ML20140E758

Weekly Info Rept for Wk Ending 970418

ML20140E758
Person / Time
Issue date:	04/24/1997
From:	Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
SECY-97-089, SECY-97-089-R, SECY-97-89, SECY-97-89-R, WIR-970418, NUDOCS 9704290157
Download: ML20140E758 (25)

Text

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OI April 24.1997 SECY 97-089- )

i For: The Commissioners From: James _L. 'Blaha. Assistant for Operations., Office of the EDO  !

Sub.iect: WEEKLY INFORMATION REPORT - WEEK'ENDING APRIL 18, 1997 1

Contents Enclosure Nuclear Reactor Regulation A 1

-Nuclear Material. Safety and Safeguards B l Nuclear Regulatory Research C*  ;

Analysis and Evaluation of Operational Data D l

. General Counsel E*  !

Administration F Chief Information Officer G  !

Chief Financial Officer H* I Personnel I J Small Business & Civil Rights J* i Enforcement K* i State Programs L* i Public Affairs M International Programs- N-Office of the Secretary 0* ,

Region I P '

Region II P Region III P <

Region IV P Executive Director for Operations 0*

Congressional Affairs R

• No input this week. .

.g,; :-Qn2d by Jmnes L. Blaha James L. Blaha Assistant for Operations, OEDO

Contact:

q</-g(-

G. Tracy. OEDO Document Name: C:\WE K418. i ah O 97 04Pjn'97 y b toe 04/; 7g cp J BiE @idsEss,CUfY n00114 9704290157 970424e i PDR COMMS NRCC MEEKLYINFOREPT PDR

a UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D. C. 20665 INFORMATION REPORT l l

April 24.1997 SECY 97-089 l l

l For: The Commissioners From: James L. Blaha. Assistant for Operations. Office of the EDO Subiect: WEEKLY INFORMATION REPORT - WEEK ENDING APRIL 18. 1997 Contents Enclosure Nuclear Reactor Regulation A i Nuclear Material Safety and Safeguards B i Nuclear Regulatory Research C*

Analysis and Evaluation of Operational Data D ,

General Counsel E* I Administration F l Chief Info'rmation Officer G l Chief Financial Officer H* l Personnel I Small Business & Civil Rights J*

Enforcement K*

State Programs L*

Public Affairs M International Programs N Office of the Secretary 0*

Region I P Region II P Region III P Region IV P Executive Director for Operations 0*

Congressional Affairs R

• No input this week.

^

. Blaha Assistant for Operations. OEDO

Contact:

G. Tracy. OED0'

a Office of Nuclear Reactor Regulation Items of Interest Week Ending April 18. 1997 Thermo-Lao Status -- Davis-Besse Nuclear Power Station On April 3. 1997, the NRC staff met with Centerior Energy, the licensee for Davis Besse Nuclear Power Station, to discuss the status of Thermo-Lag corrective actions. The licensee has decided to eliminate reliance on Thermo-Lag fire barriers by circuit modifications, fire hazard reanalysis, and 4 installing alternate fire barrier materials. The licensee has a five phase

. program. Phase I consisted of removing the Thermo-Lag from circuits in three rooms and from fire dampers in five rooms. Phase I is complete. Under  ;

Phase II. which is scheduled for all of 1997 and the first two quarters of 1998, the licensee will remove the Thermo-Lag from containment and install new radiant energy heat shields. Under Phase III which is scheduled for the second and third quarter of 1997 the licensee will install new fire barrier material for circuits for which it had removed the Thermo-Lag during Phase I.

Under Phase IV. which is tied to Cycle 11 Refueling outage scheduled for the second quarter 1998, the licensee will remove the Thermo-Lag radiant energy heat shields from the annulus and install new 3-hour fire barrier material.

Under Phase V, which is scheduled for the third quarter 1997 through all of 1998, the licensee will complete the installations on circuits that had the Thermo-Lag removed in Phase III. The licensee plans to complete its program by the end of the fourth quarter 1998. The licensee is considering accelerating its schedule to be complete by the end of the second quarter 1998. On the basis of the information provided by the licensee during this

, meeting. the staff concluded that the licensee is applying appropriate i management attention to the Thermo-Lag issues at Davis Besse, is making progress towards the overall resolution of the issues. and the completion schedule is acceptable.

i Thermo-Lao Status -- River Bend Station i On April 8.1997, the NRC staff called Entergy Operations. Incorporated, the licensee for River Bend Station. Unit 1 (RBS). to discuss its corrective

" action schedule and to obtain information needed to determine whether or not a management meeting was needed. During the call, the licensee demonstrated

management involvement in resolving the Thermo-Lag issues. The licensee also demonstrated that it has made measurable progress towards overall resolution of the issues. For example, the licensee is implementing 10 plant modifications to fully resolve the Thermo-Lag issues. These include for example. Thermo-Lag removal and cable rerouting. The licensee has removed all Thermo-Lag from the containment and has removed about 80 percent of the other Thermo-Lag barriers that it plans to remove. The licensee plans to complete all of the modifications during the September / October 1997 refueling outage.

