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SECY 97-292

December 18, 1997

Office of Nuclear Reactor Regulation
Items of Interest
Week Ending December 12, 1997

South Texas Project, Unit 2

Houston Light and Power Company (HL&P), the licensee for South Texas Project Unit 2 (STP-2), briefed the staff on HL&P's plans to submit a license amendment request to implement a 3.0 volt Interim Plugging Criteria (IPC) for steam generator (SG) tube repair. The amendment is similar to the 3.0 volt IPC amendment previously approved at Braidwood Unit 1 and Byron Unit 1. At those plants, SG tubes were expanded at the tube support plates (TSPs) to "lock" the TSPs in place and thus justify a higher voltage repair limit than allowed in Generic Letter 95-05 due to negligible burst probability and reduced leakage during accident conditions. Experience from the last SG tube eddy current inspection at Braidwood Unit 1 resulted in the identification of a voltage-dependent growth rate that resulted in nonconservative predictions of the end-of-cycle (EOC) conditions. This issue needs to be addressed to ensure that nonconservative predictions of EOC leakage would not occur at STP-2. Degradation at the top of the tubesheet (TTS) in the form of circumferential cracking due to outside diameter stress corrosion cracking (ODSCC) was also identified in the locked tubes at Braidwood Unit 1. HL&P proposes severing and subsequently sleeving the locked tubes at the TTS to eliminate residual stresses from the expansion process, thus reducing the likelihood of ODSCC. In addition, the licensee proposed changes from the Braidwood and Byron 3.0 volt amendment in the following areas: the bounding leakage assigned to indications restrained from burst, the inspection program for the locked tube expansions, and the safety factor for the thermal hydraulics analysis. In light of the number of difficult issues involved in this review, the staff indicated its evaluation of the 3.0 volt IPC at STP-2 will need to stand alone, and the differences from the Braidwood and Byron 3.0 volt IPC discussed above will require an in-depth review. The licensee plans to submit the 3.0 volt amendment in its entirety in March 1998 for implementation in Fall 1998. The staff expressed its concern regarding the proposed schedule given the complexity and extent of the review.

Calvert Cliffs

On December 8, 1997, Baltimore Gas and Electric (BGE) company representatives presented to the Probabilistic Safety Assessment Branch (SPSB) staff an overview of the Calvert Cliffs' Level 1 (plus external events) probabilistic risk assessment (PRA). Mr. Bruce Mrowca, supervisor of the Calvert Cliffs' reliability unit led the discussion. Attendees included staff members from the Offices of Nuclear Reactor Regulation (NRR), Nuclear Regulatory Research (RES), Region I (Resident Inspector and SRA), and Nuclear Energy Institute (NEI). Based on the most recent update, BGE estimated the Calvert Cliffs' core damage frequency (CDF) (which now includes external events) to be 3E-4 for Unit 1 and 4E-4 for Unit 2. Although the PRA estimated a relatively high CDF, there appeared to be significant plant features and modeling assumptions that tended to both justify and differentiate the Calvert Cliffs PRA from other licensee PRAs. The staff plans to continue to interact with BGE to better understand their PRA model and associated insights. According to Mr. Mrowca, the CE Owners Group also started to review the model to obtain a better understanding.

DC Cook Use of Leak-Before-Break

On Friday, December 5, 1997, members of the NRR staff from the Containment Systems and Severe Accident Branch (SCSB) and the Materials and Chemical Engineering Branch (EMCB) and Region III participated in a conference call with representatives of American Electric Power, the licensee for the DC Cook Units 1 and 2. The purpose of the call was to discuss the application of leak-before-break (LBB) in order to show the operability of the ECCS and safety-related containment spray systems at DC Cook during a design basis loss-of-coolant accident. General Design Criterion 4 states that dynamic effects associated with pipe ruptures may be excluded from the design basis. The licensee informed the staff that it intended to include debris generation caused by the ruptured pipe as a dynamic effect. The safety concern is that the debris might block the ECCS sump and prevent adequate recirculation flow of coolant to the reactor core.

In addition, the Westinghouse Owners Group (WOG), in a letter dated November 25, 1997, requested that "the provisions provided by GDC-4 ... be made part of other related federal regulations." The letter goes on to state: "As such, dynamic effects of a pipe break would not be considered as a debris generation source or as a coatings removal mechanism."

