ML18032A609

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Summary of 870915 Meeting W/Tva Re Differences (Deltas) Between Sequoyah & Browns Ferry Nuclear Performance Plans. Attendance List & Browns Ferry Program Description Encl
ML18032A609
Person / Time
Site: Browns Ferry, Sequoyah, 05000000
Issue date: 10/06/1987
From: Stang J
NRC OFFICE OF SPECIAL PROJECTS
To:
NRC OFFICE OF SPECIAL PROJECTS
References
TAC-62247, NUDOCS 8710230145
Download: ML18032A609 (40)


Text

0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Docket Nos.

50-259/260/296 October 6, 1987 LICENSEE: Tennessee Valley Authority FACILITY; Browns Ferry Nuclear Plant, Units 1, 2 and 3

SUBJECT:

'UMMARY OF MEETINGS HELD ON SEPTEMBER 15, 1987 BETWEEN TVA AND NRC CONCERNING THE DELTAS IN MAJOR PROGRAMS BETWEEN THE SEQUOYAH AND BROMNS FERRY NUCLEAR PERFORMANCE PLANS (TAC NO. 62247)

On September 15,

1987, a meeting was held in Bethesda between the OSP staff and representatives of TVA for the purpose of the OSP technical staff being briefed on the differences

("deltas" ) between the Browns Ferry and Sequoyah programs in an effort to assist the staff in resolving resource and scheduling

. conflicts and to become better acquainted with the Browns Ferry technical staff.

The following programs were discussed at the meetings:

1.

guality Assurance 2.

Piece-Parts Procurement 3.

Environmental Oualification 4.

Melding 5.

Heat Code Program 6.

Moderate Energy Line Break Analysis Attachment 1 is the list of attendees.

Attachment 2 contains program descrip-tions presented by TVA during the meeting.

The meetings provided the OSP staff with useful information regarding similarity and differences between the above Sequoyah and Browns Ferry programs'.

The meetings resulted in the following TVA action items:

1.

TVA will make available to the OSP staff the detail plans of Moderate Energy Line Break Analysis.

2.

TVA will provide greater details of Heat Code

Program, because it is a

new topic in Revision 1 of Volume 3 of the Browns Ferry Nuclear Performance Plan.

87f0230l45 87100b PDR ADQCK 050002S9 P

PDR

3.

TVA would provide a firm dated for a 30% Eg binder inspection, because of the many schedule slippages TVA has had in this area.

Enclosures:

l.

Attendees List 2.

Meeting Handouts cc w/enclosures:

See next page Original Signed By John F. Stang, Project Manager TVA Projects Division Office of Special Projects DISTRIBUTION NRC PDR Local PDR See attached lists OSP:TVA/LA CJamerson 10/ IA /87 J

10

as

/87 0

/PM P'/PM 87 OSP:AD/P JZwolinski 10/(, /87

I 3.

TVA will provide a

firm date for a 30K Eg binder inspection, because of the many schedule slippages TVA hys had in is area.

Attachments:

l.

Attendees List 2.

Meeting Handouts cc w/attachments:

See next page J

n F. Stang, Project Manager TVA Projects Division Office of Special Projects

Mr. S.'A. White Tennessee Valley Authority Browns Ferry Nuclear Plant Units 1, 2, and 3

CC:

General Counsel Tennessee Valley Authority 400 West Summit Hill Drive Ell B33 Knoxvi 1 le, Tennessee 37902 Mr. R. L. Gridley Tennessee Valley Authority 5N 1578 Lookout Place Chattanooga, Tennessee 37402-2801 Mr. H. P.

Pomrehn Tennessee Valley Authority Browns Ferry Nuclear Plant P.O.

Box 2000

Decatur, Alabama 35602 Mr. M. J.

May Tennessee Valley Authority Browns Ferry Nuclear Plant P.O.

Box 2000

Decatur, Alabama 35602 Mr. D. L. Williams Tennessee Valley Authority 400 West Summit Hill Drive W10 B85 Knoxville, Tennessee 37902
Chairman, Limestone County Commission P.O.

