ML20083Q083: Difference between revisions

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#REDIRECT [[W3P84-1007, Forwards Safety Parameter Display Sys (Spds), Providing Details of SPDS Implementation,Per NUREG-0737,Suppl 1. Detailed Description of SPDS Display Hierarchy Included in Rept]]
| number = ML20083Q083
| issue date = 04/16/1984
| title = Forwards Safety Parameter Display Sys (Spds), Providing Details of SPDS Implementation,Per NUREG-0737,Suppl 1. Detailed Description of SPDS Display Hierarchy Included in Rept
| author name = Cook K
| author affiliation = LOUISIANA POWER & LIGHT CO.
| addressee name = Knighton G
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000382
| license number =
| contact person =
| case reference number = RTR-NUREG-0737, RTR-NUREG-737
| document report number = W3P84-1007, NUDOCS 8404200320
| package number = ML20083Q086
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
}}
 
=Text=
{{#Wiki_filter:LOUISIANA f 242 ocLAnoNoe Sincer P O W E F1 & L 1 G H T/ P O BOX 6008
* NEW ORLEANS. LOUISIANA 70174 * (504) 366-2345 NuSNIvsS$
April 16, 1984 W3P84-1007 3-A1.01.04 3-H1 Director of Nuclear Reactor Regulation Attention: Mr. G.W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
 
==SUBJECT:==
Waterford SES Unit 3 Docket No. 50-382 Safety Parameter Display System (SPDS)
 
==REFERENCE:==
W3P83-2936 dated September 29, 1983
 
==Dear Sir:==
 
As we stated in the referenced letter, the SPDS for Waterford 3 will be implemented prior to exceeding 5% power operation. In order to provide you with the details of the SPDS implementation as well as satisfying the NUREG 0737 Supplement I request for a written safety analysis, enclosed please find a description of the Waterford 3 SPDS.
The SPDS is a software implementation on the preexisting Plant Monitor Computer (PMC), a non-safety related system. As such, the SPDS introduces no unresolved safety question nor Technical Specification change. An added advantage is that a good deal of the SPDS verification and validation is accomplished through the start-up test program on the PMC (i.e. no new hardware, save for display terminals, and minimal calculational software was necessary for SPDS development).
Included with the enclosed report is a detailed description of the SPDS display hierarchy.        It should be noted that the SPDS display formats, at the time of this writing, have not been completely finalized and should be treated as representative only. While we expect that no displayed parameters will be deleted, the format of the displays may change prior to implementation. We would be happy to provide you with the finalized displays at a later time should you feel it necessary.
As mentioned in the enclosure, the SPDS is not intended to be a static system. As operational experience increases and unique situations are encountered, enhancements to the initial SPDS design will be incorporated.
However, we feel that at this time the Waterford SPDS is capable of fulfilling its function to aid the control room personnel in rapidly and reliably determining the safety status of the plant.
8404200320 840416                                          h        .$
00 PDR ADOCK 05000362 g                      eor                                ya        e
 
[
Should you have any questions or comments on this matter please feel free to contact Mike Meisner at (504) 363-8938.
{
Yours very truly, Jk K.W. Cook Nuclear Support & Licensing Manager KWC/MJM/pco Enclosure cc:  E.L. Blake, W.M. Stevenson, J.T. Collins, D.M. Crutchfield, J. Wilson, G.L. Constable
                                                                                  .}}

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