Text

Amend 195 to License NPF-6,modifying Actions Associated with TS Table 3.3-1 for Reactor Protective Instrumentation & TS Table 3.3-3 for Engineered Safety Feature Actuation Sys Instrumentation
	ML20198M735
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/29/1998
From:	Nolan M; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20198M741	List: ML20198M735; ML20198M749;
References
	NPF-06-A-195 NUDOCS 9901050339
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UNITED STATES j

j NUCLEAR REGULATORY COMMISSION f

WASHINGTON, D.C. 30686-0001 49.....,o ENTERGY OPERATIONS. INC.

DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDj 1ENT TO FACILITY OPERATING LICENSE Amendment No 195 License No. NPF-6 1.

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

j A.

The application for amendment by Entergy Operations, Inc. (the licensee) dated l

July 28,1997, 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; i

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 1

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 license amendment will not be inimical to the common defense and security or to the health and safety of the public; and j

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.

i 9901050339 981229 PDR ADOCK 05000368 PDR P

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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-6 is hereby amended to read as follows:

2.

Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 195 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The license amendment is effective as of its date of issuance to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION N

b M. Christopher Nolan, Project Manager Project Directorate IV-1 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: Deceiaber 29, 1998

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i ATTACHMENT TO LICENSE AMENDMENT NO.195 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Revise the following pages of the Appendix "A" Tecnnical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of <:hange. The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE PAGES INSERT PAGES i

3/4 3-5 3/4 3-5 3/4 3-Sa 3/4 3-Sa

'3/4 3-14 3/4 3-14 3/4 3-15 3/4 3-15 B 3/4 3-ja B 5/4 3-1a B 3/4 3-1b B 3/4 3-1b i

9 1

V TABLE 3.3-1 (Continued)

ACTION STATEMENTS

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I ACTION 2 - With the number of channels OPERABLE one less than the Total Number of Channels, operation in the applicable MODES may continue provided the l

inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

If the inoperable channel is bypassed for greater than 48 2

hours, the desirability of naintaining this channel in the bypassed i

condition shall be reviewed at the next regularly scheduled PSC meeting in accordance with the QA Manual Operations. The channel shall be returned to OPERABLE status prior to startup following the next COLD SHUTDOWN.

dith a channel process measurement circuit that effects multiple functional units inoperable or in test, bypass or trip all associated functional units as listed below.

Process Measurement Circuit Functional Unit Bypassed 1.

Linear Power Linear Power Level - High (Subchannel or Linear)

Local Power Density - High i

DNBR - Low i

Log Power Level - High' 2.

Pressurizer Pressure - NR Pressurizer Pressure - High Local Power Density -High DNBR - Low 3.

Containment Pressure - NR Containment Pressure - High (RPS)

Containment Pressure - High (ESFAS)

Containment Pressure - High-High (ES EAS) 4.

Steam Generator 1 Pressure Steam Generator 1 Pressure - Low Steam Generator 1 AP (EFAS 1)

Steam Generator 2 AP (EFAS 2) 5.

Steam Generator 2 Pressure Steam Generator 2 Pressure - Low Steam Generator 1 AP (EFAS 1)

Steam Generatcr 2 AP (EFAS 2) 6.

Steam Generator 1 Level Steam Generator 1 Level - Low Steam Generator 1 Level - High l

Steam Generator 1 AP (EEAS 1) 7.

Steam Generator 2 Level Steam Generator 2 Level - Low Steam Generator 2 Level - High Steam Generator 2 AP (EFAS 2) l 8.

Core Protection Calculator Local Power Density - High l

DNBR - Low l

Only for failure common to both linear power and log power.

i ARKANSAS - UNIT 2 3/4 3-5 Amendment No. M,M 9,M 4,195 l.

TAELE 3.3-1 (Continusd)

ACTIOM STATEMENTS ACTION 3 - With the number of channels OPERASLE one less than the Minimum Channels OPERABLE requirement:, operatica in the applicable MODES may continue l

provided the fellowing conditions are satisfied:

a.

