Text

Proposed Tech Specs 3/4.3.1 Re Reactor Trip Sys Instrumentation,Lco,Action Requirements & Surveillance Requirements & Associated Tables
	ML18096A695
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Site:	Salem
Issue date:	05/06/1992
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ML18096A691	List: ML18096A690; ML18096A693; ML18096A695;
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ATTACHMENT 2 MARKED UP PAGES

(./)

Pl n>

TABLE 3.3-1 (Continued) 3 c:

REACTOR TRIP SYSTEM INSTRUMENTATION

J MINIMUM rt TOTAL NUMBER CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE HODES ACTION

11.

Pressurizer Water Level--High 3

2 2

1, 2 11

12.

LOBB of Flow - Single Loop 3/loop 2/loop in 2/loop in 1

11 (Above P-8) any oper-each oper-ating loop ating loop

13.

LOBB of Flow -

Two Loops 3/loop 2/loop in 2/loop in 1

11 (Above P-7 and below P-8) two oper-each oper-w ating loops ating loop

.i:.

14.

Steam Generator Water Level--

3/loop 2/loop in 2/loop in 1, 2 11 w

Low-Low each oper-I any oper-w ating loops ating loop

15.

Steam/Feedwater Flow Mismatch 2/loop-level 1/loop-level 1/loop-level 1, 2 11 and Low Steam Generator Water and 2/loop-coincident and 2/loop-Level flow mismatch with flow mismatch 1/loop-flow or 2/loop-mismatch in level and same loop 1 /loop-flow mismatch

):lo

16.

Undervoltage-Reactor Coolant Pumps 4-1/bus 1/2 twice y3 1

6 5

J

0.

17.

Under frequency-Reactor Coolant 4-1/bus 1/2 twice

/3 1

6 5

J Pumps rt z

0 w....

DI.

ID El c:

I....

w

~

w I

~

i

J

a.

Hr

J r+

z:

0 w....

TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION FUNCTIONAL UNIT

18.

Turbine Trip Q, Low Autoatop Oil Pressure

b. Turbine Stop Valve Closure

19.

Safety Injection Input from ESF

20.

Reactor Coolant Pump Breaker Position Trip (above P-7)

21. Reactor Trip Breakers

22. Automatic Trip Logic TOTAL NUMBER OF CHANNELS 3

4

.2 l/breaker 2

2 CHANNELS TO TRIP 2

4 1

2 1

1 MINIMUM CHANNELS OPERABLE 2

3 2

1/breaker per opera-ting loop

.2 2

APPLICABLE MODES 1

1 1,2 1

1, 2 ACTION 11 7N 1

11 1111, 14 3*,4*,5*

13 1, 2 3*,4*,5*

1 13

~I..,

J J

I TABLE 3.3-1 CContinu~

TABLE NOTATION With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

The provisions of Specification 3.0.4 are not applicable.

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

1. 1. If ACTION Statement 1 is entered as a result of Reactor Trip Breaker (RTB) or Reactor Trip Bypass Breakers (RTBB) maintenance testing results exceeding the following acceptance criteria, NRC reporting shall be made in accordance with Specification 6.9.1.9:

ACTION 1 -

ACTION 2 -

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 STAIEHENIS With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4. 3.1.1 provided the other channel is OPERABLE.

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b.

-*;~..,-

The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.

c.

Either, THERMAL POWER is restricted to < 75t of RATED w'-~ ~and the Power Range, Neutron FlWc trip setpoint fO is reduced to< 85t of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least

.~/(VLJ---~-------------------------0-n_c_e_* ~p_e_r __

1_2_h_o_u_r_s_. __ ~

tJ"-"' 1 t1~

1~

With the number of channels OPERABLE one less than required J

by the Minimum Channels OPERABLE requirement and with the

~

THERMAL POWER level:

SALEM

UNIT 1 3/4 3.5 Amendment No.

