ML20098H085

Informs of Current Status of Procurement of New Computer Sys,Which Is Part of Safety Assessment Sys.Revised Schedule for Development,Installation,Startup/Testing & Operation of New Computer Sys Will Be Provided by End of 1984

ML20098H085
Person / Time
Site:	Point Beach
Issue date:	10/01/1984
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	Harold Denton, John Miller Office of Nuclear Reactor Regulation
References
NUDOCS 8410090352
Download: ML20098H085 (17)

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- 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 October 1, 1984 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S.. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 Attention: Mr. J. R. Miller, Chief Operating Reactors, Branch 3 Gentlemen:

DOCKET NOS. 50-266 AND 50-301 NEW PLANT COMPUTER SYSTEM POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Our March 8, 1984 letter provided the most recent achedule for the installation of the Safety Assessment System (SAS)

(our version of the Safety Parameter Display System). The purpose of this letter is to inform you of the current status of the procurement of the new computer system, of which the SAS is a part, for installation at our Point Beach Nuclear Plant.

Recently, the contract with Electronic Associates, Inc.

(EAI), for the manufacturing and furnishing of the new plant computer system was terminated because EAI was unable to meet

, the terms and conditions of the contract 'or reasons not attributable to Wisconsin Electric. Mr. T. G. Colburn, the NRC Project Manager for Point Beach, was informed of the contract termination in a telephone conversation with Mr. C. W. Krause of Wisconsin Electric on August 3, 1984.

Currently, we are performing a status evaluation of all of the system hardware and software which were removed from EAI. The results of this evalua2 ion will be used to request proposals from other contractors to complete the system and software work. We expect to have a new contractor identified and a contract signed by the er.d of 1984. At that time, we will be cble to provide a revised schedule for the development, installation, startup/ testing, and operation of the new computer system. With these circumstances, it is very unlikely that we wl'll be able to meet the SAS completion date of December 31, 1985 contained in the NRC Confirmatory Order dated July 3, 1984.

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October 1, 1984 x- This delay in' the ~ installation of 'our new computer system Swillcalso affect the completion of several.other items identified

.inethe' July 3,-1984 Order. These items include. Technical Support

- '  ; Center (TSC). data, Emergency Operations Facility (EOF) data, real: time,'off-site meteorological monitoring and dose assessment,

~ Regulatory; Guide 1.97 parameters, thermocouple monitoring and

+ Jprocessing, and the' Radiation' Monitoring System. The following

. is' a -discussion of the effects and -the' compensatory actions we have?taken, Hor will take,fto mitigate these effects:

. l .1 Safety Assessment System-

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As described -in previous correspondence, the SAS is

.~' - designed to: fulfill ~the. requirements of NUREG-0737, Item. I.D.2,lPlant = Safety- Parameter Display Console.

'The SAS willLnot be complete'until the new plant

-computer' system is installed. However, to a certain extent, . the Auxiliary Safety Instrumentation Panels (ASIP ' s) which we.are currently installing are a seismically designed, analog equivalent to the.SAS. (A list of the recorders' available in the control room, a list of ASIP . instruments, and a drawing of each of the two ASIP's'are. attached.) The analog strip chart recorders available gn each of the two ASIP's will allow us to record and trend some parameters not currently recorded in the control room but which will be recorded by the new computer system. These include selected core exit thermocouple averages, subcooling, and wide and narrow range reactor vessel water level..

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2. Technical Support Center Data

~

Because the final TSC instrumentation displays are an integral part of the'new computer output display ~ system, ~

~t' final operability of the TSC is dependent upon the new

. computer system. The plant' parameters currently l

displayed in the TSC, as described in Table 2.2.2.b-2 of our March 14, 1980 submittal and in our March 8, 198^ letter, will continue to be provided using interim loop: configurations. Additionally, an RMS terminal is b .

available in the'TSC to display the status and indications of the RMS..

, 3. Emergency Operations Facility Data As with the TSC, the EOF instrumentation displays a.e an integral part of the computer output display system.

Final operability of the EOF'is, therefore, dependent upon the computer. Currently, we use a high speed telecopier to update plant status at the EOF. This c

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Mr. H. R. Denton ' October 1, 1984 mechanism for providing plant status was demonstrated during the. September 11, 1984 emergency drill held at the plant and proved.to be effective. This practice will be continued until the computer system is operational.

4.- ~O ff-Site Dose Assessment The new computer. system will automatically receive RMS~and MET data and will perform off-site dose assessments.

