Text

Proposed Tech Specs Re Surveillance Test Intervals & Allowable Outage Times for Instrumentation Increase
	ML20101L913
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Site:	Perry
Issue date:	06/29/1992
From:	; CENTERIOR ENERGY
To:	;
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ML19311A938	List: ML20101L913; PY-CEI-NRR-1496, Application for Amend to License NPF-58,revising TSs to Increase Surveillance Test Intervals & Allowable Outage Times for Instrumentation.Ge Proprietary Documents Supporting Request Encl.Ge Documents Withheld;
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Attech cnt 2 PY-CEI/NRR-1496 L 3/4.3 INSTRUMENTATION Page 1 of 50 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reacte protection system instrnentation channels

. shown in Table 3.3.1-1 shall ba OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABILITY: As shown in Table 3.3.1-1.

ACTION:

4

a. With the number o OPERABLE channels leststhan required by the Minimum OPE (ABLE Channels r Trip System req 91 rem t for one trip system, piece the tqoperable chann (s) and/or that trip s tem in the tripped condithn* within 1 ho .

The provisions of S cification 3.0.4 are not appl able.

b. With the nu r of UPERABLE annels less than requ by the Minimum .

OPERABLE Chann s per Trip Sys requirement for bot ip systems, place at least one tr ystem** in th tripped condition wit g one hour and take the ACTION r ired.by Table . 1-1.

SURVEILLANCE RE0VIREMENTS 4.3.1.1 Each reactor protection s) stem instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL' CHECK. CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.1-1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shallibe performed at least once per 18 months.

. 4. 3.1. 3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its ,

limit at least once per 18 months. Each test shall include at least one channel per trip system 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 systen.

4.3.1.4 The provisions of Specification 4.0.4 are not applicable to the CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION surveillances for the Intennediate Range Monitors for entry into their applicable OPERATIONAL CONDITIONS (as shown in Table 4.3.1,1-1) from OPERATIONAL CONDITION 1, provided the surveillances are performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after such entry, r 4 (INSERT 2)

O ~' Aq inoperable tttannel need not bE p1'a d in the tripoed coQition where this 0$

0 wob(d cause the Trip Function to occur In these cases, theNinoperable channel N required by oo - sha11xbe restored t OPERABLE status wi 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the AC

@ Table 3x3.1-1 for tha Trip Function shall taken.

" **Thetriphttemneednot placed in the trip condition if this uld cause Z the Trip Funt on to occur. When a trip system c be placed in the ipped to condition wit causing the rip Function to occu placethetripsystem R with the most i erable channe in the tripped cond t, ion; if both systems ;

R@ have the same numblir s of inoperable hannels, place eithers trip system in ttiet gg tripped condition.

> a. a.

PERRY - UNIT 1 3/4 3-1 Amendment No. 41 .

Attachment 2 PY-CEI/NRR-1446L Page 2 of $0 i

INSERT 1:

a. With one channel required by Table 3.3.1-1 inoperable ,

in one or more Functional Units, place the inoperable I channel and/or that trip eystem in the tripped condition

within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. With two or more channels required by Table 3.3.1-1 I inoperable in one or more Funesional Units:

1. Within one hour, verify sufficient channels remain OPERABLE or tripped

to maintain trip capability i in the Functional Unit, and

2. Within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , place the Inoperable channel (s) in one trip system and/or that trip systom** in the tripped condition *, and

3. Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , restore the inoperable channels in the other trip system to an OPERABLE etatus or tripped *.

Otherwise, take the ACTION required by Table 3.3.1-1 for the Functional Unit. -

i INSERT 2:

l

An inoperable channel or trip system 'need not be placed in the a tripped condition where this would cause the Trip Function to

occur. In these cases, if the inoperable channel-is not restored to OPERABLE status within the required time. the ACTION required oy Table 3.3.1-1 for the Functional Unit shall be taken.

- This ACTION applies to that trip system with the most inoperable channels; if both trip systems have the same number of inoperable channels, the ACTION ~can be applied to either trip system.

..x

At tech:::nt 2 PY-CE1/NRR-1496 L Page 3 of 50 TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION TABLE NOTATIONS

]

(a) A channel say be placed in an inoperable status for up to urs for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip systes is monitoring that parameter.

l (b) Unless adequate shutdown margin has been demonstrated per $pecifice-tion 3.1.1 and the "one-rod-out" Refuel position interlock has been l i

demonstrated OPERABLE per Specification 3.9.1, the shorting links shall 1 be removed from the RPS circuitry prior to and during the time any control l rod is withdrawn." t (c) An APRM channel is inoperable if there are less than 2 LPRM inputs per j level or less than'14 LPRM inputs to an APRM channel.

(d) This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification 3.10.1.

(e) This function shall be automatically bypassed when the reactor mode switch is not in the Run position.

(f) This function is not required to be OPERABLE when DRYWELL INTEGRITY is not required.

1 (g) With any control rod withdrawn. Not applicable to control rods removed

per Specification 3.9.10.1 or 3.9.10.2.. '

(h) This function is automatically bypassed when turbine first stage pressure ,

is less than the value of turbine first stage pressure corresponding to 40%" of RATED T)iERMAL POWER.

1

Not required for control rods removed per Specification 3.9.10.1 or 3.9.10.2.

- The Turbine First Stage Pressure Bypass Setpoints and corresponding Allowable Values are adjusted based on Feedwater temperatures (see 3/4.2.2 for definition of AT). The Setpoints and Allowable Values for various ATs are as follows: '

T('F) Setooint (psio) Allowable Value (osio) 0=T < 212 < 218 0< AT < 50 7 190 7 196 50 < - AT~< 100 7 168 7 174 100 < AT < 170 ,_ E146 5152 <

PERRY - UNIT 1 3/4 3-5 knendment No. 29

^

l TABLE 4.3.1.1-1

' E REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 4 !

.. CHANNEL OPERATIONAL .;

i e CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH E FUNCTIONAL UNIT CHECK TEST CAL 18 RATION I *) SURVEILLANCE REQUIRED i

. -4 -

l 1. . Intermediate Range Monitors: .

a. . Neutron Flux - High S/U,5,(b) W R 2 'i 5 W R 3,4,5

b. Inoperative . NA W MA 2,3,4,5

]

2. Average Power Range Monitor:(f)

I a.- Neutron Flux - High, l S/U,5,(b) W SA 2 Setdown S W SA 3, 5 k

b. -Flow Blased Simulated y(d)(e) . SAI "), RIII 1

' Thermal Power - High S.D(h) _ ,y. 1

c. Neutron Flux - High 5 -W- q W IdI, SA 1 Y

u

'd. Inoperative NA -W q NA 1, 2, 3, 5

3. Reactor Vessel Steam Dome Pressure - High 5 46 q R III 1, Z UI-

4. Reactor Vessel Water Level - '

l Low.-Level 3 5 _M- Q R III 1, 2

5. - Reactor Vessel Water Level - .

R I8I

. t

'High, Level 8 -5 -M- q 1 !

! 6. Main Steam Line Isolation. '

4 g Valve - Closure NA 4t q .R 1

7. Main Steam Line Radiatten -

i k" High 5 -M--Q R 1, 2 03 -

8. Drywell Pressure - High 1,2(1) z 5 -M- q R(8) E'o=

.M "" <

P 9.. Scram Discharge Volume Water- >!3E-1 S Level - High o E fe

} - a. Level Transmitter S 44- Q } A(g) 1,2,5(k) wf~

Z"

b. Float Switches MA M- g - R 1,2,5(k)

i zwm . s-..-

t TABLE 4.3.1.1-1 (Continued) ,

i.

l ;E REACTOR PROTECTION SYSTEM INSTRUNENTATION SURVEILLANCE REQUIREMENTS

=

E CHANNEL OPERATIONAL CONDITIONS FOR WICH

CHANNEL FUNCTIONAL. CHANNEL CHECK TEST CALIBRATION SURVEILLANCE REQUIRED E FUNCTIONAL UNIT U 10. Turbine Stop Valve - Closure NA TQh R 1

11. Turbine control Valve fast closure Valve Trip System 011 NA MQ R 1 Pressure - Low

12. Reacter '1 ode Switch 1,2,3,4,5 Shutdown Position NA R NA

13. Manual Scram NA .

(a). Neutron detectors may be excluded from CHANNEL CALIBRATION.

h NA 1,2,3,4,5 l (b) The IRM and SRM channels shall be determined to overlap for at least 1/2 decades during each startup after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for t' at least 1/2 decades during each controlled shutdown, if not performed within the previous 7 days.

+ (c) Deleted .

, */ (d) This callbration shall consist of the adjustment of the APRM c'hannel to conform to the power values i

- calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER > 25% of RATED THERMAL POWER. Adjust the APRM channel if the absolute difference is greater than 2% of RATED THERMAL POWER.

The provisions of Specification 4.0.4 are not appilcable provided the survelliance is performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months af ter reaching 255 of RATED THERMAL POWER.

(e) This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a calibrated flow signal.

(f) The LPRMs shall be calibrated at least once per,3000_M_WD/luslog the TIP system.

(g) Calibrate trip unit setpoint at least once perQi t,n 92 days.) -

p (h) Verify measured core flow (total core flow) to be greater than or equal se dtablished core flow at the

. existing loop flow (APRM % flow).

R (1) This calibration shall consist of verifying the 610.6 second simulated thermal power time constant.

2 (j) This function is not required to be.0PERA8LE when the reactor pressure vessel head is removed 5 per Specification 3.10.1. 1

< z (k) With any control rod withdrawn. Not appilcable to control rods removed per

'. Spectfication 3.9.10.1 or 3.9.10.2. -e o > '

g (1) This function is not required to be OPERA 8tE when Drywell Integrity is not required. A7j (m) The CHANNEL CALIBRATION shall exclude the fiow referince transmitters, these transmitters shall be *On calibrated at least once per 18 months.

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l 1 Attach :nt 2 PY-CEI/NRR-1496 L Page 6 of 50 INSTRUMENTATION 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION

! LIMITING CONDITION FOR OPERATION 4 :

3.3.2 The isolation actuation instrumentation' channels shown in Table 3.3.2-1 L shall be OPERA 8LE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE 4

TIME as shown in Table 3.3.2-3.

APPLICA8ILITY: As shown in Table 3.3.2-1. !

ACTION:

a. With an isolation actuation instrumentation channel trip setpoint

! , less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable until the channel is restored to 0PERABLE status with its trip setpoint adjusted consistent with the-Trip.Setpoint value. ,

, Insert D th the number of OPERA 8LE channels less than required by t b.

Min um OPERABLE Channels per Trip System requirement for ne trip-syste . lace the inoperable channel (s) and/or that tr system in the tripp'e(condition" within one hour. The provis s of Specifica-tion 3.0.4 d not applicabin.

c. With the number o PERABLE channels less t quired by the Minimum

~rip System requ1rja6at for both trip systems, OPERABLE Channels. pe place at least one trip sten ** in tt(tripped condition within one i

hour and take the ACTION rbited br^ fable 3.3.2-1.

I 4

I

An inoperable channel need n would cause the Trip Func. n tobe placed in theIn these$d condition where this occur. ca s, the inoperable channel shall be restored to OP ACTION required by-

! Table 3.3.2-1 for that'EtABLE Trip Function shall status be taken.within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or

/ is would

- The trip systempd not be pland in the tripped condition 't

- f Function to occur. When a trip system can be p1 ed in the I cause tripped the cond Tr)ition without causing the Trip Function to occur,-place %

trip system with the most inoperable channels in the tripped conditionbif, both4ystems have the same numbst of inoperable channels, place either trig -

gystem in the tripped cadition. ,

1 PERRY - UNIT 1 3/4 3-9

Attachment 2 PY-CEf/NRR-1496L Page 7 of 50 INSERT 3:

b. With the number of OPERABLE Channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one tri! cystem,

1. Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for Trip Functions common to RPS instrumentation, and

2. Within 24 hourn for Trip Functions not common to RPS Instrumentation, place the inoperable channel (s) and/or that trip system in the tripped condition *.

c. With the number of OPERABLE Channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems,

1. Within one hour, place the inoperable channel (s) in one trip system and/or that trip system ** in-the tripped condition *, and

2. Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for Trip Functions common to RPS

instrumentation, and within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Trip Functions not common to RPS instrumentation, place

, the inoperable channel (s) in the other trip system in the tripped condition *.

I

An inoperable channel or trip system'need not'be placed in the tripped condition where thi's would cause.the Trip Function to occur. In these cases, if the inoperable channel is not restored to . OPERABLE status within the required time, the ACTION required by TABLE 3.3.2-1 for that Trip Function shall be taken.

- This ACTION applies to that trip system-with the most inoperable channels; if both trip systems have the same number of inoperable channels, the ACTION can be applied to either trip system.

Attcch::nt 2 PY-CEI/NRR-1496 L Page 8 of 50 TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATIDN ACTION NOTES (Continued)

(a) A channel may be placed in an inoperable status for up tot /6 ours for required surveillance without placing the trip system in the tripped con-dition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

(b) Also actuates the standby subsystem of the annulus exhaust gas treatment systes.

(c) Also actuates the control room emergency filtration systes in the recir-culation mode of operation.

(d) Also trips and isolates the mechanical vacuum pumps.

(e) Closes only RWCU system. isolation valve (s) 1G33-F004 (SLCS / ump A) and 1G33-F001 (SLCS Pump B).

(f) Manual initiation isolates 1E51-F064 and 1E51-F031 only and only following manual or automatic initiation of the RCIC system.

(g) Containment and Drywell Purge System inboard and outboard isolation valves each use a separate two out of two isolation logic.

(h) Requires RCIC system steam supply pressure - low coincident with drywell pressure high to isolate valve 1E51-F077. .

(1) For this signal, one trip system has two channels which close valves 1E51-F063 and 1E51-F076 while the other trip systen has two channels which close valve 1E51-F064.

(j) Isolates both RHR and RCIC.