Box 188

Athens, Alabama 35611 Claude Earl Fox, M.D.

State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36130 Regional, Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W.

Atlanta, Georgia 30323 Resident Inspector/Browns Ferry NP U.S. Nuclear Regulatory Commission Route 12, Box 637

Athens, Alabama 35611 Mr. Richard King c/o U.S.

GAO 1111 North Shore Drive Suite 225, Box 194 Knoxville, Tennessee 37919 Mr. S.

A. White Manager of Nuclear Power Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Place Chattanooga, Tennessee 37402-2801

ATTACHMENT I DELTA MEETING RRIIRS 955~9 15 IRSI Name John Stang B.

C. Morris Gerry Gears Bob Pierson Rex Wescott Jim Watt Pete Hearn Paul Cortland Robert Hermann John A. Zwolinski B.

D. Liaw W. L. Elliott I. V. Holt J.

D. Wolcott J.

R. Norris C.

D. Lvndin David Bjorkbom W. S. Little A. Ignatonis Patrick Carier G. L. Paulk T.

G.

Chapman G. T. Hubbard M. J.

May Organization/Position NRC/OSP/TVA - Project Manager TVA - TVA - BFN Licensing NRC/OSP/TVA - Project Manager NRC/OSP/PSP - Branch Chief NRC/OSP/PSB - Plant Systems Engineer NRC/OSP/ROB - Reactor Systems Engineer NRC/OSP/ROB - Sr. Reactor Engineer NRC/OSP/EB - Materials Engineer NRC/OSP/EB - Chief NRC/OSP/TVA - AD for Projects NRC/OSP - AD for Technical Programs TVA -

EQ Prog Manager SQN TVA - Materials Manager BFN TVA - Licensing TVA - BFN QA TVA - Weld Program Manager SERCH Licensing - Bechtel NRC/OSP - Special Assistant NRC/OSP/TVA - Inspection Programs TVA -

BFN Licensing NRC -

BFN SRI TVA/BFNP NRC/OSP TVA -

BFN Licensing

Director Division of l lucleor Quality Assurance Site Director Erlgineering AssuI-ance Site Quality Manager-.

l l

I IManager Qualit" Assurance Group Technical ServicesSection I

Manager, Quality Engineering and Control Group l

l I

4

~ ~

~ n su porvlJoc, rJuolitj Surveillance I

Section I

.JI II.uI.'ISOr, Q.;.s.".t

~

< orltrol Sec tion 5<JpvrvI Joc QIIalit; Engineering S action

. J SupeI vIsoI, Materials/Receipt Section

IAJOR EL.EMEI'ITS OF THE SITE QUAL.I1 I'SSURANCE STAFF INCLUDED AT SQN COMMENTS Organi ation Structure Changes Yes Erlgincering A-durance

!nterface Yes Si:~ Qua!it,'1anagor's Dutias cnd Responsibilities Yes Cucli:> Assurance t.ianager's Duties and Responsibilities Yes Qua.'i'.,

6:ngirlevring and Control

.'.;.nager's Duties and Responsibilities Yes

%Il4V 1%

Conti ol Soction Yes t".;a:it" Engir leering Section Yes auri'ail!ance Section Ies I

C. 'a.it.,

!+q.l occrnent Section I

The Ql Program for SQN will not be ln place until after plant etartup.

BFN'e Ql Program le In place and tunotlonlng.

OLIALITY IMPRO VEi"/EiVT (OI)

PROGRAM The Gl or ganization

@as assigned specific r esponsi bi li ti es vhi ch include the folloui ng.

0 6/oni tor G'vali t Performance o Guali ty Trending Program implemented; Periodic Repor ts Issued.

~ Trend analysis performed routinely (ll to date/

'"/orA '!i th Line i"1anaoemen'o::u"-".-

Performance Acti on Teams (5J ini tiated and typical problems resol ved.

o Socket veld fi tup conflicts between

codes, dr awnings, and NOE cri teria.

~ Guali ty questi ons (iZ) concerning RHRSA'ump installati on resol ved.

