ML18096A383

Proposed Tech Spec Page 3/4 3-5 Re Reactor Trip Breaker Reporting Requirements

ML18096A383
Person / Time
Site:	Salem, Hope Creek
Issue date:	12/10/1991
From:	Public Service Enterprise Group
To:
Shared Package
ML18096A382	List: ML18096A380 ML18096A383
References
NUDOCS 9112170311
Download: ML18096A383 (6)

Text

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With the reactor r:rip sysr:em breakers in r:he closed position a~d :~e control rod drive sysr:em capable of rod ~ir:hdrawal,

• • The channel(s) associar:ed wir:h the protecr:ive funcr:ions derived Er-Jen the ouc of service Reacr:or Coolant: Loop shall be placed in the tri;:i-.:_ed condir:ion.

1. The provisions of Specificar:ion 3.0.4 are not: applicable.

~ High volr:age to detector may be de-energized above P-6.

• 1. 1. If ACTION Statement l is entered as a result of Reactor Trip Breaker (RTB) or Reactor Trip Bypass Breakers (RTBB) maintenance r:est:ing resul::s exceeding the following acceptance criteria, NR.C reporting shall be made

• 30 ~v~

11 IL..::..:..:.....:.:..:.:__~__;.,,_~_.

1,4/1#1/fl t:f~ T ~ \~- in accordance with Specificatio~  :.:! 6. ':r. l. 9.

I '"* 1. ~1

l. A RTB or RTBB r:rip failure during any surveillance test wir:h less than or equal to 300 grams of weight added to the breaker r:rip bar.

2. A RTB or RTBB time response failure thac results in the overall reactor trip system time response exceeding the Technical Specification limit.

ACTION SIATEMENtS ACTION l

• With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STASDBY within 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />s: 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 provided the other channel is OPERABLE.

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 l hour.

b. Th* 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 surveillance testing per Specification 4.3.l.l.

c. Either, THERMAL POWER. is restricted to < 75t of RATED I~p_o

__t..J_E_~.........,..l--.;....;..._ _~TH=:::ERMAL=:-:~~and the Power Range, Neutron FlWc trip setpoint is reduced to< 85t of RATED THERMAL PO\lEll 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 lease 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 l*s* than required by the Minimum Channels OPERABLE requirement and with r:he THERMAL POWER. level:

3/4 ~-5 Amendmenc No. tl4

AOMINISTRATIVE COfltCtOLS Type of

• • container (e.g., LSA, Typ1 A, Type B, Lar91 Quantity), and

f. Solidification agent or absorb1nt (1.g., cement, urea fonnaldf'i;yde).

Th1 R1d1oact1v1 Eff1u1nt R1l11s1 R1parts shall includ1 a list of d1scr1ptio"56f unplannld releas1s fra11 th* sit1 to UNRESTRICTED AREAS of r1d1oactiv' materials in gis1aus and 1iqu1d 1fflu1nts 1111d1 during th* r1~orting p1r1od.

Th* R1d1oactiv1 Eff1u1nt R1l11s1 Reports shall include any changes rnad1 during the r1part1ng p1r1od ta the PROCESS CONTROL PROGRAM (PCP) and ta the*OFFSITE COSE CALCULATION MAHUAL (ODCM)~ IS well IS I 11st1ng of new locit1ons far dost c1lcul1t1ons 1nd/or 1nv1ron1111nt11 nmnitor1ng 1dent1fitd by th* land us1 census pursuant ta Sp1c1f1cat1an 3.12.2.

SPECIAL REPORTS

• ~el! INSEe:r.i.- U.S. ,Jv,/ear Q.e'J"klar'I C....,m;,~ia11/

Cbc.u.t77etrl Co;i rrol :Jes~, t.Ja.~/,.-t1i{c"

0. C. 02 0 S"ST, ..JI 1Ji a.. Co 'fa fJ,..p S.9.Z Special r1ports shall be subftl1ttld to the Adlll1n stratar 0,,4e1 w1~h1n th* t1* period spec1 f1td for 1ach report. J,....__ _ _ ____,

5.10 RECORD RET!NTION In addition ta the 1ppl1c1bl1 record r1t1nt1on r1quirement*s of Title 10., Code af Fed1ral R19ul1t1ons, th* fo11aw1ng r1cords shall bl rt;Jntd for at l11st the minimum p1r1od ind1c1t1d. @ .

s.10.1 The following records sh*ll be r1t1fnld far 1t l11st five years:

a. Records and logs of un1t op1r1tiaft- cav1ring tfme 1nt1rv1l at each po~*r level.

b. Records and logs of pr1nc1pal 1111f nt1nanc1 act1v1ti1s, fnsp1ctions, rep*ir and r1pl1c1111nt of pr1ncfp1l items of 1quipm1nt related to nuclear _saf1ty. levENTSj

c. ~ REPORTABLE eeetJRRENtes submf tt1d to th1 Conaissf on.

d. Records of surv11111nc:a act1v1ti1s, inspections and calibrations

.-.qul....S ~ these Technicil ~pec1f1cat1ons.

e. oc:1..~go~

f. Records of changes 1111d1 to Operating Proc1dures required by Spec1f1cat1on 5.8.1.

g. Records af r1d101ctive shipments.

n. Records of s11l1d saurc1 and fission detector leak tests and results.

