ML20202D258

Weekly Info Rept for Wk Ending 971121

ML20202D258
Person / Time
Issue date:	11/26/1997
From:	Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO)
To:
References
SECY-97-272, SECY-97-272-R, WIR-971121, NUDOCS 9712040213
Download: ML20202D258 (27)

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r p z November - 20 1997 SECY 97 272 ,

i EQC: The Commissioners Etos: James L. Blaha. Assistant for Operations. Office of the EDO SIMett: WEEKLY INFORMATION REPORT - WEEK ENDING NOVEMBER 21, 1997 Contents Enclosure Nuclear Reactor Regulation A Nuclear Material Safety and Safeguards B Nuclear Regulatory Research C Analysis and Evaluation of Operational Data D General Counsel E* i Administration F Chief Information Officer G Chief Financial Officer H*

Human Resources 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 11 P Region 111 P Region IV P Executive Director for Operations 0*

Congressional Affairs R*

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UNITED FTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20065 INFORMATION REPORT November 26. 119Z SECY 97-272 Egt: The Commissioners Ets: James L. Blaha. Assistant. for Operations. Office of the EDO Subhtt: WEEKLY INFORMATION REPORT WEEK ENDING NOVEMBER 21, 1997 Contents Enclosure Nuclear Reactor Regulation A Nuclear Material Safety and Safeguards B Nuclear Regulatory Research C Analysis and Evaluation of Operational Data D General Counsel E*

Administration F Chief Information Officer G Chief Financial Officer H*

Human Resources 1 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 111 P Region IV P L .cutive Director for Operations 0*

Congressional Affairs R*

• No input this week.

m ames' L. B a a

,sistant for Operations. OEDO

Contact:

L. Trocine. OEDO

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0 Office of Nuclear Reactor Regulation items of Interest Week Ending November 21, 1997 November 6. 1997. Meetina with Westinahouse 0mers Grouc RE Fuel Claddina Oxidation / 10 CFR 50.46(b)

On October 28, 1997 Westinghouse (W) notified NRC (by telecon) and its I licensees (36 plants, including Fort Calhoun. a CE design) that it had discovered a non conservatism in the oxidation model for high burnup Zr-4 clad integral fuel burnable absorber (IFBA) fuel. The model was non-conservative when compared to data for IFBA fuel with greater than about 39-40K MWD /MTU burnu). Information provided by W indicates that this is not a safety issue, but t1ere is a question of com)11ance with 10 CFR 50.46 (b)(2) (> 17% local cladding oxidation). On Novem>er 6. 1997, the staff met with W and the W Deers Group (WOG) in a public meeting to verify its safety determination and discuss the compliance issue (present compliance for each slant, continued near term compliance, including compensatory actions for t1ose plants reaching burnups at which non compliance was projected, and long term resolution). At '

the meeting, the WOG identified that one plant was probably about to enter into non compliance but was shutting down for a scheduled refueling outage.

For the remainder of the plants. W presented assessment criteria to identify plants and times at which it could no longer assure compliance.

The WOG committed to provide formally to the staff information presented at the meeting including a list of affected plants, the )rojected dates of potential noncompliance, and plans for resolution. T1e WOG also indicated that each affected plant (the next plants would be affected in about one month to six weeks) would take appropriate actions per 10 CFR 50.46 (a)(3)(ii) when it became affected and indicated that compensatory actions could include peaking limitations or derating. W would continue to do more detailed assessments for plants and make timely assessments with regard to the compliance issue. in the longer term. W plans to correct its modt and begin implementing it by August 1998.

The staff concluded that the 1 licensees are in present compliance with 10 CFR 50.46 requirements and that tie overall plan offered the licensees a means to show continued compliance with both the reporting and the analytical requirements of 10 CFR 50.46.

Palo Verde Unit 2 Steam Generator Tube Eddy Current Inspection Results Arizona Public Service Company (APS), the licensee for Palo Verde Unit 2 (PV-2), has completed its steam generator (SG) tube eddy current (EC) in pections for the current refueling outage (end-of-cycle 7). Through its bobbin coil 3 robe inspections. APS identified 54 pluggable wear indications in the

)atwing-stay cylinder area. (The batwings are diagonal straps that provide support for the SG tubes. The stay cylinder region is an untubed area located in the center of the tube bundle.) The structural limit for SG tube wear is 75% throughwall, but the licensee implements a conservative plugging limit of NOVEMBER 21, 1997 ENCLOSURE A

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o i 20% throughwall to account for high growth rates in this region. PV-2 reported 51 pluggable batwing wear indications in the #22 SG and 3 pluggable l indications in the #21 SG. The licensee attributed the difference in number of pluggable indications in each SG to the shroud modifications made in the

1. 22 SG. These modifications increased the flow rates through the SG resulting  !

in increased wear rates < APS used an Electric Power Research Institute (EPRI)

A)pendix H qualified technique to size the wear indications: the largest of tie batwing wear indications was sized at a depth of 70% throughwall.

In a Request for Additional Information (RAI) dated October 2.1997, the staff requested the licensee to discuss APS' decision to not in 51tu pressure test or )ull the tube with the 70% throughwall indication to ensure adequate leacage and structural integrity over the past operating cycle was maintained.  !

In developing its response to the RAI. the licensee identified several  :

significant issues associated with the EPRI qualification of the technique used to size wear indications. An assessment of these issues resulted in APS concluding the sizing technique used in past inspections may have been nonconservative. The licensee plans to document its position in the RAI response including an operability determination for PV-2 as well as similarly affected SGs in the other Palo Verde units. APS also notified EPRI and the Combustion Engineering Owners Group of its findings.

