ML20065B669

Proposed Tech Specs Re Approved Analytical Methods for Developing Core Operating Limits Rept

ML20065B669
Person / Time
Site:	Monticello
Issue date:	03/28/1994
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20065B661	List: ML20065B658 ML20065B669 ML20065C041
References
NUDOCS 9404040084
Download: ML20065B669 (4)

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March 28, 1994 Attachment A Revised Exhibit B Technical Specification Page 249b Marked Up With Proposed Change p

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7. Core Operatine Limits Report a.

Core operating limits shall be established and documented in the Core Operating Limits Report before each reload cycle or any remaining part of a reload cycle for the following:

Rod Block Monitor Operability Requirements (Specification 3.2.C.2a)

Rod Block Monitor Upscale Trip Settings (Table 3.2.3, Item 4.a)

Maximum Average Planar Linear Heat Generation Rate Limits (Specification 3.ll.A)

Linear Heat Generation Ratio Limits (Specification 3.11.B)

Minimum Critical Power Ratio Limits (Specification 3.11.C)

Power to Flow Map (Bases 2.3.A) b.

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:

NEDE-240ll-P-A, " General Electric Standard Application for Reactor Fuel" (12tect44tc approved version o.t tbu+ wa 4}w r.(onb e am\yws n.st pu4o esA)

NSPNAD-8608-A, " Reload Safety Evaluation Methods for Applic'ation to the Monticello

• Nuclear Generating Plant" (-In.tc + hs. et approved ' version cd- %c 4 64 4fsc. reAc d M e.l y za M c P 'M)

NSPNAD-8609-A, " Qualification of Reactor Physics Methods for Application to Monticello" OApy (Ingtapprovedversion aA4hc. %ryr +lw re.W.A Me.Y5c5 o.rt pu4oe d )

05 c.' 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) aof the safety analysis are met.

d.

The Core Operating Limits Report, including any mid-cycle revisions or supplements, shall be supplied upon issuance, Administrator andforResident each reload Inspector. cycle, to the NRC Document Control Desk with copies to the Regional 1 6.7 .

249b ANF-91-0481(P)(A), " Advanced Nuclear Fuels Corporation Methodology for Boiling REV' Water Reactors-EXEM BWR Evaluation Model," Siemens Power Corporation (the approved version at the time the. reload analyses are performed) v 4 e

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March 28, 1994 Attachment B Revised Exhibit C Monticello Technical Specification Page 249b

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7. Core Operatine Limits Report

a. Core operating limits shall be established and documented in the Core Operating Limits Report before each reload cycle or any remaining part of a. reload cycle for the following:

Rod Block Monitor Operability Requirements (Specification 3.2.C.2a)

Rod Block Monitor Upscale Trip Settings (Table 3.2.3, Item 4.a)

Maximum Average Planar Linear Heat Generation Rate Limits (Specification 3.ll.A)

Linear. Heat Generation Ratio Limits (Specification 3.11.B)

Minimum Critical Power Ratio Limits (Specification 3.11.C)

Power to Flow Map (Bases 2.3.A)

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

NEDE-240ll-P-A, " General Electric Standard Application for Reactor Fuel" (the approved version at the I time the reload analyses are performed) i NSPNAD-8608-A, " Reload Safety Evaluation Methods for Application to the Monticello Nuclear Generating Plant" (the approved version at the time the reload analyses are performed) l ,

NSPNAD-8609-A, " Qualification of Reactor Physics Methods for Application to Monticello" (the approved version at the time the reload analyses are performed) I

" Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors-EXEM-BWR Evaluation Mo ANF-91-0481(P)(A)llel,d) " Siemens Power Corporation (the approved version at the time the reload analyses are performe ,

c. 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.

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

6.7 249b REV

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