~ Welding problems (Electri cal Modi ficati onset resol ved.

~ High ~orkplan rejection rejection rate has deer eased over 50$.

..oo ause

.~n~~~ Y.. y',~s'ess'ment

~ Eight Root Cause AnalysisAssessments

opened, varuni ng.

~ J.

Plan vari tten and issued.

~ 0

Corrective Action Program I 1A.jOR EI.EI"1ENTS OF

. CORfiEi.. I I'=: ACTION PROGRAM INCLUDED AT SQN COMMENTS

. t,l.>>> ~>genlent Reviewer Responsibilities Yes i(~.-;;o:isiol~

.r gani"ations Responsibilities Yes F.- c.:-s tiara (R~n>+dial Corrective Action)

Iiiqu'r -n ion ts (Recurrence Control)

Yes C

~i 'ncl Is Is I lftllcotlorls Yes l.ive A tion Approvals Yes

i I..i."ion of Coi rcctive Action Yes l.ianagement I'r.);.l i< >g ~1 i ending

~.>>la::>>.)nca 1 ags Ycs Ye=s Yes SON is not placing non-coi>forming togo on all hardwarc-rclatcd items.

PIECE PARTS REPLACEMENT PROGRAM BROWNS FERRY NUCLEAR PLANT NRC PRESENTATION BETHESDA, MD SEPTEMBER 15, 1987

TECHNICAL ISSUE e Problem TVA's procurement. program could allo>'reviously qualified equipment Lo be degraded by purchasing replacement.

components and parts as commercial grade, mthout. documentation of its qualificaUon and without. adequat,e dedication of t,he it.ems by TVA.

o fdentified by TVA Nuclear Safety Review Staff reports, R-84-17-i%'S, I-83-13-i%'S, and 8-85-07-NPS.

NBC Inspection Report 50-327, 328/86-61.

I BFN problem is identical to Sequoyah.

o hsue covers three major areas:

~ Evaluation of previously installed piece parts

~ Evaluation af existing present inventory of piece parts for safety-related application

~ Procurement process control

0 PREVIOUSLY INSTALLED PIECE PARTS o Records search to deterrrLtne piece parts reylacemeo.t activity completed:

~ Approximately 500,000 records searched and sorted from. Cate of unit 2 startup

~ Approximately 100,000 records (MRs, TRs, and 575s) applicable to unit 2 Evaluation of 50.49 equipment established as pre-startup activity".

~ Approximately 5,400 components required to be evaluated

~ Approximately 1,000 completed to Cate

~ 46 Chips issued

~ 150 replacement items identified hy Eg Project and scheduled for change-out

~ Problems maizQy due ta paperwork I Scheduled.

completion date:

~ 50.49 equiymeat October 1987

~ Hemahmt, safety-related equipment March 1988

iNyZNTORY PROGRAM o EvaIuate present inventory of piece parts for safety-related application

~ Approximately 5,500 inventoried (lA Level I/II items to be replaced or evaluated.:

> Estimate a mirdmum of 500 items mll require evaluation

~ 50.49 piece parts estabIished, as pre-startup activity:

II 82 Of i37 itexns evaluated. to date

~ Scheduled completion date:

+ M.N piece parts December 1987 II Relnairmg safety-related equipment April 1968 o ConditionaQy released.

piece parts

~ Approxhnately 7,500 issues require evaluation none evaluated to date:

~ SchedUled completion date is April i988

PROCUREMENT PROCESS CONTROL

~ Qngoing Procurement EG reviews all purchase requests/stock reorders for appropriate gA level.

EG defines dedication process and initated dedication yaekage for all gA level II yrocurernents.

