ML021190177

From kanterella
Jump to navigation Jump to search
Part 2 of 2, Edwin I. Hatch Nuclear Plant, Revision to Request to Revise Technical Specifications: Quarterly Surveillance Extension, Enclosure 5
ML021190177
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 04/25/2002
From: Sumner H
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
-nr, GL-91-004, HL-6224
Download: ML021190177 (188)


Text

Lacý-osa-ze 5 -Pýcb Edwin I. Hatch Nuclear Plant Request to Revise Technical Specifications:

Quarterly Surveillance Extension Bases for Change Reauest for Reduced Intervals This proposed Technical Specifications change requests no reductions in Surveillance Requirement intervals.

HL-6224 E5-1 04/02

Edwin I. Hatch Nuclear Plant Request to Revise Technical Specifications:

Quarterly Surveillance Extension 10 CFR 50.92 Significant Hazards Evaluation and Environmental Assessment A.

10 CFR 50.92 Significant Hazards Evaluation The standards used to arrive at a determination that a request for amendment does not involve a significant hazards consideration are included in 10 CFR 50.92, which states that operation of the facility in accordance with the proposed amendment would not:

1.

Involve a significant increase in the probability or consequences of an accident previously evaluated; or

2.

Create the possibility of a new or different kind of accident from any accident previously evaluated; or

3.

Involve a significant reduction in a margin of safety.

Southern Nuclear Operating Company has reviewed the proposed amendment with respect to these three factors, and determined that the proposed change does not involve a significant hazard based upon the following:

1.

The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed Technical Specifications (TS) change involves an increase in the surveillance testing intervals for various Surveillance Requirements (SRs) from 92 days to 92 days on a STAGGERED TEST BASIS.. The proposed TS changes do not physically impact the plant, nor do they impact any design or functional requirements of the associated systems. That is, the proposed TS change does not degrade the performance of, or increase the challenges to, any safety systems assumed to function in the safety analysis. The proposed TS changes neither impact the TS SRs themselves nor the way in which the surveillances are performed. In addition, the proposed TS change does not introduce any accident initiators, since no accidents previously evaluated relate to the frequency of surveillance testing. Also, evaluation of the proposed TS change demonstrates that the availability of equipment and systems required to prevent or mitigate the radiological consequences of an accident are not significantly affected because of other, more frequent testing that is performed, the availability of redundant systems and equipment, or the high reliability of the equipment. Since the impact on the systems is minimal, it is concluded that the overall impact on the plant safety analysis is negligible.

A sensitivity analysis was performed to determine the effect of the increased surveillance intervals on the HNP Probabilistic Risk Assessment (PRA). This sensitivity analysis shows a negligible increase in core damage frequency (CDF) and HL-6224 04/02 E6-1 Request to Revise Technical Specifications:

Quarterly Surveillance Extension 10 CFR 50.92 Significant Hazards Evaluation and Environmental Assessment essentially no change in large early release frequency (LERF) due to the proposed change.

Furthermore, an historical review of surveillance test results and associated maintenance records indicates there is no evidence of any failure that would invalidate the above conclusions. Therefore, the proposed TS change does not significantly increase the probability or consequences of an accident previously evaluated.

2.

The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed TS change involves a change in the various SR intervals from 92 days to 92 days on a STAGGERED TEST BASIS. The proposed TS change does not introduce any failure mechanisms of a different type than those previously evaluated, since no physical changes to the plant are being made. Also, no new or different equipment is being installed, and no installed equipment is being operated in a different manner. As a result, no new failure modes are introduced. In addition, the surveillance test requirements themselves, and the way surveillance tests are performed, remain unchanged.

Furthermore, an historical review of surveillance test results and associated maintenance records indicates there is no evidence of any failure that would invalidate the above conclusions. Therefore, the proposed TS change does not create the possibility of a new or different kind of accident from any previously evaluated.

3.

The proposed amendment will not involve a significant reduction in a margin of safety.

Although the proposed TS change results in changes to the interval between surveillance tests, the impact, if any, on system availability is minimal, based upon other, more frequent testing that is performed, the existence of redundant systems and equipment, or overall system reliability. Evaluations show there is no evidence of time-dependent failures that would impact the availability of the systems. The proposed change does not significantly impact the condition or performance of structures, systems, and components relied upon for accident mitigation.

A sensitivity analysis was performed to determine the effect of the increased surveillance intervals on the HNP PRA. This sensitivity analysis shows a negligible increase in CDF and essentially no change in LERF due to the proposed change.

Furthermore, an historical review of surveillance test results and associated maintenance records indicates there was no evidence of any failure that would HL-6224 04/02 116-2 Request to Revise Technical Specifications:

Quarterly Surveillance Extension 10 CFR 50.92 Siqnificant Hazards Evaluation and Environmental Assessment invalidate the above conclusions. Therefore, the proposed change does not involve a significant reduction in a margin of safety.

B.

Environmental Assessment The proposed TS changes were reviewed for environmental considerations against the criteria set forth in 10 CFR 51.22. Based upon the results of this review, Southern Nuclear Operating Company has determined that the proposed TS change revises a requirement with respect to the installation or use of a facility component located within the restricted area, as defined in 10 CFR 20 or revises an inspection or SR. However, the proposed TS change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) as follows:

1.

The amendment involves no significant hazards consideration.

2.

There is no significant change in the types or significant increase in the amounts of any effluent that may be released offsite.

3.

A significant increase in individual or cumulative occupational radiation exposure.

Therefore, pursuant to 10 CFR 51.22(b), an environmental assessment of the proposed TS amendment is not required.

HL-6224 E6-3 04/02

-7

(ý LI-17( -1, Edwin I. Hatch Nuclear Plant Request to Revise Technical Specifications:

Quarterly Surveillance Extension Technical Specifications Page Chanaqe Instructions Unit 1 Page 3.3-5 3.3-17 3.3-21 3.3-28 3.3-32 3.3-40 3.3-49 3.3-54 3.3-61 3.3-64 3.3-65 3.3-68 Instruction Replace Replace Replace Replace Replace Replace Replace Replace Replace Replace Replace Replace HL-6224 04/02

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.7


NOTE---------------

Only required to be met during entry into MODE 2 from MODE 1.

Verify the IRM and APRM channels overlap.

7 days SR 3.3.1.1.8 Calibrate the local power range monitors.

1000 effective full power hours SR 3.3.1.1.9 Perform CHANNEL FUNCTIONAL TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.1.1.10 ----------------- NOTE--------------

For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

184 days SR 3.3.1.1.11 Verify Turbine Stop Valve--Closure and 184 days Turbine Control Valve Fast Closure, Trip Oil Pressure -

Low Functions are not bypassed when THERMAL POWER is

SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST.

18 months (continued)

Proposed Quarterly HATCH UNIT I 3.3-5

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.3.2.1.2 NOTE--------------

Not required to be performed until I hour after any control rod is withdrawn at

< 10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

SR 3.3.2.1.3 NOTE--------------

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after THERMAL POWER is < 10% RTP in MODE 1.

Perform CHANNEL FUNCTIONAL TEST.

SR 3.3.2.1.4 NOTE--------------

Neutron detectors are excluded.

Verify the RBM:

a.

Low Power Range -

Upscale Function is not bypassed when THERMAL POWER is 2 29% and < 64% RTP.

b.

Intermediate Power Range -

Upscale Function is not bypassed when THERMAL POWER is ý 64% and < 84% RTP.

c.

High Power Range -

Upscale Function is not bypassed when THERMAL POWER is S:84% RTP.

FREQUENCY 92 days on a STAGGERED TEST BASIS I.

92 days on a STAGGERED TEST BASIS 18 months (continued)

Proposed Quarterly HATCH UNIT 1 3.3-17

Feedwater and Main Turbine Trip High Water Level Instrumentation 3.3.2.2 SURVEILLANCE REQUIREMENTS


NOTE------------------------------

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided feedwater and main turbine high water level trip capability is maintained.

SURVEILLANCE FREQUENCY SR 3.3.2.2.1 Perform CHANNEL FUNCTIONAL TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.2.2.2 Perform CHANNEL CALIBRATION.

The 18 months Allowable Value shall be s 56.5 inches.

SR 3.3.2.2.3 Perform LOGIC SYSTEM FUNCTIONAL TEST 18 months including valve actuation.

Proposed Quarterly 3.3-21 HATCH UNIT I

EOC-RPT Instrumentati on 3.3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

One or more Functions B.1 Restore EOC-RPT trip 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with EOC-RPT trip capability.

capability not maintained.

OR AND B.2 Apply the MCPR limit 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for inoperable MCPR limit for EOC-RPT as specified inoperable EOC-RPT in the COLR.

not made applicable.

C.

Required Action and C.1 Remove the associated 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion recirculation pump Time not met.

from service.

OR C.2 Reduce THERMAL POWER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to < 28% RTP.

SURVEILLANCE REQUIREMENTS


NOTE When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains EOC-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.1.1 Perform CHANNEL FUNCTIONAL TEST.

92 days on a STAGGERED TEST BASIS (continued)

Proposed Quarterly 3.3-28 HATCH UNIT 1

ATWS-RPT Instrumentation 3.3.4.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.2.2 Perform CHANNEL FUNCTIONAL TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.4.2.3 Perform CHANNEL CALIBRATION. The 18 months Allowable Values shall be:

a.

Reactor Vessel Water Level ATWS-RPT Level: * -73 inches; and

b.

Reactor Steam Dome Pressure -

High:

s 1175 psig.

SR 3.3.4.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST 18 months including breaker actuation.

Proposed Quarterly HATCH UNIT I 3.3-32

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS


NOTES

1.

Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 3.c and 3.f; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.5.1.3 Perform CHANNEL CALIBRATION.

92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION.

18 months SR 3.3.5.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months Proposed Quarterly 3.3-40 HATCH UNIT I

RCIC System Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS


NOTES

1.

Refer to Table 3.3.5.2-1 to determine which SRs apply for each RCIC Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Function 2; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 1, 3, and 4 provided the associated Function maintains RCIC initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.5.2.3 Perform CHANNEL CALIBRATION.

92 days SR 3.3.5.2.4 Perform CHANNEL CALIBRATION.

18 months SR 3.3.5.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months Proposed Quarterly 3.3-49 HATCH UNIT I

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS


NOTES

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.
2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.6.1.3 Perform CHANNEL CALIBRATION.

92 days on a STAGGERED TEST BASIS SR 3.3.6.1.4 Perform CHANNEL FUNCTIONAL TEST.

184 days SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.

18 months SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months Proposed Quarterly HATCH UNIT I 3.3-54

Secondary Containment Isolation Instrumentation 3.3.6.2 SURVEILLANCE REQUIREMENTS


NOTES

1.

Refer to Table 3.3.6.2-1 to determine which SRs apply for each Secondary Containment Isolation Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.6.2.3 Perform CHANNEL CALIBRATION.

92 days on a STAGGERED TEST BASIS SR 3.3.6.2.4 Perform CHANNEL CALIBRATION.

18 months SR 3.3.6.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months Proposed Quarterly 3.3-61 HATCH UNIT 1

LLS Instrumentation 3.3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Declare the Immediately associated Completion associated LLS Time of Condition A, valve(s) inoperable.

B, or C not met.

OR Two or more LLS valves with initiation capability not maintained.

SURVEILLANCE REQUIREMENTS


NOTES

1. Refer to Table 3.3.6.3-1 to determine which SRs apply for each Function.
2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided LLS initiation capability is maintained.

SURVEILLANCE FREQUENCY SR 3.3.6.3.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.3.2 Perform CHANNEL FUNCTIONAL TEST for 92 days on a portion of the channel outside primary STAGGERED TEST containment.

BASIS (continued)

Proposed Quarterly 3.3-64 HATCH UNIT 1

LLS Instrumentation 3.3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.3.6.3.3


NOTE--------------

Only required to be performed prior to entering MODE 2 during each scheduled outage > 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when entry is made into primary containment.

Perform CHANNEL portions of the containment.

FUNCTIONAL TEST for channel inside primary FREQUENCY 92 days on a STAGGERED TEST BASIS SR 3.3.6.3.4 Perform CHANNEL FUNCTIONAL TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.6.3.5 Perform CHANNEL CALIBRATION.

18 months SR 3.3.6.3.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months Proposed Quarterly HATCH UNIT I 3.3-65

MCREC System Instrumentation 3.3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

Required Action and B.1 Place the associated 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated Completion MCREC subsystem(s) in Time not met.

the pressurization mode of operation.

OR B.2 Declare associated I hour MCREC subsystem(s) inoperable.

SURVEILLANCE REQUIREMENTS NOTE When a Control Room Air Inlet Radiation-High channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the other channel is OPERABLE.

SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST.

31 days SR 3.3.7.1.3 Perform CHANNEL CALIBRATION.

The 92 days on a Allowable Value shall be < 1 mr/hour.

STAGGERED TEST BASIS SR 3.3.7.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months Proposed Quarterly 3.3-68 HATCH UNIT I

ýjj,,T J-Iýb Request to Revise Technical Specifications:

Quarterly Surveillance Extension Technical Specifications Page Change Instructions Unit 2 Page Instruction 3.3-5 Replace 3.3-18 Replace 3.3-22 Replace 3.3-29 Replace 3.3-33 Replace 3.3-41 Replace 3.3-50 Replace 3.3-55 Replace 3.3-55a Add 3.3-55b Add 3.3-62 Replace 3.3-65 Replace 3.3-66 Replace 3.3-69 Replace HL-6224 04/02

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.7


NOTE---------------

Only required to be met during entry into MODE 2 from MODE 1.

Verify the IRM and APRM channels overlap.

7 days SR 3.3.1.1.8 Calibrate the local power range monitors.

1000 effective full power hours SR 3.3.1.1.9 Perform CHANNEL FUNCTIONAL TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.1.1.10 ----------------- NOTE--------------

For Function 2.a, not required to be performed when entering MODE 2 from MODE I until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

184 days SR 3.3.1.1.11 Verify Turbine Stop Valve--Closure and 18 months Turbine Control Valve Fast Closure, Trip Oil Pressure -

Low Functions are not bypassed when THERMAL POWER is > 28% RTP.

SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST.

18 months (continued)

Proposed Quarterly HATCH UNIT 2 3.3-5

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.3.2.1.2 NOTE--------------

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after any control rod is withdrawn at

< 10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

SR 3.3.2.1.3 NOTE--------------

Not required to be performed until I hour after THERMAL POWER is < 10% RTP in MODE 1.

Perform CHANNEL FUNCTIONAL TEST.

SR 3.3.2.1.4 NOTE--------------

Neutron detectors are excluded.

Verify the RBM:

a.

Low Power Range -- Upscale Function is not bypassed when THERMAL POWER is

,29%

and < 64% RTP.

b.

Intermediate Power Range -

Upscale Function is not bypassed when THERMAL POWER is a 64% and < 84% RTP.

c.

High Power Range -- Upscale Function is not bypassed when THERMAL POWER is n:84% RTP.

FREQUENCY 4

92 days on a STAGGERED TEST BASIS 4

92 days on a STAGGERED TEST BASIS 18 months (continued)

Proposed Quarterly HATCH UNIT 2 3.3-18

Feedwater and Main Turbine Trip High Water Level Instrumentation 3.3.2.2 SURVEILLANCE REQUIREMENTS


NOTE When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided feedwater and main turbine high water level trip capability is maintained.

SURVEILLANCE FREQUENCY SR 3.3.2.2.1 Perform CHANNEL FUNCTIONAL TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.2.2.2 Perform CHANNEL CALIBRATION.

The 18 months Allowable Value shall be a 55.5 inches.

SR 3.3.2.2.3 Perform LOGIC SYSTEM FUNCTIONAL TEST 18 months including valve actuation.

Proposed Quarterly HATCH UNIT 2 3.3-22

EOC-RPT Instrumentation 3.3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

One or more Functions B.1 Restore EOC-RPT trip 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with EOC-RPT trip capability.

capability not maintained.

OR AND B.2 Apply the MCPR limit 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for inoperable MCPR limit for EOC-RPT as specified inoperable EOC-RPT in the COLR.

not made applicable.

