ML20054L849

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Forwards Current Schedule for Installation of Qualified Electrical Equipment.Evaluation Worksheets & Test Repts Have Not Been Sent for Item II.D.3, Valve Position Indication, Since Five of Six Units Tested Failed
ML20054L849
Person / Time
Site: Rancho Seco
Issue date: 07/01/1982
From: Mattimoe J
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To: Stolz J
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.D.3, TASK-2.E.1.2, TASK-2.E.3.1, TASK-2.E.4.1, TASK-2.E.4.2, TASK-2.F.2, TASK-2.G.1, TASK-2.K.2, TASK-TM TAC-42507, NUDOCS 8207090005
Download: ML20054L849 (3)


Text

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SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, Box 15830, Sacramento. California 95813; (916) 452 3211 July 1, 1982 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTN JOHN F STOLZ CHIEF OPERATING REACTOR' BRANCH 4 a

U S NUCLEAR REGULATORY COMMISSION WASHINGTON DC 20555 DOCKET 50-312 RANCHO SECO NUCLEAR GENERATING STATION UNIT NO 1 NUREG 0737 EQUIPMENT QUALIFICATION Your letter of April 9,1982, requested information on the qualification of electrical equipment installed as a result of NUREG 0737. With the exception of Item II.D.3, Valve Position Indication, the District has not installed any environmentally qualified electrical equipment to meet NUREG 0737.

System Component Evaluation Worksheets and Test Reports are not being sent for Item II.D.3, since five of six units tested failed.

When the District has resolved the qualification of these units, the infor-mation will be forwarded to the NRC and Franklin Institute. Attached to this letter is the current schedule for installation of the items discussed in your letter.

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John J. Mattimoe Assistant General Manager and Chief Engineer Attachment OY cc:

Cyril J. Crane 8207090005 820701 PDR ADOCK 05000312 P

PDR Ah ELECTRIC SYSTEM SERVING MORE THAN 600.000 IN THE HEARI 0F CAIIf0PNIA

Item Title Discussion II.B.3 Post Accident The requirements set forth in NUREG 0737, Sampling 0660, and 0578 do not include installing a Class 1 post accident sampling system. The new equipment was specified to operate under the environmental conditions for the equip-ment location, however, no special test report or testing was specified by the District. Only Class 1 equipment, as de-fined by SMUD Quality Assurance Procedure No. 3; "...Those plant structures, systems, subsystems, and equipment which are nec-essary to assure the integrity of the reactor coolant pressure boundary, the capability to shut down the reactor and maintain it in a safely shutdown conditioa, or the cap-ability to prevent or mitigate the conse-quences of accidents which could result in offsite exposures in excess of 10 CFR Part 100..." are purchased as environmentally qualified to NUREG 0588 or DOR Guidelines.

The post accident sampling system is scheduled to be installed and operational at the end of the next refueling outage.

II.D.3 Valve Position

'1he District has installed a sonic valve Indication position indication system. This system, manufactured by TEC, was installed prior to completion of environmental qualification testing. Testing was completed in December 1980 as scheduled.

Five of six conitors tested failed to function throughout the test.

TEC has recommended two solutions, both of which the District has under consideration.

The first requires the purchase and instal-lation of an environmentally hardened charge converter, the failed component. The second solution would relocate the converter outside of containment.

Neither fix is scheduled to be complete prior to the end of the 1983 re-fueling outage.

II.E.1.2 Auxiliary Feedwater The District is purchasing an Emergency System Initiation Feedwater Initiation and Control (EFIC) and Flow System from B&W.

Currently this system is to be installed and operational by the end of the 1984 outage.

Item Title Discussion Item 2a, control grade flow indication, has been installed. The safety grade flow in-dication is scheduled to be installed during the 1983 outage.

II.E.3.1 Emergency Power for No new equipment was installed for this mod-Pressurizer Featers ification. Please refer to the October 31, 1980 submittal for the cable and penetration SCEW sheets.

II.E.4.1 Dedicated Hydrogen This modification is scheduled to be completed Penetrations during the 1983 outage. Presently, no new equipment has been installed.

II.E.4.2 Containment Isolation No new equipment has been installed for this Dependability modification.

II.F.2 Instrumentation De-The saturation meters (including inputs) are tection of Inadequate scheduled to be upgraded to safety grade Core Cooling status during the 1983 outage.

II.G.1 Power Supplies for The only new equipment required for this Pressurizer Relief modification are level indicators. These Valves, Block Valves will not be installed until the 1983 outage.

and Level Indicators II.K.2 Orders on B&W Plants This item is not complete. The schedule for

10. Safety-Grade Trip completion is the 1983 outage.

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