ML18096A256

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Proposed Tech Specs 6.5.1 Re Station Operations Review Committee
ML18096A256
Person / Time
Site: Salem  PSEG icon.png
Issue date: 09/10/1991
From:
Public Service Enterprise Group
To:
Shared Package
ML18096A254 List:
References
NUDOCS 9109180124
Download: ML18096A256 (9)
v • d • e


Text

TA.BLE 3.3-1 e

rcor.t:i.:--:..:ec l TABLE

~10TATION With the reactor trip system breakers in the closed position and t:he 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.

      1. If ACTION Statement 1 is entered as a result (RTB) or Reactor Trip Bypass Breakers (RTBB) l exceeding the following acceptance criteria, j--t'in accordance with Specification.r6.9.l.9.

I"* 9. al of Reactor Trip Breaker maintenance testing results NRG reporting shall be made ACTION l -

ACTION 2 -

ACTION 3 -

l. 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 ~xceeding the T~chnical Specification limit.

ACTION SIATEHENTS With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STA...~DBY 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.l.l

,provided the other channel is OPERABLE.

With the number of OPERABLE channels one less than the Total Number of Channels, STARTIJP 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 surveillance 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 setpoint 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 />.

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

SALEM - UNIT 1 3/4 3-5 Amendment No.

114 9109180124 Qj09t0 PDR ADOCK 6~o6b~72 P-PDR

AOMUHSTRA T!'/E CONTROLS i.S REVIEW ~NO AUO!T_

6.-S.l STATION OP~RATJO~S REV!E\\ij COMMITTEE (SORC)

F'UNCT!ON 6.5.l.l The Station Operations Review Committee shall function to adviSe the General Manager - Salem Operat-ions on operational matters related to nuclear safety.

COMPOS IT! OH 6.5.l.2 The Station Operations Revie~ Committee (SORC) shall be composed C)f:

Chairman:

~lf!Der aAa Viee CAairman:

Member and V1ca Chairman:

Member and Vice Chairman:

~

~Member and Vice Chairman:

~ember:

"embel" 1

  • M'elftbe,. :

Member:

. Member:

Member:

ti4eRIBePt Member:

ALTERNATES General Manager - Salem Operations AssistaRt GeReral MaRageP

  • Salem O~erat1eRs Maintenance Manager Operat1ons Manager Technical Mana99r*

Op*rating Engineer t & *c ERgi R**r Seniel" Nueleal" Shift S1;119eJ"visafP Technical Engineer Maintenance Engineer

. r:;;:J Radiation Protection Engineer~

Chemistry Engineer 14anageP'

  • On Site Safety Review Gret11'~

e,. Ai s aes1 gRee, 5.5.l.3 All alternate ITl!mbers shall be appointed in writing by the SORC Chairman.

I :tr'sE £T ~.~-a-a...

, -.lf-'1~1 eee_ !--l::rb.ff-A a.:a iHP!.ffNl!ft.A ~SHA...aa~l +1 -t"H*~mel!!miRMlfi-,.,,1 ~aHf~S&ot a1:itr11~a.,..A-1m:RCalfAh1a,e~e1MP.11!ill. tf!Aint *

b.
c.

d *.

~ rrare than t'lllO alternates to members shall participate as voting IT'l!mbers in SORC act1~it1e~a any one 119eting.

S Sita.II 5

AlternatiV"appeiAtees w11~ only represent their respective departmen~

Alternates forrrembers will r1>t make up part of the._.,ting quarumwnen the 1119mbers the alternata represents 1s also present.

MEET!NG FRE O.JEMC Y 6.5.l.4 The SORC shall meet at least once per calendar rmnth and as conven~ by by the SORC Chairman or his designated altarnate.

O.JORUM 5.5.l.5* The mininw.1m quorum of the SORC necessary far the performance of the SORC respansib111ty and authority provisions of these technical specifications shaJl c:ansist af *tne Chairman or his designated alternate anftft~ lll!mbars including alternates.

r r11111A,-

SAL£M - UNIT 1 5.7 Amendment No. 62

Insert 1 to p. 6-7 Member:

Radiation Protection/Chemistry Manager Insert 2 to p. 6-7

a.