C.

Required Action and C.1 Remove the associated 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion recirculation pump Time not met.

from service.

OR C.2 Reduce THERMAL POWER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to < 28% RTP.

SURVEILLANCE REQUIREMENTS


NOTE When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains EOC-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.1.1 Perform CHANNEL FUNCTIONAL TEST.

92 days on a STAGGERED TEST BASIS (continued)

Proposed Quarterly HATCH UNIT 2 3.3-29

ATWS-RPT Instrumentation 3.3.4.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.2.2 Perform CHANNEL FUNCTIONAL TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.4.2.3 Perform CHANNEL CALIBRATION.

The 18 months Allowable Values shall be:

a.

Reactor Vessel Water Level ATWS-RPT Level: * -73 inches; and

b.

Reactor Steam Dome Pressure -

High:

1175 psig.

SR 3.3.4.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST 18 months including breaker actuation.

Proposed Quarterly HATCH UNIT 2 3.3-33

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS


NOTES

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.
2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 3.c and 3.f; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST.

92 days on a STAGGERED TEST BASIS SR 3.3,.5.1.3 Perform CHANNEL CALIBRATION.

92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION.

18 months SR 3.3.5.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months Proposed Quarterly HATCH UNIT 2 3.3-41

RCIC System Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS


NOTES I.

Refer to Table 3.3.5.2-1 to determine which SRs apply for each RCIC Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Function 2; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 1, 3, and 4 provided the associated Function maintains RCIC initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.5.2.3 Perform CHANNEL CALIBRATION.

92 days SR 3.3.5.2.4 Perform CHANNEL CALIBRATION.

18 months SR 3.3.5.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months Proposed Quarterly HATCH UNIT 2 3.3-50

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS


NOTES

1.

Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.6.1.3 Perform CHANNEL CALIBRATION.

92 days on a STAGGERED TEST BASIS SR 3.3.6.1.4 Perform CHANNEL FUNCTIONAL TEST.

184 days SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.

18 months SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months Proposed Quarterly HATCH UNIT 2 3.3-55

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.1.7


NOTE--------------

Channel sensors are excluded.

Verify the ISOLATION SYSTEM RESPONSE TIME 18 months on a is within limits.

STAGGERED TEST BASIS Proposed Quarterly HATCH UNIT 2 3.3-55a

Primary Containment Isolation Instrumentation 3.3.6.1 This page intentionally left blank.

Proposed Quarterly HATCH UNIT 2 3.3-55b

Secondary Containment Isolation Instrumentation 3.3.6.2 SURVEILLANCE REQUIREMENTS


NOTES

1. Refer to Table 3.3.6.2-1 to determine which SRs apply for each Secondary Containment Isolation Function.
2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.6.2.3 Perform CHANNEL CALIBRATION.

92 days on a STAGGERED TEST BASIS SR 3.3.6.2.4 Perform CHANNEL CALIBRATION.

18 months SR 3.3.6.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months Proposed Quarterly HATCH UNIT 2 3.3-62

LLS Instrumentation 3.3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Declare the Immediately associated Completion associated LLS Time of Condition A, valve(s) inoperable.

B, or C not met.

OR Two or more LLS valves with initiation capability not maintained.

SURVEILLANCE REQUIREMENTS


NOTES

1. Refer to Table 3.3.6.3-1 to determine which SRs apply for each Function.
2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided LLS initiation capability is maintained.

SURVEILLANCE FREQUENCY SR 3.3.6.3.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.3.2 Perform CHANNEL FUNCTIONAL TEST for 92 days on a portion of the channel outside primary STAGGERED TEST containment.

BASIS (continued)

Proposed Quarterly HATCH UNIT 2 3.3-65

LLS Instrumentation 3.3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.3.6.3.3


NOTE--------------

Only required to be performed prior to entering MODE 2 during each scheduled outage > 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when entry is made into primary containment.

Perform CHANNEL portions of the containment.

FUNCTIONAL TEST for channel inside primary FREQUENCY 4.

92 days on a STAGGERED TEST BASIS SR 3.3.6.3.4 Perform CHANNEL FUNCTIONAL TEST.

92 days on a STAGGERED TEST BASIS SR 3.3.6.3.5 Perform CHANNEL CALIBRATION.

18 months SR 3.3.6.3.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months Proposed Quarterly HATCH UNIT 2 3.3-66

MCREC System Instrumentation 3.3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Place the associated I hour associated Completion MCREC subsystem(s) in Time not met.

the pressurization mode of operation.

OR B.2 Declare associated I hour MCREC subsystem(s) inoperable.

SURVEILLANCE REQUIREMENTS


NOTE When a Control Room Air Inlet Radiation-High channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the other channel is OPERABLE.

SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST.

31 days SR 3.3.7.1.3 Perform CHANNEL CALIBRATION.

The 92 days on a Allowable Value shall be s I mr/hour.

STAGGERED TEST BASIS SR 3.3.7.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months Proposed Quarterly HATCH UNIT 2 3.3-69

8

ý-A c Loeýu ý E Edwin I. Hatch Nuclear Plant Request to Revise Technical Specifications:

Quarterly Surveillance Extension Marked-Up Technical Specifications Pages HL-6224 04/02

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.7


NOTE--------------

Only required to be met during entry into MODE 2 from MODE 1.

Verify the IRM and APRM channels overlap.

7 days SR 3.3.1.1.8 Calibrate the local power range monitors.

1000 effectiVe full power hours SR 3.3.1.1.9 Perform CHANNEL FUNCTIONAL TEST.

92 days e SR 3.3.1.1.10 ----------------- NOTE--------------

For Function 2.a, not required to be performed when entering MODE 2 from MODE I until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

184 days SR 3.3.1.1.11 Verify Turbine Stop Valve -

Closure and 184 days Turbine Control Valve Fast Closure, Trip Oil Pressure -

Low Functions are not bypassed when THERMAL POWER is ; 28% RTP.

SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST.

18 months (continued)

Amendment No.

214 3.3-5 HATCH UNIT 1

Control Rod Block Instrumentation 3.3.2.1 eIInlrTI I RNC

OAIITDMNJT

(,nntin,,orI

CUl LI LrI~- Aktrr~

DC~

L HT LICKT(

i-n i nr SURVEILLANCE SR 3.3.2.1.2


NOTE--------------

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after any control rod is withdrawn at

< 10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

t 4

SR 3.3.2.1.3


NOTE--------------

Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after THERMAL POWER is < 10% RTP in MODE 1.

Perform CHANNEL FUNCTIONAL TEST.

SR 3.3.2.1.4


NOTE--------------

Neutron detectors are excluded.

Verify the RBM:

a.

Low Power Range -

Upscale Function is not bypassed when THERMAL POWER is 2 29% and < 64% RTP.

b.

Intermediate Power Range -

Upscale Function is not bypassed when THERMAL POWER is 2 64% and < 84% RTP.

c.

High Power Range -

Upscale Function is not bypassed when THERMAL POWER is

84% RTP.

(continued)

Amendment No.

195 HATCH UNIT I FREQUENCY 92 days oA

ý 92 days op 18 months 3.3-17

Feedwater and Main Turbine Trip High Water Level Instrumentation 3.3.2.2 SURVEILLANCE REQUIREMENTS


NOTE-When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided feedwater and main turbine high water level trip capability is maintained.

SURVEILLANCE SR 3.3.2.2.1 Perform CHANNEL FUNCTIONAL TEST.

FREQUENCY 92 days

-on 57;7

=7 f

A?.AsS I-SR 3.3.2.2.2 Perform CHANNEL CALIBRATION.

The 18 months Allowable Value shall be : 56.5 inches.

SR 3.3.2.2.3 Perform LOGIC SYSTEM FUNCTIONAL TEST 18 months including valve actuation.

Amendment No.

195

-i 3.3-21 HATCH UNIT 1

EOC-RPT Instrumentation 3.3.4.1 ACTIONS (continued)

CONDITION B.

One or more Functions with EOC-RPT trip capability not maintained.

AND MCPR limit for inoperable EOC-RPT not made applicable.

C.

Required Action and associated Completion Time not met.

REQUIRED ACTION B.1 OR B.2 C. 1 Restore EOC-RPT trip capability.

Apply the MCPR limit for inoperable EOC-RPT as specified in the COLR.

Remove the associated recirculation pump from service.

OR C.2 Reduce THERMAL POWER to < 28% RTP.

I ________________________

I COMPLETION TIME 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 2 hours 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours SURVEILLANCE REQUIREMENTS


NOTE When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains EOC-RPT trip capability.

I FRLtUL!ILY SURVEILLANCE SR 3.3.4.1.1 Perform CHANNEL FUNCTIONAL TEST.

92 days !n a 3AE*.s° r4EYr i SAsa5'd' 3.3-28 HATCH UNIT 1 (continued)

Amendment No.

214 I

FREQUtNUY

ATWS-RPT Instrumentati on 3.3.4.2

  • tIIVFT11ANrF RFnUITREMENTS (continued)

Amendment No. 197 HATCH UNIT 1 SURVEILLANCE FREQUENCY SR 3.3.4.2.2 Perform CHANNEL FUNCTIONAL TEST.

92 daysp1i0 SR 3.3.4.2.3 Perform CHANNEL CALIBRATION.

The 18 months Allowable Values shall be:

a.

Reactor Vessel Water Level ATWS-RPT Level: 2 -73 inches; and

b.

Reactor Steam Dome Pressure -

High:

s 1175 psig.

SR 3.3.4.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST 18 months including breaker actuation.

3.3-32

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS NOTES----------------

1.

Refer to Table 3.3.5.1-I to determine which SRs apply for each ECCS Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 3.c and 3.f; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains initiation capability.

SURVEILLANCE SR 3.3.5.1.1 Perform CHANNEL CHECK.

SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST.

SR 3.3.5.1.3 Perform CHANNEL CALIBRATION.

SR 3.3.5.1.4 Perform CHANNEL CALIBRATION.

SR 3.3.5.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST.

FREQUENCY 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 92 days 92 days 18 months 18 months HATCH UNIT 1 3.3-40 Amendment No.

195

RCIC System Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS


...-------------------- NOTES---------------------

1. Refer to Table 3.3.5.2-1 to determine which SRs apply for each RCIC Function.
2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Function 2; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 1, 3, and 4 provided the associated Function maintains RCIC initiation capability.

SURVEILLANCE SR 3.3.5.2.1 Perform CHANNEL CHECK.

SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST.

SR 3.3.5.2.3 Perform CHANNEL CALIBRATION.

SR 3.3.5.2.4 Perform CHANNEL CALIBRATION.

SR 3.3.5.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST.

FREQUENCY FREQUENCY 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 92 days 92 days 18 months 18 months I _________________________________________________________

HATCH UNIT 1 3.3-49 Amendment No.

195

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS


NOTES

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.
2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.6.1.3 Perform CHANNEL CALIBRATION.

92 days c a

SR 3.3.6.1.4 Perform CHANNEL FUNCTIONAL TEST.

184 days SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.

18 months SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months Amendment No.

195 3.3-54 HATCH UNIT I

Secondary Containment Isolation Instrumentation 3.3.6.2 SURVEILLANCE REQUIREMENTS NOTES

1.

Refer to Table 3.3.6.2-I to determine which SRs apply for each Secondary Containment Isolation Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains isolation capability.

SURVEILLANCE SR 3.3.6.2.1 SR 3.3.6.2.2 T

Perform CHANNEL CHECK.

Perform CHANNEL FUNCTIONAL TEST.

-F SR 3.3.6.2.3 SR 3.3.6.2.4 Perform CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION.

FREQUENCY 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 92 days a

92 days d a.

-WAOWZJP re 18 months SR 3.3.6.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months 3.3-61 Amendment No.

195 HATCH UNIT 1 I

LLS Instrumentation 3.3.6.3 A.IU I QN tconinLTued)

CONDITION D. Required Action and associated Completion Time of Condition A, B, or C not met.

OR Two or more LLS valves with initiation capability not maintained.

REQUIRED ACTION D.I Declare the associated LLS valve(s) inoperable.

I COMPLETION TIME Immediately SURVEILLANCE REQUIREMENTS NOTES

1. Refer to Table 3.3.6.3-1 to determine which SRs apply for each Function.
2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided LLS initiation capability is maintained.


i--------------

m---------------------------------

SURVEILLANCE FREQUENCY SR 3.3.6.3.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.3.2 Perform CHANNEL FUNCTIONAL TEST for portion of the channel outside primary containment.

1 92 days nn a-.

5xvilezz 7n:$/

14s/.s (continued)

Amendment No.

195 HATCH UNIT 1 i

I 3.3-64

LLS Instrumentation 3.3.6.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEI LLANCE FREQUENCY SR 3.3.6.3.3


NOTE--------------

Only required to be performed prior to entering MODE 2 during each scheduled outage > 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when entry is made into primary containment.

.Perform CHANNEL portions. of the containment.

FUNCTIONAL TEST for channel inside primary 4"

SR 3.3.6.3.4 Perform CHANNEL FUNCTIONAL TEST.

92 days vifl 92 days s7Aaax;o 7WS7 RA~SI5 SR 3.3.6.3.5 Perform CHANNEL CALIBRATION.

18 months SR 3.3.6.3.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months Amendment No.

195 HATCH UNIT I 3.3-65

MCREC System Instrumentation 3.3.7.1 AtL I WU NZo> s L MU C I I _._u____,___u_

CONDITION REQUIRED ACTION I

B.

Required Action and associated Completion Time not met.

B.1 Place the associated MCREC subsystem(s) in the pressurization mode of operation.

Declare associated MCREC subsystem(s) inoperable.

OR B.2 COMPLETION IIML I hour 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1

.1 SURVEILLANCE REQUIREMENTS


NOTE--

When a Control Room Air Inlet Radiation-High channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the other channel is OPERABLE.

SURVEILLANCE SR 3.3.7.1.1 Perform CHANNEL CHECK.

I SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST.

FREQUENCY 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 31 days I

SR 3.3.7.1.3 SR 3.3.7.1.4 Perform CHANNEL CALIBRATION.

Allowable Value shall be _ I The mr/hour.

Perform LOGIC SYSTEM FUNCTIONAL TEST.

92 days

'" C c

7.ST 18 months j

3.3-68 Amendment No.

195 HATCH UNIT I flP R'IP I4 FREQUENCY

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS(continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.7


NOTE --------------

Only required to be met during entry into MODE 2 from MODE 1.

Verify the IRM and APRM channels overlap.

7 days SR 3.3.1.1.8 Calibrate the local power range monitors.

1000 effective full power hours SR 3.3.1.1.9 Perform CHANNEL FUNCTIONAL TEST.

92 days :f r

.S4ý,rA" 7XsT SR 3.3.1.1.10 ----------------- NOTE--------------

For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

184 days SR 3.3.1.1.11 Verify Turbine Stop Valve--Closure and 18 months Turbine Control Valve Fast Closure, Trip Oil Pressure -

Low Functions are not bypassed when THERMAL POWER is > 28% RTP.

SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST.

18 months (continued)

Amendment No.

155 3.,3-5 HATCH UNIT 2

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.3.2.1.2 1

FREQUENCY T

-NOTE-Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after any control rod is withdrawn at

< 10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

. rI SR 3.3.2.1.3

-NOTE Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after THERMAL POWER is < 10% RTP in MODE I.

Perform CHANNEL FUNCTIONAL TEST.

I*

SR 3.3.Z.1.4 NOTE Neutron detectors are excluded.

Verify the RBM:

a.

Low Power Range -

Upscale Function is not bypassed when THERMAL POWER is

ý 29% and < 64% RTP.

b.

Intermediate Power Range -

Upscale Function is not bypassed when THERMAL POWER is 2 64% and < 84% RTP.

c.

High Power Range -

Upscale Function is not bypassed when THERMAL POWER is 2:84% RTP.

92 days t

92 days sv* o 18 months (continued)

Amendment No.

135 HATCH UNIT 2 3.3-18

Feedwater and Main Turbine Trip High Water Level Instrumentation 3.3.2.2 SURVEILLANCE REQUIREMENTS NOTE When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided feedwater and main turbine high water level trip capability is maintained.

