Text

Amend 186 to License NPF-6,revising Channel Functional Testing Frequency for Most of RPS & ESFAS Instrumentation from Monthly to Every 4 Months.Amend Also Allows Use of Cisam Elements to Be Used in CPC
	ML20141H536
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/21/1997
From:	Kalman G; Office of Nuclear Reactor Regulation
To:	;
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ML20141H542	List: ML20141H536; ML20141H543;
References
	NPF-06-A-186 NUDOCS 9705270008
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UNITED STATES

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. soseMoot i

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DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE

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I Amendment No.186 License No. NPF-6 i

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

A.

The application for amendment by Entergy Operations, Inc. (the licensee) dated October 7, 1996, as supplemented February 10, and May 8, 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 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 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 i

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.

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9705270000 970521 PDR ADOCK 05000368 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,

.J Paragraph 2.C.(2) of Facility Operating License No. NPF-6 is hereby a.<nded to read as follows:

i 2.

Technical Soecifications

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The Technical Specifications contained in Appendix A, as revised through Amendment No.186, 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.

FOR THE NUCLEAR REGULATORY COMMISSION M

George Kalm ior Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Ai.Lachment: Changes to the Technical Specifications Date of Issuance:

May 21, 1997

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I ATTACHMENT TO LICENSE AMENDMENT NO. 186 L

FACILITY OPERATING LICENSE N0. NPF-6 DOCKET NO. 50-368 Revise 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. The corresponding overleaf pages are also provided to maintain document completeness.

I REMOVE PAGES INSERT PAGES 1-9 l-9 3/4 3-5 3/4 3-5 3/4 3-7 3/4 3-7 3/4 3-8 3/4 3-8 3/4 3-9 3/4 3-9 3/4 3-12 3/4 3-12 3/4 3-13 3/4 3-13 3/4 3-14 3/4 3-14 3/4 3-21 3/4 3-21 3/4 3-22 3/4 3-22 3/4 3-23 3/4 3-23 B 3/4 3-1 B 3/4 3-1 9

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TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY i

S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l w

At least once per 7 days.

M At least once per 31 days.

O At least once per 92 days.

TA At least once per 123 days.

l SA At least once per 184 days.

R At least once per 18 months.

S/U Prior to each reactor.startup.

P Completed prior to each release.

N.A.

Not applicable.

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ARKANSAS UNIT 2 1-9 Amendment No. 40,186

4 TABLE 3.3-1 (Continued) i ACTION STATENENTS j

ACTION 2 - WJtu the number of channels OPERABLE one less than the Total Number of Satanels, STARTUP and/or POWER OPERATION may continue 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 neeting in accordance with the QA Manual Operations. The channel shall be l

returned to OPERABLE status prior to startup following the next COLD i

SNUTDOWN.

With a channel process measurement circuit that affects multiple functional units inoperable or in test, bypass or trip all associated i

functional units as listed below.

Process Measurenent Circuit runctional Unit Bypassed j

1.

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

Local Power Density - High I

DNBR - Low i

Log Power Level - High*

4 2.

Pressurizer Pressure - NR Pressurizer Pressure - high Local Power Density -High DNBR - Low i

j 3.

Containment Pressure - NR Containment Pressure - High (RPS) d Containment Pressure - High (ESEAS)

Containment Prissure - High-High (ESEAS) 4.

Steam Generator 1 Pressure Steam Generator 1 Pressure - Low Steam Generator 1 AP (EEAS 1) 4.

Steam Generator 2 AP (EEAS 2) 5.

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

Steam Generator 2 AP (EFAS 2) 4 6.

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

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

Core Protection Calculator Local Power Density - High

, DNBR - Low

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

ARKANSAS - UNIT 2 3/4 3-5 Amendment No. W), M 9,186

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AET10N ETATFMFNTS ACTION'3 - With the number of channels OPERABLE one less than the Minimum Chann

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OPERABLE requirement. STARTUF and/or POWER OPERATION may continue provided the following 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 I hour, and b.

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

fragent Neaturement rircuit Functinnal Unit Rvensted/Trinned 1.

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

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 (ESFAS)

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Containment Pressure High High (ESFAS) 4.

Steam Generator 1 Pressure Steam Generator 1 Pressure - Low Steam Generator 1 AP (EF,AS 1)

Steam Generator 2 AP (EFAS 2)

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

Steam Generator 2 AP (EFAS 2) 6.

Steam Generator 1 Level Steam Generator 1 Level - Low l

Steam Generator 1 Level High Steam Generator 1 AP (EFAS 1) 7.

