ML20246B957

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Summary of 890801 Meeting W/Util in Rockville,Md Re Loss of Offsite Power Event at Plant.List of Attendees,Agenda & Handouts Encl
ML20246B957
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 08/15/1989
From: Hayes J
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8908240109
Download: ML20246B957 (41)


Text

-- _ _ _ _ _ - _ _ - - _ _ _ _ _ _ _ - . _

August 15, 1989-locket No. 50-395 LICENSEE: South Carolina Electric & Gas Company FACILITY: V.-C. Summer Nuclear Station, Unit No. 1

SUBJECT:

SUMMARY

OF MEETING WITH SOUTH CAROLINA ELECTRIC & GAS COMPANY GENERAL On August 1, 1989,.the NRC staff consisting of representatives of the Office of Nuclear Reactor Regulation (NRR) and Region II met with representatives of the South Carolina Electric & Gas Company (SCE&G) to discuss the loss of offsite power event at the V. C. Summer Nuclear Station. The meeting was held at the NRR offices in Rockville, Maryland. A list of those persons who attended the meeting is included as Enclosure 1. Enclosure 2 was the agenda for the meeting.

DISCUSSION A handout, Enclosure 3, provided information on the SCE&G electrical grid system, the Summer Station offsite power design, a description of the July 11, 1989 and interim short term and long term corrective actions which have been taken or which are under consideration. The licensee also emphasized that, while they considered this a very serious event, they did not believe it was a system instability event. They characterized the severe voltage reduction as being very localized - only one bus tie saw a. voltage reduction. The licensee represented that the' better measure of system impact was frequency shift which was Very small. They further stated that their initial conclusions were that a major contribution to the event was the generator backup relay settings at their McMeekin, Saluda, and Fairfield Stations. The staff indicated at the close of the meeting that if any future information was required that the staff would request it at a later date.

Original Signed By:

l John J. Hayes, Jr., Project Manager Project Directorate 11-1 Division of Reactor Projects -I/II Office of Nuclear Reactor Regulation

Enclosures:

As stated cc w/encls:

See next page PD P -1 JH$yks:sw EA nsam 1 8//p/89 '8/g/89 h 890824o109 spogig ii fDR ADOCK 05000395 PDC

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Mr.' O. S. Bradham South Carolina Electric & Gas Company Virgil C. Sumer Nuclear Station l

cc:

' Mr.. William A. Williams, -Jr.

. Technical Assistant - Nuclear Operations Santee Cooper P. O. Box 764.(Mail Code 153)

Columbia, South Carolina 29218 J. B. Knotts, Jr. , Esq.

L Bishop, Cook, Purcell .

E and Reynolds 1400 L Street, N.W.

Washington, D. C.- 20005-3502 Resident Inspector /Sumer NPS c/o U.S. Nuclear Regulatory Comission Route 1, Box 64-Jenkinsville, South Carolina 29065 Regional Administrator, Region II U.S. Nuclear Regulatory Comission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia -30323' Chairman, Fairfield County Council

P. O. Box -293 Winnsboro, South Carolina 29180

'Mr. Heyward G. Shealy, Chief Bureau of Radiological Health.

South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia,' South Carolina 29201

' South C5rolina Electric & Gas Company Mr. A. R. Koon, Jr. , Manager Nuclear Licensing Virgil C. Sumer Nuclear Station P. O. Box 88 Jenkinsville, South Carolina 29065

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DISTRIBUTION FORIMEETING.

SUMMARY

DATED: August 1, 1989 Facility: Summer, Unit 1

.aocket!Ptlee-

'NRC PDR Local PDR

PDII-11 Reading T. Murley 12-G-18 J. Sniezet' G-18 S..Varga . 14-E-4 G. Lainas 14-H-3 E. Adensam 14-B-20 P. Anderson. 14-B-20

, J. Hayes 14-B-20 OGC 15-B-18 E. Jordan- MNBB-3302 B. Grimes 9-A-2

0. Chopra 8-D-20 C.'Haughney 9-A-1 D. Tondi 8-D-20 E. Mershcho11 RII T. Reed 14-H-25 J.' Carter 12-H-7 N. Kadambi- 11-A-1 C. Rossi .11-E-4 N. Trehan 8-D-20 J. Knight 8-D-20 P. Kang 8-D-20 P. Fillion RII J. Hopkins 14-H-25 L. Engle 14-H-22

.R. Prevatte RII ACRS(10) P-315

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4 Enclosure 1 ATTENDANCE AUGUST 1, 1989 SCE8G NRC OTHERS D. Nauman J. Hayes, Jr. J. Hegner (VA. Power)