Corporate program for pre-engineered procurement specifications

aRovm Fiear/SEqUona COMpmISON Piece Part Ideatification BFN SgN HHMARKS Records search Computer maint-BFN maintenance eaance program activities not sort computerized i0 CFR 50.49 Pre-startup Pre-startup Seismic Evalu-ation A46 Pre-startup Number of Piece 46 Parts mith Pro-

. blems Identified Lack of procurement paper trail due to number of years since date of criticality (Sequoyah data ie more recent)

Total Number of Larger Items to Evaluate Longer maintenance history Inventory Eval-uation Yes Yes Procurement Pro-cess Control Yes

ENVI RONMENTRL QURLI t= I CRT X GN F'

C)&WR M C DMF' W X R C}N

EQ Program Comparison PROGRAM ELEMENTS INCLUDED AT SQN DIFFERENCES MAJOR MINOR NOTES Equipment Identification (10 CFR S0.49 List)

Identification of Category and Operating Times Informat>on Category b(2) Equipment Identification Environmental Parameter Draw>ngs Environmental Qualification Documentation Packages (EQDP)

Field Yer iiication of Installed Equipment Qualification Maintenance Data Sheets YES YES YES YES YES YES YES NO NO NO NO YES NO NO NOTES:

A. Some Brogans Ferry equipment is qualified to the DOR guidelines due to the age of the equipment and the vintage of the plant.

EXAMINE THE ORGANIZATIONAL WELDING PROGRAMS IN TVA. DETERMINE ANY REMED I AL ACT I ONS THAT MAY BE NEEDED r AND TAKE THOSE ACT I ONS NECESSARY TO ASSURE THAT FUTURE TVA PERFORMED WELDING ACTIVITIES ARE IN ACCORD WITH TVA'S COMMITMENT TO EXCELI ENCE IN ITS NUCLEAR PROGRAM.

VERIFY THAT THE TYA PERFORMED WELDING OF STRUCTURES'IPING SYSTEMS'ND OTHER SAFETY-RELATED PLANT COMPONENTS'HICH ARE CURRENTLY IN PLACE AT TVA'S NUCLEAR PLANTS ARE ADEQUATE TO MEET TVA. CODE.

AND REGULATORY REQUIREMENTS,

PURPOSE Et%~

THE PRIMARY PURPOSES OF PHASE I ARE TO:

0 ENSURE THAT THE TVA PROGRAM, DESIGN.

DOCUMENTS, POLICIES AND PROCEDURES CORRECTLY REFLECT TVA COMMITMENTS AND REGULATORY REQUIREMENTS 0

IDENTIFY AND CATEGORIZE CONCERNS/DEFICIENCIES IN THE WFI DING PROGRAM PHRS JJ.

THE PRIMARY PURPOSES OF PHASE II ARE TO:.

0 EVALUATE THE IMPLEMENTATION OF PROCEDURES 0

VERIFY THAT INSTALLED WELDMENTS MEET REQUIREMENTS OR ARE ADEQUATE FOR SERVICE o

CORRECT ANY PROBLEMS, IMPLEMENT CHANGES TO PREVENT RECURRENCE THE PRIMARY PURPOSES OF PHASE III ARE TO:

0 EVALUATE PROGRAM MODIFICATION EFFECTIVENESS 0

ISSUE FINAl REPORT DNE0 0632

WELDING PROJECT PHASE I ACTION PLAN 1.

REVIEW TVA WELDING RELATED REGULATORY COMMITMENTS 2.

VERIFY THAT Wi;ITtEN PROGRAM REFLECTS COMMITMENTS 0

DETERMINE THAT WELDING RELATED COMMITMENTS ARE REFLECTED IN DESIGN OUTPUT 0

DETERMINE THAT CONSTRUCTION AND NUCLEAR OPERATIONS PROGRAMS AS APPLICABLE REFLECT DESIGN OUTPUT AND QUALITY REQUIREMENTS 3.

ASSEMBLE WELDING PROGRAM QUALITY INDICATORS

( INCLUDING EMPI OYEE WELDING CONCERNS)

BY TYPE AND PLANT 4.

ANALYZE AND EVALUATE EFFECT OF QUALITY INDICATORS ON PROGRAMS 5.

