ML20211L479

Proposed Tech Specs,Adding NRC Recommended Sentence to Spec 3.5.1.8 & Adding pre-startup Surveillance Test Requirement to Items 13a & B of Table 4.1-1

ML20211L479
Person / Time
Site:	Rancho Seco
Issue date:	12/09/1986
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20211L474	List: ML20211L470 ML20211L479
References
NUDOCS 8612160046
Download: ML20211L479 (2)

Text

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l RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 114> 3.5.1.7 In the event that both Reactor Trip Breaker diverse trip features fail in the untripped state, the Breaker will be declared INOPERABLE, i and the power supplied to the rod drive mechanisms through the failed .

trip device shall be manually removed within 30 minutes. The l condition will be corrected and the remaining trip devices shall be tested within eight hours. If the condition is not corrected and the remaining trip devices are not tested within the eight-hour period, j the reactor shall be placed in the hot shutdown condition within an additional four hours.

3.5.1.8 The SCR retcys for the regulating rods duplicate the trip function of the DC breakers for the safety rods. With the number of operable SCR relays one less than the total number of SCR relays in a channel, restore the inoperable SCR relay to operable status in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or place the SCRs associated with the inoperable relay in trip in the ,

next hour. With two or more SCR relays inoperable, place all SCR relays associated with that channel in trip in the next hour.

3.5.1.9 The INOPERABLE channel in Sections 3.5.1.6, 3.5.1.7, and 3.5.1.8 may be bypassed for up to 30 minutes in any 24-hour period when necessary

< for surveillance testing per Specification 4.1.1.

i l

9612160046 861EK)9 PDR ADOCK 050 2 Proposed Amendment No.114, Revision 1, Supplement 1 3-25a c

TEC AL 1 T ONS S ryelliance Standerds Table 4.1-1 (Continued)

INSTRUMENT SURVEILLANCE REQUIRDENTS .

Channel Description Check Test Calibrate Remarks

8. Reactor coolant pressure /

M R temperature comparator S

9. Power /fobalance/ flow M R comparator S M R

10. Pump / flux comparator S

11. High Reactor Building R Pressure Channels O M 114p 12a. Protection channel M NA coincidence logic NA M R

b. ARTS Turbine Trip S Monitor Channels

c. ARTS Loss of MFW Pumps S M R Monitor Channels 13a. CRD Trip Breaker RPS Undervoltage trip NA M,P NA

b. RPS Shunt Trip NA M,P NA M NA a c. SCP Relays RA Safety Features System 14 Emergency core cooling injection, emergency buf1 ding cooling and building isolation analog channels

a. Reactor coolant pressure channel S M R

b. Reactor Building M R 4 psig channel S Proposed Amendment No.114, Revision 1, Supplement 1 4-4