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

Core Protection Calculator Local Power Density - High DNBR - Low STARTUP and/or POWER OPERATION may continue until the performance of the next required CHANNEL FUNCTIONAL TEST.

Subsequent STARTUP and/or POWER OPERATION may continue'1f one channel is restored to OPERABLE status and the provisions of ACTION 2 are satisfied.

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

' ARKANSAS - UNIT 2 3/I 3 Sa Amendment No.159 f

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REACTOR PROTECTION INSTRUMENTATION SURVEILIANCE REQUIREMENTS 3

CHANNEL MODES IN WHICH

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CHANNEL CHANNEL FUNCTIONAL SURVEILIANCE FUNCTIONAL UNIT CNECK CALIBRATION TESTS REQUIRED 1.

Manual Reactor Trip W.A.

N.A.

S/U(1)

N.A.

i 2.

Linear Power Level - Eigh 3

D (2,4 ),

TA(10) 1, 2 l

M(3,4),

Q(4) l 4

i 3.

Logarithmic Power Level - High 3

R(4)

TA(10),

1,2,3,4,5 S/U(1) and

1 t

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?ressuriser Pressure - High 3

R TA(10) 1, 2 l

5.

Pressuriser Pressure - Low 3

R TA(10) 1, 2

,3*,4*,5*

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6.

Containment Pressure - High 3

R TA(10) 1, 2 l

7.

Steam Generator Pressure - Low 3

R TA(10) 1, 2,3*,4*,5*

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8.

Steam Generator Level - Low s

R TA(10) 1, 2 l

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Local Power Density - High 8

D (2,4 ),

TA (10),

1, 2 i

R(4,5)

R(6) 10.

DNBR - Low 3

S(7),

TA(10),

1, 2 1

D(2,4),

R(6)

M(8),

R(4,5) 11.

Steam Generator Level - High 3

R TA(10) 1, 2 l'

12.. Reactor Protection system Logic N.A.

N.A.

TA(10)'

1, 2,3*,4*,5*

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13.

Reactor Trip Breakers N.A.

N.A.

M 1, 2,3*,4*,5*

I 14.

Core Protection calculators S

D(2,4)

TA(9,10),

1, 2 R(4,5)

R(6)

I 15.

CEA Calculators s

R TA(10),

1, 2 R(6)

ARKANSAS - UNIT 2 3/4 3-7 Amendment No. 44,49,M,M9,186

.. - - - - ~ ~ -

TABLE 4.3-1 (Crntinutd)

TABLE NOTATIONS-l With reactor trip breakers in the closed position and the CEA drivo system capable of CEA withdrawal.

(1)

If not performed in previous 7 days.

(2)

Heat balance only (CHANNEL PUNCTIONAL TEST not included) a.

Between 15% and 80% of RATED THERMAL POWER, compare the Linear Power Level, the CPC AT power, and the CPC nuclear power signals to the calorimetric calculation.

If any signal is within -0.5% to +10% of the calorimetric calculation, then do not calibrate except as required during l

initial power ascension following refueling.

If any signal is less than the calorimetric calculation by more j

than 0.5%, then adjust the affected signal (s) to within 0.0% to j

+10.0% of the calorimetric calculation.

If any signal is greater than the calorimetric calculation by i

more than 10%, then adjust the affected signal (s) tc eithin 8%

+

to 10% of the calorimetric calculation.

b.

At or above 80% of RATED THERMAL POWER, compare the Linear Power Level, the CPC AT power, and CPC nuclear power signals to the calorimetric calculation. If any signal differs from the calorimetric calculation by an absolute difference of > 2%,

I then adjust the affected signal (s) to within i 2% of the calorimetric calculation, f

During PHYSICS TESTS, these daily calibrations may be suspended provided these calibrations are performed upon reaching each major test power plateau and prior to proceeding to the rext major test power plateau.

(3)

Above 15% of RATED THERMAL POWER, verify that the linear power subchannel gains of the excore detectors are consistent with the values used to establish the shape annealing matrix elements in the Core Protection Calculators.

(4)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5)

After each fuel loading and prior to exceeding 70% of RATED THERMAL POWER, the incore detectors shall be used to determine or verify the shape annealing matrix elements used ia the CPCs.

l (6)

This CHANNEL FUNCTIONAL TEST shall include the injection of sLmulated process signals into the channel as close to the sensors as practicable to verify OPERABILITY including alarm and/or trip functions.