1. Records of annual physical inventory of 111 s11l1d saurc1 mat1r1al of record.

~--..:.:..::.:....,::..:.--......----~----'--::-------~------~~--~~~~~~~-------...

/ j- ~urolr. o F r~vi~1<.1s p~rt;,.,.,,cJ For "-4~" ~ 1r> l°~6'"t~s or r~~ie..x o-F ~fs

. '""-..__ and BJ(peril'V1S"'+.s/ ,.ur,ua.11 r t'o tOt:.f'R,G'D.G'I.

SALEM - UN tT l S-2l Am1ndmen.t Na. 59

NLR. - N'lll'B

• The F xy INSERT TO SECTION 6.9.1 RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.9 limits for Rated Thermal Power (FRTP) for all xy core planes containing bank "D" control rods and all unrodded core planes, and the plot of predicted heat flux hot channel factor times relative power (F~*PREL) vs. Axial Core Height with the limit envelope shall be provided to the NRC Document Control-Desk with copies to the Regional Administrator and the Resident Inspector. The Report shall be provided to the Commission upon issuance.

In addition, in the event that the limit should change, requiring a new submittal or submittal of an amended Peaking_ Factor Limit Report, it will be submitted upon issuance .

• With the reactor trip system brea~era in the closed po*ition and the control rod drive aystem capable of rod withdrawal.

• • The channel(*) as*ociated with the protective function* d~rived from the out of service Rea~to~ Coolant Loop shall be placed in the tripped condition.

I The proviaions of Specification J.0.4 are not applica~le.

High voltage to detector may be de-energized above P-6.

I## If ACTION Statement l ia entered a* a re*ult ot Reactor Trip Breaker (RTB) or Reactor Trip Bypas* Breaker (RTBB) maintenance te*ting re*ult*

exceeding the following acceptance criteria, NRC reporting *hall be made in accordance with Specif icatio~

. ~~~

l. A RTB or RTBB trip fai ure during any *urveillance te*t with le** than or equal to JOO gram* of weight added to the breaker trip bar.

2. A RTB or RTBB time re*pon1e failure that reault8 in the overall reactor trip ay1tem time reapon*e exceeding the Technical Specification limit.

ACTION STAT!M!jNTS ACTION l With the number of channel* OPERABLE one l*** than required by th* Minimum Channel* OPERABLE requirement, b* in HOT STANDBY within 6 houri; however, one channel may be bypa11ed for up to 2 hour* for 1urveillance te1ting per Specification 4.3.l.l provided th* other channel is OPERABLE.

ACTION 2 With th* numb*r of OPERABLE channel* one l*** than the Total Nwnb*r of Channel*, STARTUP and/or POWER OP!RATION may proceed provided th* following condition* are 1ati1tied1

a. Th* inoperable channel i* placed in the tripped condition within l hour.

b. Th* Minimum channel* OPERASLZ requirement i* met; however, one additional channel may be bypa***d tor up to 2 hour* for

• urv*illancs t**ting per Specification 4.3.l.l. ctolJce]

c. lither, TDRMAL POWER ii re*tricted to ~ 75' of RATED THJ:RMAI.

and th* Pow*r Range, Neutron Plux trip **tpoint i* reduced to S 85\

ct RATED THERMAL POWER within 4 hour*1 or, th* QUADRANT POWER TILT RATIO i* monitored at lea1t enc* per 12 hour*.

d. Th* QUADRANT POWER TILT RATIO, ** indicated by th*

remaininq three d*t*ctor1, i* verified conaiatant with th*

_ normaliz*d 1yanetric power di*tributicn obtained by u*inq th*

mov&Dl* in~cor* detector* in the tour pair* of *ymmetric thim.bl*

location* at lea1t once per 12 hou'ra when TDRMAL ~R i* i;reater than 75' of RAT!D THERMAL POWER.

SALIM - tJNI'1' 2 3/4 3-5 Amendment No. 96

rJ 1-R. _, N.C/llCB

4. e ACM[NIS~Ai!VE CON~OLS

1. Typ1 of cant11n1r (1.g., ~SA. Typ1 A, Typ1 B, ~1rg1 Qu1nt1ty), ind

f. So11d1f1,at1on 191nt or ibsorbent (1.g., '11119nt, urt1 fonnald~yde).

