ML15260A021
| ML15260A021 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Mcguire, Catawba, McGuire, 05000000 |
| Issue date: | 06/15/1989 |
| From: | Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Tucker H DUKE POWER CO. |
| References | |
| NUDOCS 8906290024 | |
| Download: ML15260A021 (26) | |
Text
JUN 1 5 1989 Docket Nos.-50-413,.50-414, 50-369, 50-370, 50-269, 50-270, 50-287 License Nos. NPF-35, NPF-52, NPF-9, NPF-17, DPR-38, DPR-47, DPR-55 Duke Power Company ATTN:
Mr. H. B. Tucker, Vice President Nuclear Production Department 422 South Church Street Charlotte, NC 28242 Gentlemen:
SUBJECT:
MEETING
SUMMARY
NUCLEAR PLANT DESIGN BASIS DOCUMENTATION This letter refers to the Nuclear Plant Design Basis Documentation Meeting held at your request on May 25, 1989.
This meeting concerned activities to be conducted at all of your nuclear facilities.
The subject of our meeting related to your new Nuclear Plant Design Basis Documentation program.
A list of attendees, a summary, and a copy of your handouts are enclosed.
In accordance with Section 2.790 of the NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Room.
Should you have any questions concerning this letter, please contact us.
Sincerely, Stewart D. Ebneter Regional Administrator
Enclosures:
- 1. List of Attendees
- 2. Meeting Summary
- 3. Presentation Handout cc w/encls:
(See page 2)
PDR ADOCK N
P
Duke Power Company 2
JUN 1 5 1989 cc w/encls:
M. S. Tuckman, Station Manager T. L. McConnell, Station Manager T. B. Owen, Station Manager State of South Carolina State of North Carolina bcc w/encls:
NRC Resident Inspector K. Jabbour,,NRR L. Wiens, NRR D. Hood, NRR Document Control Desk RII R11 RH RII RII Ionser AHerdt s
t 6/ /89 6/c7/89 6/ /89
()48 6/i /89
ENCLOSURE 1 LIST OF ATTENDEES U.S. Nuclear Regulatory Commission S. D. Ebneter, Regional Administrator M. L. Ernst, Deputy Regional Administrator C. W. Hehl, Deputy Director, Division of Reactor Projects (DRP)
E. W. Merschoff, Deputy Director, Division of Reactor Safety A. R. Herdt, Chief, Reactor Projects Branch 3, DRP M. B. Shymlock, Chief, Reactor Projects Section 3A, DRP Duke Power Company H. B. Tucker, Vice President, Nuclear Production T. C. McMeekin, Vice President, Engineering G. W. Grier, Vice President, Quality Assurance P. R. Herran, McGuire Mechanical/Nuclear Engineering Manager
ENCLOSURE 2 MEETING
SUMMARY
On May 25, 1989, representatives from Duke Power Company (DPC) met with the NRC in the Region II office in Atlanta, Georgia at DPC's request.
DPC gave a presentation (Enclosure 3) on their Nuclear Plant Design Basis Documentation program.
The DPC presentation covered their new Quality Initiative. This initiative includes both a "look back" and a "look forward" feature.
With these features, a Design Basis Documentation program can be developed.
The Design Basis Documentation program was then further explained.
This program would be developed for all three plant sites.
In the program area of problem resolution process, DPC requested our evalua tion and input in the area of LER reporting and subsequent corrective action.
S. Ebneter, NRC Region II Regional Administrator, closed the meeting by stating that it had served to inform Region II personnel of how DPC had planned to develop this new program.
He also informed DPC that we would initiate appropriate action to their request.
ENCLOSURE 3 Nuclear Plant Design Basis Documentation Duke Power Company and Nuclear Regulatory Commission Region II May 25, 1989 Meeting Agenda HB Tucker I.
Purpose A. Present our DBD Concepts B. Determine Best NRC Interface TC McMeekin II.
Duke Power Company Quality Initiatives A. Look Back B. Look Forward PR Herran III.
Design Basis Documentation A. Steering Committee and Pilots B. Format and Content C. Scope, Project Management and Schedule GW Grier IV.
