ML20117K203

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Proposed Tech Specs Re Changes Extending Surveillance Test Interval for Reactor Trip Breakers,Reactor Trip Modules & Electronic Trip Relays
ML20117K203
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 04/07/1996
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20117K198 List:
References
NUDOCS 9606100106
Download: ML20117K203 (11)
v • d • e


Text

.

Other channels are subject'only to " drift" errors induced within the instrumentation itself and, consequently, can tolerate longer intervals between calibrations.

Process system instrumentation errors induced by drift can be expected to remain within acceptable tolerances if i

recalibration is performed'once every 18 months.

j Substantial calibration shifts within a channel (essentially a ch'annel failure) will be revealed _during routine checking and testing procedures.

Thus, minimum calibration frequencies for the nuclear flux (power range) channels, and once every 18 months for the process system channels is considered acceptable.

Testing on-line testing of reactor protective channel and EPIC channels is required once every 4 weeks on a rotational or staggered basis. The rotation scheme is designed to reduce the probability of an undetected failure existing within the system and to minimize the likelihood of the.

same systematic test errors being introduced into each redundant channel.

l The rotation schedule for the reactor protective channels is as follows:

i Channels A, B,

C, D

Before Startup if the individual l

channel rotational frequency has been discontinued or if outage activities

-i could potentially have affected the operability of one or more channel j

f Channel A One Week After_Startup Channel B Two weeks After Startup l'

Channel C Three Weeks After Startup Channel D Four Weeks After Startup i

The reactor protective system instrumentation and EFIC test cycle is continued with one channel's instrumentation tested each week.

Upon detection of a failure that prevents trip action, all instrumentation i

associated with the protective channels will be tested after which the rotational test cycle is started again.

If actuation of a safety channel j

occurs, assurance will be required that actuation was within the limiting

'1 safety system setting.

The protective channels coincidence logic and control rod drive trip

. breakers are trip tested every six months. The trip test checks all logic l

~

l combinations and is to be performed on a rotational basis.

The logic and breakers of the four protective cLannels shall be trip tested prior to startup and their individual channels trip tested on a cyclic basis.

Discovery of a failute requires the testing of all channel logic and breakers, after which the trip test cycle is started again.

t

}

9606100106 960531 PDR ADOCK 05000313-P PDR Amendment'No. 26,91 68 Revised by NRC Letter Dated 4/12/01

'u Table 4.1-1 Instrument Surveillance Requirements Channel Description Check Test Calibrate Remarks.

1.

Protective Channel NA SA NA l

Coincidence Logic 4

2.

Control Rod Drive NA SA (1 ) -

NA (1)

To include independent testing l

Trip Breaker of the shunt and undervoltage trip attachments.

3.

Power Range Amplifier NA NA T/W(1)

(1)

Heat balance calibration twice weekly under steady state operating conditions, daily-under non-steady state opera-ting conditions.

4.

Power Range Channel S

M M(1) (2) -

(1)

Using core instrumentation.

M(1)

(2)

Axial offset upper and lower chambers monthly and after each startup if not done previous week.

5.

Intermediate Range Channel S

P/M.

NA 6.

Source Range Channel S (l) -

P NA (1)

When in service.

7.

Reactor Coolant Temperature S

M R

Channel 8.

High Reactor Coolant S

M R.

Pressure Channel

. 9.

Low Reactor Coolant S

M R

Pressure Channel j

10. Flux-Reactor Coolant Flow S

M R

Comparator 1

11. Reactor Coolant Pressure 3

M R

l Temperature Comparator i

l

12. Pump Flux Comparator S

M R

)

Amendment No. M,4-W 69

.c.

m.

m m m m

..m-.,. -., _ _ _ _ - -

m w.

.%s--

m---

.m w

-+,

..---i.,

Table 4.1-1 (Cont.)

Channel Description Check Test Calibrate Remarks d.

