ML18095A224
| ML18095A224 | |
| Person / Time | |
|---|---|
| Site: | Salem |
| Issue date: | 05/21/1990 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18095A223 | List: |
| References | |
| NUDOCS 9005290131 | |
| Download: ML18095A224 (4) | |
Text
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TABLE 3.3-1 (Continued)
TABLE NOTATION
- With the reactor trip system breakers in the closed position and the_ control rod drive system capable of rod withdrawal.
- The channel(s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped condition.
- The provisions of Specification 3.0.4 are not applicable.
- High voltage to detector may be de-energized above P-6.
- ~f ACTISN Statement 1 is eA't-ef'ea Elt1e te.tt:1e Pes1:1lts ef fflairrteAaAee testiA§
~A Reaeter TPi13 8peal<ePs (RTB) er Reaeter Tri13. B:Yi:iass Breakers (RTBB)
@1<ceeei A§ aAy 13Fecee1:1 Fal acce13taAce cFiteFi a, er RTE! /Rnl9 t Fi Iii fe Fees e*eeeeiA§ tRe reeefflmeAeee 1:11313er limit, imm&diate NRC RQtifiGatieR [~itbiR 1 lie1:1 r afld f}ri e F te a Ry re13a i P er aelj 1::1 st111eAt te tRe affeeteEI BPeal< e P ( s)] is re~1:1iFee iA acceFeaAce witR §13ecificatieA ~.Q,2 ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requiremen~, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1.1.
ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:
- a.
The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
- b.
The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for
?Urveillance testing per Specification 4.3.1.1.
- c. Either, THERMAL POWER is restricted to < 75% of RATED THERMAL and the Power Range, Neutron Flux trip set point is reduced to* < 85%
of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
ACTION 3 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER 1eve1 :
SALEM - UNIT 1
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l, 9005290131 900521 PDR ADOCK 05000272 p
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. 3/4 3-5 Arrendrcent No. 60
If ACTION Statement 1 is entered as a result of Reactor Trip Breaker (RTB) or Reactor Trip Bypass Breaker (RTBB) maintenance testing results exceeding the following acceptance criteria, ~RC reporting shall be made in accordance with Specification 6.9.1.9:
- 1.
A RTB or RTBB trip failure during any surveillance test with less than or equal to 300 grams of weight added to the breaker trip bar.
- 2.
A RTB or RTBB time response failure that results in the overall reactor trip system time response exceeding the Technical Specification limit.
T~BLE 3.3-1 (Cantin~~d)
T.~3LE NOT.\\TiON
- With che reactor* trip systam br~d~~rs in Che closa~ ~ositicn a~~ ch~ ~antrcl rod dri'le system.:a:JaJle of rod *,o1ithdra*.Hl.
- The channel(s) associated with the protective functions derived f~om t~e out of service Reactor Coolant Loop shall be placed in the tripped :ondition.
1The provis101'S of Specification 3.0.4 are not applicable.
f#Hfgh voltage to detector may be de-energized above ?-6.
- llit ACTION Statement 1 1i eAtered due ta the results of maintenance testing et:' ReactaP Trip Breakers (RTB) eP AeaetaP Trtp Bypass Breakers (RTBB) 1.vse~-r.
~xeeed1Ag aAy pp;c1dural 1cseptaAGI GJ!4.4:eF1a, GP ATl/RT88 trip '8rees exceeding t~e Peee111111eAde4 wpper ltmtt, 11111111diat1 NAG net4f1eat1en (w1th1PI
~ haur and prier ~a a,., Pe19a1 r er adj1;1stmenl ta t.he:.affected ~reaker(s)] is re~utred 1A aGGGFdlAGI with. s,,ee1ffeat1eA ia9w2 ACTION STATEMENTS ACTION 1 - Wtttl th* number of dlann1l s OPERAS\\.! on* *11ss thu requtred by the M1ntmua Channels OPERAB\\.E requtrtmant, be tn HOT STANDBY,,,fttltn 5 houn: however. one chun*l 11111 b* bypHsad for up ta Z haurs far surv*1111nce t1sttng per Spectftcatton 4.3.t.1 provided the ath*r cliun*l ts OPERABL.!.
ACTtON Z - With th* nwn01r at OPERAS\\.! channels one less than the Total Number of ~1nn1ls, STAATIJP 11td/or. POWER OPERATION may proceed provtdld th*
fallawtng candtttons a.-. sattsttld:
~. The tnap1r1bl1 dl1nn11 ts placed tn the tripped condttton within l haur.
- b. The MtntlllWI Chann*ls OPERABLE requtrement ts met; however, on1 add1t1ana1 channel 11111 be bypassed far up ta Z hours for surv1tllance t1sttng.p*r Spectftcattan 4.3.l.t.
- c. Etth1.-, T14ERMAL PO\\llR 1s r1strictad ta lHs than or equal ta 1si af RATED ~ERMAL and th* Pa-i1r Range, N1utran Flux trip s1tpatnt ts r1ducad ta less thu or equal ta.ass af RATED TMERMM.. POWER wtthtn 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; or, the QUADRANT POWER TI~T RATIO ts monttor1d ac least once per lZ hours.
- d. Th* QUADRANT POWER TILT RATto. as f ndtcated by th* r111t1tntng three d1t1ctars, ts v1rtftld*canststant with the narmaltild syaanetrtc pawer dtstrtbuttan abtatned by,ustng,th* mov1bl1 tn-care detectors tn th* four p1trs of' symmetrtc tl'l1.mble lacattans at l111t anc1 p1r 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when THERMAL POWER ts gr11t1r than 751 of RATED ~E.~L POWER.
SALEM
- UNlT Z 3/4 3-5 Amendment No. 28
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If ACTION Statement 1 is entered as a result of Reactor Trip Breaker (RTB) or Reactor Trip Bypass Breaker (RTBB) maintenance testing results exceeding the following acceptance criteria, ~RC reporting shall be made in accordance with Specification 6.9.1.9:
- 1.
A RTB or RTBB trip failure during any surveillance test with less than or equal to 300 grams of weight added to the breaker trip bar.
- 2.
A RTB or RTBB time response failure that results in the overall reactor trip system time response exceeding the Technical Specification limit.