ML15244A796
| ML15244A796 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Oconee, Arkansas Nuclear, Crystal River, Crane  |
| Issue date: | 02/04/1993 |
| From: | Hiltz T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9302160077 | |
| Download: ML15244A796 (29) | |
Text
0 0 B;jREGU, UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 February 4, 1993 Docket Nos.:
50-269, 50-270 50-287, 50-289 50-302, 50-313 50-346 ORGANIZATION: Babcock and Wilcox Owners Group (BWOG)
PROJECT:
BWOG Generic License Renewal Program
SUBJECT:
SUMMARY
OF MEETING BETWEEN U.S. NUCLEAR REGULATORY COMMISSION STAFF AND BWOG REPRESENTATIVES TO DISCUSS THE BWOG GENERIC LICENSE RENEWAL PROGRAM (JANUARY 12, 1993)
On January 12, 1993, representatives of the U. S. Nuclear Regulatory Commission (NRC) and representatives from the Babcock and Wilcox Owners Group (BWOG) Generic License Renewal Program met in Clearwater Beach, Florida.
Meeting participants discussed issues relating to the implementation of the License Renewal Rule (10 CFR Part 54) and aspects of the BWOG's proposed program to resolve license renewal issues on a generic basis.
contains a list of meeting attendees. BWOG representatives indicated that they were not representing the nuclear utility industry and that the information presented at the meeting should only be associated with the BWOG and the BWOG Generic License Renewal Program. Enclosure 2 contains copies of presentation material discussed at the meeting.
The NRC staff outlined the recent senior management review efforts which focused on the effective implementation of 10 CFR Part 54. The staff indicated that it was considering several issues associated with the implementation of 10 CFR Part 54 including:
- Credit for effective programs;
- Reliance on and interrelationships with technical specifications, regulatory requirements, and the Maintenance Rule (10 CFR 50.65);
- The need to revise either the License Renewal Rule or the Maintenance Rule; and
- Methodologies for determining systems, structures, and components (SSC) that are important to license renewal and that have degradation unique to license renewal.
BWOG representatives discussed their Program Plan for the Generic License Renewal Program. The BWOG Generic License Renewal Program is designed to streamline the license renewal process for B&W plants, in part, through preparation, and subsequent NRC review, of documents that address license renewal issues applicable to all B&W plants. BWOG representatives indicated that the plan is essentially complete, is considered a 'living' document, and will be updated approximately annually. The Program Plan organization' structure is complete and position staffing is in progress.
(6 170072
0I
-2 According to BWOG representatives, they believe that they can implement the License Renewal Rule without a rule change if the staff and the Commission can make favorable determinations and interpretations regarding implementation of the rule.
The BWOG Generic License Renewal Program individual plant assessment process and philosophy was discussed. A flowchart which describes the major decision points in their proposed approach is enclosed (part of Enclosure 2).
More detailed discussions were provided on the BWOG's proposed approach to screen systems, structures, and components for the license renewal process. The staff expressed particular interest in the BWOG approach for: 1) deter mining SSCs that could have age-related degradation unique to license renewal;
- 2) determining whether a SSC was enveloped by an effective program;
- 3) utilizing risk significance in the screening methodology; and, 4) capturing all previous current licensing basis commitments.
BWOG representatives and the staff discussed the development and review process for approximately 15 technical reports which are scheduled to be submitted to the NRC staff for its review in 1993.
These technical reports should contain generically relevant information dealing with component evaluations, screening methodologies and their application, and technical reference material.
The BWOG goal is to work closely with the staff-to help ensure issuance of a final safety evaluation report (FSER) 7 months from the date the report is submitted to the NRC for its review.
The staff noted that the BWOG proposed schedule was optimistic but potentially achievable for some reports. The success of this schedule would depend largely on the scope and content of the technical report and the ability of the staff and BWOG representatives to identify and resolve issues at the draft safety evaluation report stage (4 months after submittal of the report to the NRC).
