ML20058M449

From kanterella
Jump to navigation Jump to search
Summary of 900727 Meeting W/Util on Site Re Plant Tour. Restart Status & Condition of Unit 2 Primary Focus of Site Tour.List of Attendees Encl
ML20058M449
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 08/08/1990
From: Ross T
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 9008100135
Download: ML20058M449 (31)
v • d • e


Text

%

Docket Nos. 50 259, 50 200, and 50-296

-)

LICENSEE: Tennessee Valley Authority (TVA)

FACILITY: Browns Ferry Nuclear (BFN) Plant, Units 1, 2, and 3

SUBJECT:

SUW.ARY OF MEETING WITH TVA AND SITE TOUR AT BROWNS FERRY NUCLEAR l n PLANT, UNITS 1, 2, AND 3 1 1

On July 27, 1990, NRC management from Region II and the Office of Nuclear ReactorRegulation(NRR)participatedinageneralsitetourandattendeda presentation by TVA at the BFN site. The purpose of the tour and presentation was to familiarize senior NRR Projects management, with newly assigned respon.

sibilities for TVA plants, with the BFN site and status of the BFN units. The restart states and condition of Unit ? was the primary focus of the site tour and TVA presentation. Enc osure 1 provides a list of the TVA and NRC attendees, i Enclosure 2 is copy of the handouts utilized during the presentation by TVA i Original signed by +

Thierry M. Pa 4, Project Manager Project Directorate 11 4 Division of Reactor Projects . I/II ,

Office of Nuclear Reactor Regulation -)

D

Enclosures:

1. List of Attendees  ;
2. Presentation Handouts cc w/ enclosures:

See next page-0FC :PDil-4/LA :PDII-4/PM :PD1 -4/D  :  :  :

......:................:..............:., s.........:..............:..............:........... ,

FH don  :  :  :

NAME:MKrebsh.(.......::TRoss

......:..)..... .......[h....:..............:..............:..............:...........

DATE :8N /90 :8/g/90 :8/3/90 RECORD COPY ,l 0 0E" M Name: BFN HTG 7/27_ gI 00s10o133 900 sos gg, ADOCK 0500 f

(/h

^^ ~ ^^

m',

.I j

CC:

Mr. Marvin Runyon, Chairman Mr. O. J. Zeringue, Site Director

Tennessee Valley Authority Browns Ferry Nuclear Plant ET 12A 7A Tennessee Valley Authority -

400 West Sumit Hill Drive P. O. Box 2000 Knoxville, Tennessc-e 37902 Decatur, Alabama 35602 Director Mr. P. Carter, Site Licensing Manager Tennessee Valley Ai:tho-ity Browns Ferry Nuclear Plant ET 12A 11A Tennessee Valley Authority 400 West Sumit Hill Drive D. O. Box 2000 Knoxville, Tennessee 37902 Decatur, Alabama 35602 Mr. John B. Waters, Director Mr. L. W. Myers Plant Manager Tennessee Valley Authority Browns Ferry Nuclear Plant ET 12A 9A Tennessee Valley Authority 400 West Summit Hill Drive P. O. Box 2000 Knoxville, Tennessee 37902 Decatur, Alabama 35602 '

Mr. W. T. Willis Chairman, Limestone County Comission Cnief Operating Officer P. O. Box 188 ET 12B 16B Athens, Alabama 35611 400 West Summit Hill Drive Knoxville, Tennessee 37902 Claude Earl Fox, M.D.

State Health Officer General Counsel State Department of Public Health Tennessee Valley Authority State Office Building 400 West Summit Hill Drive Montgomery, Alabama 36130 ET 11B 33H Knoxville, Tennessee 37902 Regional Administrator, Region II U.S. Nuclear Regulatory Comission Mr. Dwight Nunn 101 Marietta Street, N.W.