114

3 (12.0"'

7';.aL: J.3-1 tc:~:*.,!.Oe-:'

ft c n o 4ll fll~rJiovs P~a°:-e3elow ?-6, restore t!'le incperable c~annel :o *:?S~).3L~

status prior to increasing 7HERMAL POWE~ abcve

~e ~-6 Setpo int.

b.

Above P-6 but below S~ of ~ATED THERMAL POWER, res::re the inoperable channel to OPERABLE status prior to increasing THERMAL POWER abQve.5~ of RATED THERMAL

?C~E~.

c.

Above 5~ of RATED THERMAL POWER, POWER OPERATION may continue.

ACiION 4 - \\.lith the number of channels OPERABLE one less than required

'by the Minimum Channels OPEAABLE re<;uirement and with the THERMAL POWER level:

a.

B~low P-6, restore the inoperable channel to OPEAASLE status prior to increasing THERMAL POWER above

~he P-6 Setpoi nt.

b.

~bove P-6, operatiori ~ay continue.

ACTION 5 - \\.Ii th the number of channels OPERABLE one less than required by tne Minimum Channels OPERABLE requirement, verify c:m-pliance with tne SHUTOOWN MARGIN requir!ments of Scecification 3.1.1.l or 3.1.1.2, as ~cplicable, within hour and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

.=.c7!0N 6 - Wi tl'1 ene number of OPERABLE channels one less than the iota1 ~~umaer of Channels, Si~R7UP and/or POWER OPE~Ai:GN may proceed provided the following conditions al"'e sa:isf~e*c:

a.

!lie i noperab 1 e channe 1 is i:i 1 aced in c.he tri cpe<1

~ndition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b.

Tlie Minimum Channels OPE~ASLE r-equirement is :i!et; however, one additional channel may be bycassea f:r up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing ~er Specification 4.3. 1.1.

ACiraN 7 - With the number of OPERABLE channels one less than the Totai Numoer of Channels, ST~RTUP and/or POWER OPEAAitON may :iroceed until ;:ierfonnance of tne next required CHANNEL F:.;Nc7::NAL rEST ~rovided tne inoperable channel is ~iaced in :ne :ri;cec condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

SALE.)1 - uNrr 314 3-6

.. 1...

/+.C:.TI O,J '(,.

ACTION 9 -

/JO'( LJ Sf' D ACTION 10 -

ACTION 11 -

ACTION 12 -

ACTION 13 -

"9elete~ N or us£ i::>

With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 1 hour~

With the number of channels OPERABLE one less than required by

the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6"hours and/or open the reactor trip breakers.

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip.

breakers within the next hour.

ACTION 14 -

With one of the diverse trip features (Undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and be in at

.least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to

- - restore the breaker to OPERABLE status.

. DESIGNATION P-6 P-7.

SALEM - UNIT 1 REACTOR TRIP SYSTEM INTERLOCKS CONDITION AND SETPOINT With'2 of 2 Intermediate Range_11 Neutron Flux Channels < 6 x 10 amps.

With 2 of 4 Power Range Neutron Flux Channels ~ 11% of RATED THERMAL POWER or i of 2 Turbine

impulse chamber pressure channels

~ a pressure equivalent to 11% of RATED THERMAL POWER.

3/4 3-7 FUNCTION P-6 prevents or defeats the. manual block of source range reactor trip.

P-7 prevents or defeats the automatic block of*

reactor trip on: Low flow in more than *one primary coolant loop, reactor coolant pump undervoltage and under-frequency, pressurizer low pressure, pressurizer high level, and the opening of more than one reactor coolant*

pump breaker.

Amendment No.97

w -

w I

a TABLE J.J-2 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT

12.

Loss of flow.- Single Loop (Above *P-8) ll. Loss of Flow - Two Loops (Above P-7 and below P-8)

14.

Steam Generator Water Level--Low-Low

15. Steam/Feedwater Flow Mismatch and Low Stea* Generator Water Level

16.

Undervoltage-Reactor Coolant Pwnps

17. Underfrequency-Reactor Coolant Pt.111ps

18.