On the bases of the information provided during the call, the staff concluded that the licensee has been and will continue to make ]rogress towards the overall resolution of the Thermo-Lag issues at RBS. t1e completion schedule is acceptable, and a senior management meeting is not needed.

APRIL 18. 1997' ENCLOSURE A 4

3 Thermo-lao Status -- Limerick 1 and 2 and Peach Bottom 2 and 3

. On April,14, 1997, the NRC staff met with representatives of PECO Energy

. Company, the licensee for Limerick Generating Station. Units 1 and 2. and Peach Bottom Atomic Power Station. Units 2 and 3. to discuss the status of i Thermo-Lag corrective actions. The licensee has installed substantial amounts of 1-hour and 3-hour Thermo-Lag fire barriers at Limerick and 3-hour barriers at Peach Bottom. The licensee is in the ]rocess of completing a safe shutdown

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reanalysis which it initiated in 1992. T1e revised safe shutdown J configurations include the ccmbining of fire areas and new manual operator actions. The licensee expects that the safe shutdown reanalysis will eliminate the need for up to 70 percent of the Thermo-Lag fire' barriers. For

the remaining barriers, the licensee is considering exemptions, circuit modifications, upgrades, and replacement with other fire barrier materials. ,

The licensee stated that it will require two outages to complete corrective actions at both Limerick (April 1998 for Unit 1 and April 1999 for Unit 2) and at. Peach Bottom (October 1998 for Unit 2 and October 1999 for Unit 3). The licensee has not completed the preparatory work needed to complete modifications and is not considering accelerating its schedule. On the basis of the information provided by the licensee during the meeting, the staff could not evaluate the progress made by the licensee. Before the staff can fully assess the acceptability of the licensee's schedule, additional details of the work already performed and a detailed plan to complete corrective actions are needed. The staf f will meet again with the licensee to discuss the details of the licensee's plans and schedules. -

Calvert Cliffs Unit 2 -

During a diving operation in the Unit 2 Spent Fuel Pool on April 3.1997, to '

repair components affecting the operation of the Unit 2 fuel handling transfer  :

cart /upender, a diver left the approved diving area, moved to an area that was i in closer proximity to stored spent fuel, and received an unplanned exposure when he entered a significantly higher radiation field. The event occurred due to lack of continuous visual observation of the diver, a misunderstanding ,

of the limited extent of the a] proved dive area (an area that was '

comprehensively surveyed and claracterized to support diving operations, i.e. .

general area dose rates between 50 and 100 millirem per hour), and a lack of ,

understanding of the approved work. While, direct visual observation was not -

maintained.. remote monitoring of the divers multiple dosimetry systems and I survey probes by the assigned radiation protection technicians indicated that I the diver had entered a high radiation field of 9 rem per hour and increasing. l Consequently, the diver was warned and prevented from further exposure and was subsequently removed from the spent fuel pool.

.. Preliminary evaluation based on the multiple TLD (thermoluminescent dosimeter) elements that the diver was wearing indicates a whole body exposure of 245 millirem and an extremity exposure (right hand) of 790 millirem, compared to I annual regulatory limits of 5000 millirem, total effective dose equivalent (whole body) and 50.000 millirem, maximum shallow dose equivalent for  ;

extremities. While significant personnel exposure was averted in this instance, due to the quick actions of the assigned radiation protection APRIL 18. 1997~ ENCLOSURE A i

technicians in responding to alarms from the diver's teledosimetry systems.

. potential for significant personnel exposure existed. Post dive surveys, performed to characterize the area that the diver entered, revealed accessible l (within a few feet of where the individual was warned of the increasing radiation field) dose rates in excess of 12,000 rad per hour due to the

proximity of stored spent fuel.

l While no exposure in excess of regulatory limits is apparent, based on preliminary assessment, the individual has been restricted by the licensee from performing further radiological work activities until a final exposure evaluation is completed.

l Nine Mile Point Unit 1 On April 14, 1997, the NRC held a public meeting in Fulton, N.Y., to discuss.

l the cracks in the Unit 1 core shroud and anomolies regarding the design and installation of the shroud tie rod assemblies. The meeting was well attended by local citizens and officials who demonstrated concern for the safety of the facility and asked several related questions regarding the associated

. evaluations and plans.

The NRC staff is reviewing proposed modifications to the tie rod assemblies and will complete the review prior to restart. The licensee's present schedule for restart is April 30, 1997.

Watts Bar -- TVA Proceedina with SFP Rerackina The TVA licensing contact for Watts Bar informed the PM on April 15 that TVA is ]roceeding with the reracking of the Watts Bar spent fuel pool in advance of laving an amendment of the license authorizing installation of the replacement racks.

