ML20195E235

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Forwards Response to NRC 990517 RAI Re Util Proposed Change to TS Re Calibr Frequency of Reactor Recirculation Flow Transmitters Associated with APRM
ML20195E235
Person / Time
Site: Cooper Entergy icon.png
Issue date: 06/08/1999
From: Swailes J
NEBRASKA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLS990056, NUDOCS 9906110012
Download: ML20195E235 (7)
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. N Nebraska Public Power District Nebraska's Energy Leader June 8,1999 i

U.S. Nuclear Regulatory Commission j Attention: Document Control Desk '

Washington, D.C. 20555-0001 Gentlemen:

Subject:

Response to Request for AdditionalInformation Proposed Change to Technical Specifications APRM Neutron Flux - High (Flow Biased) Calibration Frequency .

Cooper Nuclear Station, NRC Docket 50-298, DPR-46

Reference:

1) Letter (No. NLS980200) to USNRC Document Control Desk from J. H. Swailes )

(NPPD) dated March 1,1999, " Proposed Change to CNS Technical l i

Specifications; Reactor Protection System Instrumentation"

2) Letter (No. NLS990030) to USNRC Document Control Desk from L. Newnmn (NPPD) dated March 10,1999, " Submittal of Calculation Referenced in Significant Hazard Determination"
3) Letter to G. R. Hom (NPPD) from L. J. Burkhart (USNRC) dated May 17,1999,

" Cooper Nuclear Station - Request for Additional Information" In Reference 1, and as supplemented by Reference 2, the Nebraska Public Power District (District) submitted to the Nuclear Regulatory Commission (NRC) a proposed change to the Cooper Nuclear Station (CNS) Technical Specifications (TS) conceming the calibration frequency of reactor recirculation flow transmitters associated with the Average Power Range Monitors (APRM). In Reference 3, the NRC forwarded to the District a request for additionalinfonnation (RAI) concerning the proposed TS change. Please find attached the District's response to the RAI.

Should you have any questions regarding this matter, please contact me.

Sincerely, .

I

! J. H. Swailes

! Vice President ofNuclear Energy Cooper Nudear Station

, PO. Box 98/ Brownville NE 683210098 b \; ,l\+ ,' Q Telephone: (402) 82S-38n / Fax: (402) 825-52n

'""/www nppd com PDR ADOCK 05000298i P PDR h

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. NLS990056 '

' June 8, _1999 Page 2 of 2'

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Attachment cc: Regional Administrator USNRC - Region IV Senior Project Manager USNRC - NRR Project Directorate IV-1 Senior Resident Inspector

.USNRC Environmental Health Division - Program Manager Nebraska Depsitment ofHealth -

NPG Distribution 3

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Attachm:nt I to NLS990056 Page 1 of 2

, Response to Nuclear Regulatory Commission Request for Additionalinformation Concerning the Cooper Nuclear Station Proposed Change to CNS Technical Specifications  !

Reactor Protection System Instrumentation Average Power Range Monitor Neutron Flux - High (Flow Biased)

Calibration Frequency The following is the Nebraska Public Power District's (District's) response to each of the individual questions contained in the Nuclear Regulatory Commission's (NRC) Request for Additional Information (RAI), dated May 17,1999 (Reference 3 of Coverletter), concerning the proposed change to the Cooper Nuclear Station (CNS) Technical Specifications (T , addressing the calibration frequency ofreactor recirculation flow transmitters associated with the Average Power Range Monitors (APRM). The individual NRC questions (identified in italic) are presented below along with the District's response.

NRC Ouestion 1. i in your submittal dated March 1,1999, you state that " site-specific drift datapointsfor these transmitters are limited, due to the past testfrequency and the limited collection of past datapoints, the datapoints that are available are consistent with the calculated drift value."

Despite thefact that the drift data may be limited, it will be usefid in evaluating the proposed change. Pleaseprovide the site-specific drift data that is available.

District's Response Attachment 2 to this letter contains CNS site-specific drift datapoints collected from April 1989 through November 1998 (most recent datapoint collection during Refueling Outage 18) for each of the Reactor Recirculation (RR) loop flow transmitters (FT).

NRC Ouestion 2.

On sheet 18 of 65 ofyour attachment to your March 10,1999, letter, at the bottom ofthe page you state that "since theflow units are checked every month, it is assumed that the above drift is applicablefor calculation. " Please describe the " check" that isperformed monthly. Is this check a technical specification requirement? What equipment ispart of this check?

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Attachment 1 to NLS990056 Page 2 0f 2

' Distril:t's Response i

The Reactor Recirculation loop flow units (equipment identification numbers: NMF-FM- I

. 81 A and B) are checked (tested) monthly per CNS surveillance procedures in order to perform a CHANNEL FUNCTIONAL TEST as defined by CNS TS. The monthly test satisfies TS Surveillance Requirement 3.3.1.1.7 for Table 3.3.1.1-1, Function 2b, along with satisfying CNS Technical Requirements Manual (TRM) Surveillance Requirement

~ (TSR) 3.3.1.3 for Table T3.3.1-1, Functions 4 and 5, TSR 3.3.1.4 for Table T3.3.1-1, Function 3a, TSR 3.3.1.5 for Table T3.3.1-1, Function 5, and part of TSR 3.3.1.7 for Table T3.3.1-1, Function 4. The monthly testing satisfies both a TS requirement and a TRM requirement for control rod block instrumentation and data is taken during this testing.

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. ATTACHMENT 3 LIST OF NRC COMMITMENTS Correspondence Nos. M 990056 The.following. table identifies those. actions committed to by the District in this' document. Any other actions discussed in the submittal represent

' intended or planned actions by the District. They are described to the NRC

'for the NRC's'information and are not regulatory commitments. Please notify the NL&S Manager at' Cooper Nuclear Staticn of any questions regarding this

. document.or any associated regulatory commitments.

COMMITTED DATE COMMITMENT OR OUTAGE

'I Mone NlA j

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i PROCEDURE NUMBER 0.42 REVISION NUMBER 6 PAGE 9 OF 13 l

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