SG A High Range Level S

M R

High-high e.

SG B High Range Level S

M R

High-high

57. Containment High Range D

M R

Radiation Monitors

58. Containment Pressure-High M

NA R

59. Containment Water Level-Wide M

NA R

Range

60. Low Temperature Overpressure NA R

R Protection Alarm Logic

61. Core-exit Thermocouples M

NA R

62 Electronic (SCR) Trip Relays NA SA NA l

63 RVLMS M

NA R

64 HLLMS M

NA R

NOTE:

S - Each Shift T/W - Twice per Week R - Once every 18 months W - Weekly Q-Quarterly PC - Prior to going Critical if not M - Monthly P-Prior to each done within previous 31 days D - Daily startup if not done NA - Not Applicable previous week SA - SA Twice per Year B/M - Every 2 months Amendment No. M, 94, M, -146,44-7,-146,4-!M-72d

S e

l MARKUP OF CURRENT ANO-1 TECHNICAL SPECIFICATIONS 1

(FOR INFO ONLY) 1

\\

l l

I l

l i

i i

... _ _ _ _ __.._.-. _ _.~.

6 Other channels are subject only to " drift" errors induced within the instrumentation itself and, consequently, can tolerate longer intervals between calibrations.

Process system instrumentation errors induced by drift can be expected to remain within acceptable tolerances if recalibration is performed once every 18 months.

Substantial calibration shifts within a channel (essentially a channel failure) will be revealed during routine checking and testing procedures.

Thus, minimum calibration frequencies for the nuclear flux (power range) channels, and once every 18 months for the process system channels is considered acceptable.

l Testir33 On-line testing of reactor protective channel and EFIC channels is required once every 4 weeks on a rotational or staggered basis. The rotation scheme is designed to reduce the probability of an undetected failure existing within the system and to minimize the likelihood of the same systematic test errors being introduced into each redundant channel.

The rotation schedule for the' reactor protective channels is as follows:

Channels A, B,

C, D

Before Startup if the individual i

channel rotational frequency has been discontinued or if outage activities could potentially have affected the operability of one or more channel l

. Channel A one Week After Startup l

L Channel B Two weeks After Startup Channel C Three Weeks After Startup

.i Channel D Four Weeks After Startup The reactor protective system instrumentation and EFIC test cycle is continued with one channel's instrumentation tested each week.

Upon detection of a failure that prevents trip action, all instrumentation associated with the protective channels will be tested after which the rotational test cycle is started again.

If actuation of a safety channel occurs, assurance will be required that actuation was within the limiting safety system setting.

The protective channels coincidence logic and control rod drive trip l

breakers are trip tested every fcur ucckssix months. The trip test checks all l

logic l

combinations and is to be performed en a rotational basis.

The logic and breakers of the four protective channels shall be trip tested prior to startup and their individual channels trip tested on a cyclic basis.

Discovery of a failure requires the testing of all channel logic and breakers, after which the trip test cycle is started again.

t s

i i

3 Amendment No. 46,91 68 Revised by NRC Letter Dated t/12/91 e

r-

Table 4.1-1 Instrument Surveillance Requirements Channel Description Check Test Calibrate Remarks 1.

Protective Channel NA Mg NA l

Coincidence Logic 2.

Control Rod Drive NA Mg (l)

NA (1)

To include independent testing l

Trip Breaker of the shunt and undervoltage trip attachments.

3.

Power Range Amplifier NA NA T/W (1)

(1)

Heat balance calibration twice weekly under steady state operating conditions, daily under non-steady state opera-ting conditions.

4.

Power Range Channel S

M M (1) (2)

(1)

Using core instrumentation.

M(1)

(2) Axial offset upper and lower chambers monthly and after each startup if not done previous week.

5.

Intermediate Range Channel S

P/M NA 6.

Source Range Channel S(l)

P NA (1)

When in service.

7.