The unit is currently in its first fuel cycle. The current racks only have a capacity of 484 fuel assemblies. TVA plans to replace them with racks previously used at Sequoyah for 13 years for a capacity of over 1300 fuel assemblies. The staff is reviewing TVA's application to install the Sequoyah racks in the Watts Bar pool and does not expect to complete its review until mid-summer 1997.

The PM consulted with the Plant Systems Branch and no reason has been identified to preclude TVA from removing the current racks from the pool or from -installing the Sequoyah racks in the Watts Bar pool. TVA understands that they are proceeding at their own r.isk under this ap3 roach and will have

to keep the fuel in the reactor until the staff issues t1e amendment to the

license authorizing use of the replacement racks specifically for use at Watts Bar or', failing that, until TVA reinstalls the original racks.

l The first refueling outage for Watts Bar Unit 1 is scheduled to begin

September 6. 1997. The new fuel for that outage is scheduled to arrive onsite i about mid-July.

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laSalle Units 1 and 2 -- Confirmatorv Action Letter Supplement issued Both units at LaSalle have been shutdown since September 1996 due to various material condition human performance, corrective action process, and design issues. On April 14, 1997. the NRC issued a CAL to LaSalle to require certain actions prior to restart of either unit. The CAL is a supplement to the CAL issued on July 2,1996, in response to an event in which ex)andable foam grout i was injected into the service water tunnel. The revised CA_ confirms the licensee will:

(1) develop and docket a restart plan:

(2) update the NRC on the projected startup date to facilitate NRC inspection planning:

(3) meet with the NRC monthly to discuss startup plan implementation:

(4) meet with the NRC after completing the high intensity training program a for licensed operators: and

(5) meet with the NRC when one of the units is ready to restart.

A Plant Performance Improvement Review Panel consisting of regional and headquarters personnel meets approximately twice a month.

Status of Review of Licensee Resoonses to 50.54(f) Reauest on Desian Bases Phases 1 and 2 of.the process for reviewing licensee responses to the 10 CFR 3

50.54(f) request for information on design bases are complete. In addition, the Regions and NRR have completed the initial effort for Phase 3 with a i

presentation of the results of the reviews at their respective Plant Performance Review /10 CFR 50.54(f) Assessment meetings.

During the weeks of April 7 and 14, 1997, regional management discussed the i

results of their reviews at the Senior Management Meeting screening meetings.

, Phase 3 will culminate in May 1997 with a status report to the Commission on the results of the initial reviews of the responses, identification of insights gained to date, and the recommendations for Phase 4 of the 4

initiative.

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l APRIL 18, 1997 ENCLOSURE A l

Office of Nuclear Material Safety and Safeguards items of Interest Week Ending April 18. 1997  !

Site Visit to Westinahouse Columbia Fuel Facility l

On April 15. 1997. Nuclear Regulatory Commission staff visited the Westinghouse Electric Corporation Commercial Nuclear Fuel Division facility in i Columbia South. Carolina. One purpose of the visit was to familiarize  !

licensing staff and managers with the site and to-improve familiarity with '

fuel fabrication technology and . terminology. This.part of the visit consisted of an entrance meeting and a walk through the complete plant. including uranium hexafluoride vaporization, ammonium diuranate conversion, pellet j production, rod loading. assembly production, scrap recovery, and waste management areas. The visit also included discussions regarding implementation of. risk-informed. performance-based conditions for criticality safety in Westinghouse's license. and the amount of flexibility the licensee has to change the basis for criticality safety without seeking a license amendment or prior review by.the NRC. ,

West Valley Citizen Task Force Video Conference ,

On April 15. 1997. Nuclear Regulatory Commission staff participated by video conference in the seventh of a series of public meetings of the West Valley Citizen Task Force. This Task Force was convened in early 1997 by the Department of Energy and the New York State Energy Research and Development Authority for advice on the decommissioning and closure of the Western New York Service Center after completion of the West Valley Demonstration Project.

near Springville and Ashford. New York. The meeting focused on erosion at the West Valley site. its potential impact on the long-term stability of radioactive waste disposal facilities. and the risk to the public. The Task Force requested that the NRC participate in a meeting on May 20. 1997, as a i follow-up to NRC presentations made at the April 2. 1997. Task Force meeting.

Task Force participants expressed concern about time constraints and about the need for timely guidance from NRC regarding potential application of the draft final rule on radiological criteria for decommissioning, which is currently  :

being reviewed by the Commission. The Task Force is particularly interested in regulatory alternatives to deal with closure of radioactive waste facilities at West Valley that could exceed the 500 millirem / year dose cap in the draft final rule.

