ML20065T146

Forwards Description of New Hardware & Software for Spds,Per Generic Ltr 89-06 & Suppl 1 to NUREG-0737.Rev 6 to Emergency Operating Procedure EOP-12.0, Monitoring of Critical Safety Functions Also Encl

ML20065T146
Person / Time
Site:	Summer
Issue date:	12/18/1990
From:	Skolds J SOUTH CAROLINA ELECTRIC & GAS CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20065T147	List: ML20065T146 ML20065T148
References
RTR-NUREG-0737, RTR-NUREG-737 GL-89-06, GL-89-6, NUDOCS 9012270283
Download: ML20065T146 (29)

Text

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e So t Caro na Electric & Gas Cornpany J Sk a Jenkinulio, Sc ?900$ tuloar OperMons s -" (B03) 34%4040 ,

SCE&G

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DE[ l B 1990 Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:

Subject:

VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 GENERIC LETTER 89-06 SAFETY PARAMETER DISPLAY SYSTEM (LTR 890006-1)

South Carolina Electric & Gas Company (SCE&G) has completed the installation '

of new hardware and sof tware for the Safety Parameter Display Systein (SPDS) ,

at the Virgil C. Summer Nuclear Station. The new system has been evaluated ogAinst the guidelines contained in Generic Letter 89-06 and is considered to "

be in full compliance with NRC requirements addressed in Supplement 1 to NUREG 0737.

To facilitate NRC review (TAC NO. 73713) of the new system, SCE&G has -

attached to this letter a description of how the new SPOS meets or exceeds those areas previously evaluated. This documentation, along with the completed checklist and supporting photographs as addressed in Generic Letter 89-06, will be maintained for a minimum of three years.

If you should have any questions in regards to this certification, please contact Mr. Charles McKinney of my staff at (803) 345-4723.

Very truly yours.

John L. Skolds

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CJM:JLS: Icd

. Attachment c: 0. W. Dixon, Jr. J. B. Knc , Jr.

E. C. Roberts J. F. Heibaan R. J. White D. C. Warner S. D.'Ebneter NSRC G. F. Wunder NPCF General Managers RiS (LTR890006)

NRC Residant Inspector File (815.14)

NUCLEAR EXCELLENCE - A SUMMER TRADITION! l t 9012270283 901218

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EVALUATION OF:THE V.C. SUMMER NUCLEAR STATION SAFETY PARAMETER DISPLAY SYSTEM t

WITH REGARD TO DOCKET 50-395..

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Table of Contents 1.0 I n t r od u c tio n . . . . . .. .. ... . . . . . . . . . . . . . . . . . .....

. . .... . 1 2.0 S PDS D escrip tion .... . . ..... ..... . .... ...... .... . .. ... . 1 3.0 Evaiuations............................................. 3 4.0 5ummary...................................................... 6 Attachment 1 Location of SPDS Terminals Attachment 2 SPDS and Supporting Displays Attachment 3 Keyboard / Keypad Layouts Attachment 4 Emergency Operating Procedure EOP-12 L

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1.0 INTitO D UCTION In a Safety Evaluation Report (letter from J.B. Ilopkins to D.A. Nauman dated November 13, 1987) issued by the Ofuce of Nuclear Reuetor Regulation, the Nuclear Regulatory Commision identified the strengths and weaknesses of the V.C. Summer Nuclear Station (VCSNS) Safety Parameter Display System (SPDS). The staff audit concluded that the VCSNS SPDS met most of the applicable provisions of Supplement 1 to NUREG.0737 and found no serious safety concerns. As a response to this audit, and due to concerns regarding the ability to maintain the existing hardware, SCE&G committed to replace the existing SPDS . This report provides a description of how the new SPDS meets or exceeds those areas evaluated during the audit.

2.0 SPDS DESCill PTION The VCSNS SPDS is' based on the Westinghouse Owners Group Guidelines for display of the Critical Safety Functions (CSF). The top level display provides summary indication of several parameters of particular interest to operators during or immediately following the initiation of an event, and contains the CSF status boxes at the bottom of the page. The boxes are color coded in compliance with Westinghouse Owners Group recommendations. In addition, the boxes are arranged in order of significance from left to right, with left being the most significant and right being LS least significant.

The SPDS is hosted on a Gould 32/9780 computer, known as the Integrated Plant Computer System (IPCS). The IPCS combines the functions of the SPDS, BISI (Bypassed and Inoperable Status Indication), reactivity computer, and other process computer applications (previously hosted on a Westinghouse P2500 computer) onto one platform. The Gould computer contains a redundant CPU conGguration. During normal operations both processing unita are gerational and used in performing calculations. Should one processor fail, the computer may be restarted with only one processor operational to provide the necessary SPDS

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information. The software was developed by Scientific Applications international Corporation (SAIC).