Vice President, Nuclear Engineering Atlanta, Georgia 30323 Tennessee Valley Authority 6N 38A Lookout Place Mr. Danny Carpenter 1101 fiarket Street Senior Resident Inspector Chattanooga, Tennessee 37402-2801 Browns Ferry Nuclear Plant U.S. Nuclear Regulatory Comission Dr. Mark 0. Medford Route 12, Box 637 Vice President and Nuclear Athens, Alabama 35611 Technical Director Tennessee Valley Authority Tennessee Valley Authority 6N 3BA Lookout Place Rockville Office Chattanooga, Tennessee 37402-2801 11921 Rockville Pike Suite 402 Mr. Edward G. Wallace Rockville, Maryland 20852 Manager, Nuclear Licensing and Regulatory Affairs Mr. Oliver D. Kingsley, Jr.

Tennessee Valley Authority Senior Vice President, Nuclear Power SN 157B Lookout Place Tennessee Valley Authority Chattanooga, Tennessee 37402-2801 6N 38A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801

-_ _. _ _ _ . _ _ , -- . . ~ , . _ _ . ,

.. . w 2,.

j t

i i

Meeting Sumary, Memoranda for Trip Reports or Site Visits i ee= Dedet'f.He sa i NRC'PDR Local PDR F..Miraglia (

J. Partlow i S. Varga G. Lainas 1 F. Hebdon S. Black ,

M. Krebs T. Ross l' D. Moran I' R.-Borchardt OGC E. Jordan I B. Wilson M. Callahan C. Patterson I ACRS(10) I BFN Reading File j

1 h

4 4

i r

h

4 0 ENCLOSURE 1 >

Attendees at the TVA Presentation of July 27, 1990 i TVA <

t J. Bynum, V.P. Nuclear Power Production M. Medford, V.P. Nuclear Tech & Licensing N. Kazanas, V.P. Nuclear Assurance '

O. Zerengue, Site Director ,

L. Myers, Plant Manager H. Weber, Manager Engineering & Modifications P. Carier, Manager Site Licensing B. McKinney, Tech Support Manager J. McCarthy, Licensing Supervisor D. Porier, Asst. Maintenance Supt.

J. Carlin, Asst. Operations Supt.

NRC J. Partlow, Assoc. Director of Projects G. Lainas, Asst. Director of Projects - Region II B. Wilson, Branch Chief TVA Projects ,

S. Black, Deputy Director of Project Directorate II-4 T. Ross,-Project Manager M. Calahan, Congressional Affairs C. Patterson, Senior Resident Inspector l

1

. 1

- 4 ENCLOSURE 2

. TVA - NRC Meeting I

Browns Ferry Nuclear Plant Unit 2 Restart i

i l

4 Ju y 27,1990 a

J.R. Bynum j M.O. Medford i O. J. Zeringue H. H. Weber L. W. Myers Rev. 7/26/90

+ ,

. i i

AGENDA  !

1

l. Introduction and Overview......................lke Zeringue  ;

II. Schedule / Restart Issues..........................lke Zeringue l lil. Professional Work Ethics.........................lke Zeringue IV. Licensing Restart issues......................... Mark Medford '

V. Modifications Improvements................. Henry Weber

, i VI. Plant Readiness................................................Lew Myers

- S POC............................. ........................................ Britt McKinney l , ,

Maintenance........................................................ Dan Poirier l

- Opera + ions............................................................Joh n Carlin Procedures..........................................................Lew Myers

- Technical Specification implernentation

- Fire Protection ,

Vll. Power Ascension Test Program..:.....lew Myers Vlll. Operational Readiness.............................. Joe Bynum I

IX. Close.......... .................................................................. lke Ze ring u e l

)

l l

~ - < - . . ~- ,,,,,..-.....--,,,...-...,,,,v.,, - - - , - - -- - , ~ . - . , , , , , .,...y.,.....~..,,- , . + . ,

1 i 4 d l

1. INTRODUCTION AND OVERVIEW  ;

j m

. l

+

Introductions  !