(k) There is only one (1) RCIC manual initiation channel for valve group 9.

4 J

PERRY - UNIT 1 3/4 3-16 l

TABLE 4.3.2.1-1 h ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS 2 CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH c TEST CALIBRATION SURVEILLANCE REQUIRED TRIP FUNCTION CHECK 5

--a

~ 1. PRIMARY CONTAINMENT ISOLATION -

a. Reactor vessel Water Level - 1, 2, 3 and #

Low, Level 2 5 -M- Q R

b. Drywell Pressure - HigC## .S -M- O R 1,2,3

c. Containment and Drywell Purge Exhaust Plenum Radiation -

High. -S -M- Q R 1, 2, 3 and *

d. Reactor Vessel Water Level - )

Low, Level 1 5 jQ R I} 1, 2, 3 and #

e. Manual Initiation MA R NA 1, 2, 3 and

j.

2. MAIN STEAM LINE ISOLATION y a. . Reactor Vessel Water Level - .

Low, Level 1 S -M- Q R(b) 1, 2, 3

- b. ,

, Main High Steam Line Radiation ( R 1, 2 y S -M- Q w c.- Main Steam Line Pressure -

Low' S -M- Q R(b) y ,

d. Main Steam Line Flow - High 5 4- O R 1, 2, 3 e.. Condenser Vacuum - Low 5 4 0- R 1, 2**, 3**

f. Main Steam Line Tunnel Temperature - High. S 'M Q R 1, 2,. 3 i

g. Main. Steam Line Tunnel A Temperature - High' . 5 -M Q R 1,2,3

h. Turbine Building Main Steam Line Temperature - High 5 M- R 1, 2, 3 .

1. Manual Initiation MA NA 1, 2, 3 IAN

.5a i Eh s; ~

e- - ;

, ,,m. - . m . , - v.. - - , . . ., . .. , . - , , . . . .. -. _ _ _ .

. _ _ _ . _ _ . . _ _ _ _ . . _ _ . _ _ _ . .________.______.--._._____.._.__..__m _ _ _ _ . . _ . . _ _ _ . _ _

~

TABLE 4.3.2.1-1 (Continued) !

j g ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS t

=

-< CHANNEL OPERATIONAL CONDITIONS IN 14fICH :

CHANNEL FUNCTIONAL CHANNEL g TRIP FbMCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED U

! 3. SECO*10ARY CONTAIPMENT ISOLATION

. e

a. Peactor. Vessel Water R I) 1 Level - Low, Level 2 5 M- O 1, 2, 3 and #

'- b. Drywell Preraure - Highh 5 R IU) 1, 2, 3 MA 1, 2, 3 and

l

c. Manual Initiation NA R

< ~

4. REACTOR WATER CLEANUP SYSTEN ISOLATION

i. a. A Flow - High 5 -M- O R 1, 2, 3

b. A; Flow Timer NA -M Q R 1, 2, 3

c. Equipment Area Temperature - ,

t L High _

S 4t- O k 1, 2, 3 m d. Equipment Ares Ventilation ,

2- A Temperature - High 5 -M- O R 1, 2, 3

_m e. Reactor Vessel Water f

+

/, Level - Low, tevel 2 S -M- O R(b) 1, 2, 3

+

f. Main Steam Line Tunnel Ambient Temperature - High _ _ - _S -M- Q - R 1, 2, 3

g. - Main Steam Line Tunnel-A' Temperature - High S R 1, 2, 3

h. SLCS Initiation MA Mg Q(a) MA 1, 2, 3

f. Manual Initiation MA R NA 1, 2, 3 1

1 4

?~it i TAE

=a .

L 1.M e=* 9%3 i P

4-

4 l

4

_ TA8LE 4.3.2.1-1 (Continued) h ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS

'N CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED E-

' 5. - REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION

a. RCIC Steam Line Flow - High 5 -M- O R(b) 1, 2, 3

b. RCIC Steam Supply Pressure -

Low _

S it Q R(b) 1, 2, 3

c. RCIC Turbine Exnaust Diaphrays Pressure - High .

S -M- o R(b) 1, 2, 3 j d. 'RCIC Equipment Room Ambient .

Temperature -'High S -M- O R 1,'2, 3

e. _ RCIC Equipment Room a_

' -M- O 1, 2, 3 Temperature - High S .. - .. R j- f. Main Steam Line Tunnel Ambient

w. Temperature - High 5 -M- O R 1, 2, 3

> _ g. Main Steam Line Tunnel

-M- Q 1,2,3 w- ; ' a Temperature - High .

5 R h.- Main Steam Line Tunnel

Temperature Timer NA -M - Q R 1, 2, 3

i. -RHR Equipment Room Ambient Temperature - High 5 -M- O R 1, 2, 3

j. RHR Equipment Room a Temperature - High 5 ,

-M~ Q ' R 1,2,3

k. RCIC Steam Line Flow NA +Q R 1, 2, 3 High Timor 1.. Drywe11' Pressure - High 5 R(b) 1, 2 3 m.- Manual Initiation MA - ,

R NA 1, 2, 3 I'E?

%; M

=

E;h."

r*

" " - ' ' r e- w +. , - _ _____.___________.____a__________..____.m_.-__. __..__________--.mu_ ________ - _ _ . . _ _

,- m %

TABLE 4.3.2.1-1 (Continued) 3o ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS

, CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN milch E TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

-4 m 6. RHR SYSTEM ISOLATION

a. RHR Equipment Area Ambient '

N Temperature - High 5 -M - Q R 1, 2, 3

b. RHR Equipment Area a Temperature - High 5 -M - g R 1,2,3

c. RHR/RCIC Steam Line Flow - High 5 N- g R(b) 1, 2, 3

d. Reactor Vesse1 3ater Level -

$ Low, level 3 5 -M - g R ID) 1, 2, 3 Y e. Reactor Vessel (RHR Cut-in

$ Permissive) Pressure - High 5 Jt- q R ID) 1, 2, 3

f. ' Drywell Pressure - High 5 44- Q R(b) 7. 7. 3

g. Manual Inttfation NA R NA 1, 2, 3 7 3, R SEE M '

"s 2.i: E

v. : n

When handling irradiated fuel in the primary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

- When any turbine stop valve is greater than 90% open and/or the key locked bypass switch is "" <

in the normal position.

During CORE ALTERATION and operations with a potential for drainin ,the reactor vessel.

(a) Each train or logic channel shall be tested at east every othe 31 days.

(b) Calibrate trip unit setpoint at least once per 1-jays. 92

_ _ _ _ _ _ _ _ . _ _ _ _ 92 / ,

m

1. These Trip'. ctions( th, 2b, 3b, 6d, and 6f) utilize instrurients which are common to RPS instrumentation. I

(

N. . _ _ .

- - - - ~~

TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION g

E MINIMUM OPERABLE APPLICABLE

' CHANNELS PER OPERATIONAL TRIP FUNCTION (a) CONDITIONS ACTION E TRIP FUNCTION C. DIVISION 3 TRIP SYSTEM

1. HPCS SYSTEM

a. Reactor Vessel Water Level - Low, Level 2 4(b) 1, 2, 3, 4*, 5* 34

b. Drywell Pressure - High" 4 ID) 1, 2, 3 34

c. Reactor Vessel Water Level - High, level 8 4 fC) 1, 2, 3, 4*, 5* 31

d. Condensate Storage Tank Level - Low 2 Id) 1, 2, 3, 4* , 5* 35

e. Suppression Pool Water Level - High 2 Id) 1, 2, 3, 4*, 5* 35 HPCS Pump Discharge Pressure - High (Bypass) 1 1, 2, 3, 4* , 5* 39 f.

g. HPCS System Flow Rate , Low (Bypass) 1 1, 2, 3, 4*, 5* 39 1:* ,

N 1 1, 2, 3, 4*, 5* 36

$ h. Manual Initiation MINIMUM APPLICABLE TOTAL NO. CHANNELS OPERABLE OPERATIONAL OF CHANNELS TO TRIP CHANNELS CGdDITIONS ACTION D. LOSS OF POWER

1. 4.16 kv Emergency Bus Undervoltage 2/ bus 2/tus 2/ bus 1, 2, 3, 4**, 5** 37 (Loss of Voltage) y,

2. 4.16 kv Emergency Bus Undervoltage 2/ bus 2/ bus 2/ bus 1, 2, 3, 4**, 5** 38 (Degraded Voltage)

(a) A channel may be placed in an inoperable status for up t 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months during periods of required surveillance without placing the trip system in the trippe condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

(b) Also actuates the associated division diesel generator.

(c) Provides signal to close HPCS pump injection valve only. ,

(d) Provides signal to HPCS pump suction valves only.

When the system is required to be OPERABLE per Specification 3.5.2 or 3.5.3. -r 5 :n-

- Required when ESF equipment is required to be OPERABLE. A?%

Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 100 psig.

N The injection function of Drywell Pressure - High and Manual Initiation are not required to *OE C', O ?

be OPERABLE with indicated reactor vessel water level on the wide range instrument greater than the Level 8 setpoint coincident with the reactor pressure less than 450 psig. o5E N# The Loss of Voltage and Degraded Voltage functions are cosmon to Divisions 1, 2 and 3. " i' ~

E7" e-

4 Attechm2nt 2 J PY-CEI/NRR-1496 L j TABLE 3.3.3-1 (Continued) Page 14 of 50 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION

^l ACTION ;

ACTION 30 - With the number of OPERABLE channels less than requi md by the. !

!. Minimum OPERABLE Channels per Trip Function requirement:

With one channel inoperable, place the

a. table channel

! in the tripped condition within n r n r er declare the ;

!= associated systes inoperable. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months i b. With more than one channel inoper w, declare the associated .

j systes inoperable. j ACTION 31 - With the number of OPERABLE channels less than required by the .

Minimum OPERABLE Channels per Trip Function requirementLwithin 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months sj declare the associated ADS trip system or ECCS inoperable.-

i ACTION 32 -

With the number of OPERABLE channals less than the Minimum 1 OPERABLE Channels per Trip Function rewirement, place the j inoperable channel in the tripped condition within(p r;% 24 hourYl) i ACTION 33 - With the number of OPERABLE channels leis than requimd by the I . Minimum DPERABLE Channels per Trip Func' ion requ nt, restore i the inoperable channel to OPERABLE statnwithi s or i

! declare the associated ADS valve or ECCS inoperabl ,

ACTION 34 - With the number of OPERABLE channels.less than mquimd by the l Minimum OPERABLE Channels per Tria Functun requirement: l

_ a. For one trio _.syites,11 ace t)at trip system in the trimped i (24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s] condition withind= r:0 or declars the NPCS system inoperable, j b. For both trip systems, declare the UCS system inoperable.

i ACTION 35 - With the number of OPERA 8LE channels less than required by the

! Minimum 0PERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months eq.fgip or align the HPCS system to take suction from the '. .;

suppression pool, or declare the HPCS systes inoperable.

l ACTION 36 With the number of OPERABLE channels less than required by the .

l Minimum OPERABLE Channels per Trip Function requirement, place E - at least one inoperable channel in the tripwd condition within .

, Q4 hours = = O or declare the HPCS system inoperable. ,

l ACTION 37 - With the-number of OPERABLE channels less than the Total' Number ,

j of Channels, declan the associated emergency diesel' generator

inoperable and take the ACTION required by Specificat' on 3.8.1.1 l or 3.8.1.2, as appropriate.

i ACTION 38 - With the number of OPERABLE channels less than the Total Number-

[

of Channels, place the inoperable channel in the tripped condi-tion within I hourt operation may then continue until_perfom- '

ance of the next required CHANNEL FUNCTIONAL-TEST.

I' ACTION 39 With the number of OPERA 8LE channels less;than required by the Minimum OPERA 8LE Channels-per Trip Function requirement, place:

the inoperable channel in.the tripped condition within (ne-hov. 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s] '

Restore the inoperable channel to OPERABLE status within 7~3Fys i or declare the associated system inoperable.. l p s i

j PERRY - UH!i 1 3/4 3 Amendment No. 30-i

--y e A ..,,n-,e,,, ,5,,-, A w h'_ e , - - + r c -..-+,..-r.~. ~,,...w.., .,.,r#,[.r..,, - m+ ..'_.M.,-.,5 .,,5,,,_...,m..n < r - e w- , , w wwg w--cw ap - ,, --ew,,,

TABLE 4.3.3.1-1 7 EMERGENCY CORE COGLING SYSTEM ACTU*, TION INSTRUMENTATION SURVEILLANCF REQUIREMENTS E ,

' CHANNEL OPERATIONAL CHANNEL FDNCTIONAL CHANNEL CONDITIONS FOR WHICH j

-E CALIBRATION SURVEILLANCE REQUIRED :

y TRIP FUNCTION CHECK TEST A. DIVISION I TRIP SYSTEM ,

1. RHR-A (LPCI MODE) AND LPCS SYSTEM

a. Reactor Vessel Water Level - .

Low, Level 1 5 -M- Q R 1, 2, 3, 4*, 5*

b. - Drywell Pressure - High 5 -M- Q ; '

R 1, 2, 3 '

c. LPCS Pump Discharge Flow - Low g (Bypass) S -fF Q R(,)) 1, 2, 3, 4*, 5*

d. Reactor Vessel Pressure - Low 5 -ft O R, 1, 2, 3, 4*, 5*

w . (LPCS Injection Valve Permissi-a) Rg ,)

e. Reactor Vessel Pressure - Low 5 1- O 1, 2, 3, 4* , 5*

} (LPCI' Injection Valve Permissive) m J, f. LPCI Pump A Start Time Delay

Relay NA -M Q 1, 2, 3, 4*, 5*

QR *) 5*

g. LPCI Pump A Flow - Low (Bypass) S 'M Q 1, 2, 3, 4*,

.h. Manual Initiation NA NA 1, 2, 3, 4*, 5*

2. AUTOMATIC DEPRESSURIZATION SYSTEM-TRIP SYSTEM "A"#

'a. Reactor Vessel Water Level'- R(,)

- Low, Level 1 5 -M- Q 1, 2, 3

b. Manual Inhibft -- NA. . . .