Interaaencv Workina Grouo on the Transoort of Radioactive Materials  :

On April 15, 1997, the Interagency Working Group on the Transpcrt of Radioactive Materials met at the Department of Transportation (DOT) headquarters in Washington. D.C. Attendees included staff from the Nuclear Regulatory Commission's Spent Fuel Project Office -DOT and the Department of Energy. Issues discussed included: planning and coordination for upcoming International Atomic Energy Agency meetings, status of jointly-funded guidance development for transport of radioactive materials. NRC's rulemaking for '

fissile material transport. status of uranium hexaflouride overpack APRIL 18' 1997

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I revalidation, and follow-up to an American Association of Railroads meeting on

-the transport of spent fuel.

Interest in Establishina Indeoendent Soent Fuel Storace Installations Representatives from the utilities operating the Duane Arnold. Peach Bottom and Palo Verde Nuclear Power Reactors have contacted the staff of the Spent Fuel Project Office (SFPO) to discuss establishing independent spent fusi storage installations (ISFSIs) at their facilities by 1999. The SFP0 staff met with representatives from Duane Arnold and Peach Bottom (April 3 and 10, respectively) .to discuss their plans and lessons-learned experience on licensing an ISFSI. In the next week. SFP0 expects to meet with 1 representatives from Palo Verde.  ;

Welds on UF6 Cylinders Found in Nonconformance with Reauirements On /gril 9-11. 1997, Spent Fuel Project Office (SFPO) staff conducted an inspection of the fabrication of Model =30 cylinders, used for transportation of uranium hexafluoride (UF6), at Amer Industrial Technologies. Inc. , in Wilmington, Delaware. A representative of the Department of Transportation (DOT) and a staff member from the Nuclear Regulatory Commission's Region I .

office also participated in the inspection. The inspection' team identified  !

. welds on 130 cylinders, manufactured in 1995 and 1996, that were not made in accordance vith the standard, ANSI 14.1, required by the NRC Certificate of Compliance and DOT regulations. In addition, the team noted that the  :

implementation of the quality assurance program was weak. The team presented their prelin.inary findings to Amer representatives in an exit meeting on April .11, 199'/ .

SFP0 has issued an Information Notice informing cylinders users of the issues identified in the inspection. DOT is reviewing appropriate enforcement action.

Nuclear Reaulatory Commission Staff Briefs U.S. House of Reoresentatives Staff on the Reaulation of Mixed Waste On April 11. 1997. Nuclear Regulatory Commission staff from the Division of Waste Management and the Office of Congressional Affairs met with staff

members of the House Committee on Commerce and staff from the office of i

Congressman Michael G. Oxley, at the Rayburn Office building in Washington.

D.C. . The purpose of the meeting was to provide an overview of the NRC's role in the regulation of commercially-generated mixed waste and to discuss current l issues associated with the regulation of mixed waste. Mixed waste is waste

that contains both radioactive material subject to regulation by NRC or L

-Agreement States under the Atomic Energy Act, and hazardous waste subject to regulation by the Environmental Protection Agency (EPA), or EPA Authorized States, under the Resource Conservation and Recovery Act. The Committee staff indicated they had previously been briefed by EPA staff on EPA's role in regulating mixed waste and that the meeting with NRC was intended to provide

them with a better understanding of NRC's role in regulating commercially-l generated mixed waste.

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I Meetino on Savannah River Hiqh-level Waste Tanks On April 15, 1997. Division of Waste Management staff met with Department of I' Energy (DOE) representatives from the Savannah River Site (SRS) in South Carolina. The meeting was held as a follow-up to a December 20. 1996, le'ter requesting Nuclear Regulatory Commission review of DOE's methodology for the  !

classification of the residual wastes remaining in 51 high-level waste (HLW) tanks once the tanks have been emptied of their contents. The DOE methodology uses the criteria specified in a March 1993 letter from NRC to DOE to classify the residual wastes as " incidental." The 1993 criteria were developed for the removal of wastes from HLW tanks, and NRC staff will evaluate the criteria to .

determine their applicability to the residual wastes remaining in the SRS l tanks. The results of the NRC staff evaluation will then undergo Commission review. DOE waste classified as " incidental" would not be subject to NRC i licensing.  !

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( Office for Analysis and Evaluation of Operational Data Items of Interest l Week Ending April 18, 1997 Reaional Radiological Fmeraency Prenaredness Conference -

The Director of AEOD and support staff attended the Regional Radiological Emergency Preparedness (REP) conference in Eureka Springs. AR on April 15-17.

l 1997. Commissioner Dicus was a featured speaker along.with Dr. Ross of AE00 l at this c W erence. This regional conference provides an opportunity for emergence .soonders from the local. State, utility and Federal organizations within F 'A Region VI and at the national level to address issues related to implementation of the REP program. The conference is held every year at a different location and is sponsored jointly by FEMA Region VI and NRC Region IV.