Verify that one of the inoperable channels has been bypassed and place the other inoperable channel in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and b.

All functional units affected by the bypassed / tripped channel shall also be placed in the bypassed / tripped condition as listed below:

Process Measurement Circuit runctional Unit Bypassed / Tripped 1.

Linear Power Linear Power Level - High (Subchannel or Linear)

Local Power Density - High DNBR - Low Log Power Level - High**

2.

Pressurizer Pressure - NR Pressurizer Pressure - High Local Power Density -High DNBR - Low 3.

Containment Pressure - NR Containment Pressure - High (RPS)

Containment Pressure - High (ESTAS)

Containment Pressure - High-High (ESEAS) 4.

Steam Genera *.or 1 Pre ssure Steam Generator 1 Pressure - Low Steam Generator 1 AP (EEAS 1)

Steam Generator 2 AP (EFAS 2) 5.

Steam Generator 2 Pressure Steam Generator 2 Pressure - Low Steam Generator 1 AP (EEAS 1)

Steam Generator 2 AP (EFAS 2) 6.

Steam Generator 1 Level Steam Generator 1 Level - Low Steam Generator 1 Level - High Steam Generator 1 AP (EEAS 1) 7.

Steam Generator 2 Level Steam Generator 2 Level - Low l

Steam Generator 2 Level - High Steam Generator 2 AP (EEAS 2) 8.

Core Protection Calculator Local Power Density - High DNBR - Low operation in the applicable MODES may continue until the performance of the next required CHANNEL EVNCTIONAL TEST.

Subsequent operation in the applicable MOD 2S may continue if one channel is restored to OPERABLE status and. the previsions of ACTION 2 are satisfied.

- Only for failure or activities common to both linear power and log power.

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ARKANSAS - UNIT 2 3/4 3-Sa Amendment No. +w,195 l

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TABLE 3.S-3 (Continusd)

TABLE NOTATION (a)

Trip function may be bypassed in this MODE when pressurizer pressure is below 400 psia; bypass shall be automatically removed when pressurizer pressure is 2 500 psia.

(b)

An SIAS signal is first necessary to enable CSAS logic.

(c)

Remote manual not provided for RAS.

These are local manuals at each EST auxiliary relay cabinet.

ACTION STATEMENTS ACTION 9

-With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to l

OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 10 - With the number of channels OPERABLE one less than the Total Number of Channels, operation in the applicable MODES may continue l

provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

If the inoperable channel is bypassed for greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , the desirability of maintaining this channel in the bypassed condition shall be reviewed at the next regularly scheduled PSC meeting in accordance with the QA Manual Operations.

The channel shall be returned to OPERABLE status prior to startup following the next COLD SHUTDOWN.

If an inoperable Steam Generator AP or RWT Level - Low channel is placed in the tripped condition, remove the inoperable channel from the tripped condition within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With a channel process reasurement circuit that affects multiple functional units inoperable or in test, bypass or trip all associated functional units as listed below.

Process Measurement Circuit Punctional Unit Bypassed

1. Containment Pressure - NR Containment Pressure - High (RPS)

Containment Pressure - High (ESFAS)

Containment Pressure - High-High (ESEAS)

2. Steam Generator 1 Pressure Steam Generator 1 Pressure - Low Steam Generator 1 AP (EFAS 1)

Steam Generator 2 AR (EFAS 2)

3. Steam Generator 2 Pressure Steam Generator 2 Pressure - Low Steam Generator 1 AP (EFAS 1)

Steam Generator 2 AP (EEAS 2)

4. Steam Generator 1 Level Steam Generator 1 Level - Low Steam Generator 1 Level - High Steam Generator 1 AP (EEAS 1)

5. Steam Generator 2 Level Steam Generator 2 Level - Low Steam Generator 2 Level - High Steam Generator 2 AP (EEAS 2)

ARKANSAS - UNIT 2 3/4 3-14 Amendment No.M4,M9,M4,

195,

n TABLE 3.3-3 (Continuid) e.

