ML20133F901

Summary of 850611 Meeting W/Util,General Physics & GE in Bethesda,Md Re Dcrdr Program.Agenda,List of Meeting Attendees & Viewgraphs Encl

ML20133F901
Person / Time
Site:	Hatch
Issue date:	08/01/1985
From:	Rivenbark G Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8508080476
Download: ML20133F901 (34)

Text

, - - . - -

AUG 1 1985 Q Dockets Nos. 50-321 and 50-366 LICENSEE: Georgia Power Company FACILITIES: Hatch Units 1 and 2

SUMMARY

OF JUNE 11, 1985 MEETING WITH GEORGIA POWER COMPANY ON THE DETAILED CONTROL ROOM DESIGN REVIEW PROGRAM A meeting with Georgia Power Company (GPC) representatives was held in Bethesda, Maryland on June 11, 1985 to discuss further detailed information concerning the Hatch detailed control room design review program. The agenda for the meeting and discussion slides as well as a list of meeting attendees is enclosed. The staff discussed the possibility of an in progress audit of the implementation of the plan in December 1985 and indicated it would send a detailed agenda for the audit prior to that time. ,

8-J',D,L'l C T.G E T George Rivenbark, Project Manager Operating Reactors Branch #4, DL

Enclosures:

As Stated cc w/ enclosures:

See next page ORB #

GRi erfbark;cf 8///85 8500000476 050001 PDR ADOCK 05000321 p PDR

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MEETING

SUMMARY

DISTRIBUTION

! Licensee: Georgia Power Company i l

1

• Copies also sent to those people on service (cc) list for subject plant (s).

I C nacket F h j NRC PDR

.! L POR <

. ORBf4 Rdg ,

! Project Manager - GRivenbark i JStolz BGrimes (Emerg Preparedness only)  !

OELD EJordan, IE i ACRS-10

} PMorriette l NRC Meeting

Participants:

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JUNE 11, 1985 MEETING WITH HATCH 1/2 ON DCRBR PROGAM i i i Name Affiliation I

i G. Rivenbark NRC/DL f l

S. Saba NRC/HFEB t

4 i R. Baker 904-526-7016 GPC-Nuclear Operation ,

1 1 P. Springer GPC-Nuclear Operation i

j D. Tennant GPC I/C 1

j D. Burgy 301-997-6201 General Physics 1

J L. Schroeder 301-997-6211 General Physics ,

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) B. Newell General Electric Representating Carolina Power & Light Co.

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20RGIA POER COWANY 2ERAL PHYSIG CONORATION A 2 NDA NRC METING ON PIAlff E.I. HATCH

DCRDR AND REIATED PRGIECTS i

June 11,1985

1. DCRDR Overview i

2. E@ Backgrotmd l 3. Qualifications and Structure of the DCRDR Review Team

4. Function and Task Analysis J

5. Control Room Inventory

6. Control Room Survey

7. Assessment of NEDs

8. Verification That Improvements will Provide the Necessary Correction

9. Verification That Control Roon Improvements Will Not Introduce New EDs

10. Coordination of the DCRDR With Other Improvement Programs I

1 a

4

e ATTACHMENT 1 EXPECTED

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REVIEW TEAM lw[ , l [-  %

INVOLVEMENT IN N DCRDR ACTIVITIES Human Syst. I&C Oper. Licensing Factors Engin. Engin. Spec. Engin.