-M- Q NA 1, 2, 3

c. ADS Timer NA H- Q Q 1,2,3

d. Reactor Vessel Water Level -

Low, Level 3 (Permissive) 5 -ff- O RI ") 1, 2, 3

e. LPCS Pump Discharge ;33 r Pressure - High (Permissive) S *Q R(,) 1, 2, 3 gg; LPCI Pump A Discharge mo RI *)

f.

Pressure - High (Permissive)

Manual Initiation S -M- Q 1, 2, 3 U$[

g. NA NA 1, 2, 3 3 s~ #

cs i

t-i

._.I . -. , _e , _ . . .. , , _ . , . - - . _ , _ . - x

TABLE 4.3.3.1-1 (Continued)

A g EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS

' CitANNEL OPERATISNAL CilANNEL FUNCTIONAL CllANNEL CONDITIONS FCS Mf!Clf E CliECK TEST CALIBRATION SURVEILLANCE REQUIRED Q TRIP FUNCTION w

B. DIVISION 2 TRIP SYSTEM

1. RHR B AND'C (LPCI MODE) g

a. Reactor Vessel Water Level - R 1, 2, 3, 4 * , 5*

Low, tevet 1 5 -M-Q

- 4FQ R I, 2, 3

b. Drywell Pressure - High Rg ,) 1, 2, 3, 4*, 5*

c. Reactor Vessel Pressure - Low 5 -M-Q (LPCI Injection Valve Permissive) w d. LPCI Pump B Start Time Delay 1, 2, 3, 4 *, 5*

Relay NA I -H Q Q 2 LPCI Pump Discharge Flow - Low w e. R(a) 1, 2, 3, 4*, 5*

(8ypass) 5 -M- Q

/,

NA 1, 2, 3, 4 * , 5*

f. Manual Initiation NA l

2. AUTOMATIC DEPRESSURIZATION SYSTEN TRIP SYST S "B"#

i Reactor Vessel Water Level -

a. R(*) 1, 2, 3 .

Low, Level 1 5 1,2,3 NA -M- Q NA

b. Manual" Inhibit 1, 2, 3 NA -M-Q Q

c. ADS Timer

d. Reactor Vessel Water Level -

Low, Level 3 (Permissive) 5 -M Q RI *) 1, 2, 3

e. LPCI Pump B and C Discharge .

Rg ,) 1,2,3 Pressure - High (Permirsive) 5 -H Q l 1, 2, 3 , , ,

NA NA

f. Manual Initiation E T :~

n' X C ii 2.s $

s:~*

t-as sM > ,.m

TABLE 4.3.3.1-1 (Continued) i g EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR MIICH CHECK TEST CALIBRATION SURVEILLANCE REQUIRED Q TRIP FUNCTION C. DIVISION 3 TRIP SYSTEM

1. HPCS SYSTEM

a. Reactor Vessel Water Level - 1, 2, 3, 4*, 5*

Low,' Level 2 y 5 -M- O R 5 -M- Q R 1, 2, 3

b. Drywell Pressure-High

c. Reactor Yessel Water Level - High, Rg ,) 1, 2, 3, 4*, 5*

Level 8 5 -M- O Condensate Storage Tank Level -

d.

S 49- O R 9) 1, 2, 3, 4 * , 5*

Low .

1:* e. Stepression Pool Water Rg ,) 1, 2, 3, 4*, 5*

Level - High 5 -M- O 6,3 f.. HPCS Pump Discharge Pressure -

R, 1, 2, 3, 4*, 5*

g High- S *M O S it- Q R 1, 2, 3, 4*, 5*

g. HPCS System Flow Rate - Low NA 1, 2, 3, 4*, 5*

h. Manual Initiation" NA R i

D. LOSS OF POWER 4.16 kv Emergency Bus.Under- NA NA R 1, 2, 3, 4**, 5**

1.

voltage (Loss .of Voltage) 1, 2, 3, 4**, 5** gg

2. 4.16 kv Emergency Bus Under- S ,M '

R eg=

voltage (Degraded Voltage) ~

O zZ E.

' #Not required to be OPERABLE shen reactor steam done pressure is less than or equal to 100 psig.

3.53 w l. =

1. The injection function of Drywell Pressure - High and Manual Initiation are not required to be S OPERABLE with indicated reactor vessel vder level on the wide range instrument greater than the

Level 8 setpoint coincident with reactor ,-essure less than 450 psig. r-

When the system is. required to be OPERABLE per Specification 3.5.2 or 3.5.3.

- Required when ESF equipment is required to be O RABLE.

(a) Calibrate trip unit setpoint at least once pe M days.

b

Attachm:nt 2 PY-CE1/NRR-1496 L Page IB of M INSTF.UMENTATION 3/4.3.4 RECIRCULATION PUMP TRIP IITUATION IN7RUMENTATION ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION LIMITIVG CONDITION FOR OPERATION 3.3.4.1 The anticipated transient t:ithout scram recirculation pump trip (ATWS-RPT) system instrumentation channels shown in Table 3.3.4.1-1 shall be OPERABLE with their trip setpoints set consistent with values shown in the Trip Setpoint column of Table 3.3.4.1-2.

APPLICABILITY: OPERATIONAL CONDITION'1.

ACTION:

. With an ATWS-RPT system instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Ttble 3.3.4.1-2, declare the channel inoperable until the channel is restored to OPERABLE status with the channel trip setpoint adjusted consistent with the Trip Setpoint value,

b. With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement for one or both trip sygens, place the inoperable channel (s) in the tripped ccndition withinQnehar. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 3

c. With the number of OPERABLE channels two or more less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip systes and:

1. If the inoperable channels consist of one reactor vessel wa'ter level channel and one reactor vessel pressure channel, place both inoperable channels in the tripped condition

within(one-hour. 24 hourQ

2. If the inoperable channels include two reactor vessel water' level channels or two reactor vessel pressure channels, declare the trip system inoperable.

d. With one trip system inoperaDie, mstore the inoperable trip system to OPERABLE status withir. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

e. With both trip systems inoperable, restore at least one trip system to OPERABLE status within one hour or be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.3.4.1.1 Each ATVS recirculation pump trip system instrumentation channel ,

shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.4.1-1, 4.3.4.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per IB months.

The inoperable channels need not be placed in the tripped condition where this would cause the Trip Function to occur. In this case, the inoperable channels shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or the trip system shall be declared inoperable.

PERRY - UNIT l' 3/4 3-40

4 4

p 4

TABLE 3.0.4.1-1 -

o E. ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION ,

..=<-

. MINIMUM OPERABLE C g LS PER ,

TRIP FUNCTION TRIP SYSTEM c:

2

, M ..

C t

1. Reactor Vessel Water Level - .

" Low,ilevel'2

, 2. Reactor Vessel Pressure - High 2 i

i (a) One channel may be placed in an inoperable status for up to thours for required survelliance' O

.g

. provided the other channel .is OPERA 8LE. . 6' =

,s >

g.

v.

m N t

A e p.s i 4

E >

T s .. .. -i

+

i '

6 N= .m < >. '-

9tt ; e e,--

@ no .

mo WM7 j' : e s g :-

i

. -o

m e, j' t

. 1/9 e

PJ Ob

] e:

e 1 f*

t 4

W

1. y . d.h ,

a - t-'- p

f" w '" "5'- e * % W" **-- "

TABLE 4.3.4.1-1 -

3 ATWS RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS

.Q CHANNEL CHANNEL FUNCTIONAL CHANNEL TEST' CALIBRATION CHECK-

~

c TRIP FUNCTION h

S

'R*

, 1. Reactor' Vessel Water Level -

H Low.. Level 2 y R*

2. Reactor Vessel Pressure - High S

Calibrate trip unit h etpoint at.leasir once per F, days.

92' 1

,w 3

Y O

e Y

L em **e- .a 8

- was RI ab,E O

1 e

! .tttachment 2 3- PY-CEI/NRR-1496 L INSTRUMENTATION P*ge 21-of 50 i

END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION I LIMITING CONDITION FOR OPERATION 1

3.3.4.2 The end-of-cycle recirculation pump trip (EOC-RPT) system instrumentation channels shown in Table 3.3.4.2-1 shall- be OPERABLE with:their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.4.2-2 and with the END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME as shown in Table 3.3.4.2-3. .

( APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 45 of RATED THERMAL POWER.

I ACTION:

a. With an end of-cycle recirculation pump trip system instrumentation channel trip setpoint less conservative than the value shown in the i Allowable Values column of Table 3.3.4.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with~the channel setpoint adjusted consistent with the Trip Setpoint value. --

b. With the number of OPERABLE channels one less than required by the

. Minimum 0PERABLE Channels per Trip-System requirement for one or both trip systems, place the inoperable channel (s) in the tripped condition 1 .

c. With the number or0PERABLE channels two or more less than required by the Minimum OPERABLE Channels per Trip System requirement-for one

trip system and

7 1. If the inoperable channels consist of one t W ne control valve channel and one turbine stop valva channel place both inoperable channels in the tripped condition within @ h: r twelve hours.) l

2. If the inoperable channels include two turbine control-valve channels or two turbine stop valve channels, declare the trip

system inoperable.

~

d. With one trip system inoperable, restore the inoperable trip system

to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or reduce THERMAL POWER to less than 40% of RATED THERMAL POWER within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

e. With both trip systems inoperable, restore at least one trip system to OPERABLE' status within one hour or reduce THERMAL POWER to less than 40% of RATED THERMAL POWER within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

~

PERRY - UNIT.1 3/4 3-44 l l

L J

TA8LE 3.3.4.2 END-0F-CYCLE RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION I

c MINIMUM 5 OPERA 8LECHANNEg)

F TRIP FUNCTION

e PER TRIP SYSTEM I

1. Turbine Stop Valv6 - Closure 2(b)

2. Turbine Control Valve - Fast closure 2(b) b (a)A trip system may be placed in an inoperable status for up t ours for required surveillance providen that the other trip system is OPERA 8LE.

w 1 (b)This function is automatically bypassed when turbine first stage pressure is less than the value of turbine first stage pressure corresponding to 40%* of. RATED THERMAt. POWER.

'*The Turbine First Stage Pressure Bypass Setpoints and corresponding Allowable Values are adjusted based on Feedwater temperatures (see 3/4.2.2 for definition of AT). The Setpoints and Allowable Values for various ATs.are as follows:

3 i

T(*F) Setpoint (psig) Allowable Value (psig) 0=T < 212 < 218 1

E O < AT < 50 - 7 190 7 196 -

E 50 < AT < 100 7 168 7 174

{ 100 < AT 1 170 1146 E152 e

i g

.aa =,

i

aar

4 i

TABLE 4.3.4.2.1-1 ,

.o

'E-

=

END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM SURVEILLANCE REQUIREMENTS I CHANNEL'

- a

FUNCTIONAL CHANNEL e CALIBRATION s

' z TEST

- TRIP FUNCTION-

-4

1. Turbine Stop Valve - Closure ,M R i: 2. Turbine Control Valve - Fast Closure -M o ' R i.

D i-N I

W e

O e

k e 1 4

t? *ts >-

D*<<*

og e ,,

f- @ OO Mn t,

M M D

W%$

!r I <

2 6 :

O *x 3 rw bt! c+

I

' ,, R)e s.* M a- oo

,e e

O ta '

v. .. s ., . . . ,

t TABLE 3.3.5-1 .

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION 4 . . .

MINIMUM e

c OPERABLECHANNEL{a) ACTION PER TRIP SYSTEM FUNCTIONAL UNITS 3

" Reactor Vessel Water Level - Low, Level 2 2 50 a.

2 IU) 51

b. . Reactor Vessel Water Level - High, Level 8 Condensate Storage Tank Water Level - Lew 2 fC) 52 c.

2(C) 52 i d. Suppression Pool Water Level - High

e. Manual Initiation 1(d) 53 (a) A channel may be placed in an inoperable status for up t ours for required' surveillance without ca placing the trip system in the tripped condition provided at least one other OPERABLE channel in the S same. trip system is monitoring that parameter. '

" -(b) One' trip system with two-out-of-two logic.'

(c) One trip system with one-out-of-two logic. .

(d) There is only one manual switch.

9 RT:

i

nn a~

%ti O :,2 O

E e

i n

- ' L -=- _- - _ _ . _ _ _ _ _ _ _ _, _ _ _ , _ _ _ _ __

I b Attcchmtnt 2' PY-CEI/NRR-1496 L TABLE 3.3.5-1 (continued)

Page 25'of 50

, REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION i ACTION 50 - With the number of OPERA 8LE channels less than required by the Minimum OPETd8LE Channels per Trip Systes requirement:

a

a. For one-trip systes, place the inoperable channel d or i

that trip system in the tripped condition within h r or declare the RCIC system inoperable. -

h:;;8

b. For both trip systems, declare the RCIC system inoperable.

i ACTION 51 - With the number of OPERABLE channels less than required by the Minimum OPERABLE channels per Trip System requirement, declare i

the RCIC system inoperable 6ithin 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months st .l ACTION 52 - With the' number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Systes requirement, place 3

at least one inoperable channel in the tripped condition within i h4 hour 1.970 ,.... . or align the RCIC system to take suction from the suppres on pool, or declare the RCIC systas inoperable. l l

, ACTION 53 - With the number of OPERABLE channels less than required by the Minimum OPERABLE-Channels per Trip Systes requirement %

restore the inoperable channel to 0PERABLE status within'a .br;\or declare the RCIC system inoperable.

3 QAhours i

~

i 1

4 i

PERRY - UNIT 1 3/4 3-52 Amendment No. 30 i

. . - - - - - ., , , . . ,, .. ,w-.. *_ -

TABLE 4.3.5.1-1 A

g REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS

CHANNEL CilANNEL FUNCTIONAL CHANNEL E CALIBRATION FUNCTIONAL UNITS CllECK TEST Q

s

a. Reactor Vessel Water Level -

Low, Level 2 S -H- 0 R(a)

b. Reactor Vessel Water Level - S 40 ,

RI *)

High, Level 8 - - ---

c. Condensate Storage Tank Level -

Low S , .

