ML20198D171
| ML20198D171 | |
| Person / Time | |
|---|---|
| Issue date: | 12/18/1997 |
| From: | Blaha J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| SECY-97-292, WIR-971212, NUDOCS 9801080147 | |
| Download: ML20198D171 (27) | |
Text
. _ - _ _ __- .
j ' ocosoooooooooooooooooooo I
RELEASED TO THE PDR o lll/72 AkJ
- UNITED STATES datg giggg ~ #
NUCLEAR R EGULATORY COMMISSION ' * * * * * * * * * * * * * ' ) * * * * * *
- WASHINGTON, D. C. 20066 INFORMATION REPORT December 18. 1997 SECY 97-292 f.0.t: The Ccmissioners FrT1: James L. Blaha Assistant for Operations. Offict of the EDO Subiect: WEEKLY INFORMATION REPORT - WEEK ENDING DECEMBER 12, 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 I Small Business & Civil Rights J*
Enforcement K*
State Programs L*
Public Affairs M International Programs N Office of the Secretary 0 Region I P Region II P Region III P Region IV P Executive Director for Operations Q Congressional Affairs R*
- No input this week.
m i
l p q ms~-'q s
s L. Blaha 080022 Listant for Operations. OED0
Contact:
i,3 M. Leach. OEDO -
9001000147 971218
.V)llFl!!Tl w.~~ I PDR COMMS NRCC WEEKLYINFOREPT PDR
Office of Nuclear Reactor Regulation ,
Items of Interest Week Ending December 12. 1997 South Texas Proiect Unit 2 Hctiston 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 imalement a 3.0 volt Interim Plugging Criteria (IPC) for steam generator (SG) tu>e 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 ex)anded at the tube support plates (TSPs) to
" lock" the TSPs in ) lace and t1us justify a higher voltage re) air limit than allowed in Generic _etter 95-05 due to negligible burst proba)ility and reduced leakage during accident conditions. Experience from the last SG tube eddy current inspection at Braidwood Unit I resulted in the identification of a voltage-dependent growth rate that resulted in nonconservative predictions of the end-of-cycle (E0C) conditions. This issue needs to be addressed to ensure that nonconservative predictions of E0C 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 DECEMBER 12. 19?? ENCLOSURE A
I Mr. Hrowca, the CE'0wners Group also scarted 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 Brarch (EMCB) and Region III participated in a conference call with representatives of- American Electric Power, the licensee for the DC Cook i Units 1 and 2. The )urpose of.the call was to discuss the ap)lication of leak-before break (L3B) in order to show the operability of tie 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 Uwners 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 1.BB position.
Workshoo on Generic letter 96-06 The Plant Systems Branch (SPLB) coordinated (and )articipated 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
..ngineering Branch (EMEB), the Nuclear Energy Institue (NEI) and the licensee representatives. The morning session of the workshop focused on the waterhaner and two-phase flow issues, while the afternoon session focused on
-thermal overpressur12ation of piping systems that penetrate containment. The DECEMBER 12. 1997 ENCLOSURE A
3 - , - - -- - - . - -- - -
i 1 staff disdussed 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 y Revision 1.to GL 91-18-(issued on October 8.-1997) regarding schedular considerations, corrective actions, and unresolved safety question (US0) considerations.
.The workshop partic1 pants appeared to be very interested in the' presentations in. general and were especially interested in.the discussions concerning GL 91-18-and US0 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 RAls that will be' issued by the NRC. e 'the overall '
- schedule for completing review of the GL'96-06 issues. The staff indicated that RAls 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 containet 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 linstead 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 issdsnce 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 Anomalv Uodate The last two flux maps at Callaway have shown slight increases in shutdown margin indicating that the axial offset 6nomaly is starting to heal. Axial offset is now positive and increasing. Calculations bounding the effect of
. raising the power to 75 sercent predict a loss of less- than 100pcm. Presently the shutdown margin is-a)out 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 shuidown margin calculated before power is raised beyond _72 percent. The licensee has indicated that power will be. raised very sicwly, 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.
- DECEMBER-12, 1997- ENCLOSURE A
= . - _ _ . - .
p p.