ARKANSAS - UNIT 2 3/4 3-8 Amendment No. M,M,M,M3,186

so (7)

Ab:ve 704 ef RATED THERMAL PolfER, verify thtt thD totc1 RCS ficw rato co indicated by esch CPC is Icss then cr equni to the octuni j

RCs total flow rate determined by either using the reactor coolant pump differential pressure instrumentation (conservatively compensate for measurement uncertainties) or by i.

calorimetric calculations (conservatively compensated for measurement uncertainties) and if necessary, adjust the CPC addressable constant flow coefficients such that each CPC i

indicated 12ew is less than or equal to the actual flow rate.

The flow measurement uncertainty may be included in the BERR1 term in the CPC and is equal to or greater than 44.

(8)-

Above 70% of RATED THEIORL Potter, verify that the total RCS flow i

rate as indicated by each CPC is less than or equal to the actual RCs total flow rate determined by calorimetric calculations (conservatively compensated for measurement uncertainties).

(9)

The CPC CHANNEL FUNCTIONAL TEST shall include the verification that i

the correct values of addressable constants are installed in each j

OPERABLE CPC.

j (10)' -

On a STAGGERED TEST BASIS.

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ARKANSAS - UNIT 2 3/4 3-9 Amendment No. 44,48,M,443,186

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<1 INSTRUMENTATION l

3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION 1

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LIMITING CONDITION FOR OPERATION i

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3.3.2.1 TheEngineeredSafetyFeatureActuationSystem(ESFAS)instru-mentation channels and bypasses shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the i

i Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown l

in Table 3.3-5.

APPLICABILITY: As shown in Table 3.3-3.

1 ACTION:

i a.

With an ESFAS instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip set-point adjusted consistent with the Trip Setpoint value.

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b.

With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

SURVEILLANCE REQUIREMENTS 4.3.2.1.1 Each ESFAS instraentation channel shall be demonstrated OPERABLE by the perfomance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES fed at the frequencies shown in Table 4.3-2.

4.3.2.1.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass operation. The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by bypass operation.

4.3.2.1.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 sonths. Each test shall include at least one channel per funetton such that all channels are tested at least once every N times 18 months where N is the total num6er of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 3.3-3.

1 ARKANSAS-UNIT 2 3/4 3-10

~1 TABLE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION MINIMUM TOTAL No.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT

_OF CHANNELS TO TRIP OPERABLE MODES ACTION 5.

CONTAINMENT COOLING (CCAS) a.

Manual (Trip Buttons) 2 sets of 2 1 set of 2 2 sets of 2 1,

2,-3, 4

9 b.

Contairunent Pressure -

High 4

2 3

1, 2, 3 10,11 c.

Pressurizer Pressure -

Low 4

2 3

1, 2, 3 (a) 10,11 d.

ESFAS Logic 1.

Matrix Logic 6

1 3

1,2,3 12 2.

Initiation Logic 4

2 4

1, 2, 3, 4 9

e.

Automatic Actuation Logic 2

1 2

1, 2, 3, 4 13 6.

RECIRCULATION (RAS) a.

Manus.1 (TRIP Buttons)(c) 2 sets of 2 2 sets of 2 2 sets of 2 1,2,3,4 9

b.

Refueling Water Tank - Low 4

2 3

1, 2, 3 10,11 c.

ESFAS Logic 1.

Matrix Logic 6

1 3

1, 2, 3 12 2.

Initiation Logic 4

2 4

1, 2, 3, 4

9 d.

Automatic Actuation Logic 2

1 2

1, 2, 3, 4

13 ARKANSAS - UNIT 2 3/4 3-12 Amendment No. 444,449,186

._.--m 5

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_ABLE 3.3-3 (Continued)

T ENGINEERED SAFETY FEATURE ACTUATION SYSTDI INSTRUMENTATION MINIMUM TOTAL NO.

CHADIELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 7.

1455 OF POWER a.

4.16 kv Estergency Bus Undervoltage (Loss of Voltage) 2/ Bus 1/ Bus 2/ Bus 1, 2, 3 9

b.

460 volt Bnergency Bus Undervoltage (Degraded Voltage) 1/ Bus 1/ Bus 1/ Bus 1,2,3 9

8.

EMERGENCY FEEDWATER (EFAS) a.

Manual (Trip Switches) 2 sets of 2 2 sets of 2 2 sets of 2 1,2,3,4 9

per S/G per S/G per S/G 3

b.

SG Level and Pressure (A/B)

Low and AP (A/B) - High 4/SG 2/SG 3/SG 1,2,3,4 10,11 c.