PRELIMINARY NOTIFICATIONS (PNs)

a. PNO-I-97-022. Gpu Nuclear Corp. (0yster Creek-1). GPU. INC. ANNOUNCED INTENT TO EXPLORE OPTIONS RELATIVE TO FUTURE OPERATION OF OYSTER CREEK GENERATING STATION

b. PNO-I-97-023. Merck and Company. Inc., LOSS OF 880 MICR0 CURIES OF 10 DINE-125

c. PNO-III-97-031. Commonwealth Edison Co. (Quad Cities 1 2). OUTAGE DUE TO INOPERABLE 4 KV BREAKERS

d. PNO-III-97-032. Commonwealth Edison Co (D.resden 2 3). OUTAGE DUE TO l INOPERABLE MERLIN-GERIN BREAKERS

e. PNO-III-97-033. Cozzi Iron and Metal. RADI0 ACTIVE SCRAP METAL AND RADIUM INSTRUMENT DIALS FOUND

f. PNO-III-97-034. Commonwealth Edison Co. (Zion 1 2). DECISION NOT TO REPLACE STEAM GENERATORS

g. PNO-IV-97-019A. Mattingly Testing Services. Inc.. UPDATE ON THEFT OF RADIOGRAPHIC EXPOSURE DEVICE (Event: 32084)

APRIL 18. 1997 ENCLOSURE D

Office of Administration Items of Interest-Week Ending April 18. 1997 Access-to and Protection of Classified Information (Parts 25. 50. 54. and 95)

A final rule that amends regulations ap311 cable to .the protection of and access to classified information was pu]lished in the Federal Register on 1 April 11, 1997 (62 FR 17683). The final rule ensures that classified information in the possession of NRC licensees and others under NRC regulatory requ'irements is protected in accordance with current national policies. The

final rule becomes effective May 12, 1997.

Abnormal Occurrence Reports: Imolementation of Section 208 Enerav Reoraanization Act of 1974: Revision to Policy Statement

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A revised. policy statement concerning the submittal of abnormal occurrence reports to Congress ',tas published in the Federal Register on April 17, 1997

.(62 FR 188?0). The policy statement presents the revised criteria the ,

Commission will use in -submitting the annual abnormal occurrence reports to  !

Congress and to the public. The policy statement became effective April 17, 1997. -

I Rules Activity The Rules and Directive Branch (RDB) reviewed a draft rule making plan concerning recycle and reuse and provided guidance to RES staff on the OFR requirements concerning incorporation by reference, RDB suggested alternative approaches to address EPA regulations in 10 CFR Chapter 1, DOE- Tritium Irradiation l On April 14. 1997, the Director. Division of Facilities and Security (DFS) and staff met with DOE Office of Safeguards and Security staff to discuss Cognizant Security Agency (CSA) responsibilities for the classified aspects associated with DOE's tritium irradiation test at a commercial light water

reactor (CLWR). The facilities include TVA's Watts Bar and Westinghouse at 4 Columbia, SC. NRC has agreed that DOE would be the CSA for' this testing effort: that NRC would be provided copies of approved security plans to protect classi fied information and material: and that NRC would be kept apprised of any security reviews. .This agreement will be re-evaluated following the testing phase and prior to the initiation of any long-term DOE contract to use an NRC regulated CLWR for this activity.

Foreion Ownership. Control or influence (FOCI)

! On April 14. 1997, a DFS representative met with DOE representatives to discuss a FOCl case involving a NRC'10 CFR Part 95 licensee that is bidding on a DOE classified contract. DOE will take the lead on this case Because of shared interes'ts, NRC and DOE will work together in making this FOCI

determination.

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APRIL 18, 1997' ENCLOSURE F

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Security Advisors Meetina On April 15. 1997 DFS held the first of the FY 1997 semi-annual Security Advisors meetings. The Chief. Mail Section. Division of Administrative -

Services, was the guest speaker and discussed the mail room procedures for '

l screening mail and packages. In addition the following security related l topics were discussed by DFS staff members: NRC's Drug Testing Program:

, heightened security measures implemented during April 1997: the new automated l system for controlling classification-actions; facility security upgrades I (e.g., perimeter fence lighting. guard booth): and the plans for development l of a Security Home Page. Twelve Security Advisors attended the meeting. The I next meeting will be scheduled in September 1997. l 4

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Chief Information Officer Items of Interest Week Ending April 18, 1997 Reouests Received durino the 5-Day Period of April 10. 1997 - Aoril 17. 1997:

1 Temet USA Inc., exempt license and device safety evaluation application for a  !

gas and aerosol detector. (F01A/PA-97-0134) l San Onofre and Palo Verde plants enforcement activity.1988 to present. I (FOIA/PA-97-0135) l 1

Oconee plant. Duke Power Co. , 01 report of 9/24/96 incident involving named individual. (FOIA/PA-97-0136)

Advanced Medical Systems. Inc., test results relating to Tank 222 and its contents. (F01A/PA-97-0137) I Investigation of possible exposure of named individual to unauthorized' l materials transferred by ITT and DYNACORE. (F01A/PA-97-0138) 1 Global Management Systems Inc., contract no. 33-93-194. (F01A/PA-97-0139) l Anstec Inc., contract no. 33-93-201. (F01A/PA-97-0140)

Niagara Mohawk Power Corp.,1994 discrimination case and related EA-96-116.