SR 3.3.2.2.1 SR 3.3.2.2.2 SR 3.3.2.2.3

i. FREQUENLY SURVEILLANCE Perform CHANNEL FUNCTIONAL TEST.

Perform CHANNEL CALIBRATION.

The Allowable Value shall be _ 55.5 inches.

Perform LOGIC SYSTEM FUNCTIONAL TEST including valve actuation.

92 days on c 13A-S /5s 18 months 18 months 3.3-22 Amendment No.

135 HATCH UNIT 2 I

I i

FREQUENCY

EOC-RPT Instrumentati on 3.3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

One or more Functions B.1 Restore EOC-RPT trip 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with EOC-RPT trip capability.

capability not maintained.

OR AND B.2 Apply the MCPR limit 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for inoperable MCPR limit for EOC-RPT as specified inoperable EOC-RPT in the COLR.

not made applicable.

C.

Required Action and C.1 Remove the associated 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion recirculation pump Time not met.

from service.

OR C.2 Reduce THERMAL POWER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to < 28% RTP.

SURVEILLANCE REQUIREMENTS


NOTE When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains EOC-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.1.1 Perform CHANNEL FUNCTIONAL TEST.

92 days on (continued)

Amendment No.

155 I

HATCH UNIT 2 3.3-29

ATWS-RPT Instrumentation 3.3.4.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.2.2 Perform CHANNEL FUNCTIONAL TEST.

92 days on e.

SR 3.3.4.2.3 Perform CHANNEL CALIBRATION. The 18 months Allowable Values shall be:

a.

Reactor Vessel Water Level ATWS-RPT Level: 2:-73 inches; and

b.

Reactor Steam Dome Pressure -

High:

1175 psig.

SR 3.3.4.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST 18 months including breaker actuation.

Amendment No. 138 HATCH UNIT 2 I

3.3-33

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS

-I--U I L

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.
2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 3.c and 3.f; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST.

92 days a" S54S/5 SR 3.3.5.1.3 Perform CHANNEL CALIBRATION.

92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION.

18 months SR 3.3.5.1.5 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months Amendment No.

137 I

3.3-41 HATCH UNIT 2

RCIC System Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS NOTES

1. Refer to Table 3.3.5.2-1 to determine which SRs apply for each RCIC Function.
2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Function 2; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 1, 3, and 4 provided the associated Function maintains RCIC initiation capability.

I FREQUENCY SURVEILLANCE SR 3.3.5.2.1 Perform CHANNEL CHECK.

I SR 3.3.5.2.2 SR 3.3.5.2.3 Perform CHANNEL FUNCTIONAL TEST.

Perform CHANNEL CALIBRATION.

SR 3.3.5.2.4 Perform CHANNEL CALIBRATION.

SR 3.3.5.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 92 days :t c

92 days 18 months 18 months Amendment No.

135 HATCH UNIT 2 I

FREQUENCY 3.3-50

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS NOTES

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.
2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.6.1.3 Perform CHANNEL CALIBRATION.

92days on SR 3.3.6.1.4 Perform CHANNEL FUNCTIONAL TEST.

184 days SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.

18 months SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months SR 3.3.6.1.7 NOTE--

Channel sensors are excluded.

Verify the ISOLATION SYSTEM RESPONSE TIME 18 months on a is within limits.

STAGGERED TEST BASIS Amendment No.

137 HATCH UNIT 2 I

3.3-55

Secondary Containment Isolation Instrumentation 3.3.6.2 SURVEILLANCE REQUIREMENTS NOTES

1.

Refer to Table 3.3.6.2-1 to determine which SRs apply for each Secondary Containment Isolation Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST.

92 days v o 5r7*;

6*ee 7rs' SR 3.3.6.2.3 Perform CHANNEL CALIBRATION.

92 days SR 3.3.6.2.4 Perform CHANNEL CALIBRATION.

18 months SR 3.3.6.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months Amendment No.

135 HATCH UNIT 2 3.3-62

LLS Instrumentation 3.3.6.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

Required Action and D.1 Declare the Immediately associated Completion associated LLS Time of Condition A, valve(s) inoperable.

B, or C not met.

OR Two or more LLS valves with initiation capability not maintained.

SURVEILLANCE REQUIREMENTS NOTES

1. Refer to Table 3.3.6.3-1 to determine which SRs apply for each Function.
2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided LLS initiation capability is maintained.

SURVEILLANCE FREQUENCY SR 3.3.6.3.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.3.2 Perform CHANNEL FUNCTIONAL TEST for 92 days portion of the channel outside primary ST-41D

-rLT containment.

asL (continued)

Amendment No.

135 HATCH UNIT 2 3.3-65

LLS Instrumentation 3.3.6.3 I AUV

nrflhITDIMJT

SURVEILLANCE SR 3.3.6.3.3

-NOTE Only required to be performed prior to entering MODE 2 during each scheduled outage > 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when entry is made into primary containment.

Perform CHANNEL portions of the containment.

SR 3.3.6.3.4 FUNCTIONAL TEST for channel inside primary Perform CHANNEL FUNCTIONAL TEST.

I SR 3.3.6.3.5 Perform CHANNEL CALIBRATION.

CFR UE, r,

92 days o SrA60,9e4FD 7ZST BAs 15 92 days

&A d r.

18 months I

SR 3.3.6.3.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months j ________________________________________

3.3-66 Amendment No.

135 HATCH UNIT 2 I

/rnntinH*d*

FREQUENCY

MCREC System Instrumentation 3.3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Place the associated I hour associated Completion MCREC subsystem(s) in Time not met.

the pressurization mode of operation.

OR B.2 Declare associated I hour MCREC subsystem(s).

inoperable.

SURVEILLANCE REQUIREMENTS


NOTE When a Control Room Air Inlet Radiation-High channel is placed in an inoperable status solely for performance of required Surveillances, entry into

  • associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the other channel is OPERABLE.

SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST.

31 days SR 3.3.7.1.3 Perform CHANNEL CALIBRATION.

The Allowable Value shall be _ I mr/hour.

92 days on &

s -A &&,C"0 Amendment No.

135 HATCH UNIT 2 SR 3.3.7.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months 3.3-69

I

- -Tf- ý)

(ýal-T I Edwin I. Hatch Nuclear Plant Request to Revise Technical Specifications:

Quarterly Surveillance Extension Bases Paae Chanae Instructions Unit 1 Paae B 3.3-29 B 3.3-32b B 3.3-50 B 3.3-53 B 3.3-59 B 3.3-60 B 3.3-86 B 3.3-89 B 3.3-97 B 3.3-98 B 3.3-134 B 3.3-135 B 3.3-145 B 3.3-146 B 3.3-174 B 3.3-175 B 3.3-184 B 3.3-185 B 3.3-186 B 3.3-193 B 3.3-195 B 3.3-201 B 3.3-202 Instruction Replace Replace Replace Replace Replace Replace Replace Replace Replace Replace Replace Replace Replace Replace Replace Replace Replace Replace Replace Replace Replace Replace Replace HL-6224 04/02

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.9 and SR 3.3.1.1.12 REQUIREMENTS (continued)

A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency of SR 3.3.1.1.9 is based on a review of the surveillance test history, drift analysis of the associated trip units (if applicable), and Reference 18.

The 18 month Frequency of SR 3.3.1.1.12 is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

The 18 month Frequency for Table 3.3.1.1-1, Function 7.a, is based on Reference 18.

SR 3.3.1.1.10 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

For the APRM Functions, this test supplements the automatic self-test functions that operate continuously in the APRM and voter channels.

The APRM CHANNEL FUNCTIONAL TEST covers the APRM channels (including recirculation flow processing -

applicable to Function 2.b only), the two-out-of-four voter channels, and the interface connections to the RPS trip systems from the voter channels.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 184 day Frequency of SR 3.3.1.1.10 is based on the reliability analysis of References 12 and 16.

(NOTE:

The actual voting logic of the two-out-of-four voter channels is tested as part of SR 3.3.1.1.15.)

For Function 2.a, a Note that requires this SR to be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of entering MODE 2 from MODE 1 is provided.

Testing of the MODE 2 APRM Function cannot be performed in MODE 1 without utilizing jumpers or lifted leads.

This Note allows entry into MODE 2 from MODE 1 if the associated Frequency is not met per SR 3.0.2.

(continued)

Proposed Quarterly HATCH UNIT 1 B 3.3-29

RPS Instrumentation B 3.3.1.1 BASES REFERENCES

9.

NEDO-30851-P-A, "Technical Specification Improvement (continued)

Analyses for BWR Reactor Protection System,"

March 1988.

10.

Technical Requirements Manual.

11.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

12.

NEDC-32410P-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM)

Retrofit Plus Option III Stability Trip Function,"

October 1995.

13.

NEDO-31960-A, "BWR Owners' Group Long-Term Stability Solutions Licensing Methodology," November 1995.

14.

NEDO-31960-A, Supplement 1, "BWR Owners' Group Long Term Stability Solutions Licensing Methodology,"

November 1995.

15.

NEDO-32465-A, "BWR Owners' Group Long-Term Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications," March 1996.

16.

NEDO-32410P-A, Supplement 1, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option III Stability Trip Function," November 1997.

17.

Letter, L.A. England (BWROG) to M.J. Virgilio, "BWR Owners' Group Guidelines for Stability Interim Corrective Action," June 6, 1994.

18.

NRC Safety Evaluation Report for Amendment Proposed Quarterly B 3.3-32b HATCH UNIT 1

Control Rod Block Instrumentation B 3.3.2.1 BASES SURVEILLANCE SR 3.3.2.1.1 REQUIREMENTS (continued)

A CHANNEL FUNCTIONAL TEST is performed for each RBM channel to ensure that the entire channel will perform the intended function.

It includes the Reactor Manual Control System input.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The Frequency of 184 days is based on reliability analyses (Ref.

11).

SR 3.3.2.1.2 and SR 3.3.2.1.3 A CHANNEL FUNCTIONAL TEST is performed for the RWM to ensure that the entire system will perform the intended function.

The CHANNEL FUNCTIONAL TEST for the RWM is performed by attempting to withdraw a control rod not in compliance with the prescribed sequence and verifying a control rod block occurs.

This test is performed as soon as possible after the applicable conditions are entered.

As noted in the SRs, SR 3.3.2.1.2 is not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after any control rod is withdrawn at < 10% RTP in MODE 2, and SR 3.3.2.1.3 is not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after THERMAL POWER is < 10% RTP in MODE 1. This allows entry into MODE 2 (and if entered during a shutdown, concurrent power reduction to < 10% RTP) for SR 3.3.2.1.2 and THERMAL POWER reduction to < 10% RTP in MODE 1 for SR 3.3.2.1.3 to perform the required Surveillances if the 92 day on a STAGGERED TEST BASIS Frequency is not met per SR 3.0.2.

The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> allowance is based on operating experience and in consideration of providing a reasonable time in which to complete the SRs.

The 92 day on a STAGGERED TEST BASIS Frequency is based on a review of the surveillance test history and Reference 12.

SR 3.3.2.1.4 The RBM setpoints are automatically varied as a function of power.

Three Allowable Values are specified in Table 3.3.2.1-1, each within a specific power range.

The power at which the control rod block Allowable Values automatically change are based on the APRM signal's input to each RBM channel.

Below the minimum power setpoint, the RBM is automatically bypassed.

These power Allowable Values (continued)

Proposed Quarterly HATCH UNIT I B 3.3-50

Control Rod Block Instrumentation B 3.3.2.1 BASES SURVEILLANCE SR 3.3.2.1.8 (continued)

REQU IREM ENTS OPERABLE following loading of sequence into RWM, since this is when rod sequence input errors are possible.

REFERENCES

1.

FSAR, Section 7.5.8.2.3.

2.

FSAR, Section 7.2.2.4.

3.

NEDC-30474-P, "Average Power Range Monitor, Rod Block Monitor, and Technical Specification Improvements (ARTS) Program for Edwin I. Hatch Nuclear Plants,"

December 1983.

4.

NEDE-24011-P-A-US, "General Electrical Standard Application for Reload Fuel," Supplement for United States, (revision specified in the COLR).

5.

Letter from T.A. Pickens (BWROG) to G.C. Lainas (NRC),

"Amendment 17 to General Electric Licensing Topical Report NEDE-24011-P-A,"

BWROG-8644, August 15, 1986.

6.

NEDO-21231, "Banked Position Withdrawal Sequence,"

January 1977.

7.

NRC SER, "Acceptance of Referencing of Licensing Topical Report NEDE-24011-P-A," "General Electric Standard Application for Reactor Fuel, Revision 8, Amendment 17," December 27, 1987.

8.

NEDC-30851-P-A, "Technical Specification Improvement Analysis for BWR Control Rod Block Instrumentation,"

October 1988.

9.

GENE-770-06-1, "Bases For Changes To Surveillance Test Intervals and Allowed Out-Of-Service Times For Selected Instrumentation Technical Specifications,"

February 1991.

10.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

11.

NEDC-32410P-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM)

Retrofit Plus Option III Stability Trip Function,"

October 1995.

12.

NRC Safety Evaluation Report for Amendment Proposed Quarterly HATCH UNIT I B 3.3-53

Feedwater and Main Turbine High Water Level Trip Instrumentation B 3.3.2.2 BASES SURVEILLANCE SR 3.3.2.2.1 (continued)

REQUIREMENTS logic from the input of the alarm unit.

This is consistent with the CHANNEL FUNCTIONAL TEST definition requiring the signal to be injected "as close to the sensor as practicable."

Additionally, due to the physical location of the turbine trip relays and their close proximity to other sensitive equipment, accessibility is extremely limited.

Verification of relay actuation and associated relay contact status by accessing the relay introduces a high potential for turbine trip and reactor scram.

One contact from each turbine trip relay energizes an amber light indicating relay actuation.

Therefore, it is acceptable to terminate the test at the turbine trip relay, utilizing light indication for relay status.

These allowances are only acceptable if the CHANNEL CALIBRATION and the LOGIC SYSTEM FUNCTIONAL TEST overlap both the initiation and termination point of this CHANNEL FUNCTIONAL TEST such that the entire trip logic is tested.

The 92 day on a STAGGERED TEST BASIS Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 4.

SR 3.3.2.2.2 CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The Frequency is based upon the assumption of an 18 month calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.2.2.3 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel. The system functional test of the feedwater and main turbine valves is included as part of this Surveillance and overlaps the LOGIC SYSTEM FUNCTIONAL TEST to provide (continued)

Proposed Quarterly B 3.3-59 HATCH UNIT 1

Feedwater and Main Turbine High Water Level Trip Instrumentation B 3.3.2.2 BASES SURVEILLANCE SR 3.3.2.2.3 (continued)

REQUIREMENTS complete testing of the assumed safety function.

Therefore, if a valve is incapable of operating, the associated instrumentation channels would also be inoperable.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

REFERENCES

1. FSAR, Section 14.3.2.1.
2.

GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times for Selected Instrumentation Technical Specifications,"

February 1991.

3.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

4.

NRC Safety Evaluation Report for Amendment Proposed Quarterly B 3.3-60 HATCH UNIT 1

EOC-RPT Instrumentation B 3.3.4.1 BASES SURVEILLANCE analysis demonstrated that the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance REQUIREMENTS does not significantly reduce the probability that the (continued) recirculation pumps will trip when necessary.

SR 3.3.4.1.1 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency is based on a review of the surveillance-test history and Reference 7.

SR 3.3.4.1.2 This SR ensures that an EOC-RPT initiated from the TSV -

Closure and TCV Fast Closure, Trip Oil Pressure -

Low Functions will not be inadvertently bypassed when THERMAL POWER is ; 28% RTP.

This involves calibration of the bypass channels.

Adequate margins for the instrument setpoint methodologies are incorporated into the actual setpoint.

Because main turbine bypass flow can affect this setpoint nonconservatively (THERMAL POWER is derived from first stage pressure) the main turbine bypass valves must remain closed during the calibration at THERMAL POWER 2 28% RTP to ensure that the calibration is valid.

