The project manager currently projects commercial operation to begin in the period of late February 1986 to Mid March 1986.

Salem Unit No. I and Turkey Point Unit No. 4 Salem Unit No.1 and Turkey Point Unit No. 4 have been selected by the International Atomic Energy Agency (IAEA) under Article 39(b) of the US/IAEA Safeguards Agreement for the application of IAEA safeguards, effective January 1,1986. These facilities will be subject to IAEA safeguards reporting and inspection requirements. The objective of the inspection is to permit the IAEA to verify that source and special nuclear materials are not withdrawn from the facilities.

ENCLOSURE B DEC S

1985

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l Rancho Seco Nuclear Generating Station Unusual Event The Rancho Seco Nuclear Generating Station is in hot shutdown for repair of a leaking valve in the pressurizer liquid sample line. At 7:34 p.m. (EST) on December 22, 1985, with the unit at 97% power, unidentified leakage of an estimated 3-4 gpm was observed from the reactorcoolantsystem(RCS). An Unusual Event was declared at 7:42 p.m. Subsequent estimates of the leakage, based on the water inventory pumped from the reactor building sump over time, placed the leak rate at 15-20 gpm. The source of the leakage was determined to be from a valve in the pressurizer liquid sample line (containment isolation val we SFV-70001). RSC samples were being taken through the normally open valve from the pressurizer liquid sample line 10 minutes before RCS leakage was discovered. Shutting the valve effectively stopped the leakage. Maintenance personnel in containment subsequently visually verified that the leakage was through the valve stem packing.

The event (i.e., leakage) lasted approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 20 minutes, and the total RCS inventory leaked was estimated-by the licensee to be roughly 1,640 gallons. Maintenance personnel are currently repacking the valve and reactor startup is anticipated upon completion of this effort.

Arkansas Nuclear One, Unit 1 (ANO-1)

A safety system functional inspection by IE personnel will be performed at ANO-1 from January 6, 1986, to January _ 31, 1986. An exit meeting with the licensee is anticipated for January 31, 1986. The inspection will consist of a detailed review of the AN0-1 emergency feedwater system. . The objective of the inspection is- to assess the operational readiness of the emergency feedwater (EFW)' system. ANO-1 is one of the two B&W operating plants which have implemented the Emergency Feedwater Initiation and Control System (EFIC) modification, which is a comprehensive Jafety grade EFW control. system that operates off of level sensors on the steam generator. Two additional EFW modifications are yet to be implemented at AN0-1. These include the steam generator over fill protection and a new condensate storage tank with associated piping and controls. The condensate storage tank will be seismic and tornado qualified. These modifications will be implemented during the next refueling outage which will take place in. August 1986. The inspection will be of a format.similar to that which was performed at

Turkey Point and Pilgrim. It is a fallout of the Davis Besse event, and it was requested by the EDO.

ENCLOSURE B DEC2" E5

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- 0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest i Week Ending December 27, 1985 Near-Term NRC Actions Under the Nuclear Waste Policy Act (NWPA)

Section: 137 of NWPA: Transportation of HLW Status: DOE issued the draft Transportation Institutional Plan in September,1905, with comments due to DOE by December 31, 1985.

Action: NRC staff is currently preparing formal comments for transmittal to DOE by December 31, 1985. DOE expects to issue the Final Transportation Institutional Plan by May,1936.

Section: 141(b) of NWPA: Submittal of MRS Proposal Status: Submittal by DOE to the Comission of the Monitored Retrievable Storage facility proposal was received by the staff on December 24. 1985.

Action: NRC will have 45 days to review the proposal and transmit coments to 00E. NRC's coments will be submitted with the proposal to Congress in early February,.1956.

Section: 141(d) of NWPA: Licensing of MRS .

Status: NRC is currently developing revisions to 10 CFR Part 72 to provide the licensing framework for the MRS, should it be authorized by Congress.