SS Level (A/B) - Low and No S/G Pressure -

Low Trip (A/B).

4/SG 2/SG 3/SG 1,2,3,4 10,11 l

d.

ESFAS Logic 1.

Matrix Logic 6

1 3

1,2,3,4 12

[

2.

Initiation Logic 4

2 4

1,2,3,4 9

e.

Automatic Actuation Logic 2

1 2

1,2,3,4 13 i

ARMANSAS - UNIT 2 3/4 3-1')

Amiendment No. 444,M9,186 i

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TABLE NOTATION; (a)

Trip function may be bypassed in this MODE when pressuriser pressure is below 400 psias bypass shall be automatically removed when pressuriser pressure is at 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 ESF 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 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 STAND 8Y within the next 6 houra and in COLD SNUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 10 -With the atumber of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue 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 l

OPERABLE status prior to startup following the next COLD SHUTDOWN.

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

Process Measurement circuit Functional Unit Bypassed j

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

Containment Pressure - High (ESTAS)

Containment Pressure - Eigh-High (ESFAS)

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

Steam Generator 2 AP (ETAS 2)

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

Steam Generator 2 AP (ETAS 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 (EFAS 2)

ARKANSAS - UNIT 2 3/4 3-14 Amendment No. W, W,186

s TABLE 4.3-2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIrtEMENTS l

CHANNEL MOPES IN WHICH CHANNEL CHANNEL FUNCTIONAL F RVEILIANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED l

1.

SAFETY INJECTION (SIAS) s.

Manual (Trip Buttons)

N.A.

R N.A.

b.

Containment Pressure - High S

R TA(2) 1, 2, 3 c.

Pressurizer Pressure - Low S

R TA(2) 1, 2, 3 d.

Automatic Actuation Logic M.A.

N,.A.

TA(1,2) 1, 2, 3 2.

CONTAINNENT SPRAY (CSAS) f a.

Manual (Trip Buttons)

N.A.

R N.A.

b.

Containment Pressure -

High - High S

R TA(2) 1, 2, 3 c.

Automatic Actuation Logic N.A.

N.A.

TA(1,2) 1,2,3 3.

CONTAINMENT ISOIATION (CIAS) a.

Manual (Trip Buttons)

N.A.

R N.A.

b.

Containment Preseure - High S

R TA(2) 1, 2, 3 c.

Automatic Actuation Logic N.A.

N.A.

TA(1,2) 1, 2, 3 7

t 4.

MAIN STEAM AND FEEDWATER ISOLATION (MSIS) a.

Manual (Trip Buttons)

N.A.

R N.A.

b.

Steam Generator Pressure - Low S

R TA(2) 1, 2, 2 c.

Automatic Actuation Logic N.A.

N.A.

TA(1,2) 1,2,3 j

i i

[

ARKANSAS - UNIT 2

.,4 3-21

. Amendment No.186 j

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIRDfENTS CHANNEL MODES IN WNICN CHANNEL CHANNEL ETNCTIONAL SUP.VEILLANCE FUNCTIONAL UNIT CNECK CALIBRATION TEST REQUIRED 5.

CONTAINMENT COOLING (CCAS) a.

Manual (Trip Buttons)

N.A.

R N.A.

b.

Contairunent Pressure - High 5

R TA(2) 1, 2,. 3 c.

Pressurizer Pressure - Low 5

R TA(2) 1,2,3 d.

Automatic Actuation Logic N.A.

N.A.

TA(1,2) 1,2,3 6.

RECIRCULATION'(RAS)

Manual (Trip Buttons) (a)

N.A.

R N.A.

l a.

b.

Refueling Water Tank - Low S

R TA(2) 1,2,3 c.

Automatic Actuation Logic N.A.

N.A.

TA(1,2) 1,2,3 7.

LOSS OF PONER

-I a.

4.16 kv Dnergency Bus Undervoltage (Loss of Voltage)

S R

R 1,2,3 b.

460 volt Bnergency Bus Undervoltage (Degraded voltage)

S R

R 1,2,3 8.

EMERGENCY FEEDNATER (EFAS) a.

Manual (Trip Switches)

N.A.

R N.A.

l b.

SG Level and Pressure (A/B)-low and AP (A/B) - High S

R TA(2) 1,2,3 lil c.

SG Level (A/B) - Low and No Pressure - Low Trip (A/B)

S R

TA(2) 1, 2, 3 d.

Automatic Actuation Logic N.A.

N.A.