Only designated Vice Chairmen or the General Manager - Salem Operations may act as Chairman of a SORC meeting.

l

==~=:=~======~================--=\\

a.

l~";r, a. 1oc.FR.S'O*S'1 s.afe+t ellt:4/uqflo,,

Review of: (:J Stae;o,., *a,,.;"'l;stra:ive; ::'eeii::.* es

'": :*a~;es :-.;-~-

and (2) Newly created orocecures or :~a,.,ges toe is::.. ; :-::::_-.;:

tnat as ~escr oea ;,.. Sec:***

6. 5. 3. 2. d.

Upper +te:r a.d1r11'tlls +rQ,+1'11e prot:ecfures,,.,,,.

n ~e se:o e oF ~

u.l~f,,ry Guide I* "33 {~li'B )J cir.~s.,li~,..~fb. +/,4 T re~";~.:a.

1oc/:f~ ¢.5't:J Sa.Pe.

  • e v4fu.o. f,a,,
b.
c. '
d.

~eview of all crocosed tests ana e-xcer;ments cnat af.*eco; "'u:'e:r-safety.

Review,of ail crocosed cnangu to.Acptndix "A" recMica1 Scec.ifications.

Review of all crocost~ cnang1s 6r modifications :o olanc sys:ems --

eauicment tl'!a~ affect nucl.ear safet~.

e.

Review of tht safety evalu1tions tha~ have bttn comcletea ynoe,. :*e provisions of 10 CFR 50.59.

f.

Investigation of all 1iiolations of tnt T1cnnic:1l Scecificatioris including tl'lt 8Pt8&P1;i;A a~~ f;~11P~i~1 ef reports covering 1va 1 u1ti on and reconm1nd1ti ons to cr1v1nt r1curr1nc1 u 011 'J; ee-P*11; ;1At IA~ C~i~ ~w;l11P Qffi;1p &Ad ;~1 ;1AtP1l ~aAage*

  • N~el1aP §afecy ~1vi1w.
g.

R1vi1w of all REPOR'!'ABLE EVENTS.

nL R1vi1w of f*cility operations to d1t1ct pot1nti1l nuclear safe:1

~az1rds.

i.

P1rform1nc1 of satc:ial r1vi1ws, *invtstigaticins or analyses anc reaorts tn1r1on as r1au1st1d by the G1n1r1l M1n191r

  • Silem Ocierations. ** 6itl'llPl1 ~artattP' N~el11P Safety RIV'+tw-:-
j.

Review of tnt Facility Security Plan and implementing procedures :*:

le proceaures

~&+4Nf~ffffHtfi~Wfl, or-

,"nr>o/v~ a.. P*~l'lrital

~eri?a$e ;.;i e

eF+:.tfr.f,*llf!;'rtes:, oF ~

p/u, p~,. IOC ~.e 54.S( ft

. 1.*

Review of tn1 Ftr1 Protection Program and impltm1nting croceaures i-o-~~1~n~d~!HHHM"'"'..--e-1~~:0ftl11tetitei~*eeft~~*rt~t~*~1~t~o~t~~*...-;6~1~rt~*~P'tlT14M~1HP1~1~9~*~~--

rn.

Review of 111 unghnned on*sit1 r11tas1s of *1dio1c:tivity t~ ':~e environs including th1 crec1r1tion of r1corts cov1rtng evaiuat~c~.

~econm1nd1tions ind discosition of th* corr1ctiv1 action to oreve~:

recurr1nc1 IAI& ;1!11 fa*ward1AI af tAHI PllGP"U U -tAe Vi-ce O-u' ae:

i~~ '~ilf Nw;l HP<lfhffl' IRi... RI S~AIJ'll flil&Mte'

~l~cleu !ja;;K..,.

R1vi11111.

SALEM

  • UNIT l 6-8 Amendment No. 99

/6-. s: -:l. LI

)AFET'f FU/JCT/ON

'J~fit Sri~, jQ~~~lQ i i)'itim Q.;

Q'oii

~**9; cg*,..;]\\f@CS :c9m j:... :c :::=c*:.:*

ei=§aF1ii!atiei:is ta i1u1giiiant *-* **q;iac:'se 'o :~e a's:*a* *oes a.;~:::*:

~weh Ql:ialifieeJ r:e'c'iewers ina 1 i mee: :.'ie safflle euaii*i:ati:r.

!... :J

'!.ri@

~JS~ staff, al"lel,,;11 r:i;t hilli ':iiO '0"9'.*,reg ii:n sec*eF"RaRee sf:.-::**::**~*

1181"1(.