The staff requested that BWOG representatives identify those technical reports for which it considered the timely completion (7 months) of the NRC review critical for maintaining its generic license renewal program schedule.
The proposed format of the BWOG technical report was discussed. BWOG representatives proposed that a typical technical report would consist of a 1-page abstract, 5-10 pages of 'regulatory report', and then the remainder of the report (mostly proprietary technical information).
BWOG representa tives proposed that the proprietary technical information be maintained in the B&W offices in Rockville, Maryland, and stated that it would be available to the NRC staff for review.
The staff commented on several aspects of the proposed approach for submitting the technical report to the NRC.
First, it would be unlikely that the staff could draw meaningful conclusions on the 5-10 pages of non-proprietary material.
Second, the material on which the staff will base its safety determination must be formally submitted on the docket (including proprietary material).
-3 Third, inefficiencies associated with reviewing a technical report which is submitted to the NRC in segments may make the aggressive review schedule unrealistic. Finally, the staff noted that a report which includes limited technical information and lists many references can severely hamper the staff's review. The staff will not endorse entire reference lists and may require BWOG representatives to provide selected references for its review.
The staff strongly recommended that BWOG representatives consider, to the extent practical, making each technical report a 'stand-alone' type document, limiting the number of references, and minimizing the amount of proprietary material.
The staff will continue to interact with BWOG representatives to help ensure that the use of proprietary material is appropriate.
The staff provided a brief overview of the ongoing efforts on the proposed rulemaking to amend the NRC's environmental protection requirements, 10 CFR Part 51, for license renewal.
The staff is evaluating and preparing responses to the large number of public comments on the proposed amendments to 10 CFR Part 51, which was published in the Federal Register in September 1992. The majority of the staff's efforts have been to respond to comments received from the Council on Environmental Quality (CEQ, and Executive Office to the President) and from the Environmental Protection Agency (EPA).
CEQ and EPA would like to see the NRC provide the public greater opportunity to be involved with the environmental issues at the time of a site-specific license renewal application. The staff is considering several options in resolving CEQ's and EPA's concerns, including the possibility of 1) preparing site specific environmental impact statements (EIS) for public comment instead of an environmental assessment, 2) allowing the public to comment on all environmental issues, including the Category 2 and 3 issues contained in the generic Category 2 and 3 issues contained in the site-specific EIS, and 3) performing a cumulative impact assessment in the site-specific EIS instead of the conditional cost-benefit analysis in the GEIS. The staff emphasized that these were some of the preliminary options the staff was considering and that they were subject to change.
The staff plans to meet with BWOG representatives at least monthly beginning in March 1993 to facilitate resolution of issues associated with the BWOG Generic License Renewal Program.
Thomas G. Hiltz, Senior Project Manager License Renewal And Environmental Review Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of Nuclear Reactor Regulation
Enclosures:
- 1. Meeting Attendees List
- 2. Presentation Material cc: See next page DISTRIBUTION:
See Attched Sheet PDLR:LA PDW M PDLR.
LLutherA TH FAkstu ewicz 2/.2/93 2/V93 2/g/9 DOCUMENT NAME: HILTZ MEETING
SUMMARY
Crystal River Unit No.3 Florida Power Corporation Generating Plant cc:
Mr. A. H. Stephens Mr. Robert G. Nave, Director General Counsel Emergency Management Florida Power Corporation Department of Community Affairs MAC-ASD 2740 Centerview Drive P. 0. Box 14042 Tallahassee, Florida 32399-2100 St. Petersburg, Florida 33733 Mr. Bruce J. Hickle, Director Chairman Nuclear Plant Operations Board of County Commissioners Florida Power Corporation Citrus County P. 0. Box 219-NA-2C 110 North Apopka Avenue Crystal River, Florida 34423-0219 Inverness, Florida 32650 Mr. Robert B. Borsum Mr. Rolf C. Widell, Director B&W Nuclear Technologies Nuclear Operations Site Support 1700 Rockville Pike, Suite 525 Florida Power Corporation Rockville, Maryland 20852 P. 0. Box 219-NA-21 Crystal River, Florida 34423-0219 Regional Administrator, Region II U. S. Nuclear Regulatory Commission Mr. Percy M. Beard, Sr.
