ML20236L598

Forwards Supplemental Info to Util Initial Rept on ATWS Rule,Per Wa Paulson 870916 request.W/30 Oversize Drawings, Including Nine Final Design Changes

ML20236L598
Person / Time
Site:	River Bend
Issue date:	10/30/1987
From:	Booker J GULF STATES UTILITIES CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20236L600	List: ML20265A978 ML20265A983 ML20265A986 ML20265A990 ML20265A995 ML20265A998 ML20265B002 ML20265B007 ML20265B012 ML20265B016 ML20265B020 ML20265B024 ML20265B028 ML20265B031 ML20265B035 ML20265B040 ML20265B046 ML20265B050 ML20265B053 ML20265B058 ML20265B062 RBG-26874, Forwards Supplemental Info to Util Initial Rept on ATWS Rule,Per Wa Paulson 870916 request.W/30 Oversize Drawings, Including Nine Final Design Changes
References
RBG-26874, NUDOCS 8711100444
Download: ML20236L598 (9)

Text

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l GULF STATES UTELITIES COMPANY

j October 30, 1987 RBG- 26874 1 File Nos. G9.5, G9.23, 220.930 j U.S. Nuclear Regulatory Commission i Document Control Desk I Washington, D.C. 20555 Gentlemen

River Bend Station - Unit 1 l Docket No. 50-458 In response to your letter dated September 16, 1987 from W. A. Paulson (NRC) t o J.C. Deddens (GSU), GSU provides the enclosed . supplemental -j information to our initial report -on the Anticipated Transients ,

Without Scram (ATWS) rule (10CFR50.62) .

The enclosures to this letter include functional and elementary diagrams depicting alternate rod insertion (ARI)'and recirculation.  ;

pump trip (RPT), a one line diagram showing power supply to ARI,- RPT '

and the reactor protection system (RPS), a description- of test features of ARI and RPT.. a sketch showing . power ' supplies to.'the recirculation pump motor and a comparison of the RBS.RPT system design to the Monticello design. It is noted that' some of the enclosed s drawings are marked up to show.' design changes being made during this refueling outage. Because field work on these modifications is not complete, file' drawings have not iyet been, revised.

Sincerely, hk J. E. Booker Manager-River Bend Oversight

~ River' Bend Nuclear' Group Attachments r~.

r* D 8711100444 871030 h0 '

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PDR ADOCK 05000458 P PDR L l'

cc: U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 NRC Resident Inspector P.O. Box 1051 St. Francisville, LA 70775

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LIST OF DRAWINGS ENCIASED ARI Logic Diagram Sketch (Attachment 1, Item 1)

One Line Diagram - Power Supply to ARI, RPT, RPS Sketch (Attachment 2, Item 2) l Recire Pump Motor Circuit Breaker Arrangement Sketch (Attachment 4b, Item 4)

Support Drawings Nuclear Boiling Instrumentation P&ID (one sheet) PID-25-1A R5 ARI GE P&ID (1 sheet) 112D3705 R0 (Item 3)

ARI Elementary (8 sheets) 945E747AA* (Item 3)

Reactor Recirculation System Functional (7 sheets) 866E304AA* (Item 1)

Reactor Recirculation System Elementary (13 sheets) 828E446AA* (Item 1)

• These drawings have been marked up to show modifications being made l during the first refueling outage. i l

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ARI Logic Diagram '

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ATTACWENT 1 Item 1 NRC Letter Dated September 16, 1987

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ATTACINENT 2 Item 2 NRC Letter Dated September 16, 1987 i

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l TTACHMENT 3 Item 3 - NRC Letter Dated September 16, 1987 Both the ATWS-RPT and ARI systems are designed to permit "on-line" testing '

without causing an inadvertent trip. J Areas of the listed Elementary diagrams show the electrical circuits ~ which  !

would be activated during the test modes of ATWS-RPT and ARI. Functional i testing of the Low Reactor Water Level 2 and High Reactor Pressure l instrumentation will cause a half ARI Scram. For example, if a simulated low water level signal is input into trip unit B21-N099A, relay K2A will l close. Closure of relay K3A would complete the ARI trip logic. In order to I test the K101A, B, C and D relays, the ATWS-RPT test switches S116A or S116B {'

are placed' in the test position. In order to avoid an ARI Scram during testing, the T3/M3 terminals would be temporarily jumped across relay K3A thus closing the K101A relay for which a test light is available.

The ARI system is capable of being fully tested with the unit at power.

Since the K2A, K3A, K4A, KSA, K2B, K3B, K4B, and KSB relays can be tested as described above, only the ARI test switches S3, S4A and S4B are manipulated to complete the ARI test. This will cause either the inboard or outboard ARI solenoid valves to open causing position indication lights to indicate in the control room.

Calibration of the pressure transmitter and trip units is required only every 18 months. However, if the trip unit is found out of calibration, it.

is possible to adjust the trip and reset values to within tolerance during plant operation.

The capability. of the ATWS-RPT and ARI systems to permit maintenance is dependent upon the scope of work involved. Because the logic is 2-out-of-2, it is possible to perform much work with a half trip in effect. Such work impacting system operability would be subj ect to Technical Specification .

limits for ATWS-RPT equipment. I

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ATTACHMDIT 4a.-

Item 4 - NRC Letter Dated September 16,.198I As discussed in Section 4.3 ;of the RBS ATWS report, the RBS design of ,

recirculation pump trip (RPT) is similar to the Monticello design except in- l the control of the power supply to the recirculation pump motors. Both designs use two-out-of-two initiation logic with two trip logic systems, either of which will trip both recirculation pumps.

As described in NEDE-31096-P-A, the Monticello.idesigniusen M-G. sets to supply power to the recirculation pump motors. Theipumps' are tripped by tripping- the breaker to the generator field. Redundant t'rdp. coils are used to provide breaker reliability.

l The RBS design uses two power supplies at different frequengtes to provide for two speed operation of the pump motors. The primary power supply, used during power operation, is at 60 herer while the secondaryfpower supply is  !

at 15 hertz to allow.for pump operat.jon at one quarter speed during plant start up. The secondary power supply is 'from a low frequency motor. o generator set (LFMG), The primary. power supply is. tripped upon receipt of an ATWS initiation signal by tripping two redundant breakers in the . power s.

m supply to the pump motor. The LFMG power' supply is tripped by opening one breaker. While breaker redundancy is not provided in the LFMG power supply, this does not algnificantly effect recirculation pump trip' reliability in that this power sup' ply is only used for s telatively- 'short prriods 'of -time  !

during plant start-up_ operation. In addition to the automatic initiation. y y~

logic, manual breaker 6peration is'provided in t.he MainJControl Room for;all i q

the subject breakers. :GSU concludes- that the RBS design thus meets the 3 reliability requirements of the ATWS rule.

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