ML20062N873

Proposed Tech Specs 3.11, Reactor Fuel Assemblies & Bases Re Methodology for MCPR

ML20062N873
Person / Time
Site:	Monticello
Issue date:	01/04/1994
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20062N866	List: ML20062N863 ML20062N869 ML20062N873 ML20062N880
References
NUDOCS 9401240156
Download: ML20062N873 (8)

Text

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Exhibit B Monticello Nuclear Generating Plant License Amendment Reauest dated January 4, 1994 Proposed Changes Marked Up on Existing Technical Specification Pages Exhibit B consists of the existing Technical Specification pages with tho' proposed changes marked up.on those pages. Existing pages affected by this change are listed belows EARE

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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.11 REACTOR FUEL ASSEMBLIES 4.11 REACTOR FUEL ASSEMBLIES Applicability Applicability The Limiting Conditions for Operation associated with The Surveillance Requirements apply the fuel rods apply to those parameters which monitor to the parameters which monitor the the fuel rod operating conditions. fuel rod operating conditions.

Obiective Obiective The objective of the Limiting Conditions for Operation The objective of the Surveillance is to assure the performance of the fuel rods Requirements is to specify the tw e Specifications and frequency of surveillance to'be applied to the fuel rods.

A. Averar_e Planar Linear Heat Generation Rate (APLHCR) Specifications During tre recirculctier leep percr operatica--the- A. Averate Planar Linear Heat Al'illC.s limiting canditi n for e eration-for-each-type Generation Rate (APUiGR) 9 . planar - e f f=1experw+

cc - c -function-of-axial-Iocation-and-avera eh*L4-not*xceed linite hcsed-en ge The APUlGR for each type of fuel

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" MGR l'-it--values-which-have been-approved

- epeerium r..-1 ema-12ttice-tyne as a function of average planar exposure shall be determined 5 - the -cmrc ced =:thodelegpeecribed 1r.s ec- determined NEDE-240 H-P-A daily during reactor operation (6EETAR II). Thic cppreec_ is-based en-and-Limited-te- at >25% rated thermal power.

"E? TAP T T ra thodology. When hand calculations are -

required the APLHGR for each type of fuel as a function of averag,e planar exposure shall not exceed the limiting value for the most limiting lattice (excluding natural uranium) provided in the Core Operating Limits Report.

During one recirculation loop power operation, the AFLHGR bpyyrnt J limiting condition for operation for each type of fuel shall not exceed the above values multiplied by 0.85.

A If at any time during power operation, it is determined that the APLHGR limiting condition for operation is being exceeded, action shall be initiated within 15 minutes to restore operation to within the prescribed limits.

Surveillance and corresponding action shall continue until reactor operation is within the prescribed limits.

If the APLHGR is not returned to within the prescribed

' limits within two hours, reduce thermal power to less than 25% within the next four hours.

During two recirculation loop power operation, the APLHGR for each type of fuel as a function 3.11/4.11 og. average' planar exposure shall not exceed the 211 applicable limiting value specified in the Core REV 430-9/28789 Operating Limits Report.

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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 llent Generation Rate Limits (Specification 3.ll.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" (latest approved version)  :

NSPNAD-8608-A, "

Reload Safety Evaluation Methods for Application to the Monticello Nuclear Generating Plant" (latest approved version)

(;(g"^ Sc- NSPNAD-8609-A,

• Qualification of Reactor Physics Methods for Application to Monticello"

( clatest approved version) -

C> s-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 an y 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.

6.7 249b ANF-91-0481(P)(A), " Advanced Nuclear Fuels Corporation Methodology for Boiling REV 134 Water Reactors-EXEM BWR Evaluation Model," Siemens Power Corporation (latest 1/ 27/93 approved version)

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Bases Continued: -

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4 MCPR' Limit is determined from the analysis of transients discussed in Bases Sections 2.1 and 2.3. By -

maintaining an operating MCPR above these limits, the Safety Limit (T.S. 2.1.A) is maintained in the event of the most limiting abnormal operational transient. '

At less than 100% of rated flow and power the required MCPR'is the larger value of the MCPRp and MCPRp at the existing core flow and power state. The required MCPR is a function of flow in order to protect i

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the core from. inadvertent core flow increases such that the 99.9% MCPR limit requirement can be assured.

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v slo U nu.er/ flow control line, the limiting bundle's relaH m h et was adjusteil unt il

he MCPR was -slightly above the sarbyLict

• tisinc W- a lo uve bundle power, the MCPRs were .

alculated ore flows - at%:different points nlam i ivat of rated puwuu fl-" <nntrol line corresponding to differ ant mm L. Re i. sluutated MCPR at a given point of core flow (MCPR p ) is proviad 'a ehe Core Operati 1g

(,,,bf For operation above 45% of rated thermal power, the core power dependent MCPR operating limit is the C rated MCPR limit, MCPR(100), multiplied by the factor, provided in the Core Operating Limits Report. For 4 operation below 45% of rated thermal power (turbine control valve fast closure and turbine stop valve closure scrams can be bypassed) MCPR limits are provided in the Core Operating Limits Report. This protects thc. core from plant transients other than core flow increase, including a localized event such as rod withdrawal error. .