Action: The proposed rule on 10 CFR Part 72 was submitted to the Commission on November 25, 1985 for approval, which is expected in January, 1985.

Section: 306 of NWPA: Regulations for Training of Power Plant Personnel Status: The final rulemaking package on Part 55. dealing with simulator training requirements and three associated regulatory. guides is currently undergoing Office review. .

Action: The final rule will be submitted to CRGR for review in January, 1986, and then -to the Commission for approval .

Section: 121(a).of NWPA: EPA Final High-Level Waste Standards Status: EPA final rule for Environmental Standards for the Management

! and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Waste became effective November 18,1985 (50 FR 4003).

ENCLOSURE C

! DEC 2 '~ 1?f 5

Action: Staff is currently preparing revisions to 10 CFR Part 60 for conformance to EPA standards, and will submit a proposed rule to the Comission, currently scheduled for February 14, 1986.

Section: 114(a)(2)(A)ofNWPA: Second Repository -

Status: DOE plans to issue a draft Area Recommendation Report (ARR) on January 16, 1986. This report identifies 15-16 sites as possible locatiens for the second repository.

Action: NRC will comment on the report when it is issued.

Public Service Company of New Hampshire On December 19,1985, .Public Service Company of New Hampshire was issued Special Nuclear Materials License No. SNM-1963 for Seabrook Station, Unit 1,.

authorizing the receipt, possession, inspection, and storage of uranium enriched in the U-235 isotope contained in fuel assemblies. .The license also authorizes the receipt, possession, inspection, and use of other radioactive materials in the form of irradiation test capsules containin~g U-238 and Np-237, encore fission chambers and excore detectors containing uranium

enriched in U-235, and sources containing Pu-238, Pu-239, U-235, and U-238.

All materials are for eventual use at the Seabrook~ Station, Unit 1.

RER Postponement At the request of PG&E we have rescheduled the Diablo Canyon RER from January to May 1986. PG&E was concerned about overburdening their security management resources in January because they will~ be providing support for an unscheduled Unit 2 outage and are also being . impacted by an ongoing internal narcotics investigation. The NRC Resident Inspector is in favor of this postponement, and the Region and the NRR Project Managers concur. We~are making some adjust-ments to the RER schedule to accommodate this change and still permit accom-plishing'18 RERs this fiscal year. Except for the Diablo Canyon RER deferral, no other changes to the Operating Plan will be necessitated by these adjustments.

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NFS-Erwin Strike by 0 CAW members continues. There has been almost no negotiating between the. Union and NFS within the last 3 months, so resolution of the differences between the parties.is not expected in the near term. NFS is conducting limited operations of the HEU production, scrap ~ recovery, and R&D facilities.

Category II - Nonpower Reactor ~ Rule Dr. Carl Withee of the NMSS/SG staff,' queried the National Organization of Test, Research and Training Reactors (TRTR) on December 19, 1985 regarding the status of their effort to poll TRTR members concerning the proposed Category II nonpower rule. To date, 11 responses.have'been received and a few more are in preparation.

After TRTR has analyzed the comments,-they plan to meet with NMSS/SG and discuss their. conclusions (possibly'at the;end of January 1986). ENCLOSURE C DEC 2 71985

Office of Inspection and Enforcement Items of Interest Week Ending December 27, 1985

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

None.

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

a. PNO-II-85-121, Georgia Power Company (Hatch Unit 1), Flooding of Safety Equipment.

b. PNO-III-85-95D, Detroit Edison Company (Fermi.2 Nuclear Power Station), Damage to Diesel Generator During Testing (Third Update).

c. PN0-V-85-89, Sacramento Municipal Utility District (Rancho Seco Nuclear Utility District), Unidentified Reactor Coolant Leak at Rancho Seco.

d. PN0-V-85-90, Sacramento Municipal Utility District (Rancho Seco Nuclear Power Plant), Loss of Electric Power to Integrated Control System--Reactor Trip and Cooldown.