~
Enterov Nuclear: inc. and Duke Enoineerina Entergy Nuclear. Duke' Engineering _ Agree to Partner- l
'0n December 19, 1997,-Entergy. Nuclear and Duke Engineering & Services announced:
that they Will- partner to offer management and engineering services to the +
nuclear 1 industry. They announced that:this agreement sets the stage for the i two companies to make joint proposals to~ manage and operate nuclear plants by ;
other utilities.
-This agreement 11s 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 mansgement, 7 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 . i
, management services to non-Entergy owned nuclear plants for nuclear plant
-operations and decommissioning. It is aroviding management services for the decommissioning activities at Maine Yan(ee nuclear plant. ;
Prairie Island Nuclear Generatina Plan n_t 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. lhe 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 o>erations in 2007 at Prairie Island. NSP management has just elected to tace 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 DECEMBER 12. 1997- ENCLOSURE A iv,- -, - . . . - , - 4 , 'e-- .-a a e - - - . y,,
-e
- 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 re)orted tepering is being investigated. including the )ossibility this-may ye relami to a work-force-reduction-announcement. Walcdowns of plant systems conducted prior to the tampering event also identified mispositioned valves. The licensee intends to re> lace the seals, re-check valve )ositioning in the affected- -
systems. and las increased security. Also, tie licensee has concluded that all of the identified defects would have been self-revedling 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.
DECEMBER 12, 1997 ENCLOSURE A
m Office of Nuclear Material Safety and Safeguards Items of Interest Week Ending December 12, 1997 Reaulatory Guide PublicatiQn i
Regulatory Guide D-3013, " Nuclear Criticality Safety Standards for Fuel and Materfal facilities. " will be published in the Federal Reaister next week.
-The Draft Regulatory Guide consolidates 10 Regulatory Guides endorsing the ANSI /ANS 8 National Technical Standards on Nuclear Criticali.y Safety. The period of review will be 90 days.
Meetina with Sierra Nuclear Corooretion and Ventilated Storaae Cask-24 Owne.Ch CtCD1!D 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 Grou] 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 anJ SNC:
(3) provide site-specific stai.us 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 Reaulatory Commission Staff Issuance of the Safety Evaluation Report for the-Crownooint Uranium Solution Minino 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 ap)licable regulations in 10 CFR Parts 19. 20. 40, and 71. The SER supports t1e Nuclear Regulatory Commission staff's finding that issuing the license.to HRI will be in accordance with the aforementioned regulations.
and with all a)plicable safety requirements of the Atomic Energy Act of 1954.
as amended, here are currently seven petitions for leave to intervene that DECEMBER 12, 1997 ENCLOSUP.E B t .
the Presiding Officer has been holding in abeyanc6 pending the results-of the staff's review.
Notice to Envirocare on its Emoloyee Protection Policies Oi, December 8. 1997, the Director of the Office of Nuclear Material Safety and Safeguards notified Envirocare of Utah. Inc. (Envirocare) that its com)any policies are inconsistent with the employee protection provisions of t1e 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 com)any's policies are limited in scope. since its employees are protected w1en raising alleged violations of state or federal environmentC 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 R. 1998. ,
Multi-Aaency Radiation Laboratory Protocols Manual Workaroun Meetina 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 develo) a multi-agency guicance nianual on radioanalytical work. The MARLAP workgroup is comprised of re)resentatives from Federal Agencies (e.g., Environmental Protection Agency. )epartment 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 y puipose 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 assuranceprojectplans,contractinglaboratoryservices,andquality a:surance/qu6lity 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.
I Radioloaical Society of North America Meetina On December 2.1997, a management representative from the Division of industrial and Medical Nuclear Safety arovided a presentation about the ongoing comprehensive revision of 10 C R 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 DECEMBER 12. 1997 ENCLOSURE B
4.
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 wereiafforded an opportunity to ' actively discuss- the Part 35 Working Group Cross Cutting Issues and.the various alternatives:unders consideration for their sulution. LA-large number _ of attendees o)ted to=
provide coments or ask questions. Among the various comments t1ere appeared -
- to be agreement on the following issues: (a) medical institutions should-
-continue to b. cequired to have a Radiation Safety Committee to include 7
dibnostic use only particiaants:-(b)-the requirement for a Quality ManagementL Program was-not necessary', lowever, the basic requirements to use a written -
- directive.: redundantly identify patients, and verify dose _ delivery compared to' dose . required':::+med reasonable; and (c) Board certified physicians should not be required to take an examination demonstrating competency in radiation u
- safety matters as their certification process adequately addressed this: issue.