Representatives of SCSB, Reactor Systems Branch (SRXB), and Region III responded to the licensee on December 8, 1997. The licensee was told that the staff considers it inappropriate to define debris generation as a dynamic effect in order to take credit for leak-before-break. The licensee agreed not to pursue this approach.

While, the DC Cook licensing basis does not include an explicit debris generation assumption for ECCS performance, the licensee is taking action to remove a large amount of fibrous insulation and degraded coatings from the containment. The licensee has also determined that the available flow area of the sump screen is much smaller than it was originally thought to be. The staff is continuing to discuss this issue with the licensee.

SCSB is preparing a reply to the WOG on their generic LBB position.

Workshop on Generic Letter 96-06

The Plant Systems Branch (SPLB) coordinated (and participated in) the joint NRC/Industry workshop on GL 96-06, "Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions," that was held at the Gaithersburg Marriott on December 4, 1997. The workshop was attended by about 90 people, and was a good exchange of information between NRC and industry. Presentations were made by the SPLB, the Materials and Chemical Engineering Branch (EMEB), the Nuclear Energy Institue (NEI), and the licensee representatives. The morning session of the workshop focused on the waterhammer and two-phase flow issues, while the afternoon session focused on thermal overpressurization of piping systems that penetrate containment. The staff discussed the status of ongoing review efforts, discussed findings and lessons learned, and answered questions from the industry. The staff also discussed Supplement 1 to GL 96-06 (issued on November 13, 1997) and Revision 1 to GL 91-18 (issued on October 8, 1997) regarding schedular considerations, corrective actions, and unresolved safety question (USQ) considerations.

The workshop participants appeared to be very interested in the presentations in general and were especially interested in the discussions concerning GL 91-18 and USQ considerations, reasons that are (and are not) acceptable for delaying final resolution of the GL 96-06 issues (as allowed by Supplement 1 of GL 96-06), use of the ASME Code Appendix F criteria for permanent resolution of the thermal overpressurization issue, content and schedule information about RAIs that will be issued by the NRC, and the overall schedule for completing review of the GL 96-06 issues. The staff indicated that RAIs should be issued by the end of the first quarter of 1998, and the GL 96-06 reviews are currently scheduled to be completed by December 31, 1999. Industry participants complained about the GL 91-18 restriction that limits use of the ASME Code Appendix F criteria for interim operability determinations of degraded piping and pipe supports to the next refueling outage. Supplement 1 to GL 96-06 makes an exception to the guidance contained in GL 91-18 and allows licensees to credit the Appendix F criteria beyond the next outage (if justified), and workshop participants felt that this exception should be the rule rather than the exception. Some participants also thought that it would be better to address any additional waterhammer concerns that are not specifically related to the containment fan coolers in a new generic letter instead of in another supplement to GL 96-06 so the books could be closed on the GL 96-06 issues. The main criticism of the NRC that was voiced during the workshop was the staff's issuance of GL 96-06 in September 1996 without first seeking public comments.

Beth Wetzel, the lead PM for GL 96-06, will issue a meeting summary within the next few weeks. The summary will include a list of questions and answers, and the presentation handouts will be included as an attachment.

Callaway Axial Offset Anomaly Update

The last two flux maps at Callaway have shown slight increases in shutdown margin indicating that the axial offset anomaly is starting to heal. Axial offset is now positive and increasing. Calculations bounding the effect of raising the power to 75 percent predict a loss of less than 100pcm. Presently the shutdown margin is about 1845 (the TS limit is 1300). The licensee increased power to 72 percent on December 9, 1997. A flux map will be taken after the core stabilizes (probably 12/12/97). The data will be analyzed and shutdown margin calculated before power is raised beyond 72 percent. The licensee has indicated that power will be raised very slowly, with evaluations of shutdown margin based on flux maps. A COLR revision will be needed before power is raised above 75 percent. All Tech Specs continue to be met. SRXB will continue to monitor the progress.

Entergy Nuclear, Inc., and Duke Engineering

Entergy Nuclear, Duke Engineering Agree to Partner

On December 9, 1997, Entergy Nuclear and Duke Engineering & Services announced that they will partner to offer management and engineering services to the nuclear industry. They announced that this agreement sets the stage for the two companies to make joint proposals to manage and operate nuclear plants by other utilities.

This agreement is the first of its kind between the two companies, both of which are non-regulated entities of major U.S. utilities. The association of the two companies was stated to provide a broad range of management, technical, and engineering support for nuclear plant opportunities.