Specialist o PLANNING (orientation courso) X X X X s

o OPERATING EXPERIENCE REVIEW (Interviews & LER Survey) X X X o CONTROL ROOM SURVEY X X o SYSTEM FUt3CTION DESCRIPTIONS X o TASK ANALYSIS X X X o VERIFICATION X X X o VALIDATION X X X o ASSESSMENT & IMPLEMEllTATION SCHEDULING X X X X X 0

SUMMARY

REPORT (Draft) X l

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GENERAL PHYSICS C'ORPORATION COLUMBIA, MARYLAND lt4, 'i~ lJ ATTACHMENT 2 PROPOSED DCRDR TEAM ORIENTATION OUTLINE GEDRGIA POWER COMPANY PLANT HATCH Time Topic Chapter DCRDR TEAM ORIENTATION (DAY 1)

9

00- 9:15 Introduction and Objectives 9:15-10:00 Synopsis of DCRDR project 10:00-11:00 NRC Requirements and recommendation 2 11:00-11:15 EPRI/INPO Programs and Research 3 11:15-12:00 Lunch j 12:00-12:45 Introduction to Human Factors Engineering 1, 12:00- 1:30 Stress in the Workplace 6 1:30- 2:30 Maintainability 9 2:30- 2:45 Break 2:45- 3:45 Introduction to Systems Analysis Techniques 4 3:45- 4: 15 Practicum on Control Panel Design DCRDR TEAM ORIENTATION (Day 2) 8:00- 0:30 Overview of the Control Room Review Techniques 11 8:30- 9:00 Operating Experience Review 9:00-10:00 Control Room Survey 10:00-10:15 Break 10:15-11:15 System Review and Task Analysis 4 11:15-12:00 Lunch 12:00- 1:00 Verification and Validation 1800- 1:30 HED Assessment l

1:30- 2:30 Implementation 2:30- 2:45 Break 2:45- 3:30 Practicum Discussion 3:30- 4:15 Implications for Hatch and Puture Issues From text " Applied Human Factors in Power Plant Design and Operation,"

General Physics Corporation i

e ATTACHMENT 3 Flow Chart of Decision Process for Verifying Equipment Suitability For every tese en she took enelyses. ver-6% est the sowement asocited a matense te meet the esmends of emer-pacy sentinencies.

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INFORMATION . . .

PRESENTATION TO THE NRC ON GEORGIA POWER CO - PLANT HATCH EMERGENCY OPERATING PROCEDURES TO BE USED DURING CONTROL ROOM DESIGN REVIEW O

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b USE OF SYMPTON ORIENTED FULLY INTEGRATED (SOFI)

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FOR LOSS OF PLANT SERVICE WATER

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HOW UPGRADE E0Ps I

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- EMERGENCY PROCEDURE GUIDELINES (EPGs) l - HATCH IMPLEtiENTATION TO DECEllBER 8,1983 - REV 3 (NRC SER)

~~

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' "~~ ~ ~ MID 1983 TTEAM FORMED' .

- PROJECT MANAGER (SR0 LIC)

- 6 ENGINEERS (SRO CERTIFIED)

APPROACH TAKEN SAME AS AT BRUNSWICK - FULLY INTEGRATED E0Ps l IN FL0ll CHART FORMAT

- N0 tiEtiORIZATION

- CONSISTENT PESP0flSE AM0flG OPERATORS

- FLEXIBLE RESP 0flSE ,

- FAST REACTION TIME - NO FUMBLIllG F0P/IN BOOKS

- ALLOWS AMPLE RECORD KEEPING -

EllD PATH MAtlUAL - AFTER PROBLEM IS BOUNDED

- NO FINGERS IN PAGES

- GRAPHS PRINTED

- CHECK 0FFS -

- C0tlTAINS BULK OF EPG',

PLANT HATCH SitiULATOR

- 1900 NAthl0VP.S, 400 0F WHICH WERE GPC INSTRUCT 0P,5 AtlD LICEllSED OPERATORS

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_HOW UPGRADE E0Ps (Continued) .

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' SUPPORTING DOCUMENT / PROGRAMS -

COMMENTS ..