- Several attendees commented positively about the Nuclear Regulatory -
w
,Comission's efforts to solicit input and keep the regulated industry informed Labout the ongoing. revision of Part 35.
i, R
1
-0ECEMBER 12, 1997- ENCLOSURE B ,
Office of Nuclear Regulatory Research items of Interest Week Ending December 12. 1997 Reactor Pressure Vessel lower Head Failure Exoeriments at Sandia National
- aboratories 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 Lat; oratories (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.
- tieetino with Nuclear Eneroy Institute on Risk-Informed Reaulation The Nuclear Energy Institute (NEI) has proposed a program whoreby 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 (AN0) to discuss this program. The pur the general approach developed by NEl as a) pose for the meeting was to discussplied to t licensing basis change being proposed by A10. The next meeting with NEI is scheduled for December 15, 1997, to discuss 'wcific aspects of the proposed NEI process.
DECEMBER 12, 1997 ENCLOSURE C
'I =
b "
Office for1 Analysis and Evaluation of Operational. Data Itemstof 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 NAccident Progression in the Reactor Vessel. Accident Progression in xthe Containment, and Accident Consequences and Emergency Plans. Sixteen
- people ~ from_ Region -1 and two from Pagion III attended.
'A special cresentation of the FRA 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-
- applii
- ations. The course included an introduction to PRA methods used in 1 system modeling. accMent progression analysis, accident consequence analysis, land performance assenment. -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 fused PRA in making policy on decisions, andthe theuse of PRA, value of andinformation methods foron howPRA using the to agency has 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 prosentation.
6 -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 licensingprogram. Consequently. NRR is taking measures to ensure that sufficient NRL examiners are trained and certified to review. ap3 rove, and administer the licensing examinations that will be Attendees were from~ Region II, Region III, and NRR. prepared by tie licensees.
Meetina with DOE AE00 management and staff met with representatives of the Department of Energy Headquarters and Nevada Operations to discuss issues aertaining to the Aerial Measuring System (AMS). and the Federal Radiological ionitoring 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- 4 l
- 1. PN0-I-97-074, Connecticut Yankee Atomic Power Co. (Haddam Neck 1).
l CONNECTICUT YANKEE SENIOR MANAGEMENT RESTRUCTURING DECEMBER ~12, 1997 ENCLOSURE D
- 2. PNO I-97-075. Mqs Inspection. Inc. PADIOGRAPHY SOURCE DISCONNECT AT A
-TEMPORARY JOBSITE
.3. PN0 1-97-075A. Mqs Inspection Inc.. RADIOGRAPHY SOURCE DISCONNECT AT A TEMPORARY JOBSITE (UPDATE)
DECEMBER 12, 1997 ENCLOSURE D
.c
W' .p M .
i 10ffice: of Admiriistration? -
. Items of Interest-.. -
l Week Ending-December 12, 1997 ;
J Cdritfact Awards Contract No.-NRC-10-98-144 erititl(.J. " Medical Review Officer (MRO) Services" >
wasl awarded to Rodney V. Burbach. M.D., P,C. The. fixed price / requirements type contract in the amount of'133,961.90 is effective December- 15;;1997.
througn December 14,:1999. This procurement was completc.d in-7 weeks. Award'
=
was made using the following streamlining initiatives- electronic transmittal ;
u of-50W 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 hardbouno 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 4
-proposer's questions, proposal preparation time was reduced the number of
- pages in an offeror's proposal was limited, ar.d foldouts / sales brochurer were prohibited.
Trainina for Acouisition 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 0GC 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 )arties during the negotiation process. The course was taught by Ralph C. Nas1, 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 i_n 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, discussic1. and hands-on exercises for conducting research on the Internet. The course included a brief introduction to the Internet and an1 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.
DECEMBER 12, 1997 ENCLOSURE F i
d
~ ,,< ~ -l,c. , . , - , . ,
OWFN Restack The 16th' floor Restack phase is progressing on schedule which will allow SECY, EDO staff. OCA staff, and the Director. OlP to move to the 16th floor beginning January 8. 1998. On December 10, 1997. members of the ADM Project Team met with re)resentatives of the carpet manufacturer, the carpet installer, and tie 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 )ortions of safety systems in nuclear power plants. The direct final rule is )eing 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.
