ML20126E528
| ML20126E528 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/21/1992 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20126E526 | List: |
| References | |
| NUDOCS 9212290179 | |
| Download: ML20126E528 (9) | |
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ENCLOSURE 4 NEW TECHNICAL SPECIFICATIONS REVISED FAGES 9212290179 921221 DR-p ADOCK 05000321 PDR.
BASES FOR LIMITING CONDITIONS FOR OPERAllqN 4.2 PEQlf{TIVE INSTRUMENTATION The instrumentation listed in Tablet 4.21 through 4.2-13 will be functionally tested and calibrated at regularly scheduled intervals. The minimum functional test frequencies and allowable outage times for selected instrumentation related to isolation actuation, ECCS and RCIC actuation, and control rod block have been revised.
The NRC-approved reliability based methodology in References 1 through 4 provides a basis for these changes and is consistent with similar changes to RPS instrumentation, lhe frequency of functional testing and calibration for other instrumentation is based on historical methodology (Reference 5).
A.
Peferentgi 1.
E[0C-30951P-A, "BWR Owners' Group Technical Specification Improvement Analysis for BWR Reactor Protection System,' March 1988.
2, EERC-31677P A, " Technical Specification Improvement Analysis for BWR isolation Actuation Instrumentation,' July 1990.
3.
REDC-30936P-A, "BWR Owners' Group Technical Specification improvement Methodology (with Demonstration for BWR ECCS Actuation Instrumentation)
Part 2,* June 1987.
4.
E[Q[-30851P-A, Supplement 1, " Technical Specification Improvernent Analysis for BWR Control Rod Block Instrumentation," October 1988.
5.
VCRL-50451, ' Improving Availability and Readiness of Field Equipment Through Periodic Inspection," Benjamin Epstein, Albert Shiff, July 16, 1968, page 10 Equation (24), Lawerence Radiation Laboratory.
6.
GENE-770-06-1, " Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications."
7.
GENE-770-06-2, " Addendum to Bases for Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications."
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'HC ATWS RECfRCUt ATION PUMP Trip ACTU ATION INSTRUMENTATION
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SURVEfLLANCE REcuiRi*eENTS E
C' CHANNEL
--4 CHANNEL FUNCTIONAL CHANNEL TR!P FUNOT!ON CHECK TEST CALS tATf 0N m
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ENCLOSURE 5 liAND-MARKED PAGES l
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Ba5f 5 FOR LIMIT 1HG CONDITIONS FOR OPERATION 4.2 PROTECTIVE INSTRUMENTATlg g
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The instrumentation listed in Tables 4.2-1 thru 4.2-13 ill be functio'nally
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tested and calibrated at regularly scheduled intervals. ^: ':= d::i;n n-(
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r all applications of ont-out-of-two-taken-twice logic. Therefore, on-off se ers are tested once every three months, and bi-stable trips associated with nalog sensors and amolifiers are tested once per week. The ATTS inst nts are te ted once per sionth per NEDO-21611-A.
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Those ins urnents which, when tripped, result in a rod block have thelf contacts arranged in one-out-of-nlogic,andallarecapableof*beingbypasfed. For such a tripping ary ngement with bypass capability provided, there is enr optimum test interval that ould be maintained in order to maximize the reliability of a given channel (Referen 1).
This takes account of the fact that testing degrades re-liabiftty and the timum interval between tests is spproximat/ly given ty:
i= I.1 r
Where: i = the optimum int rval between tests.
t = the time the trip c. tacts are disable f rces perfonning their function while the te 5 in progres.
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r = the expected f ailure rat of the r lays.
To test the trip relays requires that t hannel be bypassed, the test made, and the system returned to its initial statp, It is assumed this task requires an es-timated 30 minutes to complete in a thproug and workmanlike sunner and that the relays have a f ailure rate of 10-* f ailures r hour. Using this data and the aboveoperation,theoptimumtestptervalis:
- i. 2@ $1 108 hou s 40* *
= 42 days A test interval of once-per-month will be used initially.
The sensors and elect /onic apparatus have not been included re as these are ana-log devices with readouts in the control room and the sensors d electronic ap-paratus can be chp(ked by comparison with other like instruments The checks which are made ad a daily or once per shift basis are adequate to ssure oper-l ability of the sensors and electronic apparatus. and the test inter' 1 given above provid for. optimum testing of the relay circuits.
The absve/ calculated test interval optirtizes each individual channel, co idering
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it to be' independent of all others. As an example, assume that there are chann6Ts with an individual technician assigned to each. Each technician te s his /nsnnel at the optimuta f requency, but the two technicians are not allowed (to connunicate so tnat one can advise the other that his channel is under test. U (kfr these conditions, it is possible f or both channels to be under test simultane
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t 3.2-6g Amendment No. 88.103 PATCH - UNIT 1 d
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Insert E (to P. 3.2-69)
The minimum functional test frequencies and allowable outage times for selected instrumentation related to isolation actuation. ECCS and RCIC actuation, and control rod block have been revised.
The NRC-approved reliability-based methodology in References 1 through 4 provides a basis for these changes and is consistent with similar changes to RPS instrumentation. The frequency of functional testing and calibration for other instrtmentation is based on historical methodology (Reference 5).
A. Rehraum 1.
NEDC-30851P-A, "BWR Owners' Group Technical Specification Improvement Analysis for BWR Reactor Protection System," March 1988.
2.
NEDC-31677P-A, " Technical Specification Improvement Analysis for BWR Isolation Actuation Instrumentation," July 1990.
3.
NEDC-30936P-A, "BWR Owners' Group Technical Specification Improvement Methodology (with Demonstration for BWR ECCS Actuation Instrumentation)
Part 2," June 1987.
4.
F.[DC-30851P-A, Supplement 1
" Technical Specification Improvement Analysis for BWR Control Rod Block Instrumentation," October 1988.
5.
ilfRL-50451, " Improving Availability and Readiness of Field Equipment-Through Periodic Inspection," Benjamin Epstein, Albert Shiff, July 16, 163-page l_0 e
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TABLE I4.3.3-1 IContinued)
EMERCENCY C0ftE COOLlhC SYSTEM ACTUATION INSTRUMfMTATION SURVEILIANCE REQUIREMENTS
,S CilANNEL OPERATIONAL CHANNEL
~TUNCTIONAL CitAN> E L CONDITIONS IN WHICil CHECK TEST CAllBRATION SURVEILLANCE REQUIRED #
TRIP. FUNCTION c6 3.
HICH PRESSURE COOLANT INJECTION SYSTEM
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g Low Low (Level 2)
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e.
Logic Power Monitor NA R
NA 1, 2, 3
P.
Reactor Vessel Water Level-High S
WQ R
1, 2, 3 (Level 8) ti.
AUTOMATIC DEPRESSURIZATION SYSI G a.
Dryvell Pressure-High S
M-G R
1, 2, 3 b.
Low Low Low (Level 1)
S M-Q ft 1,2,3 c.
ADS Timer NA NA R
1, 2, 3 d.
ADS Low Water Level Actuation Timer NA NA R
1, 2, 3
l w
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floactor vessel Water Level - Low J4-Q
.w (Level 3) e P.
Core Spray Puep Discharge R
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RHR (LPCI HODE) Pump Discharge Pressure - High S
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Control Power Monitor NA R
NA 1, 2, 3 5.
LOW LCW SET S/RV S'/STEH a.
Reactor Stess Deze Pressure -
R 1, 2, 3
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w f itPCI and ADS are not required to be OPERABLE with reactor steam dome pressure 5150 psig.
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