ML20211J980

Proposed Tech Specs Page 249b & Cleaned Typed Page 249b, Adding Footnote to Topical Rept NEDE-24011-P-A Stating That Topical Rept Is Approved for Cycle 18 Only

ML20211J980
Person / Time
Site:	Monticello
Issue date:	09/29/1997
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20211J972	List: ML20211J966 ML20211J980
References
NUDOCS 9710090081
Download: ML20211J980 (2)

Text

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, .7. Core Operatim 1Infts'Reoort <

a. Core operating limits shall be established and documented in the Core Operating Limits l 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)-

Recirculation System. Power to Flow Map Stability Regions ~(Specification 3.5.F) ,

.l Maximum Average Planar -Linear Heat Generation Rate Limits'(Specifiestion 3.11.A) 'i

i. Linear. Heat Generation Ratio l Limits:(Specification 3.11.B) '

Minimum Critical Power Ratio' Limits (Specification 3.11.C)

Power to Flow Nap (Bases.2.3.A) s

b. The analytica1' methods'used to determine the core operating limits shall be'those previously reviewed j and approved by the NRC..specifically those described in the following documents:.  !

NEDE-24011-P-A, " General Electric St xd lication for Reactor Fuel" (the approved ~ version at the-(

time the reload analyses are perfo d) W I NSPNAD-8608-A, " Reload ty Eva uation thods for Application to the Monticello "

Nuclear Generati ant" (the approved version at the time the reload analyses are performed) ,

NSPNAD- -A, " Qualification of Reactor Physics Methods for Application to.Monticello"

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(th proved version at the time the reload analyses are performed) - '

ANF-91-048(P)(A), " Advanced Nuclear Fuels Corporation Methodology.for Boiling Water Reactors-EKEN BUR l l Evaluation Model," Siemens Power Corporation (the approved version at the time the reload analyses are.-

' ' i performed)  ;

NEDO-31960, ' "BWR Owners' Group long-Tern Stability Solutions Licensing Methodology,* June 1991' .(the

~

"I 1 _ approved version at the. time the. reload analyses are. performed) ,

NEDO-31960, . Supplement 1, "BWR Owners' Croup long-Term Stability Solutions Licensing Methodology," March .

1992 (the approved version at the time the reload analyses are performed) l c. The core operating limits-shall be determined such that all applicable' limits (e.g., fuel i thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as j shutdown margin, transient analysis limits and accident analysis limits) of the safety analysis are 3

! met. ,

t

d. The Core Operating Limits. Report, including any mid-cycle ~ revisions or supplements,-shall be supplied  ;

upon issuance, for each reload cycle, ' to the NRC Document Control Desk with copies to the RegionalL j Administrator and Resident Inspector. '

6.7 '

249b ,

REV 147. 9/17/96 l

[Le cy& \ S mdy w a9prodh Sea Axel j gb 63- '

P PDR i

,V e

i .

'7. Core Operatine Limits Report

a. Core operating liuits 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)

Recirculation System Power to Flow Map Stability Regions (Specification 3.5.F) .

Maximum Average Planar Linear Heat Generation Rate Limits (Specification 3.11.A)

Linear Heat Generation Ratio Limits (Specification 3.ll.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" (the approved version at the time ? tie reload analyses are performed)*

NSPNAD-8608-A, " Reload Safey Evaluatior Methods for Application to the Monticello Nuclear Generating Plant" (the approved version at the time the reload analyses are performed)

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

ANF-91-048(P)(A), " Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors-EXEM BUR Evaluation Model,"

Siemens Power Corporation (the approved version at the time the reload analyses are performed)

NEDO 31960, " BUR Owners' Group Long-Term Stability Solutions Licensing Methodology," June 1991 (the approved version at the time the reload analyses are performed)

NEDO-31960, Supplement 1, "BWR Owners' Group Long-Term Stability Solutions Licensing Methodology," March 1992 (the approved version at the time the reload analyses are performed)

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 NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

• For cycle 18 only as approved in SER dated l

6.7 249b Rev.