IR 05000338/1992032

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Discusses 930503 Technical Meeting in Atlanta,Ga Re Scope & Status of DBD Project & Related Activities & Concerns Identified in NRC Insp Repts 50-338/92-32 & 50-339/92-32. List of Attendees & Related Document Encl
ML18153D343
Person / Time
Site: North Anna, Surry  
Issue date: 05/13/1993
From: Merschoff E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
References
NUDOCS 9305270080
Download: ML18153D343 (29)
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MAY I 3 1993 Docket Ntis. 50-280, 50~281, 50-338, and 50-339 License Nos. DPR-32, DPR-37, NPF~4, and NPF-7 Virginia Electric and Power Company ATTN:

Mr. W. L. Stewart Senior Vice President - Nuclear 5000 Dominion Boulevard Glen Allen, VA 23060 Gentlemen:

SUBJECT:

MEETING SUMMARY-SURRY AND NORTH ANNA DESIGN BASIS DOCUMENTATION (DBD} PROJECT UPDATE This ref~rs to the technical meeting conducted at your request at the NRC Region II Office fo Atlanta, GA, on May 3, 199 The purpose of the meeting was to discuss the scope and status of the DBD project and related activiti~ The meeting also addressed concerns that were identified in NRC Inspection Report Nos. 50-338/92-32 and 50-339/92-32. Specific areas discussed during the meeting included DBD and related issues~ identification and resolution o engineering issues, DBD open items, and conclusion It is our opinion that the meeting was beneficial and provided a better_

understanding of your DBD project~ the review being given to the issues that are being identified and the corrective actions for resolving these issue In accordance with Section 2;790 of the NRC's "Rules of Pract_ice," a copy of this-letter and its enclosures will be placed.in th~ NRC Public Document Roo Should you have any questions concerning this letter, please let us kno Enclosures: List of Attendees.

. Design Basis Documentation

. Project Summary cc w/encls:

(See page 2)

9305270080 930513 PDR ADOC~ 05000280 P

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Sincerely, Original signed by Jon R. Johnson (for)

Ellis W. *Merschoff, Director Division of Reactor Projects 26nn1 *:,,

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Vir~~nia Electric & Power Company cc w/encls:

. M. L. Bowling, Jr., Manager

  • Nuclear Licensing
  • . Virginia Electric & Power Company 5000 Dominion Boulevard

. Glen Allen, VA* 23060 G. E. Kane, Station Manager North Anna Power Station P. 0. Box 402 Mineral, VA 23117 M. R. Kansler Station Manage Surry Power Station P. o. Box 315 Surry, VA 23883 Executive Vice President Old Dominion Electric Cooperative 4201 Dominion Boulevard Glen Allen, VA 23060 Mr. Ray D. Peace,.Chairman Board of Supervisors P.O. Box 130 Dendron, VA 23839 Dr. W. T. Lough Virginia Corporation Convnission Divisi'on of Energy Regulation P. 0. Box 1197 Richmond, VA 23209 William C. Porter, J County Administrator P. O. Box 160.

  • Louisa, VA 23093 Michael W. Maupin, Es Riverfront Plaza, East Tower 951 E. Byrd Street

Richmond, VA 23219 Attorney General Supreme_ Court Building 101 North 8th Street Richmond, VA 23219 cc w/encls cont'd:

(See page 3)

MAY I 3 1993

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Virginia Electric & Power Company cc w/encls cont'd:

Robert B. Strobe, M.D., M. State Health Commissioner Office of the Commissioner Virginia Department'of Health P. 0. Box 2448

_ Richmond, VA 23218 bee w/encls:

G. Be 1 i s 1 e, RI I S. Vias, RII L. Engle, NRR Document Control Desk NRC Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 78-A Mineral, VA 23117 NRC Resident Inspector U.S. Nuclear Regulatory Commission Route 1, Box 166-Surry, VA 23883 Rllf_~P

- ur GBelisle 05/ \\ \\,/93 _

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'"'W MSinkule 05/\\,~ /93 G:NASUDBD.MTG R~~RS AG~n 05/~/93 e