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PROCEDURES GENERATION PACKAGE '(PGP). ~. ~. .' 'EOP TEAM DEVELOP - - -

,' PLANT SPECIFIC TECHNICAL GUIDELINE PLANT QA REVIEWED l

(PSTG) SUBillTTED TO NRC MAY,198Il -

WR I TER '.S _G U I DE - -

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} TRAINING PLAN g

Y t Y PLAN PSTG APPENDIX A, B  ; ; ; . . .  ; , .  ; ;  ; .EOP TEAM DEVELOP

[ . . i PSTG BfSES -

PSTG APPENDIX C . . . ; . . . . . . . . . . . .BECHTEL, SOUTHERN CO. PERFORtt CALCULAT!0tlS PSTG APPENDIX D . . . . . . . . . . . . . . . . .EOP TEAM DEVELOP

( PROVIDES REF FOR PLANT VALUES  !

PROCEDURE CHANGE NOTICE (PCN) P.EVIEW . . . . . .EOP TEAM DEVELOP - '

EtlSURE NRC/ CORPORATE COMMITilENTS MET PROCEDURE DISPOSITION REPORT (PDR). ; . . . . . .EOP TEAM DEVELOP t SHOWS WHERE OLD E0P STEPS WENT 2

YERIFICATION PROGRAM. . . ; ; . . . . . . . . . ;STA DEVELOP, PERFORM '

ENSURE PROCEDURES TRUE TO PSTGs PLANT ?!ANAGEMENT REVIEWS

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5 VALIDAT10tl PROGRAM. . . . . . . . . . . . . . . 6ENERAL PHYSICS PERFORM ENSURE PROCEDURES WORK HUMAN FACTORS .

REVIEW. . . . . . . . . . . . . . 6ENERAL PHYSICS PERFORM e

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AllALOG TRANSMITTER TRIP SYSTEM

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EMERGENCY RESP 0flSE FACILITY

- GRID SYSTEM  :

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- SAME GROUP DOING HUMAll FACTORS AND VAllDATI0li O!!

E0Ps ENSURES COORDINATED EFFORT APPENDIX R FIRE PROTECT!0fl

- ALL CURRElli FIRE PROCEDURES INTEGRATED

- FUTURE FIRE ACTIONS WILL BE ADDED TO E0Ps l

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19 ADVANTAGES OF SYMPTOM ORIENTED PROCEDURES

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NO PRE-DIAGNOSIS REQUIRED SLOW ,,

5 OVERALL RESPONSE

- ALLOWS TIME FOR AUTO RESPONSE

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SIMPLIFIES PROCEDURES '

REQUIRES OPERATOR TO C0tlSTANTLY MONITOR XEY PLANT PARANETE

- ELIMINATES "TullNEL VIS10ti" RELIEVES OPERATOR OF REQUIREMENT TO MAKE PROCEDURE APPLIC DECIS10tlS lil lilG}l-STRESS EMERGENCY SITUAT!0flS c

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- A PICTURE IS WORTH 1000 WORDS

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- REDUCE RELIANCE ON COMPLICATED LOGIC STRUCTURE DURING HIGH-STRESS EMERGENCY SITUATI0flS EASY TO KEEP TRACK OF WHERE YOU ARE IN PROCEDURE .

a MINIMIZES WASTED TIME "PAGE-FLIPPING" -

NO " FINGERS IN PAGES" SYNDROME SIMPLE INSTRUCTI0tlS TO USE

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' REQUIRED BY ANSI CONSISTENT WITH BWROG GUIDELINES -

VERIFY AUTOMATIC ACTIONS '

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VERIFY POWER SOURCES AVAILABLE

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VERIFY REACTOR IN SAFE CONDITIONS VERIFY PRINARY CONTAINMENT EXHAUST SYSTEMS OPERATING i

( VERIFY PRESSURE B0UNDARY INTACT '

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EVENT BASED EMERGENCY OPERATING PROCEDURES

', TYPES INCLUDED IN FLOW CHARTS

• ic PRIMARY SYSTEM RUPTURE IN DRYWELL (LEAKS) ~

RUPTURE INSIDE DRYWELL '~ ' '

SMALL OR LARGE BREAK OUTSIDE DRYWELL -

LOSS OF CONTROL ROD' SHUTDOWN CAPABILITY

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MSIV CLOSURE HPCI FAILURE RCIC_ FAILURE

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ABNORMAL REACTOR WATER LEVEL CONDENSATE AND FEEDWATER FAILURE RBCCW FAILURE STATION BLACK 0UT .