-~e :4al"lage'"

Qff Siu Ri 1i;i\\lj an'1 Staff st;:iall _i~eet ei= e)(eeee ':ii:le eioiaiifieat:ieRs eesei=iee'1 in ~eetier:i 4.7 ef.~~JS 3.1(1981) al"la s'"la~

1 :e :~'::e:

~Y tre e,:9yi5iens fei= iF1aeseF19el"lt Fe¥ie\\~ ~eseri~ee il"I Sec:io~ ~.3,, ~~s:

Nli,7 (:g-5) (HIS J,£), Tbe MaRa~ei= -

GF1 Site qe 1,*ie*11 al'lt! staH,.;**"'lee!~

eY :aee tr:ie awil i fi eiti er:is aesei=i see i F1. Seeti el"I 4. 4 ef MJS 3.1 ( i381).

CONSULTANTS oy Hie rJ~lt!Ar "1..tt7 Depa.rf~rrf tie e.¥1'-n'f nee.er;~ ry 6. 5. 2. 3 Cons u 1 tan ts sh a 11 be u ti 1 i zed ~s::E~;ff~'*"H~..;;;.-&-..J~~:.e.l....!ii.~;o.Q.;::..__.

Nuel eu Safety ~e*;i e\\~ ta 13Pe.,*i ae )(13el"t

) o FFls m REV I Ewicncwr I (osR) I

. J,;..FFI 6.5.2.4./nie OH Site ~e*,*ie*.~ 'di=;w; lasR/.shall function to provide incieoe,.,~er-:

review and audit of designated activities in the areas of:

a. Nuclear Power Plant Operations
b. Nuclear Engineering
c. Chemistry and Radiochemistry
d. Metallurgy
e. rnstrumentation and Centro l
f. Radiological Safety
g. Mechanical Engineering
h. Electrical Engineering i. Quality Assurance
j. Nondestructive Testing
k. Em*rgency Preparedness Tiqe OSA shall ahe f~P'leti eP'I te e><alfli l"le !"liP'lt oe,.ati A9 el:lu*aetui sties. *:=:

4ss~aP'lel9, iP'ld~!tPy adv~!erie!, LieeP'l!ee EveP'lt Re!"ePt!,

aP'I~ et~e,. se~re:s 11l:lieR ~ay i~ai61te aPaas feP i~~PeviRi ~laRt safaiy.

SALEM - UN IT 1 6-9a Amendment No. 99 1

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 o~t of service ~eacior coolant Loop shall be placed in the tripped condition.

I The provisions of Specification 3.0.4 are not applicable.

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

      1. 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, NRC reporting shall be made in accordance with Specification1G,9.1.94 1~.t?.a\\
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.

ACTION STATEMENTS ACTION l With the number of channels OPERABLE one leea than required by the Minimum Channels OPERABLE requirement, 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 />; howeve*r, 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.l.l 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 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 i* 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 aurveillanca 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 **tpoint i* reduced to S 85\\

of RATED THERMAL POWER within 4 hour*1 or, the QUADRANT POWER TILT RATIO i* monitored at lea*t once per 12 hour**

d.

The QUADRANT POWER TILT RATIO, a* indicated by the remaining three detectors, i* verified con*i*tant with the

_ normalized *ymmetric power distribution obtained by u*inq the movable in-core detectors in the four pair* of *ymmetric thimble location* at least once per 12 hour* when THERMAL POWER i* greater than 75\\ of RATED THERMAL POWER.

SALEM -

UNIT 2 3/4 3-5 Amendment No. 96 l

ADMINISTRATIVE CONTROLS 5.5 REVIE~ ANO AUDIT 5~5.l STATION OPERATIONS REV!E\\il COMMITTEE (SORC)

FUNCT!QN.

6.5.l.l The Station Operations Review Committee shall function to advise ~he General Manager* - Salem Operations on operational matters related to nuci*ear safety.

  • COMPOS!T!ON 5.5.l.2 The Station Operations Review Connittee (SORC.) shall be composed of:

Chairman:

General Manager - Salem Operations.,

~el!!Gel" aAe *viee Gl!!airmaF11 1.ssisu,.t GePleral MaPlagel"

  • Sale"' Gperat;ol"I!

Member and Vice Chairman: *Maintenance Manager *.

Member and. Vice Chairman:

  • Operations Manager
  • r=-:-.:=:-7iJ~-~..._~emeer and Vice Chairman:. Technical Manager' I
!"~SERT I

~f'llember:

Operat1 ng Eng1 neer Me!ll8eP:

I I C iA91 AeeP Meneel" !