Boilina Water Reactor (BWR) Fall Outaae issues Hooe Creek Jet Pumo Sensina Line Crackina and Core Sorav Inlet Nozzle Crackina During RF07, the licensee found cracking indications on the jet pump sensing line (JPSL) lower brackets for Jet Pumps 8 and 15 and found a failure of the same weld on Jet Pum) 9. Cracks or failures of the sensing lines _were not observed. T1e sensing lines are 0.25 inch pipes which are welded to the jet pump diffuser by two 0.5-inch square sup)oct brackets; the lower of which were found to be cracked and failed. T1e licensee has installed semi-circular ring clamps to restrain the JPSL aga'nst their support brackets (replacing the original welds). Similar cracks were observed at Susquehanna Unit 2 in 1994. and similar clamps were installed at that time. Subsequent inspections of the clamps have shown that the clamps are still in place.

Additionally, the licensee round a stress corrosion cracking (SCC) crack in the weld butter of the core spray inlet nozzle. The licensee expanded its inspection to the other core spray nozzle and four other reactor coolant system nozzles, and did not find any additional cracking. The examinations were performed by qualified automated ultrasonic testing systems.

The staff is continuing to evaluate the licensee's evaluations.

Peach Bottom Unit 3 Jet Pumo Riser Elbow Crackina The licensee has found cracks on the thermal sleeve to jet pump riser elbow side of weld RS-1 in the heat affected zone on three jet pump NOVEMBER 21. 1997 ENCLOSURE A

risers (jet pumps 1 and 2, 9 and 10, and 13 and 14). The cracks are 10.8. 1.7 and 12.7 inches, respectively. All other jet pum) assemblies have been inspected at jet pump riser locations, and no furtier cracking ,

was detected. The other welds on the risers were also inspected.

The licensee has completed a fracture mechanics evaluation of the ,

cracking utilizing industry topical report BWRVIP-41, 'BWR Jet Pump Assembly inspection and Flaw Evaluation Guidelines " which is presently under staff review. The licensee has determined that continued operation (The unit is presently at 100% power.) is justified for several months and that if flow is reduced to 80% of rated (approximately 92% power),

the licensee has stated that fatigue crack growth will be bounded for  :

operation as long as 8 months. Further, the licensee has stated that it plans on installing a repair to jet pumps 1 and 2 and to 13 and 14 within the time frame of the analysis. ,

The staff is evaluating the licensee's evaluation. especially the technical significance of combining fatigue and SCC crack growth rates, and is reviewing if any additional regulatory actions may be necessary.

Hatch Unit 1 Core Plate Suonort Rino and Jet Pumo Riser Crackina The licensee found a 0.3-inch long vertical crack on the outside diameter of the core plate support ring segment weld. The inspection scope was expanded to one other weld (The additional four welds in this segment are ir.Jccessible.), and no other indications were found. The licensee also found cracking in the heat affected zones of the elbow to thermal sleeve weld in two of the ten jet pump inlet nozzles (N2B and N20). The cracks are 1.625 inches at the 12:00 position on the sleeve side of nozzle N2B and 2.178 inches at the 12:00 position on the elbow side of nozzle N20.

The licensee expanded its inspection scope to include the accessible

)ortions of welds at the elbow to riser. riser to transition aiece, riser

)racc. jet pump diffuser. and jet pump adaptor locations on tie associated Jet pumps, and the licensee found no additional cracking.

The licensee performed an evaluation of the above cracking and determined that an additional cycle of operation was acceptable. Further, the licensee comitted to re-inspecting during the next outage to determine crack growth.

The staff is evaluating the licensee's evaluation and is continuing discussions with the licensee on this issue.

Crystal River Unit 3 Restart Proaress Licensing Submittals Florida Power Corporation (FPC or the licensee) continues to maintain its target for completing the corrective actions and restarting the facility by December 1997. FPC identified 37 potential licensing submittals that would require NRC approval prior to restart in December 1997. Additionally, the staff, during its recent Safety System Functional Inspection (SSFI).

NOVEMBER 21, 1997 ENCLOSURE A

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identified several unresolved issues, and the region submitted four Task i Interface Agreements (TIA) for NRR determination whether the issues must be  !

resolved prior to restart. The current status of these issues is as follows:

Status of Licensina Submittals That are Reauired for Restart Total Identified (including the four TIAs) 41 Awaiting initial submittal 6 Received and review in progress 18 Completed / Closed 17 On November 6. 1997, in a telephone conference with the staff. FPC indicated that it has made preliminary assessments using the Generic Letter 91-18.

Revision 1. guidance to determine operability for several identified '

Unreviewed Safety Questions (US0). Based on the licensee's preliminary-assessments. FPC believes that its amendment requests for six US0s would not- ,

require staff approval prior to restart. The staff plans to independently l review FPC's position on these six issues.

Salem Unit 1 0)erational Status - Salem Unit 2 is operating at 100% power. Salem Unit 1 is slut down and defueled. The licensee's target date for restart is February .

1998.  ;

Salem Assessment Panel - The next meeting of the Salem Assessment Panel will be held at the site on November 20, 1997. Following the meeting, the Panel will meet with the licensee to review the items that have to be closed prior to restart of Salem Unit 1.

Licensing Actions - One amendment is required to support restart of Salem Unit 1 to incorporate parameters from the Margin Recovery Program. These paraheters have been used in the Chapter 15 accident analyses in the 10 CFR 50.59 evaluations that were developed by the licensee for the replacement of the steam generators.

Peach Bottom Unit 3 On November 10. 1997, the staff (NRR. Region I, end Consultant) discussed the information submitted regarding the indications in three jet pump riser welds l with PECO Energy and their-consultants. During the conference call. PEC0 Energy comitted to provide the staff the following additional information:

l - General Electric's analysis of a design base accident-loss of coolant accident with jet pump riser failure:

a sub.mittal date for their reply to our RAls of November 7.1997.

regarding the jet pum) crack analysis (the timing for PECO's response to our August 14, 1997. mis on ECCS pump NPSH will be determined after the staff's review of the'above stated GE analysis): and NOVEMBER 21.-1997 ENCLOSURE A

- a letter discussing their operational strategy regarding power, flow. and time limits (keeping the plant operation withir the bounds of the piping analysis).