MAY I 3 9.33-

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ENCLOSURE 1 LIST OF ATTENDEES U. S. Nuclear Regulatrirv Commission E. W. Merschoff, Director, Division of Reactor Projects (DRP), RII A. F. Gibson, Director, Division of Reactor Safety {DRS), RII J. P. Jaudon, Deputy Director, DRS, RII

M. V. Sinkule, Chief, Reactor Projects Branch 2, DRP, RII G. A. Belisle, Chief, Rea~tor Projects Section 2A, DRP, RII F. Jape, Chief, Test Programs Section, DRS, Rll M. Branch, Acting Chief, Test Programs Section, DRS, RII J. W. York, Acting Sinior Resident, North Anna, DRP D.-M. Tamai, Engineering Intern, DRP, RII J. Miyagawa, DRP, RII

  • L. B. Engle, Senior Project Manager, North Anna, Project Directorate 11-2, Office of Nuclear Reactor Regulation

.*D. R. Taylor, Resident Inspector, North Anna, DRP, RII

  • Attended by telephone conference Virginia Electric & Power Company E. W. Harrell, Vice Presfdent, Nuclear Services M. L. Bowling, Manager,Nuclear Licensing and Programs D. L. Benson, Manager, Nuclear Engineering J. T. Benton, Supervisor, Design Basis Documentation Project

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ENCLOSURE 2

. Design Basis Documentation.

  • Project Update May 3, 1993

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PS06.

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I Objectives

  • . Review Scope and Status of Design Basis Documentation and Related Activities
    • Address the Concerns Expressed in North Anna Inspection Report 92-32 Regarding the Review of Open Items Identified by the Design Basis.

Documentation Process I'

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PS06 Agenda e*

  • _Design Basis Documentation and Related Activities.

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Document Assessment

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Design Basis Documentat~on

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Related Design Reviews and Verifications

  • Identification and Resolution of Engineering Issues

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Station Deviation ~eport

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Potential Problem Report

- * DBD Information Assessment Process

  • Design Basis Document Open Items

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  • . Development of Open. Items

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Review and Classification of Open Items

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Specific Concerns of Inspection Report 92-32

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Resolution of Open Items

  • * Conclusions

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  • Document Assessment Program

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  • * Initiated in 1989 in Conjunction With the Design Basis Documentation Program
  • Objective

~ Identify, Collect, Revi.ew, Code, Index, and Computerize Those Documents That Contain Design Basis Information

  • * Documents Assessed Include both Primary and Secondary Source Documents

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Licensing Correspondence Calculations

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Design Changes (DCPs)

.,... Engineering Work Requests (EWRs)

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Setpoint Changes Technical Reports

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Preoperational And Startup Tests

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NSSS and NE Project Correspondence

-. Equipment Specifications System Des~ription*s Plant Life Extension Reports (Surry)

- * Training Modules* (Nuclear Control Room Operator's_ Development Program)

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NSSS Manufacturer Information UFSAR

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Technical Sl)eCifications

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PS068.4.

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Document Assessment Program, continued'*

Document Assessment Process

  • Identify Documents That Contain Significant Design Basis Information
  • Locate and Acquire Target Documents
  • Establish Review and Coding Criteria.
  • Scan Documents as Raster Images
  • Perform Document Review and Code.

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  • . Data Entry
  • Build Index
  • Integrate With Design Basis Document Library Seri~s PS06 e e

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Design Basis Document Library Series

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  • Computerized Design Basis Information System CD-ROM Based System

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User Friendly Search And Retrieval Software Runs on PC With Windows View Images of Document on Screen About 300 5 Drawer Fi le Cabinets in 1 Foot.of Shelf Space

  • Used By System DBD Developer Each Developer Has Work Station

- * Complete And Accurate Research

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Logistics of Transferring Large Amount of Information Quickly, Accurately, and Efficiently

-, Electronic "Cut and Pasting"

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Significant Productivity Improvement Over Standard Procedures Shorten Development Time

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Thorough Research Enhances Quality Allows Developers to Concentrate on Technical Concerns

  • * * - * Other Advantages
  • Flexible And Expandable

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~ Working On NSSS Design Basis Information

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Add CD-ROM Discs

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D0cun1ent Assessment Results*

e IP ffliil'ffl Fi *:nnr Record Type Licensing Correspondence Calculations Approximate Number of Total Records 25,274.