-M-Q RI ")

d. Suppression Pool Water Level - ,

Rg ,)

High 5 -M-

[. e. Manual Initiation NA R NA (a)Calibratetripunitsetpointatleastonceperkdays.

3

~

2AE k

am:

8h" .

F

_.-__.m. _ _ _ _ ___-.m._

TABLE 3.3. .

A:o CONTROL ROD BLOCK INSTRUMENTATION 4 . MINIMUM APPLICABLE

! . OPERABLE CHANNELS OPERATIONAL j TRIP FUNCTION PER TRIP FUNCTION - CONDITIONS ACTION g

4 1. ROD PATTERN CONTROL SYSTEM t.

a. Low Power Setpoint 2 1, 2 60

' b. RWL - High Power 2 1 60 Setpoint

>2. APRN'

a. Flow Blased Neutron Flux -

Upscale 6 1 61

b. Inoperative- '6 1, 2 - 5 61

c. Downscale' .

6 1 61

. d. Neutron Flux - Upscale, Startup 6 2, 5 61 w 3. SOURCE RANGE MONITORS A a.- Detector not full inI ") 3 2# 61- ;

y 2** 5 61

3 2# 61

b. Upscale (b) 2** 5 61 !

i 3 2#. 61

c. Inoperative (b) 2**' 5 61 3 2# 61-

d. Downscale(c) 2** 5 61

4. INTERNEDIATE RANGE MONITORS ._ . .. __

a. : Detector not full in 6 2, 5 61 b .- Upscale. 6 2, 5 61

c. ' Inoperative- 6 2, 5 61

, d. Downscale Id) 6: 2, 5 61

. .5. SCRAM DISCHARGE VCb.NE

'a. Water.. Level-Hig 2 1, 2, 58 62 .]y{

6. REACTOR COOLANT SYSTEM RECIRCULATION FLOW- *@{

a. Upscale 6 1 62 [$j n % .,

7. REACTOR MODE-SWITCN SHUTOOWN POSITION 2' 3, 4 63 m.

e a 3 .

F g - y _. . .

m

1 j 1

Attachment 2 PY-CEI/NRR-1496-L Page 28 of 50 4

TABLE 3.3.6-1 (Continued)

CONTROL ROD BLOCK INSTRUMENTATION ACTION-ACTION 60 - Declare the RPCS inoperable and take the ' ACTION required by 4 Specification 3.1.4.2.

ACTION 61 -

With the number of OPERABLE Channels:

a. One less than required by the Minimum 0PERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 7 days or place the inoperable 2 channel in the tripped condition within the next hour.

i

b. Two or more less than required by the Minimum OPERABLE'-

Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within .

one hour.

ACTION 62

- With the number of OPERABLE channels less than required by the I Minimum OPERABLE Channels per Trip Function requirement, place _

the inocerable channel in the tripped condition within(= t,ar. -

(12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 63 - With the number of OPERABLE channels less than required by the .

~

Minimum OPERABLE Channels per Trip Function requirement, E

initiate a rod block.

e NOTES

With more than one control rod withdrawn. - Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

- 0PERABLE channels .must be associated with SRMs required OPERA 8LE per Specification 3.9.2.

With IRMs on range 2 or below.

(a)This function is automatically bypassed if detector count rate is:> 100 cps or the IRM channels are on range 3 or higher.

(b)This function-is ' automatically bypassed when the associaiad IRM channels are on range 8 or higher, s (c)This function is autosctically bypassed when the IPM channels are on range 3 or higher.

(d)This function is automatically bypassed when the IRM channels are on range 1.

(e) A channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for required surveillance without placing the TRIP SYSTEM in the tripped condition, provided at least one other OPERABLE channel in the same- .

' TRIP SYSTD1 is monitoring that parameter.

%~

PERRY - UNIT l' 3/4 3-57

. . . . , - . - . - . . ~ - . - . - . . . . - . . - .-.-- .....-.~--.-...- - .-.- _... ___.-- . .- -.

i s

TA8LE 4.3.6-1 -

L l CONTROL ROD BLOCK INSTRUMENTATION SURVEILLANCE REQUIREMENTS !

' 3 CHANNEL. OPERATIONAL Q .

CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WICH ':

1-

, TRIP FUNCTION' CHECK TEST CALIBRATIONg,)

. SURVEILLANCE REQUIRED i

[ g 1. 'R00 PATTERN CONTROL' SYSTEM .

.t i

[ a. . Low Power Setpoint. #

[ NA S/U(b 34 1, 2 !

b. RWL - High Power Setpoint NA S/U(b) , M- 0 #

SA 1 i

2. APRM f

, a. Flow Blased Neutron Flux - Upscale

'1) Flow'81ased NA S/U(b) VO SA(c) y

2) High Flow Clamped NA SA(c) 3 b. Inoperative- NA S/Uh;W W0 0 NA 1

1,'2, 5

c. Downscale NA S/U(b)

S/U W- 0 SA-

~ .

1 't

d. . Neutron Flux -' Upscale, Startup- NA S/U(b) W0 SA 2, 5

. .g 3. SOURCE RANGE MONITORS y .a. Detector not full In NA 2**,

NA g b. Upscale: NA. S/U(b)

.S/U

,W W(d) R 2**,

5 5

c. Inoperative NA' S/U

d. Downscale S/W(.b),WId).

NA 2**, 5 '

NA ,W -- R 2**,

5

, 4. INTERME0! ATE RANGE MONITORS

s. Detector not full in MA : S/U(b) W NA 2, 5

.g

b. Upscale NA S/U ,,W(d) R 2, 5 g c. Inoperative NA S/U W NA

" d. 2, 5 Downscale .NA $/U(b),W(d)

, -R 2, 5

.E 5. SCRAM DISCHARGE VOLUME' 4

g a. Water Level - High _a m,>

-W 0 NA r. j {j _;

1, 2, 5*

i 1~ 6.. REACTOR COOLANT SYSTEM RECIRCULATION FLOW y C 9. '

a. Upscale

s! '

NA S/U(b) W Q l SA IC) 1 ,. E E i i- 7.. REACTOR MDOE SWITCH SHUT 00 W wLn'

). POSITION.. NA oS.

i R 'NA 3, 4 I' ,

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. _ _ _ __-u-______ , . - ~ _ _ _ . _ _ ,

i Attachmtnt 2 PY-CSI/NRR-1496 L Page 30 of 50 TABLE 4.3.6-1 (Continued)-

CONTROL R00 BLOCX INSTRJMENTATION SURVEILLANCE REQUIREMENTS

j. NOTES: -

~

a. Neutron detectors may be excluded from CHANNEL CALIBRATION.

b. Within 7 days prior to startup.

c. The CHANNEL CALIBRATION shall exclude the flow reference transmitters, 2

these transmitters shall be calibrated at-least once per 18 months.

{

d. Trip setpoints are verified during weekly CHANNEL FUNCTIONAL TESTS.

"With more than one control rod withdrawn.- Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2. '

- With IRMs on range '2 or below.

, # Calibrate trip unit setpoint at least once per days.

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PERRY'- UNIT 1 3/4 3-60 Amendment No. 31

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Attech:2nt 2 PY-CEIhmR-1496 L Pege 31 of 50

_ INSTRUMENTATION -

3/4.3.9 PLANT SYSTEMS ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.9 The plant sys'tems actuation instrumentation channels shown in Table 3.3.9-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.9-2.

APPLICABILITY: As shown in Table 3.3.9-1.

. ACTION:

a. With a plant system actuation instrumentation channel trip setpoint

less conservative than the value shown in the Allowable Values col n of Table 3.3.9-2. declare the channel inoperable,fdHftEF clece the

-r rI d to :hr (d5io:re:bl: r.:1 1.5 th: t-f;;:d =d%mTufftT1 the channel is OPERA 5LE status with its~tri etpoint ad. justed consistent with the Trip Setpoint value; or dec1;r: the-esseeiet,eO Q:t:M pper:bler "

A For the cbntainment spray systaa:

With the number of OPERA 3LE channels less than required by the nimum OPERABLE Channels per Trip System requirement foptine e tr stem, place at least one inoperable channel in,the

' trippedqndition within one hour or declare the associated system ino ble. /

2. With the number PERABLE channels les rtav'. red by the Minimum OPERABLE C annels per Trip Syst equirement for both trip systems, declare t associatedsfsteminoperable.

c. For the feedwater system / main turb trip system:

' i

1. With the number of OPE nnels less than required by the Minimum OPERABLE yht'nnels requiremenb,qestore the.

inoperable channel tti CPERABLE status within days or be in at least STARTUP wjtttfin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

2. With the numIer of OPERABLE channels two less than requ? red by !

- the Minim'um OPERABLE Channels requirement, restore at leait one '

of the' inoperable channels to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 'or be'in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

PERKY - UNIT 1 3/4 3:98 Amendment No.30

Attachment 2--

PY-CEI /NRR- 14 96L Page 32 of 50 3.3.9 INSERT 4

b. With one or-more plant systems actuation instrumentation channels i noperable, take the ACTION required by Table 3.3.9-1.

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m_ _ _ _ _ _ _____

Attschment 2 INSTRUMENTATION- Pa 3 LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued)

For the suppression pool makeup system:

1. For the Drywell Pressure-High and the Reactor Vessel Water ;

vel-Low, Level 1:-

With t number of OPERA 8LE channels less than utred by the ,

Minimum 0 4ABLE Channels per Trip Function r uirement:

a) With one ch el inoperable, place noperable channel in the trippe ndition within e hour or declare the associatedsysteals- inoperab .

b) With more than one chan inoperable, declare the asso-ciated system (s) ino,ef'able. ,

2. FortheSuppressionJoolWaterLevel-L Suppression Pool Makeup Timer and e SPMU Manual Initiatie..

With the nu. r of OPERABLE channels'less than re red by the Minimum 0)ERABLE Channels per Trip System requirementNestore-the inoperable channels to OPERABLE status within 8 hourg othe.rfise, declare the associated suppression pool makeup system ipo'perable and take the action required by Specification 3.6.374.

SURVEILLANCE REQUIREMENTS .,

4.3.9.1 Each plant system actuation instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL- CONDIT. IONS and at the frequencies shown in-Table 4.3.9.1-1. -

4.3.9.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

PERRY - UNIT 1 3/4 3-99 Amendment No.10

- - THIS PEE IS INIINTICNALLY BIANK ***

I

TABLE 3.3.9-1~

m"

PLANT SYSTEMS ACTUATION INSTRUMENTATION

HINIMUM APPLICABLE OPERATIONAL g OPERA 8LECHANNEg)

PER TRIP SYSTEM CONDITIONS s

ACTION i y TRIP FUNCTION 1

1. CONTAINMENT SPRAY SYSTEM-i 2 1,2,3 130 i

a. Drywell Pressure - High -

2 1, 2, 3- 131 \

b. Containment Pressure - High '

Reactor Vessel Water Level.- Low, Level 1 2 1,2,3 130 c.

- d. Timers 1 1,2,3 131 (1) System A and 8 (10 minute timer) 131 (2) System B (1.5 minute timer) 1 1, 2, 3 1 1, 2, 3 131

e. Manual Initiation y 2. FEE 0 WATER SYSTEM / MAIN TUR8INE TRIP SYSTEM

a. Reactor Vessel Water. Level - High, Level 8 3 'I

{ 132

3. SUPPRESSION POOL MAKEUP SYSTEM 2 2, 3 130

a. Drywell Pressure - High ~ l',

2' 130

5. Reactor vess.e1 Water Level - Low.. Level I 1, 2, 3 f

2 1, 2, 3 ' 131

c. Suppression Pool Water Level . Low

' Suppression Pool Makeup Timer 1 1,2,3 131 d.

e. SPMU Manual Initiation 1 1,2,3 131 /

p!

d hs Mys j' 6 A channel may be placed in an inoperable status for up to illance without (a) placing the trip"gytsed)in the tripped condition provided(-2-hours at least one other OPERAfor 8LE channel insurvemm>

required the same trip system is monitoring that parameter. {?{

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Attachment 2 PY-CEI/NRR-1496L Page 35 of 50 I-INSERT 5:

TABLE 3.3.9-1 (Continued)

PLANT SYSTIO4R S~rDATION INSTRUMENTATION ACTIONS ACTION 130 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System _ requirement:

a. With one channel inoperable, place the inoperable channel in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or declare the-associated system (s) inoperable.

b. With moro than one channel inoperable, declare the associated system (s) __

inoperable. '

I ACTION 131 - With the number of OPERABLE channels less- than required by the . Minimum OPERABLE Channels per Trip System requirement,-place the inoperable channel (s) in-the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or declare the associated system (s) inoperable. .

ACTION 132 - a. With the number of OPERABLE. Channels one less than . required by- the Minimum-OPERABLE Channeis- per: Trip System <

requirement, restore- the- inoperable '

channel to OPERABLE status within 7 days or be in at least -STARTUP within the next

-6 hours. .

b. With the number of.OPF?.ABLE chann'els two

-less than- required- by the ' Minimum OPERABLE Channels- per Trip- System

requirement.: restore at least one of the ,

inoperable (hannels ' to OPERABLE status within- 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least STARTUP within the next'8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

TABLE 4.3.9.1-1 m" -

j PLANT SYSTEMS ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS

' CHANNEL OPERATIONAL CilANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH E CALIBRATION SURVEILLANCE REQUIRED CHECK TEST Q TRIP FUNCTION e.

1. CONTAINMENT SPRAY SYSTEM _

Drywell Pressure - Nigh 5 -M- Q R$ 1, 2, 3 l a.

