View source for 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

{{Adams
| number = ML20236L598
| issue date = 10/30/1987
| title = Forwards Supplemental Info to Util Initial Rept on ATWS Rule,Per Wa Paulson 870916 request.W/30 Oversize Drawings, Including Nine Final Design Changes
| author name = Booker J
| author affiliation = GULF STATES UTILITIES CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM)
| docket = 05000458
| license number = 
| contact person = 
| document report number = RBG-26874, NUDOCS 8711100444
| package number = ML20236L600
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 9
}}

=Text=
{{#Wiki_filter:I                                                                                      ._
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|date=September 16, 1987|text=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    '
                                                                                          -}
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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ATTACWENT 1 Item 1 NRC Letter Dated September 16, 1987

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                   **        !'    e* 0"    l'  @ @"        INSTRUMENTS          ATVS RELAYS                INSTRUMENTS                 ATVS RELAYS             I l
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                        $hkh#g$E  m oa                        321-N658A B21-N699F K1A,KEA, K3A,K4A D21-N658' h21-N699E                   #3RK43, 321-N658F            K5A                        B21-N65BE -                 K5B hh                g H13-P632                                               H13-P632 66 e i e i"i i gy                                                                                                                        .
5558                  2   55                                                                                                               j ARI SOLENIDD VALVES SIMPLIFIED RIVER . BEND STATION ATVS - RPT AND ARI POVER SUPPLIES 1
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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