TXX-4283, Forwards Response to NRC 840807 Request for Addl Info Re Safety Parameter Display Sys.List of Parameters Available in Each Mode of Operation (Normal,Heat Up/Cool Down &/Or Cold Shutdown) Encl

Forwards Response to NRC 840807 Request for Addl Info Re Safety Parameter Display Sys.List of Parameters Available in Each Mode of Operation (Normal,Heat Up/Cool Down &/Or Cold Shutdown) Encl

ML20095G772
Person / Time
Site:	Comanche Peak
Issue date:	08/24/1984
From:	Schmidt H TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	Youngblood B Office of Nuclear Reactor Regulation
References
TXX-4283, NUDOCS 8408280190
Download: ML20095G772 (24)

Text

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e -1 1 YEXAS UTILITIES G5'NERATING COMPANY Log # TXX-4283 m'"

xvw4r rowsn . noo .murn ou t e nruxx1. i..n. n . maa..w.1xx4 File # 10010 919 August 24, 1984 Director of Nuclear Reactor Regulation Attention: Mr. B. J. Youngblood, Chief Licensing Branch No.1 Division'of Licensing .

U. S. Nuclear Regulatory Commission' thshington, D.C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION DOCKET NOS. 50-445 AND 50-446 RESPONSE TO QUESTIONS ON THE SAFETY PARAMETER DISPLAY SYSTEM REF: (1) B. J. Youngblood to M. D. Spence letter of August 7,1984, entitled " Request for AdditionaT Information Concerning the Safety Parameier Display System (SPDS) for Comanche Peak Steam Electric Station (Units 1 and 2)"

Dear Sir; s.

Attached is the response to reference (1). Attachsent A responds to the 3pecific questions. Attachment B is a list of the parameters availaHe in each Mode of Operation (NORMAL, HEAT 'UP/C00L D0WN, and/or CblD SUUTDOWN). Also indicated in the list is if the parameter is trended or available (numerically) in the 1/2 page Accident Indication Displays (AIDS). Also available,on the top level display is,the -

Critical Safety Function Monitor (CSFH), summary for each tree'. In s the message area of the top level display are indications of Power, AUCT HI Tavg, Start-up rate, etc.

The final Jarameter safety analysin is scheduled for completion mid-Septem)er 1984. Th.is analysis will be submitted when available.

x Respectfully,

• f H. C. Schmidt DRW: tis -

Attachmbnt's Original.+ 40 copies 8408280190 g40824 '

PDR ADOCK 00000445 PDR 8

, A DEVINDON OF rKKAN t*TELETEEN ELECTNir CURtPANY Boo /

\

' ATTACHMENT A CPSES/FSAR QO33.1 SAFETY PARAMETER DISPLAY SYSTEM Each operating reactor shall be provided with a Safety Parameter Display System (SPDS). The Commission approved requirements for an SPDS are defined in NUREG-0737, Supplement 1.. In the Regional Workshops on Generic Letter 82-33 held during March 1983, the NRC discussed these requirements and the staff's review of the SPDS.

The staff reviewed the SPDS description provided by

-Texas Utilities Generating Company (Reference 1). The staff was unable to complete the review because of insufficient information. The following additional information is required to continue the review:

Instrumentation and Control Systems Information

1. Isolation Devices:

Provide the following:

a. For each type of device used to accomplish electrical isolation, describe the specific testing performed to demonstrate that the device is acceptable for its application (s).

This description should include elementary diagrams when necessary to indicate the test configuration and how the maximum credible faults were applied to the devices,

b. Data to verify that the maximum credible faults applied during the test were the maximum voltage / current to which the device 033-1

V)

CPSES/FSAR l

could be exposed, and define how the maximum voltage / current was determined.

c. Data to verify that the maximum credible fault was applied to the output of the device in the transverse mode (between signal and return) and other faults were considered (i.e., open and short circuits).

d. Define the pass / fail acceptance criteria for each type of device,

e. A commitment that the isolation devices comply with the environmental qualifications (10 CFR 50.49) and with the seismic qualifications which were the basis for plant licensing.

f. A description of the measures taken to protect the safety systems from electrical interference (i.e., Electrostatic Coupling, EMI, Common Mode and Crosstalk) that may be generated by the SPDS.

2. Provide conclusions regarding unreviewed safety questions or changes to technical specifications.

The applicant has committed to providing a safety analysis concerning the SPDS prior to fuel load (Reference 2). When that analysis is submitted and the applicant has responded to this request for information, the staff will continue its review process.

033-2

., a CPSES/FSAR REFERENCES 1

1. Amendment 36 to the Comanche Peak FSAR,Section III, A-21 through A-28.

2. Letter to B. J. Youngblood (NRC) from R. J. Gary (TUGCO), dated April 15, 1983.

R033.1 1. Isolation Devices The isolation of the SPDS from safety related devices is described as follows for each type of safety related device that has an input to the SPDS computer system.

