ML20236S291
| ML20236S291 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 11/23/1987 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8711250033 | |
| Download: ML20236S291 (25) | |
Text
,
NOV 2 3'1987 Docket No. 50-395 DISTRIBUTION 5ee attached sheet LICENSEE: South Carolina Electric and Gas Company 1 1
-FACILITY: V. C. Sumer Nuclear Station
SUBJECT:
SUMMARY
OF, MEETING ON NOVEMBER.5 AND 6, 1986 WITH SOUTH CAROLINA' !
ELECTRIC AND GAS COMPANY l GENERAL On November 5 and 6 -1986, the NRC staff met with the South Carolina Electric' !
and Gas. Company (SCE&G) to audit the Safety. Parameter Display System (SPDS)' '
i The meeting was held at the V. C. Sumer Nuclear Station and the Nuclear' I
Training Center. A list of those persons who attended the meeting is included as Enclosure 1.
DISCUSSION The agenda for the meeting is included as ~ Enclosure 2. Handouts _ used at the
. meeting are included as Enclosures 3 and 4. 'SPDS items' discussed include j isolation' devices, human factors, reliability, minimum information needed, .
procedures, training, data validity, security, and response times. -
4 S
Jon B. Hopkins, Project Manager.
Project Directorate 11-1 Division of Reactor Projects - I/II
Enclosures:
As stated cc: See next page
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-- _ _ - _ _ _ _ _ _ _ _ _ - _ - _ _ . _ . _- -_ . _ _ _ .. . _- _ __ a
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g MEETING
SUMMARY
DISTRIBUTION'
!. PD II-1 r/f E. Adensam Attorney, OGC , .j P. Anderson E.~ Jordan l
J; Partlow ACRS (10)
Project Manager Jon B. Hopkins l NRC PARTICIPANTS J. Hopkins'-
S. Saba J. Kramer P. Hopkins 1
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cc: Applicant & Service List l
U _E mi_._.___ . _ _ _ . _ _ . _ ._ _. _. . _ . _ _ _ _ _ . . _ _ . . - - -.
Mr. D. A. Nauman South Carolina Electric & Gas Company Virgil C, Summer Nuclear Station J r.c :
Mr. William A. Williams, Jr. j
. Technical Assistant - Nuclear Operations i Santee Cooper P.O. Box 764 (Mail Code 153) ,
Columbia, South Carolina 29218 I i'
J. B. Knotts, Jr., Esq.
Bishop, Liberman, Cook, Purcell and Reynolds 1200 17th Street, N.W.
Washington, D. C. 20036 1 Resident Inspector / Summer NPS c/o U.S. Nuclear Regulatory Commission i Route 1, Box 64 {
Jenkinsville, South Carolina 29065 ;
Regional Administrator, Region II l U.S. Nuclear Regulatory Commission.,
101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Chairman, Fairfield County Council P.O. Box 293 Winnsboro, South Carolina 291P0 t
Attorney General Box 11549 Columbia, South Carolina 29211 i 1
Mr. Heyward G. Shealy, Chief j Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201
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ENCLOSURE-l ATTENDANCE NRC SAIC LCOMEX' 1
J. Hopkins J. : DeBor G; Bryan, 'Jr. 1 S. Saba M. Archer J. Kramer ,
P. Hopkins' j j
'SCE&G WESTINGHOUSE A. Monroe J.. Easter .;
W. Higgins R.,Breide i J. Skolds H A. Koon G. Taylor R. Barton K. Woodward J. LcBorde G. Parsons M. Browne C. Tyler H 4
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ENCLOSURE 2 I
DAY 1 i l
NUCLEAR TRAINING CENTER I
FORMAL PRESENTATIONS (PARTI) ]
i I. INTRODUCTION ]
II. WESTINGHOUSE GENERIC SYSTEM l III. HARDWARE / PHYSICAL LAYOUT IV. OVERVIEW OF BASIC DESIGN j i
- 1) HED's
- 2) Parameter Selection / Critical Safety Functions V. IMPLEMENTATION / MILESTONES .
1 VI. TRAINING PRACTICAL APPLICATIONS SIMULATOR DEMONSTRATION i
1 l LUNCH i
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FORMAL PRESENTATIONS (PARTII)
I. ENGINEERING PESIGN
- 1) HED
- 2) Parameter Selection / Critical Safety Functions II. SYSTEM DESIGN
- 1) Hardware
- 2) V&V
- 3) Reliability
- 4) Data Validity PRACTICAL APPI,ICATIONS EOF DEMONSTRATION-
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DAY 2 VIRGIL C. SUMMER NUCLE AR STATION I. TOUR OF THE CONTROL ROOM l
II. TSC TOUR / DEMONSTRATION III. OPERATORINTERVIEWS
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ENCLOSURE 3 V. C. SUMMER STATION SPDS RELIABILITY AS OF 11-1-86 SYSTEM AVAILABILITY = 97,49%
REASONS FOR THE 2.51% SYSTEM UNAVAILABILITY:
HARDWARE UNAVAILABILITY = 56% )
The hardware related unavailability specifics are t.s follows:
- 1. The week of January 17th, the system was down for four days due to problems l in the common bus switch that contains the data acquisition controller. Digital l Equipment Corporation (DEC) holds the maintenance contract and had difficulty i acquiring spare parts to repair the bus switch.
- 2. On March 14th a controller failed in the DT07 bus switch. The system was ,
repaired the same day. I l !