Turbine.Trip

. 19.

20.

Z.l t"L A.

Low Fluid Oil Pressure

0.

Turbine Stop Valve Safety Inject ton Input from ESF

Reactor Coolant Puurp Br:eaker Pos i.t ion Trip ll~A c.:roa. /fl. 1P 8R-~14Jl..~Yt-~

Av1bM 1t*nc-

'/"fC.1 P J-oc;,,1c...

RESPONSE TIME

< 1.0 seconds

<< l. 0 seconds

< 2.0 seconds NOT APPLICABLE

< 1.2.seconds

< 0.6 seconds NOT APPLICABLE NOT APPLICABLE NOT APPLICABLE NOT APPLICABLE

!Nor 1t-PP1...1 CA e t.G:'

j1.Jor IJ p Pt.. I c. IH3 L~

3/4.3 INSTRUMENTATION 3/4.3. 1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION s.~.1.1 3.3.1 *As a m1n1mum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.*3-2.

APPLICABILITY:

As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

SURVEILLANCE REQUIREMENTS i{'.-s~1._LI 4.3.1..1 Each reactor tr.ip system instrumentation channel shall be demon-

- I strated OPERABLE by the performance of.the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-1.

l-/.'3././.2 4.3.1.2 The logic for ~he interlocks shall be demonstrated OPERABLE prior to each reactor startup unle.ss performed during the preceding 92 days.

The*

total interlock function shall be demonstrated OPERABLE at least once per 18 months during CHAN"EL CALIBRATION testing of each channel affected by interlock operation.

Lj, 3.J./.3

'4.3.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months.

Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the "Total No. of Channels 11 column of Table 3.3-1.

SALEM - UNIT 2 3/4 3-1

(/)

Ill 11>

3 IAB~E 3.3-1 c:

I

(!EACTOR IHI~ SXSIEH lUSIRUMENTATION rt N

MINIMUM TOTAL NUMBER CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNII OF CHANN!LS TO IBIP OPERABLE HODES l!CTION

1.

Manual Reactor Trip 2

1 2

1, 2 and

12

2.

Power Range, Neutron Flux 4

2 3

1, 2 2 9i

3.

Power Range, Neutron Flux 4

2 3

1, 2 2

High Positive Rate w -

~

4.

Power Range, Neutron Flux, 4

2 3

1, 2 2

w High Negative Rate I

N

5.

Intermediate Range, Neutron Flux 2

1 2

1, 2 and

3

6.

Source Range, Neutron Flux

,A.

Startup 2

1 2

211, and

4

e.

Shutdown 2

0 1

3; 4 and 5 5

7.

Overtemperature AT

~

f?.

c FeYE E.eep 9peEa£ieR 4

2 3

1, 2

. )>

'l'hEee E.eep 9peEa£ieR 4

I -- 1, 3!

3 RI

I a.*

e.

Overpower AT

+

3 Qf)OEmloi.eA C-4 2

3 l! 2 6~

RI i!'11WE Leef!

I rt

'fhree Loop Opezatioft 4

1**

J l, 2 9

z:

0

9.

Pressurizer Pressure-Low 4

2 3

1, 2 6

10.

Pressurizer Pressure--High*

4 2

3 1 I 2

6 0

(./)

Ill ro 3

TABLE 3.3-l {Continued) c::

J rt f!EACTOR TRIP S)'.SIEH INSTRUMENTATION N

MINIMUM TOTAL NUMBER

. CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE HODES ACTION

11.

Pressurizer Water Level--High 3

2 2

1, 2 11

12.

Loss of Flow -

Single Loop 3/loop 2/loop in 2/loop in 1

71 *

(Above P-8) any aper-each aper-ating loop ating loop

13.

Loss of Flow -

Two Loops 3/loop 2/loop in 2/loop in 1

71 (Above P-1 and below P-8) two aper-each aper-a ting loops a ting loop w -

14.