t I

Organizations / Staffing Levels i l-i t

I i

.I

('

k i

h

, 'to

  • h 9 I

+

d(f' j.,

1 1

1

)%_

4

. _ . _ __ _ _ _ _ . - . . ~ - _ - _ _ . __ _ _ . ._ _ . - _ . . . _ _ _ . _ _ _ _ _ _ . . - _ . _ _..-___.m

l .

i t

BROWNS FERRY NUCLEAR PLANT ~

i

SUMMARY

LEVEL ORGANIZATION CHART ,

1 Vice President n' Vice President L Vice Psesident ' Vice President j NuclearTech & '

Nuclear Power - Nuclear . Nuclear -

Licensing' Production  : Engineering Assurance l M.O.Medford : J.R. Bynoni D.Nenn ,

N.C. Kazanas

r. ,

Bsowns Ferry Site Diaector 1

- O.J Zeringue 1 I I I

r .
.

, r ., r. , r. ,

m Financial Materials & -

Managerof ;9 Site Psegraris  : BFN Plant , E- ' - 'Qg, ' - - & Site Quality l Site Licensing & Support Mgr j Manager g g,. ,p,g Manager l P.P. Carier gg, g,,,g,,g S.H. Rudge L.W. Myess

. R.D. Hicks H.H. Weber G.G. T-

! rm t.

m Am t  ; e C <  ;

1

, V > V %m p.L

r w ;.,9 r,. - ., r

.h r- .

., r. m r m .r- -

.I ,

Maint.k {hN= , I'"I w Pselect h M g net Meds l  : Manager . Manager "*"'8 '

"*"'8

JA.W. SorreB M.E. Hesseu "'8

-3.T* -

_ J.Hotoon H.E.Crister R.W. Jelensen

. J.M.Cesey McKinney ran

-ran ren rsn ru rw rus v )c i c e a w w an 4

r v v

r. W w w /c w

-- mme m.peet,ss= in/s, chngessim m/sp 4

4 8

. f i

1. INTRODUCTION AND OVERVIEW  :

i 1

S':a"ing Leve s -

Actual Actual Actual Planned .

_239._ 200 7mo 10/90  :

Plant 1718 1430 1323 1346 Nuclear Engineering 790 674 501 282  !

L Modifications 861 1207 928 464 Other

  • 940 7ss a s73 Total 4309 4096 3440 2665-l.

a

. ~ - ,

Other Licensing, includes and Human Training,ResourcesQuality Assurance, Site Security, I

l t

b y

e 't -<-----r,--.. ..,--**--..,-+<.,...m,-.-......--*-,.--.-,=------w- ,-~.....----w--.~.-

4 II. SCHEDULE / RESTART ISSUES Sc1edule S i?page Added Scope 02/14 - Higher Modification Rate (75%) Than Anticipated

- CRDH Lateral Supports

- TMI Items Moved From Cycle 6 to Cycle 5 SPD3 Phase 1 ADS Accumulators -

PASS

- Cable Pulby Problem From Watts Bar g

- 75 Design Changes Added to the Outage Since Jan.1,1990

^

.Changeout of 12 LPRMs

- Furnace Weld Pipe

. EQ Program ,

Multi-Contractors Resul ting in Many Passoffs of Some Problems ,

- Cable Qualification Issue .

- Qualification of HVAC Equipment

- Electrical Switchgear Qualifications

- EnvironmentalCalculations Reassessment of Manpower and Duration Estimates Based on Conceptual Design Information

- Approximately 40% Underestimation of Work Based on Preliminary Design

  • Low Productivity Rates

l

~

II. SCHEDULE / RESTART ISSUES .i I

a Potentia Sc1edule Impacts Work Completion

- Work in Drywell 09/02

- systems for support of Fuel Load 10/13 ,

- Remaining systems 12/04 Outage Mi estones

- Fuel Load 10/13 to 10/21

-lLRT 11/10 to 11/12

- Hydro' 11/15 to 11/25

- Completion of Licensing. Items 11/26 i

- Criticality 12/05 t

- Close Breaker 12/24 ,

L Remaining TVA Assessments '

