ML19331D590

Forwards Request for Addl Info Re Instrumentation & Control Sys in Order to Complete Evaluation of Facility FSAR

ML19331D590
Person / Time
Site:	South Texas
Issue date:	08/15/1980
From:	Tedesco R Office of Nuclear Reactor Regulation
To:	Oprea G HOUSTON LIGHTING & POWER CO.
References
NUDOCS 8009030272
Download: ML19331D590 (9)

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THIS DOCUMENT CONTAINS P00R QUAUTY PAGES y'

AUG 151920 DISTRIBUTION W/ ENCLOSURE:

Docket File R. Tedesco D. SuTlivan NRC PDR A. Schwencer c

P Docket No. STN 50-498/499 p 9 r ce D. Eisenhut IE (3)

R. Purple Mr. G. W. Oprea, Jr.

BCC: ACRS (16)

Executive Vice President NSIC Houston Lighting and Pcwer Company TERA P. O. Box 1700

/

Houston, Texas 77001

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION As a result of our continuing review of the South Texas Project FSAR, we find that we need additional information to complete our evaluation. The specific information required is in the area of instrumentation and control systems and is listed in the Enclosure to this letter.

To maintain the review schedule it is important for you to respond to this request promptly. Since this portion of the review is being conducted fcr the staff at ORNL, please provide a copy directly to J. Anderson concurrent with your submittal to NRC.

Please infom us when you plan to submit your responses to this request.

If you desire any discussion or clarification of the enclosed request, contact D. Sells, (301) 492-7792, the Project Managar.

Sincerely, Original s'4ned by Robert L. Tedesco, Assistant Director for Licensing Division of Licensing

Enclosure:

As stated cc w/ enclosure:

See next page 8009030

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Et! CLOSURE REQUEST FOR ADDlTIONAL INFORMATION ~2.0 INSTRUMENTATION AND CONTR(L SYSTEMS BRANCH' 32.24 Please provide a discussion of how your design conforns to the i i following Regulatory Guides identified in the standard review r plan Section 7.1. 1 (1) R. G. 1.12, Instrumentation for Earthquakes (2) R. G. l.45, Reactor Coolant Pressure Boundary Leakage Detection Sys tems (3) R. G. 1.67, Installation of Overpressure Protection Devices. 22.25 In Section 7.1.2.6, ccnformance to Regulatory Guide 1.47 is discussed. Provide justification for not including in the list, the safety-related systems, such as the Containment Recirculation and Ventilation System, the Eattery Room Ventilation System, the Fuel Handling Suilding Ventilation System, and the Chill Water System. 22.26 In accordance with the Standard Review Flan Section 7.1, please cross reference in Table 7.1-1 the discussions presented in - Sections 7.4, 7.5 and 7.7 describing confcrcance to IEEE Sta. 279-1971. 32.27 With regard to remote shutde,n panels, describe the criteria for the ir.s talla: ice and routing cf instrumentaticn and control circuitries between thes e panels and the ain cor. trol room cen:roi boards. O i 4

O . ? 32.28 In Section 7.2.1.1.3 it is stated that the manual trip consists of E "' two switches with two outputs on each switch. One output from each switch is used to actuate the train A trip breaker while, ~ the other output actuates the train B trip breaker. Explain how this design: (a) satisfies the Single Failure Criterion for redundant trains and (b) satisfies the separation reouirements for redundant trains. _.._, ____32.29 Describe the Reactor Coolant System Wide Range Pressure Measure:r.ent System including number of senscrs, manufacturer, Model number, sensor location and installation arrangements. If the sensors are located outside the containment, describe hcw this system design confcrms to recornendations of R. G.1.11 (instrument Lines Penetrating Primary Reactor Containment) or justify any exceptions taken. 32.30 It is stated in Section 7.2.2.2.3 that the power range channels are tested by superimposing a test signal cn the detector signal being received by the 05annel at the time of testing. Basec on this information, we are unable to concluce that the p:aer range high neutron flux rate reactor trip circuitry is ade:Lately tes:ec to verify its performance capability. Provide a detailed discussi n of h:w this ;;rtien of the nuclear instrumen:ation is periodicali;. tested. I s E