TABLE NOTATION ACTION 11 - With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement, operation in the applicable MODES l

may continue provided the following conditions are satisfied Verify that one of the inoperable channels has been bypassed a.

and place the other inoperable channel in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and b.

All functional units affected by the bypassed / tripped channel shall also be placed in the bypassed / tripped condition as listed below:

Process Measurement Circuit runctional Unit Bypassed / Tripped

1. Containment Pressure - NR Containment Pressure - High (RPS)

Containment Pressure - High (ESEAS)

Containment Pressure - High-High (ES EAS)

2. Steam Generator 1 Pressure Steam Generator 1 Pressure - Low Steam Generator 1 AP (EFAS 1)

Steam Generator 2 AP (EEAS 2)

3. Steam Generator 2 Pressure Steam Generator 2 Pressure - Low Steam Generator 1 AP (EEAS 1)

Steam Generator 2 AP (EEAS 2)

4. Steam Generator 1 Level Steam Generator 1 Level - Low Steam Generator 1 Level - High Steam Generator 1 AP (EFAS 1)

5. Steam Generator 2 Level Steam Generator 2 Level - Low Steam Generator 2 Level - High Steam Generator 2 AP (EEAS 2)

If an inoperable Steam Generator AP or RWT Level - Low channel is placed in the tripped condition, remove the inoperable channel from the tripped condition within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SNUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Operation in the applicable MODES may continue until the performance of the next required CHANNEL FUNCTIONAL TEST. Subsequent operation in the applicable MODES may continue if one channel is restored to OPERABLE status and the provisions of ACTION 10 are satisfied.

ACTION 12 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE, restore the inoperable channel to OPERABLE status within 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SNUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 13 - With the number of OPERABLE channels one less than the Total Number of Channels,

store the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least NOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SNUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for surveillance testing provided the other channel is OPERABLE.

ARKANSAS - UNIT 2 3/4 3-15 Amendment No. M9,195

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3/4.3 INSTRUMENTATION e

BASES l

3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEEAED SAFETY FEATURES (F Q l

INSTRUMENTATION The OPERABILITY of the protective and Ear instrumentation systems and bypasses ensure that 1) the associated ESF ection and/or reactor trip will be initiated when the parameter annitored by each channel or combination thereof reaches its setpoint, 2) the specified coincidence logic is maintained, 3) sufficient redundancy is maintained to permit a channel to be out _ of service for testing or maintenance, and 4) sufficient system functional capability is available for protective and Esr purposes from diverse parameters.

The OPERASILITY of these systems is required to provide the overall reliability, 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 maintamd comparable to the original design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability. The triannual channel functional testing frequency is to be performed on a STAGGERED TEST RASIS.

j The measurement of response time at the specified frequencies provides s

assurance that the protective and Esr action function associated with each j

channel is completed within the time limit assumed in the accident analyses.

j The RPS and ESFAS response time tables have been relocated to the Safety s

Analysis Report (SAR). No credit was taken in the analyses for those channels

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with response times indicated as not applicable.

I Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests j

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.

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ARERNSAS - UNIT 2 3 3/4 3-1 Amendment No. 44,*e,444,189

3/4.3 INSTRUMENTATION BASES Plant Protective System (PPS) legic is designed for operation as a 2-out-of-3 logic, although normally it is operated in a 2-out-of-4 mode.

The RPS Logic censists of everything downstream of the bistable relays and upstream of the Reactor Trip Circuit Breakers. The RPS Logic is divided into two parts, Matrix Logic, and Initiation Logic.

Failures of individual bistables and their relays are considered measurement channel failures.