Containment Pressure - High 5 *O R* 1, 2, 3 b.

c. Reactor Vessel Water Level - Low Level 1 S -M- O R* 1,2,3

d. Timers . . . . -

(1) System A and B NA *OJ R 1, 2, 3 1, 2, 3 (2) System B NA (-M- Q / R 1,2,3

$ e. Manual Initiation NA R NA w

,, 2. FEEDWATER SYSTEM / MAIN TUR8INE TRIP SYSTEM.

n Reactor Vessel Water Level - High, a.

Level 8 5 -M- O R* 1

3. SUPPRESSION POOL MAKEUP SYSTEM

a. Urywell Pressure - Nigh 5 - W .O . R* 1,2,3

b. Reactor Vessel Water Level.-

Low, Level:1 _

S tQ R* 1, 2, 3

c. : Suppression Pool Water Level - Low 'S .

-M- 0 R* 1, 2, 3 Suppression Pool Makeup Timer NA -M O 1, 2, 3 l

d. Q

e. SPMU Manual Initiation ' NA "/ 1, 2, 3 ' >

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m e n

" Calibrate trip unit setpoint-at least once perl 4 days. "' Q S 7w

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Attcchnnt 2 PY-CBI/NRR-1496 L Page 37 of 50 REACTOR COOLANT SYSTEM

[ 3/4.4.2 SAFETY VALVES SAFETY / RELIEF VALVES LIMITING CONDITION-FOR OPERATION 3.4.2.1 Of the following safety / relief valves, the safety valve function of at least 7 valves and the relief valve function of at least 6 valves other than those satisfying the safety valve function requirement shall be OPERABLE with the specified lift $cttings:

Number of Valves Function Setpointa (psia) 8 Safety 1165 2 11.6 psi 6 Safety 1180 1 11.8 psi 5 Safety 1190 2 11.9 psi 1 Relief 1103 1 15 psi 9 Relief 1113 1 15 psi 9 Relief 1123 1 15 pst APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

a. With the safety and/or relief valve function of onet or more of the above required safety / relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

b. With en or more safety / relief valves stuck open, close the stuck open safety / relief valve (s); with suppression pool average water temperature

/

t 110*F or greater, place the reactor mode switch in the Shutdown position.

c. With one or more safety / relief valve tail pipe pressure switches inoperable, restore the inoperable switch (es) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . '

d. With either relief valve function pressure actuation trip system "A" or "B" inoperable, restore the inoperable trip system to OPERABLE status within 7 days; otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.4.2.1.1 The tail pipe pressure switch for each safety /reifef valve shall be demonstrated OPERABLE with the setpoint verified to be 3015 psig by per-formance of a:

a.

CHANNEL FUNCTIONAL TEST at least once per'31) days, and a Q

b. CHANNEL CALIBRATION at least once per 18 months.

4.4.2.1.2 The relief valve function pressure actuation instrumentation shall be demonstrated OPERABLE by performance of a:

a. CHANNEL FUNCTIONAL TEST, includinc calibration of the trip unit, at least once per h day W

b. CHANNEL CALIBRATIOHTLOGIC SYSTEM FUNCTIONAL TEST" and simulated automatic operation of the entire system at least once per 18 months.

The lift setting pressure shall correspond to ambient conditions of the l.' valves at nominal operating temperatures and pressures.

- SRV solenoid energization shall be used alternating between the "A" solenoid 1 the "B" solenoid.

PERkt - UNIT 1 3/4 4-7

Attechmsnt 2-PY-CEI/NRR-1496 L Page 38 of 50-REACTOR COOLANT SYSTEM y SAFETY / RELIEF VALVES LOW-LOW SET F F. TION LIMITING CONDITION FOR OPERATION-3.4.2.2 The relief valve function and the low-low set function of the following reactor coolant systes safety / relief valves shall be OPERABLE with the following settings:

Low-Low Set Function Relief Function Setsoint* (psig) t 15 psi Setpoint* (psia)

Valve No., ) pen Close- Open - Close 1821-F0510 1033 926 n03

15 psi 1003 1 20 psi 1821-F051C 1073 936 n 13 1 15 psi 1013 t 20 psi 1821-F051A n13 946- 1113 i 15 psi - 1013

20 psi-1B21-F051B -In3 946 n13 t 15 psi .1013 t 20 psi ,

1821-F047F n13 946 n13 i 15 psi 1013 1 20 psi 1821-F051G.- n13 - 946 in3 215 psi 1013 t 20 psi-I APPLICABILITY: OPERATIONAL CONDITIONS 1.-2 and-3.- ,-

ACTION:

a. With the relief valve function and/or the-low-low set function of one of _

(. the above required reactor coolant system safety / relief valves' inoperable -

restore the inoperable relief valve function and the' low-low set function to OPERABLE status within 14 days or be in at least HOT _ SHUTDOWN within the next'12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . -

b. - With the relief valve function and/or the low-low set function of more -

than one of the above required reactor coolant system safety / relief:

, valves inoperable, be in at least HOT. SHUTDOWN within~12 hours and in COLD SHUTDOWN within the-next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

c. With either relief valve / low-low set function pressure actuation trip system "A" or "B"' inoperable, restore the inoperable trip system to OPERABLE status within 7 days; otherwiseL be in at least NOT- SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and-in COLD SHUTDOWN within .the following-24 hours.

SURVEILLANCE-REQUIREMENTS 4.4.2.2.1- The relief valve function and the low-law set function pressure

~

actuation instrumentation shall be demonstrated OPERABLE by performance of a:

a. CHANNEL FJ1HCTIONAL TESI, including calibration of the trip . unit, ~at least ,

once per Q1 Qays / ]92

b. CHANNEL CALIBRATION, LOGIC SYSTEM FUNCTIONAL TEST. and simulated automatic-operation of the entire system-at least once per.18 months.

-- L, "The lif t setting pressure shall correspond;to ambient conditions:of- the valves at nominal oporating temperatures and pressures.

PERRY - UNIT 1 3/4 4-8

- - THIS PAGE IS INIHEIOPLLY BIANK ***

e i

Attachment 2 PY-CEI/NRR- 14 96L Page 39 of 50 3/4.3 INSTRUMENTATION BASES 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION The reactor protection system automatically initiates a reactor scram to:

a. Preserve the integrity of the fuel cladding.

b. Preserve the integrity of the reactor coolant system,

c. Minimize the energy which must be absorbed following a loss-of-coolant accident, and

d. Prevent inadvertent criticality.

This specification provides the limiting condition's for operation necessary to preserve the ability of the system to perform its intended function even during periods when instrument channels may be out of service because of main-tenance. When necessary, one channel may be made inoperable for brief intervals to conduct required surveillance.

The reactor protection system is maue up of two independent trip systems.

{ There are usually.four channels to monitor each parameter with two channels in each trip system. The outputs of the channels in a trip system are combined in a logic so that either channel will trip that trip system. The tripping of both trip systems will produce a reactor scram. The sys em meets the intent of IEEE-279 for nuclear power plant protection systems. The bases for the trip (in3ert{ '

settings of the RPS are discussed in the bases for Specification 2.2.1.

The measurement of response time at the specified frequencies provides assurance that the protective functions associated with each channel are com-pleted within the time limit assumed in the safety analyses. No credit was taken for those channels with response times indicated as not applicable.

Response time may be demonstrated by any series of sequential, overlapping or total channel test measurement, provided such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either (1) inplace, onsite or offsite test measurements, or (2) utilizing replacement sensors with certified response times.

i PERRY - UNIT 1 8 3/4 3-1

' Attachment 2

'PY-CEI/NRR-1496L Page 40 of 50 INSERT 6:

-Specified- surveillance intervals and surveillance and

' maintenance outage times have been determinedLin accordance with NEDC-30851P. " Technical Specificat,lon Improvement Analysis for BWR-Reactor Protection System," as approved by the NRC and documented in the NRC Safety Evaluation Report

, (SER). letter to T. A. Pickens from A. Thadani dated July 15, 1987. In regards ' to ACTIONS a - and b, Trip Capability is defined as each Functional Unit. being capable of . initiating a Reactor Protection System actuation '(without considering a further single failure event).

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Attachment:

2 PY-CEI /NRR- 14 96t, Page 4 I of 50 INSTRUMENTATION j 8ASES 3/4.3.2 ISOLATION ETUATION INSTRtMENTATION This specification ensures the effectiveness of the instrumentation used to mitigate the consequences of accidents by prescribing the OPERABILITY trip setpoints and response times. for isolation of the- r= actor systems. When neces-sary, one channel may be inoperable for brief intervals to conduct required nsere 7]where both the high and low values are critical and may have a substantial-surveillance > S effect on safety. The setpoints of _other instrumentation, where only the high or low and of the setting have a direct bearing on safety, are established at a level away from-the nomal operating range to prevent inadvertent actuation of the systems involved.

Except for the _MSIVs,. the safety analysis does not address individual sensor response times or the response times of. the logic systems to which the sensors are connected. For_0.C. operated valves, a 3-second delay is asstmed-before the valve-starts to move. For Atc. operated valves, it is assumed that-the A.C. power supply is lost and is restored by startup of'the emergency diesel generators. In this event, a time of 13 seconds is assumed before the ~

valve starts to move. In addition to the-pipe break,. the failure of the O.C.

operated valve is assumed;- thus the signal delay.(sensor _ response) is concurrent

(

s.

with the 13-second diesel startup.- The safety analysis considers an allowable inventory loss in each case which in turn determines the valve speed in conjunc-tion with the 13-second delay. It follows that checking the valve speeds and the 13-second time for emergency power establishment' will establish the response time for the isolation functions.

. Operation with a trip set less conservative than its Trip Setpoint but-within its specified Allowable Value is acceptable on .the basis that the-difference between each Trip Setpoint and the Allouable Value is_an allowance for-instrument drift specifically allocated for each trip .in the safety' analyses.

3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION-The-emergency core cooling system actuation instrumentation is provided to initiate actions to mitigate the consequences of accidents-that are beyond the ability of the operator to-control. - This . specification provides the OPERABILITY requirements, trip setpoints and-response times.that.will ensure

- effectiveness of the systems to provide the design protection. - Although the instrumsnts are listed by system, in some cases the same instrument may-be used sena the actuation signal to more than one system at the -same time.

Insert Operation with a trip . set less conservative than its: Trip Setpoint but within its specified Allowable Value is acceptable on the basis that'the difference between each Trip Setpoint and the Allowable Value is an allavance g- for instrument drift specifically allocated for each trip in _the safety analyses.

PERRY - UNIT'l B 3/4 3-2

Attachment 2 PY-CEI /NRR- 1496L Page _42 of $0 INSERT 7:

Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with NEDC-30851P, Supplement 2, '" Technical Specification Improvement Analysis for BWR Instrumentation Common to RPS and ECCS Instrumentation," as approved by the NRC and documented in the NRC Safety Evaluation Report (SER) letter to D.N. Grace from C.E. Rossi dated January 6, 1989 anu NEDC-31677P,

" Technical Specification Improvemmt Analysis for _BWR Isolation Actuation Inatt : %ntation" as approved by the NRC and documented in the NRC SER-letter to S.D. Floyd from C.E.

Rossi dated Jure 18, 1990.

INSERT 8:

Specified surveillance inter-als and surveillance and maintenance outage times have been determined in accordance with NEDC-30936P, Part 2, " Technical Specification Improvement Methodology (with Demonstration for BWR ECCS Actuation Instrumentation)" as approved by the NRC- and documented in the ~

NRC Safety Evaluation Report (SER) letter to D.N. Grace.from C.E. Rossi dated December 9, 1988 (Part 2).

(

A t t ac' ment ?

PY-CEI/NRR-1496t Page 43 of 50 INSTRUMENTATION hw BASES 3/4.3.4 RECIRCU(,ATION PUMP TRIP ACTUATION INSTRUMENTATION The anticipated transient witho.ut scram (ATVS) recirculation pump trip system provides a means of limiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient. The response of the plant to this postulated event falls within the envelope of study events in General Electric Company Topical Report NE00-10349, dated March 1971 and HEDO-24222, dated December 1979, and Section 15.8 of the FSAR.

CInsert

" 9h The end of-cycle recirculation pump trip (EOC-RPT) system is an essential safety supplement to the Reactor Protection System. The pu Pose of the EOC-RPT is to recover the loss of thermal margin which occurs at the end of-cycle. The physical phenomenon invcived is that the void reactivity feedback due to a pressurization transient can add positive reactivity to the reactor system at a faster rate than the control rods add negative scram reactivity. Each EOC-RPT system trips L"h recirculation pumps, reducing coolant flow in order to reducs the void collapse in the core during two of tS most limiting pressurization events. The two events for which the EOC-RPT protective feature will iunction are closure of the turbine stop valves and f6sf. closure of the turbine control valves.

A fast closure sensor from each of two turbine control valves provides inpu,t to the EOC-APT system; a fast closure sensor from each of the other two turbine control valves provides input to the second EOC-RPT system. Similarly, a position switch for each of two turbine stop valves provides input to one EOC-RPT system; a position switch from each of the other two stop valves provides input to the other E0C-RPT system. For each EOC-RPT system, the sensor relay contacts are arranged to form a 2-out-of-2 logic for the fast closure of turbine control valves and a 2 out-of-2 logic for the turbine stop valves. The operation of either logic will actuate the EOC-RPT system and trip both recirculation pumps. -

ITnsert10M k -

Each EOC-RPT system may be manually bypassert by use of a keyswitch which is administrative 1y controlled. The manual bypasses and the automatic Operating Bypass at less than 40% of RATED THERMAL POWER are annunciated in the control room.

The EOC-RPT system response time is the tint assumed in the analysis between initiation of valve motion and complete suppression of the electric arc, i.e., 140 ms. Included in this time are: the time ' rom initial valve movement to reaching the trip setpoint, the response ti:a of the sensor, the response time of the system logic, and the time allotted for breaker arc suppression, Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the

.. difference between each Trip Setpoint and the Allowablo Value is an allowance p- for instrument drif t specifically allocated for each trip in the safety analyses.