Duke Engineering & Services is an independent operated business unit of Duke Energy Corporation and has performed work at 90 percent of U.S. commercial nuclear plants. Entergy Nuclear, Inc. was formed in February 1997 to provide management services to non-Entergy owned nuclear plants for nuclear plant operations and decommissioning. It is providing management services for the decommissioning activities at Maine Yankee nuclear plant.

Prairie Island Nuclear Generating Plant

On December 5, 1997, Jim Howard the CEO of Northern States Power Company (NSP), announced that the company would not seek approval from the Minnesota Legislature to go beyond 17 spent fuel dry storage casks at Prairie Island during the 1998 legislative session. The Minnesota state legislature enacted a bill that limits the total number of spent fuel dry storage casks to 17 at Prairie Island. The licensee has elected to delay its pursuit of legislative action until some of the other spent fuel storage initiatives are resolved, including the US Waste Policy Act of 1997 in the US Congress, the industry's legal actions against the Department of Energy and the private fuel storage initiative in Utah.

NSP currently has 7 TN-40 casks loaded and 5 more on order. The licensee has determined that 17 casks will allow operation of both units until 2007. The Prairie Island Units 1 and 2 licenses expire in 2013 and 2014, respectively. Mr. Howard informed NSP employees that his decision in no way implies that NSP intends to cease operations in 2007 at Prairie Island. NSP management has just elected to take a wait-and-see attitude with respect to spent fuel storage casks.

McGuire Nuclear Station, Unit 2

On December 4, 1997, the licensee discovered indications of potential tampering with the upper and lower personnel air lock seals. The air lock design incorporates two inflatable seals per door, for a total of four seals per air lock. The damage was identified during the performance of required testing of the air lock seal integrity to support restart of the unit. A sharp instrument was used to damage the seals. The licensee determined, and the residents confirmed, that all of the eight seals had been cut. No additional indications of tampering were identified. Currently, this unit is shut down to replace the steam generators and undertake refueling.

During a conference call, Duke Power stated that the reported tampering is being investigated, including the possibility this may be related to a work-force-reduction announcement. Walkdowns of plant systems conducted prior to the tampering event also identified mispositioned valves. The licensee intends to replace the seals, re-check valve positioning in the affected systems, and has increased security. Also, the licensee has concluded that all of the identified defects would have been self-revealing during testing.

The residents will perform additional inspections prior to Unit 2 restart. Also, on December 5, 1997, a regional security inspector arrived at the site to further review the licensee's investigation and assess compliance with applicable reportability requirements. NRR, NMSS, and RGN-II plan to have additional discussions after the completion of the RGN-II inspection.

Office of Nuclear Material Safety and Safeguards
Items of Interest
Week Ending December 12, 1997

Regulatory Guide Publication

Regulatory Guide D-3013, "Nuclear Criticality Safety Standards for Fuel and Material Facilities," will be published in the Federal Register next week. The Draft Regulatory Guide consolidates 10 Regulatory Guides endorsing the ANSI/ANS 8 National Technical Standards on Nuclear Criticality Safety. The period of review will be 90 days.

Meeting with Sierra Nuclear Corporation and Ventilated Storage Cask-24 Owners Group

On December 4, 1997, a meeting was held between representatives of the Nuclear Regulatory Commission, Sierra Nuclear Corporation (SNC), and the Ventilated Storage Cask (VSC-24) Owners Group. The meeting was held at the request of the Owners Group to allow it and SNC the opportunity to: (1) discuss the mission of the Owners Group and explain how the Group will add a cohesiveness to resolving current VSC-24 issues; (2) update NRC on the status of resolving the Confirmatory Action Letters issued to the above three utilities and SNC; (3) provide site-specific status for all three utilities and outline future VSC-24 loading needs; (4) discuss the feasibility of performing ultrasonic testing (UT) on the VSC-24 multi-assembly sealed basket closure weld; and, (5) discuss specific technical issues associated with performing the UT.

At the meeting, the Owners Group and SNC made several commitments to NRC to resolve the staff's concerns with the UT qualification process and flaw acceptance criteria. The Spent Fuel Project Office will document these commitments in a letter to SNC.

