ML20079K723

Proposed Tech Specs Table 4.3.1.1-1 Re Reactor Protection Sys Instrumentation Surveillance Requirements

ML20079K723
Person / Time
Site:	Clinton
Issue date:	10/17/1991
From:	ILLINOIS POWER CO.
To:
Shared Package
ML20079K715	List: JSP-652-91, Application for Amend to License NPF-62,requesting That S/U(C) Notation Be Retained Under Channel Functional Test Column Heading of TS Table 4.3.1.1-1, Reactor Protection Instrumentation Surveillance Requirements ML20079K723
References
NUDOCS 9110240146
Download: ML20079K723 (2)

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Attachment *

• ' to U-601884 i Page 2 of 2 1ABLE4.3.1.1-1(Continued}

PfAC10RPROTECTIONSYSTEMINSTRUMENTATIONSitRVElltANCEREQUIREMENTS TABLE NOTATIONS (a) Neutron detectort may be excluded from CHANNEL CAllBRATION.

(b) 1he IRH and SRM channels sh?ll be determined to overlap for at least 1/2 de-cade during each startup after entering OPERATIONAL. CONDITION 2 and the IRH i and APRH channels shall be determined to overlap for at least I decade dur-

, ing each controlled shutdown, if not performed within the previous 7 days.

7 -

( (c) Within 24-hout+ prior to startup, .44-not-perfomed-within4he-pnoviou6 1

t(-Qayw_ _ _L1aq$ _

(d) This calibration shall' consist of the adjustment of the APRH channel to ng OPERATIONAL conform CONDITION 1to theTHERHAL when powerPOWER values > 25%cciculated by a heat of RATED THERMAL POWER balance dtp&(/ Adjustl the APRH channel if the absolute diTference is greater than 2% of RATED TilERMAL POWER.

(c) This c litration shall consist of a setpoint verification of thyleptrig-

. _ i@ Gr#,MFlow Biased Simulated Themal Power-High trip furictio .

Ile How Blased Simulated Thermal-High trip function is verified using a

celibrated flow signal.

(f) 1he LPRHs shall be calibrated at least once per 1000 offective full power hours.(EFPH) using the TIP system.

(g) Cailbrate the analog trip module at least once per 31 days.

(h) Deleted.

(i) This calibration 1, hall consist of verifying the 610.6 second simulated thermal power time constant.

(j) This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification 3.10.1.

(k) With any control rod withdrawn.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

(1) This function is not required to be OPERABLE when DRYWELL INTEGRITY is not required to be OPERABLE per Special Test Exception 3.10.1.

(m) The CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION shall include the turbine first stage pressure instruments, p w. - --;, - ~

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Y The provisiorss of $peciGe<d; ors 4.0.4 afe twf appUcable.,j yov'ided %e surve'.\\eme. M performed wahin 12. hcws CAbr OgCecd'.rs3 25 */o of ~R Aub WERM At.70W6R ,

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CLINTON - 81 NIT 1 3/4 3-10 Amendment No. 30

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