Problem Resolution Process A. Duke Process B. NRC / Duke Interface HB Tucker V.
Summary
DUKE POWER INITIATIVES LOOK FORWARD TOPFORM LOK AC0 Initial & Final Scope Documents SSFI (NRC)
Interfacc Meetings SITA Integrated Design Reviews SBWOC SPIP Test Acceptance Criteria Design Input Documentation Enhanced 50.59 Reviews Document Upgrade & Dwg Legibility Program Analytical Model Reviews INPO Good Practice Reviews
NRC SSFI/DUKE SITA Technical Detailed Vertical Look at a System Multidiscipline GENERIC PROBLEM FINDINGS LESSONS LEARNED REVIEW Horizontal look at Specific items to be Programs to help other systems for resolved for that prevent future generic issues.
system.
problems.
EXAMPLE NRC-1986 SSFI OCONEE EMERGENCY FEEDWATER SYSTEM GENERIC PROBLEM REVIEW FINDINGS LESSONS LEARNED Caics reviewed to ensure Design calcs not com-TOPFORM Program systems operating modes plete for all operating
- Design Inputs covered modes of EFW (runout)
- Analytical Model Reviews
- Integrated Design Reviews Reviewed other electrical
- Keowee dynamic analysis
- Test Acceptance Criteria power distribution systems incomplete
- Interface Meetings Overpressure Protection
- Overpressure Protection Overpressure Protection reviewed for all steam design not adequate for Training systems one steam relief valve supplying TDEFW pumps
McGuire Diesel Generator Starting Air System GENERIC PROBLEM FINDINGS LESSONS LEARNED REVIEW Other Diesel Generator Improper Isolation
- TOPFORM Program Support Systems Added Between Safety and Test Acceptance Criteria to the Audit Non-Safety Components
- Diesel Gen. System
- Diesel Gen. Fuel Oil System Improper Component
- Design Basis Documentation Safety Classification
- Steering Committee Formed
- Diesel Gen. Lube Oil System Membership from Design Engineering and Nuclear Diesel Gen. Control System Production
- Developed a Pilot DBD for each Nuclear Station
- System Expert Program
- Diesel Generator Reliability Needs to Address Diesel Team Established Engine Reliability
- Enhanced Test Program
DUKE POWER INITFIATIVES LOOK FORWARD TOPFORNI LOOK BACK Initial & Final Scope Documents SSFI (NRC)
Interface Meetings
- SITA Integrated Design Reviews BWOO SrW Test Acceptance Citeia Design Input Documentation Enhanced 50.59 Reviews Document Upgrade & Dwg Legibility Program Analytical Model Reviews INPO Good Practice Reviews DESIGN BASIS DOCUMENTATIDN
FUTURE ENGINEERING SUPPORT
- More Responsible Operability Evals.
- Better Engineered Solutions to Problems
- Better/Easier 50.59 Evals. of Mods.
DESIGN BASIS DOCUMENTATION
- Design Requirements Required Operating Modes
- System Descriptions
- NRC Commitments DUKE SITA
- More productive audits/responses
- Better system design basis understanding eBetter able to identify generic issues
DBD PLAN January 30. 1989
- Vice Presidents Design Engineering and Nuclear Production formed DBD Steering Committee
- Chaired by Design Engineering
- Membership from Design Engineering and Nuclear Production
- Liaison with Quality Assurance
- Chartered to Produce DBD Report May 12. 1989
- Preliminary DBD Steering Committee Report Completed
Objectives of the Duke Power DBD Steering Committee Definition of the Scope, Content and Format of the Design Basis Documentation effort Definition of the Systems and Structures for which Design Basis Documents will be developed and the priority and schedule options for such work Definition of Administrative Processes Necessary for Initial Issue and to keep Design Basis Documents current Publication of Design Basis Document and associated documents (e.g., Test Acceptance Criteria) for the pilot system or structure selected for each plant Identification of automation tools which could be used and the impact on scope, cost and schedule
DBD Pilots Oconee - Emergency Feedwater System (EFW)
McGuire - Emergency Diesel Generator Starting Air System (VG)
Catawba - Nuclear Service Water Pump Structure
Relationship of DBD to Other Documents 10CFR Tech.