If any bypass channel's setpoint is nonconservative (i.e., the Functions are bypassed at 2 28% RTP, either due to open main turbine bypass valves or other reasons), the affected TSV -

Closure and TCV Fast Closure, Trip Oil Pressure -

Low Functions are considered inoperable.

Alternatively, the bypass channel can be placed in the conservative condition (nonbypass).

If placed in the nonbypass condition (Turbine Stop Valve-Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure-Low Functions are enabled), this SR is met with the channel considered OPERABLE.

The Frequency of 184 days is based on engineering judgment and reliability of the components.

(continued)

Proposed Quarterly B 3.3-86 HATCH UNIT I

EOC-RPT Instrumentation B 3.3.4.1 BASES REFERENCES (continued)

4.

GENE-770-06-1, "Bases For Changes To Surveillance Test Intervals And Allowed Out-Of-Service Times For Selected Instrumentation Technical Specifications,"

February 1991.

5.

Technical Requirements Manual.

6.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

7.

NRC Safety Evaluation Report for Amendment Proposed Quarterly B 3.3-89 HATCH UNIT I

ATWS-RPT Instrumentation B 3.3.4.2 BASES SURVEILLANCE SR 3.3.4.2.1 (continued)

REQUIREMENTS Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the channels required by the LCO.

SR 3.3.4.2.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 4.

SR 3.3.4.2.3 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The Frequency is based upon the assumption of an 18 month calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis.

(continued)

Proposed Quarterly HATCH UNIT I B 3.3-97

ATWS-RPT Instrumentation B 3.3.4.2 BASES SURVEILLANCE REQUIREMENTS (continued)

REFERENCES SR 3.3.4.2.4 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel.

The system functional test of the pump breakers is included as part of this Surveillance and overlaps the LOGIC SYSTEM FUNCTIONAL TEST to provide complete testing of the assumed safety function.

Therefore, if a breaker is incapable of operating, the associated instrument channel(s) would be inoperable.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

1.

FSAR, Section 7.23.

2.

GENE-770-06-1, "Bases for Changes To Surveillance Test Intervals and Allowed Out-of-Service Times For Selected Instrumentation Technical Specifications,"

February 1991.

3.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

4.

NRC Safety Evaluation Report for Amendment __

Proposed Quarterly B 3.3-98 HATCH UNIT 1

ECCS Instrumentation B 3.3.5.1 BASES SURVEILLANCE SR 3.3.5.1.2 REQUIREMENTS (continued)

A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 7.

SR 3.3.5.1.3 and SR 3.3.5.1.4 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The Frequency of SR 3.3.5.1.3 and SR 3.3.5.1.4 is based upon the assumption of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.5.1.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel.

The system functional testing performed in LCO 3.5.1, LCO 3.5.2, LCO 3.7.2, LCO 3.8.1, and LCO 3.8.2 overlaps this Surveillance to complete testing of the assumed safety function.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

(continued)

Proposed Quarterly B 3.3-134 HATCH UNIT 1

ECCS Instrumentation B 3.3.5.1 BASES (continued)

REFERENCES

1.

FSAR, Section 4.8.

2.

FSAR, Section 6.5.

3.

FSAR, Chapter 14.4.

4.

NEDC-31376-P, "Edwin I. Hatch Nuclear Power Plant, SAFER/GESTR-LOCA, Loss-of-Coolant Accident Analysis,"

December 1986.

5.

NEDC-30936-P-A, "BWR Owners' Group Specification Improvement Analyses Instrumentation, Part 2," December Technical for ECCS Actuation 1988.

6.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

7.

NRC Safety Evaluation Report for Amendment Proposed Quarterly HATCH UNIT I B 3.3-135

RCIC System Instrumentation B 3.3.5.2 BASES SURVEILLANCE SR 3.3.5.2.1 (continued)

REQUIREMENTS channels monitoring the same parameter should read approximately the same value.

Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious.

A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the channels required by the LCO.

SR 3.3.5.2.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 3.

SR 3.3.5.2.3 and SR 3.3.5.2.4 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

(continued)

Proposed Quarterly B 3.3-145 HATCH UNIT I

RCIC System Instrumentation B 3.3.5.2 BASES SURVEILLANCE REQUIREMENTS SR 3.3.5.2.3 and SR 3.3.5.2.4 (continued)

The Frequency of SR 3.3.5.2.3 and SR 3.3.5.2.4 is based upon the assumption of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.5.2.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel.

The system functional testing performed in LCO 3.5.3 overlaps this Surveillance to provide complete testing of the safety function.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

REFERENCES

1.

GENE-770-06-2, "Addendum to Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," February 1991.

2.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

3.

NRC Safety Evaluation Report for Amendment Proposed Quarterly HATCH UNIT 1 B 3.3-146

Primary Containment Isolation Instrumentation B 3.3.6.1 BASES SURVEILLANCE SR 3.3.6.1.2 and SR 3.3.6.1.4 (continued)

REQUIREMENTS The 92 day on a STAGGERED TEST BASIS Frequency of SR 3.3.6.1.2 is based on a review of the surveillance test history, drift analysis of the associated trip units (if applicable), and Reference 7.

The 184 day Frequency of SR 3.3.6.1.4 is based on engineering judgment and the reliability of the components (time delay relays exhibit minimal drift).

SR 3.3.6.1.3 and SR 3.3.6.1.5 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency of SR 3.3.6.1.3 is based on a review of the surveillance test history, drift analysis of the associated pressure (or vacuum) switches (if applicable), and Reference 7.

The Frequency of SR 3.3.6.1.5 is based on the assumption of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.6.1.6 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel.

The system functional testing performed on PCIVs in LCO 3.6.1.3 overlaps this Surveillance to provide complete testing of the assumed safety function.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

(continued)

Proposed Quarterly B 3.3-174 HATCH UNIT 1

Primary Containment Isolation Instrumentation B 3.3.6.1 BASES (continued)

REFERENCES

1. FSAR, Section 5.2.
2.

FSAR, Chapter 14.

3.

FSAR, Section 3.8.3.

4.

NEDC-31677P-A, "Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation,"

July 1990.

5.

NEDC-30851P-A Supplement 2, "Technical Specifications Improvement Analysis for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation," March 1989.

6.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

7.

NRC Safety Analysis Report for Amendment Proposed Quarterly B 3.3-175 HATCH UNIT I

Secondary Containment Isolation Instrumentation B 3.3.6.2 BASES SURVEILLANCE average time required to perform channel surveillance.

That REQUIREMENTS analysis demonstrated the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance does not (continued) significantly reduce the probability that the SCIVs will isolate the associated penetration flow paths and that the SGT System will initiate when necessary.

SR 3.3.6.2.1 Performance of the CHANNEL CHECK once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ensures that a gross failure of instrumentation has not occurred.

A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels.

It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value.

Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious.

A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based on operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channel status during normal operational use of the displays associated with channels required by the LCO.

SR 3.3.6.2.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 8.

(continued)

Proposed Quarterly B 3.3-184 HATCH UNIT I

Secondary Containment Isolation Instrumentation B 3.3.6.2 BASES SURVEILLANCE REQUIREMENTS (continued)

REFERENCES SR 3.3.6.2.3 and SR 3.3.6.2.4 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency of SR 3.3.6.2.3 is based on a review of the surveillance test history and Reference 8.

The Frequency of SR 3.3.6.2.4 is based on the assumption of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.6.2.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel.

The system functional testing performed on SCIVs and the SGT System in LCO 3.6.4.2 and LCO 3.6.4.3, respectively, overlaps this Surveillance to provide complete testing of the assumed safety function.

While this Surveillance can be performed with the reactor at power for some of the Functions, operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

Therefore, the Frequency was found to be acceptable from a reliability standpoint.

1.

FSAR, Section 5.2.

2.

FSAR, Chapter 14.4.

3.

FSAR, Sections 14.4.5 and 14.5.4.

4.

FSAR, Sections 14.4.3, 14.4.4, 14.5.2, and 14.5.3.

5.

NEDC-31677P-A, "Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation,"

July 1990.

(continued)

Proposed Quarterly HATCH UNIT 1 B 3.3-185

Secondary Containment Isolation Instrumentation B 3.3.6.2 BASES REFERENCES

6.

NEDC-30851P-A Supplement 2, "Technical Specifications (continued)

Improvement Analysis for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation," March 1989.

7.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

8.

NRC Safety Analysis Report for Amendment Proposed Quarterly B 3.3-186 HATCH UNIT I

LLS Instrumentation B 3.3.6.3 BASES SURVEILLANCE time required to perform channel surveillance.

That REQUIREMENTS analysis demonstrated that the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance (continued) does not significantly reduce the probability that the LLS valves will initiate when necessary.

SR 3.3.6.3.1 Performance of the CHANNEL CHECK once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ensures that a gross failure of instrumentation has not occurred.

A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on another channel.

It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value.

Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious.

A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with channels required by the LCO.

SR 3.3.6.3.2. SR 3.3.6.3.3. and SR 3.3.6.3.4 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units (if applicable), and Reference 5.

(continued)

Proposed Quarterly B 3.3-193 HATCH UNIT I

LLS Instrumentation B 3.3.6.3 BASES (continued)

REFERENCES

1.

FSAR, Section 7.19.

2.

FSAR, Section 4.11.

3.

GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications,"

February 1991.

4.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

5.

NRC Safety Evaluation Report for Amendment Proposed Quarterly HATCH UNIT I B 3.3-195

MCREC System Instrumentation B 3.3.7.1 BASES SURVEILLANCE SR 3.3.7.1.1 (continued)

REQUIREMENTS Agreement criteria are determined by the plant staff, based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channel status during normal operational use of the displays associated with channels required by the LCO.

SR 3.3.7.1.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The Frequency of 31 days is based on operating experience with regard to channel OPERABILITY and drift, which demonstrates that failure of more than one channel in any 31 day interval is a rare event.

SR 3.3.7.1.3 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency is based on a review of the surveillance test history and Reference 8.

(continued)

Proposed Quarterly B 3.3-201 HATCH UNIT 1

MCREC System Instrumentation B 3.3.7.1 BASES SURVEILLANCE REQUIREMENTS (continued)

REFERENCES SR 3.3.7.1.4 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel.

The system functional testing performed in LCO 3.7.4, "Main Control Room Environmental Control (MCREC)

System," overlaps this Surveillance to provide complete testing of the assumed safety function.

While this Surveillance can be performed with the reactor at power, operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

Therefore, the Frequency was found to be acceptable from a reliability standpoint.

I.

Unit 2 FSAR, Section 7.3.5

2.

FSAR, Section 5.2.

3.

Unit 2 FSAR, Section 6.4.1.2.2.

4.

FSAR, Chapter 14.

5.

Unit 2 FSAR, Table 15.1.28.

6.

GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications,"

February 1991.

7.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

8.

NRC Safety Evaluation Report for Amendment Proposed Quarterly B 3.3-202 HATCH UNIT 1

(LTTcg, -The Request to Revise Technical Specifications:

Quarterly Surveillance Extension Bases Page Change Instructions Unit 2 Page Instruction B 3.3-29 Replace B 3.3-32b Replace B 3.3-50 Replace B 3.3-53 Replace B 3.3-59 Replace B 3.3-60 Replace B 3.3-86 Replace B 3.3-89 Replace B 3.3-97 Replace B 3.3-98 Replace B 3.3-134 Replace B 3.3-135 Replace B 3.3-145 Replace B 3.3-146 Replace B 3.3-174 Replace B 3.3-175a Replace B 3.3-184 Replace B 3.3-185 Replace B 3.3-186 Replace B 3.3-193 Replace B 3.3-195 Replace B 3.3-201 Replace B 3.3-202 Replace HL-6224 04/02

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.9 and SR 3.3.1.1.12 REQUIREMENTS A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency of SR 3.3.1.1.9 is based on a review of the surveillance test history, drift analysis of the associated trip units (if applicable), and Reference 19.

The 18 month Frequency of SR 3.3.1.1.12 is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

The 18 month Frequency for Table 3.3.1.1-1, Function 7.a, is based on Reference 19.

SR 3.3.1.1.10 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

For the APRM Functions, this test supplements the automatic self-test functions that operate continuously in the APRM and voter channels.

The APRM CHANNEL FUNCTIONAL TEST covers the APRM channels (including recirculation flow processing -

applicable to Function 2.b only), the two-out-of-four voter channels, and the interface connections to the RPS trip systems from the voter channels.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 184 day Frequency of SR 3.1.1.1.10 is based on the reliability analysis of References 13 and 17.

(NOTE:

The actual voting logic of the two-out-of-four voter channels is tested as part of SR 3.3.1.1.15.)

For Function 2.a, a Note that requires this SR to be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of entering MODE 2 from MODE I is provided.

Testing of the MODE 2 APRM Function cannot be performed in MODE I without utilizing jumpers or lifted leads.

This Note allows entry into MODE 2 from MODE I if the associated Frequency is not met per SR 3.0.2.

(continued)

Proposed Quarterly HATCH UNIT 2 B 3.3-29

RPS Instrumentation B 3.3.1.1 BASES REFERENCES

4.

FSAR, Supplement 5A.

(continued)

5.

FSAR, Section 15.1.12.

6.

NEDO-23842, "Continuous Control Rod Withdrawal in the Startup Range," April 18, 1978.

7.

FSAR, Section 15.1.38.

8.

P. Check (NRC) letter to G. Lainas (NRC),

"BWR Scram Discharge System Safety Evaluation," December 1, 1980.

9. NEDO-30851-P-A, "Technical Specification Improvement Analyses for BWR Reactor Protection System, March 1988.
10.

Technical Requirements Manual.

11.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

12.

NEDO-32291, "System Analyses for Elimination of Selected Response Time Testing Requirements,"

January 1994.

13.

NEDC-32410P-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM)

Retrofit Plus Option III Stability Trip Function,"

October 1995.

14.

NEDO-31960-A, "BWR Owners' Group Long-Term Stability Solutions Licensing Methodology," November 1995.

15.

NEDO-31960-A, Supplement 1, "BWR Owners' Group Long Term Stability Sol utions Licensing Methodology,"

November 1995.

16.

NEDO-32465-A, "BWR Owners' Group Long-Term Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications," March 1996.

17.

NEDO-32410P-A, Supplement 1, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option III Stability Trip unction," November 1997.

18.

Letter? L.A. England (BWROG) to M.J. Virgilio, "BWR Owners Group Guidelines for Stability Interim Corrective Action," June 6, 1994.

19.

NRC Safety Evaluation Report for Amendment Proposed Quarterl y B 3.3-32b HATCH UNIT 2

Control Rod Block Instrumentation B 3.3.2.1 BASES SURVEILLANCE SR 3.3.2.1.1 REQUIREMENTS (continued)

A CHANNEL FUNCTIONAL TEST is performed for each RBM channel to ensure that the entire channel will perform the intended function.

It includes the Reactor Manual Control System input.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The Frequency of 184 days is based on reliability analyses (Ref. 11).

SR 3.3.2.1.2 and SR 3.3.2.1.3 A CHANNEL FUNCTIONAL TEST is performed for the RWM to ensure that the entire system will perform the intended function.

The CHANNEL FUNCTIONAL TEST for the RWM is performed by attempting to withdraw a control rod not in compliance with the prescribed sequence and verifying a control rod block occurs.

This test is performed as soon as possible after the applicable conditions are entered.

As noted in the SRs, SR 3.3.2.1.2 is not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after any control rod is withdrawn at < 10% RTP in MODE 2, and SR 3.3.2.1.3 is not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after THERMAL POWER is < 10% RTP in MODE 1. This allows entry into MODE 2 (and if entered during a shutdown, concurrent power reduction to < 10% RTP) for SR 3.3.2.1.2 and THERMAL POWER reduction to < 10% RTP in MODE 1 for SR 3.3.2.1.3 to perform the required Surveillances if the 92 day on a STAGGERED TEST BASIS Frequency is not met per SR 3.0.2.

The I hour allowance is based on operating experience and in consideration of providing a reasonable time in which to complete the SRs.

The 92 day on a STAGGERED TEST BASIS Frequency is based on a review of the surveillance test history and Reference 12.