T i 3 32.31 Describe the design basis, and separation and isolation criteria l a i b for: (a) " Reactor trip,en turbine trip" circuitry. Also provide 6 1

• detailed cable routing diagrams for this trip circuitry frca the p

sensor in the turbine building to the final actuation located in i. the reactor-trip system. (b) the circuitries from Reac or Trip System to the 3,0? devices in the Turbine / Auxiliary Building. i 32.32 Identify all remotely controlled valves in the Engineered Safety l Features ~ Eys-te s w1iich recuire power iocicut during a certain mode of cperation of the sys tem to satisfy single failure criterien. It is the staff's positien tnat your design shculo also satisfy the Eranch Te:hnical p:si icns EIC5-4 and EICSS-IS. Provide detailed ces:riptions, with schematic diagrams fcr the circuitry associated d witn these valves, illustrating how the above stated staff positions are satisfied in tne design. i 4 32.23 Figure 10.4.9-1 d:es rc: prcvide suffi:ien; information on control as;e::s per: lining to the auxiliary fees.ater system. Frevide a r cescri;ti:n :f the ins:Nmentaticn an: c:ntrais assetiated.ei th the auto atic ac:uation cf :ne auxiliary feed. cater system. Frovide ar.alyses in:iuding a fai'ure m:de anc effects analysis for the electricai, ins trurer.:a:Ln anc ::n:r:' ;;rtien of tne syr:er to I

r.or.stra:e h:s :ne re:.irements of IEEE 5td 279-1971 are s a tis fi ed.

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1 ' y 32.36 Describe the automatic features for switchiiig from the injec' tion mode to the recirculation mode which are provided to assure the proper operaticn of safety injection system and containment heat removal sistem. Your response should include related logic l diagraus, schematic diagrams, and the status indication i-information available to the operator in the control room. i i l 32.37 Provide the LOCA and the MSL5 accident environmental envelope inside the containment to verify the adequacy of the aalification - - - of the Class lE equipment required to mitigate these events. 32.38 In Section 9.2.2.2.1, it is stated that co: ponent cooling water i (CCW) is not supplied to RHR and containment spray heat exchangers during normal piant cperation. (a) Describe your design of initiation circuitry, control room i j indication and/or alarm circuitries utilized for this portion of CCW system, j (b) Frovide analyses, including a failure mode and effects l analysis, to demonstrate that the instrumentation and control I portiens relied upon to establish cc penent cooling water to l these safeguards systems will satisfy IEEE Std. 279-1971. l (c) Frovide a periodic tese plan for these circuitries to satisfy the racc=endations of R. G.1.22. L

5-7 32.39 It is stated in Section 7.4 that there are no identifiable safe shutdcwn systems per se. The applicant should clearly identify those systems that are required for safe shutdown of the reactor. The applicant should also provide a discussion cf hcw the instrumentation anc control portiens of the safe shutd:wn systems conform to the following acceptar.ce criteria scated in Part II of Secticn 7.4 of SRP. (1) have the required reduncancy ( c. ) meet the sing.te rai.sure critericn (3) have the required capacity anc reliability to perfcrm intended safety functions en demand. f., ej are c;;aole or..ranctiontr,g caring anc arter certain design basis events such as earthquakes, accicent, anc antici;ated operational occurrences. (.= ), .=r =.

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- - __ _.. ~. 4 7-i 32.41 We deduce from figures 7.2-3 and 7.2-4 that a single failure of the P-6 signal generation circuitry so that P-6 is energized

.5 at a power level lower than the P-6 setpoint places the reactor system in jeopardy. The operator can block out the source range trip at power levels for which it was intended for protection.

In' addition, the trip circuitry will not reset as the power level decreases below the P-6 setpoint during a 4. pcwer reduction. This appears to violate the single failure cri terion. Bring your system in compliance with the single failure criterion or justify not so doing. J h O i s -,,,--.....,,,..,..,-,,-,,-2.,-, -. -,..,.,-. --..}}