Project Correspondence Design Changes (DCP)

. Engineering Work Request (EWR)

Preop and Startup Tests Setpoint Changes NE Equipment Specs NE System Descriptions Technical Reports*

Plant Life Extension Reports*

Training Modules* *

UFSAR*

TS*

. NSSS Information

  • Full Text Total Documents:

Total Pages Scanned:

  • Total Pages OCR' d:

,.., 120,000

,.., 2,500,000

,.., 67,000 18,437 43,238 5,729'

. 18,507 945 442 1,431 594 1,074

140

2 Working

. Percent in DBD °/o 9.8°/o 91o/o 94°/o 82o/o 100°/o 100°/o 97°/o 100o/o

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'.100°/o 100°/o 100%

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Virginia Power DBD Organization and Features

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  • Syste,:n DBD Includes Component Design Basis as Well as System Design Basi * -

Compreh.ensive and Complete

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User Oriented

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28 Design Topics Addressed

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Significant Development Efforts.

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  • System DBD Is Annotated to Identify Information, Data*or Facts*

Text Is Annotated With Reference Number

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Chapter 25.0 Contains Complete Bibliography

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Directs User To Source Document * *

Facilitates Updating

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Facilitates Computerization

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Classified as "Comprehensive"

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Meets or Exceeds Requirements in All Areas

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  • Design Basis Documentation R

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  • Managen1ent Committee Formed in 1988 to Review Needs
  • DBD Program Approved and Initiated in 1989
  • Scope.

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Prepare System DBDs for Major Systems at Each Station (Approximately 50 per Station)

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Prepare Plant DBD for Each Station*

  • Schedule

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Seven Year Program, l989 Through 1996

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Approximately 7 System DBDs per Site per Year

  • Current Status

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22 System DBDs per Station Either Issued or in Draft Complete Stage

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6 Draft System DBDs per Site to Be Completed by Year End

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Approximately 22 Remaining per Site

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Plant DBD: "Accident An_alysis DBDs 11 Will Be Completed for Each Site in 1994

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PS06 Virginia Power DBD Organization and Features, continued e

  • System DBD Is "Roadmap" to More Detail-Related Information

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Safety Analysis

-. Calculations

-* Other Contr~lled Configuration Management Documents

  • System DBD 1*dentifies Open Items *

. - Missing or Incomplete Source Documentation e *.

- Conflicting Data.*or Information

-* Errors or Descrepancies in Calculations

-.source Linkages to Other DBDs

    • . -. Other Concerns With *Quality of Information

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Systen1 DBD '"fable Of Contents e.0

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  • -Introduction System Functions, Performance Criteria, and Design. Criteria (ANSI N45.2.11)

System Description *

System Classification and Boundaries System Interfaces Key System Parameters Design Basis Background Regulatory Basis and Requirements Industry Codes and Standards Designer Standards and.Guideline Plant Analyses.

Margin Evaluation'

System Safety Design Criteria Component Design Requirements Programmatic* Design Topics

. Critical Calculation Summaries Design Basis Maintenance Requirements Design Basis Procurement Requirements Design Basis Su_rveillance Requirements Modification History Design Basis Technical Specification Requirements Design Basis Operational Requirements Setpoint Parameter Bases Open Items

  • References PS068.11

Status By DBD Group Sy_?.t~I!!,~,!~gn Basis Documents

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Group: 01 (1989-1991) Issued AFW -

Auxiliary Feedwater ED

- - Emergency Power (125V DCJ EG

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Emergency Diesel Generator EP