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

a. IE Information Notice 85-95, Leak of Reactor Water to Reactor Building Caused By Scram Solenoid Valve Problem, was issued December 23, 1985 to all boiling water reactor facilities holding an operating license or a construction permit.

b. IE Information Notice 85-96, Temporary Strainers Left Installed in 4

Pump Suction Piping, was issued December 23, 1985 to all nuclear power reactor facilities holding an operating license or a construc-tion permit.

4. Other Items None.

t ENCLOSURE D DEC 2 71985 l

OFFICE OF NUCLEAR REGULATORY RESEARCH Items of Interest Week Ending December 27, 1985 Results from CSNI International Standard Problem Exercise 18 The final comparison workshop for CSNI International Standard Problem Exercise 18 (ISP 18) was held at the Joint Research Center of the European Communities,-

Ispra Establishment on December 9-11, 1985.

The ISP was based on a 1 percent cold leg break LOCA experiment conducted in the LOBI-MOD 2 facility. LOBI-MOD 2 is a 1:712 scale model of a 4-log 1300MWE PWR, the facility was recently modified for a program of studies on small breaks and transients after an earlier series of experiments on large break LOCAs. The exercise was conducted " double blind", that is, the modelers did not

, have access to the experimental results and had not previously modeled the facili ty.

There were a total of 26 calculations submitted from twelve countries. The codes used included RELAP4/M006, RELAP5/M001, RELAPS/ MOD 2, TRAC-PFI/ MOD 1 and NOTRUMP-EQ. The NRC participated with two calculations, RELAPS/ MOD 2 and TRAC-PFI/ MOD 1. Three non-U.S. participants also used RELAPS/ MOD 2, while two used TRAC-PFI/ MODI.

The results show that the current prediction of system response is sensitive to accurate modeling of the break flow. This in turn is sensitive to the proper prediction of stratified flow in the cold leg. Most participants over predicted the system mass loss. Different participants using the same code generally obtained similar results, indicating that the user effect may be relatively small.

ENCLOSURE E DEC 2 71985 ly-

High Temperature Fission Product Release Program at ORNL The High Temperature Fissi'on Product Release program at Oak Ridge National Laboratory is being conducted to obtain confirmatory data on fission product release. The data is needed to reduce the uncertainty in the current data base on fission product release, and consequently the uncertainty in severe accident source terms. A laboratory scale furnace in a horizontal configuration was used for Phase I of the program where the maximum temperature tested was 2300K.

It is believed that the process of fuel dissolution due to chemical interaction with molten unoxidized cladding affects fission product release. To study this phenomenon, the horizontal furnace was reoriented in a vertical position for Phase II of the_ program to simulate more realistically the fuel rod geometry in a degrading core. The first test with the vertical furnace was conducted on December 17, 1985. The experiment was conducted with an Oconee fuel specimen (burn-up ~ 38 mwd /kgU) which was heated at 1 /see to 1400K, 2000K and 2300K with a constant temperature hold of 20 minutes at each temperature. The experiment wasstopped at 1400k was to obtain a uniform layer of oxidized zircaloy on the outer cladding surface. This was done to determine whether clad pre-treatment has any effect on the subsequent fuel liquefaction and fission product release. Steam-rich conditions were maintained throughout the test. Data analysis has begun and will be reported when they become available.