PERRY - UNIT 1 B 3/4 3-3

Attachment 2 PY-CEI /NRR- 14 96L Page 44 of 50 INSERT 9:

Specified survoillance intervals and surveillance and maintenance outage times have been determin - 8 in accordance with GENE-770-06-01, " Bases for Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times for Selected Instrumentation Technical Specifications" as approved by the NRC and documented in the NRC Safety Evaluation Report (SER) letter to from dated .

INSERT 10:

Specified surveillance intervals and surveillance and maintenance outage _ times have been determined in accordance with GENE-770-06-01, " Bases for Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times for Selected Instrumentation Technical Cpecifications" as approved by the NRC and documented in the NRC SER letter to from dated .

4 i

Attachment 2 PY-CEI /NRR- 14 e6L Page 45 of $0

~

INSTRUMENTATION

(.

BASES b4. 3. 5 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATIO The reactor core isolation cooling systen actuation instrumentation is provided to initiate actions to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to r - V.he reactor vessel.

D OpIeratio'n with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the differ-ence between each Trip Setpoint and the Allowable Value is an allowance for instrument drift specifically allocated for each trip in the safety analyses.

3/4.3.6 CONTROL R00 BLOCK INSTRtMENTATION The control rod block functions are provided consistent with the requirements of the specifications in Section 3/4.1.4, Control Rod Program Controls and Section 3/4.2 Power Distribution Limits. The trip icgic is arranged so that a trip in any one of the inputs will result in a control rod fneer > l

- > Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that' the differ-ence between each Trip Setpoint and the Allowable Value is an allowance for Wtrument drif t specifically allocated for each trip in the safety analyses.

( 3/4.3.7 MONITORING INSTRUMENTATION

3/4.3.7.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring instrumentation ensures that; (1) the radiation levels are continually measured in the areas served by the individual channels; (2) the alars or automatic action is initiated when the radiation level trip setpoint is en seded; and (3) sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with 10 CFR Part 50, Appendix A, General Design Criteria 19, 41, 60, 61, 63 and 64.

3.4.3.7.2 SEISMIC MONITORING INSTRUMENTATION The OPERABILITY of the selsnic monitoring instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.

This capability is required to permit comparison of the measured response to that used in the design basis for the unit. This instrumentation is consistent with the recommendations of Regulaton Guide 1.12 " Instrumentation for Earthquakes", April 1974.

3/4.3.7.3 METEOROLOGICAL MONITORING INSTRUMENTATION The OPERABILITY of the meteorological monitoring instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of I radioactive materials to the atmosphere. This capability is required to eval-uate the need for initiating protective measures to protect the health and safety of the public. This instrumentation is consistent with the recommenda-tions of Regulatory Guide 1.23 "Onsite Meteorological Programs," February,1972.

PERRY - UNIT 1 B 3/4 3 4

Attachment 2 PV-CE1/NRR- 14 96L Page 46 of 50 INSERT 11:

Specified surveillance intervala and surveillance and maintenance outage times have been determined in accordance with NEDC-30936P, Part 2. " Technical Specification Improvement Methodology (with Demonstration for BWR ECCS Actuation Instrumentation)" as approved by the NRC and documented in the NRC Safnty Evaluation Report (SER) letter to D.N. Grace from C.E. Rossi dated December 9,1988 (Part 2), and in accordance with GENE-770-06-01, " Bases for Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times _for Selected Instrumentation Technical Specifications" and GENE-770-06-02

" Addendum to Bases for Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times for Selected Instrumentation Technical Specifications". .which were approved by the NRC and documented in the SER letter to from dated

, and in the SER letter to G. Beck from C.E. Rossi dated September 13, 1991, respectively.

I IN. SERT 12: ,

Specified surveillance ' intervals and surveillance and maintenance outage times have been determined in accordance with NEDC-30851P, Supple' ment 1, " Technical Specification Improvement Analysis for BWR -Control Rod Block Instrumentation," as approved by the NRC and documented in the NRC Safety Evaluation Report (SER) letter to D.N. Grace from C.E. Rossi dated September 22, 1988, and in-GENE-770-06-01,

" Bases for Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times for Selected Instrumentation Technical Specifications", which were approved by the NRC and documented in the SER letter to - from dated' .

_ _ _ _ . _ _ _ _ _ . _ _ ------------_:-a- - - - - - - -

~.

Attachment 2 PY-CE! /NRR- 14 96L Page 47 of 50 INSTRUMENTATION I BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.9 Pl ANT SYSTEMS ACTUATION INSTRUMENTATION (Continued) pressure and the feedwater system / main turbine trip system in the event of a failure of the feedwater controller under maximum demand. The LPCI mode of the RHR systes is automatically initiated on a high drywell pressure signal and/or a low reactor water level, level 1, signal. The containment spray system will then actuate automatically following high drywell and high con-tainment pressure signals. A 10-minute minimum and a 11.5-minute maximum time delay exists between initiation of LPCI and containment spray actuation.

The suppression pool makeup systen is automatically initiated on a low suppres-sion pool water level signal with a concurrent LOCA signal or following a speciff ed time delay after receipt of a LOCA signal.

A t*,gh reactor water level, level 8, signal will actuate the feedwater system / main turbine trip system.

I 4

4 G

PERRY - UNIT 1 8 3/4 3-7

Attachment 2 PY-CE1/NRR-1496L Page 68 of 50 INSERT 13 Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with GENE-770-06-01. " Bases for Changes to Surveillance Test Intervals and Allowed Out-Of-Service Times for Selected Instrumentation Technical Specifications" as approved by the NRC and documented in the NRC Safety Evaluation Report (SER)

letter to from dated .

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.i_________~____

A t t ec htnen t 2 PY-CEI /NRR- 14 96L Page 49 of 50 REACTOR COOLANT SYSTEM I

BASES SAFETY / RELIEF VALVES (Continued)

Demonstration of the safety-relief valve lif t settings will occur only during shutdown and will be performed in accordance with the provisions of Specification 4.0.5.

I The low-low set system ensures that safety / relief valve discharges are l minimized for a second opening of these valves, following any overpressure tran- )

sient. This is achieved by automatically lowering the closing setpoint of 6 I valves and lowering the opening setpoint of 2 valves following the initial l opening. In this way, the frequency and magnitude of the containment blowdown i duty cycle is substantially reduced. Sufficient redundancy is provided for !

the low-low set sysi.em such that failure of any one valve to open or close at e its reduced setpoint does not violate the design basis,

^ anort W 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE '

3/4.4.3.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect Irakage from the reactor coolant pressure boundary. (hese detection systems are consistent with the recommeendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection I Systems", May 1973. ,

3/4.4.3.2 OPERATIONAL LEAKAGE The allowable leakage rates from the reactor coolant system have been based' on the predicted and experimentally observed behavior of cracks in pipes. The normally expected background leakage due to equipment design and the detection capability of the instrumentation for detensining systen leakage was also con-sidered. The evidence obtained from experiments suggests that for leakage -

somewhat greater than that specified for UNIDENTIFIED LEAKAGE the probability is small that the imperfection or crack associated with such leakage would grow rapidly. However, in all cases, if the leakage rates exceed the values specified or the leakage is located and known to be PRESSURE BOUNDARY LEAKAGE, the reactor

, will be shutdown to allow further investigation and corrective action.

The Surveillance Requirements for RCS pressure isolation valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA. Leakage from the RCS pressure isolation valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit, i

PERRY - UNIT 1 B 3/4 4-3

._-._ _._. _._____.,_. _ ___._ _ . _ m.. .._ _._ _ _ _ _ _ _ .___ _ _ . . _ _ _ . _ . .

I Attachment 2 i PY-CE! /NRR- 14 961, j Page 50 of $0 1

i l

1 INSERT 14:

i j Specified surveillance intervals _ and surveillance and

! maintenance outage times have been_ determined in accordance

! with GENE-770-06-01, " Bases for Changes to Surveillance Test i Intervals and Allowed Out-Of-Service Times for Selected

Instrumentation Technical SpecificatAona" as approved by the

[ NRC and documented in the_NRC Safety Evsluation Report (SER)

! letter to from dated .

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4 Proposed Repair Allowed Out of. Service Tirne Modifications to the ECCS Actuation Instrwnentation Standard Technical Specifications 4

9 1

v- - - - - - -

t TABLE 3*.3.3-1(Continu'edi EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION _

'nCTION

ACTION 30 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement:

a. With one channel inoperable, place the inoperable channel in the tripped condition within ett Mur* or declare the -

associated system inoperable.

Y hou't%

.b . . With more than one channel inoperable, declare the

'tssociated system inoperable. .

ACTION 31 -

With Minimum the number of OPERABLE channels less than required by the OPERABLE Channels per Trip Function requirement, declare ,,

the associated ECCS inoperablea)/t% .M have ACTION 32 -

With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition withit --- St ,

ACTION 33 -

With the number of OPERABLE channels less than requirh)hd

Minimum the inoperable OPERABLE channel inChannels the tripped percondition Trip Function within requirement,

. ;r; play.7%m3 restore the inoperable channel to OPERABLE status within 7 days or declare the associated system inoperable.

ACTION 34 -

With the number of OPERABLE channels less than m quired by the

Minimum OPERABLE Channels per Trip Functicn requirement, restore the inoperable channel to OPERABLE status within 4-hpurs or declare the associated ECCS inoperable.

ACTION 35 -

44 how.3 With the number of OPERABLE channels less than required by the Minimum CPERABLE Channels per Trip Function requirement:

a. For one trip system condition within :::, place that trip system in the tripped inoperable, ba" or declare the NPCI system p 4 llevo -

b.

For both trip systems, declare the HPCI system inoperable.

ACTION 36 -

With the number of OPERABLE channels less than mquired by the Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within -

-- S;r" or declare the HPCI system inoperable. .

ACTION 37 - t

. tSe umber of OPERABLE channels less than the Total Nu of Channels, declare the associated emergency diesel generator ,

inoperable and take the ACTION mquired by Specification 3.6.1.1 or 3.8.1.2, as appropriate.-

ACTION 38 -

With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped

' condition'within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ;* operation may then continue until performance of the next required CHANNEL FUNCTIONAL TEST.

"The provisions *of Specification 3.0.4 are not applicable. '

GE-STS (BWR/4) 3/4 3 -

i TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION I

ACTION ACTION 30 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip (System) (Function) requirement:

(For "per Trip System") /.24 heve

a. For one trip system place at least go inoperable channel in the tripped condition within p f"

or declare the l associated ADS trip system or Ecc5 inog rable. -

b. For both trip systems, declare the associated ADS trip !

system or ECCS inoperable. '

(For "per Tria Function")

a. For the LPCS system and the LPCI moce of the RHR system, declare the associated LPCS and/or LPCI systems inoperable.

b. For the HPCS system and the ADS:

1. With one channel inoperable place the ino channel in the tripped condition wihtin o @perable

"

or declare the HPCS system and associated ADS' trip g system inoperable, heud

{- 2. With more than one channel inoperable declare the HPCSsystemandtheassociatedADStrlpsystem(s) inoperable.

ACTION 31 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement d.M.6 M b s declare the associated ADS trip system or ECCS inoperable.

ACTION 32 - With the number of OPERABLE channels less than required by the Minimum 0PERABLE Channels per Trip System requirement, verify bus power availability at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or declare the associated ECCS inoperable.

ACTION 33 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Tri) Systsm requirement, restore the inoperable channel to OPERABLE status with4p or declare the associated ADS valve or ECCS inoperapie.

ACTION 34 - With the number of OPERABLE channels less than' required by the Minimum OPERABLE Channels per Trip System requirement, place at least one inoperable channel in the tripped condition within

= M =" or declare the HPCS system inoperable. l 9 y hovY.5 "The provisions of Specification 3.0.4 are not applicable. l GE-STS(BWR/5) 3/4 3 27

. TABLE 3.3.3-1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION (Continued)

ACTION 35 -

With the number of OPERABLE channels less than the Total Number of Channels, declare the associated emergency diesel generator inoperable and t d e the ACTION required by Specification 3.8.1.1 or 3.8.1.2, as appropriate.

ACTION 36 - With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months *; operation may then continue until I performance of the next required CHANNEL FUNCTIONAL TEST.

O "The provisions of Specification 3.0.4 are not applicable.

GE-STS (BWR/5) 3/4 3-27a 1

4 TABLE 3.3.3 1 (Continued)

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION I MTjg ,

ACTION 30 -

With the neber of OPEMBLE channels less than required by the -

Minimum CPEMBLE Channels per Trip Function requirement:

4.

With one channel inoperable, place the inoperable channel in the tripped condition within : : " ; " or declare the associated system inoperable. # </ h ea t6

b. -

With more than one channel inoperable, declare the associated systes inoperable.

ACTION 31 -

With the number of OPERABLE channels less than required by the Minimum 0PERAPLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within ene-Jt/ he."ort hour. Restore the inoperable channel to OPERABLE status within 7 days or declare the associated systas inoperable.

ACTION 32 -

With Minism the neber of OPEMBLE channels less than requimd by the declare the associated ADS trip system or ECC$ inoperable. OP ACTION 33 -

With the number of OPEMBLE channels less than the Minism OPERABLE Channels per Trip Function requirement, piece the inoperable channel in the tripped condition within - " " .

CTION M -

With the number of OPERABLE channels less than requfredkthi Minism OPERABLE Channels pe. Trip Function mquirement, verify w I

bus power availability at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or declare 7

\ the associated ECC$ inoperable.b.

ACTION 35 - X With the nabar of OPERABLE channels less than mhfred by the Minimus OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within4-hom or '

ACTION 36 - declare the associated AD$ valve or ECCS inoperable.\g fg With the n eber of OPERABLE channels less than requim d by the Minteum GPEMBLE Channels per Tri ton mquirement:

n. For one trip system condition within n, 9

or declarep the system in the tripped HPCS systen inoperable, b.

For both trip systems, ee-lars the HPCS system inoperable.

ACTION 37 -

With the neber of OPERABLE channels less than mquired by the Minism OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within

- - h

or declare the HPCS system inoperable.