Sensor inputs are scanned at varying intervals depending on the type of input.

There are six general scan classes ranging from 0.1 seconds to 60 seconds per scan. Sequence of Events points may also be designated which are timetagged to within 1 millisecond. Points are scanned relative to their importance to plant operations and emergency assessment. Generally, digital inputs are scanned once per second and analog inputs once per two seconds. Radiation and meteorological inputs are scanned once per ten seconds, averaged over selected intervals, and transferred to the VAX computer system for dose assessment use. This data is also accessible for display on the U)CS Most SPDS points are scanned once per two seconds, which is consistent with the display update rate for SPDS displays.

The usual time for SPDS display initialization is approximately I second with data updates occurring every 2 seconds. Many other diagnostic features are available on the IPCS; however, their update rate may be greater than 2 seconds based on the function performed and its priority relative to SPDS. In addition, all terminals on the IPCS have a continuous display of SPDS Critical Safety Function status in the upper right corner of the screen, and all terminals except the i dedicated alarm terminals on the Main Control Ikiard may access more detailed SPDS displays. SPDS terminais are provided at the same locations as the previous terminals but were upgraded as part of the replacement project. Attachment 1 L

shows the placement of the SPDS terminals in the Control Room, Technical Support Center , and Emergency Operations Facility.

All screens are easy to access through the use of a Turn.on. code or keyboard function keys. Turn on. codes are names of displays or programs which are accessed through keyboard input. Samples of SPDS and related displays are shown in Attachment 2, A general keyboard layout of both the standard keyboard and special function keypad are given in Attachment 3.

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3.0 RVALUATION This section provides responses to the staff's conclusions contained in the safety evaluation report for the VCSNS with regard to the essential elements of the SPDS required by Supplement I to NU REG-0737.

3.1 THE SPDS SHOULD PROVIDE A CONCISE DISPLAY uF Pl ANT V A RI A BLES.

The SPDS follows Westinghouse Owners Group recommendations for display of CSFs which have been previously approved by the Nuclear Regulatory Commission.

3.2 THE SPDS SHOULD BE LOCATED CONVENIENT TO THE CONTROL ROOM OPERATORS.

The previous evaluation noted that there were two SPDS terminals in the Control Room. At the time of this report, there are five SPDS terminals in the Control Room. All five terminals provide a summary indication of the CSFs.

Three of the terminals have access to more detailed information so that an accurate assessment of plant conditions may be made. Two additional terminals will be replaced following approval of the BlSI application on _the IPCS Contained in Figures 13 in Attachment 1 of this report are layout drawings which indicate the locations of SPDS terminals.

3.3 THE SPDS SH ALL CONTINUOUSLY DISPLAY INFORM ATION FROM WHICH THE SAFETY STATUS OF THE PLANT CAN BE ASSESSED, All SPDS displays except for the Operational Limits Curve contain the CSF s tatus boxes at the bottom of the page. In addition, each CSP ::tatus is displayed in the upper right corner of any terminal connected to the IPCS.

l With all CSFs fully satisfied the status box is solid green. Any CSF which is not fully satisfied will be indicated by p stripe of the appropriate color. CSPs which do not necessarily require operator action (completely satisfied

< green > or not completely satisfied < yellow >) are displayed as a solid bar in :he status block. All other conditions (threatened < orange >, severely

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4 threatened < red >, or indeterminate by the computer < magenta >) are displayed as a blinking bar in the status block to attract operator attention more quickly. This status bar is displayed continuously, updated approximately once per second, and not operator changeable.

3A TIIE SPDS SHALL llAVE RAPID AND RELIABLE DISPLAY OF THE SAFETY STATUS OF THE PLANT.

SPDS CSF status is cc-tinuously displayed at each terminal and updated once per secor.d. System response to operator commands for SPDS displays is extremely fast, usually within 1 second, but occasionally as long as 3 seconds.

Currently both SPDS systems are operational and available in the Control Room.The old system is only being used to run the BISI applica tion a not a part of SPDS), Combined system availability has been nearly perfect. Following the certification of the BlSI application on the IPCS, the old system will be formally decomissioned. SCE&G fully expects, and operating statistics indicate, that overall system availability will remain at the intended goal of greater than 99 percent.

3.5 THE SPDS SUALL BE SUITABLY ISOLATED PROM ELECTRICAL OR E LECTRONIC LNTERFERENCE.

The isolation of the SPDS inputs met the requirements of NUREG 0737, Supplement 1. No changes to the input isolations were made as a part of this computer replacement therefore the existing isolation still satisfies the requirement.

3.6 THE SPDS DISPLAY SHALL BE DESIGNED TO INCORPORATE HUMAN FACTORS PRINCFPL,ES.

Scientific Applications International Corporation performed a complete review of the SPDS displays based on the Westinghouse Owners Group critical safety function status trees used as a part of the Emergency Response Facility Information System for Carolina Power and Light Company's Shearon Harris and H.B. Robinson plants. The V.C. Summer Nuclear Station SPDS was designed and built using these same human factors principles.