Inoperable Safe Shutdown Paths and Early Unit 2 Maintenance Outage On September 26, 1997, the licensee entered a 67-day limiting condition for operation (LCO) because all safe shutdown (550) paths were determined to be inoperable. In the Quad Cities SSD analysis, all cables within a fire area are postulated to fail in the event of a fire, except for those cables provided with The SSD analysis relies on the opposite unit' passive fire protection.s equipment to help place and maintain the safe shutdown condition. This assumes that the SSD ecu1pment is not affected by the fire and that the breakers for the non-SSD loacs on the same bus as the SSD equipment would be opened or shed from the bus. If the non-SSD load breakers are not shed from the bus and the cables for these loads pass through the fire zone, damage to these cables could cause ' )ss of power to the SSD equipment on that bus for the uneffected unit.

Upon review of the Fire Protection Report (FPR) the station discovered two issues with the implementation of the SSD analysis. The first issue discovered was that even though the SSD analysis assumes shedding non-SSD loads, the station procedures do not implement all of the assumed load shedding. The second discovery was that the analysis that addresses the ability to shutdown the unaffected unit after shedding of non-SSD loads could not be located. The licensee did not have assurance that the SSD paths were operable. There is no analysis in place that ensures that equipment used to safely shutdown the unaffected unit will not be affected by fire in the affected unit: therefore, the licensee declared all SSD paths inoperable.

U)date: As of November 12. 1997, the licensee is still completing review of tie SSD procedures for Unit 1. Unit 1 is presently operating in day 47 of the 67-day administrative LC0 while Unit 2 is shutdown. Unit 2 has cco1pleted Maintenance Outage 02P01: however, startup is not planned until the procedures for Unit 2 have been reviewed / revised as necessary. Instead of revising the current SSD procedures to include load shedding on the o)posite unit the licensee is now revising the SSD procedures to include tie station blackout diesel as an alternate power source. The licensee projects completing the Unit I work prior to the expiration of the 67-day LC0. Unit 2 startup is projected to be in late December.

There was a meeting at the site on November 20. 1997, to address these issues with the licensee. NRC staff participation included Plant Systems. Projects.

Region III. and the resident inspector staff.

Braidmod Umts 1 and 2 Waterhamer at Braidwood. Unit 2 Braidwood. Unit 2 is in startup following ccmpletion of a refueling outage.

With the unit in Mode 3. the licensee was attempting to open an air-operated control valve in a 6-inch feedwater tempering line to the upper steam NOVEMBER 21. 1997 ENCLOSURE A

generator nozzle on the "D" steam generator The nozzle is also used for auxiliary feedwater. The valve did not respond, so the licensee increased the air aressure. The valve suddenly opened. The piping downstream cf the valve had been voided, and a resulting water hammer occurred. The event happened at about 2:00 a.m. (CST) on November 10, 1997.

Upon immediate visual inspection of the system, the licensee reported the following findings: (1) a spring can pipe su) port was dama pipesupportwasdamagedandpulledoutoft7ewall,and(ged,(2)aboxguide J) two snubbers on >

the 16 inch main feedwater line were challenged.

So far, the licensee has used nagnetic particle and ultrasonic testing to insoect the steam generator nozzle. Comed found no damage to the nozzle.

Comed is presently inspecting the welds in the tempering line. The s) ring can has been repaired. Most likely, the licensee will have to drill new loles to reattach the box guide. The two snubbers on the main feedwater line were tested and were found to be operable. The licensee also tested two additional snubbers downstream of the two that were challenged, and they were also found to be operable. A root cause analysis is underway. The licensee is expecting to have all actions related to this event completed within the next few odys.

Region 111 has sent an specialist inspector to the site ard plans to send one or two on November 13, 1997, to monitor and evaluate the licensee's activities.

NOVEMBER 21, 1997 ENCLOSURE A

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Office of Nuclear Material Safety and Safeguards Items of Interest Week Ending November 21, 1997 Workshoo on the Revision of 10 CFR Part 35 On November 12 14. 1997, the NRC staff conducted the second in a series of

)ublic workshops to discuss the fundamental ap) roaches and issues that need to

)e addrer. sed in revision of 10 CFR Part 35. T11s workshop, held in Chicago.

Illinois, was atter.ded by representatives of the Part 35 Working Group and Steering Group. Invited participants incleied nuclear medicine physicians:

physician specialists (such as cardiologists, endocrinologists, and radiologists): medical and health physicists: technologists; nurses:

radiopharmaceutical manufacturers: hospital administrators: patients' rights advocate; and Agreement State regulators. Topics discussed included risk <

assessment: the NRC's 1979 Medical Policy Statement; and rule alternatives for the Quality Management Program, patient notification, threshold for reportable events, radiation safety committee, and training and experience criteria.

Joint Guidance on Mixed Waste Testina On November 7, 1997, the NRC and the Environmental Protection Agency (EPA) completed development of final guidance on the testing requirements for mixed waste. Mixed waste is defined as hazardous waste that also contains source.

special nuclear. or byproduct material. Because mixed waste contains both hazardous waste and radioactive material it is regulated by both the NRC or an NRC Agreement State and the EPA or an EPA authorized State. In the past, mixed waste generators have expressed concern that EPA's testing requirements for the hazardous component of the mixed waste could result in increased radiation exposures.

The new guidance emphasizes the use of process knowledge to determine if waste is hazardous in order to avoid unnecessary exposures to radioactivity, and it 3rovides guidelines to be used by generators wishing to rely on process (nowledge as the basis for evaluating their waste. The guidance also discusses using small volume samples and surrogate materials as well as alternative sampling and testing procedures, such as representative drum simpling or samp'ing from drums containing lower concentrations of radioactive material.