SR 3.3.2.1.4 The RBM setpoints are automatically varied as a function of power.

Three Allowable Values are specified in Table 3.3.2.1-1, each within a specific power range.

The power at which the control rod block Allowable Values automatically change are based on the APRM signal's input to each RBM channel.

Below the minimum power setpoint, the RBM is automatically bypassed.

These power Allowable Values (continued)

Proposed Quarterly HATCH UNIT 2 B 3.3-50

Control Rod Block Instrumentation B 3.3.2.1 BASES SURVEILLANCE SR 3.3.2.1.8 (continued)

REQUIREMENTS OPERABLE following loading of sequence into RWM, since this is when rod sequence input errors are possible.

REFERENCES

1. FSAR, Section 7.6.2.2.5.
2.

FSAR, Section 7.6.8.2.6.

3.

NEDC-30474-P, "Average Power Range Monitor, Rod Block Monitor, and Technical Specification Improvements (ARTS)

Program for Edwin I. Hatch Nuclear Plants,"

December 1983.

4.

NEDE-24011-P-A-US, "General Electrical Standard Application for Reload Fuel," Supplement for United States, (revision specified in the COLR).

5.

Letter from T.A. Pickens (BWROG) to G.C. Lainas (NRC),

"Amendment 17 to General Electric Licensing Topical Report NEDE-24011-P-A,"

BWROG-8644, August 15, 1986.

6.

NEDO-21231, "Banked Position Withdrawal Sequence,"

January 1977.

7.

NRC SER, "Acceptance of Referencing of Licensing Topical Report NEDE-24011-P-A," "General Electric Standard Application for Reactor Fuel, Revision 8, Amendment 17," December 27, 1987.

8.

NEDC-30851-P-A, "Technical Specification Improvement Analysis for BWR Control Rod Block Instrumentation,"

October 1988.

9.

GENE-770-06-1, "Bases for Changes To Surveillance Test Intervals And Allowed Out-Of-Service Times For Selected Instrumentation Technical Specifications,"

February 1991.

10.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

11.

NEDC-32410P, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM)

Retrofit Plus Option III Stability Trip Function,"

October 1995.

12.

NRC Safety Evaluation Report for Amendment Proposed Quarterly HATCH UNIT 2 B 3.3-53

Feedwater and Main Turbine High Water Level Trip Instrumentation B 3.3.2.2 BASES SURVEILLANCE SR 3.3.2.2.1 (continued)

REQUIREMENTS logic from the input of the alarm unit.

This is consistent with the CHANNEL FUNCTIONAL TEST definition requiring the signal to be injected "as close to the sensor as practicable."

Additionally, due to the physical location of the turbine trip relays and their close proximity to other sensitive equipment, accessibility is extremely limited.

Verification of relay actuation and associated relay contact status by accessing the relay introduces a high potential for turbine trip and reactor scram.

One contact from each turbine trip relay energizes an amber light indicating relay actuation.

Therefore, it is acceptable to terminate the test at the turbine trip relay, utilizing light indication for relay status.

These allowances are only acceptable if the CHANNEL CALIBRATION and the LOGIC SYSTEM FUNCTIONAL TEST overlap both the initiation and termination point of this CHANNEL FUNCTIONAL TEST such that the entire trip logic is tested.

The 92 day on a STAGGERED TEST BASIS Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 4.

SR 3.3.2.2.2 CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The Frequency is based upon the assumption of an 18 month calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.2.2.3 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel. The system functional test of the feedwater and main turbine valves is included as part of this Surveillance and overlaps the LOGIC SYSTEM FUNCTIONAL TEST to provide (continued)

Proposed Quarterly B 3.3-59 HATCH UNIT 2

Feedwater and Main Turbine High Water Level Trip Instrumentation B 3.3.2.2 BASES SURVEILLANCE SR 3.3.2.2.3 (continued)

REQUIREMENTS complete testing of the assumed safety function.

Therefore, if a valve is incapable of operating, the associated instrumentation channels would also be inoperable.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

REFERENCES

1.

FSAR, Section 15.1.7.

2.

GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times for Selected Instrumentation Technical Specifications,"

February 1991.

3.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

4.

NRC Safety Evaluation Report for Amendment Proposed Quarterly HATCH UNIT 2 B 3.3-60

EOC-RPT Instrumentation B 3.3.4.1 BASES SURVEILLANCE analysis demonstrated that the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance does REQUIREMENTS not significantly reduce the probability that the (continued) recirculation pumps will trip when necessary.

SR 3.3.4.1.1 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency is based on a review of the surveillance test history and Reference 7.

SR 3.3.4.1.2 This SR ensures that an EOC-RPT initiated from the TSV -

Closure and TCV Fast Closure, Trip Oil Pressure -

Low Functions will not be inadvertently bypassed when THERMAL POWER is 2 28% RTP.

This involves calibration of the bypass channels.

Adequate margins for the instrument setpoint methodologies are incorporated into the actual setpoint.

Because main turbine bypass flow can affect this setpoint nonconservatively (THERMAL POWER is derived from first stage pressure) the main turbine bypass valves must remain closed during the calibration at THERMAL POWER a 28% RTP to ensure that the calibration is valid.

If any bypass channel's setpoint is nonconservative (i.e., the Functions are bypassed at

  • 28% RTP, either due to open main turbine bypass valves or other reasons), the affected TSV--Closure and TCV Fast Closure, Trip Oil Pressure -

Low Functions are considered inoperable.

Alternatively, the bypass channel can be placed in the conservative condition (nonbypass).

If placed in the nonbypass condition (Turbine Stop Valve-Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure-Low Functions are enabled), this SR is met with the channel considered OPERABLE.

The Frequency of 18 months is based on engineering judgment and the reliability of the components.

(continued)

Proposed Quarterly HATCH UNIT 2 B 3.3-86

EOC-RPT Instrumentation B 3.3.4.1 BASES REFERENCES (continued)

4.

GENE-770-06-1, "Bases For Changes To Surveillance Test Intervals And Allowed Out-Of-Service Times For Selected Instrumentation Technical Specifications,"

February 1991.

5.

Technical Requirements Manual.

6.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

7.

NRC Safety Evaluation Report for Amendment Proposed Quarterly I

HATCH UNIT 2 B 3.3-89

ATWS-RPT Instrumentation B 3.3.4.2 BASES SURVEILLANCE REQUIREMENTS SR 3.3.4.2.1 (continued)

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the channels required by the LCO.

SR 3.3.4.2.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency review of the surveillance test history, drift the associated trip units, and Reference 4.

is based on a analysis of SR 3.3.4.2.3 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The Frequency is based upon the assumption of an calibration interval in the determination of the of equipment drift in the setpoint analysis.

18 month magnitude (continued)

Proposed Quarterly B 3.3-97 HATCH UNIT 2

Instrumentati on B 3.3.4.2 SURVEILLANCE REQUIREMENTS (continued)

REFERENCES SR 3.3.4.2.4 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel.

The system functional test of the pump breakers is included as part of this Surveillance and overlaps the LOGIC SYSTEM FUNCTIONAL TEST to provide complete testing of the assumed safety function.

Therefore, if a breaker is incapable of operating, the associated instrument channel(s) would be inoperable.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

1.

FSAR, Section 7.6.10.7.

2.

GENE-770-06-1, "Bases for Changes To Surveillance Test Intervals and Allowed Out-of-Service Times For Selected Instrumentation Technical Specifications,"

February 1991.

3.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

4.

NRC Safety Evaluation Report for Amendment __

Proposed Quarterly BASES ATWS-RPT I

HATCH UNIT 2 B 3.3-98

ECCS Instrumentation B 3.3.5.1 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 3.3.5.1.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency review of the surveillance test history, drift the associated trip units, and Reference 7.

is based on a analysis of SR 3.3.5.1.3 and SR 3.3.5.1.4 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The Frequency of SR 3.3.5.1.3 and SR 3.3.5.1.4 is based upon the assumption of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.5.1.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel.

The system functional testing performed in LCO 3.5.1, LCO 3.5.2, LCO 3.7.2, LCO 3.8.1, and LCO 3.8.2 overlaps this Surveillance to complete testing of the assumed safety function.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

(continued)

Proposed Quarterly HATCH UNIT 2 B 3.3-134

ECCS Instrumentation B 3.3.5.1 BASES (continued)

REFERENCES

1.

FSAR, Section 5.2.

2.

FSAR, Section 6.3.

3.

FSAR, Chapter 15.

4.

NEDC-31376-P, "Edwin I. Hatch Nuclear Power Plant, SAFER/GESTR-LOCA, Loss-of-Coolant Accident Analysis,"

December 1986.

5.

NEDC-30936-P-A, "BWR Owners' Group Technical Specification Improvement Analyses for ECCS Actuation Instrumentation, Part 2," December 1988.

6.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

7.

NRC Safety Evaluation Report for Amendment Proposed Quarterly HATCH UNIT 2 B 3.3-135

RCIC System Instrumentation B 3.3.5.2 BASES SURVEILLANCE SR 3.3.5.2.1 (continued)

REQUIREMENTS channels monitoring the same parameter should read approximately the same value.

Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious.

A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the channels required by the LCO.

SR 3.3.5.2.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 3.

SR 3.3.5.2.3 and SR 3.3.5.2.4 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

(continued)

Proposed Quarterly HATCH UNIT 2 B 3.3-145

RCIC System Instrumentation B 3.3.5.2 BASES SURVEILLANCE REQUIREMENTS SR 3.3.5.2.3 and SR 3.3.5.2.4 (continued)

The Frequency of SR 3.3.5.2.3 and SR 3.3.5.2.4 is based upon the assumption of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.5.2.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel.

The system functional testing performed in LCO 3.5.3 overlaps this Surveillance to provide complete testing of the safety function.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

REFERENCES

1.

GENE-770-06-2, "Addendum to Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," February 1991.

2.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

3.

NRC Safety Evaluation Report for Amendment Proposed Quarterly I

HATCH UNIT 2 B 3.3-146

Primary Containment Isolation Instrumentation B 3.3.6.1 BASES SURVEILLANCE SR 3.3.6.1.2 and SR 3.3.6.1.4 (continued)

REQUIREMENTS The 92 day on a STAGGERED TEST BASIS Frequency of SR 3.3.6.1.2 is based on a review of the surveillance test history, drift analysis of the associated trip units (if applicable), and Reference 9.

The 184 day Frequency of SR 3.3.6.1.4 is based on engineering judgment and the reliability of the components (time delay relays exhibit minimal drift).

SR 3.3.6.1.3 and SR 3.3.6.1.5 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency of SR 3.3.6.1.3 is based on a review of the surveillance test history, drift analysis of the associated pressure (or vacuum) switches (if applicable), and Reference 9.

The Frequency of SR 3.3.6.1.5 is based on the assumption of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.6.1.6 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel.

The system functional testing performed on PCIVs in LCO 3.6.1.3 overlaps this Surveillance to provide complete testing of the assumed safety function.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

(continued)

Proposed Quarterly HATCH UNIT 2 B 3.3-174

Primary Containment Isolation Instrumentation B 3.3.6.1 BASES REFERENCES (continued)

6.

Technical Requirements Manual.

7.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

8.

NEDO-32291, "System Analyses for Elimination of Selected Response Time Testing Requirements,"

January 1994.

9.

NRC Safety Evaluation Report for Amendment Proposed Quarterly I

B 3.3-175a HATCH UNIT 2

Secondary Containment Isolation Instrumentation B 3.3.6.2 BASES SURVEILLANCE average time required to perform channel surveillance.

That REQUIREMENTS analysis demonstrated the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance does not (continued) significantly reduce the probability that the SCIVs will isolate the associated penetration flow paths and that the SGT System will initiate when necessary.

SR 3.3.6.2.1 Performance of the CHANNEL CHECK once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ensures that a gross failure of instrumentation has not occurred.

A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels.

It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value.

Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious.

A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria; it may be an indication that the instrument has drifted outside its limit.

The Frequency is based on operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channel status during normal operational use of the displays associated with channels required by the LCO.

SR 3.3.6.2.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 8.

(continued)

Proposed Quarterly HATCH UNIT 2 B 3.3-184

Secondary Containment Isolation Instrumentation B 3.3.6.2 BASES SURVEILLANCE REQUIREMENTS (continued)

REFERENCES SR 3.3.6.2.3 and SR 3.3.6.2.4 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency of SR 3.3.6.2.3 is based on a review of the surveillance test history and Reference 8.

The Frequency of SR 3.3.6.2.4 is based on the assumption of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.6.2.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel.

The system functional testing performed on SCIVs and the SGT System in LCO 3.6.4.2 and LCO 3.6.4.3, respectively, overlaps this Surveillance to provide complete testing of the assumed safety function.

While this Surveillance can be performed with the reactor at power for some of the Functions, operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

Therefore, the Frequency was found to be acceptable from a reliability standpoint.

1.

FSAR, Section 6.3.

2.

FSAR, Chapter 15.

3.

FSAR, Section 15.1.40.

4.

FSAR, Sections 15.1.39 and 15.1.41.

5.

NEDC-31677P-A, "Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation,"

July 1990.

(continued)

Proposed Quarterly HATCH UNIT 2 B 3.3-185

Secondary Containment Isolation Instrumentation B 3.3.6.2 BASES REFERENCES

6.

NEDC-30851P-A Supplement 2, "Technical Specifications (continued)

Improvement Analysis for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation," March 1989.

7.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

8.

NRC Safety Evaluation Report for Amendment Proposed Quarterly I

HATCH UNIT 2 B 3.3-186

LLS Instrumentation B 3.3.6.3 BASES SURVEILLANCE time required to perform channel surveillance.

That REQUIREMENTS analysis demonstrated that the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance (continued) does not significantly reduce the probability that the LLS valves will initiate when necessary.

SR 3.3.6.3.1 Performance of the CHANNEL CHECK once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ensures that a gross failure of instrumentation has not occurred.

A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on another channel.

It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value.

Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious.

A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with channels required by the LCO.

SR 3.3.6.3.2. SR 3.3.6.3.3. and SR 3.3.6.3.4 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units (if applicable), and Reference 5.

(continued)

Proposed Quarterly HATCH UNIT 2 B 3.3-193

LLS Instrumentation B 3.3.6.3 BASES (continued)

REFERENCES

1.

FSAR, Section 7.4.4.

2.

FSAR, Section 5.5.17.

3.

GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications,"

February 1991.

4.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

5.

NRC Safety Evaluation Report for Amendment Proposed Quarterly HATCH UNIT 2 B 3.3-195

MCREC System Instrumentation B 3.3.7.1 BASES SURVEILLANCE SR 3.3.7.1.1 (continued)

REQUIREMENTS Agreement criteria are determined by the plant staff, based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channel status during normal operational use of the displays associated with channels required by the LCO.

SR 3.3.7.1.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The Frequency of 31 days is based on operating experience with regard to channel OPERABILITY and drift, which demonstrates that failure of more than one channel in any 31 day interval is a rare event.

SR 3.3.7.1.3 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The 92 day on a STAGGERED TEST BASIS Frequency is based on a review of the surveillance test history and Reference 8.

(continued)

Proposed Quarterly HATCH UNIT 2 B 3.3-201

MCREC System Instrumentation B 3.3.7.1 BASES SURVEILLANCE REQUIREMENTS (continued)

REFERENCES SR 3.3.7.1.4 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel.

The system functional testing performed in LCO 3.7.4, "Main Control Room Environmental Control (MCREC)

System," overlaps this Surveillance to provide complete testing of the assumed safety function.

While this Surveillance can be performed with the reactor at power, operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

Therefore, the Frequency was found to be acceptable from a reliability standpoint.

1.

FSAR, Section 7.3.5

2.

FSAR, Chapter 6.

3.

FSAR, Section 6.4.1.2.2.

4.

FSAR, Chapter 15.

5.

FSAR, Table 15.1.28.

6.

GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications,"

February 1991.

7.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

8.

