ML15261A228
| ML15261A228 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Mcguire, Catawba, McGuire  |
| Issue date: | 03/15/1999 |
| From: | Labarge D NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9903230329 | |
| Download: ML15261A228 (53) | |
Text
Ma 1 15, 1999 LICENSEE:
Duke Energy Corporation FACILITY:
Oconee Nuclear Station, Units 1, 2, and 3
SUBJECT:
SUMMARY
OF THE JANUARY 20, 1999, NRC AND DUKE ENERGY CORPORATION COUNTERPARTS MEETING On January 20, 1999, members of the NRC and Duke Energy Corporation (Duke) staffs met at the Charlotte, North Carolina office of the Duke Energy Corporation to discuss various licensing issues related to the Oconee, McGuire, and Catawba Nuclear Stations. Enclosure 1 is a list of the individuals who attended the meeting and Enclosure 3 is the handout material that was used during the discussions.
The topics discussed are shown in Enclosure 2.
original signed by:
David E. LaBarge, Senior Project Manager Project Directorate 11-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287
Enclosures:
- 1. Attendance List
- 2. Agenda
- 3. Handouts cc w/encls: See next page Distribution:
See next page a
To receive a copy of this document, indicate in the box: "C" = Copy without attachmentlenclosure "E" = Copy with aachmentlenclosure "N" = No co OFFICE PM:
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 15, 1999 LICENSEE:
Duke Energy Corporation FACILITY:
Oconee Nuclear Station, Units 1, 2, and 3
SUBJECT:
SUMMARY
OF THE JANUARY 20, 1999, NRC AND DUKE ENERGY CORPORATION COUNTERPARTS MEETING On January 20, 1999, members of the NRC and Duke Energy Corporation (Duke) staffs met at the Charlotte, North Carolina office of the Duke Energy Corporation to discuss various licensing issues related to the Oconee, McGuire, and Catawba Nuclear Stations. Enclosure 1 is a list of the individuals who attended the meeting and Enclosure 3 is the handout material that was used during the discussions.
The topics discussed are shown in Enclosure 2.
David E. LaBarge, Senior Project Manager Project Directorate 11-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287
Enclosures:
- 1. Attendance List
- 2. Agenda
- 3. Handouts cc w/encls: See next page
Meeting Summary dated Ma r ch 1 5,J 999 HARD COPY Docket File PUBLIC PDII-2 Reading DLaBarge OGC (w/o encl)
ACRS (w/o encl)
E-MAIL S. Collins/J. Zimmerman B. Boger J. Zwolinski H. Berkow C. Hawes T. Martin (e-mail to SLM3)
F. Rinaldi D. Roberts W. Beckner C. Ogle, RII S. Shaeffer P. Tam M. Tschiltz (MDT), edo
Oconee Nuclear Station cc:
Ms. Lisa F. Vaughn Mr. J. E. Burchfield Legal Department (PBO5E)
Compliance Manager Duke Energy Corporation Duke Energy Corporation 422 South Church Street Oconee Nuclear Site Charlotte, North Carolina 28201 -1006 P. 0. Box 1439 Seneca, South Carolina 29679 Anne Cottington, Esquire Winston and Strawn Ms. Karen E. Long 1400 L Street, NW.
Assistant Attorney General Washington, DC 20005 North Carolina Department of Justice Mr. Rick N. Edwards P. 0. Box 629 Framatome Technologies Raleigh, North Carolina 27602 Suite 525 1700 Rockville Pike L. A. Keller Rockville, Maryland 20852-1631 Manager - Nuclear Regulatory Licensing Manager, LIS Duke Energy Corporation NUS Corporation 526 South Church Street 2650 McCormick Drive, 3rd Floor Charlotte, North Carolina 28201-1006 Clearwater, Florida 34619-1035 Mr. Richard M. Fry, Director Senior Resident Inspector Division of Radiation Protection U. S. Nuclear Regulatory North Carolina Department of Commission Environment, Health, and 7812B Rochester Highway Natural Resources Seneca, South Carolina 29672 3825 Barrett Drive Raleigh, North Carolina 27609-7721 Virgil R. Autry, Director Division of Radioactive Waste Management Mr. Steven P. Shaver Bureau of Land and Waste Management Senior Sales Engineer Department of Health and Environmental Westinghouse Electric Company Control 5929 Carnegie Blvd.