Completion of this guidance is tne culmination of a multi-year effort by the two agencies to x ovide mixed waste managers with practical methods for complying with tie regulatory requirenients of the NRC and EPA. The agencies plant to publish the final guidance in the Federal Reaister.

International Physical Protection Advisory Service Mission to Poland The International Atomic Energy Agency (IAEA) has requested that a member of the Division of Fuel Cycle Safety and Safeguards staff represent the U.S. in an " International Physical Protection Advisory Service" miss Mn to Poland from November 24-December ?. 1.997. These missions were established to provide advice and assistance to IAEA member states to strengthen and enhance the NOVEMBER 21, 1997 ENCLOSURE B

effectiveness of the state's system for physical protection of radioactive materials. The mission team will also include experts from Germany France, and the United Kingdom with broad experience in design and implementation of physical protection systems and some knowledge of regulatory oversight.

Wori Stocoaae at Westerman Comoanies On November 11, 1997. Lockheed Martin Utility Services (LMUS). a contractor to U.S. Enrichment Corporation (USEC). informed the NRC that they had stopped all fabrication activities at Westerman Companies, a fabricator of UF6 cylinders for USEC. The stop work order was issued by LMUS. not by NRC. based on findings identified .!uring an August 25-29. 1997. NRC inspection at Westerman.

LMUS also informed the NRC that they were reviewing Westerman's corrective actions and anticipated restart of fabrication activities at Westerman in the near future. Prior to restarting fabrication. LMUS stated that they would assess the current conditions to ensure that there were no outstanding issues.

Insoection of fransoortation Packaaino Test Activities at Amersham Corooration On November 17-18. 1997. members of the Spent Fuel Project Office staff ins)ected test activities associated with the Model-660 transportation paccaging at Amersham Corporation in Burlington. Massachusetts, The inspectors reviewed test plan implementation and test data for accident

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condition tests performed as described in the NRC Confirmatory Action Letter dated June 10. 1997. There were no inspection findings, and an exit meeting was held with Amersham on November 18. 1997, to present the results of the inspection.

Amersham performed tests on four test specimens (units). Each unit was drop tested from 30 feet in different orientations onto an essentially unyielding surface. One of the units. test unit D. experienced some damage. Unit C 3assed the drop test and, due to minimal damage, was not thermal tested.

Jnits A. B. and D were thermal tested. Units A and B passed the test, but unit D did not. As a result of the failure. Amersham sent a letter containing a Justification for Continued Operation (JCO) for the Model-660 packaging to NRC on November 17. 1997. The NRC staff is currently reviewing the JCO.

9 NOVEMBER 21. 1997 ENCLOSURE B I

1 Office of Nuclear Regulatory Research l Items of Interest Week Ending November 21, 1997 Workshoo on Review of Dose Modelina Methods for Demonstration of Comoliance with Radioloaical Criteria for License Termination i The NRC staff is developing guidance for implementing the final rule on j radiological criteria for license termination, which includes identification of criteria for evaluating acceptability of dose models and parameter values for demonstrating compliance with the final rule. In sup) ort of tb3 t, RES and NMSS staff jointly organized a 2-day pubhc workslop on the f dose modeling methods. The workshop which was announced in the P 2.

Reaister (62 FR 51706), was held in the auditorium at the NRC Heau . ces- on November 13-14, 1997. PresentersattheworkshopincludedNMSSandt sts" who discussed dose modeling needs for licensing reviews and developh, r.. J guidance related to dose modeling and parameter selection needs: Depart d Energy (DOE) national laboratory scientists who provided responses to et e NRC s+aff-developed questions and discussed their various Federally sponsore<

dose :.udels (i .e. , D&D, RESRAD, and MEPAS codes): and an Environmental Protection Agency (EPA) scientist who presented details on the EPA dose assessment model (i.e., PRESTO code). During the lunch hour and afternoon break on November 14, 1997, computer demonstrations of the dose codes were provided to the attendees. Over 120 individuals attended the workshop including those from NRC Headquarters an : the regions: those from the Agreement States: industry representatiu 3 and consultants; staff members from EPA, Department of Defense Defense Nuclear Facility Safety Board, and DOE:

national lacoratory scientists; and interested members of the public. A transcriat of the meeting will be alaced in the Public Document Room in one week. Jnder preparation is a NUREG/CP report of the workshop proceedings that will outline the presentations made during the workshop and address questions raised during the panel discussior.c. This document is designed to provide technical bases and discus-ions to support development of the decommissioning guidance.

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Office for A,1alysis and Evaluation of Operational Data Items of Interest Week Ending November 21. 1997 Visit of Soanish Reaulatory Staff On November 18, 1997. Mr. Javier Zarzuela, head of the Operational Experience and Training section of the Spanish Nuclear Safety Commission (CSN). and Dr.

Marta Marono, a contractor to the CSN, visited AE00 to discuss the NRC's Performance Indicator (PI) and Accident Sequence Precur p (ASP) programs.

The CSN uses NRC PI software and methodology for their PI program. They include the Spanish plants in the appropriate U.S.

performance of their plants to that of similar U.S. peer (The plants. groups to compare the Spanish operate six Westinghouse plants two General Electric plants, and one Kraftwerk Union plant.) The AEOD staff discussed with Mr. Zarzuela and Dr.

Harono several issues related to PIs. including Licensee Event Report coding, future PI developments, reliability data and risk-based Pls, and the INP0 EPIX system. The CSN is also )lanning to undertake an ASP program next year that will be patterned after t7e AE00 program. AE00 staff discussed several options that the CSN is considering for beginning their ASP program and made recommendations to them based upon the NRC s experience.

