Text

Amend 13 to License DPR-22,changing Tech Specs to Incorporate Revised Safety & Operating Limits Associated W/Operational Facility During Fuel Cycle 10
	ML20070J513
Person / Time
Site:	Monticello
Issue date:	12/06/1982
From:	Vassallo D; Office of Nuclear Reactor Regulation
To:	; Northern States Power Co
Shared Package
ML20070J516	List: ML20070J513; ML20070J517; ML20070J520;
References
	DPR-22-A-013 NUDOCS 8212280003
	Download: ML20070J513 (9)
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NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 MONTICELLO NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 13 i

License No. DPR-22 L

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1.

The Nuclear Degulatory Comission (the Comission) has found that:

A.

This application for amendment by Northern States Power Compan'y (.the licensee) dated June 25, 1982 and supplements dated August 3, and 24th, 1982 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 1

B.

T'he facility will operate-in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements

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.have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license arardment, ;ne paragraph 2.C.2 of Facility Operating License No. DPR-22 4s hereby e'

amended to read as follows:

2.

Technical Specifications The Technical Specifications contained in Appendices A and D as I

revised through Amendment No. 13 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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This license amendment is effective as of the date of its issuance.

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i FOR 1IHE NUCLEAR RGULATORY COPHISSION Domenic B. Vassallo. Chief Operating Reactors Branch #2 l

Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: December 13, 1982 l

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m_ g i at ATTACHMENT TO LICENSE AMENDMENT NO.13 FACILITY OPERATING LICENSE NO. DPR-22 DOCKET NO. 50-263 Remove the following pages and insert identically numbered pages:

INSERT 82 212 21 3 214 215 4

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cyj 1.0 f.IMITING COHnITIONS FOR OPERATION 4.0 SilRVEII.I.ANCE HEf)UIREMEffrS I 'l M4 gl

Any four rod group may contain a, control rod which in valve 51 i

4 out of service provided the above requirements and Specifica-l g

t ion 3. 3. A a re me t.

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If the cycle average scram insertion time ( % ). hased on the t

a 3

3 de-energization of the scram pilot valve solenoids at t i me ~ r.e t o,

of all operable control rodn in the reactor power operat ton j

condition at the 20% inserted position is larger than the 3

adluated analysis mean agram time ('t's

), a more rest rict Ive HCPR limit (see section 3.II.C ) shall he used.

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D.

Coitrol Rod Accumulators D.

Control Rod Accipsulators In the "Startup" or "Run" Mode, a rod accuanslator may he inoperabic Once a ' Shift' check the status

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provided that no other control rod in the nine-rod square array in the cont rol room of the 43 around this rod has a:

1 reqnt <cd Operable accumulator pressurs' and level' alarms.

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Inoperable accumulator.

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Directional control valve electrically disarmed while in a j

non-fully inserted position.

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1 11 a control rod with an inoperable accumulator is inserted

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'" full-in" and its directional / control valves are electrically

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disarmed, It shall not be considered to have an inoperable accumulator.

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gl In the " Refuel" Mode, the accumulator associated with any (j-withdrawn control rod must be Operable unless att the fuel

'I has been removed from the cell. containing that control rod.

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Amendmenti No; y, X,13 l<

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I 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 1;

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minutes to restore operation.to within the prescribed limits. Surveillance and corres-ponding action shall continue until reactor operation is within the prescribed limits.

If the APLHCR is not returned to within the g

prescribed limits within two (2) hours, the reactor shall be brought to the Cold Shutdown condition within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

i 3.

Linear Heat Generation Rate (LHGR) 8.

Linear Heat Generation Rate (LHCR)

During power operation, the LHCR shall be The LHCR shall be checked daily during l I

limited to:

reactor operation at E 25% of rated

~ thermal power.

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LHCR $ 13.4 kw/ft

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If at any time during operation it is de-termined that the limiting value for LHCR is l

being exceeded, action shall be initiated 4:

within 15 minutes to restore operation to within the prescribed limits. Surveillance li and corresponding action shall continue until reactor operation is within the pre-scribed limits. If the LHCR is not.

returned to within the prescribed limits

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within two (2) hours, the reactor shall be brought to the Cold Shutdown condition within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

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I 3.11/4.11 212

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. Amendment No.13 8

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M r3 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS C. Minimum Critical Power Ratio (MCPR)

C. Minimum Critical Power Ratio"(MCPR)

I During power opera'tlon the Operating MCPR Limit MCPR shall be determined daily during l

shall be 21.36 for 8x8,21.37 8x8R fuel, E1.39 reactor power operation at at 25% rated for P8x8R fuel at rated power and flow, provided thermal power and following any change -

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(see section 3.3.C.3).