Nuclear Regulatory Commission Staff Issuance of the Safety Evaluation Report for the Crownpoint Uranium Solution Mining Project

On December 4, 1997, Division of Waste Management (DWM) staff issued its Safety Evaluation Report (SER) for Hydro Resources, Inc.'s (HRI's) proposed Crownpoint Uranium Solution Mining Project at Crownpoint, New Mexico. The SER documents the DWM safety review of the project. The SER and the Crownpoint Uranium Mining Project Final Environmental Impact Statement (FEIS), dated February 1997 (NUREG-1508), provide the bases for the Nuclear Regulatory Commission's decision to issue a 10 CFR Part 40 source material license to HRI. The staff will issue a license to HRI 30 days from issuance of the SER. The license will authorize HRI to construct and operate in situ leach (ISL) mining facilities at the Crownpoint Project for a period of five years. In preparing the SER, the NRC staff reviewed HRI's license application submittals and its Consolidated Operations Plan, Revision 2.0 (dated August 15, 1997), against the applicable regulations in 10 CFR Parts 19, 20, 40, and 71. The SER supports the Nuclear Regulatory Commission staff's finding that issuing the license to HRI will be in accordance with the aforementioned regulations, and with all applicable safety requirements of the Atomic Energy Act of 1954, as amended. There are currently seven petitions for leave to intervene that the Presiding Officer has been holding in abeyance pending the results of the staff's review.

Notice to Envirocare on its Employee Protection Policies

On December 8, 1997, the Director of the Office of Nuclear Material Safety and Safeguards notified Envirocare of Utah, Inc. (Envirocare) that its company policies are inconsistent with the employee protection provisions of the statutory requirements of Section 211 of the Energy Reorganization Act and the regulatory requirements of 10 CFR 40.7. The Nuclear Regulatory Commission's letter to Envirocare indicates, among other concerns, that the company's policies are limited in scope, since its employees are protected when raising alleged violations of state or federal environmental laws but are not afforded the same protection when raising nuclear safety concerns. Additionally, the staff stated in the letter that Envirocare's policies should be amended to indicate that: (1) employees are permitted to bypass company management and refer their concerns directly to government officials, and (2) that employees are free to bring their concerns, whether "substantial" or not to the attention of federal regulatory officials. Envirocare is requested to amend its employee protection policies in order to be consistent with both statutory and regulatory requirements and to submit the amended policies to NRC for review no later than January 8, 1998.

Multi-Agency Radiation Laboratory Protocols Manual Workgroup Meeting

On December 8-10, 1997, the Division of Waste Management (DWM) staff hosted the 10th Multi-Agency Radiation Laboratory Protocols (MARLAP) workgroup meeting to discuss and develop a multi-agency guidance manual on radioanalytical work. The MARLAP workgroup is comprised of representatives from Federal Agencies (e.g., Environmental Protection Agency, Department of Energy, Department of Defense, Department of Commerce, Department of the Interior, and Nuclear Regulatory Commission) as well as Agreement State Representatives (e.g., State of Kentucky and State of California). The purpose is to promote consistency in radioanalytical protocols, provide criteria for assessment of radioanalytical results, evaluation of radioanalytical laboratories, and promotion of high quality radioanalytical work. Over 25 participants attended the meeting. The meeting focused on several issues including: sample preparation and preservation, nuclear counting instrumentation, radiochemical separation, evaluation of radiological laboratories, radiochemical data validation, measurement statistics, quality assurance project plans, contracting laboratory services, and quality assurance/quality control. The MARLAP workgroup target is to issue a first draft MARLAP document for Agency review by June 1998 and a revised version for public review by October 1998.

Radiological Society of North America Meeting

On December 2, 1997, a management representative from the Division of Industrial and Medical Nuclear Safety provided a presentation about the ongoing comprehensive revision of 10 CFR Part 35 during the annual meeting of the Radiological Society of North America. This presentation was the same as that being provided to approximately fourteen professional societies as part of the staff's effort to solicit industry input about the revision. During the presentation, attendees were provided with an overview of the rulemaking effort and were afforded an opportunity to actively discuss the Part 35 Working Group Cross Cutting Issues and the various alternatives under consideration for their solution. A large number of attendees opted to provide comments or ask questions. Among the various comments there appeared to be agreement on the following issues: (a) medical institutions should continue to be required to have a Radiation Safety Committee to include diagnostic use only participants; (b) the requirement for a Quality Management Program was not necessary, however, the basic requirements to use a written directive, redundantly identify patients, and verify dose delivery compared to dose required seemed reasonable; and (c) Board certified physicians should not be required to take an examination demonstrating competency in radiation safety matters as their certification process adequately addressed this issue. Several attendees commented positively about the Nuclear Regulatory Commission's efforts to solicit input and keep the regulated industry informed about the ongoing revision of Part 35.