Visit of Hunaarian Atomic Enerav Authority Personnel On November 18, 1997. Dr. Ferenc Kolonits. Department Head in the Hungarian AEA Nuclear Safety Directorate, and Dr. Gabor Redey of his staff. visited AE00's Safety Programs Division to discuss nuclear alant aging. The AE00 staff described the results of the study on aging w1ich they performed for the Nuclear Energy Agency. The staff also provided them a copy of the study report entitled. Evidence of Aging Effects on Certain Safety-Related Carrponents. NUREG/CR-6642.

bir-Ocerated Valves As aart of its study on air-operated valves (A0V). AE00 its contractor.

INEEL. (two engineers), and a staff member from RES visited Palisades Nuclear Plant on November 4 and 5. 1997.

As part of the A0V program at Palisades, the A0Vs were ranked or categorized by an expert panel using insights from the maintenance rule evaluations of systems importance, and from a review of the plant's inservice testing (IST) program. The plant's probabilistic risk assessment (PRA) was not used for the first cut of determining which A0Vs are to be included in the plant's A0V program. However. insights from the PRAs are being used to further define the important valves which are to be included in the program.

The Palisades plant has a large number of important A0Vs which are included in the A0V program. The pur)ose of the A0V program is to verify the design of A0Vs to assure that they lave adequate margins when they are required to function during design basis events.

NOVEMBER 21. 1997 ENCLOSURE D l

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i The Palisades plant has perforned static diagnostic testing and is planning to perform dynamic and additional static testing early next year. Presently, the licensee is planning to run comparative tests among three different manufacturers' A0V diagnostic eqaipment.

Inde)endent of the A0V design. AE00 found significant air system deficiencies whic1 were discussed with the licensee at the exit meeting.

Calvert Cliffs Exercise Two members of Incident Response Division participated with Region I staff as an ingestion team in the Calvert Cliffs ingestion exercise on November 19 and

20. 1997. This effort was part of the AEOD State Outreach program intended to gain more Federal participation with States in licensee intermediate phase exercises. At the same time. AEOD escorted two members of the Nuclear Safety Directorate of the Hungarian Atomic Energy Authority, who observed be+S 'he plume and ingestion phases of the exercise.

PRELIMINARY NOTIFICATIONS

1. PNO-I-97-066A. Cabot Corporation. UPDATE - RETURN OF INTERMODAL CONTAINERS TO CABOT CORPORATION

2. PNO-III-97-092. Shannon and Wilson. Inc., NOTIFICATION OF DAMAGED MOISTURE / DENSITY GAUGE AND INABILITY TO RETURN SEALED SOURCES TO SHIELDED POSITION

3. PNO-IV-97-066. Texas Utilities Electric Co. (Comanche Peak 2). NEW FUEL DAMAGE

4. PNO-IV-97-067. Texas Utilities Electric Co. (Comanche Peak 1).

ELECTROCUTION AT COMANCHE PEAK UNIT 1 s

NOVEMBER 21, 1997 ENCLOSURE D

Office of Administration Items of Interest Week Ending November 21, 1997 OWFN Security Camera Uoarades Division of Facilities and Security representatives met with the General Services Administration and their contractor to coordinate the exterior site work needed to add additional cameras on the White Flint Complex. The work consists of new concrete foundations for three new poles and additional wiring to connect the new color cameras to our existing network of closed-circuit television cameras. The existing black and white cameras will be also be replaced with color cameras which will provide clearer enhanced pictures. The exterior work is expected to begin the week of November 24. 1997, and be completed within 60 days. The camera replacement is expected to begin in February 1998 and be completed in May 1998.

Pilot Course On November 20, 1997 representatives from AE00. NRR, and RES attended an in-house pilot course entitled. " Contract Administration / Property Management."

This course which was taught by re]resentatives from the Division of Contracts and Property Management. RES, and 4RR is one of ten course modules to be offered to NRC Project Managers. At the end of the pilot, the attendees were able to track project costs against a spending plan, properly approve or disapprove vouchers, remedy performance problems, and modify or terminate a contract or agreement. The course was well received by partici) ants who attended the pilot. The course will be finalized. based upon tie comments received from the class participants and will be made available on a regular basis staring in calendar year 1598.

)rocedures ADolicable to Proceedinas for the Issuance of Licenses for the Recelot of Hlah-Level Radioactive Waste at a Geoloaic ReDository (Part 2)

A proposed rule that would amend the Commission's Rules of Practice for the licensing proceeding on the disposal of high-level radioactive waste at a geologic repository was published in the Federal Register on November 13. 1997 (62 FR 60789). The proposed rule would allow the application of technological developments that have occurred since the original rule was issued in 1989 while retaining the goal of facilitating the Commission's ability to comply with the schedule for a decision on the construction authorization established by the Nuclear Waste Policy Act. The comment period for this action closes January 27. 1998.

NOVEM8ER 21. 1997 ENCLOSURE F I

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Chief Information Officer Items of Interest Week Ending November 21, 1997 Freedom of Information and Privacy Act Reauests Received durina the 5-Day Period of November 14-20. 1997:

Records on self. (F01A/PA-97-447)

Western Nuclear Corp. uranium-bearing ores. (F01A/PA-97-448)

Executive Order 12898, environmental justice strategy. (F01A/PA-97-449)

Corresaondence by named individual re performance of named employee.

(F01A/)A-97-450)

Commonwealth Edison Co. , plant issues matrix for Braidwood. Byron. Dresden.

LaSalle. Quad Cities, and Zion. (F01A/PA-97-451)

OIG report.97-40G. (501A/PA-97-452)

Request for Quotation 60780016. Training for Environmantal Impact Statements &

Assessments. (F01A/PA-97-453)

Corresoondence by named individual re performance of named employee.