Currently, these assessments are performed using a

program in the Corporate computer system with manual input of MET and.RMS data. The dose assessment methodology used.in this program is the.same as that which will be used in conjunction with the Class A model to perform dose assessments 'using the new computer.

This manual-input to the Corporate. computer system will continue to be used until the new computer system is operational.

5. Regulatory Guide 1.97 Parameters Numerous Regulatory Guide 1.97 parameters, as listed in I our September 1, 1983 submittal, will be displayed on 'either the SAS CRT or the Plant Process Computer System CRT. Additionally, the new computer system will record those parameters not presently recorded in the control room. The analog display of these parameters is currently, or will be, available in the control room when the ASIP's and the thermocouple monitoring process rack equipmcat, mentioned in Item 6 below,'are installed. Therefore, the computer system delay will essentially affect only the backup CRT display configuration of Regulatory Guide 1.97 instrumentation and the historical recording of those parameters which are not already recorded in the control room. Reactor Coolant System (RCS) wide-range loop temperaturc, RCS wide-range pressure, and steam generator wide-range water level are already recorded in the control room on strip chart recorders.

Certain additional parameters, including RCS subcooling, core exit thermoccuple temperature, and compensated reactor vessel water level, will be temporarily displayed and recorded on dedicated ASIP recorders as noted in Item 1 above.

6. Thermocouple Monitoring and Processing In view of the delays in the installation of the new computer system, we have purchased and are installing

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[Mr. H.'R.[Denton- -4 . October 1, 1984

.new thermocouple monitoring equipment in the Foxboro SPEC 200' process racks. This equipment will enable us :to display and record several parameters on the

, ASIP's'which would have otherwise been unavailable until

- the new computer system is operational. These parameters are reactor coolant system subcooling and averaged -

thermocouple readings based on selected. core exit thermocouples and compensated reactor vessel level.

7. 'RMS and MET-Monitoring

. Currently, all MET data which would be available through the computer are availablecin the control room on analog strip chart recorders. There are no remote MET

-displays inleither the TSC or the EOF. MET information is relayed to the TSC'and EOFLby telephone. All RMS lista are available -through the RMS displays in both the control room and the TSC. RMS' data are relayed to the EOF through the use of a high speed telecopier or the telephone.

In summary, any delay in the installation of the new computer system will af fect a number of items. However, we believe that our previous compensatory actions and the additional steps we are now taking are sufficient to mitigate the effects of. the delay. We will continue to keep you informed of the status of the new computer and will provide a revised schedule as soon as a new contractor is chosen and a new schedule is

available. Should you.have any questions concerning this

'information, please contact us.

Very truly yours, Vice President-Nuclear Power C. W. Fay Attachment' Copy.to NRC Resident Inspector

TABLE 1 CONTROL ROOM RECORDEPS (After ASIP's are Installed)

Location No. of Pens Description / Application Range Units UNIT 1

1. 1-C04 (Main Control Board) 3 RCS Wide-Range Pressure 0-3000 PSIG (LOOP A)

RCS Wide-Range Pressure 0-3000 PSIG (LOOP A)

RCS Wide-Range Pressure 0-3000 PSIG (LOOP B.

2 1-C04 (Main Control Board) 2 RCS Cold Leg Temperature 50-750 Deg. F (LOOP A)

RCS Hot Leg Temperature 50-750 Deg. F (LOOP A)

3. 1-C04 (Main Control Board) 2 RCS Cold Leg Temperature 50-750 Deg. F (LOOP B)

RCS Hot leg Temperature 50-750 Deg. F (LOOP B)

4. 1-CO3 (Main Control Board) 2 S/G "A" Nide-Range Water 0-520 Inches Level S/G "A" Wide-Range Water 0-520 Inches Level

5. 1-C03 (Main Control Board) 2 S/G "B" Wide-Range Water 0-520 Inches Level S/B "B" Wide-Range Water 0-520 Inches Level

=,

4 Tabla 1 continuede Location No. of Pens Description / Application Range Units

6. 1-C20 (ASIP) 1 Containment Wide-Range -5 to 195 PSIG Pressure

7. 1-C20 (ASIP) 1 Containment Wide-Range -5 to 195 PSIG Pressure

8. 1-C20 (ASIP) 2 (Computer Trend Recorder)* 0-100  %

(Computer Trend Recorder)* 0-100  %

9. 1-C20 (ASIP) 2 (Computer Trend Recorder)