NRC Safety Evaluation Report for Amendment Proposed Quarterly I

HATCH UNIT 2 B 3.3-202

0 Edwin I. Hatch Nuclear Plant Request to Revise Technical Specifications:

Quarterly Surveillance Extension Marked-Up Bases Paaes HL-6224 04/02

(i ýA-x 1 --tým

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.9 and SR 3.3.1.1.12 REQUIREMENTS (continued)

A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of e current nlant spiecific setpoint methodology J***d*F ag~**/

Ois~a~se" R 3.3. 1. 1./1 The 18 month Frequencyfis based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month r *

  • Frequency.

e SR 3.3.1.1.10 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

For the APRM Functions, this test supplements the automatic self-test functions that operate continuously in the APRM and voter channels.

The APRM CHANNEL FUNCTIONAL TEST covers the APRM channels (including recirculation flow processing -

applicable to Function 2.b only), the two-out-of-four voter channels, and the interface connections to the RPS trip systems from the voter channels.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 184 day Frequency of SR 3.3.1.1.10 is based on the reliability analysis of References 12 and 16.

(NOTE:

The actual, voting logic of the two-out-of-four voter channels is tested as part of SR 3.3.1.1.15.)

For Function 2.a, a Note that requires this SR to be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of entering MODE 2 from MODE 1 is provided.

Testing of the MODE 2 APRM Function cannot be performed in MODE 1 without utilizing jumpers or lifted leads.

This Note allows entry into MODE 2 from MODE I if the associated Frequency is not met per SR 3.0.2.

(continued)

HATCH UNIT I B 3.3-29 REVISION 16

RPS Instrumentation B 3.3.1.1 BASES REFERENCES (continued)

9.

NEDO-30851-P-A, "Technical Specification Improvement Analyses for BWR Reactor Protection System,"

March 1988.

10.

Technical Requirements Manual.

11.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

12.

NEDC-32410P-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM)

Retrofit Plus Option III Stability Trip Function,"

October 1995.

13.

NEDO-31960-A, "BWR Owners' Group Long-Term Stability Solutions Licensing Methodology," November 1995.

14.

NEDO-31960-A, Supplement 1, "BWR Owners' Group Long Term Stability Solutions Licensing Methodology,"

November 1995.

15.

NEDO-32465-A, "BWR Owners' Group Long-Term Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications," March 1996.

16.

NEDO-32410P-A, Supplement 1, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option III Stability Trip Function," November 1997.

17.

Letter, L.A. England (BWROG) to M.J. Virgilio, Owners' Group Guidelines for Stability Interim

_rn~scr ý ei-Corrective Action," June 6, 1994.

"BWR HATCH UNIT I B 3.3-32b REVISION 16

Section B 3.3.1.1 Inserts Insert A:

The +8+-dW Frequency of SR 3.3.1.1.9 is based on a review of the surveillance test history, drift analysis of the associated trip units (if applicable), and Reference 18.

Insert B:

The 18 month Frequency for Table 3.3.1.1-1, Function 7.a, is based on Reference 18.

Insert C:

18.

NRC Safety Evaluation Report for Amendment

Control Rod Block Instrumentation B 3.3.2.1 BASES SURVEILLANCE SR 3.3.2.1.1 REQUIREMENTS (continued)

A CHANNEL FUNCTIONAL TEST is performed for each RBM channel to ensure that the entire channel will perform the intended function.

It includes the Reactor Manual Control System input.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The Frequency of 184 days is based on reliability analyses (Ref. 11).

SR 3.3.2.1.2 and SR 3.3.2.1.3 A CHANNEL FUNCTIONAL TEST is performed for the RWM to ensure that the entire system will perform the intended function.

The CHANNEL FUNCTIONAL TEST for the RWM is performed by attempting to withdraw a control rod not in compliance with the prescribed sequence and verifying a control rod block occurs.

This test is performed as soon as possible after the applicable conditions are entered.

As noted in the SRs, SR 3.3.2.1.2 is not required to be performed until I hour after any control rod is withdrawn at < 10% RTP in MODE 2, and SR 3.3.2.1.3 is not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after THERMAL POWER is < 10% RTP in MODE 1.

This allows entry into MODE 2 (and if entered during a shutdown, concurrent power reduction to.< 10% RTP) for SR 3.3.2.1.2 and THERMAL POWER reduction to < 10% RTP in MODE 1 for S-.3.2.1.3 to perform the required Surveillances if the 92 daf Frequency is not met per SR 3.0.2.

The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> on C rT¢Z;Z46 b

allowance is based on operating experience and in

-AVAS-S*

consideration of providing a reasonable time in which to Corn la e

h ~eT e/ a e

The RBM setpoints are automatically varied as a function of power.

Three Allowable Values are specified in Table 3.3.2.1-1, each within a specific power range.

The power-at which the control rod block Allowable Values automatically change are based on the APRM signal's input to each RBM channel.

Below the minimum power setpoint, the RBM is automatically bypassed.

These power Allowable Values (continued)

B 3.3-50 HATCH UNIT 1 REVISION 14

Control Rod Block Instrumentati on B 3.3.2.1 SURVEILLANCE SR 3.3.2.1.8 (continued)

REQUIREMENTS OPERABLE following loading of sequence into RWM, since this is when rod sequence input errors are possible.

REFERENCES

1.

FSAR, Section 7.5.8.2.3.

2.

FSAR, Section 7.2.2.4.

3.

NEDC-30474-P, "Average Power Range Monitor, Rod Block Monitor, and Technical Specification Improvements (ARTS)

Program for Edwin I. Hatch Nuclear Plants,"

December 1983.

4.

NEDE-24011-P-A-US, "General Electrical Standard Application for Reload Fuel," Supplement for United States, (revision specified in the COLR).

5.

Letter from T.A. Pickens (BWROG) to G.C. Lainas (NRC),

"Amendment 17 to General Electric Licensing Topical Report NEDE-24011-P-A,"

BWROG-8644, August 15, 1986.

6.

NEDO-21231, "Banked Position Withdrawal Sequence,"

January 1977.

7.

NRC SER, "Acceptance of Referencing of Licensing Topical Report NEDE-24011-P-A," "General Electric Standard Application for Reactor Fuel, Revision 8, Amendment 17," December 27, 1987.

8.

NEDC-30851-P-A, "Technical Specification Improvement Analysis for BWR Control Rod Block Instrumentation,"

October 1988.

9. GENE-770-06-1, "Bases For Changes To Surveillance Intervals and Allowed Out-Of-Service Times For Selected Instrumentation Technical Specifications, February 1991.

Test It

10.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

(gekArnce-12

11.

NEDC-32410P-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM)

Retrofit Plus Option III Stability Trip Function, October 1995.

HATCH UNIT 3

BASES 8 3.3-53 if L--Ikl REVISION 14

Section B 3.3.2.1 Inserts Insert A:

q2 d~t_

=

.6,S a~v,4EXee 71557 KAI5 The 1-84-dyFrequency is based on a review of the surveillance test history and Reference 12.

Insert B:

12.

NRC Safety Evaluation Report for Amendment__

Feedwater and Main Turbine High Water Level Trip Instrumentation B 3.3.2.2 BASES SURVEILLANCE SR 3.3.2.2.1 (continued)

REQUIREMENTS logic from the input of the alarm unit.

This is consistent with the CHANNEL FUNCTIONAL TEST definition requiring the signal to be injected "as close to the sensor as practicable."

Additionally, due to the physical location of the turbine trip relays and their close proximity to other sensitive equipment, accessibility is extremely limited.

Verification of relay actuation and associated relay contact status by accessing the relay introduces a high potential for turbine trip and reactor scram.

One contact from each turbine trip relay energizes an amber light indicating relay actuation.

Therefore, it is acceptable to terminate the test at the turbine trip relay, utilizing light indication for relay status.

These allowances are only acceptable if the CHANNEL CALIBRATION and the LOGIC SYSTEM FUNCTIONAL TEST overlap both the initiation and termination point of this CHANNEL FUNCTIONAL TEST such that the entire trip logic is tested.

SR 3.3.2.2.2 CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The Frequency is based upon the assumption of an 18 month calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.2.2.3 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel. The system functional test of the feedwater and main turbine valves is included as part of this Surveillance and overlaps the LOGIC SYSTEM FUNCTIONAL TEST to provide (continued)

REVISION I HATCH UNIT 1 8 3.3-59

Feedwater and Main Turbine High Water Level Trip Instrumentation B 3.3.2.2 BASES SURVEILLANCE REQUIREMENTS SR 3.3.2.2.3 (continued) complete testing of the assumed safety function.

Therefore, if a valve is incapable of operating, the associated instrumentation channels would also be inoperable.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

REFERENCES

1.

FSAR, Section 14.3.2.1.

2.

GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times for Selected Instrumentation Technical Specifications,"

February 1991.

3.

NRC No.93-102, "Final Policy Statement on Technical TV-.ScI-23 Specification Improvements," July 23, 1993.

HATCH UNIT I 8 3.3-60 REVISION I

Section B 3.3.2.2 Inserts Insert A:

57A6 ov The 184 dFrequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 4.

Insert B:

4.

NRC Safety Evaluation Report for Amendment

EOC-RPT Instrumentation B 3.3.4.1 BASES SURVEILLANCE analysis demonstrated that the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance REQUIREMENTS does not significantly reduce the probability that the (continued) recirculation pumps will trip when necessary.

SR 3.3.4.1.1 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

ns r-n y f

2 si y

SR 3.3.4.1.2 This SR ensures that an EOC-RPT initiated from the TSV -

Closure and TCV Fast Closure, Trip Oil Pressure -

Low Functions will not be inadvertently bypassed when THERMAL POWER is z 28% RTP.

This involves calibration of the bypass channels.

Adequate margins for the instrument setpoint methodologies are incorporated into the actual setpoint.

Because main turbine bypass flow can affect this setpoint nonconservatively (THERMAL POWER is derived from first stage pressure) the main turbine bypass valves must remain closed during the calibration at THERMAL POWER a 28% RTP to ensure that the calibration is valid.

If any bypass channel's setpoint is nonconservative (i.e., the Functions are bypassed at a 28% RTP, either due to open main turbine bypass valves or other reasons), the affected TSV -

Closure and TCV Fast Closure, Trip Oil Pressure -

Low Functions are considered inoperable.

Alternatively, the bypass channel can be placed in the conservative condition (nonbypass).

If placed in the nonbypass condition (Turbine Stop Valve-Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure-Low Functions are enabled), this SR is met with the channel considered OPERABLE.

The Frequency of 184 days is based on engineering judgment and reliability of the components.

(continued)

REVISION 16 HATCH UNIT I B 3.3-86

EOC-RPT Instrumentation B 3.3.4.1 BASES REFERENCES

4.

GENE-770-06-1, "Bases For Changes To Surveillance Test (continued)

Intervals And Allowed Out-Of-Service Times For Selected Instrumentation Technical Specifications,"

February 1991.

5.

Technical Requirements Manual.

6.

NRC No.93-102, "Final Policy Statement on Technical

.-,setr-23 Specification Improvements," July 23, 1993.

(Re 4ýre-n e-7)'

HATCH UNIT I B 3.3-89 REVISION I

Section B 3.3.4.1 Inserts Insert A:

q-2 a.ý 57AýC44c6.e' 7--S7-6ASLS The 1-04 Frequency is based on a review of the surveillance test history and Reference 7.

Insert B:

7.

NRC Safety Evaluation Report for Amendment

ATWS-RPT Instrumentation B 3.3.4.2 BASES SURVEILLANCE REQUIREMENTS SR 3.3.4.2.1 (continued)

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the channels required by the LCO.

SR 3.3.4.2.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

Fr q n 2

1* se o th i

i SR 3.3.4.2.3 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

ITncýA The Frequency is based upon the assumption of an calibration interval in the determination of the of equipment drift in the setpoint analysis.

18 month magnitude (continued)

REVISION 1 HATCH UNIT 1 B 3.3-97

ATWS-RPT Instrumentati on 8 3.3.4.2 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 3.3.4.2.4 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel.

The system functional test of the pump breakers is included as part of this Surveillance and overlaps the LOGIC SYSTEM FUNCTIONAL TEST to provide complete testing of the assumed safety function.

Therefore, if a breaker is incapable of operating, the associated instrument channel(s) would be inoperable.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

REF11RENCES I.

FSAR, Section 7.23.

2.

GENE-770-06-1,

'Bases for Changes To Surveillance Test Intervals and Allowed Out-of-Service Times For Selected Instrumentation Technical Specifications,"

February 1991.

"3.

NRC No.93-102, *Final Policy Statement on Technical 2,-*s~c+ ~Specification Improvements," July 23, 1993.

HATCH UNIT 1 B 3.3-98 REVISION I

Section B 3.3.4.2 Inserts Insert A:

7" The 184 dy Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 4.

Insert B:

4.

NRC Safety Evaluation Report for Amendment

ECCS Instrumentation B 3.3.5.1 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 3.3.5.-1.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

_O.Xn e-r-f n re on r9 i

s nth r i i t SR 3.3.5.1.3 and SR 3.3.5.1.4 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The Frequency of SR 3.3.5.1.3 and SR 3.3.5.1.4 is based upon the assumption of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.5.1.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel.

The system functional testing performed in LCO 3.5.1, LCO 3.5.2, LCO 3.7.2, LCO 3.8.1, and LCO 3.8.2 overlaps this Surveillance to complete testing of the assumed safety function.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

(continued)

REVISION I B 3.3-134 HATCH UNIT I

ECCS Instrumentation B 3.3.5.1 BASES (continued)

REFERENCES

1. FSAR, Section 4.8.
2.

FSAR, Section 6.5.

3.

FSAR, Chapter 14.4.

4.

- NEDC-31376-P, "Edwin I. Hatch Nuclear Power Plant, SAFER/GESTR-LOCA, Loss-of-Coolant Accident Analysis,"

December 1986.

5.

NEDC-30936-P-A, "BWR Owners' Group Technical Specification Improvement Analyses for ECCS Actuation Instrumentation, Part 2," December 1988.

6.

NRC No.93-102, "Final Policy Statement on Technical "Specification Improvements," July 23, 1993.

(7?Ferencc 7)'-'

HATCH UNIT I B 3.3-135 REVISION I

Section B 3.3.5.1 Inserts Insert A:

qT 2 y

s ba se d o a r e f6 s

The -84 da Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 7.

Insert B:

7.

NRC Safety Evaluation Report for Amendment

RCIC System Instrumentation B 3.3.5.2 BASES SURVEILLANCE SR 3.3.5.2.1 (continued)

REQUIREMENTS channels monitoring the same parameter should read approximately the same value.

Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious.

A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the channels required by the LCO.

SR 3.3.5.2.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

T/

)e *e ue yf/2

  • a i

b*

/

t e

/li X-n. 5e-A P

naysf f e e.

7!0)

SR 3.3.5.2.3 and SR 3.3.5.2.4 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodol ogy.

(continued)

HATCH UNIT B8 3.3-145 REVISION I

RCIC System Instrumentation B 3.3.5.2 BASES SURVEILLANCE REQUIREMENTS SR 3.3.5.2.3 and SR 3.3.5.2.4 (continued)

The Frequency of SR 3.3.5.2.3 and SR 3.3.5.2.4 is based upon the assumption of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.5.2.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel.

The system functional testing performed in LCO 3.5.3 overlaps this Surveillance to provide complete testing of the safety function.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

REFERENCES

1.

GENE-770-06-2, "Addendum to Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications,'

February 1991.

2.

NRC No.93-102, "Final Policy Statement on Technical Xn.se-r+ B--*

Specification Improvements," July 23, 1993.

HATCH UNIT I B 3.3-146 REVISION I

Section B 3.3.5.2 Inserts Insert A:

The 184 day Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 3.

Insert B:

3.

NRC Safety Evaluation Report for Amendment

Primary Containment Isolation Instrumentation B 3.3.6.1 BASES SURVEILLANCE SR 3.3.6.1.2 and SR 3.3.6.1.4 (continued)

REQUIREMENTS r

-.- z Te ay F q

n f

.3

.2s e

184 day Frequency of SR 3.3.6.1.4 is based on engineering judgment and the reliability of the components (time delay relays exhibit minimal drift).