Steam Generator Water 3/loop 2/loop in 2/loop in 1, 2 71 w

. Level--Low-Low each aper-I any aper-w a ting loops ating loop

15.

Steam/Feedwater Flow 2/loop-level I/loop-level I/loop-level 1, 2 71 Mismatch and Low Steam and coincident and Generator Water Level 2/loop-flow with 2/loop-flow mismatch I/loop-flow mismatch or mismatch in 2/loop-level same loop and 1"'

I/loop-flow 3

mismatch t1)

I

0.

3 I6.

Undervoltage-Rea~tor Coolant t1)

J 4-I/bus I/2 twice

/s I

6 rt Pumps

z 0

Under frequency-Reactor Coolant I1.

Pumps 4-1/bus

. '1/2 twice

/3 1

6 0

i i

" f....

0 w.

PUNCTIQNAL UNIT

18. Turbine Trip

a.

Low Auto*top Oil Pre**ure

b.

Turbine Stop Valve Clo*ure

19. sa~ety Injection Input frG11 SSW

20. Reactor Coolant Puap Breaker Po*ition Trip tabov* P-la

21. Reactor Trip Breaker*

22. Automatic Trip Logic TABLI l.l-1 feontinued*

REACTQR TRIP &JSTIH INSTBUHINTATIQN TOTAL NUHBIR or CllAftNIL~.

l 4

2 l/breaker 2

CJIANNILS TO TRJP 2

4 1

2 1

1 HIN I HUH CHANNILS OPIRABLI 2

l/breaker per opera-

t. ing loop 2

2 APPLICABLE HQDES 1

1 1,2 1

1, 2 l*,4*,5*

ACTION 11 11 1

11 1111, 14 ll 1

ll It

l.,..

\\ J.

~*

q TAS~~ 3.J-1 IConti~ued)

TABLE NOTATION With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

The provisions of Specification 3.0.4 are not applicable.

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

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 Specification 6.9.1.9:

l.

A RTB or RTBB trip failure during any surveillance teat with leas 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 1 With the number of channels OPERABLE one leaa than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b.

The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for aurveillance testing per Specification 4.3.l.l.

Po 1..J £ >2-

c.

Either, THERMAL POWER is restricted to ~ 75\\ of RATED THERMAL "-

and the Power Range, Neutron Flux trip setpoint i* reduced to ~ 85\\

of RATED THERMAL POWER within 4 hour*1 or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hour*.

d.

Th* QUADRANT POWER TILT RATIO, a* indicated by th*

remaining three detectors, is verified con*i*tant with the

_ normalized symmetric power distribution obtained by u*ing the movable in-core detectors in the four pair* of *ymmetric thimble locationa at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when THERMAL POWER is greater than 75\\ of RATED THERMAL POWER.

SALEK -

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

TABLE 3.3-1 (C~nt~nued) f}e*notJ.- w;th the number of channels OPERABLE one less than required by the M1nim1.111 Chann*ls OPERABLE requirement and ~itn the THERMAL. ?OWER l1vel:

!ii'1C'~ i:.r.1 ~-a (!tea of Saur:a ~a!l;a. ~uc:o;- 'l"ri;:) H'!,oi,,t, ras::are :ne t,,001r1at1 ch*nntl co Ol'!.Ua&.! seacus,:-for r:-~

tncrustng TWt~MAl. l'O~ER aba*11 cn1 ~-6 Slc=iatnc.

b. Above th* P-S (Block ot Saurc1 ~**c:ta~ Trip) sec~at,,t out 0110\\f

51. of RAT!D THDHAL POWER, restart tn* t,,ap1r1bl1 ar1nn1t ea OPERAIU: sutus priar to* tnc:rus1ng THERMAL POWER *bav1 SS of RA T'ED THERMAL POWER.

c. Aboft SS af RATED THERMAL POMO, P01G OP!JUTION-., cant1nu* *

d. Abaft tas af IUTID THEUW. POWIR, tJt9 praY11fans at SpKtttcat1an 3.0.3 lr9 not.,,11~1 **

ACTION 4 * *wttJT th* number at dwvlel s OPERAILI on* lut thu,..qu1 rad by tn*

Mini.. Qwmel s OPOAIL!,,qut 1 K tftt ancl wt t!I tltl THERMAL PO'.ilER ltftl:

81la.i. thtt *-t (Ila of Soul"C9 Range Aeacto,. Trip) secpotnt,

.-.su... tit* t n$rabl 1 dtunel ta OP!RABU suta pr1 or ta tnCl"IU1ftf THIMAL PaWll &bave t!le P*f Setpatnt.

