ML20062A186

Amend 33 to License NPF-6,amending Tech Specs Per Util 820503 & 20 Application by Allowing Loop Resistance Temp Detector Response Times to Exceed 6-s,provided Penalty Factors Inserted in Core Protection Calculator Sys

ML20062A186
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/21/1982
From:	Clark R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20062A190	List: ML20062A186 ML20062A196 ML20062A212
References
NUDOCS 8208030099
Download: ML20062A186 (10)

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!(y),c Jg UNITED STATES g

NUCLEAR REGULATORY COMMISSION g*

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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 33 License No. NPF-6 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Arkansas Power & Light Company (the licensee) dated May 3,1982, as supplemented May 20, 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; B.

The facility will operate in confonnity 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 common dei ~ense 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.

ELIO.... as OAIOldAL

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Certified By u

8208030099 820721 PDRADOCK05000g P

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2-2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-6 is hereby amended to read as follows:

(2) Technical Specifications i

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 33, are hereby incorporated in the license. The licensee shall operate i

the facility in accordance with the Technical Specifications, except where otherwise stated in specific license conditions.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION i

Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing i

Attachment:

l Changes to the Technical Specifications i

Date of Issuance: July 21, 1982 1

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ATTACHMENT TO LICENSE AMENDENT NO. 33 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines. indicating the area of change. Cor-responding overleaf page,s are provided to maintain document completeness.

Remove Paces Insert Pages IX IX 3/4 3-6a 3/4 3-6a 3/4 3-6b 3/4 3-6c B 3/4 3-1/2 B 3/4 3-1 e

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INDEX BASES SECTION PAGE 3/4.0 APPLICABILITY............................................ B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTROL......................................

B 3/4 1-1 3/4.1.2 BORAT I O N S Y S T EMS......................................

B 3/41-2 3/ 4.1. 3 MOVABLE CONTROL ASSEMBLIES............................

B 3/4 1-3

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3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE......................................

B 3/4 2-1 3/4.2.2 RADI AL PEAKING FACTORS................................

B 3/4 2-2 3/4.2.3 AZIMUTHAL POWER TILT................'..................

B 3/4 2-2 3/4.2.4 DNBR MARGIN..........................................

B 3/4 2-3 3/4.2.5 R C S F LO W RAT E......................................... B 3/4 2-4 3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE..................

B 3/4 2-4 3/4.2.7 AXIAL SHAPE INDEX.....................................

B 3/4 2-4 3/4.2.8 PRESSURIZER PRESSURE..................................

B 3/4 2-4 3/4.3 INSTRUMENTATION 3/4. 3.1 PROTECTIVE INSTRUMENTATION............................

B 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE INSTRUMENTATION............. B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION............................

B 3/4 3-2 l

3/4.3.4 TURBINE OVERSPEED PROTECTION.......................... B 3/4 3-3 l

ARKANSAS - UNIT 2 IX Amendment No.74 33

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INDEX

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SECTION

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's 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION.............. B 3/4 4-1 3/4.4.2 and 3/4.4.3 SAFETY VALVES................................... B 3/4 4-1 3/4.4.4 PRESSURIZER................................................ B 3/4 4-2

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3/4.4 5 STEAM GENERATORS........................................... B 3/4 4-2 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE.............................. B 3/4 4-3 3/4.4.7 C H EM I S TR Y.................................................. B 3 / 4 4 - 4 3 / 4. 4'. 8 SPECIFIC ACTIVITY...........................................B 3/4 4-4 3/4.4.9 PRESSURE / TEMPERATURE LIMITS......... :...................... B 3/4 4-5 3/4.4.10 STRUCTURAL INTEGRITY....................................... B 3/4 4-11 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4. 5.1 S AFETY INJ ECTION TAN KS..................................... B 3/4 5-1 3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS................................. B 3/4 5-1 3/4.5.4 REFUELING WATER TANK (RWT)................................. B 3/4 5-2 3/4.6 CONTAINMENT SYSTEMS 3/ 4. 6.'1 PRI MA RY CO NTA I NM ENT........................................ B 3/ 4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS....................... B 3/4 6-3 3/4.6.3 CONTAINMENT ISOLATION VALVES............................... B 3/4 6-4 3/4.6.4 COMBUSTIBLE GAS CONTROL

.....................................B 3/4 6-4 ARKANSAS - UNIT 2 X

Amendment No. 2 9

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h TABLE 3.3-2 (Continued)

REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES g

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5 FUNCTIONAL UNIT RESPONSE TIME T

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10. DNBR - Low

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a.