FSAR Codes SAR SER Caics Corres.
Stands Plant, Systems &
DB/TAC Structures Dwgs DBD Smry Specifications Dwgs Design Design Vendor Computei NPD Dwgs Specs Does Lists Proced
Typical Documentation Reviewed for DBD 10CFR Duke Drawings FSAR PIR / LERs SER Valve / Equipment Lists Standard Review Plan I & C List Branch Technical Positions System Descriptions Tech. Specs.
Current NSM Packages Duke Nuclear Guides Fire Protection Safe Shutdown Licensing Correspondence Review Manual ANS Standards Fire Protection Review Manual ANSI Standards Response to TMI Concerns ASME Standards Response to NUREG-0588 IEEE Standards Plant Environmental Parameters SITA Audit Findings Manual INPO SOERs EQRI Manual NSSS Correspondence Testing Correspondence Files Station Task Force (testing)
Specifications IWP/IWV Code (ASME Section XI)
Calculations IWP/IWV Manual Manufacturer Drawings and NPD Directives on Retest Manuals Station Procedures and Retest List Design Studies on Testing
Plant DBD System s/Structures Systems/Structures DBD Spec.
DBD DB/TAC Drawings and Summary Drawings Equipment DBD
Systems and Structures Design Basis/System Description Specification Table of Contents INTRO DB SD 10.0 20.0 30.0 All units All units Common or Shared t
~future needs' 31.0 10.1 Boundary & Scope 10.2 System Purpose 10.3 Format & Use Unit 1 future needs 32.0 20.1 System/Structure Functional Design Basis Unit 2 20.2 System/Structure Specific Design Criteria 20.3 System/Structure Generic Design Criteria 33.0 20.4 Equipment Design Basis 20.5 Design Basis References Unit 3 31.1 General Description 31.2 Equipment Description 31.3 Instrumentation & Controls 31.4 Indication & Alarms 31.5 Power Supplies 31.6 Selected Design Document Cross Reference
'Form 45069 (R 10-38) g System Design Bases/Objectives
- Design Basis
- . The VG system shall supply control air at sufficient pressure to keep the emergency diesel generator running (Reference section 20.1.2 of specification no. MCS-1609.VG-00-0001).
Objective:
Verify that a control air pressure of no less than 90 psig and no greater than 135 psig is maintained, after the diesel starts, while the emergency diesel generator is running for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Tech. Spec. 4.8.1.1.2e(8)). The starting air compressors shall be available to start during this test.
Test Frequency:
The control air test shall be performed with the same frequency as the emergency diesel start test.
Operability:
If a diesel fails this test, then it shall be declared inoperable.
Test Acceptance Criteria Test/Measurement Reference Document Acceptable Value Including Tolerance Control air pressure TT/OB/9100/300 90 < P < 135 psig Tech. Spec. 4.8.1.1.2e (8) 2/15/89 letter from JR Hilley to F Schubert DUKE POWER COMPANY QA COND 1 McGuire Nuclear Station, Units 1 & 2 Design Basis/Test Acceptance Criteria Emergency Diesel Generator Control Air DSN/DTEI "/iL
-s5-&
INS/DTE 2W4 CHK/DTEk2
~--IINS/DTEqt M
c :tklJALT 4-APP/DTE 5-,.0 INS/DTE NO REVISIONS DSN CHK APR DTE C/E ELE M/N DWG NO MCDB-1609-VG.S002-01 REV 0
JDG MIDCSF-IG09. VG-1 33/35 RN I/Z3 PURIFINEAt /13S 8 /
AIR LET ATMOSPHERE 61/65 A1/1 IR. INLET Air RN FILTER Al/Al STARTING AIR DRYER Al/B3 AFTERCOOLER AIR 62/66 TANK A/Al
/Al/Bl COMPRESSOR Al/BI 89/91 17/19 8/
}
VOLUME D L C TK A/0 CONTROL AIR
-DEE VI BLCOUT Im HRER ENGINE HEADER
-_4 0 AEDE A/B
/3/94 00 3 / 4 NOTE 2 CONTROL AIR FILTER R/B 7S/80{1 77/78 90/92 18/20 34/3RN AIR Nt ET ATMOSPHERE PUR8 IE ZA AIRINLE T PURIFIER A2RN2 01R RN FILTER AZ/BZ STARTING AIR DRYER AZ/BZ AFTERCOOLER AIR TANK AZ/BZ AZ/AZ COMPRESSOR A2/A2 NOTES a
- 1.