2600 Bull Street Suite 500 Columbia, South Carolina 29201-1708 Charlotte, North Carolina 28209 County Supervisor of Oconee County Walhalla, South Carolina 29621 Mr. William R. McCollum, Jr.
Vice President, Oconee Site Duke Energy Corporation P. O. Box 1439 Seneca, SC 29679
Duke Energy Corp. - NRC Counterparts Meeting 1/20/99 Name Affiliation D. LaBarge NRC E. Burchfield Duke Bill Foster Duke, ONS Frank Rinaldi NRC Darrell J. Roberts NRC Scotty L. Bradshaw Duke, CNS Joe M. Davis Duke, NGO Herb Berkow NRC Ken Canady Duke/Nuclear Engineering William Beckner NRC Mike Tuckman Duke Loren Plisco NRC James Fisicaro Duke Chuck Ogle NRC Lee Keller Duke Scott Shaeffer NRC Peter Tam NRC Gary Gilbert Duke/CNS Michael T. Cash Duke/McGuire Lisa Vaughn Duke Brman Dolan Duke/McGuire
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-Page 3
Duke Energy Corporation - NRC Counterparts Meeting JANUARY 20, 1999 AGENDA Time Topic Discussion Leader 9:00 am
Introductions
D. LaBarge, M. Tuckman 9:15 General Duke Status/1999 Direction M. Tuckman 9:35 Engineering Items of Interest, With Emphasis K. Canady on Licensing Actions/Activities (Fuel Transition, Chapter 15 Reanalysis, Mixed Oxide Fuel, Oconee Steam Generator Replacement) 10:00 Station Support Items of Interest, With Emphasis J. Davis on Licensing Actions/Activities 10:05 Nuclear Assessment and Issues Division J. Fisicaro Items Of Interest, With Emphasis on Licensing Actions/Activities 10:15 Ice Condenser TS Improvement Plans R. Lytton/W. Beckner 10:30 Break 10:40 ISTS Conversion Experience, Critique, and W. Beckner, NRR PMs, Recommendations L. Keller 11:00 Discussion on Revised NOED Guidance H. Berkow 11:15 NRC Focus Areas, Organizations and Processes L. Plisco Region II
- Licensee Performance Assessment Program Enforcement Program Changes Noon Lunch 1:00 pm Anticipated Site Submittals for 1999 J. Burchfield, M. Cash, G. Gilbert 1:45 Other Discussion Items:
- Electronic Submittals Program Status D. LaBarge
- Feedback on Revised RAI Process L. Keller
- Other items as appropriate Anyone 3:00 Meeting adjourned '
UCLEAR ENGINEERING K.S.Canady SEVERE ACCIDENT NUCLEAR DESIGN &
CORE MECHANICAL &
ANALYSIS SAFETY ANALYSIS REACTOR SUPPORT NUCLEAR DESIGN FUEL MANAGEMENT T/H ANALYSIS P. M. Abraham G. B. Swindlehurst R. I. Clark R. R, St.Clair R. M. Gribble MECHANICAL CIVIL ELECTRICAL MATERIALS, G.O, LOCAL SYSTEMS & EQUIPMENT STRUCTURAL SYSTEMS & EQUIPMENT METALLUR GY & PIPING INFO. TECHNOLOGY E. E. Hite III D. E. DeMart 1K R. Caraway M. R Robinson S. A. Deskevich
DUKE POWER COMPANY NUCLEAR ENGINEERING MAJOR ORGANIZATIONAL RESPONSIBILITIES SEVERE ACCIDENT ANALYSIS NUCLEAR DESIGN & REACTOR FUEL MANAGEMENT SUPPORTIMNS-CNS Radiological source term analysis for severe e Fuel cycle economic evaluations accidents a Fuel cycle scoping studies e Uranium, enrichment fabrication specification
- Containment performance analysis for severe
- Preliminary fuel cycle design development accidents
- Final fuel cycle design Nuclear fuel/contract negotiation/
- Special reliability study e Operating & RPS limits administration support
- PRA support of maintenance rule
- Startup & operation report e Fuel cycle legislation/litigation support
- ORAM-SENTINEL support
- Safety-related physics parameters e Fuel cost allocation, fuel amortization & fuel
- Reliability based tech specs a Power distribution monitoring budgeting
- Reliability based cost benefit analysis / decision e Development of improved analysis software &
e Nuclear fuel trans. regulations analysis support micro computing e New & spent fuel trans.