Sen'fer Nuel ear SM ft sij~el"*d HI" Memaer:

Techni ca 1 Eng1 neer Member:

Maintenance Engineer

  • furl Memaer:
  • Rad1at1on Protection Engineer MelRBeF:

Chemistry Eng1 neer".

  • Member:.

MaFlagel" On*.Site Safet~ Review ~

tjE.-,;neer J aP lilis ees1gRee.

AL TERNATE-S 5.5.l.3 All alternate ITl!mbers shall be appointed in writing by the SORC Chairman.

j:r,.,s~RT ~J ) a.

V1ee GAaiFmeA &Rall ae All!IR8ePs af Stat1eA ~aAageAll!Ai.

b.
c.

~ 111>re than t._., alternates tO members shall participate ITl!mbers in SORC act1v1ti~t any one ITl!eting.

s; S *I Alternat~si"81ft~eu -.ill only ;epresent their respective as voting s

department?'

d.

Alternates for manmers -.111 riot make up part. of the...oting quorum when the l'llefllbers the alter"nate represents is also present.

MEETHtG FRE Q.JENC Y 6.S.1.4. The SORC shall IT'll!et at* least once per calendar rronth and.as convened by by the SORC Chairman or his designated alternate.

Q.JORUM 6.5.l.S The minimum quorum of the SORC necessary for the performance af the SJRC responsibility and authority provisions of these technical specifications snall consist af the Chairman or his designated alternate a~d ITl!mbers i_ncluding alternates.

C' T'0&4r" SALEM

  • UN IT 2 6-7 Amendment. No. 33

L Insert 1 to p. 6-7 Member:

Radiation Protection/Chemistry Manager Insert 2 to p. 6-7

a.

Only designated Vice Chairmen or the General Manager -

Salem Operations may act as Chairman of a SORC meeting.

.:. ~... :.. : : - :.:. -: :

~ ~. -: :..

~

-~--~**1* *-*--

-(:.:-...i*1

.:.~

6.5.l.6

a.
.i.

Review of safety.

'"uC *ear

c.

Review of all crocosed cnanges to Aoc1natx "A" *echn;cai

.Sctcifications.

a.

Review of all crocos1d cnang1s or moaifications to oian: s;s:e~s **

1auicm1nt tnat affect nuclear safety.

e.

Review of tn1 safety evaluations that nave betn comcletea ur.:e~ :-e grovisions of 10CFRS0.59.

f.

Investigation of all violations of th* T1chnic1l Sctcificat;~r.s including tn1 1Pe11,1cia~ aAi fa....,a,iiAt ef reoorts covering ev1luuion and reco"'"endations to gr1v1nt r1currenc1 u till* '/iee o,e9ii1At aA* ~nief ~lw&l11, Qffi11, aA~ t~* 61A1,al Ma~a 1 e, N~elti' Safety R1view,

g.

R1vi1w of all REPORTAB~E EVENTS.

n.

Rtvitw of facility ogerations to d1t1ct got1ntial nuclear safet 1 nazards. *

i.

c1rform1nc1 of so1ci1l reviews, investigations or analyses ano rtoorts thereon as rtQu1st1d by* the General Manager

  • Saiem Oc1rations.1, G1At,1l ~IA191'
  • Nw;l11, $~f*'Y R1vi1w.
j.

R1vi1w of the Facility Security Plan* and imoltm*nting croceau~es ~'":

oi :11110I~ -

p.fe111f~/

flcr~r,*,,

or Ht~ /4;,, P*r 1oe,.R St:>.G~ ft).

1.

Review of the Fire Protect on ro9ram and imoltm1ntin9 croceaures

--~~~a-n-d~lwD*i,,11 ;f Pee1111111~Gli EAa~91s ta tn1 ;IAIPll ~1Aa91F.

N~cl11r S1f1t1 ~11itM.

m.

R1vi1w of 111 unolanntd on*sit1 r1l1as1s of radioactivity to :~e environs including tn1 or1garation of r1oorts covering 1vaiu1t*:'".

r1con1111nd1tions and disoosition of the corrtctiv1 action to ore,,e,.:

r1currtnct IAi *;1111 fe,.w.,ii.........,. t~IH 1'1H'H U 01 Iii c* :i-u * :i 0 :

aa~ '~itf Mwelti' Qffiet' *~i 1~1 Q1~1Pal ~*A*t*'

N~e'taP Sai::,

A.1*:; *~*.

SAi.EM

  • UNIT Z 6*8 Am1ndm1nt No. 76
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