(F01A/PA-97-0141)

Comprehensive Medical Evaluations. North Bergen. NJ.. radioactive materials license. (F0IA/PA-97-0142) i Solicitation Number RS-IRM-97-171. (FOIA/PA-97-0143) i Crystal River plant. Florida Power Corp. - any records re mismanagement and ,

safety issues from 4/95 through 4/97. (FOIA/PA-97-0144) l Reouests Comoleted:

96-351 96-444 96-466 97-020 (No PDR) f 97-064 97-106 l

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Office of Personnel Items of Interest Week Ending April 18. 1997 Arrivals KALYANAM, Nageswaran PROJECT MANAGER (PFT) NRR RHOTEN. Robert SECRETARY (OPFT) OP/SPAC Departures l FAULKINGHAM. Sydney SECRETARY (OPFT) RI ,

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0 APRIL 18. 1997 ENCLOSURE I

Office of Public Affairs Items of Interest Week Endiig April 18, 1997 Media Interest Chairman Jackson and Joe C?llan were interviewed separately by Inside NRC.

The Washington Post Sunday magazine is planning a story on Peter Atherton, the former NRC employee who raised safety concerns at Maine Yankee some twenty years ago.

School Volunteers Procram She was Debbie Jackson. NRR, is continuing a tutoring program at Rudolph E.S.

also a judge in the Junior / Senior Division of the Prince George's County Science Fair Reginald Mitchell discussed NRC careers at Tilden M.S.

Ramin Assa. Ronaldo Jenkins, Vern Hodge, Tommy Le, George Hubbard, David Matthews. NRR, John Craig and Prasad Kadambi, RES, Heather Astwood and Mysore Natarja. NMSS. were judges in the Montgomery County Area Science Fair.

Winners were invited to NRC to display their projects for the Commission and NRC staff on May 14.

Press Rehases Headauarters:

NRC Releases B&W Apollo Site in Pennsylvania for Unrestricted 97-061 Use NRC Releases Inspection Results for Sierra Nuclear Dry 97-062 i Storage Cask NRC Advisory Committee on Reactor Safeguards to Meet May 1-3 97-063 Recions:

NRC Names New Resident Inspector at Peach Bottom Atomic Power 1-97-41 Station 7 11-97-33 Westinghouse Tells NRC Misplaced e sctor Fuel Rods Found at Temlin Nuclear Power Plant in Czech Republic III-97-37 NRC to Hold Predecisional Enforcement Conference With Centerior Service Co. on Apparent Violations of NRC Requirements at Perry Plant ENCLOSURE M APRIL 18. 1997-

111-9/-38 NRC t1 Hold Predecisional Enforcement Conference with Mallinckrodt Medical Inc. on Apparent Violations of NRC Safety Requirements 111-97-39 NRC Staff Issues Letters to Commonwealth Edison Co. on Actions to be Taken Prior to Startup of Zion and LaSalle Nuclear Plants

IV-97-28 NRC, NPPD to Meet for Discussion on Possible Violations at Cooper Nuclear Station l

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Office of International Programs items of Interest Week Ending April 18, 1997 Foreion Visitors -- France Carl Paperiello, John Greeves and members of the Waste Management staff met recently with six members of the French HLW National Assessment Committee for an exchange of views. The visiting delegation was led by M. Tissot Chairman of the Committee and member of the French Academy of Science. The National Assessment Committee was established by law to review research and associated activities relating to the disposal of HLW in France and to make annual recommendations on the further direction of the national program. The i Committee's final report is scheduled for issuance in 2006 in conjunction with the planned start of site activity on a permanent geologic repository in 2010.

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I Region I ltems of Interest Week Ending April 18. 1997 NRC Staff Meetina with Heritaae Minerals. Inc.

On April 10. 1997 representatives of Heritage Minerals. Inc. (HMI). the New Jersey Department of Environmental Protection, and NRC staff met at the Region 1 Office in King of Prussia. Pennsylvania. A representative from the NMSS cision of Waste Management participated by telephone. The purpose of the

, eting was to discuss the licensee's final status survey plans for the NRC-i censed portions of the site, which include two buildings and a monazite sand pile comprising approximately one-half acre. The NRC-licensed portion of the site is within a former processing area of 150 ac.es to be remediated in accordance with Stat: of New Jersey regulations. The HMI site is an NRC Site Decommissioning Management Plan site. The licensee expects to request license termination by the Fall of 1997.

