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

Responds to WR Butler Re Activities Supporting First Refueling Outage.Encls Provide Expected Schedules for Currently Identified Activities Requiring NRC Action

ML20206C567
Person / Time
Site:	River Bend
Issue date:	03/26/1987
From:	Booker J GULF STATES UTILITIES CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-83-28, GL-86-10, RBG-25559, NUDOCS 8704130089
Download: ML20206C567 (5)

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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

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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

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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

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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 ,

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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

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