ML19309A491

Responds to NRC Re Requirements for Continued Upgrade of Auxiliary Feedwater Sys.Util Will Update Auxiliary Feedwater Reliability Study & Will Submit New Tech Specs by 800501

ML19309A491
Person / Time
Site:	Rancho Seco
Issue date:	03/18/1980
From:	Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Reid R Office of Nuclear Reactor Regulation
References
TASK-2.E.1.1, TASK-TM TAC-44673, NUDOCS 8003310359
Download: ML19309A491 (4)

Text

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$SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, Box 15830, Sacrarnento, California 95813; (916) 452 3211 March 18, 1980 Director of Nuclear Reactor Regulation Attn: Mr. Robert W. Reid, Chief Operating Reactors, Branch 4 U. S. Nuclear Regulatory Comission Washington, D. C.

20555 Docket 50-312 Rancho Seco Nuclear Generating Station, Unit 1

Dear Mr. Reid:

The Sacramento Municipal Utility District has carefully reviewed your February 26, 1980 letter concerning requirements for the continued upgrade of the Rancho Seco Auxiliary Feedwater System.

The attachment to this letter provides the District's response to each of the requirements listed in Enclosure 1 of your letter, and to the schedule proposed in Enclosure 2 to your letter.

Sincerely,

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(/ John J. Mattimoe Assistant General Manager and Chief Engineer Attachment soossia 3 S*7 AN ELECTRIC SYa.*V S E R VIN G MORE THAN 7 0,000 IN THE HEART OF C A LIF O R N I A 1

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ATTACHMENT SACRAMENTO MUNICIPAL UTILITY DISTRICT Response to February 26, 1980 Letter Concerning NRC Requirements for Continued Upgrade of the Rancho Seco Auxiliary Feedwater System Part A Item 1 AFW Reliability Study Success Criteria The District will update the AFW Reliability Study by the NRC proposed date of May 1, 1980.

Part A Item 2 AFW Pump Suction and Discharge Instrumentation Modifications To AFW Reliability Study By May 1, 1980 the District will analyze any changes to the results of the AFW Reliattility Study due to AFW Pump Suction and Discharge Pressure Instru-mentation assumptions.

Part A Item 3 ICS/NNI Failure Impact on AFW Reliability Study The District will review the AFW Reliability Study to see if ICS/NNI failures lie within the scope of study.

If they do lie within the scope of study, we will address potential effects upon AFW Reliability Study results by May 1, 1980.

Part B Item 1.a Safety Grade AFW Initiation System The District is currently working toward completion of the design of the safety grade auxiliary feedwater control system by August 1,1980. As with other Category B (January 1, 1981) NUREG-0578 modifications, the District is attempting to complete design and to procure hardware to allow installation by January 1, 1981.

The magnitude of the task associated with design and procurement of a safety grade auxiliary feedwater control system is substantial. Many other NUREG-0578 Category B items are of equal or greater magnitude. The total effort, however, is much greater than the sum of the tasks considered individually.

(For example, for this system we are still awaiting a final location for the control cabinets because existing space is not available and because plans are only now being finalized for additional space.) Attempts to integrate this design into a well coordinated overall design causes us to continue to inform you that refueling 1981 is a realistic date for incorporation of the j

system at Rancho Seco.

I Part B Item 1.b AFW System Testability i

The AFW flow control valves (FV-20527 and FV-20528) will be tested during the current refueling outage.

In addition, until the safety grade control system is installed, the District will establish and implement a procedure for performing channel functional tests of the automatic initiation circuitry of the AFW pumps using the loss of main feedwater signal at least every thirty-one days.

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_ Part B Item 1.c Automatic' Loading of Pump P319 Onto the Nuclear Service Bus on Loss of Offsite Power The District's letter of February 18, 1980 provided the information requested for this section.

Part B Item 2a Safety Grade AFW Flow Indication See the District's comments in Part B Item la above.

Part B Item 2b AFW Flow' Indication Testability Until safety grade AFW flow indication is installed, the District will establish and implement a procedure for performing channel functional tests of the AFW flow indication and 0TSG level indication at least every thirty-one days when the plant is operating.

Part B Item 3 System Modification for Full Flow AFW Pump Testing The District will provide details of full flow AFW pump testing modifications by May 1, 1980. The District will continue to use the surveillance procedure which requires stationing an operator at flow control valve FWS-055 during pump testing until the full flow test modification is installed.

Part B Item 4 Emergency Procedure for Alternate Water Sources The District will review procedures for providing alternate water sources to the AFW system. Prior to startup we will ensure that procedures describe how to obtain water from these alternate sources.

Part B Item 5 AFW System Flow Path Verification By May 1,1980 the District will submit a technical specification related to full flow testing to the OTSGs.

Part B Item 6 Condensate Storage Tank Level Indication and Alarms As described in the District's December 17, 1979 letter, the District will install safety grade condensate storage tank level indication and alarms.

The safety grade design will include redundant sensors, detectors, readouts, and alarms from the condensate storage tank to the control room including power supplies. The District will use Class lE circuitry and power supplies in all cases except for the alarm annunciator panel. The District is not aware of qualified Class lE annunciator panels.

Part B Item 7 AFW Pump Endurance Test The District will provide the results of oar AFW pump endurance test in a format approximating as closely as possible the one requested by May 1,1980.

Part B Item 8 Periodic Testing of AFW Motor Operated Valves No response required.

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. Part B Item 9 AFW System Operation During Loss of All AC Power Prior to startup the District will verify that the Auxiliary Feedwater System Operating Procedure, A.51, requires an operator to be stationed at the flow control valves following loss of all AC power.

In addition, prior to startup the District will verify that in a loss of AC power condition at least two hours of adequate lighting and communications with the control room are available at the local valve stations.

In the long term the District will modify our design to enable the control room operator to control AFW system operation and steam generator level from the control room for two hours with only inverter supplied AC power available.

Part B Iten: 10 New Technical Specification Related AFW System Outages

'By May 1, 1980 the District will submit a new Technical Specification concerning AFW system outages.

Part C AFW System Review per Section 10.4.9 of the Standard Review Plan By September 1,1980 the District will review the auxiliary feedwater system in the areas defined by your letter to need further evaluation. The review will be done using the system as it will be configured after the safety grade AFW control system and the full flow test modifications are installed.

Part D Design Basis for AFW System Flow Requirements The District will provide the requested AFW System design basis information by May 1, 1980.