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APRIL 18. 1997 ENCLOSURE P L-

Region II Items of Interest Week Ending April 18, 1997 International Visitors Hosted by Reaion II On April 14. the Region hosted a group of International visitors, representing the countries of Russia and Armenia, on a visit and tour of the Barnwell Low-Level Radioactive Waste Disposal Facility located in Snelling. South Carolina.

The group is currently on a Decommissioning Study Tour in the U. S. , and during tnis visit they had the opportunity to meet with officials of the State of South Carolina, and management representatives of the Chem-Nuclear Systems.

Inc.

After departing South Carolina. the group was scheduled to visit the Yankee- '

Rowe facility, which is currently being decommissioned.

Southern Nuclear Ooeratina Comoany Representatives from Southern Nuclear Company were in the Regional Office to attend two Predecisional Enforcement Conferences. The first meeting was held to discuss the transportation of a Jackage which exceeded dose rate limits at Vogtle, and the second meeting was 1 eld to discuss associated penetration room filtration systems at Farley.

Tennessee Valley Authority -- Browns Ferry The Director. Division of Reactor Safety, attended the exit of the Maintenance i Team Inspection at the Browns Ferry plant. The inspection team found that TVA had developed a very good program for implementation of the maintenance rule 1 at Browns Ferry. One issue developed was the status of the maintenance rule program for Unit 1. which has been shutdown and defueled for over ten years.

The maintenance rule implementation for Unit 1 addresses those systems relied upon by the operating units, but it does not address other systems (i.e.. Unit 1 only systems). Thus the team had no concerns with TVA's implementation of

! the rule from a safety perspective at Browns Ferry, but did develop a question l of whether TVA's implementation of the maintenance rule met the regulatory requirements for Unit 1.

Seouoyah On April 17. TVA management met with Region II management to discuss the results of a recent licensee assessment of performance problems at Sequoyah I

and proposed actions. The licensee also presented charts of Sequoyah using i the Arthur Anderson perforniance measuring methodology.

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Carolina Power and light Company - Brunswick l l

Brunswick Unit 1 completed staff training, equipment checks, and calibration l the first part of this week in preparation for implementation of their five percent power uprate.

Westinghouse - Two low-Enriched Uranium Fuel Rods Inadvertently Shioned by Westinghouse to the Czech Republic On April 15. 1997, the Westinghouse Electric Corporation's Commercial Nuclear l Fuel Division Columbia Plant in Columbia. South Carolina informed NRC that two low-enriched uranium fuel rods could not be located. The licensee had fabricated the rods in late 1996 and had initiated an investigation to locate ,

them on March 24, 1997. Each fuel rod contained approximately 1588 grams of uranium and 57 grams of U-235 (3.8 weight percent U-235). On April S. the licensee determined that the two rods might have been inadvertently included in two replica (non-fuel containing) assemblies manufactured by Westinghouse and sent to the Czech Republic for training purposes. On April 17, the licensee's investigation confirmed that the two rods were located in the replica assemblies at the Temelin reactor.

The State of South Carolina has been notified. NRC has informed the International Atomic Energy Agency staff responsible for tracking i international transfers. The NRC has also notified the Department of Transportation. .

1 The NRC, Office of Nuclear Materials Safety and Safeguards and Region II will I conduct a special inspection of the incident.

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Region III Items of Interest Week Ending April 18. 1997 Confirmatory Action Letters issued to Common':ealth Edison Companv On April 14. 1997. Confirmatory Action Letters (CAL) were issued by NRC Region III to Commonwealth Edison Company regarding concerns with LaSalle and Zion Nuclear Power Stations. The CALs document Comed's agreement to: develop plans to address corrective actions for the various performance deficiencies at Zion and LaSalle and submit the plans to the NRC. The plans will include the utility's criteria for assessing the effectiveness of the corrective actions: keep the NRC staff informed of the projected startup dates for the two plants; meet with the NRC periodically to discuss the status of the correctivs action plans: meet with the NRC following the completion of the evaluation and training 3rograms for reactor operators at the two plants to discuss the results of t1e training activities: and meet with the NRC to discuss the readiness of the initial unit at each site to resume operations once the utility has determined that the unit is ready for restart.

Manaaement Meetina with Commonwealth Edison Company On April 14, 1997, a management meeting was conducted in the Region III Office. Lisle. Illinois, between management representatives from Commonwealth Edison Company and members of the NRC staff to discuss the status cf Dresden Nuclear Power Station's progress in completing the actions outlined in the November 1996 Confirmatory Action Letter and other improvement initiatives.