0. Bradham S. Varga R. Saunders (VA. Power)

M. Frick G. Lainas L. Ellis (VA. Power R. Clary O. Chopra A.Mistr(VA. Power) )

W. Higgins C. Haughney H. Ernst, Jr. (Duke Power)

K. Kee D. Tondi R. Gill (Duke Power)

E. Merschoff Jr., (CP&L) i E. /densam R. Snider B. Prunty,(Souther Services

! T. Reed Company) l J. Carter H. Majors (GA. Power)

I N. Kadambi C. Rossi l N. Trehan J. Knight P. Kang l

P. Fillion J. Hopkins L. Engle R. Prevatte 1

. m. Enclosure 2-e

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.,a o ,. AGENDA' MEETING ON LOSS'0F GENERATING FACILITIES FROM THE SCE8G GRID AS A RESULT OF JULY II,1989 REACTOR TRIP AUGUST I, 1989 I. INTRODUCTION JACK HAYES (NRC)

II. SCE8G INTRODUCTION OLLIE BRADHAM III. BACKGROUND SCE8G ELECTRICAL GRID SYSTEM KNOX LEE V. C. SUMMER OFFSITE POWER DESIGN RON CLARY IV. DESCRIPTION OF THE EVENT- ,

SUMMER STATION RON CLARY SYSTEM REACTION MARION FRICK TRANSIEMT EVALUATIONS KNOX LEE

! V. CORRECTIVE ACTIONS INTERIM MARION FRICK SHORT TERM LONG TERM V. SCE&G

SUMMARY

DAN NAUMAN l

VI. NRC

SUMMARY

JACK HAYES l

PARTICIPANTS SCE&G NRC OTHERS

, Enclosure 3

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J JULY 11,1989 LOSS OF OFFSITE POWER MEETING WITH NRC AUGUST 1,1989 WASHINGTON, DC

JULY 11,1989

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TRIP OF VIRGIL C. SUMMER NUCLEAR STATION i i

INTRODUCTION OLLIE BRADHAM BACKGROUND SCJ&G ELECTRIC GRID SYSTEM KNOX LEE V. C. SUMMER OFFSITE POWER DESIGN RON CLARY JULY 11,1989 EVENT SUMMER STATION RON CLARY SYSTEM REACTION MARION FRICK TRANSIENTEVALUATIONS KNOX LEE l CORRECTIVE ACTIONS INTERIM CONTROL MEASURES MARION FRICK SHORT TERM \

LONG TERM

SUMMARY

DAN NAUMAN l

h Og d INTRODUCTION OLLIE BRADHAM

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ATTENDEES Dan Nauman Senior Vice President, Power Production Ollie Bradham Vice President, Nuclear Operations Ron Clary Manager, Design Engineering Marion Frick Manager, System Relaying 1

l Knox Lee Manager, '

System Planning i l

Wes Higgins Supervisor, i

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1 V. C. SUMMER OFFSITE POWER .

DESIGN

& l SUMMER STATION EVENT RON CLARY l

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C. SUMMER OFFSITE POWER SYSTEM DESIGN REQUIREMENTS i

NUCLEAR REGULATORY COMMISSION GENERAL DESIGN CRITERIA 17 REGULA TORY GUIDE 1.32 FSAR QUESTIONS STANDARD REVIEWPLAN - SECTION 8.2 INDUSTRYSTANDARDS IEEE 308 IEEE 765 3

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JUL Y 11,1989 TRIP OF VIRGIL C. SUMMER NUCLEAR STATION l

TURBINE TRIP REACTOR TRIP '

LOSS OF OFFSITE POWER TO ESF

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SYSTEM REACTION l REVIEW OF S YSTEM OPERA TING CONDITIONS BEFORE AND AFTER THE EVENT SEQUENCE OF EVENTS PRIMARY AND CONTRIBUTING FACTORS GENERATOR BACKUP RELAYS 1

CORRECTIVEACTION l

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SOUTH CAROLINA ELECTRIC & GAS CO.

MAJOR GENERATION

~ MCMEEKIN #1 & #2 254 (0)

V. C. SUMMER 868 (0) SALUDA HYDRO #1 thru #,5 135 (35)

FAIRFIELD PUMP STORAGE

  1. 1 thru.#8 WATEREE #1 & #2 295 (0) 310 (315) 4,,

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. 1 URQUHART #1 thru #3 251 (251) ,

A. M. WILLIAMS

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CANADYS #1 thru #3 395 (395)

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' NET TIE LINE 693MW =

NETWORK 730MW~__ NET TIE-LINE FLOWS IN FLOWS ~OUT n

3077MW INTERNAL .TOTALLGEN.

GENERATION. CAPABILITY-389lMW GEN. AVAILABLE SYSTEM JULY ll LOAD 3480MW' 3040MW l AFTER p

l NET TIE-LINE I643MW _

NETWORK.

