ML20129G961

Amend 235 to License DPR-59,eliminating Selected Response Time Testing Requirements for Certain Sensors & Specified Loop Instrumentation

ML20129G961
Person / Time
Site:	FitzPatrick
Issue date:	10/28/1996
From:	Bajwa S NRC (Affiliation Not Assigned)
To:
Shared Package
ML20129G964	List: ML20129G961 ML20129G968
References
NUDOCS 9610300288
Download: ML20129G961 (7)

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• ge UNITED STATES j

NUCLEAR REGULATORY COMMISSION t

WASHINGTON, D.C. 20066-0001

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POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR POWER PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 235 License No. DPR-59 1.

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

J A.

The application for amendment by Power Authority of the State of New York (the licensee) dated May 30, 1996, as supplemented by letter dated October 11, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I;

B.

The facility will operate in conformity with the application, 4

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

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 j

have been satisfied.

1 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, 4

and paragraph 2.C.(2) of Facility Operating License No. DPR-59 is hereby amended to read as follows:

9610300288 961028 PDR ADOCK 05000333 i

P PDR x,;

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 235, 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 its issuance to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION S. Singh Bajwa, Acting Director Project Directorate I-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: October 28, 1996 i

ATTACHMENT TO LICENSE AMENDMENT NO.235 i

FACILITY OPERATING LICENSE NO. OPR-59 DOCKET NO. 50-333 Revise Appendix A as follows:

Remove Paaes Insert Paaes 30g 30g 38 38

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JAFNPP 3.1 LIMITING CONDITIONS FOR OPERATION 4.1 SURVEILLANCE REQUIREMENTS 3.1 REACTOR PROTECTION SYSTEM 4.1 REACTOR PROTECTION SYSTEM Acohcatphty:

Anchcatmhtv:

Applies to the instrumentation and associated devices which Applies to the survesilance of the instrumentation and associated l

initiate the reactor scram.

devices which initiate reactor scram.

i Obiective:

Oblectsve:

i To assure the operability of the Reactor Protection System.

To specify the type of f,requency of survestlance to be apphed to the protection instrumentation.

Specification:

Specification:

f A' The setpoints and mmemum number of instrument A.

Instrumentation systems shall be functionally tested and calibrated f

channels per trip system that must be operable for each, as indicated in Tables 4.1-1 and 4.1-2 respectively.

position of the reactor mode switch, shell be as shown m Table 3.1-1.

The response time of the reactor protection system trip functions j

listed below shall be demonstrated to be wetten its limit once per i

24 months. Neutron detectors are exempt from response time testing. Each test shall include at least one chonnel in each trip system. All channels in both trip systems shell be tested within l

two test intervals.

1. Reactor High Pressure IO2-3PT-55A, B, C, D) l

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2. Drywell High Pressure 105PT-12A,8, C, D)

3. Reactor Water Level-Low (L3) (02-3LT-101 A, 8, C, D) f,

4. Mein Steam Line Isolation Velve Closure L

(29PNS-80A2, B2, C2, D2) i (29PNS-86A2, B2, C2, D2)

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5. Turbine Stop Velve Closure (94PNS-101,102,103,104)

6. Turbine Control Valve Fast Closure (94PS-2OOA. B C, D)

7. APRM Fixed High Neutron Flux

8. APRM Flow Referenced Neutron Flux

• Sensor is ehmeneted from response time testing for the RPS actuotion i

logic circuits. Response time testing and conformance to the test acceptance criteria for the remeening channel components includes trip unit and re8ay logic.

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' Amendment No. 227,222, 1

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JAFNPP l

i 4.1 BASES (cont'd) l The indivuluel sensor response time may be measured by B. The MFLPD is checked once per day to determme if the sunulating a step change of the porticular parameter. This APRM scram requires W-i..

.i. Only a senell number of method provides a conservative value for the sensor control rods are moved daily and thus the MFLPD is not

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response time, and confirms that the instrument has expected to change significantly and thus a daily check of

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retained its specified electromecherucal characteristics.

the MFLPD is adequate.

i When sensor response time is measured independently, it is necessary to also measure the remowsng portion of the The sensitivity of LPRM detectors decreases with exposure s

response time in the logic train up to the time at which the to neutron flux et a slow and appronometely constant rete.

I scram pilot volve scienceds de-energize. The channel This is compensated for in the APRM system by calibrating i

response time must include all component delays in the twice a week using host belance data and by calibrating response chain to the ATTS output relay plus the design individuel LPRM's every 1000 effective fun power hours, I

allowance for RPS logic system response time. A response using TIP traverse date.

I time for the RPS logic releys in excess of the desegn

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allowance is acceptable provided the overall response time does not exceed the response time limits specified in the UFSAR. The bases for excludeng the neutron detectors from response time testing is provided by NRC Regulatory Guide

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1.118, Revision 2, section C.S.

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i The sensors for the Reactor High Pressure and Reactor f'

Water Level - Low (L3) trip functions are exempted from response time testeg based on analyses provided in NEDO-32291-A, " System Analyses for the Elimenetion of Selected Response Time Testing".

