ML20071F445
| ML20071F445 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 06/30/1994 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20071F449 | List: |
| References | |
| NUDOCS 9407080225 | |
| Download: ML20071F445 (6) | |
Text
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- 'e / i E UNITED STATES
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NUCLEAR REGULATORY COMMISSION g-j wassisovow. o.c. rosswooi i
NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANJ AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 License No. DPR-22 1.
The Nuclear Regulatory Commission (the Commission) has found that:
2 A.
The application for amendment by Northern States Power Company (the licensee) dated January 4, 1994, supplemented March 28, 1994, complies with the standards and requirements of the Atomic Energy 'et of 1954, as amended (the Act), and the Commission's rules and rr4 intions set forth in 10 CFR Chapter I; D.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the cohmon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragr,ph 2.C.2 of facility Operating License No. DPP-22 is hereby amended t. read as follows:
9407000225 940630 PDR ADOCK 05000263 P
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2-1echnical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 88, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
FOR TH UCLEAR REGULATORY COMMISSION yk for Ledyard B. Marsh, Director Project Directorate 111-1 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 30, 1994 l
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k A
ATTACHMENT TO LICENSE AMENDMENT NO. 88 4
FAClllTY OPERATING LICENSE NO. DPR-22 E0CKET NO. 50-263 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
REMOVE INSERT 211 211 217 217 249b 249b l
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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.11 REACTOR WEL ASSEMBLIES 4.11 REACTOR WEL ASSE!1BLIES Applicability Apolicability 1
6 I
The' Limiting Conditions for Operation The Surveillance Requirements apply to associated with the fuel rods apply to those the parameters w* tch monitor the fuel i
parameters which monitor the fuel rod rod operating ccaditions.
1 operating conditions.
1 Obiective i
Obiective i
The objective of the Surveillance i
The objective of the Limiting Conditions for Requirements is to specify the type and L
t herstIon is to assure the performance of frequency of surveillance to be applied l
the fuel ruds.
to the t'uel rods, i
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Specifications Specifications t
4 9
A.
Averare Planar Linear Heat Generation A.
Averane Planar Linear Heat jf Kate IAFLMbK)
Generation Mste (APLMbK)
I Durin two recirculation loop operation.
The APLHGR for each type of fuel i
the ArLMGR for each twe of fuel as a as a function of average planar function of averare p1a'nar exposure exposure shall be determined daily I
shall not exceed he applicable limiting during reactor operation at 2231 values specified in the Core Operating rated thermal power.
a Limits Report. When hand calculations the APLHGR for each type are reautred, function of average planar of fuel as a exoosure shall not exceed the Ilmiting i
value for the most limitin lattice the Core @g natural uranium providei in (excludin erating Limits eport.
During one recirculation loop power operation, ion for each type otthe APLHGR limiting condition for operat fuel shall not exceed the above values l
multiplied by O.85.
4 Ifatanferminedthak$heAPLbGReration, time durin over it is de limiting condition for operation is being exceeded action shall be i
1 initiated within 15 minutes to restoro l
operation to within the prescribed limits. Surveillance and correrponding i
action shall continue until reactor I
j operation is within the prescribed i
limits.
If the APLHGR is not returned i
to within the prescribed limits sithin i
two hours,ithin the nextthermal power to less reduce than 25I w four hours.
211
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3cll/4.11 4
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L Amendnent f40. $/,70,88 l
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A..
Bases Contin _ted:
i4CPR Limit is determined from the analysis of transients discussed in Bases Sections 2.1 and 2.3.
By maintaining an operating MCPR above these limLts, 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 ti.
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 99.91 MCPR limit requirement can be assured.
Flow runout events are analyzed with the purp ose of establishing a flow dependent MC?R 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 result!.ig change in CPR when core flow is increased to a possible maximum.
Several combinations of iniilai power, flow, and exposure are analyzed to cover the range of operability defined by the power / flow map.
The calculated flow dependent MCPR limit (MCPR ) for a given core flow is provided in the Core Operating Limits Report.
r For operation above 45% of rated thermal power, the core power dependent MCPR operating limit is the rated MCPR limit MCPR(LOO), multiplied by the factor, provided in the Core Operating Limits Report.
For operation below 45I of rated thermal power (turbine control valve fast closure and turbine stop valve closure scrans can be bypassed) MCPR limits are provided in the Core Operating Limits Report.
This protects the core from plant transients other than core flow increase, including a localized event such as rod withdrawal error.
b 3.11 BASES 217 Amendment tk). $J,/0,88
7.
Core Ooerstine Limits Report Core operating limits shall be established and documented in the Core Operating Limits Report before a.
each reload cycle or any remaining part of a reload cycle for the following:
Rod Block Monitor b erability Requirements (Specificetion 3.2.C.2a)
Rod Block Monitor Upscale Trip Settings (Table 3.2.3, item 4.a) t Maximus Average Planar Linear Heat Generation Rate Limits (Specificatien 3.11.A)
Linear Heat Generation Ratio Limits (Specification 3.ll.B)
Minimum Critical Power Ratio Limits (Specification 3.ll.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 l
time the reload analyses are performed) i I
NSPNAD-8608-A, " Reload Safew Evaluation Methods for J.pplication to the Monticello l
Nuclear Generating Plant" (the approved version ac the time the reload analyses are performed) l JSPNAD-8609-A, " Qualification of Reactor Physics Methods for Application to Monticello" (the approved version at the time the reload analyses Ore performed)
I ANF-91-0481(P)(A) del," Siemens Power Corporation (the approved version at the time the reload" Advanced Nuclear Fuels Corpora r
BWR Evaluation Mo analyses are performed) j Thecoreoperatinglimitsshallbedeterminedsuchthatallakplicablelimits(eg, fuel j
c.
thermal-mechanica. ILaits, core thermal-hydraulic limits, ECC limits, nuclear limits such as shutdown margin, transient analysis limits and accident analysis limits) of the safety analysis are i
met.
d.
The Core Operating Lir'ts Report, including any mid-cycle revisions or supplements, shall be supplied upon issuance, for escr. reload cycle, to une PG.C Document Control Desk with copies to the Regional Administrator and Resident Inspector.
6.7 249b i
Amendment N. Jp,7,/,88
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