I70MW _ NET TIE LINE -

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SYSTEM OPERATIONS

SUMMARY

OF JULY 11TH EVENT PRE-EVENT POST-EVENT GENERATING STATION MEGAWATTS MEGAVARS MEGAWATTS MEGAVARS 1

v. C. SUMMER 868 440 0 0 FAIRFIELD 295 65 0 0 MCMEEKIN 254 116 0 0 SALUDA HYDRO 135 45 35 15 WATEREE 310 180 315 210 CANADYS 395 178 395 270 URQUHART 251 63 251 118 A. M. WILLIAMS 545 220 545 270 MISC. 24 10 26 15 SUB-TOTAL 1525 651 1532 883 TOTALS 3077 1317 1567 898 GENERATION LOST - 1517 MW, 651 MVARS PRE-EVENT POST-EVENT INTERNAL GEN. 3077 MW 1567 MW NET INTERCHANGE -37 MW (EXPORT) 1473 MW (IMPORT)

SYSTEM LOAD 3040 MW 3040 MW FREQUENCY 59.99 HZ 59.965 HZ

(.025 HZ DECAY)

SEQUENCE OF EVENTS q

1. V. C. SUMMER PLANT TRIP '
2. McMEEKIN PLANT TRIP
3. SALUDA HYDRO PLANT TRIP
4. ONE OR MORE FAIRFIELD HYDRO UNITS TRIP S. SUMMER ESF BUS 1DA TRIP
6. ONE OR MORE FAIRFIELD HYDRO UNITS TRIP
7. SUMMER ESF BUS 1DB TRIP
8. FINAL FAIRFIELD PUMPED STORAGE UNITS TRIP 1

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PRIMAR Y CA USE OF GENERA TION L OSS A T OTHER STA TIONS GENERATOR BACK-UP RELA YING MCMEEKIN STATION SALUDA HYDRO STATION FAIRFIELD PUMPED STORAGE CONTRIBUTING FACTORS L -

PEAK LOADING CONDITIONS HIGH REACTIVE OUTPUT (VARS) FROM SUMMER STATION A UTOMA TIC VOLTA GE REGULA TOR RESPONSE I

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VOLTAGE DIFFERENTIALS BETWEEN POWER SYSTEM ELEMENTS CA USE PREDOMINANTLY Y REA CTIVE PO WER FL O W (VARS) {

POWER SYSTEM IMPEDANCE IS COMPOSED OF RESISTANCE AND REACTANCE.

THE RATIO OF THE REA CTIVE IMPEDANCE TO RESISTIVE ^

IMPEDANCE ON A TYPICAL TRANSMISSION LINEIS APPROXIMATELY8 TO 1 REAL POWER FLOW (WATTS) CAUSES A VOLTAGE DROP PREDOMINANTLY Y DUE TO THE RESISTANCE PORTION CF TOTAL IMPEDANCE REACTIVE POWER FLOW (VARS) CAUSES A VOLTAGE DROP PREDOMINANTLY Y D UE TO THE REA CTIVE PORTION OF TOTAL IMPEDANCE l

1 SINCE THE REA CTANCE TO RESISTANCE RA TIO IS 811, REA CTIVE

PO WER FLO WS RESUL TIN LARGER VOL TA GE DROPS THAN REAL  ;

POWER FLOWS IMPORTING REAL POWER (WA TTS) FROM MORE DISTANT l LOCA TIONS RESULTS IN SOME VOLTA GE DROP

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IMPORTING REACTIVE POWER (VARS) FROM MORE DISTANT  ?

LOCATIONS RESULTS IN MUCH LARGER VOLTAGE DROPS

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l LOCAL VAR SUPPLY IS IMPORTANT TO MAINTAINING SYSTEM VOLTAGES i

I CONTRIBUTING FACTORS PEAK LOADING CONDITIONS:

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REQUIRE HIGH REACTIVE POWER (VARS) GENERA TION TO MAINTAIN SYSTEM VOLTAGES HIGH REACTIVE OUTPUT (VARS) FROM SUMMER STA TION:

LOSS OF LARGE BLOCK OF VAR GENERA TION RESULTS IN S YSTEM VOLTAGE REDUCTION AUTOMATIC VOLTAGE REGULATOR ACTION:

SUDDEN DROP IN SYSTEM VOLTAGE WITHOUT GENERA TOR VOLTAGE REGULA TOR ACTION NA TURALL Y LEADS TO HIGHER VAR OUTPUT ACTION OF VOLTAGE REGULA TOR 15 TO RETURN GENERATOR VOLTA GE TO NORMAL RESULTING IN INCREASED EXCITA TION AND INCREASED VAR OUTPUT INCREASED VAR OUTPUTINCREASES TENDENCY OF GENERATOR BACKUP RELAYS TO OPERATE i

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F

. GENERATOR BACKUP RELAYS GENERA TOR BA CKUP RELA YS PRO VIDE PRO TECTION TO THE GENERATOR AGAINSTINTERNAL AND EXTERNAL FAULTS NOT PROPERL Y CLEARED B Y OTHER RELA YS AND CIRCUIT BREAKERS  !

