ML19261D601

Submits Info Re Design Changes in Emergency Feedwater Automatic Actuation Logic & Flow Control Valve Hand Switches in Control Room,Addl Operator Training & Procedural Changes

ML19261D601
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/13/1979
From:	Trimble D ARKANSAS POWER & LIGHT CO.
To:	Reid R Office of Nuclear Reactor Regulation
References
1-069-9, 1-69-9, NUDOCS 7906200360
Download: ML19261D601 (4)

Text

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ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK ARKANSAS 72203 (501) 371-4000 June 13, 1979 1-069-9 Director of Nuclear Reactor Regulation ATTN: Mr. R. W. Reid, Chief Operating Reactor Branch #4

. U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Subject:

Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 June 2,1979 Order (File: 1510, 1510.1)

Gentlemen:

Pursuant to conversations with your Mr. Gerry Mazetis concerning recent design changes and additional operator training and procedural changes, the following is provided.

The Emergency Feedwater (EFW) automatic actuation logic will be changed to provide for actuation as shown in Attachment 1. This revised logic allows the automatic actuation feature to be made operable at 280F RCS Average Temperature along with the EFW pumps and flow paths. From that point until 5% Rated Thermal Power (RTP) is reached, the EFW system will be automatically actuated on low level in either steam generator or a loss of reactor coolant pumps. Above 5% RTP, the EFW system will also be actuated by loss of both main feedwater (MFW) pumps. No operator action is required to enable that additional feature at 5% RTP during plant startup.

The autmatic actuation on loss of both MFW pumps is automatically by-passed (no operator action required) during plant shutdown upon reaching 5% RTP, following a 30 second time delay. The time delay is provided in the bypass circuit so that, in the event of a trip of both MFW pumps and simultaneous reactor trip to(5% RTP, the circuit would not be bypassed for approximately 30 seconds and a start. signal to the EFW System would thus be provided.

2286 106 790620CW MEMBER MlOOLE SOUTH UTIUTIES SYSTEM

1-069-9 Mr. R. W. Reid, Chief June 13, 1979 A change will also be made in the EFW flow control valve hand switches in the control rom. The switches will be changed fra 3 positions (Locked Open, Locked Closed, and Normal) to 2 positions ( Auto and Manual). This change will allow the operator to use either the block valve or the bypass valve to feed the steam generators when he takes manual control of EFW.

Previously, the block valve could not be used during manual control due to the design. Procedures to be modified as a result of this change to reflect the new switch position are 1202.06, 1202.14, 1202.24, 1202.26, 1106.06 and 1205.05. Only those sections affected by this hand switch change are being revised except as noted below.

Procedure 1106.06 has also been changed to no longer require stationing of a dedicated operator at the EFW pump during surveillance testing. We have deleted this requirement from the procedure because changes in manually operated valve positions are no longer required to perfonn this surveillance. Therefore an operator is not needed at the pump location during the test to re-align valves in the event an automatic actuation signal is received by the EFW system.

Over the most recent 10 day period, the following training has been accomplished:

a) Seven individuals (six operators and one licensed, non-shift individual) have undergone retraining on the TMI incident and the procedural and design changes that have taken place at AN0 as a result of the incident. These personnel had previously exhibited weaknesses in either written or oral exams. All of them were tested after the retraining, and all made scores of greater than 90%,

b) Four hours of training were given to operations personnel on the changes recently made to twelve mergency procedures, 1102.01 (Plant perheatup and precritical checklist), 1102.02 (PlantStartup), 1102.10 (Plant Shutdown and Cooldown proce-dure),and 1106.06 (Emergency Feedwater Surveillance Pro-cedure).

c) Training was given to operational, maintenance and I&C personnel on standing Order #3 Rev.1 (Valve Lineups) and Standing Order #39 Rev.1 (Adherence to procedures).

The training for operators was given by the training staff.

The training for maintenance and I&C personnel was given by their supervisors.

d) All procedure changes that have been made have been in-cluded in the routing systen which Licensed operators are required to read.

2286 107

1-069-9 Mr. R. W. Reid, Chief June 13,1979 Your prompt attention to this matter is requested.

David C. Trimble Manager, Licensing DCT/DGM/ew 2286 108

........e..,

Attachment 1 e 30 Sec. From 100" Rx Trip f d ryer_< Sr 2 F.W. Turbines Trip

'A' OTSG Level < 18 inches Actuate Q EFW

'R'__

OTSG Level < 18 inches V

__ 4 QCP Available 2286 109

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