Reactor Coolant Temperature S

M R

Channel 8.

High Reactor Coolant S

M R

Pressure Channel 9.

Low Reactor Coolant S

M R

Pressure Channel

10. Flux-Reactor Coolant Flow S

M R

Comparator

11. Reactor Coolant Pressure S

M R

Temperature Comparator

12. Pump Flux Coinparator S

M R

Amendment No. 60,-1-14 69

Table 4.1-1 (Cont.)

Channel Description Check Test Calibrate Remarks d.

SG A High Range Level S

M R

High-high e.

SG B High Range Level S

M R

High-high

57. Containment High Range D

M R

Radiation Monitors

58. Containment Pressure-High M

NA R

59. Containment Water Level-Wide M

NA R

Range

60. Low Temperature Overpressure NA R

R Protection Alarm Logic

61. Core-exit Thermocouples M

NA R

62 Electronic (SCR) Trip Relays NA Mg NA l

63 RVLMS M

NA R

64 HLLMS M

NA R

NOTE:

S - Each Shift T/W - Twice per Week R - Once every 18 months W - Weekly Q-Quarterly PC - Prior to going Critical if not M - Monthly P-Prior to each

.done within previous 31 days D - Daily startup if not done NA - Not Applicable previous week SA - SA Twice per Year B/M - Every 2 months Amendment No. N,94,96,-144,4-14,-146,444-72d

O s

PROPOSED GENERIC CHANGES TO NUREG 1430 1

)

i i

l

CRD Trip Devices 3.3.4 ACTIONS (continued)

CONDITION REQUIRED ACTION C0W'LETION TIME C.

One or more ETA relays C.1 Transfer affected I hour inoperable.

CONTROL R0D group to power supply with OPERABLE ETA relays.

OR C.2 Trip corresponding AC 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> CR0 trip breaker.

D Required Action and D.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met in AND MODE 1, 2, or 3.

D.2.1 Open all CRD trip 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> breakers 0_R D.2.2 Remove all power to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> the CRD System.

E.

Required Action and E.1 Open all CRD trip 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion breakers.

Time not met in MODE 4 or 5.

OR E.2 Remove all power to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> the CRD System.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform CHANNEL FUNCTIONAL TEST.

M11B.11 days l

i l

BWOG STS 3.3-11 Rev 1, 04/07/95

CRD Trip Devices B 3.3.4 BASES ACTIONS C.1 and C.2 (continued)

The I hour Completion Time is sufficient to perform the Required Action.

D.1, D.2.1, and 0.2.2 If the Required Actions of Condition A, B, or C are not met within the required Completion Time in MODE 1,--2, or 3, the unit must be brought to a MODE in which the LCO does not apply. To achieve this status, the unit must be brought to at least MODE 3, with all CRD trip breakers open or with all power to the CRD System removed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The allowed Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from full power conditions in an orderly manner and without challenging unit systems.

E.1 and E.2 If the Required Actions of Condition A, B, or C are not met within the required Completion Time in MODE 4 or 5, the unit must be brought to a MODE in which the LCO does not apply.

To achieve this status, all CRD trip breakers must be opened or all power to the CRD System removed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The allowed Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is reasonable, based on operating experience, to open all CRD trip breakers or remove all power to the CRD System without challenging unit systems.

SURVEILLANCE SR 3.3.4.1 REQUIREMENTS SR 3.3.4.1 is to perform a CHANNEL FUNCTIONAL TEST every mil &il days. This test verifies the OPERABILITY of the l

trip devices by actuation of the end devices. Also, this test independently verifies the undervoltage and shunt trip mechanisms of the AC breakers. The Frequency of4111&4} days l 1s based on operating experience, which has demonstrated that failure of more than one channel of a given function in any4111&il day interval is a rare event.

l REFERENCES 1.

FSAR, Chapter [7].

BWOG STS B 3.3-44 Rev 1, 04/07/95

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