- Operational Readiness Team Review. --

10/90 l - SMART (Senior Management Auessment Review Team) 11/90 L - Power Ascension Test Program 12/05/90 to 2/11/91 1 (Management Hold Points)

..~---,_.,..,--,.,--,,-c -.,w. , - -.3e* - --- , - ~- + - = - + - - --

)

.+

111. PROFESSIONAL WORK ETHICS l

)

l i

i Operational Mentality / Team j 1

- - Accountability l L

Defined Expectations l Personne Error L

?

t F

5

IV. LICENSING RESTART ISSUES Coma eted NRC Inspections 1 - Design Baseline & Verification 6/89

- Tech Specs 10/89

- REP 12/89

- ElectricalIssues 12/89

- Appendix R/ Fire Protection 5/90

- EQ 6/90

- Quality Verification 6/90

- SALP 6/90 Remaining NRC Insaections

- ATWS- 7/23*

- Seismic (90 % Implem6ntation) 8/31*

- TS Implementation 10/01

- Reg Guide 1.97 10/15  !

- Operational Readiness for Restart' 10/22

- Other Schedule Driven inspections

s IV. LICENSING RESTART ISSUES Pro lect Chart NRC Inspections .

Tech Specs

- 12 Restart Tech Spec Changes Submitted &

Awaiting NRC Approval

- 3 Restart Tech Spec Changes to be Submitted by 8/06/90 NRC Meetings

- NRR Site Visit 7/27/90

- ACRS Subcommittee 9/24-25/90

- ACRS Full Committee ,

11/13/90

- Commissioners Briefing Late 11/90

- NPP VOLUME 3

- 21 Restart items Remain Open

- Program Completion will be reviewed by SMART (TVA Management) &.NRC Pnor to

. Restart

k, IV. LICENSING RESTART ISSUES l

l

-)

Pro.'ect C1 art (cont?

l Items ':o be Closed by Region ll I Closed WITH TVA WITH NRC (6/1/89-7/15/90) 1 Inspector Findings

(

Violations 20 (27) 11 62 (53)  !

URis 7 (10) 8 72 (67) ,

IFis 13 (23) 7 92 (82) ,

j LERs 31 (42) 1 108 (95) ,

TOTAL 71 (102) 49 334 (297) l i

( ) As of 6/15/90 4

. t.

r h:

.. . . . ~ . . . . . _ _ . . _ _ _ . . _ , . . _ _ _ . . . _ . . . _ . . _ . .

e < ,

i V. MODIFICATIONS IMPROVEMENTS  !

Accomplis 1ments

- Changed Mentality from Construction to.

Modifications

- Restructured and Upgraded Top Level of  !

, Modifications

- Set Unit Rates on Par With Nuclear Industry

- Raised Productivity from 30 to 46 %

- Improved Procedure Efficiency.& Ability to Perform

- Promoting Accountability Down to Working Level l-

- Known Status of All Work to Go

- Personnel Error Reduction ,

Final walkdown by Foremen & OC in Workplans

[ -

Further Training of Crafts and Foremen in Procedure

l. Compliance Lower Rejection Rates .

- Performed incident Investigations on Significant Mods Events Areas for Impiovement

- Procedure Compliance 1

- Productivity increase

, . , - . . - , - . ~ , , - - . . , - - . . .-m_._ ,_ _ _ _ _ _ - _,.__..- -______ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ ____._.____.._

. w .

a 4

VI. PLANT READINESS Svs:em Pre-Oceraaiitv C1ec< is"

'.SPOC1 l Systematic Method to Ensure Open Work Items 'nd i Outstanding Programmatic items Affecting System l Operability are Resolved Prior to System Return to Service Integral Part of the Site Managed Operational

~

Readiness Program l

- Necessary due to the Volume of Work and Issues Associated i i

with Restart  ;

Each SPOC Addresses Open items Affecting:  ;

- Testing ,

Modifications

- Maintenance l

- Licensing (including NRC commitments) -

- Procedures

- Design Completion l

- System Configuration - --

U

- Walkdowns l

l

)

b I

I i

3

=y..

