ML20236R982

Proposed Tech Specs Section 6.5.1,re Implementation of BWR Thermal Hydraulic Stability Solution

ML20236R982
Person / Time
Site:	Cooper
Issue date:	07/16/1998
From:	NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20236R974	List: ML20236R972 ML20236R982
References
NUDOCS 9807240063
Download: ML20236R982 (5)

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1 ATTACHMENT 1 TECIINICAL SPECIFICATIONS REPLACEMENT PAGES l

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l. 9907240063 990716 I h- '

PDR ADOCK 05000298 l l P PM .

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I core coeratino Limita naenort (Continued)

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

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. "'h: "'g  :::: fler "CP" edjuct :nt fetter fer Spreifientien 2.11.C.

k The nimum[ritical[owerMtio(MCPR) for Specification 3.11.C.

The %d Mock jilbnitor upscale setpoint for Table 3.2.C of t.

Specification 3.2.C.

gM;[ig 3,g The, reatr/Sloa %p The analytical methods u,definin3 the Exe.lusion 3 Repew b Spee.$1c.dien := . r. E =.; )

sed to determine the core operating limits shall be

" E-M O W P *., " Cer.a.1 thosepreviouslyreviewedandapprovedbytheNRC[4" Electric S**=dard ann 14"**4an fnv Da="en* mal _" Tha 9- ;-roved-revision--a t-the-

-timthe rele=A =a=1ysam ar= parfnrmad 1 Th= approved revision-numbewhall b- id-atifi-d ta *ha enra Tarme i ner f.4m4e= Dannre.

NT The (e.g.,core operating limits shall be determined such that all applicable limits l 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 NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

6.5.2 Reoortable Events

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A Reportable Event shall be any of those conditions specified in Section 50.~n 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, i

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l Am:ndment No. 142 -234 05/22/91

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l l Insert p. 234:

l ...specifically those described in the following documents:

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1. NEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel" '

(Revision specified in COLR),

2. *BWR Owner's Group Long-Term Stability Solutions Licensing Methodology,"

NEDO-31960 (the approved revision at the time reload analyses are performed),

3. "BWR Owner's Group Long-Term Stability SolutiorvLicensing Methodology,"

NEDO-31960, Supplement 1, (the approved revision at the time reload analyses i are performed),

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Core Ooeratina Limits Reoort (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 approve 1 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).

2. "BWR Owner's Group Long-Term Stability Solutions Licensing Methodology",

NEDO-31960 (the approved version at the time reload analysis are performed).

3. ""BWR Owner's Group Long-Term Stability Solutions Licensing Methodology",

NEDO-31960, Supplement 1, ((the approved version at the time reload analysis are performed).

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 NRC 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, l

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Amendment No. 142 -234- 05/22/91 L__---_-------_--___-_------ - - - - - - -

• • l ATTACHMENT 3 LIST OF NRC COMMITMENTS l l l

Correspondence No: NLS980120 The following table identifies those actions committed to by the District in this l 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.

j COMMITTED DATE COMMITMENT OR OUTAGE None l

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l l PROCEDURE NUMBER 0.42 l REVISION NUMBER 5 l PAGE 9 OF 13 l

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