A840006, Forwards Three Repts Re Facility Safety Parameter Display Sys (Spds),Per Requirements of Suppl 1 to NUREG-0737. SPDS Will Be Installed During Upcoming Recirculation Piping Replacement Outage

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Forwards Three Repts Re Facility Safety Parameter Display Sys (Spds),Per Requirements of Suppl 1 to NUREG-0737. SPDS Will Be Installed During Upcoming Recirculation Piping Replacement Outage
ML20087A938
Person / Time
Site: Cooper Entergy icon.png
Issue date: 03/01/1984
From: Pilant J
NEBRASKA PUBLIC POWER DISTRICT
To: Eisenhut D
Office of Nuclear Reactor Regulation
Shared Package
ML20087A940 List:
References
RTR-NUREG-0737, RTR-NUREG-737 LQA8400069, TAC-51232, NUDOCS 8403080265
Download: ML20087A938 (2)


Text

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GENERAL OFFICE

  • Nebraska Public Power District " "Vetess"eisa"#57""

March 1,1984 i LQA8400069 Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Reference:

1) Letter from J. M. Pilant to D. G. Eisenhut dated April 15, 1983, (LQ A8300129) " Response to NUREG-0737, Supplement 1"
2) Letter from J. D. Weaver to B. L. Siegel dated December 30, 1S83, " Emergency Response Capability - Revision 4"

Dear Mr. Eisenhut:

Subject:

NUREG-0737, Supplement 1 - Safety Parameter Display System (SPDS)

In accordance with the requirements of NUREG-0737, Supplement 1, and the District's commitments made in References 1 and 2, enclosed are the following documents relating to the Cooper Nuclear Station Safety Parameter Display System (SPDS):

1. Safety Analysis, March 1, 1584, 503-8500000-76, Revision 0
2. Verification and Validation Plan , March 1, 1984, S AI-84 /1525-264, Revision 0
3. Implementation Plan , March 1, 1984, 503-8500000-27, Revision 0 In Reference 1, the District requested a preimplementation review and approval of this modification by the NRC. Per discussions with our Project Manager, it is understood that a meeting with the staff on this subject may be possible during Ju ne , 1984. The District looks forward to such a meeting after the staff has reviewed the enclosed documents.

l As References 1 and 2 have stated, the CNS SPDS is a portion of the station's Plant Management Information System (PMIS), ,

Although the enclosed documents were generated to address NRC 3 8403080265 840301 PDR ADOCK 05000298 I F PDR

Mr. Darrell G. Eisenhut Pago 2 March 1,1984 requirements for the SPDS specifically, the documents contain information relative to the entire capabilities of the PMIS. The District presently intends to nrovide for this additional capability beyond the requirements of NUREG-0737, Supplement 1; however, these capabilities are not to be considered by the Staff as a commitment on the part of the District. The PMIS is presently undergoing review and evaluation and is subject to future changes. It should also be recognized that this SPDS project is presently scheduled to be installed during the upcoming recirculation piping replacement outage. This complex outage has the potential for large schedule shifts which could affect the SPDS/PMIS schedule.

Eight copies are enclosed for the staff's use. Two additional copies are being provided directly to our NRC Project Manager 3 to expedite the review process. <

Sincerely, M

Jay M. Pflant Technical Staff Manager Nuclear Power Group JMP/jdw:emz29/3 Enclosures cc: J. T. Collins U. S. Nuclear Regulatory Commission l

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