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Emergency Power IA

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lnstru!lMlnt and Service Air QS

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Quench *spray

RS

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Recirculation Spray SI

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Safety Injection SW Service Water Total Systems per Station= 9 C.,oup: 02 0 991-19931 Draft Complete CC

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Component Cooling Water CN Condensate ESS

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Station Service Power FW

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Feedwater MS

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Main Steam Total Systems per Station= 5 Group: *03 (1991-1993) Draft Complete CH

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Chemical and Volume Control NC NSSS Control System NI

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Nuclear Instrumentation RC

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Reactor Coolant RH

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Residual Heat Removal RPS

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Reactor Protection e Total Systems per Station = 6 Group: 04 (1992-1'.193) Draft Complete EA

-. Power Generation EB

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Black Battery (125V DC) (Surry only)

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Lighting (Emergency and Normal)

EV

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Vital Bus (120/240V)

FC

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Fuel Pool Cooling and Reactor Cavity Puri Total Systems per Station= 5 Group: _ 05 (1993-1994) Un Progress)

CD Chilled Water GW -

Gast'OUS Waste HA

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Auxiliary Building Ventilation HC

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Control Room Air Conditioning and,Pres HL Service Building Ventilation HO

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Miscellaneous Building Ventilation

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Fuel and Decontamination Building Ven HR

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Containment Air Cooling HT Turbine Building Ventilation Total Systems per _Station = 9 Group: 06 (1994-1995) (Proposed)

BC Bearing Cooling BO Steam Generator Blowdown, Recirc. & Xfer CV

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Containment Vacuum and Leakage Monitoiring CW -

Circulating Water and Vacuum Priming FP

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Fire Protection IC lncore Instrumentation PHC -

Postaccident Monitoring & Hydrogen Removal RM - -

Radiation Monitoring SS

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Normal and Accident Sampling System Total Systems per Station = 9 Group: 07 (1995-1996) (Proposed)

BR

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Boron Recovery and Primary Grade Water ERF ERF Computer FH

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Nuclear Fuel Handling and Storage

GN

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Primary and Secondary Plant Gas Supplies NS Neutron Shield Tank and Cooling PVD -

Primary Vents and Drains - Radioactive RD

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Rod Control and Rod Position Indication RW

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Liquid and Solid Waste Total Systems per Station= 8 Group: 08 (1996-1997) (Proposed)

CO

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Reactor Core and Internals CP

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Condensate Polishing EC

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Communications El

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Electrical Instrumentation & Plant Computer NF Neutron Flux Instrumentation (Post Accident)

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Secondary & Bldg Svcs Drains - Nonradioactive TG Turbine Generator and Auxiliiries Total Systems per Station = 7.

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Related Design Reviews And Verifications*

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  • System Critical Calculations.Are Reviewed Concurrent With System DBD Preparation
  • System Walkdown~

Functional Verification of Design

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Component Data Collection Verification of Safety Classification

  • Electrical Engineering Calculation Upgrade.
  • Setpoint, Scaling Verification
  • Surveillance Review
  • Environmental Qual_ification Documentation Upgrade_
  • Safety Analysis Code Verification
  • Off-Site Dose Methodology Upgrade mn**. a** ffl' -;*: mrt1*rr*mercne1h-*:rnnrmrstmzmrrmr"rKffl!Wnr WM Cit * tmtJ&'

PS068.13

Identification And Resolution Of

. Engineering.lssues

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  • * Potential *Problem* Reporting System e * * DBD Information Assessment Process PS068.14

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Station Deviation Report

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  • The Process for Identifying and Determining*
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  • Reportability of Conditions Potentially Adverse to

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Quality and Operability

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  • * Applies to All Activities Within the Nuclear
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  • * Directed to Station Management for Assessment of *

Reportab i I ity, Operab i I ity WFh'*ftF'.. nne,mm Ni TEl M:fflt?Flfflffl

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  • * Potential Proolern Report f:, e\\m*t* * a,,n nwtrre iiffit c:tih ;znrr,
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  • A Process. Within Nuclear Engineering Services for Reporting, Reviewing and T~king Corr~ctive Actions on Potentially

.Significant Problems Arising From Design and _Engineering Activities

  • Al I PPRs Are Promptly RevieWed by a Review Committee Comprised of the Engineering Managers
  • Provides Guidelines for Notifying Station Management of Defects and Non-Compliances That May Be Reportable

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  • Reporting of Unreviewed Safety Questions or Operability Concerns to Station Management Will Be By Initiation of a Station Deviation. Report.