- Safety system unavailability monitoring a Spent fuel storage technology
- Nuclear System Events support e Long-term SF storage strategy
- Probabilistic safety analysis planning/implementation
- Equipment failure rates e Spent fuel inventory
- Administration of NWPA waste contract
- Crisis management scenarios & technical
- Accountability of system-wide SNM support SAFETY ANALYSIS NUCLEAR DESIGN/ONS CORE MECH. & T ANALYSIS 9 Simulations of plant transients & accidents
- Fuel cycle scoping studies a Fuel assembly design
- Reload core safety analysis
- Preliminary fuel cycle design
- Final fuel cycle design e Fuel fabrication problem resolution (design tech spec setpoints
- Maneuvering analysis consequences)
Simulations of the containment response to pipe
- Physics operating report
- Radiochemistry analyses ruptures
- Safety related physics parameters o Fuel burnup limits Hydraulic simulations of ECCS (MNS/CNS)
- Incore detector monitoring & mgmt.
e Fuel reliability goals/action levels UFSAR Chapter 15 analysis
- Development of improved analysis software &
- Fuel PIE programs/inspection stations Emergency procedure guidelines (ONS) micro computing
- Transient validation of plant simulators f
Core thermal hydraulics Crisis management technical support e Fuel assembly flow tests/hydraulic issues Simulation of fuel pin transients
- Fuel site problem resolution
- LOCA analysis vendor interface
MECHANICAL SYSTEMS & EQUIPMENT ELECTRICAL SYSTEMS & EQUIPMENT G.O. LOCAL INFORMATION TECH.
- Appendix J
- Cable Expertise
- Desktop Support
- Maintenance Rule
- Electrical Equipment Aging Issues
--SPOC Interface
- EPIX / FATS
- Electronics
--Hardware/Software Install/Setup
- Thermal Cycle Performance / Secondary
- Equipment Qualification (EQ)
--Troubleshooting/Problem-Solving
- Turbines / Generators
- Grounding
- Application Support
- Diesels / Generators
--Design Specification Development
- AP600 / ALWR Review
- License Renewal Support
--Vendor Interface
- P & V IST / Retest
- Power Systems (AC, 3-phase)
--Installation and Testing
- Raw Water Support / HX Thermal Perf.
--Voltage Studies
--Nuclear Site Interface Analysis
--Fault Duty Analysis
- Technology Project Mgmnt & Consult.
Pumps
--Protective Device Coordination
- NSD-800 / SDQA Support & Consult.
- Motors
--Dynamic Analysis (Motor Starting)
- Performa Development & Support
- Ice Condenser
--Bus Transfer Analysis
- Process Systems Support
- Protective Relaying
--Nuclear Site OAC Applications
- Switchyard Oversight Committee
--Nuclear Site Plant Security System
- Generator Electrical Support
--Plant Information (PI) System
--Application Support CIVIL STRUCTURAL MATERIALS, METALLURGY, & PIPING
- Fire Protection
- Piping/Code Support
- Metallurgy-Materials Support
- Containment / ISI
- ISI/NDE Support.
- Tanks & Pressure Vsls.