ACTION 38 - '

Number of OPEMBLE channels less than the Total Numbe of Channels, declare the associated emergency diesel generator

~

inoperable and take the ACTION required by Specificet'on 3.B.1.1 ,

or 3.8.1.2, as appropriate.

ACTION 39 -

With the number of OPERABLE channels one less than the Total Nuncer of Channels, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months *; operation may then continue until perfomance of the next required CNANNEL FUNCTIONAL TEST.

"The provisions of 5pecification 3.0.4 are not appliable.

GE-STS(BVR/6) 1/4 3-31

3 ..

4

[ TABLE 3.3.3 1 (Continued) f [M[RG[NCY CORE COOLING SYSTFM ACTUATION INSTRUMENTATION l ACTION ACTION 30 - With the number of CPERABLE channels less than required by the

., Minimum OPERABLE Channels per Trip Function requirement:

1

a. With one channel incperable, place the inoperable channel

in the tripped condition within n-he$rr" or declare the

, associated system inoperable. 2-y hcot%S*

! b. With amore than one channel inoperable, declare the associated

system inoperable.

! . ACTION 31 - Deleted.

l ' ACTION 32 -

With Minieuethe number of OPERABLE channels less than required try)theOP

, . declan the associated AD$ trip system or ECC5 inoperable.

I ACTION 33 - With the number of OPERABLE channels less than the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable channel (s) in the tripped condition within4-hous, ACTION 34 - Deleted. U lladt6 ACTION 35 - With the number of OPERABLE channels less than n eutred by the Minimum CPERABLE Channels per Trip Function requirement, restore i

the inoperable channel to OPERABLE. status within a "rr

. , declare the associated AD$ valve or ECC5 inoperable.N; ory /g,. 3 l >

h

(-

ACTION 36 -

With the number of OPERABLE channels less than required by the Minimum CPERABLE Channels per Trip Function requirement:

i i a. For one trip system, place that trip system in the tripped condition within c/hovrb- M a* or declare the HPC$ system inoperable, f i b. For both trip systees, declare the HPCS system inoperable.

. ACTION 37 - With the n"% =r of OPERABLE channels less than required by the .

Minieur liPERABLi Channels per Trip Function Meutrement, place at

east one inopeuble channel in the tripped condition within 1

"r*g declare th HPCS systes inoperable.

( . ACTION 3B t the number of OPtRABLE channels less than the Total Number .

of Channels, declare the associated emer0euy diesel generator

. inoperable and take the ACTION required by Specifications 3.8.1.1 J'

or 3.8.1.2, as appropriate.

9

ACTION 39 - With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped i i condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months "; operation may then continue until performance of the next required CHANNEL FUNCTIONAL TEST.

! . ACTION 40 - With the number of OPERABLE channels'less than required by the Minimum CPERABLE Channels per Trip Function requirement, place i,

the inoperable channel in the tripped condition within n; W.Whe.vt,5 Restore the. inoperable channel to OPERABLE status within i days.

or declare the associated system inoperable.

The provisions of Specification 3.0.4 are siot applicable.

CLINTON - UNIT 1 3/4 3 38 k

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Enclosure 2 Proposed Modifications to.the RCIC Actuation Instrumentation BVR Standard Technical Specifications

1 Bk'R 4 RCIC Actuation Instrwnentation Technical Specification O

i

i INSTRUMENTATION

[

3/4.3.5 REACTOR C0RL_150LAT10N COOLING SYSTEM ACTUATION INSTRUMENTATION LIMITING CONDITION FOR Of**ATljN

3. 3. 5 The reactor core isolation cooling (RCIC) system actuation j

instrumentation channels shown in Table 3.3.5-1 shall be OPCRABLE with their 1 trip setpoints set consistent with the values shown in the Trip Setpoint i column of Table 3.3.5-2.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3 with reactor steam 4

dome pressure greater than (100) psig.

ACTION:

a. With a RCIC system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.5 2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint *

adjusted consistent with the Trip 5etpoint value.

b. With one or more RCIC system actuation instrumentation channels

{j inoperable, take the ACTION required by Table 3.3.5-1.

SURVEILLANCE REQUIREMENTS 4.3.5.1 Each RCIC system actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.5.1-1.

4.3,5.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

4 i

GE-STS (BWR/4) 3/4 3-46

. . .. .-. , . . . - . _ . - ~- .- . - - . . _

4 o

j 3 TABLE 3.3.5-1 l

$ ~

, REACTUR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION

=

E MININUM 3 FUNCTIONAL UNITS OPERABLECHANNEL{,)

, PER TRIP SYSTEM ACTION

a. Reactor Vessel Water level - (Low low. Level 2) 2 50

b. Reactor Vessel Water Level - High Level (8) 2 I) 51

c. Condensate Storage Tank Water Level - Low (2)ICI 52

, d. Suppression *~wl Water Level - High (2)IC 52

e. Manual Initiation (1)/(system)I I (53) b y (a) A channel may be placed in an inoperable status for up to K hours for required survelliance without

placing the trip system in the tripped condition provided at least one other OPERA 8tE channel in the a same trip system is monitoring that parameter. .

(b) ' One trip - system with two-out-of-two' logic.

(c) - One trip system with one-out-of-two logic.

(d) One trip system with one channel.

4

&'*g

itinued)

REACTOR COR, af!0N COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION 50 - With 15e number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement:

a. For one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition within :n: h;gr or declare the RCIC system inoperable. #V hour.b

b. For both trip systems, declare the RCIC system inoperable.

' ACTION 51 - With the number of OPERABLE channels less than required by the.

minimum OPERABLE channels per T ip System requirement, declare the RCIC system inoperableul, ht ;14 hour1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months 5, ACTION 52 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place.

at least one inoperable channel in the tripped condition within se,i,vvi- or declare tne RCIC system inoperable, e24hovt.b ACTION 53 - With the number of OPERABLE channels one less than required by the Minimum OPERABLE Channels per Trip System requirement, restore the inoperable channel to OPERABLE status within (0) 5:ure or declare the RCIC system inoperable.

$/V hoJWG OE-STS (BWR/4) 3/4 3-48

____o

. _ . - . . .~ . ... - _ . -._. .- ... . -. . _ . - . . - . _ -. .. .

E J, TABLE 3.3.5-2 ;

.d

m. REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTHUBENTATICII SETPOINTS E

R ALLOWRSLE ,

FtWICTIONAL UIIITS TRIP SETPoiNT VALUE

a. Reactor' Vessel Water Level - (Low Low, Level 2) 1 - (38) inches

1 -( ) inches

~

b. Reactor Vessel Water level - High, Level.(8) 5 (54) inches *' $ (55.5) inches c.' Condensate' Storage Tanit Level - Low 1( ) inches >( ) inches

.d. _ Suppression Pool Water level - High 5( ) inches i( ) inches

-e.- Manual' Initiation MA NA Y-

"See Bases Figure 5 3/4 3-1.

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3 TABLE 4.3.5.1-1

[w REACTOR CORE ISOLATION COOLING SYSTEM ACTUATIDW INSTRUMENTATION SURVEILLAfCE REQUIREMENTS

'E CHANNEL D CHANNEL FUNCTIONAL CHANNEL FUNCTIONAL UNITS' CHECK TEST CALI8".ATION 1

a. Reactor Vessel Water Level -

Yk.

(Low Low, level 2) S X R

b. Reactor Vessel Water Level.- High, Level (8)

S M- Th R

c. Condensate Storage Tank Level - Low (S) " -

7-h (R) w d. Suppression Pool Water Level -

-A

.High (S) "

7 (R) -

w h e. Manual Initiat'on NA (M(a)) gg) gg

.((a) Manual initiation switches shall be tested at least once per 18 months during shutdown. All other circuitry associated _with manual initiation shall receive a CHANNEL FUNCTIONAL TEST at least once per 4P days as_part of circuitry required to be tested for automatic system actuation.)

92 e

4 r's w

1 l

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j BWR 5 RCIC Actuation Instrumentation Technical Specification O

4 i

INSTRUMENTATION I

1 3/4.3.5 REACTOR CORE ISOLATIM COOLING SYSTEM ACTUATION INSTRUMENT LIMITING CONDITION FOR OPERATION 3.3.5 The reactor core isolation cooling (RCIC) system actuation instrumenta-tion channels shown in Table 3.3.5 1 shall be OPERABLE with their trip set-points set consistent with the values shown in the Trip Setpoint colern of

, Table 3.3.5-2. j APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3 with reactor steam l done pressure greater than (100) psig. l ACTION:

a.

With a RCIC system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable values column of Table 3.3.5-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b. With one or more RCIC system actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.5 1.

O SURVE1LLANCE REQUIREMENTS 4.3.5.1 Each RCIC system actuation instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL cat 1BRATION operations at the frequencies shown in Table 4.3.5.1-1.

4.3.5.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

GE-STS (BWR/5) 3/4 3-45

O E

J. TABLE 3.3.5-1 l v.

l - REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUNENTATION "c

R MINIfRM S OPERABLECHANNEl{*)

FUNCTIONAL UNITS PER TRIP SYSTEN ACTION

a. Reactor Vessel Water Level - (Low Low, Level 2) 2 50 I

b. Reactor Vessel Water Level - High 2(b) 51

c. Condensate Storage Tank Water Level - Low (2)IC) 52 l

d. Suppression Pool Water Level - High (1)(d) 52 l

e. Manual Initiation (1)/(system)(d) 33 g k

Y (a) A channel may be placed in an inoperable status for up to hours for required serveillance without

& placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

(b) One trip system with two-out-of-two logic.

(c) One trip system with one-out-of-two logic.

(d) Single channel. l

. . - . - . . - _ _ - - - _ _ = . - -- . - . . . ._ . - . . . - -

4

~1 i j' _ TABLE 3.3.5-1 (Continued) l REACTOR CORE ISOLATION C00LINC SYSTEM ACTUATION INSTRUMENTATION

' ACTION 50 -

4 With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement:

i s.

For one trip system place the inoperable channel in the i tripped condition wIthin =; M.: or declare the RCIC system inoperable. JLyhogy) b.

For both trip systems, declare the RCIC system inoperable.

ACTION 51 -

With the number of OPERABLE channels less than required by thi minimum OPERABLE channels per Trip System requirement, declare the RCIC system inoperable a f g /ffy p q -h o g l' ACTION 52 -

i With the number of OPERABLE channels less than required by the e Minimum OPERABLE Channels per Trip System requirement, place at least one-inoperable channel in the tripped condition-j

~

within M r:h & .bM r or declare the RCIC system inoperable.

i ACTION 53 -

With the number of OPERABLE chennels'one less than required by

the Minimum OPERADLE Channels per Trip System requirement, ,

]

(() restore the inoperable channel to OPERABLE status within 4') M r; or declare the RCIC system inoperable.

l

2 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .S i

GE-STS(BWR/5) 3/4 3-47 4

2

s. , .

~

E g TA8LE 3.3.5-2 m

g REACTOR CORE IS01AT10N COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS 4 ALLOWABLE O FUNCTIONAL IMITS TRIP SETMINT VALUE

a. Reactor Vessel Water level - (Low Low, Level 2) > - (38) inches * > -( . ) inches

l

b. Reactor Yessel Water level - High 5( .) inches *- 1( ) inches *

c. Condensate Storage Tank. Level - Low . >( ) inches >( ) inches

d. Suppression Pool Water Level - High 5 (- ) inches 5( ) inches l

e. Manual Initiation N4. NA l

C g'-seeeasesrigoreW3/43-1.

)

. _ _ _ _ _ _ _ _ _ _ . ___ _...,.r . . + * - - - - ' ' ' ' ' "' ' ' ' ' ' "

h

O R

TABLE 4.3.5.1-1 m

REACiOR CORE ISOLATION $00 LING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS R CHAletEL

$ CHANNEL FUNCTIONAL CHANNEL FUNCTIONAL UNITS CHECK TEST CALIBRATION '

a. Reactor Vessel Water Level -

(Low Low, Level 2) S ri N R l

b. Reactor Vessel Water Level.- High 5 M >Q R

c. . Condensate Storage Tank Level - Low (5) "

% (R) l R. d. Suppression Pool Water Level -

High (5) M

>Q (R) l b e. Manual Initiation MA M) > NA' g

1 (a) Manual- initiation switches shall be tested at least once per 18 months during shutdown. All other circuitry associated with manual initiation shall receive a CHANNEL FUNCTIONAL TEST at least once

.per Ways as part of circuitry required to be tested for automatic system actuation. l l {'-

l J

2 4

Bk'R 6 4

RCIC Actuation Instrumentation Technical specification O

VJ 4

e i

4 l

INSTRUMENTATION 3/4.3.5 RCACTOR CORE ISOLATION COOLING $YSTEM ACTUATION INSTRUMENTATION i

LIMITING CONDITION FOR OPERATION '

3.3.5 The reactor core isolation cooling (RCIC) system actuation instrumenta- .

tion channels shown in Table 3.3.51 shall be OPERABLE with their trip set-points set consistent with the values shown in the Trip Setpoint column of Table 3.3.5-2.

APPL.ICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3 witt. reactor steam done pressure prester than (100) psig.

ACTION: .

a.

With a 'RCIC system actuation instrutantation channel trip setpoint less conservative than the value shown in the Allowable values column of Table 3.3.5-2, de:lare the channel inoperable untti the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value, b.

With ont or more RCIC systee actuation instrumentation channels i inoperable, take the ACTION required by Table 3.3.5-1.

SURVEILLANCE REQUIREMENTS 4.3.5.1 Each RCIC system actuation instrumentation channel-shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST 4.3.5.1-1, and CHANHCL CAlllRATION operations at the frecuencies shown in Table 4.3.5.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

e e

GE-STS (BWR/6) 3/4 3-49

- TA8tt 3.3.5-1

.R

~ REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION IN5il W RTATION n NIN!fRNt E .