Office of Nuclear Regulatory Research
Items of Interest
Week Ending December 12, 1997

Reactor Pressure Vessel Lower Head Failure Experiments at Sandia National Laboratories

The lower head of the reactor pressure vessel (RPV) can be subject to significant thermal and pressure loads in the late phases of core melting during a severe accident. An understanding of the mode, timing, and size of lower head failure is important in the evaluation of the consequences of a severe accident because it defines the initial conditions for many of the subsequent challenges to containment integrity. A series of tests to understand the nature of RPV lower head failure are being conducted by Sandia National Laboratories (SNL). The 6th test (LHF-6) in the series was conducted successfully at SNL on December 5, 1997. The vessel failure occurred near the vessel bottom center. Data from these experiments will be used in developing and validating analytical models of RPV lower head failure.

Meeting with Nuclear Energy Institute on Risk-Informed Regulation

The Nuclear Energy Institute (NEI) has proposed a program whereby a full-scope PRA will be used, in conjunction with information on plant resource allocations, to better allocate expenditures to the most risk-significant aspects of plant design and operations. On November 24, 1997, NRC staff members met with representatives of NEI and the licensee for Arkansas Nuclear One (ANO) to discuss this program. The purpose for the meeting was to discuss the general approach developed by NEI as applied to the specific risk-informed licensing basis change being proposed by ANO. The next meeting with NEI is scheduled for December 15, 1997, to discuss specific aspects of the proposed NEI process.

Office for Analysis and Evaluation of Operational Data
Items of Interest
Week Ending December 12, 1997

Reactor Safety Course

A Perspectives on Reactor Safety Course (R-800) was presented in Region I December 8-12, 1997. This was the last course presentation under the present contract. Major areas of discussion were: Historical Perspectives, Accident Sequences, Accident Progression in the Reactor Vessel, Accident Progression in the Containment, and Accident Consequences and Emergency Plans. Sixteen people from Region I and two from Region III attended.

A special presentation of the PRA for Technical Managers Course (P-107) was conducted for Commissioner McGaffigan and Commission staff December 8-10, 1997. The course introduced PRA concepts including reactor and non-reactor applications. The course included an introduction to PRA methods used in system modeling, accident progression analysis, accident consequence analysis, and performance assessment. In addition to furnishing a discussion of the mechanics, strengths, weaknesses, and limitations of a PRA, the course provided information on advanced training available to the technical staff, the current agency policy on the use of PRA, information on how the agency has used PRA in making decisions, and the value of and methods for using PRA to get the most benefit from available resources. The course also discussed agency applications of PRA methodology including the new risk-informed Regulatory Guides and Standard Review Plans, Performance Assessment for Yucca Mountain, and the Integrated Assessment for Materials applications. NRR, RES, and NMSS managers and staff supported this special course presentation.

A special Examination Techniques Course (G-107) was presented at the TTC December 8-12, 1997. This course was added to the schedule in response to a request by the Chief, Operator Licensing Branch, NRR. This additional course was necessary because of staff turnover and a proposed change in the operator licensing program. Consequently, NRR is taking measures to ensure that sufficient NRC examiners are trained and certified to review, approve, and administer the licensing examinations that will be prepared by the licensees. Attendees were from Region II, Region III, and NRR.

Meeting with DOE

AEOD management and staff met with representatives of the Department of Energy Headquarters and Nevada Operations to discuss issues pertaining to the Aerial Measuring System (AMS), and the Federal Radiological Monitoring and Assessment Center (FRMAC) course currently under contract review. They also discussed FRMAC's participation in exercises and AMS deployment in actual events.

PRELIMINARY NOTIFICATIONS

1.  PNO-I-97-074, Connecticut Yankee Atomic Power Co. (Haddam Neck 1), CONNECTICUT YANKEE SENIOR      MANAGEMENT RESTRUCTURING

2.  PNO-I-97-075, Mqs Inspection, Inc. RADIOGRAPHY SOURCE DISCONNECT AT A TEMPORARY JOBSITE

3.  PNO-I-97-075A, Mqs Inspection, Inc., RADIOGRAPHY SOURCE DISCONNECT AT A TEMPORARY JOBSITE      (UPDATE)

Office of Administration
Items of Interest
Week Ending December 12, 1997

Contract Awards

Contract No. NRC-10-98-144 entitled, "Medical Review Officer (MRO) Services" was awarded to Rodney V. Burbach, M.D., P.C. The fixed price/requirements type contract in the amount of $33,961.90 is effective December 15, 1997, through December 14, 1999. This procurement was completed in 7 weeks. Award was made using the following streamlining initiatives: electronic transmittal of SOW, use of commercial product description, and reduced proposal preparation time.