- Materials/Program Leadership
- Seismic Qualification
--SIIM Program
- General Civil Support
--Welding Program
- Valves
--Erosion-Corrosion Program
--RV Embrittlement
--Raw Water Program
--Reactor Vessel Internals
- Life Cycle/Aging Management
- Licensing Renewal Support
FUEL ASSEMBLY DESIGN TRANSITIONS Oconee Oconee 1 Cycle 20 (startup 1/1/200.1) will be the first implementrfiotiib the FCF Mk-B 11 fuel assembly design. The main new design features of the Mk-B 11 are mixing vane grids, M5 cladding, BWU CHF correlation, and 0.416 (vs. 0.430) inch OD.
Licensing Tasks
- NRC approval of FCF M5 cladding topical report (BAW-10227 - 9/97). We understand that the NRC review will be completed by 3/99.
- NRC review of Revision I to DPC-NE-3005-P (UFSAR Ch.15 non-LOCA accident analysis methodology) necessary for 01C20 startup.
- Technical specification revisions related to fuel design description (M5 cladding), BWU CHF correlation.
- Exemption to 10 CFR 50.46 for M5 cladding (future Duke submittal).
- Reload submittal will be made with 6 month NRC review window.
FUEL ASSEMBLY DESIGN TRANSITIONS McGuire / Catawba Catawba 2 Cycle 11 (startup 5/2000) will be the first implementation of the Westinghouse RFA fuel assembly design. The main new design features of the RFA will be IFM grids and the WRB-2M CHF correlation.
Licensing Tasks Duke topical report DPC-NE-2009, "Westinghouse Fuel Transition Report" submitted 7/22/98. Duke is finalizing responses to the NRC RAI letter and expects approval in the near future.
- Westinghouse is performing new LOCA analyses within their current approved EMs
- The C2C1 1 reload will be implemented under 50.59.
IMPLEMENTA TION OF NEW OCONEE UFSAR CH.15 METHODOLOGY'
- Topical report DPC-NE-3005-P, "UFSAR Chapter 15 Traniehirial-is Methodology" was submitted on 7/30/97. These methods replace the 1970s vintage B&W non-LOCA accident analyses with modem codes and methods.
- Revision 1 will be submitted by 2/1 to address the SER conditions. Do not consider the NRC review of this submittal to be difficult or lengthy.
- Need NRC approval of Revision 1 to support 02C 18 reload (startup date 1/2000).
- 02C18 reload report will include related T.S. revisions and UFSAR Ch.15 reanalyses. Need NRC review of reload submittal by 12/1/99.
D UKE PRO CESS FOR TOPICAL REPOR T REVISIONS Revisions to Duke topical reports are necessary to improve ni eti-6 W
issues, and to keep the document up-to-date.
For significant revisions submittal for NRC review is necessary.
No clear regulatory guidance as to whether minor revisions can be made without NRC review, for example via the 50.59 process.
Duke letter dated April 14, 1998 describes a proposed process for managing topical report revisions. This is under review at the Reactor Systems Branch.
The process requires submittal of topical report revisions only if either of the following criteria are met:
New computer code or models New modeling approach with less conservative Revisions that are error corrections, modeling approaches that produce more conservative results, and minor code revisions, can be revised internally via the 50.59 process.
A process for updating the T.S. list of COLR topical reports is also proposed.
MOX Fuel Project.-,
Convert 33 mT of surplus Pu into MOX fuel.
Note -- a contract from DOE has not been awarded. Information on these slides is based on a potential award to the Duke Cogema Stone & Webster LLC team in the near future. DOE may or may not make this award.
Key Elements of the Base Contract Qualify Analytical Methods (Duke/Va Power/FCF)
Fabricate and irradiate two LTAs in M2C16 (Duke/Cogema/FCF)
Design MOX Fuel Fabrication Facility (MFFF) (Duke/Cogema/S&W)
Design and license fresh MOX shipping container (Cogema)
Design plant modifications for batch irradiation (Duke/Va Power)
MOX Fuel Project-Irradiation Services Propose meeting with NRC to discuss the MOX Project in April 1999.