101 Marietta Street N.W., Suite 2900 Vice President Atlanta, Georgia 30323 Nuclear Operations ATTN: -Manager, Nuclear Operations Mr. Jacob Daniel Nash Licensing Office of Radiation Control P.O. Box 219-NA-21 Department of Health and Crystal River, Florida 34423-0219 Rehabilitative Services 1317 Winewood Blvd.
Senior Resident Inspector Tallahassee, Florida 32399-0700 Crystal River Unit 3 U.S. Nuclear Regulatory Administrator Commission Department of Environmental Regulation 6745 N. Tallahassee Road Power Plant Siting Section Crystal River, Florida 34428 State of Florida 2600 Blair Stone Road Mr. Gary Bolt Tallahaseee, Florida 32301 Vice President, Nuclear Production Attorney General Florida Power Corporation Department of Legal Affairs P.O. Box 219-SA-2C The Capitol Crystal River, Florida 34423-0219 Tallahassee, Florida 32304
Entergy Operations, Inc.
Arkansas Nuclear One, Unit 1 cc:
Mr. Donald C. Hintz, President Mr. John R. McGaha and Chief Executive Officer Vice President, Operations Support Entergy Operations, Inc.
Entergy Operations, Inc.
P. 0. Box 31995 P. 0. Box 31995 Jackson, Mississippi 39286 Jackson, Mississippi 39286 Mr. Charles B. Brinkman, Manager Mr. Robert B. McGehee Washington Nuclear Operations Wise, Carter, Child & Caraway ABB Combustion Engineering P. 0. Box 651 Nuclear Power Jackson, Mississippi 39286 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Mr. James J. Fisicaro Director, Licensing Mr. Nicholas S. Reynolds Entergy Operations, Inc.
Winston & Strawn Route 3, Box 137G 1400 L Street, N.W.
Russellville, Arkansas 72801 Washington, D.C. 20005-3502 Admiral Kinnaird R. McKee, USN (Ret)
Mr. Robert B. Borsum 214 South Morris Street Licensing Representative Oxford,.Maryland 21654 B&W Nuclear Technologies 1700 Rockville Pike, Suite 525 Mr. Jerry W. Yelverton Rockville, Maryland 20852 Vice President, Operations ANO Entergy Operations, Inc.
Senior Resident Inspector Route 3 Box 137G U.S. Nuclear Regulatory Commission Russellville, Arkansas 72801 1 Nuclear Plant Road Russellville, Arkansas 72801 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Honorable Joe W. Phillips County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 Ms. Greta Dicus, Director Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street Little Rock, Arkansas 72205-3867
Mr. Donald C. Shelton Davis-Besse Nuclear Power Station Toledo Edison Company Unit No. 1 cc:
Mary E. O'Reilly Centerior Energy Corporation Radiological Health Program 300 Madison Avenue Ohio Department of Health Toledo, Ohio 43652 Post Office Box 118 Columbus, Ohio 43266-0149 Mr. Robert W. Schrauder Attorney General Manager, Nuclear Licensing Department of Attorney Toledo Edison Company General 300 Madison Avenue 30 East Broad Street Toledo, Ohio 43652 Columbus, Ohio 43215 Mr. James W. Harris, Director Gerald Charnoff, Esq.
Division of Power Generation Shaw, Pittman, Potts Ohio Department of Industrial Regulations and Trowbridge P. 0. Box 825 2300 N Street, N.W.
Columbus, Ohio 43216 Washington, D.C.