VI. PLANT READINESS l

l J

Maintenance Accomplis 1ments Management Changes  !

Accountability

- Specific Performance Indicators i 1

Computerized Maintenance System

]

1 Backlog Reduction ,

Maintenance Team Inspection L -

Scheduling [

Communications j

\

l Areas for Improvement Planning .

q Parts Availability . - -

Trending  ;

In-process Work identification ,

i l

I--_._.u_____m___m , - . -, ,, ..,-. - , - , , - - . ~, . - . ,.,.,_..,- ,, ,...

Y VI. PLANT READINESS i Oaerations  !

l

  • Accomplishments j

- Improved Quality of Licensed Operators

- Operator Requalification Exams  !

- Ownership'- Reclaiming Systems f

- Senior Management involvement in Training l

L - Incident Investigation  :

i  :

  • Areas for Improvement l

- Continued improvement in Command and Control l

- Operator Experience Level '

- Continued Improvement of incident Investigation 4 Recent Plant Operating Experience

. Utility Observation by BFN Licensed Op,erators

- Senior Mgmt on Shift During Start Up i Most Experienced Personnel on Unit 2 I

i e

s .

l VI. PLANT READINESS .

, . i L .

Procedures - Adequacy and implementation Technical Content l

- Technical Reviews .

- Improved Verification and Validation Process  ;

  • Programmatic Issues  ;

- Standards for Conduct of Test ,

- SI Reviews

- Senior Management independent review  :

- Peduction of Non-Intent Changes.

Implementation

- Defined Expectations l

- Ownership of Performance and Cognizant Engineer '

- Sensitivity to Procedure Adherence"

- Lower Threshold of incident investigation-t J

--w.-w.e-e, -w-, .v,- aw.,., , ---,mww-,- e-,,~,w,,- ~,<msev-

i VI. PLANT READINESS I 1

Technical Specification im a ementation  ;

LCO Trac <ing Compensatory Measures System Return to Service Limited Use of Tec1nica Speci"ica: ion l Interareta': ions l

l -

l l l' .

l t i

L ...

L

'r,,. ., _

. j

. i

~

VI. PLANT READINESS . +

r  ;

Fire Protection Im arovements Technical Specification Im alementation i

- LCO Tracking Fire Protection Operators Assigned to Operations Standards Estaa isled by Oaerations Supervision Fire Protection System Engineer Assigned to Tec1nica Support 4

g *% 9 0

1 l.

l

.e, w .

i

?

I Vll. POWER ASCENSION TEST '

. PROGRAM t

i 5

Oblectives

- Verify the with Conjunction SafetheShutdown Restart Test Design Program Basis Req)uirements (in Demonstrate Functionality and Control System Tuning 1

Bases for Deve opment

- Design Basis Verification Program (DBVP)

I

- Revised FSAR Content

- RG 1,68 Review (NTOL Criteria) *

- Pilgrim and Peach Bottom Program Content

- 3 Major Test Plateaus -

- 32 Tests after Fuel Load

- Integrated Safeguards Test Prior to Fuel Load c

- 7 Management Hold Points -

f e

0

- ,~---.--_.---_______.___.a_--...,_,-n,,-w,

,,.. .,n..,_.,n,_,.. - - . . , , . , , _ . -. .. ., . . . . ._, . , - ., .,v.,n., ,-..

l 1

l Vll. POWER ASCENSION TEST l PROGRAM i l Management Ho d Points

1. Prior to Withdrawal of Control Rods for initial Criticality, Completion of Open Vessel Testing
  • L 2. Prior to increasing Reactor Vessel Pressure Above Atmospheric, Completion of Training l Criticals  :

1

3. Prior to Placing the Reactor Mode Switch In \

the Run Position

  • l
4. Prior to Exceeding 25% Power *
5. Prior to Exceeding 55% Power *
6. Prior to Exceeding 80% Power
7. Completion of Power Ascension Test Program
  • NRC Hold Point ,

7 1

[

a ~ . - - .