Effect of Radiation on Cesium Iodide Stability As reported previously a series of scoping experiments were conducted at Sandia National Laboratory to study the effect of ionizing radiation on the stability of Cs! during transport. Results from the experiments indicated a significant decomposition of CsI. Cesium was retained on the piping of the experimental apparatus and iodine was collected downstreain in the condensate tank. Many interpretations of the experimental observations have been proposed. In order to review these and other proposals and to discuss possible follow-on experi-ments a meeting was held at Argonne National Laboratory on December 12 and 13, 1985. Three independent consultants whose expertise lies in the area of radiation chemistry were invited to the meeting, Dr. A. Allen from Brookhaven National Laboratory, retired (also a member of APS Study Group), Dr. N. Bidler from Savannah River Laboratory and Dr. M. Sauer from Argonne National Laboratory. An important conclusion from the meeting was that gas phase interactions resulting in Csl decomposition by fon formation, radical formation, thermal degradation and oxidation are ruled out by analysis. An alternative mechanism of surface interaction between Csl and stainless steel was proposed. A clear consensus of recommendations pointed to the need to first obtain experimental confirmation of the current results and the role of a metal surface in Csl decomposition at Sandia, with certain improvements in procedure.

Another recommendation was that experiments should be conducted to indepen-dently confirm the Sandia results. Such experiments were proposed by Atomic Energy of Canada Ltd. (under consideration for EPRI sponsorship) to independently confirm the results of the Sandia experiments. It was also recommended that additional experiments should be conducted to expand the current test conditions to a wider range relevant to severe accidents.

ENCLOSURE E DEC 2 71985

Safeguards Research

" Safety / Safeguards Interactions During Safety-Related Emergencie.s at Nuclear Power Reactor Facilities," NUREG/CR-4093, (BNL), has been published by the Division of Risk Analysis and Operations, RES. The report contains an analysis of the safety / safeguards interactions that could occur during safety-related emergencies at licensed nuclear power reactors, and the extent to which these interactions are addressed in existing or proposed NRC guidance. The safety / safeguards interaction during a series of postulated emergencies was systematically examined to identify any potential performance deficiencies or conflicts between the Operations (safety) and Security (safeguards) organizations. This examination included the impacts of coordination with off-site emergency response personnel. Duties, responsibilities, optimal methods, and procedural actions . inherent in these interactions were explored.

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Purpose of guide is to: 1) assure adequate access'for safety purposes while providing necessary physcial security, 2) prcvide the protection of specified physical security equipment which, if sabotaged, could impact significantly security of the plant, and 3) provide guidance for key, lock, and combination changes when an employee with access to them leaves.

Contact:

K. Jamgochian, RES 443-7985 Recently Issued Publications Draft Regulatory Guide and Value/Inpact Statement: Guide for the Preparation of Applications for Licenses for Medical Teletherapy Programs (fecond draft, previously issued as TM 608-4), Task FC 414-4. Comments requested by Februa ry 21, 1986.

Contact:

P. Vacca (NMSS) (301) 427.-4002 Reg. Guide 1.153 - Criteria for Power, Instrumentation, and Control Portions of Safety Systems (Task IC 609-5) .

Reg. Guide 4.16, Rev.1 - Monitoring and Reporting Radioactivity in Releases of Radioactive Materials in Liquid and Gaseous Effluents from Nuclear Fuel Processing and Fabrication Plants and Uranium Hexafluorice Production Plants (TaskCE401-4) i ENCLOSURE E

ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING DECEMBER 27, 1985 International Meetings The following international meeting notices supplement those previously announced:

February 3-7, 1986, Vienna, Austria - IAEA Ad Hoc Advisory Group for International Conference on Technical and Economic Performance of Nuclear Power February 10-14, 1986, Vienna, Austria - IAEA Advisory Group Meeting on Nuclear Power Cost Data for Nuclear Power Planning Studies in Developing Countries

' March 11-13, 1986, Vienna, Austria - IAEA Advisory Group Meeting on Spent Fuel Management March 17-21, 1986, Vienna, Austria - IAEA Technical Committee Meeting on the Decontamination and Demolition of Concrete and Metal Structures During the Decommissioning of Nuclear Facilities May 12-16, 1986, Vienna, Austria - IAEA Technical Committee Meeting on the Event Oriented Assessment of Incidents in Nuclear Power Plants June 3-20, 1986, Bristol, UK - IAEA Interregional Training Course on Commissioning of Nuclear Power Plants September 9-11, 1986, Wuerenlingen, Switzerland - IAEA Specialists' Meeting on Power Supplies of Instrumentation and Control Systems in Nuclear Power Plants Foreign Trip Reports Robert W. Roussin, Director, Radiation Shielding Information Center, ORNL September 5-18, 1985; Visited the FRC and France:

The purpose of this trip was for discussions of radiation protection and shielding information exchange at the University of Stuttgart in the-FRG. Mr. Roussin also attended a meeting of shielding specialists at -

the Stuttgart Institute of Nuclear Energy (IKE) and was invited to-l attend the EEC EURADOS Working Committee #4 Meeting on numerical dosimetry. In France, Mr. Roussin made visits to 'the CEA/CEN-LEPF (shielding laboratory) in Paris and the OECD Nuclear Energy Agency Data

Bank in Saclay.

ENCLOSURE G

~DEC 2 71985

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s Guy H. Cunninabam, Executive Legal Director November 5-6, 1985; Visited France:

1 Mr. Cunningham attended, as the U.S. Representative, the meeting of the Group of Governmental Experts on Third Party' liability in the Field of .

s Nuclear Energy, held at the NEA in Paris. N ,

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OFFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA ,

ITEMS OF INTEREST ,

WEEK ENDING DECEMBER 27, 1985 AE0D Case Study C503, " Decay Heat Removal Problems at U.S. PWRs" was issued.

The study analyzes PWR experiences involving loss of decay heat removal (DHR) systems. Data analysis indicates that the root causes of most loss-of-DHR system events are human factors deficiencies involving procedural inadequacies and personnel crrors. Most of the errors were committed during maintenance, testing and repair operations. Several recommendations are presented to improve DHR system availability, including: upgrading coordination, planning and administrative control, surveillance, maintenance and testing performed during shutdown; providing operator aids to assist in recovering from s loss-of-DHR events; upgrading training and qualification requirements for operations and maintenance staffs; and implementing several hardware modifi-cations. . Th'is Case Study has been issued for information and appropriate action by NRR,

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ITEMS ADDRESSED BY THE COMMISSION - WEEK ENDING DECEf1BER 27, 1985 i

A. STAFF REQUIREMENTS - DISCUSSION OF 1986 POLICY AND PLANNING GUIDANCE, 2:00 P.M., TUESDAY, NOVEMBER 26, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to W. J. Dircks and J. E. Zerbe dated 12/23/85 ,

l The Commission met with the staff and OPE to discuss the draft document on 1986 policy and planning quidance.

The Commission requested that OPE highlight for Commission review the differences between the 1985 PPG and the 1986 PPG.

(Subsequently, on December 6, 1985 OPE provided to the Commission a draft 1986 PPG that highlighted the changes from the 1985 PPG.)

The Commission adopted the suggestion of the EDO that the PPG contain a discussion on reducing the number of challenges to safety protection systems.

Tue commission further requested a line-in line-out version of the 1986 draft PPG which would reflect Commission comments provided to the staff in the meeting and subsequent to the meeting. The following Commissioner comments should be represented in the draft:

Chairman Palladino:

For each of the mission areas provide a statement describing its relationship to a strategic goal or goals as a means of tying the mission areas to the strategic goals.

Attempt to bring together at one point in the document the general importance of research and the degree to which the Commission relies on data from research for making regulatory dec.isions.

The role of research should be indicated in the mission areas.

Consider including training of NRC employees that would contribute to a more effective interrelationship of staff to the licensee.

Highlight the discussion on technical specifications indicating their importance and the work to be done in the area.

ENCLOSURE O DEC 2 71985

A. CONTINUED Commissioner Roberts:

Reduce the discussion on the research program where it appears on pages 10, 11, and 12.

Commissioner Asselstine:

Include in the back part of the documeat as illustrative of excellence objective concepts such as honest assess-ments, valid analysis, effectiva decision making, and strong and vigilant management.