Two instrument chonnels in Table 4.1-1 have not been mcluded in Table 4.1-2. These are: mode switch in shutdown and manuel scram. All of the devices or sensors associated with these scram functions are semple on-off f

switches and, hence, calibration during operation is not l

applicable.

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Amendment No. 14,29, ?31, ?S3, 227, 233, 235 38 t

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JAFNPP i

3.2 LifWTING CONDITIONS FOR OPERATION 4.2 SURVEILLANCE REQUIREMENTS 3.2 INSTRUMENTATION 4.2 INSTRUMENTATION Aachcability:

Accimatuhtv:

Applies to the plant instrumentation which either (1) initiates and Applies to the surveillance requwement of the instrumentation which f

controls a protective function, or (2) provides information to aid either (1) initiates and controls protective function, or (2) provides the operator in monitoring and assesseng plant status during information to aid the operator in monstonng and assessing plant i

normal and accident conditions.

status during normal and accident conditions.

l Otmactsve-Otusctsve-To assure the operability of the aforementioned instrumentation.

To specify the type and frequency of surveellence to be appised to i

the aforementioned instrumentation.

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Specifications:

Specifmetions:

A. Prwnst r Containment isolation Functions A.

Prunary Containment laalanen Functsang l

When primary containment integrity is required, the limiting Instrumentation shen be functoonelly tested and calibrated as conditions of operation for the instrumentation that initiates indicated in Table 4.2-1. System logic shell be functionally L

primary contamment isolation are given in Table 3.2-1.

tested as indicated in Table 4.2-1.

i The response time of the main steem isoletion volve actuation I

instrumentet on isoletion trip functions hsted below shen be demonstrated to be within their limits once por 24 months.

i Each test shell include at toest one channel in each trip system.

All chonnels in both trip systems shen be tested withen two test i

intervals.

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1. MSIV Closure - Reactor Low Water Level (L1)

(02-3LT-57A,8 and 02-3LT-58A,8)

2. MSIV Closure - Low Steam Line Pressure *

(02PT-134A,B,C D)

3. MSIV Closure - High Steem Line Flow *

(02DPT-1 16 A-D, 1 17A-D, 1 18 A-D, 1 19A-D) 1

• Sensor is elemensted from response time testing for the MSIV actuation logic circuits. Response time testing and conformance to the test acceptance critoria for the rememing channel components includes trip unit and relay logic.

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. Amendment No. 12^. ? S3, 227, 233, 235 i

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JAFNPP 4.2 BASES The instrumentation listed in Tables 4.2-1 through 42-8 will be 5.

GE Topical Report NEDC-30936P-A, Parts 1 and 2, "BWR functionally tested and cahbrated at regularly scheduled Owners Group Techrncal Specification imprownnent intervals. The same design reliabihty goal as the Reactor Methodology (With Demonstrahon for BWR ECCS Protection System is generally apphed. Sensors, trip devices Actuation Instrumentation)," December 1988.

and power supphes are tested, cabbrated and checked at the 1

"samQrequency as comparable dewces in the Reactor Protection 6.

. GE Topical Report GENE-770-06-1-A, " Bases for Changes i System.

to Surventance. Test intervals and Anowed Out-Of-Serwce i

Times For Selected instrumentation Technical The surveillance test interval for the instrumentation channel Specificahons," December 1992.

functional tests are once/three months for most instrumentation.

This surveillance interval is based on the following NRC 7.

GE Topical Report GENE-77006-2-A, " Addendum to Bases

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approved licensing topical reports:

a

p ",'

for Changes to SurvelRance Test Intervals and Apowed Out.

, Of-Serwce Times For Selected instrumentation Technical 1.

GE Topical Report NEDC-30851P-A, " Technical Speedications," December 1992.

Specification livec.;... eat Analysis for BWR Reactor Protection System," March 1988.

The measurement d the response time interval for the Main 2.

GE Topical Report NEDC-30851P-A, Supplement 1 Steam isolahon Valve (MSIV) isolabon actuahon instrumentation I

"Techrucal Speedication Improvement Analysis for BWR begins when the monitored parameter exceeds the isotahon Control Rod Block Instrumentation," October 1988.

actuahon setpomt at the channel sensor and ends when the MSIV pilot solenoid relay contac's open. WNh the excephon d 3.

GE Topical Report NEDC-30851P-A, Supplement 2 the MSIVs, response time teshng is not required for any other "Techrscal Specification improvement Analysis for BWR primary containment isolation actuahon instrumentation. The tsolahon Instrumentation Common to RPS and ECCS safety analyses results are not sensitive to individual sensor l

Instrumentation," July 1986.

iespur6e times d the logic systems to which the sensors are f

connected for isolation actuation instrumenlahon. The sensors 4.

GE Topical Report NEDC-31677P-A, " Technical for the MSIV actuation isolation titp funchons are exempted from i

Specification liipc...rw6i Analysis for BWR isolation response time testing based on analyses provided in NEDO-Actuation Instrumentation, " July 1990.

32291-A, " System Analyses for the ENmineNon d Selected Response Time Tesung".

I Amendment No. 00,10', tSt.100,227,235 m

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