20037 Regional Administrator, Region III Ohio Environmental Protection Agency U.S. Nuclear Regulatory Commission DERR--Compliance Unit 799 Roosevelt Road ATTN: Zack A. Clayton Glen Ellyn, Illinois 60137 P. 0. Box 1049 Columbus, Ohio 43266-0149 Mr. Robert B. Borsum Babcock & Wilcox President, Board of Ottawa Nuclear Power Generation Division County Commissioners 1700 Rockville Pike, Suite 525 Port Clinton, Ohio 43452 Rockville, MD 20852 Resident Inspector State of Ohio U. S. Nuclear Regulatory Commission Public Utilities Commission 5503 N. State Route 2 180 East Broad Street Oak Harbor, Ohio 43449 Columbus, Ohio 43266-0573 Mr. Murray R. Edelman Mr. James R. Williams Executive Vice President -
State Liaison to the NRC Power Generation Adjutant General's Department Centerior Service Company Office of Emergency Management Agency 6200 Oak Tree Boulevard 2825 West Granville Road Independence, Ohio 44101 Columbus, Ohio 43235-2712 Mr. Donald C. Shelton Vice President, Nuclear -
Davis-Besse Centerior Service Company c/o Toledo Edison Company 300 Madison Avenue Toledo, Ohio 43652
Mr. T. Gary Broughton Three Mile Island Nuclear Station, GPU Nuclear Corporation Unit No. 1 cc:
Michael Ross Francis I. Young O&M Director, TMI-1 Senior Resident Inspector (TMI-1)
GPU Nuclear Corporation U.S. Nuclear Regulatory Commission Post Office Box 480 Post Office Box 311 Middletown, Pennsylvania 17057 Middletown, Pennsylvania 17057 Michael Laggart Regional Administrator, Region I Manager, Licensing U.S. Nuclear Regulatory Commission GPU Nuclear Corporation 475 Allendale Road 100 Interpace Parkway King of Prussia, Pennsylvania 19406 Parsippany, New Jersey 07054 Robert B. Borsum Robert E. Rogan B&W Nuclear Technologies TMI Licensing Director Suite 525 GPU Nuclear Corporation 1700 Rockville Pike Post Office Box 480 Rockville, Maryland 20852 Middletown, Pennsylvania 17057 Ernest L. Blake, Jr., Esquire William Dornsife, Acting Director Shaw, Pittman, Potts & Trowbridge Bureauof Radiation Protection 2300 N Street, NW.
Pennsylvania Department of Washington, DC 20037 Environmental Resources Post Office Box 2063 Chairman Harrisburg, Pennsylvania 17120 Board of County Commissioners of Dauphin County Dauphin County Courthouse Harrisburg, Pennsylvania 17120 Chai rman Board of Supervisors of Londonderry Township R.D. #1, Geyers Church Road Middletown, Pennsylvania 17057 Mr. T. Gary Broughton, Vice President and Director -
TMI -
1 GPU Nuclear Corporation Post Office Box 480 Middletown, Pennsylvania 17057
Mr. J. W. Hampton Duke Power Company Oconee Nuclear Station cc:
Mr. A. V. Carr, Esquire Mr. M. E. Patrick Duke Power Company Compliance 422 South Church Street Duke Power Company Charlotte, North Carolina 28242-0001 Oconee Nuclear Site P. 0. Box 1439 J. Michael McGarry, III, Esquire Seneca, South Carolina 29679 Winston and Strawn 1400 L Street, NW.