.+ -

  • *[ .

l 1

f i

4

POWER ASCENSION MILESTONE CHART .

-l MANAGEMENT HOLD POINTS 11D 7 .

j RFwPUMP ,

TRe . TURBNE 120 -- REORC RUMBACK '., mp i

100 - - REORC '. '

l TuNec e e_,  :

n  ;

80 .

resonnisniumem 6 m> arp n

v. +T

. P .

g

~_e g, m,,

... . - . m. .-.,- _ ,:  :

.c  ;

m O 60 _ _

m; 1 5 w&,,., ~,

o:~= . .n< .+. ~gna .amo - -c_. ,m- . ;. . xx e t

W INmAL& HPCWRCICMENG -@ M ,'N NO W U 1 1 . .

m,. 44.- - - resonnw wm.m .x, ., + .+ . u.s-  ;

E camcats .

g

.Ma :niunse w w a sre,n

. ,.w.,,,

.n

4 sw em s., < - a.wa
. e =- -

R 20 -

w. a w.w.m. - b.' ...,,w=v ,~ , mu. ~mwwwwww&W4

..n. e .vu 2s

. m m,.

m= wn.....a_.<*

3 ,,:

wwwwuw...v~ wsum. me m=?x e' . .+._

e ,n ps--p s.,c;rc . = ;e--s < .-.-.a --

x.. .a. r..:- -

1 !2 -

-! ' 3 [~kytiRBUEISwisii[: i g- . ijjfgHPCORCCJUNBGygg,. w. =.-..%df.[g..,

p 7 f...m ................'a:A a a aa a am . m a mz.m awn a li 'm A e A ~ a a,.1.a & a e &

t aa Aad-'A eaA-a aA A Il

. . .. . .. . . . . . . . a

. a. .. . .. . ....'eA'aa5'eaA. . . . . . . . ..' & ' s a & ~ A ' A. .' &

..a .E ..... . A.a. . A.

i

{

0 4 8 12 16 20 24 28 32 36 40 44 48 52 56 60 64 68 i DAYS 1

5 4

h i

t I

r f

. [

w. - + . - y -r w -# . , , , .
m. . , _,-w f ._.,. _ _ _ _ _ _ _ . _ _ .

_ _ _ _ _ _ , _ _____,______________________________,___.,____,._,1

POWER ASCENSION TEST MATRIX COMPARISON .

4 RG 1.68 - BROWNS FERRY - PILGRIM - PEACH BOTTOM '

SHEET 1 OF 2 i i

~

! . i i

BROWNS PEACil . i

. TEST DESCRIITION RG 1.68 FERRY PIII; RIM BOrITOM  !

! CHEMISTRY & RADIOCHEMISTRY X X X X l 3

RAD PROTECTION X X X X l COREIDAD X X X X FULL CORE SDM X X X X

, GD X X X X i SRM X X X X IRM X X X X j i

LPRM CAL X X X X  ;

APRM (CONSTANT HEATUP) X X .Y ,

APRM CAL X X X X l PROCESS COMPUTER X X X t RCIC X X X X HPCI X X X X l WATER LEVEL MEASUREMENTS X X X X j SYSTEM EXPANSION X X CORE POWER DISTRIBUTION X X X X CORE THERMAL LIMITS X X X X  !

PRESSURE REGULATOR X X X X FEEDWATER TUNING X X X  !

FEEDWATER PUMP TRIP X X X MSIV X X X X SRV X X X X ,

TURBINE TRIP X X X b

.w.,

e m +. ., w,-, r ,, . -e.. -e_

  • _ _ _ _ -, y _. __- __-w_ __w_ -
  • _._ .__ _- _-

av POWER ASCENSION TEST MATRIX' COMPARISON -

-l RG 1.68 - BROWNS FERRY - PILGRIM - PEACH BOTTOM SHEET 2 OF 2  ;

e t

' BROWNS PEACil i

'EST DESCRIPTION RG 1.68 FERRY PILGRIM DOrITOM SHUTIJOWN OUTSIDE CONTROL ROOM X X- X RECIRC 1UNING/ RUNBACK X X X RECIRC PUMP TRIP X X

! DRYWELL TEMPERATURES X X X RWCU X X CONTAINMENT INERTING . X  !