DECEMBER 12. 1997 ENCLOSURE F
Chief!Informat' ion:0fficer:
Items of Interest 1 Week Ending-December 12. 1997 Treedom'of Information~and= Privacy'Act Recuests Received durina the 5-Day-
)eriod of December-5-11 '1997:-
-Westin
'(F0lA/ghouse~
PA-97-471)Nuclear fuel'Div.-,-scc audits or. visits since 1/1/96.
~
MLTS~~ database, portable' gauge-licensees on-diskette. (F01A/PA-97-472)
- Susquehanna power-plant.f latest 01 report and exhibits. (F01A/PA-97-473)
Schlumberger: Company. violations for past 3 years. (F01A/PA-97-474) y Nuclear Materials 'and Equipment Corp.. form AEC-592 (identifies areas of
-license _non-compliance). -(F01A/PA-97-475) iVacancy Announcement R9758016 Sr -Fuel Facility Project Inspector
'(F01A/PA-97-476)
Diablo Canyon. allegation RIV-95 A-0067, pressurized safety valve. j (F01A/PA-97-477) i e )
ll IMPAC' listing. (F01A/PA 97-478)
T' 1
U e
- l a>
i DECEMBER 12.-1997 ENCLOSURE G
.- . - - , . . . - . - . . . . . . . - . = 1
Office of Human Resources Items of Interest Week Ending December 12, 1997 Workshoo on Controllina Your Personal Finances Held On December 3 and 10, 1997.- the NRC Employee As;istance Program sponsored a '
workshop. " Controlling Your Personal Finances." More than 80 em)loyees attended the two sessions. Judy McCoid. Education Director of tie 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.
Arrivals None.
Retirements POTTER. John TECHNICAL ASSISTANT (PFT) RII URYC. Bruno DIRECTOR. EICS (PFT) RII Departures i KENNEDY. Janet PROJECT MANAGER (PFT) NRR DECEMBER 12. 1997 ENCLOSURE I
L y
c ;
X-
+ '"
- Offic'e of Public> Affairs
- 1 -Items of' Interest;
~ '
- Week 1Endi_ng December 12.}1997
- Media Int (fJi.ti Severa1' newspapers interviewed Chairman Jackson onLa telephone _ conference call--
regarding the. proposed $2.1H fint. against Millstone. ,
.Nine{ reporters attended a:special-ev~slust'on team exit meeting-at Clinton.
-School Volunteers ^Proaram--
Ron-Hernan and: Tom Fredrichs. NRR.- Ed Halman, 'ADM. Martie Lopez-Nagle.; OIG; ..
iand-Bob' Hiller. ' ADM. visited Westland M.S. to talk about their c6reers in electrical engineering, chemistry. business, personnel.- and photography.
Charlotte Abrams.ENMSS talked about rocks and geology with students at i Charles' Drew E.S.
0 (Bret-Leslie._NMSS,talkedabout'geologywithstudentsatWhetstoneE.S. ,
gss Releases ~
Headqu'arters:-
9 7-180- NRC-Proposes-$2.1 Million in Fines. for Violations at Millstone Station 97-181 Note to Editors: ACRS Meeting January 23 J 97-182 Note to Editors: ACRS Meeting January 20-Regions:-
I 97-155 NRC. Pennsylvania Firm to Disciss Apparent Violations Involving Radiation Safety Program on December 12
-I-97-157' NRC.- PP&L to: Discuss. Apparent Violations at Susquehanna Plant 97 85~ NRC Staff Proposes $55.000 Fine Against Sequoyah Nuclear Power-Plant' '
II-97 NRC Staff to Hold Predecisional Enforcement Conference With CP&lito Discuss Regulatory Concerns at-Brunswick II-97-87L NRC Staff Plans. Performance Review Meeting At Framatome Facility in Lynct. burg. Virginia -
111-97 106- NRC Staff to Meet Wie ican Electric-Power Company to iDiscuss:the D.C. Cook . .at's Readiness to Restart p
6' g4
' DECEMBER 12.-1997 ENCLOSURE M 4
\- -
, 3. -
't i
'111-97-107: NRC-Staff. Proposes;$55.000 Fine Against U.S. Enrichment i Corporation for Security Violations at Paducah Plant .