• 0-100  %

(Computer Trend Recorder)* 0-100  %

10. 1-C20 (ASIP) 2 (Computer Trend Recorder)* 0-100  %

(Computer Trend Recorder)* 0-100  %

11. 1-C20 (ASIP) 2 (Computer Trend Recorder)* 0-100  %

(Computer Trend Recorder)* 0-100  %

UNIT 2

12. 2-C04 (Main Control Board) 3 RCS Wide-Range Pressure 0-3000 PSIG (LOOP A)

RCS Wide-Range Pressure 0-3000 PSIG (LOOP A)

RCS Wide-Range Pressure 0-3000 PSIG (LOOP B)

13. 2-C04 (Main Control Board) 2 RCS Cold Leg Temperature 50-750 Deg. F (LOOP A)

RCS Hot Leg Temperature 50-750 Deg. F (LOOP A)

__m Tabli' 1 continued.

Location No.<f Pena Description /Applic^ tion Range Units  !

14. 2-C04 (Main Control- Board) 2 RCS Cold Leg Temperature 50-750 Deg. F (LOOP B)

RCS Hot Leg Temperature 50-750 Deg. F (LOOP B)

15. 2-C03 (Main Control Board) 2 S/G "A" Wide-Range Water 0-520 Inches Level S/G "A" Wide-Range Water 0-520 Inches Level

16. 2-C03 (Main Control Board) 2 S/G "B" Wide-Range Water 0-520 Inches Level

17. 2-C20 (ASIP) 1 Containment Wide-Range -5 to 195 PSIG Pressure

18. 2-C20 (ASIP) 1 Containment Wide-Range -5 to 195 PSIG Pressure

19. 2-C20 (ASIP) 2 (Computer Trend Recorder)* 0-100  %

(Computer Trend Recorder)* 0-100  %

20. 2-C20 (ASIP) 2 (Computer Trend Recorder)* 0-100  %

(Computer Trend Recorder)* 0-100  %

21. 2-C20 (ASIP) 2 (Computer Trend Recorder)* 0-100  %

(Computer Trend Recorder)* 0-100  %

22. 2-C20 (ASIP) 2 (Computer Trend Recorder)* 0-100  %

(Computer Trend Recorder)* 0-100  %

CThese recorders will be used to trend computer-stored data when the new computer system is installed. In the interim, selected core exit thermoccuple average temperature, RCS cubcooling based on wide-range loop or selected core exit thermocouple average temperature, and wide and narrow range compensated reactor vessel level for each unit will be displayed using these recorders.

y TABLE 2 H ASIP ' (IC20 AND 2C20)INSTREMENTATION AND RANGES l

l Indicator Unit- Range Engineering Units' i !i

1. Containment High-Range Radiation. 1& 2 'l-10 8' R/HR.

2. RCS Wide-Range Pressure 1 &'2 0-3000 PSIG

3. RCS Cold Leg Wide-Range Temperature- 1& 2 50-750 Deg. F

4. RCS Hot Leg Wide-Range Temperature 1& 2 50-750 -Deg. F

5. Steam Generator Wide-Range Level 1& 2 0-520 Inches

6. Reactor. Vessel Wide-Range Water Level 1&2 0-125 Feet

7. Reactor Vessel Narrow-Range Water 1& 2 0-45 , Feet.

Level ,

l 8. RCS Gas Vent Pressure 1&2 0-3000 PSIG

9. Containment Wide-Range' Pressure 1& 2 -5 to 195 PSIG l

l 10. Cortiinment Sump-"A" Level 1& 2 0-90 Inches l

11. Containment Sump "B" Level 1& 2 0-90 Inches

12. Containment Hydrogen Concentration 1&2 0-10 Percent

13. Containment Air Temperature 1& 2 50-350 Deg. F

14. Containment Sump "B" Temperature ] & 2 50-350 Deg. F

15. 120 VAC Instrument Bus voltage 2 0-150 AC Volts l

l 16. 125 VDC-Instrument Bus Voltage 2 0-150 DC Volts i 17. Battery Charge-Discharge Amps 2 100-0-1000 DC Amps I

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e TABLE 3 UNIT 1 ASIP (1C20) ITEM IDENTIFICATION LIST (Indicators Unless Noted)