ISSUE ADEQUACY STATEMENT REGARDING WRITTEN PROGRAMS TO IMPLEMENT/CONTROL WELDING DNE4 0632

FINDINGS OF SEQUOYAH AND BROWNS FERRY NUCLEAR PLANT PHASE I REPORT SQN WAS DESIGNED, CONSTRUCTED, AND OPERATED UNDER WRITTEN PROGRAMS THAT PROPFRLY REFLECT ki.LDING COMMITMENTS.

BFN WAS DESIGNED, CONSTRUCTED, AND OPERATED UNDER WRITTEN PROGRAMS THAT PROPERLY REFLECT WELDING COMMITMENTS.

DNEI 0632

WELDING PROJECT PHASE I I ACTION PLAN 1.

PERFORM WELDING PROGRAM IMPLEMENTATION AUDIT CONSTRUCTION PROGRAM IMPLEMENTATION OPERATIONS PROGRAM IMPLEMENTATION 2.

PERFORM REINSPECTIONS 3.

IMPI EMENT ANY ADDITIONAL REINSPECTIONS AND DEFICIENCY RESOLUTIONS (BOTH INDIVIDUALAND GENERIC CASES)

WELDING PROJECT WILL ISSUE PHASE II REPORT DNEQ 0632

2 UNITS 3 UNITS 333 PROCESS PIPE WELDS AUXILIARYFEEDWATER CAUSTIC BATCH TANK DISCHARGE COMPONENT COOLING CHEMICAL AND VOLUME CONTROL ESSENTIAL AIR ESSENTIAL RAM COOLING MATER INSTRUMENT SENSING LINES 391 PROCESS PIPE MFLDS EMERGENCY EQUIPMENT COOLING WATER DG DIESEL GENERATOR EECM RB REACTOR BUILDING EECM DIESEL GENERATOR STARTING AIR RHR SERVICE MATER RHR SYSTEM DRAIN PUMPS DISCHARGE DIESEL GENERATOR FUEL OIL SYSTEM FUEL POOL COOLING SYSTEM STANDBY LIQUID CONTROL SYSTEM INSTRUMENT SENSING LINES 15 HVAC SPIRAL WELDED PIPE DUCT MELDS 21 HVAC PIPE DUCT MELDS 50 STRUCTURAL COMPONENTS 70 STRUCTURAL COMPONENTS DNE0 0632

PJ'S~

COMPLETE COMPLETE EVALUATION REPORT COMPLETE COMPLETE COMPLETE COMPLETE COMPLETE COMPI ETE AUDIT INSPECTION EVALUATION REPORT COMPLETE COMPLETE COMPLETE COMPLETE COMPLETE COMPLETE COMPLETE SCHFDULED

- ISSUE 9/30/87 DNEQ 0632

0

EMPLOYEE CONCERN'IPE AND FITTINGS INSTALLED IN TVA SYSTEMS DID NOT ALWAYS MEET TVA COMMITMENTS PROCUREMENT WAS TO ANSI B31. 1 AND ASME SECTION I I I TVA REQUIRED ADDITIONAL NDE IN ACCORDANCE WITH ANSI B31.1 OR ASME SECTION III CLASS REQUIREMENTS IN SOME CASES MATERIALS WAS N01 ADEQUATELY CONTROLLED TO ASSURE MATERIAL BE.ING INSTALLED MET TVA REQUIREMENTS

DETERMINE EXTENT OF PROBLEM DEFINE PROGRAM TO CORRECT RESPOND TO EMPLOYEE CONCERN EVALUATE PLANT FOR COMMITMENT COMPLIANCE UPGRADE OR REPLACE MATERIAL NOT FOUND IN COMPLIANCE WITH TVA COMMITMENTS REVISE MATERIAL CONTROL PROGRAM TO PROVIDE CONTROL BY CLASS AS WELL AS NUMBER ASSURE TVA DRAWINGS CORRECTLY IDENTIFY CLASS BREAKS

MODERATE ENERGY LINE BREAK ANALYSIS COMPARISON

- SCRBFNNEB8510 IDENTIFIED LACK OF ADEQUATE DOCUMENTATION

- SIMILAR CONCERNS IDENTIFIED FOR SQN 3

WBN PROGRAM FOR BFN WILL BE SAME AS SQN

~ >

SCRFBNNEB8513RO IDENTIFIED THAT BROWNS FERRY NUCLEAR PLANT DOES NOT HAVE ADEQUATE DOCUMENTATION CONCERNING THE EVAI UATION OF FLOODING EFFECTS DUE TO MODERATE ENERGY LINE BREAKS (NELB) OUTSIDE OF PRIMARY CONTAINMENT.