NRC Submittals for Irradiation Activities Work Item Submittal Date SER Need Date Base Contract MOX Fuel Methodology Reports August 2001 February 2003 COPERNIC for MOX CASMO-4/SIMULATE-MOX LOCA License Amendment Request(LAR) for August 2001 February 2003 LTAs Option 1 Topical Reports to support batch irradiation January 2004 January 2006 LAR for batch irradiation January 2004 January 2006
MOX Fuel Fabrication,Fa ilit
- Develop detailed licensing and permitting plan 5/99
- Submit Licensing Application 5/00
- NRC Review of Licensing Application 11/01 Atomic Safety and Licensing Board Decision 11/02
- Receive Permit to Construct and License to Operate 11/02
Duke Topicals Dynamic Rod Worth Topical Same technique as Westinghouse DRWM Uses CASMO-3/SIMULATE-3k For McGuire and Catawba Submit April 1, 1999
- Request SER by October 1, 1999 Conditional Elimination of EOL MTC Measurement Similar technique as Westinghouse WCAP-13749 Uses CASMO-3/SIMULATE-3P codes For McGuire and Catawba Submit December 15, 1999 Request SER by May 15, 2000
Technical Specification Amendments to be submitted in 1999 Station Specification Reason Submittal Date MNS P-10 Reset Reliability due to April 99 Range Narrow Range Aux Feedwater Non-Conservative May 99 Swap Setpoint Specification Spent Fuel Boraflex Degradation July 99 Storage Management DNB Flow Non-Conservative March 99 Specification (MNS/CNS)
Extended Outage Management July 99 D/G AOT Risk Informed (MNS/CNS)
RPS/EFS Clarify Nominal Set January 99 Setpoints Point Meaning (MNS/CNS)
Technical Specification Amendments to be submitted in 1999 Station Specification Reason Submittal Date CNS Spent Fuel Clarify Surveillance January 99 Ventilation Reactor Prot.
Recover Operating January 99 Response Time Reactor Bldg.
Outage Scheduling February 99 Surveillance RPS/EFS Clarify Nominal Set January 99 Setpoints Point Meaning (MNS/CNS)
DNB Flow Non-Conservative March 99 Specification (MNS/CNS)
Extended Outage Management July 99 D/G AOT Risk Informed (MNS/CNS)
RCS Specific Non-Conservative July 99 Activity
Technical Specification Amendments to be submitted in 1999 Station Specification Reason Submittal Date ONS P/T limits RCP wear March 99 for 2/0 RCP operation MSLB design EFW runout protection March 99 basis change and SG tube loads Emergency Outage Scheduling March 99 Hatch GL 96-06 Establish new TS April 99 RBCU for isolating RBCUs waterhammer Positive Non-Conservative April 99 MTC Specification Control Room Address CR habitability TBD Habitability non-conformances 02C18 Reload New USFAR March 99 Chapter 15
NUCLEAR ASSESSMENTS & ISSUES DIVISION ORGANIZATION CHART James J. Fisicaro Manager NUCLE4R REGULATORY REGULATORY NSRBAND BUSINESS AUDITS/OPERATIONAL AND INDUSTRY OPERATING SERVICES ASSESSMENTS A FeIRS E PERIENCE Terry Dimmery, Manager Rich Freudenberger, Manager Le KelTler, Mannar Bill Pitesa. Manager
ICE CONDENSER MINIGROUP Ice Condenser Technical Specification Rewrite Project NRC Briefing Duke Power Company January 20, 1999
ICMG Members
- Duke Power Company McGuire Units 1&2, Catawba Units 1&2
- Tennessee Valley Authority Sequoyah Units 1&2, Watts Bar Unit 1
- American Electric Power D.C. Cook Units 1&2
- Westinghouse Electric Corporation
Ice Condenser Technical Specification Rewrite Project ICMG Background
- ICMG formed in 1994 to facilitate ice condenser technical information exchange (domestic utilities only)
- Westinghouse (OEM) agreed to be project manager for common issue resolution
- Provides tie to WOG for official business
- Gives I/C industry a platform from which to operate on issues of common interest
- ICMG team makeup is technical (primarily Maintenance and Engineering)
- Issues visited are varied
- Duke is current Chair 3
Ice Condenser Technical Specification Rewrite Project Project Process
- ICMG has met formally three times since last fall, beginning with Ice Condenser Symposium in Chattanooga
- Effort since that time devoted to reviewing the I/C Technical Specifications for improvements In-house I/C maintenance and operation experience Results of recent NRC I/C inspections I/C industry events