TA(1,2) 1,2,3 ARKANSAS - UNIT 2 3/4 3-22 Amendment No.186 I

Tablo 4.3-2 (continu-d)

TABLE NOTATION (a)

Remote manual not provided for RAS. These are local manuals at each ESF auxiliary relay cabinet.

(1) The logic circuits shall be tested manually at least once per 123 l

days.

(2) On a STAGGERED TEST BASIS.

l I

ARFANSAS - UNIT !!

3/4 3-23 Amenndment No. jg6

INiuUrH.NTATION s

3/4.3.3 MONIToffMC TWITRtMENTATION RADI ATION MONTIORTWO INETttMENTATTON I.TMTTfMS CONDTTf0N FOR DPtWATf0N 3.3.3.1 The radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alara/ trip setpoints within the epecified limits.

APPLICABILITYt As shown in Table 3.5-6.

ACTION:

'With a radiation monitoring channel alare/ trip setpoint a.

exceeding the value shown in Table 3.5-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.

b.

With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-5.

The provisions of Specification 3.0.3 are not applicable.

l c.

XURVEf f1ANET REQUTRTMTNTE I'

4.3.3.1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the modes and at

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the frequencies shown in Table 4.3-3.

4 1

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I AltKANSAS - UNIT 2 3/4 3-24 Amendment No. 134 NAY 5 1992

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

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 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 ESF purposes from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundancy and diversity assumed available in the facility design for the protection and mMption of accident and transient conditions. The integrated opup11oa of each of these systems is consistent with the assumptions used in the m.ident analyses.

The surveillance requirements specified for these systen's ensure that i

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 triannual channel functional testing frequency is to be performed on a STAGGERED TEST BASIS.

The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is coupleted within the tima 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 f

time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizing replacement sensors with certified response, times.

RTD response time is defined as the time interval required for the RTD output to achieve 63.2% of its total change when subjected to a step change in RTD temperature. The RTD response time for the Core Protection Calculator l'

System (CPCS) is expressed as an effective time constant.

For hot leg temperatures, the effective time constant for a given CPC channel is defined as the mean time constant fo'r averaged pairs of hot leg RTD inputs to the L

channel. This is done because the CPCS utilizes the mean hot leg temperature in its calculations. The maximum hot leg effective time constant allowable for use in the CPCs is 13.0 seconds. For cold leg temperatures, the effective time constant to be used in Figure 3.3-1 is the maximum time constant of the two cold leg RTD inputs for a given channel. The CPCs utilizes the more conservative cold leg temperature in the various DNBR and LPD calculations.

The maximum cold leg effective time constant allowable for use in the CPCS is 13.0 seconds.

ARKANSAS - UNIT 2 B 3/4 3-1 Amendment No, M,M,186

3/a.3 INSTRUMENTATION BASES Plant Protective System (PPS) logic 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 consists of everything downstream of the bistable relays and upstream of the Reactor Trip Circuit Breakers. The RPS

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.Logie is divided into two parts Matrix Logic, and Initiation Logic.

Failures of individual histables and their relays aregnsidered measurement channel failures.

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The ESFAS Logic consists of everything downstream of the bistable i

relays and opstream of the subgroup relays. The ESFAS Logic is i

divided into three parts. Matrix Logic. Initiation Logic.'and Actuation Logic. Failures of ir.dividual bistables and their relays I

are considered measurement channel failures.

Matrix Logic refe,rs to the matrix power supplies trip channel bypass contacts, and interconnecting astrix wiring between-bistable relay l

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 s

channel.

l Initiation Logic consists of the trip path power source, matrix relays and their associated contacts, all interconnecting wiring, and i

the initiation relays (including contacts).

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ESFAS Actuation Logic consists of all circuitry housed within the '

i Auxiliary Relay Cabinets (ARCS) used to house the ESF Function;

-excluding the subgroup relays, and interconnecting wiring to the 1

initiation relay contacts mounted in the PPS cabinet.

i For the purposes of this LC0. de energization of up to three matrix l

power supplies due to a single failure. such as loss of a vital instrument bus. is to be treated as a single matrix channel failure.

i providing the affected matrix relays de energize as designed to

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produce a half-trip. Although each of the six matrices within en ESFAS Function (e.g.. SIAS. MSIS, CSAS. etc.) uses separate power i

supplies, the matrices for the different ESFAS Functions share power supplies. Thus, failure of a matrix power supply may force entry into the Condition specified for each of the associated ESFAS t

Functional Units.

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ARKANSAS - UNIT 2 83/43ja An'endment No.159 WP &

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