On December 5, 1997, a fixed price requirements contract was awarded to Kelly & DeWitt, Inc., under a small business set-aside, entitled "NRC Issuances and Indexes." The contractor is responsible for the preparation of a camera-quality copy and an electronic version of the monthly issuances, including quarterly and semi-annual indexes, and a six-month hardbound edition of the NRC Issuances and Indexes. The contract award amount is $316,662.58 and the period of performance is December 7, 1997, through December 6, 2002. The streamlining initiatives utilized included: deadline was set for proposer's questions, proposal preparation time was reduced, the number of pages in an offeror's proposal was limited, and foldouts/sales brochures were prohibited.

Training for Acquisition Personnel

On December 9 and December 12, 1997, the Division of Contracts and Property Management (DCPM) sponsored two separate all day training sessions for the acquisition professional. The first session, held December 9, 1997, was attended by DCPM and OGC staff. This training session focused on the rewrite of Federal Acquisition Regulation Part 15. The major purpose of the rewrite is to improve the efficiency of the competitive negotiation process. A secondary purpose of the rewrite is to improve communication between the contracting parties during the negotiation process. The course was taught by Ralph C. Nash, Jr., Professor Emeritus of Law at George Washington University's National Law Center. Professor Nash, a widely respected authority on this subject, has been actively engaged in Government contracting as an administrator, attorney, educator, and author for over 35 years.

The second training session, held December 12, 1997, covered the subject, "Research for the Acquisition Professional". The training session, attended by DCPM staff, featured lecture, discussion, and hands-on exercises for conducting research on the Internet. The course included a brief introduction to the Internet and an introduction to various Internet sites -- government and private industry -- which could be accessed to obtain information of importance to the acquisition professional. At the completion of the course, attendees used the Internet to identify and locate acquisition information materials and sources, as well as to access a variety of sources of information to support market research.

OWFN Restack

The 16th floor Restack phase is progressing on schedule which will allow SECY, EDO staff, OCA staff, and the Director, OIP to move to the 16th floor beginning January 8, 1998. On December 10, 1997, members of the ADM Project Team met with representatives of the carpet manufacturer, the carpet installer, and the general contractor to discuss concerns over the appearance of the installed carpet. The manufacturer has sent out several carpet tiles to be tested and is confident that a remedy will be found which will not interfere with the scheduled move date.

CCTV Cameras

Cabling for the new outdoor cameras is in the process of being installed. A few additional cameras are being added and black and white cameras are being replaced with color cameras/monitors throughout the White Flint complex as part of the NRC Headquarters final phase of physical security upgrades.

Rules Activity

The Rules and Directives Branch (RDB) provided assistance in the preparation of a document withdrawing a direct final rule published October 17, 1997 (62 FR 53933), concerning the incorporation by reference of the most recent version of a national consensus standard for power, instrumentation, and control portions of safety systems in nuclear power plants. The direct final rule is being withdrawn because the NRC received significant adverse comment on this action. The direct final rule must be withdrawn before the effective date that was specified in the direct final rule when it was originally published.

Chief Information Officer
Items of Interest
Week Ending December 12, 1997

Freedom of Information and Privacy Act Requests Received during the 5-Day Period of December 5-11, 1997:

Westinghouse Nuclear Fuel Div., SC, audits or visits since 1/1/96. (FOIA/PA-97-471)

MLTS database, portable gauge licensees on diskette. (FOIA/PA-97-472)

Susquehanna power plant, latest OI report and exhibits. (FOIA/PA-97-473)

Schlumberger Company, violations for past 3 years. (FOIA/PA-97-474)

Nuclear Materials and Equipment Corp., form AEC-592 (identifies areas of license non-compliance). (FOIA/PA-97-475)

Vacancy Announcement R9758016, Sr. Fuel Facility Project Inspector. (FOIA/PA-97-476)

Diablo Canyon, allegation RIV-95-A-0067, pressurized safety valve. (FOIA/PA-97-477)

IMPAC listing. (FOIA/PA-97-478)

Office of Human Resources
Items of Interest
Week Ending December 12, 1997

Workshop on Controlling Your Personal Finances Held

On December 3 and 10, 1997, the NRC Employee Assistance Program sponsored a workshop, "Controlling Your Personal Finances." More than 80 employees attended the two sessions. Judy McCoid, Education Director of the Consumer Credit Counseling Service (CCCS), gave a talk on budgeting and debt management, which included discussions on how to strengthen financial security, plan a realistic budget, obtain credit and maintain a good credit record, choose the best credit cards, and get copies of and interpret credit reports.