- Licensing groups at each utility involved to assist with wording and interpretation
- Agreement reached between ICMG and Licensing on individual TS revisions
- Industry submittal of each revised IIC TS will occur through the NEI TS Task Force 4
Ice Condenser Technical Specification Rewrite Project Current Status ICMG and Licensing counterparts assembling a matrix of ice condenser issues Primarily TS-related, but includes other issues as well Serves as the governing document for priorities, schedule, individual utility requirements and identified NRC concerns Provides platform for inter-utility discourse on important I/C issues
- First two I/C TSs being finalized Flow Channel Blockage Boron Sampling Goal is to submit to NEI TSTF in first quarter 1999 Next TS priorities Ice Bed Weight Intermediate Deck Door Opening Force 5
Ice Condenser Technical Specification Rewrite Project Project Notes
- Ice Condenser TS Rewrite effort may not change all I/C TSs, but all will be reviewed
- Issues/concerns deemed outside of TS arena will be technically justified
- ICMG agreed that due to prior utility commitments (D.C. Cook, Watts Bar) I/C TS submittals made in parallel to current effort would not be recalled 6
Ice Condenser Technical Specification Rewrite Project Questions 7
Duke Energy Corp ITS Conversion Experience January 20, 1999
What Went Well
- Open Communications
- Face to Face Meetings
- Number of Questions
- Electronic Format
Open Communications
- Lead Technical Reviewers
- Project Managers
- 'Conference Calls
Face to Face Meetings
- A//owed Interface with Individual Reviewer
- Effective Resolution of Complicated Issues
- Facilitated Timely Completion of Open Items
Number of Questions
- Less than other utilities
- DEC able to answer many on first response
Electronic Format
- Efficient resolution of ONS questions via e-mail
- CNS/MNS format allowed individual response for each question
- CNS/MNS facilitated formal response
Suggestions for Process Improve-ment
- Delay of RAIs for CNS/MNS
- One on One Meetings Prior to RAI
- Bases Only RAIs for CNS/MNS
- Beyond Scope Items for ONS
Delay of RAls for CNS/MNS 1st RAI received 8 months after submittal
- Additional RAIs over period of next 6 months Created significant delay
- Expected first RAI in 11/97 Significant cost to utility
- Resources for this project extended
One on One Meetings Prior to RAI
- Meetings early in review process
- Could have avoided some questions
- Discussion of some issues could result in agreement on our response
- Eliminate one step in review process
Bases Only RAls for CNS/MNS Significant Number of RAls covered Bases Only Bases questions could have been avoided in meetings prior to RAI Level of justification for Bases 10
Beyond Scope Items for ONS
- Changes can cause delays
- Questions concerning existing design and licensing basis
- Several iterations of wording changes
- Often generic in nature 11
Summary of ITS Review
- After initial delays, review process was smooth and timely
- High Cost for DEC
- High Level of Unpredictability in Schedule
- DEC Anticipates Some Positives
- Still too early in process to realize 12
NOTICES OF ENFORCEMENT DISCRETION REVISED PROCESS AND GUIDANCE Contacts Herb Berkow, 415 -1485 L. Raghavan, 415 -1471
NOED POLICY BACKGROUND AND CHRONOLOGY 7/85 - ENFORCEMENT GUIDANCE MEMO TEMPORARY WAIVERS OF COMPLIANCE 3/93 - 10 CFR 2, APPENDIX C, SECTION VIII.C (NOW NU'REG-1600, SECTION VII c),
NOED ADDED TO THE POLICY 8/ 93-STAFF IMPLEMENTATION GUIDANCE MANUAL CHAPTER PART 9900 o.5 -9/94 - CONGRESSIONAL, STAFF AND OIG REVIEWS 1/95 - MANUAL CHAPTER 9900 -REVISED GUIDANCE 11/95' - REVISED GUIDANCE -PART 9900 7/98 -
OIG FOLLOW-UP REVIEW OF NOED PROCESS 12/98 - REVISED STAFF GUIDANCE
NOED Guidance Part 9900 has been revised
- Revision as a result of:
- Policy changes - COMEXM-98-004, dated July 28, 1998
- OIG audit findings and recommendations OIG/98A-06, July 30, 1998 Utility/NRC Interface Licensing Workshop, July 20-21, 1998
- Staff experience with the current guidance.