The ESEAS Logic consists of everything downstream of the bistable relays and upstream of the subgroup relays. The ESEAS Logic is divided into three parts, Hatrix Logic, Initiation Logic, and Actuation Logic. Failures of individual bistables and their relays are considered measurement channel failures.

Matrix Logic refers to the matrix power supplies, trip channel bypass contacts, and interconnecting matrix wiring between bistable relay cards, up to, but not including the matrix relays. Matrix contacts on the bistable relay cards are excluded from the Matrix Logic definition since they are addressed as part of the measurement channel.

Initiation Logic consists of the trip path power source, matrix relays and their associated contacts, all interconnecting wiring, and the initiation relays (including contacts).

ESEAS Actuation Logic consists of all circuitry housed within the Auxiliary Relay Cabinets (ARCS) used to house the EST runctions excluding the subgroup relays, and interconnecting wiring to the initiation relay contacts mounted in the PPS cabinet.

For the purposes of this LCO, de-energization of up to three matrix power supplies due to a single failure, such as loss of a vital iristrument bus, is to be treated as a single matrix channel failure, providing the affected matrix relays de-energize as designed to produce a half-trip. Although each of the six matrices within an ESFAS Punction (e.g., SIAS, MSIS, CSAS, etc.) uses separate power supplies, the matrices for the different ESEAS Punctions share power supplies. Thus, failure of a matrix power supply may force entry into the Condition specified for each of the associated ESFAS Functional Units.

Table 3.3-3 Action 10 allows for continued operation in the applicable MODES with the number of channels OPERABLE one less than the Total Number of Channels provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

If an inoperable Steam Generator AP or Refueling Water Tank (RWT) Level - Low channel is placed in the tripped condition, it must be removed from the tripped condition within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or the plant must be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SNUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . This condition is limited to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months because of the single failure vulnerability that exists with one of the Steam Generator AP or RWT Level - Low channels in the trip condition.

ARKANSAS - UNIT 2 B 3/4 3-la Amendment No. M9,195

O 3/4.3 INSTRUMENTATTON BASES operation with a channel of Steam Generctor AP (EEAS 1 or EEAS 2) in the tripped condition renders EEAS susceptible to single failure scenarios.

With Channel of Steam Generator AP in trip, certain single failures concurrent d

with a MSIS actuation can result in initiation of Erw to a faulted steam Generator.

Other single failures can result in failure of automatic control of Steam Generator level and could allow Steam Generator overfill. Placing a channel of Steam Generator AP in the tripped condition is acceptable fer up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months because operating experience has demonstrated the low probability

}

of the above single failure scenarios to occur.

l Operation with a channel of RWT Level - Low in the tripped condition renders the RAS susceptible to a single failure scenario. With a channel of RWT Level

- Low in trip, concurrent with the injection phase of a valid SIAS actuation, and a single failure of another RWT Level - Low channel would result in a RAS Actuation.

These sequence of events would cause the ECCS suction to be shifted f rom the RWT to t he containment sump prematurely.

Placing a channel of RWT Level - Low in th cripped condition is acceptable for up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months because operating experience has demonstrated the low probability of the above single failure scenario to occur.

l Table 3.3-3 Action 11 allows for continued operation in the applicable MODES 3

with the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement, provided the following conditions are satisfied; one of the inoperable channels has been bypassed and the other inoperable channel has been placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and all functional units 4

affected by the bypassed / tripped channel shall also be placed in the bypassed / tripped condition. An inoperable channel may be placed in the trip condition to allow another channel to be bypassed for testing or repair purposes.

If an inoperable Steam Generator AP or RWT Level - Low channel is placed in the tripped condition, it must be removed from the tripped condition within 49 l

hours or the plant must be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . This condition is limited to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months because of the single failure vulnerability that exists with one of the Steam Generator AP or RWT Level - Low channels in the trip condition.

ARXANSAS - UNIT 2 5 3/4 1-lb Amendment No.195

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