SR 3.3.6.1.3 and SR 3.3.6.1.5 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

rn*seri

.23 --

The Frequency of SR 3.3.6.1.5 is based on the assumption of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.6.1.6 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel.

The system functional testing performed on PCIVs in LCO 3.6.1.3 overlaps this Surveillance to provide complete testing of the assumed safety function.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

(continued)

REVISION 1 HATCH UNIT I B 3.3-174

Primary Containment Isolation Instrumentation B 3.3.6.1 BASES (continued)

REFERENCES

1.

FSAR, Section 5.2.

2.

FSAR, Chapter 14.

3.

FSAR, Section 3.8.3.

4.

NEDC-31677P-A, "Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation,"

July 1990.

S.

NEDC-30851P-A Supplement 2, "Technical Specifications Improvement Analysis for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation," March 1989.

6.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

(Rekewe 7)7 HATCH UNIT 1 B 3.3-175 REVISION I

Section B 3.3.6.1 Inserts Inser dA..

The Frequency of SR 3.3.6.1.2 is based on a review of the surveillance test history, drift analysis of the associated trip units (if applicable), and Reference 7.

Insert B:

The 1-84-day Freqlency of SR 3.3.6.1.3 is based on a review of the surveillance test history, drift analysis of the associated pressure (or vacuum) switches (if applicable), and Reference 7.

Insert C:

7.

NRC Safety Evaluation Report for Amendment

Secondary Containment Isolation Instrumentation B 3.3.6.2 BASES SURVEILLANCE average time required to perform channel surveillance.

That REQUIREMENTS analysis demonstrated the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance does not (continued) significantly reduce the probability that the SCIVs will isolate the associated penetration flow paths and that the SGT System will initiate when necessary.

SR 3.3.6.2.1 Performance of the CHANNEL CHECK once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ensures that a gross failure of instrumentation has not occurred.

A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels.

It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value.

Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious.

A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based on operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channel status during normal operational use of the displays associated with channels required by the LCO.

SR 3.3.6.2.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

-(o t i nued (continued)

REVISION I HATCH UNIT 1 B 3.3-184

Secondary Containment Isolation Instrumentation B 3.3.6.2 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 3.3.6.2.3 and SR 3.3.6.2.4 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint me tho do liogy.

5

.JZ et" -

.,.......-..The Frequenc of @ZMR;K d SR 3.3.6.2.4 (a based on the assumpion of the magnitude of equipment dri-it in the setpoint analysis.

SR 3.3.6.2.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel.

The system functional testing performed on SCIVs and the SGT System in LCO 3.6.4.2 and LCO 3.6.4.3, respectively, overlaps this Surveillance to provide complete testing of the assumed safety function.

While this Surveillance can be performed with the reactor at power for some of the Functions, operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

Therefore, the Frequency was found to be acceptable from a reliability standpoint.

REFERENCES

1.

FSAR, Section 5.2.

2.

FSAR, Chapter 14.4.

3.

FSAR, Sections 14.4.5 and 14.5.4.

4.

FSAR, Sections 14.4.3, 14.4.4, 14.5.2, and 14.5.3.

5.

NEDC-31677P-A, 'Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation,"

July 1990.

(continued)

REVISION I HATCH UNIT I B 3.3-185

Secondary Containment Isolation Instrumentation B 3.3.6.2 BASES REFERENCES

6.

NEDC-30851P-A Supplement 2, *Technical Specifications (continued)

Improvement Analysis for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation," March 1989.

7.

NRC No.93-102, *Final Policy Statement on Technical Specification Improvements," July 23, 1993.

HATCH UNIT 1 B 3(3-186 REVISION I

Section B 3.3.6.2 Inserts Insert A:

The 464-deA Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 8.

Insert B:

The 1-84-day F*quency of SR 3.3.6.2.3 is based on a review of the surveillance test history and Reference 8.

Insert C:

8.

NRC Safety Evaluation Report for Amendment

LLS Instrumentation B 3.3.6.3 BASES SURVEILLANCE time required to perform channel surveillance.

That REQUIREMENTS analysis demonstrated that the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance (continued) does not significantly reduce the probability that the LLS valves will initiate when necessary.

SR 3.3.6.3.1 Performance of the CHANNEL CHECK once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ensures that a gross failure of instrumentation has not occurred.

A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on another channel.

It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value.

Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious.

A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with channels required by the LCO.

SR 3.3.6.3.2. SR 3.3.6.3.3. and SR 3.3.6.3.4 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

e 2

F q n

i b e o

t e el Ii al s f

e r e n (continued)

HATCH UNIT I B 3.3-193 REVISION I

LLS Instrumentati on B 3.3.6.3 BASES (continued)

REFERENCES

1.

FSAR, Section 7.19.

2.

FSAR, Section 4.11.

3.

GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications,"

February 1991.

JJse,-+.23 (Rjevee'we 57-

4.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

REVISION 1 HATCH UNIT 1 B 3.3-195

Section B 3.3.6.3 Inserts Insert A:

The 1-84 de Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units (if applicable), and Reference 5.

Insert B:

5.

NRC Safety Evaluation Report for Amendment

MCREC System Instrumentation B 3.3.7.1 BASES SURVEILLANCE SR 3.3.7.1.1 (continued)

REQUIREMENTS Agreement criteria are determined by the plant staff, based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channel status during normal operational use of the displays associated with channels required by the LCO.

SR 3.3.7.1.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The Frequency of 31 days is based on operating experience with regard to channel OPERABILITY and drift, which demonstrates that failure of more than one channel in any 31 day interval is a rare event.

SR 3.3.7.1.3 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

/'*fe Feo Jen* *"se*

u n

h as) m -o-of Lej~nfuf uaserf A

f q*m t if i e etoi a 1 is.

(continued)

REVISION I HATCH UNIT 1 B 3.3-201

MCREC System Instrumentation B 3.3.7.1 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 3.3.7.1.4 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel.

The system functional testing performed in LCO 3.7.4, "Main Control Room Environmental Control (MCREC)

System," overlaps this Surveillance to provide complete testing of the assumed safety function.

While this Surveillance can be performed with the reactor at power, operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

Therefore, the Frequency was found to be acceptable from a reliability standpoint.

REFERENCES

1.

Unit 2 FSAR, Section 7.3.5

2.

FSAR, Section 5.2.

3.

Unit 2 FSAR, Section 6.4.1.2.2.

4.

FSAR, Chapter 14.

5.

Unit 2 FSAR, Table 15.1.28.

6.

GENE-770-06-1,

'Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications,"

February 1991.

7.

NRC No.93-102, *Final Policy Statement on Technical

  • nsP_

Specification Improvements,* July 23, 1993.

(A-f-drenre.e SN A

HATCH UNIT I 8 3.3-202 REVISION 1

Section B 3.3.7.1 Inserts Insert A:

71-=57 5 The 1 Frequency is based on a review of the surveillance test history and Reference 8.

Insert B:

8.

NRC Safety Evaluation Report for Amendment

T-fvb

RPS Instrumentation B 3.3.1.1 BASES SURVEILLANCE SR 3.3.1.1.9 and SR 3.3.1.1.12 REQUIREMENTS A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoi nt methodol ogy~~h e'/i**e

-ý*/6

-T n se-rSP F R 3.3 The 18 month Frequencybis based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency SR 3.3.1.1,10 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

For the APR1 Functions, this test supplements the automatic self-test functions that operate continuously in the APR4 and voter channels.

The APRP4 CHANNEL FUNCTIONAL TEST covers the APRP4 channels (including recirculation flow processing--applicable to Function 2.b only), the two-out-of-four voter channels, and the interface connections to the RPS trip systems from the voter channels.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The 184 day Frequency of SR 3.1.1.1.10 is based on the reliability analysis of References 13 and 17.

(NOTE:

The actual voting logic of the two-out-of-four voter channels is tested as part of SR 3.3.1.1.15.)

For Function 2.a, a Note that requires this SR to be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of entering MODE 2 from MODE 1 is provided.

Testing of the MODE 2 APR14 Function cannot be performed in MODE 1 without utilizing jumpers or lifted leads.

This Note allows entry into MODE 2 from MODE I if the associated Frequency is not met per SR 3.0.2.

(continued)

B 3.3-29 HATCH UNIT 2 REVISION 21

RPS Instrumentation B 3.3.1.1 BASES REFERENCES

4.

FSAR, Supplement 5A.

(continued)

5.

FSAR, Section 15.1.12.

6.

NEDO-23842, "Continuous Control Rod Withdrawal in the Startup Range," April 18, 1978.

7.

FSAR, Section 15.1.38.

8.

P. Check (NRC) letter to G. Lainas (NRC),

"BWR Scram Discharge System Safety Evaluation," December 1, 1980.

9.

NEDO-30851-P-A, "Technical Specification Improvement Analyses for BWR Reactor Protection System,"

March 1988.

10.

Technical Requirements Manual.

11.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

12.

NEDO-32291, "System Analyses for Elimination of Selected Response Time Testing Requirements,"

January 1994.

13.

NEDC-32410P-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC.PRNM)

Retrofit Plus Option III Stability Trip Function,"

October 1995.

14.

NEDO-31960-A, "BWR Owners' Group Long-Term Stability Solutions Licensing Methodology," November 1995.

15.

NEDO-31960-A, Supplement 1, "BWR Owners' Group Long Term Stability Solutions Licensing Methodology,"

November 1995.

16.

NEDO-32465-A, "BWR Owners' Group Long-Term Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications," March 1996.

17.

NEDO-32410P-A, Supplement 1, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNN) Retrofit Plus Option III Stability Trip Function," November 1997.

18.

Letter, L.A. England (BWROG) to M.J. Virgilio, "BWR Owners Group Guidelines for Stability Interim

=1?5er-r Corrective Action," June 6, 1994.

(Rte4ýeence 1q)

B 3.3-32b HATCH UNIT 2 REVISION 21

Section B 3.3.1.1 Inserts Insert A:

The,84-day Frequency of SR 3.3.1.1.9 is based on a review of the surveillance test history, drift analysis of the associated trip units (if applicable), and Reference 19.

Insert B:

The 18 month Frequency for Table 3.3.1.1-1, Function 7.a, is based on Reference 19.

Insert C:

19.

NRC Safety Evaluation Report for Amendment __

Control Rod Block Instrumentation B 3.3.2.1 BASES SURVEILLANCE SR 3.3.2.1.1 REQUIREMENTS (continued)

A CHANNEL FUNCTIONAL.TEST is performed for each RBM channel to ensure that the entire channel will perform the intended function.

It includes the Reactor Manual Control System input.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The Frequency of 184 days is based on reliability analyses (Ref.

11).

SR 3.3.2.1.2 and SR 3.3.2.1.3 A CHANNEL FUNCTIONAL TEST is performed for the RWM to ensure that the entire system will perform the intended function.

The CHANNEL FUNCTIONAL TEST for the RWI4 is performed by attempting to withdraw a control rod not in compliance with the prescribed sequence and verifying a control rod block occurs.

This test is performed as soon as possible after the applicable conditions are entered.

As noted in the SRs, SR 3.3.2.1.2 is not required to be performed until I hour after any control rod is withdrawn at < 10% RTP in MODE 2, and SR 3.3.2.1.3 is not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after THERMAL POWER is < 10% RTP in MODE 1.

This allows entry into MODE 2 (and if entered during a shutdown, concurrent power reduction to < 10% RTP) for SR 3.3.2.1.2 and THERMAL POWER reduction to < 10% RTP in MODE 1 for SR 3.3.2.1.3 to perform the required Surveillances if the

. *r 92 dar'Frequency is not met per. SR 3.0.2. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 7Xý r~/-!57 allowance is based on operating experience and in consideration of provtdina aftsenablý +.A 4- -h4h complete the -SRs

-W "M

Z a(=z6 AA The RBM setpoints are automatically varied as a function of power.

Three Allowable Values are specified in Table 3.3.2.1-1, each within a specific power range.

The power at which the control rod block Allowable Values automatically change are based on the APRM signal's input to each RBM channel.

Below the minimum power setpoint, the RBM is automatically bypassed.

These power Allowable Values (continued)

HATCH UNIT 2 B 3.3-50 REVISION 14

Control Rod Block Instrumentation B 3.3.2.1 BASES SURVEILLANCE S

(continued)

REQUIREMENTS OPERABLE following loading of sequence into RWM, since this is when rod sequence input errors are possible.

REFERENCES

1.

FSAR, Section 7.6.2.2.5.

2.

FSAR, Section 7.6.8.2.6.

3.

NEDC-30474-P, "Average Power Range Monitor, Rod Block Monitor, and Technical Specification Improvements (ARTS)

Program for Edwin I. Hatch Nuclear Plants,"

December 1983.

4.

NEDE-24011-P-A-US, "General Electrical Standard Application for Reload Fuel," Supplement for United States, (revision specified in the COLR).

5.

Letter from T.A. Pickens (BWROG) to G.C. Lainas (NRC),

"Amendment 17 to General Electric Licensing Topical Report NEDE-24011-P-A," BWROG-8644, August 15, 1986.

6.

NEDO-21231, "Banked Position Withdrawal Sequence,"

January 1977.

7.

NRC SER, "Acceptance of Referencing of Licensing Topical Report NEDE-24011-P-A," "General Electric Standard Application for Reactor Fuel, Revision 8, Amendment 17," December 27, 1987.

8.

NEDC-30851-P-A, "Technical Specification Improvement Analysis for BWR Control Rod Block Instrumentation,"

October 1988.

9.

GENE-770-06-1, "Bases for Changes To Surveillance Test Intervals And Allowed Out-Of-Service Times For Selected Instrumentation Technical Specifications,"

February 1991.

10.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

11.

NEDC-32410P-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM)

Retrofit Plus Option III Stability Trip Function,"

xnser/

October 1995.

erC HATCH UNIT 2 REVISION 14 B 3.3-53

Section B 3.3.2.1 Inserts Insert A:

The 1-84-dey Frequency is based on a review of the surveillance test history and Reference 12.

Insert B:

12.

NRC Safety Evaluation Report for Amendment

Feedwater and Main Turbine High Water Level Trip Instrumentation B 3.3.2.2 BASES SURVEILLANCE SR 3.3.2.2.L 1 (continued)

REQUIREMENTS logic from the input of the alarm unit.

This is consistent with the CHANNEL FUNCTIONAL TEST definition requiring the signal to be injected 'as close to the sensor as practicable.* Additionally, due to the physical location of the turbine trip relays and their close proximity to other sensitive equipment, accessibility is extremely limited.

Verification of relay actuation and associated relay contact status by accessing the relay introduces a high potential for turbine trip and reactor scram.

One contact from each turbine trip relay energizes an amber light indicating relay actuation.

Therefore, it is acceptable to terminate the test at the turbine trip relay, utilizing light indication for relay status.

These allowances are only acceptable if the CHANNEL CALIBRATION and the LOGIC SYSTEM FUNCTIONAL TEST overlap both the initiation and termination point of this CHANNEL FUNCTIONAL TEST such that the entire trip logic is tested.

SR 3.3.2.2.2 CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The Frequency is based upon the assumption of an 18 month calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis.

The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel. The system functional test of the feedwater and main turbine valves is included as part of this Surveillance and overlaps the LOGIC SYSTEM FUNCTIONAL TEST to provide (continued)

HATCH UNIT 2 REVISION I B 3.3-59

Feedwater and Main Turbine High Water Leve 1 Trip Instrumentation B 3.3.2.2 SURVEILLANCE REQUIREMENTS SR 3.3.2.2.3 (continued) complete testing of the assumed safety function.

Therefore, if a valve is incapable of operating, the associated instrumentation channels would also be inoperable.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

REFERENCES

1.

FSAR, Section 15.1.7.

2.

GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times for Selected Instrumentation Technical Specifications,"

February 1991.

3.

NRC No.93-102, 'Final Policy Statement on Technical Xns-r*

Specification Improvements," July 23, 1993.

Z e 4n-e-nc)

HATCH UNIT 2 BASES REVISION I B 3.3-60

Section B 3.3.2.2 Inserts Insert A:

The 184-4erequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 4.

Insert B:

4.