1.1 Multiplexed Analog 'and Digital Inputs These inputs are obtained from various systems throughout the plant. Examples of analog signals are: tank levels, system pressures, flow rates, etc. Examples of digital signals are: valve position, breaker position, etc. All multiplexed inputs from safety related devices are routed to their respective (Train A or B) qualified multiplexer cabinets (MUX) located in the environmentally protected cable spread room.

Since the output of the qualified multiplexers is used as input to tha non-qualified SPDS computer system, an appropriate qualified isolation device was chosen that would electrically isolate the MUXs from the SPDS and also allow the rapid transmission of data. Fiber Optic Cable (F0C) was chosen as the isolation device. F0C provides optical coupling and is totally immune to all 033-3

f' a w CPSES/FSAR types of electrical interference (i.e., -I electrostatic coupling, electro-magnetic i interference,- RF interference, cross talk, etc. )

that. might otherwise affect the safety device.

All credible adverse conditions were considered

- and tested per specifications given in the qualification test report. The isolation devices are in compliance with applicable NRC ' guidelines and IEEE standards for environmental and seismic qualification' and the entire MJX system is

- designed and qualified for " fail-safe" operation.

L 1.2 Core Cooling Monitor Inputs t

.The inputs to the SPDS- from the core exit thermocouples and the Margin to Saturation indicator is by way_ of the two (Train A and Train

- B) qualified safety related Core Cooling Monitors (CCM). The input signal from each CCM is an ,

optically isolated ASCII character string transmitted on a standard RS232 data link. The optical isolation between the safety related circuits and the non-qualified data link is 4

accomplished within the CCM itself using a qualified optical isolator which provides electrical isolation and rapid data transmission.

All credible adverse conditions were considered and tested per specifications given in the qualification test report. The isolation devices are in compliance with applicable NRC guidelines and IEEE standards ~ for environmental and seismic qualification and the entire CCM system is designed for "f:ii-safe" operation.

033-4

, ,+ -,--w.s, ,w'.--- - - - ---r--r,. , --#_ - . - - . e , .- , . -+ - -

CPSES/FSAR 1.3 Radiation Monitoring System Inputs All' inputs to the SPDS from the Radiation Monitoring System (RMS) are transmitted as ASCII data from the RMS computer system. (Except for containment radiation inputs which are routed to the multiplexers described in section 1.1 above.)

The RMS computers are non-safety related devices

- therefore no provision for electrical isolation between them and the SPDS is required.

1.4 Reactor Vessel Level Indication System Inputs All inputs to the SPDS from the qualified Reactor Yessel Level Indication System (RVLIS) are transmitted as ASCII data through a fiber optic cable (FOC) data link from the qualified, safety related RVLIS cabinet to the SPDS computer system.

F0C was chosen as the electrical isolation device for the reasons given in 1.1 above. All credible adverse conditions were considered and tested per specifications given in the qualification test reports. The isolation devices are in compliance with applicable NRC guidelines and IEEE standards for environmental and seismic qualification and the entire RVLIS system is designed for

" fail-safe" operation.

2.0 Safety Question / Technical Specification All portions of the SPDS have been designed and specified such that all design basis safety questions have been considered. The SPDS, as

-implemented at CPSES Units 1 and 2, 033-5

[ . -a CPSES/FSAR

1. does not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the FSAR,

2. does not create the possibility for an accident or malfunction of a different type than any evaluated previously in the FSAR, or

.3. does not reduce the margin of safety as defined in the technical specifications.

No changes to the CPSES Unit 1 or Unit 2 Technical Specifications have been effected by the addition of the SPDS.

Reference 2 did not include a commitment to submit the parameter safety analysis; however, in response to this question, the analysis will be submitted by separate letter when completed.

033-6 l

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- ATTACHMENT B' MODES AIDS TRENDS '- (Is HR)'

(2.Hr. Trend).

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.PRZR LVL~ .X X LOCA X SGTR LOSC

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SGTR ICC SG NR LVL 4 X X LOSC X SGTR ICC SG PRESS 1 X X LOSC X SG PRESS 2 X X LOSC X SG PRESS 3- X X LOSC X SG PRESS 4 X X LOSC X SEC RAD TARGET X X-(a) COND OFF GAS- SGTR X (b) SG BLDN RAD SGTR' X CNTMT. ATMOS TARGET X X (a) PRESSURE-~ LOCA X SGTR LOSC (b) TEMP LOCA X SGTR-LOSC

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-4 MODES AIDS TRENDS (15 HR)

(2 Hr. Trend)

INPUT PARAMETER NORMAL HU/CLDN CLD SHTDN

'(c) WTR LVL LOCA X (d) HUMIDITY LOCA X SGTR LOSC' CNTMT RAD X X LOCA X

-RV LVL X X X ICC X MARGIN TO SATURATION X X ICC X CORE EXIT TEMP X X X ICC X-SR A X SR B. X RHR FLOW A.- X RHR FLOW B X ,

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LOWEST SG NR LVL LOSC LOWEST SG PRESS LOSC 2-

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