. t t
4
.111-97 108 NRC Staff to Meet =With Consumers. Energy Co. to Discuss Apparent Violations'at Palisades Nuclear Plant.
IV-97-75 Meeting. Scheduled to Address Pilot Program for NRC Oversight at' DOE s Berkeley Laboratory l
IV-97 NRC. University of South Dakota to Discuss Apparent Violations in Handling of-Radioactive Materiais d
J-9 L
\
. DECEMBER 12. 1997 ENCLOSURE M -
J p
< i; =.-
^
n n .
4 ~
Wil- Office of: International Programs;- - a' Items 2of Interest-y -. Week Ending December-12F1997E 1
't IAEA Vacancy Not.irag -
LThe.following notices l from.the International: Atomic EnergyfAgency have been .
posted:on NRC bulletin boards:- , l P-5 Section Head- 97/076.: >
Safeguards , .
P 5;.Section Head" -97/070- l Safeguards,
" 5 D-1LDirector_. . :97/071 1 Technical 1Co-operation P5tunitHead..P/ojectMgmt.&.SupportforSupportDiv. 97/073 ,
Safeguards.-
'P-5 Unit Head.cProject Mgmt. & Support for 0per. Div. 97/0741
' Safeguards +
0' p.47 Budget & Finance'0fficer 97/075 L Safeguards-
'P-4.-Safeguards Analyst 97/078 'i l.. - Safeguards.-
.P-3 Management Analyst 97/079-Administration v
0-1 Director: 97/080 SafeguaNs 4 P 4 -Research Reactor Specialist 97/081 Research and 1sotopes iP-3 Supervi~sor Radiometry Group: 97/082-Research and; Isotopes-P-1 Reactor Engineer 97/083 Nuclear Energy P-4 Regional Manager:for Radiation & Waste-Safety 97/801-Technical- Co-operation -
?
- DECEMBER 12.1 1997.e ENCLOSURE N
' +.
Visit of Dr. Rooer Clarke. Director. U.K. National Radiolooical Protection 2
Board (NRPB) and Chairman of the international Commission on Radiolooical orctection (ICRP)
Dr. Roger H. Clarke visited the Comission on Decerber 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 l Commission the issue of how to effectively communicate the concept of ' risk' to the public.
Annual Proaram Review Meetina with Gosatomnadzor. the Russian Nuclear Reaulator. December 8-12. 1997 During the week of Dec mber 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 t commitments, and to consider proposals for future activities under the
' Lisbon ~ program. The NRC agreed to support the program efforts described in the Memorandam of Meeting signed on December 12 by Acting Executive Director for Operations Hugh Thompson and First Deputy Chairman of GAN, L
-DECEMBER 12, 1997 ENCLOSURE N l
Office of the Secretary items of Interest-Week Ending December 12, 1997 Decision Documents Released to the Public Document Date Subject
- 1. SECY-97-263 11/4/97 Request by New Mexico to Relincuish Authority for Sealed Source anc Device Evaluation and Approval
- SRM on 97-263 12/2/97 (same)
- Commission Voting 12/2/97 (same)
Record on 97-263
- 2. SECY-97-241 10/17/97 Redelegation of Authority
- SRM on 97-241 12/2/97 (same)
- Commission Voting 12/2/97 (same)
Record on 97-241
- 3. SECY-97-273 11/26/97 Staff Requirements - SECY-96-221 -
"ImprovingNRC'sControlOver,and Licensees Accountability for.