MAJOR ELEMENTS OF BFNP MELB FLOODING STUDY MAJOR.ELEMENTS OF MODERATE ENERGY LINE BREAK FLOODING STUDY INCLUDED AT NO MAJOR MINOR NOTE SQN DIFFERENCE CHANGE CHANGE REVIEW PLANT ENGINEERING DOCUMENTS YES DESIGN CRITERIA PREPARATION IDENTIFICATION OF FLOODING AREAS YES YES WALKDOWN TO IDENTXFY FLOOD PARAMETERS YES PROJECT XNSTRUCTXON FOR FLOODING EVALUATION YES X

A X

B IDENTIFXCATION OF FLOOD SOURCES IDENTIFICATION OF SUBMERGED EQUIPMENT DOCUMENTATION OF DETECTION/ISOLATION METHODS CALCULATION OF LIMITING FLOOD LEVELS IDENTIFICATION OF SAFE SHUTDOWN METHODS YES YES YES YES YES NON-SAFE SHUTDOWN LOAD ANALYSXS YES CRACK EXCLUSION ANALYSIS YES STRUCTURAL LOAD ASSESSMENT YES REFINED STRUCTURAL ANALYSIS YES EVALUATION OF FLOOD EFFECTS FOR EACH ZONE YES PREPARATION OF FINAL

SUMMARY

REPORT YES DEVELOPEMENT OF RECOMMENDED CORRECTIVE ACTION YES VERIFXCATION WALKDOWN YES NOTES:

A.

The Project Instruction Mill Be Similar For Plant Specific Differences B.

The Project Instruction Will Be Similar Except For Plant Specific Differences

DEVELOP TASK SCOPING DOCUMENT INCLUDE SQN ELEMENTS

'EFINE BFN UNIQUE REQUIREMENTS ASSIGN TO TASK PERFORMANCE CONTRACTOR REVIEW FINAL REPORT IMPLEMENT RECOMMENDED CORRECTIVE ACTIONS

Oy

BROJyNS FERRY/SEqlJOYAE COMFARJSO."i ITEM Piece Part Identification REMARKS Records search

(.'nmputer maint-BFil maintenance.e enance program activities not

sort, computerized 10 CFR 50.49 Pre-st.artup Pre-start.up Seismic Evalu-ation A46 Pre-start.up Number of Piece 46 Parts mith Pro-blems identified Lack of procurement paper trail due to number of years since date of criticality (Sequoyah data is more recent)

Total Number of Larger Items to Evaluate Longer mahtenance history Inventory Eval-uation Yes Procurement Pro-cess Control Yes Yes

Distribution for Meetin Summar Dated:

October 6, 1987 Facility.:

Browns Ferry Nuclear Plant, Units l, 2 and 3*

Doc ket-Fi-1 e-g[ (

NRC PDR Local PDR Projects Reading BFN File J. Keppler/J.

Axelrad S. Ebneter S. Richardson J. Clifford J. Zwolinski J.

Stang G.

Gears J.

Donohew C. Jamerson OGC-Bethesda F. Miraglia E. Jordan J. Partlow R. Pierson R. Wescott J. llatt P.

Hearn P. Cortland R.

Hermann B.

D. Liaw G. T. Hubbard A. Ignatonis W. Little ACRS (10)

Hon.

M. Lloyd Hon. J.

Cooper Hon.

D. Sundquist Hon. A. Gore Dr. Henry Myers Mr. R. Kino, GAO P.

Gwynn C. J.

Heltemes, Jr.

C. Miller G. Felgate C. Ader F.

Combs TVA-Bethesda

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