RECIRC FLOW CALIBRATION X- X X

) OFFGAS X X X RPV INTERNALS VIB- X .

l RHR SYSTEM X i i CORE POWER VOID MODE RESPONSE X

! TURBINE TRIP WITHIN BYPASS X

! LOSS OF OFFSITE POWER / TURBINE TRIP X i i

i ,

\ .

i i I

i

_ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ ~ _ _ . . - _ _ _ _ _ _ _ _ _ _ - _ __ _sv .~ e.,. v,--ee..-r ,.e...-

<,--rw .. -w--v.ew-ie.e ==-+=mv.--a w ev m- cw-- v - er-*==

e

...o .

..  ; Vill. OPERATIONAL READINESS .

1. Operational Readiness Review (ORR) Team 2
  • Objectives Assessing Readiness of BFN Unit 2 for Restart j
  • Team Members Independent of BFN Management (8 members)

-- Two TVA Employees

- Five were Members of the SON Unit 2 ORR Team (

p Six were Members of the SON Unit 1 ORR Team p

  • Phase I Results - 6/89 -

i Operations

- Conduct of Operations not at Desired Standards j - Divis' ion of Responsibilities in Control Room not well Defined

=

- Sensitivity to Reactor Safety factors not at Desired Levels T - Actions to improve AUO Supervision not Effectively Addressed

- Walkdowns by Managers anc ' .TNisors not Effective

{ -

- Admin.istrative, Operating and Work Procedures are Deficient

- Maintenance

- Work Packages Need Adequate Work Instructions for Personnel

, - PMTs did not Consistently Verify Maintenance Performed Correctly.

T

- Managemoni involvement Needed for PM Bac6tiog

_ t/endor Technical Recommendations not Timely .

1

r ;o , -

Vill. OPERATIONAL READINESS

. 4 i

Phase l Results (cont)  !

- Chemistry PASS Procedures, Training and Lab Techniques Need

, improvement Other ,

0 Emergency Preparedness Exercise Lacked High Standard of  !

Performance  !

j Nuclear Experience Reviews & Lessons Leamed Lack Attention

-1 a

Corrective ~ Actions Response Revised to Address Senior VP i Comments  :

Phase 11 Results -3/90 L

- ORR Results ' -

]

Standards of Performance inconsistent 1 Quality of Procedures Lacking -

Maintenance Planning and' Preventive Maintenance Need -i

- Attention  !

Training Effectiveness Affected by Poor Communication  !

Occupational Safety Practices Need Significant Improvement j Phase Ill

- Independent Review of Operations and_ Work Control

' l 9

. - .- - . . _ - - . _ - .. . - . . .._. . .- . ._ _. .-. ._- - .~ . . _ . - . . . . . - . _ . . . .

l VI'I. OPERATIOkAL READINESS

- '2 k SMART (Senior Management Assessment Review Team)

' Objectives-

- Adequate Resolution of NRC Commitments Completion of Program to Establish Operability of Systems.

Implementation of Self Assessment Program Evaluation of Independent Review Results Evaluation of Performance Trends 3

- Chaired by VP Nuclear Power Production, and Composed of. '

VPs Reporting to Senior VP Nuclear Power 2

4 e

}

g,

. . __-______m_____- _ __ _ _

.y.

l H

IX. CLDSING REMARKS .

~1 TVA and NRC Staff are in Agreement on Resolution I of Technical Issues l 4

Flerdware Fixes identified and in Progress 1 Piant Organization is in Place to Support Operation l Reinforcing Operations' Focus with Systems. Return  !

to Service '

Comprehensive Review of Operational Readiness-4 4

1

. ~- -

i l

l A

Retrieved from "https://kanterella.com/w/index.php?title=ML20058M449&oldid=3564635"