DEGRADED AUXILIARY ELECTRICAL POWER OPERATION MAIN CONDENSER TUBE FAILURE PLANT SERVICE WATER SYSTEM FAILURE '

TURBINE GENERATOR FAILURE MAIN STEAM LINE LEAKS MAIN STEAM LINE HIGH RADIATION DRYWELL COOLING SYSTEM FAILURE OFF GAS HIGH RADIATION MALFUNCTION OF PRESSURE CONTROL SYSTEM (TURBINE CONTROL VALVE & BYPASS VALVE OPEN)

REACTOR SCRAM AIR SYSTEMS FAILURE -

SAF$TY/ RELIEF YALVE FAILS OPEN LOSS OF CONDENSER VACUUM LOSS OF UNINTERRUPTIBLE POWER SUPPLY-(UPS)

ANTICIPATED TRANSIENT WITHOUT SCRAM - ATWS FIRES (OPERATOR ACTIONS ONLY) k

• ALL-OTHERS OF 1900 SERIES CONVERTED TO ABNORMAL OR INCORPORATED INTO ANNUNCIATOR PROCEDURES

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ADVANTAGES I .

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SYMPT 0M ORIENTED FULLY INTEGRATED i .-

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h FLOW CHART PROCEDURES -

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INCLUDES; ALL ADVANTAGE OF SYMPf0M ORIENTED FLOW CHART PROCEDURES FURTHER REDUCE SOFTWARE REQUIRED TO ABSOLUTE MINIMUM INTEGRATES EXISTING PROCEDURE STEPS

- MINIMIZE MEMORIZATI0tl REQUIREMENTS .

MAXIMIZES EQUIPMENT PROTECTION PROVIDES OPERATOR WITH PREDETERMINED PRIORITY OF "IMMEDIATE ACTIONS .

IMPROVES AWARENESS OF TOTAL PLANT CONDITIONS INTEGRATES OTHER EMERGENCY RESPONSE CAPABILITIES '

- SPDS j - APPENDIX R -

l - ERF

- EMERGENCY PLAN PROVIDES EASY RECORDKEEPING ,

PROVIDES SIMPLE ACTION IF OPERATOR GETS LOST CONSISTENT OPERATOR RESPONSE EASY VERIFICATION OF AUTOMATIC ACTIONS ,

l PUTS OPERATOR AHEAD OF PLAtlT

- MAKE PLANT REACT TO OPERATOR RATHER THAtl VICE VERSA i

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- T ARROW l COLOR CODE h5 GRID FOR LOCATION e -

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• END PATH MANUAL I

, TRND TREND ENTRY SYMBOL EMER GENCY ,

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=..... . . - - . . . . -..--.. -. .

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( KEY PARAMETERS

.- . _ AnD -

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- ALWAYS IN THE TOP, OUT BOTTOM OR SIDE l '

{ - N0 LINES CROSS .

$ DESIGNED FOR TWO-MAN USE

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- MINIMUM TECH SPEC ALLOWANCE

. - CAN BE USED BY A SINGLE MAN CHARTS MOUNTED S0 THAT THE ONE "0N THE BACK" IS VERY LIKELY THE NEXT ONE NEEDED

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INITIAL KEY PARAMETERS QUICKLY DETERMINE CORRECT CHART SIMPLY ENTRY CONDITIONS - SCRAM MANY LINES / SYMBOLS

- IF OPERATOR GETS LOST, SIMPLY RETURN TO TOP OF CHART IF KEY PARAMETER CHANGES AFTER IT'S PASSED, RETURN TO TOP 0F CHART IF PATH SPECIFIC PARAMETER CHANGES AFTER IT'S PASSED, RETURN.T0