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DBD lnforn1ation Assessment.Process

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      • mre*e-"S: ZF:ffflt*t Draft Related Issues
  • Lack of Valid Source Documents
  • Missing Information
  • Errors, Conflicting Information

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.REVIEW CPMMENTS RESOLVE COMMENTS *

i Information Assessment

  • System/Component Margins
  • Critical Calculations
  • Adequacy of Supporting Documentation Open Items Priority Categories:
  • Immediate
  • Intermediate Term
  • Resolve If Needed I

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  • . Held Following Receipt of Comments on Draft DBDs *
  • * Purpose of the Information Assessment Meeting Is To Document and Assess Any Areas of e

Incomplete or Deficient Design Basis Documen~tion or System Deficiencies

  • Participants Include Rep~esentatives From*

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Engineering Disciplines: Civil, Mechanical, E_lectrical, and Nuclear Analysis

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System Engineering

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Licensing

-.. DBD Preparer

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Quality Assurance

  • Assessment Includes Margins

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Critical Calculations

- * Adequacy of Supporting Documentation

- * Significant Open Items

  • * Participants Assess Whether There Is Sufficient Design Information of Adequate Quality to Support..

Design, Maintenance and Operability of the System err- *MiE:ri*- "ii' C:ilitffi *CT;)fz iitrffid:W' ffliWtmilltZWfPZtY"TiBYTP

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. Design Basis Documentation Open Items*

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The DBD Writer's Guide Requires the Preparer to Identify Any 110pen Items* in the Text of the Document by Number and to Summarize the "Open Item"* in Chapter 24 of the Document Open Items Provide:.

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  • Clarifi~ation to the Reader.Regarding the Accuracy or Quality of the Sousce Document
  • Linkages to Other Documents to Ensure Proper Integration With Other DBDs *
  • * An Organized Basis From Which to Further Upgrade the Design Basis Open Items Include:

1. Missing or Incomplete Source Documentation or Referencing of a Secondary Reference

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2. Conflicting Information or Data in Source or Reference Documents e

3. Errors or Discrepancies in Calculations, Reports, et. Missing or Incomplete Calculations 5. * Linkages to Other DBDs Not Yet Completed 6. Other Matters Judged to Require Additional Review or Action

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Desi(JTl Basis Docurr1ent - Open Items ewmr ** W' 'ff **** sin rtnmPi,1ntt,Wiiii * tm ea 'ittmre**m:**r*e*eer2,e1tntwm I,

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On Average Each Group 1 DBD Had 180 110pen items

. Distributed as Follows:

Calculations 27 Items, 15%

Specifications 27 Items, 15% *

Document Concerns 39 Items, 22%

Document Linkages 62 Items, 34 o/o Other 27 Items, 15%

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Classification, Of Open Items

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Open Items Will Fall Into Three Categories

41 Immediate Intermediate Term

-. Operability or Safety Concerns Which Are Resolved Immediately (Critical Calculations Are Reconstitu:ed Within 30 Days).

I Not Immediate Concerns, But Should Be Resolved in the Interest of Having a Quality Body of Design Information Resolve If Needed -

Resolve Only if Needed to Support Design Work or Operations Support

  • The Information Assessment Is Intended to Ensure That Only 11lntermediate Term

and 11Resolve If Needed

. Items Are Deferred and Entered in Chapter 24

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  • Open Items Add.ressed In Inspection Report 92-32

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Item 24. Delay in Delivery of Recirwlation Spray Flow for Certain Accident Scenarios

Initial Notification by Stone & Webster Via Telecon in September, 1989. S&W Concluded There Was No Adverse Impact on Pump Perforriance or Off-Site (?os *

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PPR Initiated in February, 1990. Issue and Related Documentation Reviewed by Management Problem Review.