(F01A/)A-97-454)

Crystal River, radiological effluent technical specifications implementation (EGG-PHYS-6171), specific exhibits. (F01A/PA-97-455)

Contract. NRC-33-95-173. performance reviews. (F01A/PA-97-456)

NOVEMBER 21. 1997 ENCLOSURE G

1 Office of Human Resources Items of Interest Week Ending November 21. 1997 Eve Disease Education and Vision Screenina Proaram Conducted During the mor,th of November, the Employee Health Center conducted an Eye Disease Education and Vision Screening program. Thirty-six employees attended the video presentation on November 4, 1997, which focused on glaucoma and diabetic eye disease. Sixty-three people signed up for the vision screening to be conducted by the Lions Club on November 18 and 19,1997. The program was presented in conjunction with the National Diabetes Month Eye Initiative sponsored by the National Eye Health Education Program Partnership.

Emolovee Assistance Proaram Association (EAPA) Conference Attended On November 16-19, 1997, the Employee Assistance Program Manager attended the National EAPA Conference held in Baltimore. Topics covered at the workshops included chemical dependency, mental health treatment and prevention issues, work / family programs, violence in the workplace, and organizational change.

Arrivals BLUMBERG. William HEALTH PHYSICIST (PFT) NRR KHAN. Tariq REACTOR SYSTEMS ENGINEER (PFT) NRR LIEBERMAN, Jodi INT'l POLICY ANALYST (PFT) OIP SUTTORA. Linda ENVIRONMENTAL SCIENTIST (PFT) NMSS Retirements ,,

None Departures None NOVEMBER 21, 1997 ENCLOSURE I l

Office of Small Business & Civil Rights Items of Interest Week Ending November 21, 1997 Minority Enterorise Develooment Week The Office of Small Business and Civil Rights participated in the 15th Annual Minority Enterprise Development Week (MED Week) held at the Sheraton Washington Hotel on Noveaber 21-22, 1997. Featured speakers were tha Honorable Richard Gephardt. Minority leader. U.S. House of Represent..ives, and the Honorable Aida Alvarez, Administrator. U.S. Small Business Administration. Ap3roximately 15 Federal agencies were represented. Von Deloatch attended t1e conference and manned the NRC exhibit booth providing information about potential procurement opportunities to ap3roximately 350 minority firms. Seminar to)ics included Opportunities in tie Technology and Communications Industries. :ederal Procurement Opportunities in a Post-Adarand Environment, and Emerging International Markets for the Minority Entrepreneur.

8(e) Procram Workshoo On November 18.1997. Mr. Deloatch partici)ated in a one-day workshop for businesses that recently joined the 8(a) Program. The workshop was sponsored by the Small Business Administration (SBA) and focused on marketing strategies that 8(a) firms might use to become more competitive in the Federal Procurement Program. Approximately 200 8(a) firms were in attendance.

C NOVEMBER 21, 1997 ENCLOSURE J

Office of State Programs Items of Interest Week Ending November 21, 1997 Environmental Justice Subcommittee Meetina Rosetta Virgilio attended the November 20, 1997, meeting of the Interagency IWG) on Environmental Justice (EJ) Subcommittee on Policy and Working Group Coordination he (ld in Washington, DC. A representative of the White House, Council on Environmental Quality (CE0), provided members of the IWG with a copy of the pre-publication draft of the CEO " Guidance for Considering Environmental Justice Under the National Environmental Policy Act (NEPA)"

dated November 19, 1997. The availability of the Final CEO EJ NEPA guidance is expected to be announced mid-Decemb?r via press conference.

As a result of a November 19, 1997, meeting between the White House, CEO, and African-American environmental leaders, a White House Conference on Environmental Justice (WHCEJ) will be scheduled on or about the 4th anniversary of Executive Order 12898, " Federal Actions to Address Environmental Justice in Minority Populations and Low-Income Po)ulations" (February 11, 1998). Members of the IWG were asked to provide )y December 2, 1997, an appropriate listing of any additional agency representatives and any particular environmental justice constituency to be invited to attend the WHCEJ as well as any new initiatives for achievement of the goals of the Executive Order. On or about December 12, 1997, an appropriate White House reaffirmation of agency commitments under the Executive Order will take place.

If details of the WHCEJ are available at that time, the communication will include a request for Cabinet-secretary-level participation in the conference.

The second " Report to the President on Environmental Justice," although finalized, was never submitted to the President for approval. Because the contents of the draft report have become somewhat stale and should include new issues raised at the aforementioned November 19 meeting, it will be circulated through the Office of Management and Budget for revision. The CEO will provide specific direction to agencies on new areas to be addressed and estimates having the final report to the President by December 31. 1997.

NOVEMBER 21, 1997 ENCLOSURE L

Office of Public Affairs Items of Interest Week Ending November 21, 1997 Media Interest HQ arovided information and arranged an interview for a Knight-Ridder reporter wit 1 an NRR official concerning license renewal at Oconee.

There were media inquiries in Region IV after Union Electric declared an Unusual Event because of a security threat at Callaway.

The Walnut Creek Field Office coordinated a news conference in Phoenix for Commissioner Diaz and assisted with a public meeting on the employee concerns program at San Onofre. s Press Releases Headquarters:

97-169 Note to Editors: ACRS Meeting on December 3 97-170 Note to Editors: ACRS Reports97-171 Note to Editors: ACRS Meeting on December 2 97-172 Note to Editors: ACRS Meeting on December 11-12 97-173 NRC Advisory Committee on Reactor Safeguards to Meet in Rockville. Maryland. on December 3-6 97-174 Nuclear Regulatory Commission and Department of Energy Sign Memorandum of Understanding on Pilot Program for External Regulation Regions:

I-97-149 Note to Editors: Millstone Meetings on November 20 and December 2 _

I-97-150 NRC Recognizes Improvements at Haddam Neck: Modifies Some Restrictions on Radiological Controls 11-97-81 NRC Staff to Hold Predecisional Enforcement Conference to Discuss Robinson Nuclear Power Plant Issues with CP&L 111-97-98 NRC Staff to Discuss Inspection Findings on November 19 at Palisades Nuclear Power Station 111-97-99 NRC Staff Proposes $16.000 Fine Against U.S. Army 111-97-100 NRC to Hold Predecisional Enforcement Conference with Michiqan Department of Transportation on Apparent Violations NOVEMBER 21. 1997 ENCLOSURE M