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3.7 THE SPDS SHALL DISPLAY MINIMUM INFORM ATION SUFFICIENT TO DETERMINE THE PLANT SAFETY STATUS (CRITIC A L S A FETY FUNCTIONS) DURING ABNORMAL AND EMERGENCY CONDITIONSa Westinghouse Owner's Group Guidelines for evaluation and display of the CSFs were used extensively in the development of the SPDS. The second level displays provide paths which lead the operator to the appropriate Emergency Operating Procedures for further action. Additionally, a tabular summary of the relevant information for each tree is displayed on the page along with information on the trend of the parameter.

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3.8 PROCEDURES TO BE DEVELOPED AND OPERATORS SIIOULD BE TRAINED TO RESPONL) TO ACCIDENT CONDITIONS BOTil WITH OR WITHOUTTHE SPDS AVAILABIL

- A user's guide is available in the Control Room, TSC, and EOF along with a list of points used on the SPDS. The SPDS displays are designed for minimal operator action and an online help facility provides operators with an easy to use quick reference guide. A copy of the help file for SPDS is provided in Attachment 2 along with the SPDS displays and a copy of Emergency Operating Procedure EOP 12 is enclosed in Attachment 4. Operators are trained to respond to plant conditions both with and without the SPDS and use it routinely in simulator scenarios.

3.9 NUREG-0800 SECTION 18.2 REVIEW OF SPDS VERIFICATION AND LALIDATION.

Both the factory and cite acceptance tests were conducted by the vendor and witnessed by Nuclear Computer Services and-Operations personnel. In addition to these tests, the Nuclear Regulatory Commission witnessed the use of the SPDS on the VCSNS Training Simulator during an on site EOP audit in August 1990. The SPDS received only favorable responses from the audit team.

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_ 1 i The VCSNS verifies and: validates the use of all software applications ,

o including SPDS, through a. Quality Review Board process. The Quality Review i Board is a multidisciplined group whose job is to review the verification and validation process and results to ensure that the application is consistent with

' station requirements.

4.0 SUMM A RY ,

The VCSNS SPDS is an entirely new system written primarily by SAIC and 4 based on Westinghouse Owners Group recommendations for display of CSFs.

-This system provides continuous display-on all SPDS terminals with the -

ability to acquire : detailed information quickly and reliably. Terminals are located in strategic areas in the plant: Control . Room, Technical Support -

Center, Emergency Operations Facility,'and Central Command Centers, An -

Operator's Guide and information specifically concerning the SPDS are  ;

.available~ in 'these areas, along with a complete list of computer points. The

. software is hosted on a Gould computer system, a hardware platform which has been proven reliable throughout the nuclear industry for many years. The

.VCSNS SPDS provides concise, rapid, and reliable information so -that

. Operations personnel may continuously assess the safety status of the unit.

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Attachment 1 Location of SPDS Terminals s

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Figure 1 CONTROL ROOM LAYOUT [

1-7 SPDS terminals

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-TSC LAYOUT 16L SPDSterminals*

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DEC 11,1990,' .

SELECT FUNCTION KEY OR HELP FILE N. 10:37:49 _

l HELP PAGE FOR SPTOP SPDS TOP LEVEL DISPLAY ( SPTOP)

SPTOP gives a summary of the Critical Safety Functions in the 4 plant. The six critical safety functions are: Subcriticality, Core Cooling, Heat Sink, RCS Integrity, Containment, and r RCS Inventory. Additionally, the Operational Limits Curve is available as a part of Integrity. The CSF Boxes are color coded for severity and are interpeted as follows:

GREEN -- CSF fully satisfied ( no further action required)

YELLOW -- CSF not fulig satisfied ( action may be necessary)

ORRHGE -- CSF is threatened (action is required) 1 RED -- CSF is severly threatened ( immediate action)

MAGENTA -- Computer is not currently calculating the CSF due to a problem. ( USE E0P-12 MANURL STFPS)

In addition to the CSF status boxes at the bottom, additional information which may be of interest to the op_. . tor is provided on the top level display. A brief description of each parameter followsi Containment Conditions -- either NORMAL or RDUERSE. This is determined by either high containment pressure as indicated by P1003D or high integretated containment dose ( U6054 > 1.0E6 rem). i SI Termination -- either YES or HO. This status message informs the operator if the conditions for terminating safety injection exist ( or if safety injection is not yet JK necessary). Safety injection can be terminated if: gg o

1) RCS pressure is stable or increasing, and *[

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2) RCS subcooling is >= 30 DEGF, and

3) PZR Level i s > = 4% for normal containment; 39% for , "i adverse containment, and 1 [g

4) R healthy heat sink exists, defined as heat sink csf status not in a red color.