Th1 R1d101ctive Ef1'1u.ni R1le1s1 Reports sn111 include 1 11st of d1s,r1pt1o~f unpl1nn9d .-.l11s1s frfJll the s1t1 to UNRESTRICTED AREAS of r1d101c:t1ve mat1r1als 1n gaseous Md 11qu1d ef1'1uets radl during th* ~ort1ng per1od.

Th1 R1d101c:t1ve Ef1'1u.ni R1l11s1 R1ports sn111 fnclud1 llf'1 ch1ng1s 111de dur1ng the .-.,ort1n9 ~1r1od ta the PRoctSS CONTROL PROGRAM {PO) &nd ta th1 OFFSITE DOSI CALCULATtOJt MAii.JAL. {OOOt), u .. n u a 11st1ng of new locations for dose alculat1ont &nd/or tnY1ro.-.rta1 mn1tar1ng fdant1f19d by the hnd uSI cansus pursu&nt ta Spec1f1at1on 3.12.2.

"'SE>E :J::t'tlsee.T,,.. U.S. Nu.clff"lf.r K~:.u..,n,ry C..""1,,,,;s-;;,,,,,

$,!C?AL REPORTS } ~u"'1f'rtf- _C.O-;!-ro/ ()rs.~, iJa.sJ,;-,.,J"!bn

. O.C., ~o,s:.;-5, virl, ~ c:.ofJy-+i.+l,e 5.9.2 Spec11l r'ICIOrts shall bl subll'ittld to th1 Adll1n1stratorl 9ff1M w1th1n the t1* P1r1od spec1f11d for ucn report;:.;.*=----""'--..---:-,

5.10 R!CCRD REl!NrtON I 'vSrJ~C QO~jetl r I tn add1t1an ta the 1pp11wlt .-.cord .-.ttnt1an 1"9qU1,...nts of Tftl1 10, Codi of Ftd8ra1 R1911at1ons, th* fo11a-1n9 rKal"dS !!1111 bl .-.~n9d for 1t least tile 111n1- p1r1od fnd1ated. /o.'

S.i.0.1 The follawfnt rtCOrdS Shill bl reUinld for It ltlSt fh1 yHn:

• • ,..,.1.

RICOrdS Md 1091 of unit operat1an COftr1ng t1m fnterval It 11dl ~~'"

t:I. R8COl"dl llld lats of pr1nc1pi1 111fnt1n1nc1 1ct1v1t11s, 1nspect1ans,

~*1r and .-.plic...ni of pr1nc1p11 ft ... of 1qUfpa11~ r-tl1tld to c.

d.

macl~r 11f1t1~ENT'~

ll!JIOITAIU -B1111sZs sulllli ttl<I to ell*

R8COl"dl of SUl""le11lanca IC't1v1t1es, 1nspect1ons and C-1 ss1 on.

~11br1t1ans I D~LE';eol ,..qu1 l"'Wd b1 tt1n1 1"tdln1a1 Sp.c1f1cat1ons.

• - ~M*ra ef ,.....,. tHh *11* ..... ~iw**

r. RecordS of ch&nges 1111d* to Op*rat1 ng Procedures r-equ1 red t:ly Spec1f1at1an 5.8.1.

g. Records of r-1d101ctfv1 sh1""8ftts.

l'I. Records of snlld so~* and f1ss1on detector ltu tests and ruul:s.

1. Records of 1nnu1l ~nysfcal inventory of 111 stiled sour-ca rn&tar-111 of 1"9COrd.

_.Recorols o~- r- 11 ;-t!i..JS f'"r F-r,.,,ec/ ;:;.; c),"'n1'1$ A'l-le "to fH*oc*'e.41"tos or ~viec...'"~

oq ....._ ---------------.

_o+ "tests ~ ~,rper~~11ts, pur,ut:a11f "t"o /OC~*S'l --- )

SALEM

• UNIT Z 5-21 Aalendmnt Na. ZS

• INSERT TO SECTION 6.9.1 RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.9 The Fxy limits for Rated Thermal Power (F~~P) for all core planes containing bank "D" control rods and all unrodded core planes, and the plot of predicted heat flux hot channel factor times relative power (F~*PREL) vs. Axial Core Height with the limit envelope shall be provided to the NRC Document Control Desk with copies to the Regional Administrator and the Resident Inspector. The Report shall be provided to the Commission upon issuance.

In addition, in the event that the limit should change, requiring a new submittal or submittal of an amended Peaking Factor Limit Report, it will be submitted upon issuance *