NRC Safety Evaluation Report for Amendment __

EOC-RPT Instrumentation B 3.3.4.1 BASES SURVEILLANCE analysis demonstrated that the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance does REQUIREMENTS not significantly reduce the probability that the (continued) recirculation pumps will trip when necessary.

SR 3.3.4..1, A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

SR3.3.4.1.2 This SR ensures that an EOC-RPT initiated from the TSV -

Closure and TCV Fast Closure, Trip Oil Pressure -Low Functions will not be inadvertently bypassed when THERMAL POWER is ; 28% RTP.

This involves calibration of the bypass channels.

Adequate margins for the instrument setpoint methodologies are incorporated into the actual setpoint.

Because main turbine bypass flow can affect this setpoint nonconservatively (THERMAL POWER is derived from first stage pressure) the main turbine bypass valves must remain closed during the calibration at THERMAL POWER 2 28% RTP to ensure that the calibration is valid.

If any bypass channel's setpoint is nonconservative (i.e., the Functions are bypassed at ? 28% RTP, either due to open main turbine bypass valves or other reasons), the affected TSV--Closure and TCV Fast Closure, Trip Oil Pressure -

Low Functions are considered inoperable.

Alternatively, the bypass channel can be placed in the conservative condition (nonbypass).

If placed in the nonbypass condition (Turbine Stop Valve-Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure-Low Functions are enabled), this SR is met with the channel considered OPERABLE.

The Frequency of 18 months is based on engineering judgment and the reliability of the components.

(continued)

HATCH UNIT 2 REVISION 21 B 3.3-86

EOC-RPT Instrumentation B 3.3.4.1 BASES REFERENCES

4.

GENE-770-06-1, "Bases For Changes To Surveillance Test (continued)

Intervals And Allowed Out-Of-Service Times For Selected Instrumentation Technical Specifications,"

February 1991.

5.

Technical Requirements Manual.

6.

NRC No.93-102, "Final Policy Statement on Technical

-2nser~l 23Specification Improvements," July 23, 1993.

HATCH UNIT 2 B 3.3-89 REVISION I

Section B 3.3.4.1 Inserts Insert A:

The 1-84-dey'Frequency is based on a review of the surveillance test history and Reference 7.

Insert B:

7.

NRC Safety Evaluation Report for Amendment

ATWS-RPT Instrumentation B 3.3.4.2 BASES SURVEILLANCE SR 3.3.4.2.1 (continued)

REQUIREMENTS Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated-with the channels required by the LCO.

A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

A CHANNEL CALIBRATION is a complete check of the Instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The Frequency is based upon the assumption of an 18 month calibration interval in the determination of the magnitude of equipment drift-in the setpoint analysis.

(continued)

REVISION 1 HATCH UNIT 2 B 3.3-97

ATWS-RPT Instrumentation B 3.3.4.2 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 3.3.4.2.4 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required trip logic for a specific channel.

The system functional test of the pump breakers is included as part of this Surveillance and overlaps the LOGIC SYSTEM FUNCTIONAL TEST to provide complete testing of the assumed safety function.

Therefore, if a breaker is incapable of operating, the associated instrument channel(s) would be inoperable.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

REFERENCES

1.

FSAR, Section 7.6.10.7.

2.

GENE-770-06-1, 'Bases for Changes To Surveillance Test Intervals and Allowed Out-of-Service Times For Selected Instrumentation Technical Specifications,"

February 1991.

3.

NRC No.93-102, "Final Policy Statement on Technical j27,i se-r-Specification Improvements. July 23, 1993.

(Reerenee4)

HATCH UNIT 2 8 3.3-98 REVISION 1

Section B 3.3.4.2 Inserts Insert A:

The 184-day Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 4.

Insert B:

4.

NRC Safety Evaluation Report for Amendment

ECCS Instrumentation B 3.3.5.1 BASES SURVEILLANCE REQUIREMENTS (continued)

A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

7-2 n',

A

-000 SR 3.3.5.1.3 and SR 3.3.5.1.4 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

The Frequency of SR 3.3.5.1.3 and SR 3.3.5.1.4 is based upon the assumption of the magnitude of equipment drift in the setpotnt analysis.

SR 3.3.5.1.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel.

The system functional testing performed in LCO 3.5.1, LCO 3.5.2, LCO 3.7.2, LCO 3.8.1, and LCO 3.8.2 overlaps this Surveillance to complete testing of the assumed safety function.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

(continued)

HATCH UNIT 2 B 3.3-134 REVISION I

ECCS Instrumentation B 3.3.5.1 BASES SURVEILLANCE REQUIREMENTS (continued)

REFERENCES

..2piser-+ B

(,Re-Feredice

1.

FSAR, Section 5.2.

2.

FSAR, Section 6.3.

3.

FSAR, Chapter 15.

4.

NEDC-31376-P,

  • Edwin I. Hatch Nuclear Power Plant, SAFER/GESTR-LOCA, Loss-of-Coolant Accident Analysis,"

December 1986.

5.

NEDC-30936-P-A,

  • BWR Owners' Group Technical Specification Improvement Analyses for ECCS Actuation Instrumentation, Part 2,0 December 1988.
6.

NRC No.93-102, "Final Policy Statement on Technical 7>-

Specification Improvements," July 23, 1993.

HATCH UNIT 2 I

B 3.3-135 REVISION 4

Section B 3.3.5.1 Inserts Insert A:

The 184* 'equency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 7.

Insert B:

7.

NRC Safety Evaluation Report for Amendment

RCIC System Instrumentation B 3.3.5.2 BASES SURVEILLANCE SR 3.3.5.2.1 (continued)

REQUIREMENTS channels monitoring the same parameter should read approximately the same value.

Significant deviations between the instrument channels could be an Indication of excessive instrument drift in one of the channels or something even more serious.

A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the channels required by the LCO.

SR 3.3.5.2.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

rn s eri-A SR 3.3.5.2.3 and SR 3.3.5.2.4 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

(continued)

HATCH UNIT 2 B 3.3-145 REVISION I

RCIC System Instrumentation B 3.3.5.2 BASES SURVEILLANCE REQUIREMENTS SR 3.3.5.2.3 and SR 3.3.5.2.4 (continued)

The Frequency of SR 3.3.5.2.3 and SR 3.3.5.2.4 is based upon the assumption of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.5.2.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel.

The system functional testing performed in LCO 3.5.3 overlaps this Surveillance to provide complete testing of the safety function.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

REFERENCES

1.

GENE-770-06-2, "Addendum to Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," February 1991.

2.

NRC No.93-102, nFinal Policy Statement on Technical

.ns er-. 2:5 Specification Improvements," July 23, 1993.

HATCH UNIT 2 B 3.3-146 REVISION 1

Section B 3.3.5.2 Inserts Insert A:

The +84-dey Frequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 3.

Insert B:

3.

NRC Safety Evaluation Report for Amendment

Primary Containment Isolation Instrumentation B 3.3.6.1 BASES SURVEILLANCE SR 3.3.6.1.2 and SR 3.3.6.1.4 (continued)

REQUIREMENTS 84Z day requency 4 o;

..9..4 is base on eng neering judgment and the reliability of the components (time delay relays exhibit minimal drift).

SR 3.3.6.1.3 and SR 3.3.6.1.5 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

T The Frequency of SR 3.3.6.1.5 is based on the assumption of the magnitude of equipment drift in the setpotnt analysis.

SR 3.3.6.].6 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel.

The system functional testing performed on PCIVs in LCO 3.6.1.3 overlaps this Surveillance to provide complete testing of the assumed safety function.

The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power.

Operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

SR 3.3.6.1.7 This SR ensures that the individual channel response times are less than or equal to the maximum values assumed in the accident analysis.

The instrument response times must be added to the PCIV closure times to obtain the ISOLATION SYSTEM RESPONSE TIME.

(continued)

HATCH UNIT 2 B 3.3-174 REVISION I

Primary Containment Isolation Instrumentation B 3.3.6.1 BASES SURVEILLANCE SR 3.3.6.1.7 (continued)

REQUIREMENTS ISOLATION SYSTEM RESPONSE TIME acceptance criteria are included in Reference 6.

This test may be performed in one measurement, or in overlapping segments, with verification that all components are tested.

A Note to the Surveillance states that the channel sensors are excluded from ISOLATION SYSTEM RESPONSE TIME testing.

The exclusion of the channel sensors is supported by Reference 8 which indicates that the sensors' response times are a small fraction of the total response time.

Even if the sensors experienced response time degradation, they would be expected to respond in the microsecond to millisecond range until complete failure.

ISOLATION SYSTEM RESPONSE TIME tests are conducted on an 18 month STAGGERED TEST BASIS.

This Frequency is consistent with the typical industry refueling cycle and is based upon plant operating experience that shows that random failures of instrumentation components causing serious response time degradation, but not channel failure, are infrequent occurrences.

REFERENCES

1.

FSAR, Section 6.3.

2.

FSAR, Chapter 15.

3.

FSAR, Section 4.2.3.4.2.

4.

NEDC-31677P-A, "Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation,"

July 1990.

5.

NEDC-30851P-A Supplement 2, "Technical Specifications Improvement Analysis for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation," March 1989.

6.

Technical Requirements Manual.

7.

NRC No.93-102, 'Final Policy Statement on Technical Specification Improvements," July 23, 1993.

8.

NEDO-32291, "System Analyses for Elimination of Sse r f Selected Response Time Testing Requirements,"

January 1994.

HATCH UNIT 2 B 3.3-175 REVISION 4

Section B 3.3.6.1 Inserts Insert A:

The +84-dY Frequency of SR 3.3.6.1.2 is based on a review of the surveillance test history, drift analysis of the associated trip units (if applicable), and Reference 9.

Insert B:

The 1e4-day Fr*'quency of SR 3.3.6.1.3 is based on a review of the surveillance test history, drift analysis of the associated pressure (or vacuum) switches (if applicable), and Reference 9.

Insert C:

9.

NRC Safety Evaluation Report for Amendment __

Secondary Containment Isolation Instrumentation B 3.3.6.2 BASES SURVEILLANCE average time required to perform channel surveillance.

That REQUIREMENTS analysis demonstrated the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance does not (continued) significantly reduce the probability that the SCIVs will isolate the associated penetration flow paths and that the SGT System will initiate when necessary.

Performance of the CHANNEL CHECK once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ensures that a gross failure of instrumentation has not occurred.

A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels.

It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value.

Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious.

A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including Indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based on operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channel status during normal operational use of the displays associated with channels required by the LCO.

SR 3.3.6.2.2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

(continued)

HATCH UNIT 2 B 3.3-184 REVISION I

Secondary Containment Isolation Instrumentation B 3.3.6.2 BASES SURVEILLANCE REQUIREMENTS (continued)

SR 3.3.6.2.3 and SR 3.3.6.2.4 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpolnt mathndn1 nlv 3nser

.i '

The Frequ-Bc sof SR 3.3.6.2.46 based on the assump 0on oTfthe iag-ntuideof equipment df-Tft in the setpoint analysis.

SR 3.3.6.2.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel.

The system functional testing performed on SCIVs and the SGT System in LCO 3.6.4.2 and LCO 3.6.4.3, respectively, overlaps this Surveillance to provide complete testing of the assumed safety function.

While this Surveillance can be performed with the reactor at power for some of the Functions, operating experience has shown that these components usually pass the Surveillance when performed at the 18 month Frequency.

Therefore, the Frequency was found to be acceptable from a reliability standpoint.

REFERENCES

1.

FSAR, Section 6.3.

2.

FSAR, Chapter 15.

3.

FSAR, Section 15.1.40.

4.

FSAR, Sections 15.1.39 and 15.1.41.

5.

NEDC-31677P-A, "Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation,"

July 1990.

(continued)

REVISION 1 HATCH UNIT 2 B 3.3-185

Secondary Containment Isolation Instrumentation B 3.3.6.2 BASES REFERENCES

6.

NEDC-30851P-A Supplement 2, *Technical Specifications (continued)

Improvement Analysis for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation,* March 1989.

7.

NRC No.93-102, 'Final Policy Statement on Technical uis te+

c

)

  • Specification Improvements,' July 23, 1993.

HATCH UNIT 2 8 3.3-186 REVISION I

Section B 3.3.6.2 Inserts Insert A:

qz. d

-/,

The 184 dayFirequency is based on a review of the surveillance test history, drift analysis of the associated trip units, and Reference 8.

Insert B:

The 1-F equency of SR 3.3.6.2.3 is based on a review of the surveillance test history and Reference 8.

Insert C:

8.

NRC Safety Evaluation Report for Amendment

LLS Instrumentation B 3.3.6.3 BASES SURVEILLANCE time required to perform channel surveillance.

That REQUIREMENTS analysis demonstrated that the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> testing allowance (continued) does not significantly reduce the probability that the LLS valves will initiate when necessary.

SR 3.3.6.3.1 Performance of the CHANNEL CHECK once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ensures that a gross failure of instrumentation has not occurred.

A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on another channel.

It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value.

Significant deviations between the instrument channels could be an indication of excessive instrument drift in one of-the channels or something even more serious.

A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria are determined by the plant staff based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with channels required by the LCO.

SR 3.3.6.3.2. SR 3.3.6.3.3. and SR 3.3.6.3.4 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpolnt methodology.

(continued)

HATCH UNIT 2 B 3.3-193 REVISION 1

LLS Instrumentation B 3.3.6.3 BASES (continued)

REFERENCES

1.

FSAR, Section 7.4.4.

2.

FSAR, Section 5.5.17.

3.

GENE-770-06-1, "Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications,"

February 1991.

4.

NRC No.93-102, 'Final Policy Statement on Technical "Zri se r

-f-B Specification Improvements,* July 23, 1993.

(Re-Fecre, ee; L11 REVISION I HATCH UNIT 2 B 3.3-195

Section B 3.3.6.3 Inserts Insert A:

The dey Frejuency is based on a review of the surveillance test history, drift analysis of the associated trip units (if applicable), and Reference 5.

Insert B:

5.

NRC Safety Evaluation Report for Amendment

NCREC System Instrumentation B 3.3.7.1 BASES SURVEILLANCE SR 3.3.7.1.1 (continued)

REQUIREMENTS Agreement criteria are determined by the plant staff, based on a combination of the channel instrument uncertainties, including indication and readability.

If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit.

The Frequency is based upon operating experience that demonstrates channel failure is rare.

The CHANNEL CHECK supplements less formal, but more frequent, checks of channel status during normal operational use of the displays associated with channels required by the LCO.

A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function.

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology.

The Frequency of 31 days is based on operating experience with regard to channel OPERABILITY and drift, which demonstrates that failure of more than one channel in any 31 day interval is a rare event.

SR 3.3.7.1.3 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor.

This test verifies the channel responds to the measured parameter within the necessary range and accuracy.

CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the plant specific setpoint methodology.

In(ot.ne A

(continued)

HATCH UNIT 2 B 3.3-201 REVISION I

MCREC System Instrumentation B 3.3.7.1 BASES SURVEILLANCE REQUIREMENTS (continued)

REFERENCES ZnseCL7 B --

I (Re 4ference- ?

SR 3.3.7.1.4 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required initiation logic for a specific channel.

The system functional testing performed in LCO 3.7.4, 'Main Control Room Environmental Control (MCREC)

System," overlaps this Surveillance to provide complete testing of the assumed safety function.

While this Surveillance can be performed with the reactor at power, operating experience has shown these components usually pass the Surveillance when performed at the 18 month Frequency.

Therefore, the Frequency was found to be acceptable from a reliability standpoint.

1.

FSAR, Section 7.3.5

2.

FSAR, Chapter 6.

3.

FSAR, Section 6.4.1.2.2.

4.

FSAR, Chapter 15.

5.

FSAR, Table 15.1.28.

6.

GENE-770-06-1, *Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications,'

February 1991.

7.

NRC No.93-102, 'Final Policy Statement on Technical Specification Improvements," July 23, 1993.

HATCH UNIT 2 B 3.3-202 REVISION I I

Section B 3.3.7.1 Inserts Insert A: z 77557-4L The 184-dey Frequency is based on a review of the surveillance test history and Reference 8.

Insert B:

8.

NRC Safety Evaluation Report for Amendment __