Text

Amend 111 to License NPF-43,revising TS SR 4.3.1.3 for Reactor Protection Sys Instrumentation to Indicate That Certain Sensors Exempt from Response Time Testing
	ML20138B692
Person / Time
Site:	Fermi
Issue date:	04/18/1997
From:	Kugler A; NRC (Affiliation Not Assigned)
To:	;
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ML20138B697	List: ML20138B692; ML20138B700;
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	NUDOCS 9704290239
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UNITED STATES aj NUCLEAR REGULATORY COMMISSION f,g WASHINGTON, D.C. 20066 4001

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DETROIT EDISON COMPANY DOCKET NO. 50-341 i

FERMI-2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 111 License No. NPF-43 1.

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

A.

- The application for amendment by the Detroit Ecison Company (the licensee) dated March 27, 1997, as supplemented on April 4, 1997, 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 conformity with the application, the provisions of the Act, and the rules and regulations of the l

Commission; C.

There is reasonable assurance (1) 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 3

conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common l

defense and security or to the health and safety of the public; and E.

The issuance of this d..andment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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9704290239 970418 PDR ADOCK 05000341 P

PDR 4

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, 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-43 is hereby amended to read as follows:

Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.111, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

t DECO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance with full implementation prior to entry into Operation Condition 2 or 3.

FOR THE NUCLEAR REGULATORY COMMISSION j

Andrew J. Kugler, Project Manager Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation i

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Attachment:

Changes to the Technical i

Specifications s

Date of Issuance: April 18, 1997 4

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ATTACHMENT TO LICENSE AMENDMENT NO.111 FACILITY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

REMOVE INSERT 3/4 3-l*

3/4 3-1*

3/4 3-la 3/4 3-13 3/4 3-9 3/4 3-9 3/4 3-10 3/4 3-10 3/4 3-23 3/4 3-23 3/4 3-24*

3/4 3-24*

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0verleaf page provided to maintain document completeness.

No changes contained on these pages.

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f 3/4.3 INSTRUMENTATION I

i 3/4.3.1 REACTOR PROTICT10N EViivi INSTRLMENTAT10N LIMITING CONDITION FOR OPERATION j.

3.3.1 As a minimum, the reacter protection system instrumentation channels i

shown in Table 3.3.1-2 shall be OPERABLE.

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APPlICARILITY: As shown in Table 3.3.1 1.

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ifith the number of OptRABLE channels less than required by the Minimum i

OPERABLE channels per Trip Eystem requirement for one trip system:

3.

Within 1 bour, verify that each Functional Unit within the i

affected trip system contains ne more than one inoperable channel or place the inoperable channel (s) and/or that trip system in the tripped condition *.

2 2.

If placing the inoperable channel (s) in the tri would cause a scram, the inoperable channel (s) pped con i

stall be restored to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or the AC' ION required by Table 3.3.1-1 for the affected Functional Unit shall be taken.

3.

If placing the inoperable channel (s) in the tri.pped condition would not cause a scram, place the inoperable citannel(s) and/or that trip system in the tripped condition within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b.

With the number of OPERA 8LE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip system ** in the tripped condition within I hour and take the ACTION required by Table 3.3.1-1.

'An inoperable channel need not be placed in the tripped condition where this would cause a scram to occur. In these cases, the inoperable channel shall be-restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after the channel was first determined to be inoperable or the ACTION required by Table 3.3.1-1 for that Functional Unit shall be taken.

- The trip system need not be placed in the tr!pped condition if this would cause a scram to occur. When a trip system can he placed in the tripped condition without causing a scram to occar, plece'tto trip system witt the most inoperaHe channels in the tripped condition; if both systems have the same number of inoperable channels, place either trip system in the tripped condition.

FERMI - UNIT 2 3/4 3 1 Amendment No. N, pp,100 JUN p g

1 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REOUIREMENTS 4.3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations for the OPERATIONAL 1

CONDITIONS and at the frequencies shown in Table 4.3.1.1-1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit

shall be demonstrated to be within its limit at least once l

per 18 months. Neutron detectors are exempt from response time testing.

Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip system.

The sensor response time for Reactor Vessel Steam Dome Pressure - High and Reactor Vessel Low Water Level - Levell need not be measured and may be assumed to be the design sensor response time.

FERMI - UNIT 2 3/4 3-la Amendment No. 7), J## 111

$NSTRUMENTATIM 2/4.3.2 ISDLATIM ACTUAflg p5faseffATIM LIMITING CONDIT10N FOR OPERATim 3.3.2 The isolation acteatten instroentation channels shem in Table 3.3.t.1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint solen of Table 3.3.t-2.

l APPLICABILITY: As shoun ta Table 3.3.2-1.

EJjg:

a.

With an isolatten actestion instrumentation channel trip setpoint less conservative than the value shoun in the A11eueble Values colism of Table 3.3.t-2 declare the chamael inoperable estil the channel is restored to EPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip j

system:

1.

If placing the inoperable channel (s) in the tripped condition would cause an isolation, the inoperable channel (s) shall be restored to OPERABLE status within 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months or the ACTION required b be taken. y Table 3.3.2-3 for the affected trip function shall 2.

If placing the inoperable channel (s) in the tripped condition I

would not cause an isolation. the inomrable channel (s) and/or that trip system shall he placed in tle tripped condition within:

a) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for trip functions cosmon to RPS Instrumentation; and b) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for trip functions not common to RPS Instrumentation.

c.

With the number of OPERABLE channels less than required by the Minimum OPERA 8LE Channels per Trip System requirement for both trip systems, place at least one trip system

in the tripped condition within one hour and take the ACTION required by Table 3.3.2-1.

" Place one trip system (with the mest inoperable ci,annels) in the tripped condition. The trip system need not be placed in the tripped condition when this would cause the isolation to eccer.

FERMI - UNIT 2 3/43-9 Amendment No. #1, 75, 53,100

.WN 2 9 EM

INSTRUMENTATION l

SURVEILLANCE REOUIREMENTS 4'

4.3.2.1 Each isolation actuation instrumentation channel shall be demonstrated OPERABLE by the perfomance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL 1

CONDITIONS and at the frequencies shown in Table 4.3.2.1-1.

4.3.2.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

I 4.3.2.3 The ISOLATION SYSTEM RESPONSE TIME of each isolation trip function

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shall be demonstrated to be within its limit at least once per 18 months.

Radiation detectors are exempt from response time testing.

Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months, where N is'the total number of j

redundant channels in a specific isolation trip system.

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The sensor response time for Primary Containment Isolation Reactor Vessel Low Water Level - Level 1 and Main Steam Line Flow - High need not be measured and may be assumed to be the design sensor response time.

FERMI - UNIT 2 3/4 3-10 Amendment No. JPE,111

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INSTRUMENTATION 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3 The emergency core cooling system (ECCS) actuation instrumentation channels shown in Table 3.3.3-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.3-2.

APPLICABILITY: As shown in Table 3.3.3-1.

E11%:a.

With an ECCS actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.3-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b.

With one or more ECCS actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.3-1.

c.-

With either ADS trip system "A" or "B" inoperable, restore the inoperable trip system to OPERABLE status within:

1.

7 days, provided that the HPCI and RCIC systems are OPERABLE, othenvise, 2.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and reduce reactor steam dome pressure to less than or equal to 150 psig within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.3.1-1.

4.3.3.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.*

i 4.3.3.3 The ECCS RESPONSE TIME of each ECCS trip function ** shall be demonstrated to be within the limit at least once per 18 months.

For the diesel generator output breakers: Completion of logic system functional testing. for the loss of power function, to positively verify that the breaker reclosure permissive relay (52XX) is re-energized by the associated bus load shedding logic contact closing, rather than the 52XX i

being re-energized by a parallel path, may be deferred and must be completed no later than during the first plant outage after September 29, 1995.

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- ECCS actuation instrumentation response time need not be measured and may be assumed to be the design instrumentation response time.

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l FERMI - UNIT 2 3/4 3-23 Amendment No. J##, JS), 111

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ML20138B692

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