Say in the PPG what the priorities are with respect to the strategic goals.

Strategic Goal Four -- identify early technical 4 sues that must be addressed as part of the Commission. a licensing process for the repository and attempt to reach n scien-tifically defensible resolution of those issues.

Strategic Goal Four -- emphasize encouraging state and Indian tribe participation.

Strategic Goal Five -- emphasize that NRC personnel will receive training with respect to current developments and have as a goal within the training area insuring equal employment opportunity. -

Rephrase the paragraph on the cleanup of TMI-2. Also include the section on TMI-2 cleanup under the waste management section.

Oversee Operating Reactor Performance -- What does the second policy mean, what is it intended to convey and how does it modify the first policy. What message is the second policy trying to convey to the staff.

i

Monitoring performance (pages 13 and 14) -- strengthen by adding an element that the staff will prepare a set of performance indicators and a system for reporting plant performance information which will be used as the basis for evaluating plant performance.

l ENCLOSURE O DEC 2 71M

A. CONTINUED Research discussion (pages 10, 11 and 12) -- in addition to paring back on the discussion bolster the discussion in specific areas to show what specific contributions are expected of the research program in each area.

Containment performance (page 23) -- include an item on page 23 that says that the staff should develop a set of containment performance criteria that vill ensure safe and effective containment performance by all plants.

Safety goals (page 24) -- update item number 6 to say that the Commission is going to be working to develop a final set of safety goals during the current year.

Commissioner Bernthal:

Research -- should emphasize ct:at where a discussion of research programs or objectivas appears in the PPG, which relate to the Commission's overall policy, the discussion should state that the objectives should be met and tell what the Commission expects to be done.

Strategic Goal (page'8) -- NRC should have a program of instruction for field staff in particular on the kind of demeanor and professionalism that should be displayed in exercising dealings with licensees.

Emergency planning (page 13) -- consideration should be given to rewriting point five. Also on point six, the commitment to occupational radiation protection should be more positively stated.

Amendments (page 15) -- should discuss the milestones that the staff expects to achieve in the tech spec area and a discussion of the amendment problem.

Rewrite point one under planning guidance (page 19).

Source terms, point five (page 24) -- rewrite to say that specific changes to regulatory policies will be timely pursued when the reassessment ....

Staff should provide the Commission with a document that represents Commission policy on IAEA..

Consideration should be'given on developing new guidance on handling data, such as: ADP data handling, document handling and communications and having these functions administered by one office. ;

ENCLOSURE 0 DEC 2 7198

, A. CONTD4UED Commissioner Zech:

Plant performance (pages 13 and 14) -- The staff should develop operational criteria against which plant perfor-mance can be measured.

Staff and OPE should provide their recommendations to the Commission goals.

on expansion of the scope of the strategic Mission areas -- Consideration should be given to combining the Mission areas. Rather than have 12, reduce the number to seven.

Research -- Consideration should be given to revamping the discussion.on research and whether it is wise to separate it in the PPG from the mission areas.

Goal four (page 9) -- Rephrase the reference to the clean-up of TMI-2 but emphasize that the NRC supports the clean-up effort.

Goal.five (page 9) -- Should include a discussion of the NRC people programs and our emphasis on our human resources.

Also expand " Reorganize value of NRC employees" to indicate the importance the Commission places on its employees.

The reference to employees on page 38 should also be strengthen in a similar manner and provide a discussion on the ways employees may be encourage to be more effective and productive.

(Subsequently, on December 13, 1985, OPE provided a revised-version of the PPG which incorporated Commission comments at the 11/26/85 meeting as well as supplemental written comments from individual Commissioners.)

The Commission also requested that the staff provide recommendations on safety goals.

(EDO) (SECY Suspense: 2/14/86)

DEC 2 71955 ENCLOSURE O

B. STAFF REQUIkTMENTS - BRIEFING ON STATUS OF DAVIS-BESSE, 9:30 A.M.,

WEDN G AY, DECEMBER 18, 1985, COMMISSIONERS' CONFERENCE ROOM, D.C.