Neutron Flux Power from Excore Neutron Detectors

< 0.39 seconds

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CEA Positions

{l.09secondsjj c.

Cold Leg Temperature

< 3.79 secondsgg d.

Hot Leg Temperature

< 1.54 seconds e.

Primary Coolant Pump Shaft Speed 7 0.80 seconds #

f.

Reactor Coolant Pressure from Pressurizer

{3.19 seconds

11. Steam Generator Level - High Not Applicable s"

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In Neutron detectors are exempt from response time testing. Response time of the neutron flux signal l

portion of the channel shall be measured from detector, output or input of first electronic component in channel.

Response time shall be measured from the onset of a single CEA drop.

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1. esponse time shall be measured from the onset of a 2 out of 4 Reactor Coolant Pump coastdown.

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1. 1. ased on a resistance temperature detector (RTD) response time of < 6.0 seconds where the RTD B

l response time is equivalent to the time interyal required for the RTD output to achieve 63.2%

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, of its total change when subjected to a step change in RTD temperature.

O If the effective RTD time constant for a CPC channel exceeds 6.0 seconds, the DNBR and LPD penalties for the affected channel (s) shall be increased by the amount indicated on Figure 3.3-1, and the Power Operating Limit on DNB will be decreased by the amount shown in Table 3.3-3.

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DNBR POWER OPERATING LIMIT ADJUSTMENTS Effective RTD Time' Constant Penalty (Seconds)

(% Power) 1 6.0 0

6.0 < r 1 8.0 4

8.0 < t < 10.0 5

10. 0 < T 1 13. 0 9

ARKANSAS - UNIT 2 3/4 3-6b Amendment No. 33 e

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CPC PENALTY VS. EFFECTIVE RTD TIME CONSTANT s

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ARKANSAS - UNIT 2 3/4 3-6c Amendment.No. 33 e

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3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF)

INSTRUMENTATION The OPERABILITY of the protective and ESF instrumentation systems and bypasses ensure that 1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its setpoint,

2) the specified coincidence logic is maintained, 3) sufficient redundancy is main-tained to permit a channel to be out of service for testing or maintenance, and

4) sufficient system functional capability is available for protective and ESF purposes from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliabil-ity, redundancy and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.

The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses. No credit was taken in the analyses for those channels with response times indicated as not applicable.

Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or

2) utilizing replacement sensors with certified response times.

The RTD response time for the Core Protection Calculator System (CPCS) is expressed as an effective time constant. The effective time constant is determined' based on the utilization within the CPCS calculations.

For hot leg t' mperatures, e

the effective time constant to be used in Figure 3.3-1 for a given CPC channel is determined from the mean time onstant for averaged pairs of hot leg RTD inputs to the channel. This is done because the CPCS utilizes the mean hot leg temperature in its DNBR and LPD calculations.

For cold leg temperatures, the effective time constant to be used in Figure 3.3-1 may be considered to be the smaller time constant of the two cold leg RTD inputs for a given channel. This is due to the fact that the CPC utilizes either the maximum cold leg temperature or the minimum cold leg temperature in its various DNBR and LPD calculations for conservatism.

However, for asymmetric steam generator protection, the maximum time constant of the two cold leg RTDs input to a given channel must be used in Table 3.3-3 since the CPC utilizes both cold leg RTD inputs in this calculation.

ARKANSAS - UNIT 2 B 3/4 3-1 Amendment No. 33

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3/ 4.'3 INSTRUMENTATION i

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i 3/4.3.3 MONITORING INSTRUMENTATION N

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3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION

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4 The OPERABILITY of the radiation monitoring channels ensures that 1) the t

radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.

3/4.3.3.2 INCORE DETECTORS j

The OPERABILITY of the incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system

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accurately represent the spatial neutron flux distribution of the reactor core.

3/4.3.3.3 SEISMIC INSTRUMENTATION i

The OPERABILITY of the seismic instrumentation ensures that sufficient i

capability is available to promptly determine the magniture of a seismic event and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured. response to that used in the I

design basis for the facility to determine if plant shutdown is required pursuant i

to Appendix "A" of 10 CFR Part 100. The instrumentation is consistent with the i.

recommendations of Regulatory Guide 1.12. " Instrumentation for Earthquakes,"

April 1974.

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3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient i

i meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating.

protective measures to protect the health and safety of the public and is' consistent with the recommendations of Regulatory Guide 1.23. "Onsite Meteorological Programs," February 1972.

3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with' General Design Criteria 19 of 10 CFR 50.

t ARKANSAS - UNIT 2

- B 3/4 3-2 Amendment No. 33 v

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