Number On Drawirg Identification lA-B Reactor Vessel Head Vent Valve Controls IC-D Pressurizer Vent Valve Controls lE Combined RCS Vent to PRT - Vent Valve Control IF Combined RCS Vent to Containment - Vent Valve Control 2 Status Indicator Lights (Green) 3 Status Indicator Lights (Red) 4 Status Indicator Lignts (White) 5 Status Indicator Lights (Yellow) 6A-B RCS Hot Leg Temperature - Loop A 6C-D RCS Hot Leg Temperature - Loop B 7A-B RCS Cold Leg Temperature - Loop A 7C-D RCS Cold Leg Temperature - Loop B BA RCS Wide-Range Pressure - Loop A 8B-C RCS Wide-Range Pressure - Loop B

9A-C Containment High-Range Radiation 10A-B Wide-Range Containment Pressure llA-D Containment Hydrogen Concentration 12 RCS Gas Vent Header Pressure 13A-B Reactor Vessel Wide-Range Level 14A-B Reactor Vessel Narrow-Range Level 15A-B Containment Sump B Level 16A-B Containment Sump A Level 17A Subcooling Margin - Loop A 17B Subcooling Margin - Loop B 18 Radiation Monitoring System Alarm Acknowledge Pushbutton 20A-D Annunciator Panels 23-26 Annunciator Acknowledge Pushbuttons 27A-B Plant Process Computer System Displays (Later) 31A-B Subcooling Monitor RTD - T/C Selector Switches i

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Number On Drawing Identification 32A Containment Temperature Foot' Elevation j 32B . Containment Temperature Foot Elevation-l 34A-B Containment Sump Temperature Foot Elevation

35A-B Steam Generator A Wide-Range Level 35C-D Steam Generator B Wide-Range Level 38 LED Matrix Computer Display Panel (Later) 40A-B Containment Wide-Range Pressure Recorders 41A-D Computer Trend Recorders j 48 1RE-211/212 - Sample Exhaust Switch 49 1RE-211/212 - Mode Select Switch 50 1RE-211/212 - Sample Pump Switch 51 .1RE-211/212 - Containment Vent Switch-52-53 l Pressurizer Safety Valve Position Indicators i

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. i TABLE 4 UNIT 2 ASIP (2C20) ITEM IDENTIFICATION LIST (Indicators Unless Noted)

Number On Drawing Identification lA-B Reactor Vessel Head Vent Valve Controls IC-D Pressurizer Vent Valve Controls IE Combined RCS Vent to PRT - Vent Valve Control 1F Combined RCS Vent to Containment - Vent Valve Control 2 Status Indicator Lights (Green) 3 Status Indicator Lights (Red) 4 Status Indicator Lights (White) 5 Status Indicator Lights (Yellow) 6A-H Battery Charger Feeder Control Switch 7A-B RCS Hot Leg Temperature - Loop A 7C-D RCS Hot Leg Temperature - Loop B BA-B RCS Cold Leg Temperature - Loop A 8C-D RCS Cold Leg Temperature - Loop B 9A Wide-Range RCS Pressure - Loop A 9B-C Wide-Range RCS Pressure - Loop B 10A-C Containment High-Range Radiation llA-B Containment Wide-Range Pressure 12A-D Containment Hydrogen Concentration 12 RCS Gas Vent Header Pressure 14A-B Reactor Vessel Wide-Range Level 15A-B Reactor Vessel Narrow-Range Level 16A-B Containment Sump B Level 17A-B Containment Sump A Level 18A-R 120 VAC Instrument Bus Voltmeters 13A-D 125 VDC Bus Voltmeters 20A-D Battery Charge / Discharge Ammeters 21A Subcooling Margin - Loop A 21B Subcooling Margin - Loop B 24A-D Annunciator Panels 27-30 Annunciator Acknowledge Pushbuttons

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Number On Drawing Identification 32A-B Subcooling Monitor RTD-T/C Selector Switches-33A Containment Temperature Foot Elevation 33B Containment. Temperature Foot Elevation

-35A-B Containment Sump B Temperature - ll-Foot Elevation 36A-B Steam Generator A Wide-Range Temperature

-36C-D Steam Generator B Wide-Range Temperature

'41 . LED Matrix Computer Display Panel (Later) 43A-B. Wide-Range Containment Pressure Recorders 44A-D Computer Trend Recorders 53 2RE-211/212 - Sample. Exhaust Switch 54 2RE-211/212 ' Mode Select Switch 55 2RE-211/212 -~ Sample Pump Switch 56 2RE-211/212 - Containment Vent Switch 57-58 Pressurizer Safety Valve Position Indicators

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