CCCS is a non-profit financial counseling service dedicated to helping people learn to live within their budgets and pay off their debts. Services offered by CCCS include free professional money management advice, a debt repayment plan, mortgage counseling, and viable alternatives to personal bankruptcy.

Office of Public Affairs
Items of Interest
Week Ending December 12, 1997

Media Interest

Several newspapers interviewed Chairman Jackson on a telephone conference call regarding the proposed $2.1M fine against Millstone.

Nine reporters attended a special evaluation team exit meeting at Clinton.

School Volunteers Program

Ron Hernan and Tom Fredrichs, NRR, Ed Halman, ADM, Martie Lopez-Nagle, OIG, and Bob Miller, ADM, visited Westland M.S. to talk about their careers in electrical engineering, chemistry, business, personnel, and photography.

Charlotte Abrams, NMSS, talked about rocks and geology with students at Charles Drew E.S.

Bret Leslie, NMSS, talked about geology with students at Whetstone E.S.

Office of International Programs
Items of Interest
Week Ending December 12, 1997

IAEA Vacancy Notices

The following notices from the International Atomic Energy Agency have been posted on NRC bulletin boards:

Visit of Dr. Roger Clarke, Director, U.K. National Radiological Protection Board (NRPB) and Chairman of the International Commission on Radiological Protection (ICRP)

Dr. Roger H. Clarke visited the Commission on December 11, 1997. The purpose of his visit was to discuss his views on 1) release of two ICRP Publications- Policy for Waste Disposal and Dose Limit for Intakes of Radionuclides of Workers, 2) adoption of Publication 60 in the U.S., 3) threshold controversy, and 4) ICRP future program of work. While here, he also discussed with the Commission the issue of how to effectively communicate the concept of "risk" to the public.

Annual Program Review Meeting with Gosatomnadzor, the Russian Nuclear Regulator, December 8-12, 1997

During the week of December 8-12, 1997, representatives of the Russian Federal Authority on Nuclear and Radiation Safety (Gosatomnadzor - GAN), including Alexander Gutsalov, First Deputy Chairman; Alexander Matveev, Director, Scientific and Technical Department; Andrei Vistgof, Director, Inter-Regional Information Center; and Irina Sokolova, International Relations Officer, visited the NRC during the period December 8-12, 1997.

During their visit, the representatives met with Chairman Jackson and the Commissioners, the Executive Director for Operations, and appropriate members of the NRC staff. This was the sixth annual meeting between the two agencies, the purpose of which was to review program results and accomplishments since the last meeting in February 1997, to reaffirm or revise previous program commitments, and to consider proposals for future activities under the "Lisbon" program. The NRC agreed to support the program efforts described in the Memorandum of Meeting signed on December 12 by Acting Executive Director for Operations Hugh Thompson and First Deputy Chairman of GAN.

Office of the Secretary
Items of Interest
Week Ending December 12, 1997

Commission Correspondence Released to the Public

No Commission correspondence was released this week

Federal Register Notices Issued

1.     Advisory Committee on Reactor Safeguards; Subcommittee on Human Factors; Notice of Meeting on
        January 20, 1998

2.     Advisory Committee on Reactor Safeguards; Subcommittee on Plant License Renewal; Notice of Meeting on
        January 23, 1998

3.     Receipt of an Amended Petition for Rulemaking: Peter G. Crane

Region I
Items of Interest
Week Ending December 12, 1997

PECO Energy Company - Peach Bottom Unit 1

On December 4, 1997, the NRC Region I Project Manager and the Peach Bottom site Senior Resident Inspector toured the Peach Bottom Unit 1 Reactor. Peach Bottom Unit 1 was a High Temperature Gas Cooled Reactor which operated from 1964 until 1972, when the reactor was shut down. The fuel was off loaded and all liquids were shipped for disposal in 1974. Unit 1 currently is in safe storage and is scheduled to be decommissioned, along with Units 2 and 3, after the licenses for Units 2 and 3 are due to expire in 2015. The tour included the waste handling building, the refueling platform, the turbine building, and the primary containment. The tour was performed to become familiar with and to assess the activities which may be required to fully decommission the facility. The Project Manager also performed a preliminary evaluation of the complexity of the radiological surveys required to provide the necessary information to demonstrate that residual radioactivity levels satisfy the criteria for license termination.