If at any.

In power level or distribution which has time during operation it is determined that the the potential of bringing the core to its

,i limiting value for MCPR is being exceeded, action operating MCPR Limit.

j shall be initiated within 15 minutes to restore operation to within the prescribed limits. Surveil-lance and corresponding action shall continue until reactor operation is within the prescribed limits.

If the st.?sdy state MCPR is not returned to within the prescribed limits within two (2) hours, the reactor shall be brought to the Cold Shutdown con-dition within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . For core flows other than rated the Operating MCPR Limit shall be the above I

applicable MCPR value time K where K is as shown j

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in Figure 3.11.3.

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If 1 Gen >* "fs,, the operating MCPR Limit shall be a linear interpolation between the limits in 3.II.C and 1.41 for 8x8,1.42 for 8x8R fuel and 1.44 for P8x8P fuel.

3.11/4.11 213 i

'Amendme'nt No. 5,13 r

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1, Bases 3.11 a

A. Average Planar Linear Hedt Generation Rate (APLHCR).

This. specification assures that the peak cladding temperature following the postulated design basis loss-of-coolant accident will not exceed the limit specified in' the 10CFR50, Appendix K.

, The peak cladding temperature'following a postulated loss-of-coolant accident is primarily a function of the average heat generation rate of all the rods of a fuel ~ assembly at any axial location and is

.g only dependent secondarily on the rod to rod power distribution within an assembly. Since expected local variations in power distribution within a fuel assembly affect the calculated peak cladding "4

temperature by less than + 20* relative to the peak temperature for a typical fuel design, the limit on the average linear heat generation rate is sufficient to assure that calculated temperatures

.j are within the 10CFR50 Appendix K limit. The limiting value for APLHGR is given by this specification.

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Reference 6 demonstrates that for lower initial core flow rates the tpotential exists for earlier DNB

'l during postulated LOCA's.

Therefore a more restrictive limit for APLHCR is required during reduced flow conditions.

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Those abnormal operational transients, analyzed in FSAR Section 14.5, which result in a automatic reactor scram are not considered a violation of the LCO.

Eyceeding APLHCR limits in such cases need not be reported.

B. LHCR This specification assures that the linear heat generation. rate in any rod is less than the design linear heat generation.

Those abnormal operational transients, analyzed in FSAR Sect, ion 14.5, which result in an automatic reactor scram are not considered a violation of the LCO.

Exceeding LHCR limits' in such cases need not be(eported.

I 3.11 BASES 215 Amendment No. 13 i

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, i R i0 Bases Continued C. Minimum Critical Power Ratio (MCPR) s The ECCS evaluation presented in Reference 4 and Reference 6 assumed the ste'ady state MCPR prior to the postulated loss-of-coolant accident to be 1.24 fo'r all fuel types for normal and reduced flow. The Operating 8

.MCPR Limit is determined from the analysis of transients discussed in Bases sections 2.1 and 2.3.

By maintain-

, ing 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.

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.j l Use of CE's new ODYN code Option B will require average scram time to be a factor in determining the MCPR

6. A (ODYN code Option A), the 0 l (Reference 7).

In order to increase the operating envelope for MCPR below MCPR cycle average scram time (1'..s) must be determined (see Bases 3.3.C).

If is below the adjusted analysis scram time, the MCPR Limit can be used.

If T.) T a linear interpolation must be used to determine the o

g appropriate MCPR. For example:

MCPR = MCPR,+

-- (MCPR -MCPR A

B i

HCPR and MCPR ave been determined from the most limiting accident analyses.

B For operation with less than rated core flow the Operating MCPR Limit is adjusted by multiplying the above limit by K. Reference 5 discusses how the transient. analysis done at rated conditions encompasses the g

j reduced flow situation when the proper K factor is app 11,ed, g

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Those abnormal operational transients, analyzed in FSAR Section 14.5, which result in an automatic reactor scram are not considered a. violation of the LCO.

Exceeding. HCPR limita in such cases need not be reported.

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i-i 3.11 BASES 216 6

Amendment No. 5,13 i

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ML20070J513

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