Generally and Specifically Licensed Devices" Information Papers Released to the Public _
- 1. SECY-97-267 11/13/97 Weekly Information Report - Week Ending November 7. Z 37
- 2. SECY-97-272 11/26/97 Weekly Information Report - Week Ending November 21. 1997
- 3. SECY-97-277 12/4/97 Weekly Information Report - Week Ending November 28. 1997
- 4. SECY-97-280 12/3/97 Proposed NRC Generic Letter " Steam Generator Tube Inspection Techniques"
- 5. SECY-97-282 12/3/97 Results of the Staff's Evaluation of Ongoing Feedback from Licensees on the Impact of NRC's Activities on Licensees' Operations
- 6. SECY-97-283 12/4/97 Recovery of Millstone Nuclear Power Station DECEMBER 12, 1997 ENCLOSURE 0
Memorandum Released to the Public
- 1. M971029B 12/11/97 Staff Requirements - SECY-97-242 -
Update on the Site Decommissioning Management Plan and Briefing on Site Decommissioning Management Plan (SDMP),
Wednesday, October 29. 1997 Commission Correspondence Released to the Public No Commission correspondence was released this week Federal Reaister 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 DECEMBER 12, 1997 ENCLOSURE 0
x E'
Reg' ion:11
' Items.ofnInterest--
Week Ending December 12,:1997-
- PECO Enerav Comoany - Peach Bottom Unit i On December 4.=1997,Ethe NRC Region I Project Manager-and the Peach BottomL 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 -
11964 until71972, when the reactor was shut down. The fuel was off loaded and!
tall-liquidsswere shipped for disposal in 1974. Unit 1- currently is-in safe --
--stor6Tand'is scheduled to be decommissioned, along with Units- 2 and 3cafter
-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 1
- : facility. The Project Manager also performed a preliminary evaluation of thei '
complexity of the radiological surveys required to provide the necessary W 'information-to demonstrate that residual radioactivity levels satisfy the-criterib':for license termination.
1 l
S
- n 3 DECEMBER 12 D1997- ENCL.0SURE P
^
O' Region I.
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 11 Utility senior-managers. Region Il 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 Licht Comoany - 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.
-DECEMBER 12, 1997 ENCLOSURE P
Region 111 Items of Interest Week Ending December 12. 1997 Soecial Insnection 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 corre:tive actions taken by the U.S. Enrichment Corporation to the problems identified c/er 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 Jublic exit meeting was helti at the Clinton Nuclear Power Plant to present tie 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 )lant's performance. . The 10 member team was headed by Kenneth Perkins. Jr.. w1o 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.
9 DECEMBER 12. 1997 ENCLOSURE P
i Region IV-Items of Interest '!
Week Ending December 12. 1997 l Erp ')ecisional Enforcement Conference with South Texas Pro.iect-On Honday. December 8. the Regional Administrator and members of the Region IV- '
and NRR staffs met with representative.e of the South Texas Project to conduct a predecisiona' 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. -3 ,
Chairman Jackson Visit-to Reaion IV (Ar11naton) Office-On December 10l1997, Chairman Jackson visited Region IV accompanied by- !
members of her personal staff. The Chairman met with regional managen.ent and l small, groups of the regional staff. The groups represented all aspects of i re ional operations, including both resident and region based inspectors, as j we 1 as the investigative and administrative staff.
l Reaion'1V Resident in;oector Countercart Meetina j The semi annual Resident Inspector Counterpa.*t 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 fcr 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 u)date on the application.of the maintenance rule. . The agenda included a-wortshop to '
improve inspection of plant material condition. In addition, two outside ,
. g- speakers representing Texas Utilities Electric Company and the Texas Independent System Operator presented information concerning grid reliability
.- =and stability in a deregulated electricity market.
4 I
f
, f L
0ECEMBER 12. 1997 ENCLOSURE P [
V
- -%J',,m',-[.e,<<-se.- % .w . si- % -e. L, - , . .w un n s . yow- -emray, h~ .'e 5,. - , . m h U, , .,, m m .. e.-w-- ,r. m, , ,, ,,-y _-a, *-e- .r,.y+.y.,pw
w- . _. . _ . . . . . . - - . . .-
A Office of the Executive Director for Operations Items of Interest .
Week Ending December 12. 1997 Office of small Business and Civil Richts Prooosed Rule Sianed by EDO In accordance with the~rulemaking authority delegated to the Executive Director for Operations (EDO) a aroposed joint rule promulgated by the U.S. t Departnent of Justice was signed ay the E M on December 9. 1997, that would -,
anend the NRC regulations at 10 CFR Part 4 to implement the provisions of Title IX of the Education Amendments of 1972. Title IX-prohibits i
' 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 1mplementation oversight. i Y
e-1 i
b DECEMBER 12. 1997 ENCLOSURE 0 T
,--,y. ,.--., y 7.,,, .-