COMPROMISE SETTINGS WHICH PROVIDE BETTER GENERATOR PROTECTION ARE MORE SUSCEPTIBLE TO OPERA TION DURING SYSTEM i ABERRATIONS SETTINGS MORE SECURE AGAINST OPERA TION DURING SYSTEM ABERRATIONS PROVIDE LESS PROTECTION TO THE GENERATOR SCE&G'S APPLICATIONS SETAT 150% OF GENERATOR RATING LOOKS INTO TRANSMISSION SYSTEM PROVIDES GOOD GENERATOR PROTECTION UNTIL NOW EXPERIENCE HAS BEEN GOOD INDUSTRY APPLICATIONS DIVERSE REFLECTS VARYING COMPROMISES BETWEEN GENERATOR PROTECTION AND SECURITY AGAINST TRIPPING DURING SYSTEM ABERRATIONS REFLECTS DIFFERENT EXPERIENCES OF OPERA TION DURING SYSTEM ABERRATIONS TELEPHONE SURVEY OF SEVERAL COMPANIES REVEALS APPLICA TION OF SETTINGS AS-LOW-AS 125% AND IN EXCESS OF 200 %

OF GENERATOR RATING

SURVEY OF GENERATOR BACK-UP RELAYING PRACTICES SURVEY RESPONDENTS - 37 ELECTRICAL UTILITIES SUR VEY REPRESENTS 6698 UNIT YEARS OF OPERA TION OF 37 UTILITIES, 30 USE PHASE DISTANCE BACK-UP RELA YS 49% LOOKINTO TRANSMISSIONSYSTEM S1% LOOKINTO STEP-UP TRANSFORMER 2 REPORTED OPERA TIONS DURING SYSTEM SWINGS

COMMITTEE COMMENTS l

VOLTAGE REGULATOR BOOSTING IN RESPONSE TO A SYSTEM OVERLOAD MAY REQUIRE LIMITING THE REACH OF BACK-UP DISTANCE 1 RELAYS TO PREVENT RELAY OPERATION FOR RECOVERABLE SWINGS, SETTINGS OF MORE THAN 200 % OF GENERATOR RA TINGS MA Y BE REQUIRED

REFERENCE:

A SURVEY OF GENERATOR BACKUP PROTECTION PRACTICES, IEEE COMMITTEE REPORT: GENERATOR BACKUP PROTECTION WORKING GROUP OF IEEE POWER SYSTEM RELAYING.

COMMITTEEREPORTPRINTED JUNE 1989

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PSAP TRANSIENT EVALUATION TRANSIENT STABILITY STUD Y WITH CEB RELA YS A T PREVIOUS SETTING REVEALS THA T THE RELA Y OPERATING SETTING IS BEING APPROACHED DURING THE TRANSIENTPERIOD.

TRANSIENT STABILITY STUD Y WITH CEB RELA YS A T THE NEW OPERA TING SETTING REVEA LS INCREASED PROTECTION FROM INAD VERTENT OPERA TING DURING THE TRANSIENTPERIOD.

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CORRECTIVE ACTIONS MARION FRICK l

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CORRECTIVE ACTIONS 1

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l INTERIM CONTROLS: 1 4

I LIMIT V. C. SUMMER MVAR OUTPUT TO 300 MVARS GENERATE MVARS AT OTHER STATIONS STARTPARR GAS TURBINES DURING PEAK LOADS (ALTERNATE OFFSITESOURCE)

RUN ONE OR MORE OF FAIRFIELD PUMPED STORAGE UNITS AS VAR GENERATORS SHORT-TERM:

1 DE-SENSITIZE GENERA TOR BA CKUP RELA YS l

i LONG-TERM:

INSTALLA TION OF VOLTAGE REGULA TORS ON V. C. SUMMER'S 7.2 KV SYSTEM (ENGINEERING IN PROGRESS) \

FURTHER STUD Y AND EVALUA TION OF GENERA TOR BA CKUP RELA Y SETTINGS (COMPROMISE BETWEEN GENERA TOR BA CKUP PROTECTION AND SECURITY AGAINST OPERA TION FOR SYSTEM ABERRATIONS)  ;

l EVALUA TE THE ELIMINA TION OR REVISION OF THEINTERIM CONTROL MEASURES 1

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SUMMARY

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