. b. Abaft tit*,_, (11aa af Saurc1 Auge R11cta,. Trip) s1tpatnt, operation _, caattnue.

ACTION 5

Wftb th* tnlltl..- at ctwtnels QP!RASU: one less tnan ~tr.t ti, th*

Mt nt.. Qlune11 QPD..*111 rtq111 rwnt. ver1 f-t =mpl t 1nc:a w1 th cne SHUTDQ\\lt ~GIN.-..Ufl"llllllCS of Speciftcattan 3.1.l.l or 3.1.l.Z, lS 1pp11c:1~le, witntn 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 111d. 1c l11st anc1 per lZ haurs cner**ftar.

ACTtOft 5 - t41ttl tn* malb1r at QP!RAIU dl*n,,*h 011* lass cn1n cne T'at1l ~wnb*r of Qtlftftels, STARTUI' flld/ar POWER OPERArtON 1111 prac1ed ~rov1dld Chi fol1.cw1ng ccncl1ttons.,.. s.tt~ftld:

a. 11te tnaper&ble dlannl ts phCICi tn tn* tripped ecndtttan w1th1n 1 ltaur.

b.

1'1'11 M'fn1=m Ollftnel OP!RAll.! rtqUtr.-nt is *t; l'law*Yer, one ldctt Cfan*l dlunel 11a1 ~ ti,p1ssed far UCI ta Z tiours far surv*f 1l 1nca tuttftf per Spect ftcactan *4.l.1.1.

ACTION 7

Wf ttl tit* nullb1r at OP!.'UILE dt1nn*ls one llss tttu ttt1 iacal Nwneer of Olun*ls, STARTUP 111d./ar POWO OPERATION m&y ~rcc1ed u~11 perfa,,_,.c:a ot tit* neg,..qutr-ff OWtNll. FUMCTtO"AL. TEST prov1dld cne tnaper&bl* dlannel is pl1cad tn t?t* trippld cand.1t1an with l hour.

SAUM *UNIT Z 3/4 3.a Amndment Mo. ZS

A ~TIDiU g ACTION 9 A.Joi USeO ACTION 10 -

ACTION 11 -

ACTION 12 -

ACTION 13 -

'Cont.::.:1Ueaj Dela tei?.-

IV o "J U S e t>

With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the reactor trip breakers.

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within the next hour.

ACTION 14 -

With one of the diverse trip features (Undervoltage or shunt trip attachment) inoperable, restore it to OPE..~LE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to

- restore the breaker to OPERABLE status.

DESIGNATION P-6 P-7 SALEM - UNIT 2 REACTOR TRIP SYSTEM INTERLOCKS CONDITION AND SETPOINT With 2 of 2 Intermediate Range_11 Neutron Flux Channels < 6 x 10 amps.

With 2 of 4 Power Range Neutron Flux Channels ~ 11% of RATED THERMAL POWER or 1 of 2 Turbine impulse chamber pressure channels

~ a pressure equivalent to 11% of RATED THERMAL POWER.

3/4 3-7 FUNCTION P-6 prevents or defeats the manual block of source range reactor trip.

P-7 prevents or defeats the automatic block of reactor trip on:

Low flow in more than one primary coolant loop, reactor coolant pump undervoltage and under-frequency, pressurizer low pressure, pressurizer high level, and the opening of more than one reactor coolant pump breaker.

Amendment No.

74

ML18096A695

Text

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