.Significant changes to the NOED guidance are:
NOED involving severe weather or other natural events Process change Documentation changes Tracking
NOED -invol ving severe weather or
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Process changes
- Teleconferences / Discussions Should be made through the NRC headquarter's Emergency Operations Center recorded telephone line: Telephone No. (301) 415-0550 This provides a e
ication of its consistency with t icese 'sf ow-up written request.
Criteria Changes Reiterates that NOED process is for temporary nonconformances from the license conditions and TS only Not appropriate for any USQs Not appropriate for non-compliance with__
regulations or codes
Documentation and Concurrences Licensees are no longer required to state whether:
prior adoption of TS enhancement initiatives (GL 87-09, Line Item Improvements or the Improved Standard TS) would have obviated the need for the NOED the noncompliance involves a USQ.
The NOED Letter Should Identify Name and title, the key staff participants in the NOED evaluation and approval when the licensee's follow-up license amendment request will be or was submitted.
Concurrence PD should obtain concurrence at technical branch chief level instead of the division director level.
Follow-up TS amendment should be issued:
As an exigent amendment.
Within 4 weeks Any delay beyond the 4 weeks should be justified by the responsible PM in a memorandum to the Associate Director for Projects.
Distribution is expanded: PM should send an electronic copy of the follow-up TS amendment letter to the email address NOED.
Tracking cTracking Each office, region or NRR, is responsible for:
tracking the NOEDs it issues entering the required data into its tracking system.
On a semi-annual basis, the technical assistant for NRR, DRP-III, will request the regions to provide updated database information r6garding follow-up actions to previously issued NOEDs.
For all NOEDs (regional or NRR) Region to open an Unresolved Item (URI).
This will facilitate:
tracking
-I_-_
verification and resolution activities documentation and closure of inspection enforcement action determinations
Road Map An NOED checklist is provided in Attachment D This is only an aid to assure adherence to this guidance.
It's use is discretionary It is a companion, not a substitute, for the detailed guidance.
NOTES ON COMPUTER SYSTEM MODIFICATION -ADAMS Definition of ADAMS Agencywide Documents Access and Management System The policies, processes, and software tools to manage unclassified, official program and administrative records of lasting business value to the NRC in an electronic rather than paper-based environment.
FileNet Software Process Single entry point for receipt of mail. Input can be by any software, paper input will be scanned into system.
Distribution via email Document generation, assign action, track, and obtain concurrences Search and retrieval Filing of outgoing records Public access via Internet d'5.-l~v~
L LC Schedule as I know it now March 1999 Pilot process and procedures developed May 1999 Administrative Letter explaining process due October 1999 Final processes and procedures developed for agency-wide implementation. Administrative Rule published to allow for electronic submittals.
Licensees no longer need to submit hard or multiple copies Living Documents Documents that must be maintained up-to-date in accordance with agency policies and requirements and for which there is a requirement to update by replacing small segments at a time (traditionally, page, pen and ink changes)
Annual UFSAR submittals TS Changes, Reactor Licenses Emergency Plans, EPIPs
Fire Protection Plans COLR RPS/LOP Reactor Program System/Licensing and Other Planning Will provide an integrated methodology for planning, scheduling, project managing, reports and analyzing most of the functions performed by NRR Headquarters staff.
Certain functions also available to Regions.
Implementation scheduled for September 1999.
Replaces WISP.
LOP Modules: Inspection Planning, Inspection Reporting being used. Will also be used to generate a number of internal reports (approx. 27 at last count).
SYBASE database.