111-97-101 NRC Staff Proooses $100.000 Fine for Two Violations of NRC Requirements 'at Perry Nuclear Power Plant IV-97-69 NRC Proposes $5,000 Fine Against the Terracon Companies for Violation of Radiation Safety Requirements IV-97-70 NRC Comissioner Diaz to Meet With News Media Following Visit to Palo Verde Nuclear Plant NOVEMBER 21. 1997 ENCLOSURE M l

Office of the Secretary Items of Interest Week Ending November 21, 1997 Decision Documents Released to the Public Document Date Subject

1. SECY-97-146 7/11/97 NRC's Mandated and Non-Mandated Activities and Revisions to Aency Policy on Performing Reimbursable Work for Others

- SRM on 97-146 11/5/97 (same)

- Commission Voting 11/5/97 (same)

Record on 97-146

2. SECY-97-188 8/18/97 Formerly Licensed Sites identified for Further Investigation in Agreement States

- SRM on 97-188 11/7/97 (same)

- Commission Voting 11/7/97 (same)

Record on 97-188

3. SECY-97-228 10/3/97 Final Amendments to 10 CFR Part 73.

" Changes to Nuclear Power Plant Security Requirements"

- Commission Voting 11/5/97 (same)

Record on 97-228

4. SECY-97-232 10/9/97 Final Rule on Exempt Distribution and Use of a Radioactive Drug Containing One Microcurie of Carbon 14 Urea (Parts 30 and 32)

- Commission Voting 11/5/97 (same)

Record on 97-232 Negative Consent Papers Released to the Public

1. SECY-97-214 9/24/97 Changes to 10 CFR Part 72. Expand A4plicability to Include Certificate Holders and Applicants and Their Contractors and Subcontractors

- SRM on 97-214 11/4/97 (same)

NOVEMBER 21, 1997 ENCLOSURE O

2. SECY-97-224 10/1/97 Creation of a Research Effectiveness Review Board

- SRM on 97-224 11/4/97 (same)

Information Papers Released to the Public

1. SECY-97-261 11/5/97 Weekly Information Report - Week Ending October 31, 1997 Hemoranda Released to the Public

1. SRM on 97-193 11/5/97 Assistance to the U.S. Department of Energy's Fissile Materials Disposition Program

2. M971015 11/18/9 Briefing on PRA Implementation Plan:

7 Wednesday. October 15. 1997 Commission Correspondence Released to the Public

1. Letter to Dr. John H. Gibbons The White House Office of Science and Technology, dtd 11/14/97 provides a report on classified research projects involving human subjects

2. Letter to the President of the United States dtd 11/14/97 concerns the proposed Agreement for Cooperation with Kazakhstan

3. Letter to the Vice President of the United States dtd 11/13/97 provides the FY 1997 annual report on the Welfare-to-Work initiative Federal Reaister Notices Issued

1. Advisory Committee on Reactor Safeguards: Subcommittee Meeting on Thermal-Hydraulic and Severe-Accident Phenomena: Notice of Meeting on December 9 and 10, 1997

2. Advisory Committee on Reactor Safeguards: Subcommittee Meeting on Thermal-Hydraulic and Severe-Accident Phenomena: Notice of Meeting on December 11 and 12. 1997 NOVEMBER 21. 1997 ENCLOSURE O

4 Region I Items of Interest Week Ending November 21, 1997 Pilarim On November 21. 1997 NRC staff met with Boston Edison Company in King of Prussia. Pennsylvania, for a predecisional Enforcement Conference. The apparent violations which are discussed in Inspection Report No. 50-293/97-05.

include failure to maintain the licensing and design basis, improper design control. Inadequate and/or untimely corrective actions, and not reporting conditions outside the design basis.

Indian Point Units 2 and 3 On November 19 20. 1997, the NRC Executive Director for Operations: Associate Director for Projects. NRR: Director. Project Directorate. I-1. NRR: EDO Regional Coordinator: Region I Administrator: Director. Division of Reactor Projects: Deputy Director. Division of Reactor Safety; and Region I staff from Division of Reactor Projects met with officials from the New York Power Authority and Consolidated Edison at the sites to tour the plants and hold discussions with plant personnel.

NOVEMBER 21, 1997 ENCLOSURE P

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l Region 11 Items of Interest Week Ending November 21, 1997 Florida Power and Licht Comoany - St. Lucie On November 17. 1997, the Regional Administrator accompanied Chairman Jackson to Florida Power & Light Com3any's (FP&L) St. Lucie nuclear power plant.

Chairman Jackson met at St. ucie with the NRC's resident inspectors, held discussions with FP&L officials on current improvement initiatives at the plant, and took a working tour of the facility including areas where replacement of the Unit 1 steam generators is currently in progress. At the conclusion of the visit. Chairnan Jackson held a news conference with members of the media and the public.

Tennessee Valley Authority - Seouovqh Representatives from the Tennessee Valley Authority met with the NRC on November 19, 1997, for a predecisional enforcement conference to discuss the causal factors that led to an inoperable vital battery bus at Sequoyah in July 1997. The licensee presented its analysis of the safety significance and its completed and planned corrective action to preclude recurrence.

BWX Technoloaies On November 20, 1997. representatives from BWX Technologies were in the Regional Office to attend a predecisional enforcement conference. The meeting was closed to the public due to the potential for discussion of classified information. The issues discussed involycd exceeding the nuclear criticality safety limits for an accountability transfer cart on July 26, 1997. The licensee presented an analysis of the safety significance to the incident and its completed and planned corrective actions to preclude recurrence.

