ML20236W114

Proposed Tech Specs Re Implementation of BWR Thermal Hydraulic Stability Solution

ML20236W114
Person / Time
Site:	Cooper
Issue date:	07/28/1998
From:	NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20236W109	List: ML20236W108 ML20236W114
References
NUDOCS 9808050089
Download: ML20236W114 (5)

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ATTACHMENT 1 TECHNICAL SPECIFICATIONS MARKED UP PAGE AND REPLACEMENT PAGE 9eososooe9 98072e m-PDR ADOCK 05000293' P PDR-t

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9p core Oneratiner Lf mits Renort (Continued) i

b. The Linear Heat Generation Rate for Specification 3.11.B.

-c. "'h: ".g  :::: fl u MO!- 2djuct crt f Oter fer Sp rific tir: 2.11.0.

f Thehnimum[ritical[owerMtio(MCPR) for Specification 3.11.C.

The /bd hock jilbnitor upscale setpoint for Table 3.2.C of Specification 3.2.C. SMj(I

e. The. mw/41%p g,g The analytical methods u,de. A1n3 he Exc 3 usion Reclew fav Sree$laaeb[ n 3.r. e.n sed to determine the core operating limits shall be those previously reviewed and approved by the NRC,4" "N-2 4 011 "  ?., " C:r.ewl Elec**ic ?*=adaed una14e=*4an far n==aen* *"=1

• I*e =pra=r-d r=ricien :t th:

t4=e *hm ra i a n d_ mnm1vene sem navfnrmmA i  %. annentrad *=tr4 = ia" =n=h-- ch:11 l b= id="*if4=d 4a *ka r^*= nnarmeina L4m4*= Dann"*.

/NT 1 The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, transient analysis limits, and accident analysis limits) of the safety analysis are met.

The Core Operating Limits Report, including any mid-cycle revisions or supplements thereto, shall be provided, upon issuance for each reload cycle, to the ifRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

6.5.2 Reoortable Events A Reportable Event shall be any of those conditions specified in Section 50.73 to 10CFR Part 50. The NRC shall be notified and a report submitted pursuant to the requirements of Section 50.73. Each Reportable Event shall be reviewed by SORC and the results of this review shall be submitted to SRAB and the Nuclear Power Group Manager.

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Amendment No. 142 -234- 05/22/91 L

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Insert p. 234:

...specifically those described in the following documents:

1. NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel" (Revision specified in COLR),

2. "BWR Owner 4broup Long-Term Stability Solutions Lloensing Methodology,"

NEDO-31960=e=-- rf -

Gu.e iR$ 1, CN Wrced =v;;;;sa  :: n: tme f65THnWaaure:perforfDed)3) hg HPC.SEC,6044ck  % tZn fM ,

3. *BWR Ownet's' Group Long-Term Stability SolutlorsLicensing Methodology,"

NEDO-31960, Supplement 1, (tha e~ye"^d =vl:::sa et the tlms reload analyses-

= ""MWL MareIN 197z. (Apececcl bg NE SM, dctM N (2, N93),

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1 Core Oneratino Limits Renort (Continued)

b. The Linear Heat Generation Rate for Specification 3.11.B.

c. The Minimum Critical Power Ratio (MCPR) for Specification 3.11.C.

.d. The Rod Block Monitor upscale setpoint for Table 3.2.C of Specification 3.2.C.

e. The power / flow map, defining the Stability Exclusion Region for Specification 3.11.D.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel" (Revision specified in COLR),

l 2. "BWR Owners' Group Long-Term Stability Solutions Licensing l Methodology," NEDO-31960, June 1991, (Approved by NRC SER, dated July 12, 1993).

3. "BWR Owners' Group Long Term Stability Solutions Licensing Methodology," NEDO-31960, March 1992, (Approved by NRC SER, dated July 12, 1993).

The core operating limits shall be determined such that all applicable limits - (e.g. , fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin,. transient analysis limits, and accident analysis limits) of the safety analysis 6

are met.

!. The Core Operating Limits Report, including any mid-cycle revisions or I- . supplements thereto, shall be provided, upon issuance for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

6.5.2 Renortable Events A Reportable Event shall be any of those conditions specified in Section 50.73'to 10CFR Part 50. The NRC shall be notified and a report submitted pursuant to the requirements of Section 50.73. Each Reportable Event shall be reviewed by SORC and the results of this review shall be submitted to SRAB and the Nuclear Power Group Manager.

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l ATTACHMENT 3 LIST OF NRC COMMITMENTS l

l Correspondence No: NLS980125 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 Licensing Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments. I COMMITTED DATE l COMMITMENT OR OUTAGE l

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l PROCEDURE NUMBER 0.42 l REVISION NUMBER S l PAGE 9 OF 13 ~l l

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