ML20012G562

Corrected Response to Request for Addl Info Re Proposed Change 100 to Tech Specs, Elimination of Main Steam Line Radiation Monitor Scram & Isolation Functions

ML20012G562
Person / Time
Site:	Cooper
Issue date:	02/24/1993
From:	Horn G NEBRASKA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NSD930278, TAC-M83768, NUDOCS 9303090232
Download: ML20012G562 (2)

Text

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NSD930278 February 24, 1993 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C.

20555 Gentlemen:

Subject:

Correction to Response to Request for Additional Information Regarding Proposed Change No.

100 to Technical Specifications Elimination of Main Steam Line Radiation Monitor Scram and Isolation Functions, Cooper Nuclear Station, NRC Docket No. 50-298, DPR-46

References:

1)

Letter from G. R. Horn (NPPD) to NRC dated January 13, 1993,

" Response to Request for Additional Information Related to Proposed Change No.

100 to the Cooper Nuclear Station Technical Specifications, ' Elimination of Main Steam Line Radiation Monitor Scram and Isolation Functions,'

(TAC No. 83768)"

2)

Letter from G.

R.

Horn (NPPD) to NRC dated May 4,

1992,

" Proposed Change No.

100 to Technical Specifications, Elimination of Main Steam Line Radiation Monitor Scram and Isolation Functions, Cooper Nuclear Station NRC Docket No. 50-298, DPR-46" The Nebraska Public Power District (District) hereby makes a correction to its earlier response to an NRC Request for Additional Information (Reference 1) which was submitted in support of Proposed Change No.100 to the Cooper Nuclear Station (CNS) Technical Specifications, " Elimination of Main Steam Line Radiatien Monitor Scram and Isolation Functions" (Reference 2).

The Request for Additional Information (RAI) requested, in part, that the District demonstrate that the GE Topical Report (NEDO-31400) bounds the CNS Control Rod Drop Accident analysis, by comparing input assumptions.

The correction to the response to the RAI, discussed with the CNS NRC Project Manager and detailed below, does not change the conclusion that NED0-31400 bounds the CNS Control Rod Drop Accident (CRDA) analysis. Therefore, this correction does not alter the District's conclusion that Proposed Change No. 100 involves no significant hazards considerations.

In the response to the RAI, the District indicated in the table provided therein (page 3, item 7) that the CNS licensing basis CRDA analysis does not take credit for a reduction of the accident source term due to MSIV closure.

This information was not correct.

The CNS licensing basis CRDA analysis does tak r

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U. S. Nuclear Regulatory Commission Page 2 of 2 February 24, 1993 credit for a reduction in source term due to MSIV closure.

This correction, however, has no net impact on the District's conclusion that NEDO 31400 bounds the CNS licensing basis CRDA analysis. In fact, this correction shows that'the NEDO-31400 even more conservatively bounds the CNS CRDA analysis, as the l

NEDO-31400 evaluation takes no credit for source term reduction due to MSIV closure, and therefore contributes to a larger radionuclide inventory available j

for release to the environment. Therefore, while this correction does not impact the conclusion that NEDO-31400 evaluation bounds the CNS CRDA analysis, the District determined that in accordance with 10 CFR 50.9, " Completeness.and i

Accuracy of Information," that this correction should be communicated to the NRC and reflected on the docket.

As stated above, this correction to the District's response to the NRC's RAI does not impact the conclusion that the NEDO-31400 evaluation bounds the CNS CRDA i

analysis; therefore, this correction does not impact the District's Significant Hazards evaluation contained in Reference 2.

Please contact me if you have any questions or require c.ny additional information.

Sincerely,

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C/k.) Horn Nuclear Power Group Manager GRH/MJB

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H.R. Borchert Department of Health State of Nebraska NRC Regional Administrctor Region IV Arlington, TX NRC Resident Inspector Cooper Nuclear Station i

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