Florida Power Corocration - Crystal River On November 18, 1997. Crystal River 3 reached a milestone in their station recovery plan and established a vacuum in the main condenser. This evolution was conducted using auxiliary steam from an adjacent fossil plant. On November 20, 1997. a pressurizer steam bubble was established using the pressurizer heaters. Temperature inside the pressurizer is being controlled at approximately 297 degrees Fahrenheit to maintain approximately 50 pounds per square inch gauge pressure in the reactor coolant system (RCS). The RCS temperature is 81 degrees Fahrenheit. Major problems or concerns were not identified during the two evolutions.

Work on the planned upgrades for the B Emergency Diesel Generator (EDG) was completed, and functional testing is in progress. Following return to operation of the B EDG. additional testing will be conducted on the power upgrades for the A EDG. Appendix R modifications, along with the EDG work, are the present critical path hardware activities.

NOVEMBER 21, 1997 ENCLOSURE P 1

Region III Items of Interest Week Ending November 21, 1997 Special Insoection Team at Palisades Nuclear Power Plant -- Public Exit On November 19, 1997 NRC staff conducted a public exit meeting at the Palisades Nuclear Power Plant in Michigan to discuss the findings of a special inspection at the Palisades plant. The inspection covered an October 17.

1997, incident in which the entire reactor control rod drive system was taken out of service for maintenance of one control rod drive while the plant was in operation. The utility used a procedure .1at was Intended for use while the plant was shut down. The use of the incorrect procedure was discovered by the utility during a review of the maintenance on October 20, 1997.

Duane Arnold Nuclear Power Plant A public meeting between NRC staff and IES Utilities. Inc., was held at the Ouane Arnolo Nuclear Power Plant in Iowa on November 18. 1997, to discuss the plant's Systematic As mssment of Licensee Performance report. The plant received performance ratings of ' superior" in operations, engineering and plant support and " good" in maintenance.

Predecisional Enforcement Conference with Detroit Edison Comoany - Fer'ai Plant On November 18, 1997, a Predecisional Enforcement Conference was conducted in the Region III Office in Lisle Illinois, between management representatives of Detroit Edison Company and members of the NRC staff. The conference was held to discuss the utility's apparent inadequate evaluation of the safety implications when it changed procedures affecting the emergency equipment cooling system of the Fermi Nuclear Power Plant.

Predecisional Enforcement Conference with B P. Chemicals. Inc.

On November 19, 1997, a Predecisional Enforcement Conference was conducted in the Region III Office in Lisle Illinois, between management representatives of B.P. Chemicals and cembers of the NRC staff. The conference was held to discuss the company's apparent failure to oversee decommissioning activities adequately to assure compliance with federal regulations.

From 1964 to 1971, the company used depleted uranium as catalyst material for chemical production. Some of the resulting contaminated waste was placed into 3 settling Jonds and other localized places on site. Remediation of the facility Jegan in 1991. Final decommissioning activities now under way include permanent on-site disposal of the low level contaminated sludge and soil in specially de;igned cells.

NOVEMBER 21, 1997 ENCLOSURE P l

L Predecisional Enforcement Conference jlth the Michioan Deoartment of Transoortation On November 21, 1997, a Predecisional Enforcement Conference was conducted in the Region III Office in Lisle Illinois, between management representatives of the Michigan Department of Transportation and members of the NRC staff.

The conference was held to discuss two incidents in September and October in which the Michigan Department of Transportation apparently failed to maintain control of two nuclear gauges.

Manaaement Meetina with Commonwealth Edison Comoany - LaSalle On November 21. 1997, a management meeting was conducted in the Region III Office in Lisle, Illinois, between management re)resentatives from Commonwealth Edison Com)any and members of the NRC staff. The meeting discussion focused on t1e status of LaSalle Nuclear Pever Station's restart action plan and the effectiveness of plant performance improvement actions.

Manaaement Meetina with Commonwealth Edison Comoany - Byron Nuclear Power Station On November 20. 1997, a management meeting was conducted in the Region III Office in Lisle. Illinois, between management rearesentatives from Commonwealth Edison Com)any and members of the NRC staff. The meeting discussion focused on t1e current status of the Byron Nuclear Power Station.

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Region IV Items of Interest Week Ending November 21. 1997 China Atomic Enerov Authorit/ Reoresentatives Visit WNP-2 On November 19.'1997.'the WNP-2 Senior Resident inspector met with members of the China Atomic Energy Aathority and the China National Nuclear Corporation as part of a visit to the WNP-2 facility. The members were invited to visit the facilities by the U.S. Department of Energy _(DOE) under the auspices of mutual cooperation to enhance China's nuclear material and control accountability programs. WNP-2 was one of several diverse facilities toured b" the delegation to review safeguards and material controls. The members of tfiedelegationwereasfollows:

Dr. Chen Fang 11u. Director of the National Office of Nuclear Mate.-ial-Control 4

Ms. Ma Yar.,in. Deputy Director of the Office of Nuclear Material Control Mr. Qiao Shengzhong. Deputy Director of the Bureau of Nuclear Fuel. China National Nuclear Corporation Mr. Shen Lixin. Project Officer. China National Nuclear Corporation Ms. Dong Chaojie. Project Officer. Bureau of Legislative Affairs. State Council, PRC Accompanying the members were as follows:

James Busse. International Safeguards Division. DOE Robert Sorenson Fanior Program Manager. International Safeguards._PNNL Comissioner Diaz Visit tc Palo Verde On November 19, 1997. Commissioner Diaz visited the Palo Verde Nuclear

! Generating Station. He toured the site with Region IV Regional Administrator, met with the Palo Verde resident inspectors, discussed industry initiatives with licensee senior managers, and held a question and answer session with a

. representative group of licensee employees. In addition. Commissioner Diaz toured a neutrino experiment being conducted by Stanford, the California Institute of Technology, and the University of Alabama at the Palo Verde site.

c NOVEMBER 21, 1997 ENCLOSURE P

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