Integrated. Containment Dose -- either (1.0E6 or > 1. 0 E 6. This F2= F3= F4= F5= F6=

Fl= PLHT KBD=HORMRL RMODE= POWER OPERATION

DEC 11,1990 -

SELECT FUNCTION KEY OR HELP FILE EEEEEEEE 10:39:1T l HELP PAGE FOR SPTOP is calculated by converting RMG7 and RMG18 readings to 6 Rem based on the calculation intervals of points and '

summ i ng ( i ntegrat i ng ) over time. The integrated dose may be reset to 0 using L6096.

RMST Swapover -- either REQUIRED or HOT REQUIRED. This .

message informs the operator if the RMST has reached '

i low level, and the suction of the SI pumps must be switched to the RHR/RBS Sumps. IF 1/2 of the RMST levels, LO990R and LO992R are < 18% swapover is required.

CST Swapover -- either REQUIRED or HOT REQUIRED. This status message informs the operator if 2/4 of the CST press. ( Y9008R , Y9009R , Y9010R, Y9011R ) have reached the low setpoint of 11.94 psis indicating that EFW Pump suction must be switched from the CST.

RCP Trip Criteria -- either SRTISFIED or HOT SRTISFIED. This message informs the operator if the conditions for tripping the RCPs have been met. The trip is allowed if RCS pressure is <= 1380 psig.

Natural Circulation -- either SRTISFIES (color), HOT SRTISFIED, or HOT APPLICROLE. This message informs the operator if natural circulation is in effect. A loop is in natural circulation if:

1) RCS Subcooling > 30 DEGF, and 2E

2) Core exit Temp is stable or decreasing, and

3) SG Pressure is stable or decreasing, and jg

4) Hot Les Temp is stable or decreasing, and o

5) Cold les Temp is at the saturation temp for El '

the prevailing SG Pressure.

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me In addition to the above criteria, natural circulation wo is NOT APPLICABLE unless all RCP breakers are open. "

Each RC loop is checked and determined to see if it is in natural circulation based on the criteria above.

If all loops are in natural circulation, the displau will Fl=: F 2 = F ._' M F3=

F4= F5= F6=

KBD=HORMAL RMODE= POWER OPERATION PLHT

DEC 11,1990

• SELECT FUNCTION KEY OR HELP FILE WWWNEMMW 10:40:41

. HELP PAGE FOR SPTOP show SATISFIED in green. If only two loops are in natural cire. the display will show SATISFIED in vellow. If only one RC Loop is in Natural Cire. the dispia9 will show SATISFIED in orange. If no loops are in natural circulation the display will show HOT SATISFIED in red.. There is a 5 minute delay after the RCP breakers open prior to .I a proper natural circ. indication. Until that time, the display will indicate NOT APPLICABLE.

Heat Si nk ( Feed & Bleed) -- either REQUIRED or HOT REQUIRED.

This message alerts the operator that Feed & Bleed per EOP-15.0 may be necessary. The underiving assumption is that the Steam Generators are not serving as a viable heat sink and additional heat removal capabilities may be required. This occurs if 2 of 3 Steam Generator Levels are < 10% OR Primary Pressure > 2335 with loss of Heat Sink as indicated by a RED Heat Sink CSF Status.

By each parameter on the top level display and asterisk may or may not appear. This is the suspect tag for computer points and is usually used to indicate a calculated point which uses several inputs did not use all of them to perform the calculation. An example of this would be Average SG Level where 3 inputs are averaged. If one of the input levels is bad, it will not be used, the level calculated using the other two inputs,and the resultant value tagged as suspect.

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KBD=HORMAL AMODE= POWER OPERATION PLHT

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Attachment 3 Keyboard / Keypad Layouts

i

' 51 ANT ARD VT220 l<EYBOARD LAYOUT

/ '

i GRP GRP GRP GRP GRP GRP MAP ZZ OF5 SPDS St31 PJL RBU RAOC LIB AS DIS B TND 1

LOG AFDCALM MENU 2P51 MENU 4RW1 LMT  !

I I I ll l 1 I E 11 I I I I E ll 11IrRvil c^Nc !I ll 11 Il ,

F1 F2 F3 F4 F5 F6 A PPLICA TICeN STANDARD QWERTY KEYBOARD KEYPAD

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SPECIAL FUNCTION KEYPAD LAYOUT l

l 1

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05 06 07 ~80 5 a^o on I WAUf IMI (

09 10 11 12 PRV CANC 13 14 15 '16 F1 F2. F3 17 18- 19 20- F4 F5 F6

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21 22 23 24 -  :: -/\ E i- -

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Attachment 4 Emergency Operating Procedure EOP 12 9

4