Committee. Previous Conclusions Confirmed. Directed lsssuance of Advisory to Trainin *

Documented in Information Assessment Meeting, March 14, 1990. Action Assigned to Nuclear Analysis and Fuel Department to Confirm That This Is Not a Significant Concer *

Nuclear Analysis and Fdel Confirms by Memorandum, May 2, i' 990 That Issue Has No Significant Impact on Pump Performance or Off-Site. Dos *.

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Item 24. Differences in Spray Effectiveness Values

Notified by Stone & Webster by Telecon in September, 1989. Treatment of Spray Coverage Was Typical ot Vintage; Site Boundary Thyroid Dose Is 46 rem Versus a 300 rem Limi.

Documented in Information Assessment Meeting, March 14, 1990. _Action Assigned to Nuclear Analysis and

. Fuel Department to Confirm That This Is Not a Significant Concern.

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Nuclear Analysis and Fuel Confirms by Memorandum September 30, 1990 That Use of More Current*

. Methodology Would Not Significantly Reduce Margin to the 300 rem Limi.

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  • Open Items Addressed In. Inspection Report 92-32, continued

Item 24.14.135 Casing Cooling Tank Setpoint In Potential Vortexing Zone

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Prior to the Information Assessment Meeting, Stone & Webster Was Directed to Reconstitute the Casing Cooling Tank.Volume Calculation Which Could Not Be Located. Reconstitution Was in Progress at the lime of the Information Assessment Meeting on March 14, 199 *

  • On March 26, 1990, After the Assessment Meeting, Notification Was Received by Letter Stating That Usab_le Volume Is Adequate But That Low Level Setpoint Is Within Potential VortexingZon *

DBD Staff Elected to Defer Item Based on Belief That Tank Would Drain,Down a~ Designed..

Following Inquiry From Resident Inspector, Mechanical Engineering Provided Position Paper Restating This Conclusio Item 24. Incorrect Safety-Classification of Casing Cooling Level Transmitters

  • A Reverification of Safety Classification of Station Components Has Been in Progress Since 1992 and Will Continue Through 199 * Given the Active Component Classification Review Effort, DBD Open Items Related To Classification Issues Were Deferre *

PS068.23*

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  • Actions In Progres*s Or Planned To Resolve Oper1 Item~;

And Improve The Review And Documentation Process

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  • For Group 1 DBDs Approximately 25°/o of All Open Items Are Being ~esolved During the First Revisions Which Are Being Completed in the Second Quarter of ThisYear *

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  • Open Items for Group 1 DBDs Will Be Re-Reviewed Following Receipt of Revision 1 *

Documents Items to Be Resolved Will Be Specifically Assigned Basis for Deferral Will Be Provided for Deferred Open ltEms (lrx:luding Those Assigned and in Progress)

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  • lnformationAssessmerit Meeting Minutes Will Be.strengthened* to More Fully Document the Basis for Deferral of Significant Open Items
  • For Group 2 and Later DBDs, a Deferral Basis Will Be Provided for Open Items Within Approximately 90 Days of Issuance

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PS068.24

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Conclusions

  • Document Assessment Project Has Provided a Comprehensive Design Information Base From Which to Prepare DBDs and Support Engineering Activities.
  • DBDs Are Thorough, Consistent, Address Both System and Component Level Design Basis and Are Designed to Be Maintained and Augmente *
  • * Open Items Are Properly Assessed for Reportability and Unreviewed Safety Questions._ Documentation of Basis for Deferring Open lt~ms

Will Be Improve *

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  • We Will Continue to Improve the Quality of Design Basis Information by Preparation of DBDs, by Comple~ion of Design Verificatiorn Activities and by Resolving Open Item PS068,25

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