Manaaement Meetina with Illinois Power Comoany On April 18. 1997, a management meeting was conducted at Illinois Power's Energy and Environmental Center. Clinton. Illinois, between management representatives from Illinois Power Company and members of the NRC staff to discuss the progress and effectiveness of Clinton Power Station Startup Readiness Plan.

Predecisional Enforcement Conference with Wisconsin Publ'c i Service Corooration On April 17, 1997, a predecisional enforcement conference was conducted in the Region III Office. Lisle. Illinois, between managers from Wisconsin Public Service Corporation and members of the NRC staff. The focus of the meeting was on the utility's failure to implement an effective testing program for two safety systems at the Kewaunee Nuclear Power Station. The safety systems that were discussed were the auxiliary feedwater system and residual heat removal system. The conference was scheduled as the result of findings from an NRC inspection in January.

Predecisional Enforcement Conference with Centerior Service Comoany On April 18, 1997, a predecisional enforcement conference was conducted in the Region III Office. Lisle. Illinois, between managers from Centerior Service Company and members of the NRC staff. Discussions will focus on instances of inadequate testing and corrective actions by the utility at the Perry Nuclear APRIL 18, 1997 ENCLOSURE P

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Power Station. The conference was scheduled as the result of findings from i NRC inspections late last year.  ;

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Region IV Items of Interest Week Ending April 18, 1997 Cooper Pre-decisional Enforcement Conference

A Pre-decisional Enforcement Conference was conducted with Nebraska Public Power District- (Cooper Nuclear Station) in the NRC Region IV office 3n April 15,1997. Apparent violations associated with failures to update the i Final Safety Analysis Report and failures to perform 10 CFR 50.59 evaluations were discussed. The conference was open for public observation.

River Bend Manaaement Visit On April 14, 1997, the Vice President Operations, the General Manager Plant Operations, and the Director, Nuclear Safety, from River Bend visited the Region IV office to discuss topics of current interest with the Regional Administrator, the Director, Division of Reactor Projects, and the Director.

Division of Reactor Safety.

Visit at Arkansas Nuclear One

.Dr. Denwood Ross, Director. Office for Analysis and Evaluation of Operational Data (AEOD), toured the Arkansas Nuclear Units 1 and 2 facilities on April 16, 1997, While on site, Dr. Ross met C. Randy Hutchinson, Vice President -

Operations Arkansas Nuclear One, and the Resident Inspector.

FEMA IV/NRC IV Radioloaical Emeroency Plannino (REP) Workshoo (Aoril 15-17.

1997) l l

Commissioner Dicus, Director AE0D and Deputy Regional Administrator, i Region IV, participated in the REP workshop in Eureka Springs, Arkansas. The l workshop was attended by representatives from FEMA, DOE, USDA, and FEMA IV i States to discuss emergency planning activities, )

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Office of Congressional Affairs Items of Interest Week Ending April 18. 1997 CONGRESSIONAL HEARING SCHEDULE. No. 14 OCA ~DATE .

' ASSIGN 2 '&'. TIME l WITSESS' 1+ LSUBjECN 1 COMMITTEE HENT - PhiCE Madden 04/22 9:30 TBA DOE's FY98 Budget. Environmental Senators Domenici/Reid

( 124 DSDB Management Program Energy & Water Development Appropriations ,

Madden 04/23 10:00 OMB. GAO. CRS Two-Year Federal Budget Senators Thompson /Glenn 342 DS0B Governmental Affairs Gerke 04/24 9:30 TBA Federal Hiring from the Welfare Reps. Mica /Moran 311 CHOB Rolls Civil Service Gov't Reform & Oversight Gerke 04/29 10:00 IBA Post FTS-2000 Procurement Reps. Horn /Maloney

2154 RHOB Gov't Mgmnt. Info & Tech Gov't Reform & Oversight Keeling 04/29 TBA 00E. Industry. PUCs H.R. 1270. amend Nuclear Waste Reps. Schaefer/ Hall TBA Policy Act Energy & Power Commerce Gerke 04/30 9

30 IBA Federal Employee Group Life Reps. Mica /Moran 2154 RHOB Insurance Civil Service Gov't Reform & Oversight Gerke 05/02 10:00 Chicago Electricity Deregulation Field Reps. Schaefer/Hiii 05/09 Dallas Hearings Energy & Power Commerce

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9:30 Effects of Competition on Fuel Senators Murkowski/ Bumpers Gerke 05/08 TBA 366 D508 Use and Types of Fuel Generation Energy & Natural Resources 9:30 IBA Financial Implications of Senators Murkowski/ Bumpers Gerke 05/22 366 050B Restructuring the Electric Energy & Natural Resources Utility Industry 9:30 Benefits and Risks of Senators Murkowski/ Bumpers Gerke 06/12 TBA 366 050B Restructuring to Consumers and Energy & Natural Resources Communities APRIL 18. 1997 ENCLOSURE R.

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