Region II
Items of Interest
Week Ending December 12, 1997

ANS Conference

On December 8-10, 1997, there was a Utility/NRC Interface Workshop at the Atlanta Marriott Northwest in Atlanta, Georgia. The workshop was well attended by Region II Utility senior managers, Region II managers, and NRC senior managers. Approximately 90 participants discussed topics such as enforcement, allegations, risk-informed regulation, and the Year 2000 computer issue.

Carolina Power and Light Company - Harris

Representatives from Carolina Power and Light Company were in the Regional Office to attend a Harris Self-Assessment presentation. The licensee discussed overall plant performance, organizational initiatives, and strengths and challenges in each functional area. The Harris SALP period ends January 17, 1998.

Region III
Items of Interest
Week Ending December 12, 1997

Special Inspection Team at Portsmouth Gaseous Diffusion Plant

On December 8, 1997, NRC staff commenced a special inspection at the Portsmouth Gaseous Diffusion Plant. The inspection reviewed the corrective actions taken by the U.S. Enrichment Corporation to the problems identified over the last six months with the Nuclear Criticality Safety Controls Program.

Clinton Nuclear Power Plant - Special Evaluation Team Public Exit

On December 11, 1997, a public exit meeting was held at the Clinton Nuclear Power Plant to present the findings of NRC's Special Evaluation Team. The team monitored Illinois Power Company's Integrated Safety Assessment and, in addition, performed an independent review of the plant's performance. The 10-member team was headed by Kenneth Perkins, Jr., who is Director of the NRC's Field Office in Walnut Creek, California.

The NRC team observed the work of the utility assessment at the Clinton site September 24-October 3. Its independent onsite follow-up took place October 20-31. The written report of the NRC team's findings will be issued in late December.

Region IV
Items of Interest
Week Ending December 12, 1997

Pre-Decisional Enforcement Conference with South Texas Project

On Monday, December 8, the Regional Administrator and members of the Region IV and NRR staffs met with representatives of the South Texas Project to conduct a predecisional enforcement conference. The purpose of the pre-decisional enforcement conference was to discuss seven apparent violations: one related to corrective action, five related to design control, and one related to 10 CFR 50.59 safety evaluations.

Chairman Jackson Visit to Region IV (Arlington) Office

On December 10, 1997, Chairman Jackson visited Region IV accompanied by members of her personal staff. The Chairman met with regional management and small groups of the regional staff. The groups represented all aspects of regional operations, including both resident and region-based inspectors, as well as the investigative and administrative staff.

Region IV Resident Inspector Counterpart Meeting

The semi-annual Resident Inspector Counterpart Meeting was held in the Region IV offices on December 10-12, 1997. The Director, Office of Nuclear Reactor Regulation (NRR), was the keynote speaker for the meeting. The meeting agenda included presentations by NRR management and staff concerning topics of current interest, including the recent changes to Generic Letter 91-18, the current application of 10CFR50.59, recent PRA initiatives, and an update on the application of the maintenance rule. The agenda included a workshop to improve inspection of plant material condition. In addition, two outside speakers representing Texas Utilities Electric Company and the Texas Independent System Operator presented information concerning grid reliability and stability in a deregulated electricity market.

Office of the Executive Director for Operations
Items of Interest
Week Ending December 12, 1997

Office of Small Business and Civil Rights

Proposed Rule Signed by EDO

In accordance with the rulemaking authority delegated to the Executive Director for Operations (EDO), a proposed joint rule promulgated by the U.S. Department of Justice was signed by the EDO on December 9, 1997, that would amend the NRC regulations at 10 CFR Part 4 to implement the provisions of Title IX of the Education Amendments of 1972. Title IX prohibits discrimination on the basis of sex in education programs and activities receiving or benefitting from Federal financial assistance. The Office of Small Business and Civil Rights is responsible for Title IX implementation oversight.