OFFICE (OPEN TO PUBLIC ATTENDANCE) Memo SECY to RECORD dated 12/26/85 The Commission met with staff and representatives of Toledo Edison to discuss the status of the Davis-Besse plant.

The following representatives of Toledo Edison were in attendance at the meeting:

John P. Williamson Chairman Joe Williams, Jr.

Senior Vice President-Nuclear Steve Smith Assistant Plant Manager, Maintenance John Wood

. Mechanical / Structural Engineering Manager Jacque Lingenfelter Operations Engineering Manager Sushil Jain Senior Nuclear Engineer Bill O'Connor Assistant Plant Manager Operations Phil Hilderbrandt Chairman Independent Process Review Committee (Consultant to Toledo Edison)

No staff requirements were issued following the staff and Toledo Edison presentations.

l DEC 2 71985 ENCLOSURE 0

E o

" NPR MEETING NOTICES

DECEMBER 27, 1985

$.3

DOCKET- APPLICANT /

DATE/ TIME NUMBER LOCATION PURPOSE ATTENDEES NRR CONTACT 1/7-9/86 50-410 Nine Mile Point Instrumentation and Control Niagara Mohawk M. Haughey 8:00 a.m.- Unit 2 Site Site Visit Power Corporat. ion

Scriba, N. Y.

1/8-9/86 50-461 Wed - P-110 Discuss fire protection issues Clinton Power Station B. Siegel 8:30'a.m. Thurs - 6507 MNBB associated with Clinton's Unit 1 recently submitted fire pro-

tection evaluation report 1/9/86 50-416 P-422 Request for additional Grand Gulf Unit 1 L. Kintner j 10: 00 a.m. Phillips Bldg. information regarding deferral

. of main steam turbine disc

. inspection 1/8-9/86 50-344 330-B Discuss current licensing Portland General D. Neighbors 9:00 a.m. Old Phillips Bldg. activities for the Trojan Electric Nuclear Plant i

1/13/86 50-461 P-110 Brief the new NRR organization Clinton Power Station B. Siegel

. Phillips Bldg. on the status of Clinton with Unit 1 regard to current and new j

l licensing actions i

1 1/14/86 50-316 P-422 Licensee and Exxon presentation Indiana & Michigan D. Wigginton i

10:00 a.m. Phillips Bldg. On Reload Documentation and Electric Company l- Evaluation to support Cycle 6

operation 2

i 1/29/86 P 50-321 Edwin I. Hatch Meeting with Georgia Power Edwin J. Hatch G. Rivenbark i' 8 50-366 Nuclear Plant Company (GPC) representatives Nuclear Plant

9:00 a.m.E Baxley, Georgia to discuss the-GPC plans related

[ to Hatch Unit 1 and 2

!

Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s)~

j in the NRC and local public document rooms

NHSS MEETING NOTICES FOR WEEK ENDING: 12/27/85 g Divisicn of Fuci Cycle and Matirial Safaty ,

O .

- DOCKET ATTENDEES /

NUtBER LOCATION PURPOSE APPLICANT NRC CONTACT 1w DATE/ TIME 1/7-9/86 40-8027 Ft. Smi th. To attend hearing on Sequoyah Fuels D. Cool (FC) Cool AK Corporation License Amendment for M. Horn (FC)

UF6 to UF4Conversion. E. Shum (FC) 1/15/86 Willste Meet with Waste Management Group (WMG) Odegaarden 9:00-12:00 5th Floor (Pete Tuite); discuss proposed R. Odegaarden (FC) conf room irradiated HDWR package - French H. Lee (FC)-

design. C. MacDonald (FC)

P. Tuite (WMG) ,

. Division of Safeguards None Division of Waste Management None P

8 E

m -

5

'O 1

ML20141E721

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