- 3. On April 23rd the data acquisition communications controller located in the DT07 bus switch failed. The system was repaired the same day.
- 4. On two separate occasions a hardware failure cause a system failover that ,
accouof ed for less than 1/2 hour of system unavailability.
SOFTWARE UNAVAILABILITY = 39%
The softyvare related unavailabiUty specifics are as follows:
- 1. STOLIN - This is task that processes the keyboard inputs, and would exit intermittently due to various errors. Westinghouse provided a fix on July 28th, and we have not experience any additional STOLIN problems.
- 2. CRT - This is the task that displays the information of the Aydin monitors.
This task would exit due to various error conditions. Westinghouse provided a fix for this r roblem on August lith, and we have not experience any additional CRT problems.
l 3. Installations of miscellaneous software updates required the system to be booted on several occasions, but this accounted for a very small percentage of the software related unavailability.
l MISCELLANEOUS UNAVAILABILITY = 5%
l l
This period of unavailability secounts for the following activities:
( 1. HVAC problems.
- 2. )vlaintenance on the UPS system.
- 3. System Diagnostics / Preventive Maintenance.
l
- 4. Software backup.
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ENCLOSURE 4~
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, 2PS1 PLANT SYSTEM STATUS GRAPHIC 20L1 PLANT OPERATING LIMITS GRAPH 2TR1 & 2 ICONIC TREND - NARROW RANGE
, 2TR3 & 4 ICONIC TREND - WIDE RANGE i
2HS1 & 2 ICONIC HISTORY - NARROW RANGE 2HS3 & 4 ICONIC HISTORY - WIDE RANGE LEVEL III 3RC1 REACTOR COOLANT SYSTEM GRAPHIC 3RC2 PRESSURIZER GRAPHIC 3 nil NUCLEAR INSTRUMENTATION
( 3MS1 MAIN STREAM SYSTEMS GRAPHIC I
, 3RM1 RADIATION MONITORING SYSTEM A/N j l 3FW1 FEEDWATER SYSTEM GRAPHIC '
l 3CY1 CVCS SYSTEM GRAPHIC = '
l 3RH1 RHR SYSTEM GRAPHIC i 3511 SAFETY INJECTION SYSTEM GRAPHIC l 3CS1 CONTAINMENT SYSTEMS GRAPHIC 3TC1 IN-CORE THERMOCOUPLE MAP LEVEL IV i 4RC1-4 REACTOR COOLANT SYSTEMS A/N 4 nil & 2 NUCLEAR INSTRUMENTATION SYSTEM A/N .
4MS1 & 2 MAIN STEAM SYSTEM A/N u 4RM1 & 2 RADIATION MONITORING SYSIEM A/N ;
4FW1 & 2 FEEDWATER SYSTDi A/N i 4CY1 ' CYCS SYSTEM A/N '
4RH1 RHR SYSTEM A/N 4SIl SAFETY INJECTION SYSTEft A/N 4CS1 CONTAINMENT SYSTEM A/W 4TC1:& 2 IN-C,0RE THERMOCOUPLE A/N !
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TABLE 2.3-1. OTSC SYSTEM DISPLAYS l
Display Page Number Description ;
LEVEL 1 2PS1 PLANT SYSTEM STATUS GRAPHIC q LEVEL II 3RC1 REACTOR COOLANT SYSTEM GRAPHIC 3RC2 PRESSURIZER GRAPHIC 3FW1 FEEDWATER SYSTEM GRAPHIC 3MS1 MAIN STEAM SYSTEMS GRAPHIC
' 1 3CY1 CVCS SYSTEM GRAPHIC 3 nil NUCLEAR INSTRUMENTATION-3TC1 IN-CORE THERMOCOUPLE f1AP i 3RW1 LIOUID RAD WASTE GRAPHIC i
, 3RW2 LIQUID RAD WASTE GRAPHIC 3RW3 GASEOUS RAD WASTE GRAPHIC l 3SIl SAFETY INJECTION SYSTEM GRAPHIC 3RH1 RHR SYSTEM GRAPHIC l 3CSl CONTAINMENT SYSTEMS GRAPHIC 3RM1 RAD MONITORING
SUMMARY
A/N
( 3CC1 3SW1 COMPONENT COOLING WATER SUPPLY GRAPHIC SERVICE WATER GRAPHIC 3SW2 SERVICE WATER GRAPHIC 3SW3 SERVICE WATER GRAPHIC 3EL1 ESF ELECTRICAL POWER TRAIN A GRAPHIC 3EL2 ESF ELECTRICAL POWER TRAIN B GRAPHIC 3MT1 METEOROLOGICAL DATA
SUMMARY
A/N LEVEL III 4RCl-4 REACTOR COOLANT SYSTEM A/N 4FW1 & 2 FEEDWATER SYSTEM A/N 4MS1 & 2 MAIN STEAM SYSTEMS A/N 4CV1 CVCS SYSTEM A/N ;
4 Nil & 2 NUCLEAR INSTRUMENTATION A/N ;
i 4TC1 & 2 INCORE THERf10 COUPLE A/N 4RW1 RAD' WASTE A/N 4SIl SAFETY INJECTION SYSTEM A/N 4RH1 RHR SYSTEM A/N 4CS1 CONTAINMENT SYSTEMS A/N t 4RM1 & 2 RAD MONITORING A/N l 4CC1 COMPONENT COOLING WATER A/N 45W1 SERVICE WATER A/N 4EL1 ESF ELECTRICAL POWER A/N L
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