Flow runout events are ana!yzed wnh the purpose of estabnsh!ng a flow dependent MCPR Ilmit that would prevent the Safety Lim?! CPR from beIng reached dudng a flow runout. A flow .

ninout event is a slow flow and power increase which is not terminated by e SCRAM, but which stabilizes at a new core power corresponding to the maximum possible core flow Inftlat conditions for the transient are set such that the limiting CPR is near the Safety Limit. MCPR -

values are determined from the resulting change in CPR when core flow is increased to a possible maximum. Seversi combinations ofInitial power, tjow, and exposure are analyzed to cover the range of operablilty defined by the power /IJew map. The ceiculated flow dependent MCPR limit (MCPRg) for a given core flow is provided in the Core Operating 1.im!!s Report.

3.11 BASES  :

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Exhibit C i

Monticello Nuclear Generating Plant- ,

License Amendment Recuest dated Januarv 4, 1994 i Revised Technical Specification Pages j Exhibit C consists of the Technical Specification pages with the proposed changes incorporated. Existing pages affected by this change are listed 1 below:

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. 1 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS i

3.11 REACTOR FUEL ASSEMBLIES 4.11 REACTOR FUEL ASSEMBLIES Applicability Acolicability . I

The Limiting Conditions for Operation The Surveillance Requirements app 1v to '

associated with the fuel rods apply to those the parameters which monitor the fuel parameters which monitor the fuel rod rod operating conditions.

operating conditions.

Obiective Obiective The objective of the Surveillance i The objective of the Limiting Conditions for Requirements is to specify the type and Operation is to assure the performance of frequency of surveillance to be applied the fuel rods, to the fuel rods.

Soecifications Specifications

• A. 'Averace Planar Linear Heat Generatinn A. Averate Planar Linear Heat .

, Fatio (APLHUK) Generation Kate (AFLMUK) 4 During two recirculation locp operation, The APLHGR for each type of fuel the AFLHCR for each type of Luez as a as a function of average planar function of average planar exposure exposure shall be determined daily shall not exceed the applicable limiting during reactor operation at 225%

3 values specified in the Core Operating rated thermal power.

Limits Report. L' hen hand calculations the APLHGR for each type are required, of fuel as a function of average planar exposure shall not exceed the limiting value for the most limitin lattice (excluding natural uranium provided in

, the Core Werating Limits eport.

During one recirculation loop power the APLHGR limiting condition operation, for operat ion for each type or fuel shall not exceed the above values multiplied by 0.85.

If at any time during power operation, it is determined that the APGGR limiting condition for operation is being exceeded action shall-be

• initiated within 15 minutes to restore i operation to within the prescribed limits. Surveillance and corresponding

, action shall continue until reactor operation is within the prescribed limits. If the APLHGR is not returned to within the prescribed limits within two hours, reduce thermal power to less than 25% within the next four hours. 211 1

3.11/4.11 REV i

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7. . Core Operatinz 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 r (Specification 3.2.C.2a) ,

t

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

Maximum Average Planar Linear Heat Generation Rate Limits '

c (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-24011-P-A " General Electric Standard Application for Reactor Fuel" (latest t approved version)

NSPNAD-8608-A, " Reload Safety Evaluation Methods for Application to the Monticello Nuclear Generating Plant" (latest approved version) i NSPNAD-8609-A, " Qualification of Reactor Physics Methods for Application to Monticello" (latest approved version)

ANF-91-0481(P)(A);

Evaluation Model, Siemens Power Corporation (latest approved version)" Advanced Nuclear Fuels Comoration Methodology for Boiling

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

6.7 249b REV

_ _ _ _ _ _ _ _ _ _ _ ___ __.____ _ __ _ ____ ___ _ _ _ _ _ _ _ _ _ _ ___ ._ ---._._._ _ _ . . - . . . . _ . _ _ _ _ . . ._, ..1.._ -_...,,__.._.m.-.-..

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-Bases Continuedt f .

MCPR Limit is determined from the analysis of transients discussed in Bases Sections 2.1 and 2.3. By maintaining an operating MCPR above these limits, the Safety Limit (T.S. 2.1. A) is maintained in the ., ,

event of the most limiting abnormal operational transient.

At less than 100% of rated flow and power the required MCPR is the larger value of the MCPR, and MCPR, at the existing core flow and power state. The required MCPR is a function of flow in order to protect the core from inadvertent core flow increases such that the 99.9% MCPR limit' requirement can be assured.

Flow runout events are analyzed with the purpose of establishing a flow dependent MCPR limit that would prevent the Safety Limit CPR from being reached during a flow runout. A flow runout event is a slow ,

flow and power increase which is not terminated by a scram, but which stabilizes at a new core power

- corresponding to the maximum possible core flow. Initial conditions for the transient are set such ,

that the limiting CPR is near the Safety Limit. MCPR values are determined from'the resulting change in ,

CPR when core flow is increased to-a-possible maximum. Several combinations of initial power, flow, and exposure are analyzed to cover the range of operability defined by the power / flow map. The calculated ,

flow dependent MCPR limit (MCPRr) for a given core flow is provided in the Core Operating Limits Report.

For operation above 45% of rated thermal power,-the core power dependent MCPR operating limit is the rated MCPR limit, MCPR(100), multiplied by the factor, provided in the Core Operating Limits Report.

For operation below'45% of rated thermal power (turbine control valve fast closure and turbine stop '

valve closure scrams can be bpassed) MCPR limits are provided in the Core Operating Limits Report.

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This protects the-core from plant transients other than core flow increase, including a locali:*d event such as rod withdrawal error.

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