Mr. Alan R. Herdt, Chief Washington, DC 20005 Project Branch #3 U. S. Nuclear Regulatory Commission Mr. Robert B. Borsum 101 Marietta Street, NW. Suite 2900 Babcock & Wilcox Atlanta, Georgia 30323 Nuclear Power Division Suite 525 Ms. Karen E. Long 1700 Rockville Pike Assistant Attorney General Rockville, Maryland 20852 North Carolina Department of Justice Manager, LIS P. 0. Box 629 NUS Corporation Raleigh, North Carolina 27602 2650 McCormick Drive, 3rd Floor Clearwater, Florida 34619-1035 Mr. G. A. Copp Licensing -
ECO50 Senior Resident Inspector Duke Power Company U. S. Nuclear Regulatory Commission P. 0. Box 1006 Route 2, Box 610 Charlotte, North Carolina 28201-1006 Seneca, South Carolina 29678 Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, NW. Suite 2900 Atlanta, Georgia 30323 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 Office of Intergovernmental Relations 116 West Jones Street Raleigh, North Carolina 27603 County Supervisor of Oconee County Walhalla, South Carolina 29621
DISTRIBUTION:
Central File NRC PDR PDLR R/F TMurley/FMiraglia, 12G18 WTravers, 11H21 FAkstulewicz, 11F23 SNewberry, 11F23 THiltz, 11F23 LLuther, 11F23 OGC EJordan, MNBB3701 ACRS (10)
NRC Participants
0 0
LICENSE RENEWAL MEETING WITH B&W OWNERS GROUP GENERIC LICENSE RENEWAL INITIATIVE JANUARY 12, 1993 ATTENDANCE LIST NAME TITLE & AFFILIATION Steven A. Reynolds Technical Assistant, ADAR:NRC Scott Newberry Director:PDLR:NRR Bill Gray BWNT -
Program Manager Tom Hiltz Sr. Project Manager, PDLR:NRC Fred Burke Manager, Plant Life Managment, BWNT Paul Shemanski Sr. Electrical Engineer, PDLR:NRC Bob Gill BWG GLRP Bill Travers DADAR:NRR:NRC Deb Staudinger B&WOG GLRP Bob Borsum BWNT -
Licensing Mark Rinckel BWNT -Project Engineer Nigel Goulding BWNT -
Systems Engineer William O'Connor Toledo Edison Co., Project Engineer John R. Concklin BWNT Tim Stack BWNT Donald Fultonberg GPU Nuclear Project Engineer Barth W. Doroshuk BGE/Calvert Cliffs Gregory D. Robison Duke Power, GLRP Project Engineer Doug Walters Sr. Project Manager, NUMARC Vincent R. Roppel Florida Power Corp. Project Engineer Tony L. McConnell Program Director, B&WOG GLRP Daniel W. Fouts Entergy Operations, Inc., Project Engineer ENCLOSURE 1
INTRODUCTION o
OVERALL DIRECTION o DETAILED APPROACH TO SYSTEM SCREENING (FLOW CHART) o SCREENING BASES DOCUMENTS o
DELIVERABLES o
SYSTEM SCREENING COMPLETED THROUGH ASSEMBLING SCREENING BASES DOCUMENTS o
SUMMARY
ENCLOSURE 2
Overview of IPA Process Step 1 Step 2 Step 3 Step 4 Categorize Identify SSCs Perform Aging Prepare SSCs as Commodities
& Effective Technical that are or Individual Program Reports ITLR Components &
Evaluations Structures Task 2.2.1 Task 2.2.4 Task 2.2.5 Task 2.2.7 2.2.2 2.2.6 2.2.3 54.21 (a) (1) 54.21 (a) (3) 54.21 (a) (4) 54.21 (a) (2) 54.21 (a) (5) 54.21 (a) (6)
OVERALL DIRECTION OF SYSTEM SCREENING PROCESS o IDENTIFY THE SSC's IMPORTANT TO LICENSE RENEWAL SSC's RELATED TO DESIGN BASIS EVENTS NON-SAFETY SSC's SSC's RELATED TO APPENDIX R, EQ, ATWS, SBO AND PTS EVALUATIONS SSC's RELATED TO TECH SPEC LCO's g
o FIGURE 1
BWOG GLRP PROCESS FLOWCHART ALL SSCs (Systems Structures &
Components)
Is SSC No Document ITLR ?
Basis Yes isto ITLR SSCs Including Bases Or Component)
'Basis ITLR ?
List OfmI SCs (Structures &
Components)
Including Basis (page two)
BWOG GLRP PROCESS FLOWCHART (page two)
Categorize
- Component
- Structure
- Commodity Identify AD ARDM Applicable Reference Aging Mechanisms Report Are Document Current Yes Basis Programs Managing
- Maintenance Rule Aging Mechanisms
-.1$s For > 60?-
Tech Specs No Is Program No Document cNeeded Basis For LR ?
