View source for RBG-25559, Responds to WR Butler Re Activities Supporting First Refueling Outage.Encls Provide Expected Schedules for Currently Identified Activities Requiring NRC Action

{{Adams
| number = ML20206C567
| issue date = 03/26/1987
| title = Responds to WR Butler Re Activities Supporting First Refueling Outage.Encls Provide Expected Schedules for Currently Identified Activities Requiring NRC Action
| author name = Booker J
| author affiliation = GULF STATES UTILITIES CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000458
| license number = 
| contact person = 
| document report number = GL-83-28, GL-86-10, RBG-25559, NUDOCS 8704130089
| title reference date = 02-25-1987
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 5
}}

=Text=
{{#Wiki_filter:_ _ - - _ - - - _ _ - - - _ _ _
GULF STATES                      UTILITIES COMPANY POSTOFFICEGoX220 e ST.FRANCISVILLE,LOUISlANA7o775 AREACODE 5q4 635 3237             387 4257 March 26, 1987 RBG- 2S5S9 File No. G9.5 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:
River Bend Station - Unit 1 Docket No. 50-458 In response to the letter from Mr. W. R. Butler, dated February 25, 1987, Gulf States Utilities Company (GSU) provides the                      enclosed information regarding activities in support of the River Bend Station (RBS) first refueling outage.             The enclosed attachments provide the expected schedules for currently identified activities which require NRC staff action to support the RBS first refueling                     outage. This information is intended to be a comprehensive listing of currently identified activities. Should additional activities require special attention prior to startup following the first refueling outage, GSU will promptly notify the NRC Staff RBS Project Manager.
Your efforts in support of the attached listing of related activities is appreciated.        If additional information is required, please contact Mr.
Eddie R. Grant, Director - Nuclear Licensing, at (504) 635-6995.
Sincerely,
                                                               , F. k % d p J. E. Booker Manager-River Bend Oversight River Bend Nuclear Group JEB/ ERG /RJK/je Attachments 8704130009 G70326 PDR   ADOCK 05000458 p                     PDR 6
I

ATTACHMENT I. License Condition (LC) Items LC 2.C(1) - Attachment 1 Item 2a, Fuel Bldg. Sampling System Complete Package to Region IV for review                                                   5-30-87 Item 3a, Load Handling Capability Test Complete-Package to Region IV for review                                                   5-30-87 Item 4a, HVAC Chiller Control Valves Package to Region IV for review                                                   During RFl Item 4b, Verify adequate communications -
Package to Region IV for review                                                   5-30-87 LC 2.C(5)b - Mark III Containment Related Issues                                                 ---
Submitted to NRC via RBG-24131 on 7-31-86 NRC Approval Needed by End of RFl LC 2.C(6) - Inservice Inspection Program                                                         ---
Last Submittal to NRC via RBG-25452 on 3-10-87 NRC Approval Needed by 8-29-87 LC 2.C(8) - TDI Diesel Engine requirements                                                       ---
Last Submittal to NRC via RBC-24487 on 9-26-86 NRC Approval Needed by 6-10-87 LC 2.C(9) - Ultimate Heat Sink Temperature Monitoring Submittal for Staff Review                                                                  4-30-87 LC 2.D(14) - Attachment 5 Item 2 - R.G. 1.97 Neutron Flux Instrumentation Submittal                                                      4-30-87 LC 2.C(15) Salem ATWS Event Generic Letter 83-28 Submittal                                                              9-30-87

II. Technical Specification Change Requests A. Required to Support RF1 APRM Frequency                          Submitted 2-19-87 RBG-25368                         Need by 3-30-87 Scram Discharge Volume Instrumentation  Submitted 1-28-87 RBG-25277                         Need by 6-10-87 Supplement Required               Submittal by 4-10-87 Drywell Bypass Leakage
: 1. 4.0.2 Applicable               Submitted 1-28-87 RBG-25278                      Need by 4-25-87
: 2. Surveillance frequency         Submitted 3-10-87    l RBC-25461                      Need by 9-11-87 SRV Accoustical Monitoring              Submitted 3-10-87 RBG-25461                         Need by 9-2-87 Supplement Required               Submittal by 4-10-87 Leak Rate Testing                       Submitted 3-10-87 RBG-25461                         Need by 8-4-87 flydrogen Mixing                        Submitted 3-10-87 RBC-25461                         Need by 7-31-87 i
~
ADS                                     Submitted 3-18-87 RBG-25505                         Need by 8-15-87 Drywell Condensate Flow Monitor         Submitted 3-18-87 RBG-25505                         Need by 9-5-87 Main Steam Line-Ili Rad Monitors        Submittal by 4-17-87 Need by 9-4-87 Main Steam Line-Ili Flow Monitors       Submittal by 4-17-87 i Need by 8-22-87 Reactor Water Low Level Instrumentation Submittal by 4-17-87 Need by 8-16-87 PVLCS                                   Submittal by 4-10-87 Need by 9-4-87 ECCS Integrated Testing                 Submittal by 4-17-87 Need by 8-16-87 Functional Testing                      Submittal by 4-17-87  i (Containment Ri1R and RWCU isolation)   Need by 9-7-87 l
l

Reactor Vessel Steam Dome - Hi Press          Submittal by 4-24-87 Need by 8-15-87 ECCS/ ADS Trip                                Submittal by 4-24-87 Need by 8-25-87 ATWS (10CFR50.62)                             Submittal by 6-1-87 Need by End of RF1
.         Reload Changes                                Submittal by 8-1-87 l                                                       Need by End of RF1
}         Section 6 - Engineering Expertise On-Shift    Submittal by 6-1-87 i
B. Others - Not Required for RF1 1
Suppression Pool Pumpback                     Submitted 9-10-86
 ;              RBG-24358 l
Control Rod Block                             Submittal by 4-30-87 1
  ;       Settlement Monitoring                         Submittal by 4-30-87 I
First Stage Turbine Pressure                  Submittal by 4-30-87 Fire Protection (Generic Letter 86-10)        Submittal by 4-30-87 l         Diesel Generator Action Statement             Submittal by 6-1-87 j         Administrative Controla                       Submittal by 6-12-87 I         Hain Steam Line Area Temperature              To Be Determined i
Drywell Average Temperature                   To Be Determined
  !       Leak Detection Isolation Actuation Instrumentation               To Be Determined s
i Main Steam Tunnel Temperature Monitoring      To Be Determined               ,
i f                                                                                     I I
1

III. Other Activities IICOG Analysis Results Status                 4-30-87 Process Control Program Revision              5-1-87 Data Collection Program for Containment Purge Tentative Meeting With Staff            5-15-87 Status Report                           7-1-87 Final Submittal                         Post RF1 Containment Venting Evaluation Report Tentative Meeting with Staff            5-15-87 Evaluation Submittal                    7-15-87 SPDS IIED Status Report                       7-31-87 Inservice Testing Program Relief Requests                                                  .
SSER Section 3.9.6                                                                   l 1
NRC Approval Needed by 8-29-87 l
1            Instrument Setpoint Methodology Report        8-29-87 i
l 1
I I
l l
1 I
I 1
l
,}}