' OPERA 8ttCHANNEL{*I j FUNCTIONAL INitTS -

PER TRIP SYSTEN ACTION

- a. Reactor Vessel Water level glow Low, Level 2) 2 50 g

b. Reactor Vessel Water Level - Nigh. Level 8( 2(b) 51 K.

c. Condensate Storage Tank Water Level - Low (2)I*I 52 d.. Suppression Pool Water Level - Nigh (2)I*) 52

e. Meneal Initiation ,

(1)/(system)IdI 53 t'

+

Ta) A channel may be placed in an fnoperable states for up to A hours for required servelliance withewt '

placing the trfp system in the tripped condition provided at least one other OPERA 8tE channel in the

'T same trip system Is monitoring that parameter.

5 (b) One trip systemawith two-out-of-two logic.

(c) One trip' system with one-out-of-two logic.

(d) One. trip system with one channel.-

~

O g

g

,' O e- ..r,... . .

~

INSTRUMENTATION TABLE 3.3.5-1 (continued) .

REACTOR CORE 150i.ATION C00L16G SY5 TEM ACTUATION Mh5TRUMENTATION ACTION 50 -

With the number of OPERABLE channels less than reqvfred by the Minimum OPERABLE Channels per Trip System ?equirement:

w'ad. w& -J yn

+

a. 't

"^ ^'

: tri; .,.^a-lPface %,

. the inoperable channel (pY

_ f a.;'m

^

in the tripped condition within ;r.; 5:gr )/ -

er declare the RCIC system inoperable.

tu' at. m X4.~ H -J: =& ' ;" Ab $9 hour $ *

b. W L^.L t; :; :y:'- , declare the RCIC system inoperable.

ACTION 51 -

K With the number of OPERABLE channels less than required by the Minimum OPERABLE channels per Trip systes requirennt, declare the RCIC system-inoperableuN/Jr/,, .7ybrs.

ACTION 52 -

g g With the number of OPERABLE channels less than required by the Minimum OPERA 8LE Channels per Trip System requirement, place at least one inoperab' channel in the tripped condition within u; h;;r or re the RCIC system inoperable.

Offhevo ACTION 53 -

With the number of OPERABLE channels less than required by the Minimum CPERABLE Channels per Trip System requirement, restore

- ia a r 61 ca aa i to oata^='t is t== itata : :==: ar (O declare the RCIC system inoperable, ptf hovr:s-SP A

t-GE-STS (BWR/6) 3/4 3-51

. __m-____-_u_----^- ^ " " - -

/

O .

g TABLE 3.3.5-2 '

i REACTOR CORE ISOLATION COOLING SYSTEM ACTIAATION INSTIRMNTATION SETP0INTS

=

AtLOWBLE k- FUNCTIONAL WITS ,/ TRIP SETPOINT VALUE -

~

a. Reactor Vessel Water level - Lew tow, tevel 2] 1 -(51) Inches

1 -(53) laches y

b. ReactorVesselWaterLevel-High,tevelf8[ $ (52) inches * $ (52.6) Inches k.

c. Condensate Storage Tank Level - tow 1 (14) inches '9) inches 1

d. Suppression Pool Water Level - High 5 (5) Inches $ W I) Inches

e. Marsal IntLlation nn-

NA , .

"See Bases Figure B 3/4 3-1.

R=

l

'C' C

h e -t- ..e.... . .

I c, '

T . TA8tE 4.3.5.1-l'

.h co REACTOR CODE ISOLATION COOLING SYSTEM ACitMTION INSTRUNENTATION SURVE

$i CHANNEL [

CHANNEL p, FUNCTIONAL UNITS FUNCTIONAL CHAf81EL ' I

_CIECK TE51 CALIBRATION

a. Reactor Vessel Water Level -

owtow, Level 2k M+k

$ R(a)-

b.

Reactor Ves*sel Water Level - High, LevelST (/ 9 -- 5 Ok . R

c. Condensate Storage Tank b d.

Level - tow 5 M4k R Sgpression Pool Water Level -

High A 5 M4 W R

e. Mensal Initiation MA u M MA 4

4.

" X (a) Ca11brate trip unit at least once per% days.

R 99--

1(b) Manual Initiation switches shall be tested at least once per 18 months during shutdown. All other circultry associated with manual initiation shall receive a CHAMMEL FUNCTIONAL TEST at least once g per 3( days as a part of circuitry required to be tested for automa'.lc system actuation.

9,1--.

X i

ie I

J 4 .

g .

4' . 4 #* . 4

4 BWR 6 (Clinton) Solid State RCIC Actuation Instrumentation Technical Specification e

4 1;

4 4

INSTRUMINT ATION 3/4.3.5 REACTOR CORE 15'OLAT!0N COOLING SYSTEM ACTUATION IN3TRUMENTATIO L1H1 TING CONDITION FOR OPERATION 3.3.5 The reactor core isolation cooling (RCIC). system actuation instrumenta-tion channels shown in Table 3.3.51 shall be OPERABLE with their trip set-points set consistent with the values shown in the Trip 5etpoint column of Table 3.3.5-2.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3 with reactor steam dome i

pressure great,er than 150 psig.

l

. ACTION:

- a. With an RCIC system actuation instrumentation channel trip setpoint less conservative than the value shown in the Allowable Value column of Table -

3.3.5-2, declare'the channel inoperable until the channel is restored to l

OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value.

b. With one or more RCIC system actuation instrumentation channels

' inoperable, take the ACTION required by Table 3.3.5-1.

Oi SURVE1LLANCE REQUIREMENTS 4.3.5.1 Each RCIC system actuation instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHEC'., CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the _ frequencies shown in Table 4.3.5.1-1. _. __

4.3.5.2 LOGIC All SYSTEM FUNCTIONAL TESTS shall be performed at least once per RCIC actuation system logic shall be manually tested

18 months.

independent of the SELF TEST SYSTEM such that all trip functions are tested at least once every four fuel cycles." .

I I

i.

" Manual testing for the purpose of satisfying Specification 4.3.5.2 is not ling

. required until after shutdown during the first regularly scheduled refue outage. '

h CLINTON - UNIT I 3/4 3-58

TABLE 3.3.5-1 0: j.

.. n

5 REACTOR CORE ISOLATION C00 TING SYSTEM ACTUATI0tt INSTRUMENTATION :

-g . .

MIN 19RJM -

OPERABLE CHiNNELS i 5

d PER TRIP SYSTEM ACit0N v FUNCTIONAL IMITS .

e. .

Reactor. Vessel Water tevel - Lew Low, tevel 2 2.(b)(a) 50 a.

. Reacter Vessel Water Level - High, level 8 2 IC) 51

b. '

c. RCIC Storage Tank Water Level - Low 2(d)(a)- 52

d. Suppeession Pool Water Level - High . 2(d)(a) 52

e. Manual' Initiation II 'I 53 k

1 O '

o Q

y i

e Y

~ . . ,

TABLE 3.3.5 1 (Continued)

' REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION .

, TABLE NOTATIONS 6 .

. (a) A channel may be placed in an inoperable status for up to I hours for

-l required surveillance without placing the trip system in the trjpped 4 condition provided at least one other OPERABLE channel in the same trip

! system is monitoring that parameter.

(b) Two trip systems with two channels per trip system.

> 4 (c) One trip system with two-out-of-two logic.

(d) One trip system with one-out-of-two-logic.

(e) One trip system with one channel.

l l ACTION ACTION 50 - With the number of OPERABLE channels less than required by the Minimum OPERABL: Channels per Trip System requirement:'

t

a. For-1 trip system, place the inoperable channel (s) and/or

.that. trip system in the tripped condition within -- ' -

or declare the RCIC system inoperable. J4 hcut*& ,

b. 'orbok.htripsystems,declaretheRCICsystem' inoperable.

ACTION $1 - With the number of OPERABLE channels less than required by the.

Minimum OPERABLE channels per Trip System requirement, declare 1 the RCIC system inoperable AN% #<./ how.s. c .

1 1 ACTION 52 - With the number of OPERABLE channels less than required by the Minimum 0FERABLE Channels-per Trip System requirement, place at least one inoperable channel in the tripped condition

. within 44 ewe or declare the RCIC system inoperable.

- #4 how5 i ACTION 53 - With-the number of OPERABLE channels'less than required by the l Minimum OPERABLE Channels per Trip 5ystem requirement, restore

( the inoperable channel to OPERABLE status within O R .. or -

j declare the RCIC system inoperable, y Jugg f

4 CLINTON ** UNIT 1 3/4 3-60

, , y . . . , - . . . ...w- .. . , _ . ~ . _ . - - ,

.5-2 TAB b REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION IItSTRUNENTATION SETPOINTS '

5 '

E ALLOWetE TRIP SETPOINT VALUE b FUNCTIONAL INitTS -

a - Reactor Vessel Water Level - Low tow, Level 2 1 -47.7 in.

a. 1 -45.5 in.* ,

I

[

b. Reactor Vessel Water tevel - High, tevel 8 1 52.0 in." $ 52.6 in.

c. RCIC Storage Tank tevel - tow 1 3% fn.** 1 0 in.** ,

d. Suppression Pool Water level - High i 6\ in.t $ 12 in.t .

NA NA

e. Manual Initiation ,

R

'* See Bases Figure 8 3/4 3-1.

y ** Instrument zero is 739' 10-3/4" as).

t Instrument zero is 731' 5" as1.

I e

9 t

O e e

O' 1 .

e i

~

TABLE 4.3.5.1-1 g b REACTOR CORE ISOLATION C00t1NG SYSTDI ACTUATION INSTRUPOITATION SURVEILLANCE REQUIREMENTS

'i .

g CHANNEL CHANNEL FUNCTIONAL CHANNEL -

. c- .

CifECK TEST CALIBRATION-5 FINICTIONAL INIITS a.- Reactor Vessel Water Level -

>h RI *)

Low tow, tevel 2 S M

b. Reactor Vessel Water RI *)

level - High, tevel 8 S M

)k

c. RCIC Storage Tank .. %

' g(a) 5 "

tevel - Lov

d. Suppression Pool Water Level - ,

s Rg ,)

S n w High A MA R NA w e. Manual Initiation

f. -

.(a) Calibrate the analog trfp module at least once perKdays.

9L 9

e

+

6

- t

g 8 GE Naciner Energy ornenwe comm

- In cow Aena. Se .w CA 95125 March 22, 1990 MTN 024 90 OC90 319 32D Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D..C. 20555 Attention: Millard L'.-Wohl -

i Technical Specification Branch-

Subject:

Clarification of Technical Specification-Changes Given ir RCCS Actuation Instrumentation Analysis

Reference:

NEDC-30936P A, *BWR Owners' Group Technical Specification Improvement Methodologyi(With Demonstration for BWR ECCS.

Actuation Instrumentation). Part 2,: December 1986.

The purpose of this letter is to provide you wit.h information that we have: forwarded to each BUR Owner to support his plant specific submittal.of changes to the ECCS actuation instrumentation surveillancoctest intervals-(STIs) and allowed out-of-service' times l(A0Ts)' given 'in the _Referenc'e. : The information deals with clarifications to modified technica1' specifications given in Appendix A of the Reference. ,

'The first clarification concerned the proposed change to-the repair A0Ts given on pages A-3 and A-9 for BWR 6 Solid State Plants, pages'A-4.and A-14 for BWR $/6 Relay Plants, and pages A 4 and A-18 for BWR 3/4 Plants.

In the technical specification markup for:the above product lines, Table-

, _ 3.3.3-1 was not . included. in Appendix A jof: the' Reference report. _ The; proposed modification as written implies ~a-24 hour A0T before taking any.

action listed in Tabla 3.3.31; It was intended that:the A0T.of 241 hours0.00279 days 0.0669 hours 3.984788e-4 weeks 9.17005e-5 months apply.to the individual. actions listed in Tablef3.3.3 1. -Therefore, we have-advised each utility to make the:following: changes relating to repair A0T in--

their plant specific submittals:

a) No change to Action b~.7 of paragraph 3/4.3.3. The paragraph should read as f611ows:-

'With one or more ECCS actuation instrumentation channels inoperable,-

take the' ACTION required by Table 3.3.3-1."

b) Revise ACTIONS given'in Table-3.3~3-1 according to the:: attached-Table 3.3;3-1 modifications (Enclosure 1) for Standard Tachnical' Specifications.

'The uecond clarification-dealt with techn! cal specification changes to the reactor- core it.olation cooling (RC.1C) system. The Reference analysis NO7 6 2 3 -1

_ d

i.

s' M111 erd L. Wohl Page 2

March 22,.1990 included proposed STI and A0T_ changes to this system (see last paragraph of.

j page 2 1). However, markups of the_ proposed modifications as they should appear in the Standard Technical Specifications for the RCIC actuation were

~

not provided in Appendix A of the Reference report, .The attached markups (Enclosure 2) of the Standard Technical Specifications for the RCIC actuation instrumentation were provided to the BVR Owners;for their use in tt.eir plant specific submittals, We feel the above information has been considered in the Reference NRC *

approved analysis and represent clarifications to ensure plant s'pecifio changes are properly interpreted. - Please give one of us a call if you should have any questions, 1-Very truly yours, 4

h >r ,,, J sf ^4 wg W. P. Sullivan _

J. F. Klapproth Reliability Engineering Services BVR Owners': Group. Programs M/C 789 (408)925 6992 M/C 382 (408)925 5434 4-l f

! . - Enclosures i

cc: BVROG Technical Specification Committee - D BVROG Primary Representatives of- Participating. Utilities S. D. Floyd,.BWROG Chairman G. J. Beck, BWROG Vice ' Chairman D..N. Grace, RRG Chairman

L. S. Gifford'(GE Rockville)

S. J. Stark (GE)

A. E.' Rogers-(GE)

(

a m- y w. .- .-4 .-# -... , r , , , .,.y -.e-,.w.,or . * *ea ++4e

. . - . . . . - , . . . , - , , . . ~ - . . .. ..

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N b-ENCLOSURE 3 4

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