Yes Describe Program Elements UT*R
- Risk Significant
SYSTEM SCREENING METHODOLOGY S
-DBA'S AND EXTERNAL EVENTS APP. R
SUMMARY
DOCUMENT EQ, APP.R, SBO,A1WS, SYSTEM PTS SCREENING TECH SPECS STRUCTURES AND SYSTEMS DESIGN SBO LCO's - INCL EVALUATION AND BASIS SUPPORT AND STRUCTURES ACCIDENTS SYSTEMS IDENTIFICATION TECH SPECS THAT ARE ITLR ARE IDENTIFIED ATWS HIGHLITED ATWS P&IDS
~
IDENTIFY STRUCTURES
-- PTS
~
)EXTERNAL EVENTS
SCREENING BASES DOCUMENTS GOALS o PROVIDE EASY ACCESS TO INFORMATION o PROVIDE BASIS FOR SYSTEM SCREENING (PROVIDES THE SYSTEM
- p SCREENING RESULTS WITH LITTLE ADDITIONAL EFFORT) o PROVIDE EASY DEFINITION OF "FRONT LINE" SYSTEM BOUNDARIES AND INTERFACING SUPPORT SYSTEM BOUNDARIES o PROVIDE EASY DEFINITION OF NON-SAFETY SYSTEMS ITLR o FACILITATE LATER COMPONENT IDENTIFICATION/EVALUATION o PROVIDES A BASIS FOR NON-INCLUSION OF SYSTEMS/COMPONENTS
DESIGN BASIS EVENTS o DESIGN BASIS EVENTS DESIGN BASIS ACCIDENTS (FSAR)
NORMAL OPERATION/ANTICIPATED OPERATIONAL TRANSIENTS EXTERNAL EVENTS o DBA's BOUND NORMAL OPERATION AND ANTICIPATED OPERATIONAL TRANSIENTS o EXTERNAL EVENTS SEISMIC EVENTS FIRES (SITE FIRES EXCLUDED)
FLOODING MISSILES HURRICANES/TORNADOS
/HIGH WINDS
NON-SAFETY SSC's o SYSTEM SCREENING PROGRAM AND SCREENING BASES DOCUMENTS (FIGURE 1) WILL PICK-UP NON-SAFETY SSC's o NO NEED FOR SEPARATE NON-SAFETY SSC EVALUATION SEISMIC 2 OVER 1 SEISMIC EXTERNAL EVENT ANALYSIS I&C/ELEC SYSTEMS ACCIDENT EVALUATIONS HELBA EVALUATIONS EQ PROGRAM SUPPORT SYSTEMS ACCIDENT EVALUATIONS
SAFETY ANALYSES AND PLANT EVALUATION PROGRAMS o
FIRE PROTECTION (10CFR50.48)
SAFE SHUTDOWN EQUIPMENT
-FIRE SUPPRESSION AND DETECTION EQUIPMENT o
ENVIRONMENTAL QUALIFICATION PROGRAM (EQ) o PRESSURIZED THERMAL SHOCK EVALUATIONS (PTS) o ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS) o STATION BLACK-OUT (SBO)
OTHER EVALUATIONS o
TECH SPEC REVIEW ALL LIMITING CONDITIONS FOR OPERATION SUPPORT SYSTEM/COMPONENT REVIEW o
STRUCTURES IDENTIFY MAJOR STRUCTURES
DELIVERABLES o
PLANT SPECIFIC
SUMMARY
REPORT(S)
OF SCREENING BASES DOCUMENTS
SUMMARY
OF ITLR FUNCTION IDENTIFICATION PROCESS REPORT PROVIDES BASIS FOR SELECTION OF SSC's o MARKED-UP P&ID's WHERE NECESSARY, SUPPLEMENTAL LOOP DIAGRAMS, LOGIC DIAGRAMS, FUNCTIONAL BLOCK DIAGRAMS, LISTS AND MANUALS WILL BE MARKED-UP 0
DELIVERABLES (CONTINUED) o THESE DELIVERABLE PACKAGES:
IDENTIFY THE ENTIRE POPULATION OF ITLR EQUIPMENT PROVIDE AN UNDERSTANDING OF SYSTEM FUNCTIONS ESTABLISH THE BOUNDARIES FOR ITLR SYSTEMS PROVIDE A VISUAL DISPLAY OF ITLR EQUIPMENT FACILITATE IDENTIFICATION OF SUPPORT SYSTEMS AND COMPONENTS PROVIDE A BASIS FOR EXCLUDING SYSTEMS AND COMPONENTS FROM ITLR CONSIDERATION
SSC SCREENING PROCESS o SCREENING BASES DOCUMENTS OUTPUT DOCUMENT
SUMMARY
REPORT HIGHLIGHTED P&ID's o SYSTEM SCREENING ESSENTIALLY IN PLACE
SSC SCREENING PROCESS (CONTINUED) o DESIGN BASIS EVENTS SELECTED DESIGN BASIS ACCIDENTS EXTERNAL EVENTS o PROGRAMS CFR 50.48 EQ
-PTS ATWS SBO o TECH SPECS LCO's SUPPORT SYSTEMS/COMPONENTS o STRUCTURES
SUMMARY
o ITLR SYSTEM SCREENING WILL BE COMPLETED THROUGH SCREENING BASES DOCUMENTS o SYSTEM SCREENING LEADS TO COMPONENT SCREENING o DELIVERABLE PACKAGES WILL FACILITATE AND PROVIDE INPUT TO THE STRUCTURE/COMPONENT SCREENING PROCESS
TECHNICAL REPORTS (1993 WORKSCOPE)
- 1. Component/Comm. Evaluations
Purpose:
Program requirements defined in these reports are sufficient for the license renewal term.
- 2. Methodology and Evaluations
Purpose:
To describe various methodologies (e.g., system screen)
- 3. Reference ARDM Report
LEVEL OF NRC REVIEW Issue draft SER 4 months after BWOG submits draft report to NRC.
Issue final SER 3 months after draft ser, allowing for ACRS review.
(See Flipchart)
0 0
TYPICAL REVIEW CYCLE Kickoff Meeting Prepare Draft Report Draft To NRC NRC Review Incorporate NRC Comments Final Report ToNRC Issue Draft SER ACRS/CRGR Review Issue SER 0
1 2
3 4
5 6
7 MONTHS
COMP./COMM. EVALUATION - 1993 (Draft to NRC)
DHR Cooler 6/7/93 DHR Pump 6/7/93 Commodity - Manual Gate Valves 7/15/93 Reactor Vessel 10/11/93 Pressurizer Heaters 11/8/93 RCP Motor 11/10/93 RCP 12/14/93
METHODOLOGY AND EVALUATION (1993)
(Draft to NRC) 0 System Screening Methodology 3/4/93 Comp./Structure Screening Methodology 5/5/93 First Plant System Screening 7/8/93 Comp./Structure Evaluation Methodology 8/6/93 Effective Program Evaluation Methodology 10/4/93 I&C Effective Program Methodology 8/25/93
REFERENCE (1993)
(Draft to NRC)
ARDM Report 11/8/93
TECHNICAL REPORTS License on Docket (1 pg)
Abstract in FSAR BWOG GLRP (5-10 pgs)
Regulatory Report B&W Propr.
Complete Technical Report Submit to NRC Available for review at B&W Rockville office
FORMAT OF TECHNICAL REPORTS (e.g., Component Evaluation Report) 1.0 Summary and Conclusions 2.0 Component Evaluation Basis 3.0 ARDM Assessment 4.0 Program Requirements to Manage Aging 5.0 ARDMs Managed by Existing Prog.
6.0 Program Enhancements