ML20154L502

Revised Tech Spec Page,Which Corrects Editorial Errors

ML20154L502
Person / Time
Site:	Hope Creek
Issue date:	10/08/1998
From:	Public Service Enterprise Group
To:
Shared Package
ML20154L499	List: ML20154L496 ML20154L502
References
NUDOCS 9810190332
Download: ML20154L502 (3)

Text

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TABLE 4.3.1.1-1 (Continued)

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REACTOR PROTECTION SYSTEN III$TRINENTATION $0RVEILLANCE E"!IRDENTS 4

I 3

B CHAISEL OPERATIGIIAL i

g FIBICTICIIAL IRIIT OIAISEL FISICTICIIAL CHAISEL COISITISIIS FOR 6811CN-l QECK TEST CAlin1 RATION

_$NRVEILLANCE RE0lIIRES i

S.

Scram 31scharge Volume lister Level - Nid a.

Float Switch

• MA P

R 1, 2, 5III h.

Level Tremonitter/ Trip A

III j

IInit S

Q R

1 5

]

9.

Turbine stap velve - Closure NA 4

R 1

18. Turtina Centrol Valve Fast 011 Pressure - Law IIA Q

R 1

l Closure Valve Trly System

$ 11.

Reacter IInde Switch f

SIntdown Positten HA R

IIA 1,2,3,4,5 i

=

12. Manual Scram IIA W

IIA 1,2,3,4,5 j

(a) Neutron detectors may be excluded from CHAIBIEL CALIBRATI0ff.

j (b) The INI and Sal channels shall be determined to overlap for at least % decades during each startup l

i after entering OPERATIGIIAL COISITIOGI 2 and the INI and APWI channels shall be determined te overlap j

for at least % decades during each centrolled sistdeun,1f not performed within the previous 7 days.

(c) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startep, if not performed within the previses 7 days.

(d) This calibretten shall censJst of the adjustment of the APWI channel to conform to the power values calculat'ad a host balance durfag SPERATISIIAL CSISITICII 1 when TIENI4L PSER > 2E of RATED i

i TIEWI4L Adjust the APWI channel if the absolute difference is greater teen 25 of RATED TIENIAL

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PWER. Amy APRI channel gala M tment made in compliance with Specificatten 3.2.2 shall not be l

included in determining the abse 'ste difference.

1 (e) This ca11bestien shall consist of the adjustment of the APWI flew hfased channel to conform to a calibrated flew signal.

(f) The LPWIs shall be calibrated at least once per 1000 effectfwe full power hours (EFFII)

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using the TEP system.

t (g) Verify measured core flow (total core flow) te he greater than er agual to estabilshed core flew at the l

g existing recirculatten leap flew (APWI E flew).

j (h) This calibratten shall censist of vertfying the 6 1 0.5 second slaulated thermal power time constant.

0 (1) This item intentionally blank l

l (j) With any centrol red wttIuiraun. Ilot applicable to centrol rods removed per Specification 3.9.10.1 j

er 3.9.10.2.

(k) "trify the tripset point of the trip unit at leas" nce per 92 days.

9810190332 981008 4

PDR ADOCK 05000354 P

PDR i

LR-N98465 Corrected Technical Specification Page

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' TABLE 4.3.1.1-1 '(Continued)

REACTOR PROTECTION' SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS' l

. 6 CHANNEL OPERATIONA.L t

CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR FHICH.'

FUNCTIONAL UNIT -

CHECK TEST

' CALIBRATION-SURVEILLANCE REQUIRED l

.8.

Scram Discharge Volume Water Level ~~High a.

Float Switch NA Q

R 1,

2, 5 '88 i

b.

Level Transmitter / Trip Unit S

Q R

1, 2, ' 5 '3 '

N 9.

Turbine Stop Valve - Closure NA Q

R 1

k i

10. Turbine Control Valve Fast Closure Valve Trip System

[

l.

Oil Pressure - Low NA Q

R 1

[

f

11. Reactor Mode Switch Shutdown Position NA R

NA-1, 2,

3, 4,

5 i

12.-Manual Scram NA~

W NA 1,

2, 3,

4, 5

I t

(a) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(b) The IRM and SRM channels shall be determined to overlap for at least 1/2 cecades'during each startup.

j after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap' j

for at least 1/2 decades during each controlled shutdown, if not periormed within the previous 7 days.

j (c) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous 7 days.

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.(d) This' calibration shall consist of the adjustment of the APRM channel to conform to the' power values l

calculated by a heat balance during OPERATIONAL CONDITION 1 when. THERMAL POWER 2 25% of RATED t

j I

THERMAL POWER.

Adjust the APRM channel if the absolute difference is greater than 2% of RATED THERMAL POWER.

j Any APRM channel gain adjustment made in compliance with Specification 3.2.2 shall not be included in determining the absolute difference.

f (e) This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a calibrated flow

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signal.

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(f) The LPRMs shall be calibrated at least once per 1000 effective full power hours (EFPH) using the TIP system.

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(g) Veri.'v measured core flow (total core flow) to be greater than or equal to established core flow at the-existing recirculation loep flow (APRM % flow).

}

(h) This calibration shall consist of verifying the 6 1 0.6 second simulated thermal power time constant.

1 (i) This item intentionally blnnk l

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(j) With any control rod withdrawn. 'Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

(k) Verify the tripset point of the trip unit at least once per 92 days.

HOPE CREEK 3/4 3-8 Amendment No. 53 l

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