[ THAT PARAMETER l' ANNUNCIATORS MAY BE RESPONDED TO AT OPERATOR'S BEST JUDiMENT END PATH MANUAL

- CONVENIENT BINDER ORGANIZED FOR EASY ACCESS

- RECOVERS PLANT AND SYSTEMS

-READIES PLANT FOR COLD S/D OR HOT S/D POSITIVE TRANSFER t'

-BATELLE REPORT PROVIDE GUIDANCE FOR "I D0ll'T KNOW"

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{ FUTURE INTEGRATED APPROACH TO .

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ADDITI0NAL INF0'RMAT10'N' * -

$u CURRENTLY WORKING ON METHODS TO INDICATE:

- PANEL NUMBER . . . . _ . _ . . _ _ . . . . . _J.;

-l - PANEL / COMPONENT LOCATION '

- IN SEQUENCE /00T OF SEQUENCE

,- SPDS NOTES

_i - CAUTIONS

.i y - NAMEPLATE DATA

- FIRE ACTIONS IN ADDITION TO APPENDIX R REQUIREMENTS

- SEVERITY OF ACTION SEQUENCE

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- OTHERS k

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i' D0 PROVIDE OPERATOR A.CTIONS TO B0utjD PR0BLEM ,

f D0 RESPOND TO SYMPT 0MS -

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DO pdOVIDE OPERAT5li' ACTIONS TO STOP SPREAD OF EQUIPHENT

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D0 P.ROVIDE OPERATOR ACTIONS TO STABILIZE SITUATION IN

{ ORDERED APPROACH DO AUTOMATICALLY LEAD OPERATOR TO CORRECT PROCEDURE i

DO INTEGRATE OPERATOR IMMEDIATE ACTIONS FOR A MULTITUDE OF .;

.l FAILURES (SINGLE OR MULTIPLE)

DO PRIORITIZE OPERATOR ACTIONS BASED ON SYMPT 0MS

~

- - KEY PARAMETERS D0 VERIFY AUTOMATIC ACTI0llS DO PUT OPERATOR AHEAD OF PLANT

> D0 MAKE OPERATOR ACTIONS VISIBLE D0 MINIMIZE OPERATOR MEMORY BURDEll - NO ROTE MEMORY REQUIRED 1

I D0 PROVIDE ALTERilATIVES IF OPERATOR MAKES ERROR

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( DO NOT RETURN PLANT TO OPERATION DO NOT REQUIRE COMPLICATED INSTRUCTIONS TO USE S

5 DO NOT REQUIRE THE OPERATOR TO PREDETERMINE WHAT HAPPENED 4  !

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SINGLE ENTRY CONDITION AND -INTERRELATIONSHIP  ;,

.y E0P FLOW CHARTS AND END PATH MANUALS t

REACTOR FAILURE OF LOSS OF VITAL TRANSIENTS VITAL EQUIPMENT POWER SOURCE l ,. v LOSS OF A ABNORMALLY COOLANT AUT R V HIGH RADIATION MANUAL SCRAM LOSS OF EXCESSIVE PRIMARY

0flTAINMENT RADI0 ACTIVITY RELEASE INTEGRITY -

V SHORT IMMEDIATE~

• MALFUNCTION TIME i ACTION OF REACTIVITY RESPONSE FLOW CHARTS CONTROL SYSTEtt s

h LONG END TIME PATH RESPONSE PROCEDURES -

• ALL ACTIONS ARE POST SCRAM OTHER PROCEDURES INCORPORATE PRE-SCRAM ACTIONS

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                                 - SAME FULL INTEGRATION                                                                                                                     '

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                                - OPERATOR ENJ0YS SAME ADVANTAGES J
                                - FULL C00RDINATI0li WITHIN ALL FLOW CHARTS FOR AUTO SELECTION                                                    .

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