EACH UNIT HAS TWO DIESEL ENGINES (A AND B).
EACH ENGINE UNCONTR0LLED HAS TWO STARTING AIR SUBSYSTEMS (AS SHOWN ABOVIE).
BOTH A AND B SUBSYSTEMS'. EQUIPMENT TAG NUMBERS ARE.DISPLAYED,
- 2.
SOLENOID VALVES VGSV5160/5170,5161/5171.5162/517Z AND 5163/5173 ARE LOCATED ON THE CONTROL AIR HERDER.
SEE ILC DETAILS MC-1499-VG3 (UNIT 1I) AND MC-2499-VG3 (UNIT 2).
TYPICAL FOR UNITS 1 AND 2
___04LLY THIS DRAuNG IS A
SUMMARY
FLOU DIAGRAM.
P04ER COMPANY I FE TI5~TC FOR COMPLETE SYSTEM DESIGN INFORHRrION.
_____NUCLEARSTATION UMITOFF VILVE NClfeeLLY CLOSED I
-ELECTRIC
_SUNAV FLV cCNTAQL TORxL TH01ROL HD c
MC-1609-4.0 VG SYSTEM (UNIT 1)
FLOW DAM OF P-PISTON DIESEL ENEATOR ENGINE ECK VLVE FL S-S0LENDIC MC-Z609-4.0 VG SYSTEM (UNIT 2)
RTING AIR SYSTEM (VG)
(tLELPE P-(
-EPRESSURE
-TEMPERATURE~IESE GENERATOR ENINGINEOI ITI F
IIELIEFSA VrV A MES S nE 1GERE ORGNLIS
Estimate of DBD Systems and Structures Scope Criteria - Nuclear Safety Related, Technical Specification, or other selected systems Mech Systems Elect Systems Civil Structures Oconee 45 26
'6 McGuire 61 34 3
Catawba 60 34 3
Total DBD 166 94 12 Total Plant 291 167
DBD Prioritization Risk Significance / Recent Experience Plant Testing Trends (performance degradation, wear, fouling, etc.)
DBD Project Management Design Quality
.eig Nuclear Assurance LeadDept.
Production Oconee Engineerin Oconee Oconee General Nuclear Services Project General Nuclear Office Station Division Division Office Station Mechanical Electrical civil
- Review DBD Specs.
- Prepare DBD
- Normal Document Audit 1989 Scope Identified
- Initiate and Resolve PIRs
- SITA Audit Lead
- Coordinate Remaining
- Initiate LERs Scope Annually
- Revise Procedures
- Prepare Test Acceptance Criteria
- Initiate and Resolve PIRs Same For McGuire and Catawba Nuclear Stations
DBD Schedule Oconee Systems & Structures 13/year McGuire Systems & Structures 16/year Catawba Systems & Structures 16/year Total 45/year Project Completion - 1995
DBD Problem Resolution Process Initial Action Document Utilizing PIR Process
- Operability Evaluation
- Reportability Evaluation 1 OCFR21 1 OCFR50.72 1 OCFR50.73 1 OCFR50.9
- Initial Root Cause and Corrective Action
- Immediate Action to Restore Operability and Comply with Tech Spec (current and future)
- Continue DBD Review
- Report to NRC As Appropriate
- LER, As Required With Schedule to Complete DBD Review and Past Operability Concerns
- Resident Inspector Kept Informed
DBD Problem Resolution Process Subsequent Action
- Complete DBD Project for System
- Review All Problems Identified
- Investigate Past Operability
- Final Root Cause and Corrective Action Determination
- Revise LERs as necessary
- Inform Resident Inspector of Status Periodically