ML20209G130

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Forwards Listed Documentation,Including 47-1139815-01, SPDS Safety Analysis for Rancho Seco Nuclear Generating Station Unit 1 & Rev 1 to BAW-1753, Availability Evaluation for Spds..., Per NRC Request Re
ML20209G130
Person / Time
Site: Rancho Seco
Issue date: 01/12/1987
From: Julie Ward
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To: Miraglia F
Office of Nuclear Reactor Regulation
Shared Package
ML20209G134 List:
References
RTR-REGGD-01.097, RTR-REGGD-01.152, RTR-REGGD-1.097, RTR-REGGD-1.152 JEW-86-1108, TAC-56525, NUDOCS 8702050284
Download: ML20209G130 (3)


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e esuun SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street, P.o. Box 15830, Sacramento CA 95852-1830 (916) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA JEW 86-1108 Ja nua ry 12, 1987 Director of Nuclear Reactor Regulation Attention: Fra nk J. Mi raglia J r., Di rector Division of PWR Licensing-B U. S. Nuclear Regulatory Camission Washington D C 20555 Docket 50-312 Rancho Seco Nuclear Generating Station Unit Ntaber 1 DISTRICT RESPONSE TO NRC REQUEST FOR INFORMATION

Reference:

SMUD to NRC, Novmber 20, 1986 Dea r Mr. Miraglia:

In onier to provide the infonnation as described in the District's letter of Novm ber 20, 1986, the followi ng attachments and their expla nations and/or expansions are provided with this sutmittal:

Attachment #1

" Safety Parameter Display Systen Safety Amlysis for the Rancho Seco Nuclear Generating Station, Unit 1", Babcock &

Wilcox document #47-1139815-01, dated Deceber 1986.

Attachment #2

" Availability Evaluation for the Safety Parameter Display System at Sacramento Municipal Utility District's Rancho Seco Plant", Babcock & Wilcox doctment BAW-1753, dated December 1986 Attachment #3 "Fimi Report - Qualification Test of Isolation Device for Safety Parameter Display System Multiplexer, Rancho Seco Nuclear Generating Station."

Document Ninber: SMD-1000-04, Rev.1.

Attactinent #4 Prelimimry Results of Central Control Unit Isolation Devices Tests.

Eigen Engineering letter dated Deceber 1986, Docinent Ntaber: SMD-1020-86-003.

Attachment #5 Description of Radioactivity Control Method and New Radiation Monitor Inputs to SPDS.

Attachment #6 SPDS Upgrade Sinma ry Report.

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e Fra nk Mi ra glia, J r. Ja nua ry 12, 1987 JEW 86-1108 Attachnent #7 Sumary of Modifications Made to the Control Rom for Resta rt.

Where required, explanation or expansion of infonnation is provided for each attachment with a cover sheet (s).

In addition to the above, the District will meet with the NRC staff at the Lynchburg office of Babcock & Wilcox during the week of February 9,1987 to walk-through the hartiware and software for two selected R.G.1.97 sigrals.

Also, at that time, an evaluation of SPDS software will be cmpleted to show a caparison of SPDS software to R.G.1.152 requirments.

If you have ary further questions, please feel free to contact Ray Ashley, our Manager of Nuclear Licensing.

Si ncerely,

/

J n4. Wa ni eputy General Marager, Nuclear Attachments cc: Sydney Miner, NRC - Bethesda Tony D' Angelo, NRC - Rancho Seco i

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ATTACHMENT #1 COVER SHEET

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