ML20059L412

Proposed Tech Specs,Relocating Tables of Response Time Limits for Reactor Protection Sys & ESFAS Instruments from TSs to Updated FSAR

ML20059L412
Person / Time
Site:	Calvert Cliffs
Issue date:	11/11/1993
From:	BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20059L409	List: ML20059L405 ML20059L412
References
NUDOCS 9311170060
Download: ML20059L412 (16)

Text

i f

r ATTACHMENT (1)

UNIT 1 TECIINICAL SPECIFICATION REVISED PAGES 3/43-1 3/43-6 3/43-7 3/4311 3/4 3-21 l 3/4 3-22 B 3/4 3-1 l

I 9311170060 931111 7 PDR ADOCK 05000317 P PDR Li

1 3/4.3 INSTRUMENTATION l 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION i

LIMITING CONDITION FOR OPERATION 3.3.1.1 As a minimum, the reactor protecti g_jnge and passes Table 3.3-1 shall be OPERABLE. ith Response imcs a5 5ncan i, sabic 3.2 2.

APPLICABILITY: As shown in Table 3.3-1.

ACTION: As shown in Table 3.3-1.

SURYEILLANCE REQUIREMENTS 4.3.1.1.1 Each reactor protective instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECX, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frecuencies shown in Table 4.3-1.

4.3.1.1.2 The logic for the bypasses shall be demonstrated OPERABLE prior to eacn reactor STARTUP unless performed during t!.a preceding 92 days. The gsg. total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION testing of each channel affected by bypass operation. .3 4.3.1.1 ' The REACTOR TRI? SYSTEM RESPONSE TIME of each reactor trip functickbshall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one channel per function such that all channels are tested at least once every N times 18 months where N is the total numoer of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.

l 1

N & & & & gSjQ$1c, @ f hon \ GJ N W '

't 2,; lie? :L:F : .:;: .  :. 2 1_ a men: men; sc. 2%g'

n D-i, TAhlE3.3-2 R G .

! REACTOR PROTECTIVE INSTRUllENTATION RESPONSE TIMES

. f9!!CIIO![ALyg! RESPONSE TIME

x

l. flanual Reacto rip Not Applicable g

, 2. Power level - liigh < 0.40 seconds *' an < 12.0 seconds "

3. Reactor Coolant flow - 5 0.50 second

4. Pressurizer Pressure - liigh 5 0.90 econds

5. Containment Pressure - liigh < .90 seconds 1> 6. Steam Generator Pressure - Low < 0.90 seconds i.

{ /. Steam Generator Water Level - Low 5 0.90 seconds 11 . Axial Flux Offset 5 0.40 seconds *' and $ 12.0 seconds "

9. a. Thermal Flargin/ Low Pressure < 0.90 seconds *' and 512.0 seconds "

h. Steam Generator Presst Difference - liigh 5 0. seconds Ji 10. loss of 1.oad Not Appli ile N

) 11. Wide Range Log ithmic Neutron Flux Flonitor Not App'icable W

49 x

3/4.3 INSTRUMENTATION y TABLE 3.3-2 (Continued)

TABLE NOTATION Neutron dete rs are exempt from Respons ime testing. Response Time of the neucqen flux signal portio f the channel shall be measured from det A'or output or i t of first electronic component in channel.

Response Time does not c de contribution of RTDs.

! RTD Response Ti only. This y e is equivalent to the time l interval r 1 red for the RTDs out t to achieve 63.2% of its total change 'en subjected to a step chan in RTD temperature.

-m l

I l

l l

l i

.w z.=: : .: .=1 - .c :

.  :. : :- ne=en ;c . yy

l l

3/4.3 INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION i 3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and bypasses shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with t e lu s sh the Trip Setpoint column of Table 3.3-4 and wi .n mcspense Timas as shcwn in APPLICABILITY: As shown in Table 3.3-3.

ACTION:

a. With an ESFAS instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inocerable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.

b. With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

3,.a SURVEILLANCE REQUIREMENTS 7 4.3.2.1.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECX, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies snown in Tacle 4.3-2.

4.3.2.1.2 The logic for the bypasses shall be demonstrated OPERABLE during the at power CHANNEL FUNCTIONAL TEST of channels affected by bypass coeration. The total bypass function shall be demonstrated OPERA 5LE at least once per 18 months during CHANNEL CALIBRATION testing of each channel  !

affected by bypass operation.

4.3.2.1.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS l

function shall be demonstrated to be within the limit at least once per i 23 months. Each test shall incluce at least one channel per function such tna: all channels are tested at leas: once every N times 18 months unere N is the total numcer of recundant cnannels in a specific ESFAS function as )

snewn in the " Total No. of Channels" Column of Table 3.3-3.

AL!E-~ :LIF 3 - ;N: 2. 2 2-;;

Amencmen: nc. 23

3/4.3 INSTRUMENTATION TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATI. SIGNAL AND FUNCTION RESPONSE T ME IN SECONDS

1. Manua

a. SIA Safet Injection (ECCS) Not Applicable

b. CSAS Containme.' Spray Not Applicable

c. CIS Containment Is ation Not Applicable

d. RAS Containment Sump Re irculat'on Not Applicable

e. AFAS Auxiliary Feedwater Ini 'ation Not Applicable

2. Pressurizer Pressure-Low

a. Safety Injection :CCS) $ 30*/30**

3. Containment Pressure-Hich

a. Safety Inje . ion (ECCS) 5 30*/30"

b. Containm t Isolation 5 30

c. Contai ment Fan Coolers 5 35'/I0**

4. Containm.nt Pressure-Hich

a. Ontainment Spray 5 60"/50**W  !

5. Co .ainment Raciation-Hich

. Containment Purge Valves Isolation 5 l

i l

l

A' '/Er ::.:=3 - x I  :<: 2-r  ; e.,=an- , _ . ,;p l l

3/4.3 INSTRUMENTATION i l

l TABLE 3.3-5 (Continued) ,

l ENGINEERED SAFETY FEATURES RESPONSE TIMES ,

INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN 5 CONDS

6. Steam Generator Pressure-Low i

a. .ain Steam Isolation 569

b. Fe water Isolation 80

7. Refuelinc ' ater Tank-low

a. Contain.ent Sump Recirculation 5 80

8. Reactor Trio

a. Feedwater F ow Reduction to 54 5 20

9. Loss of Power

a. 4.16 kv Emergen Bus Unce..olta e

. . . (Loss of Voltage) 5 2.2***

;.m ,

b. 4.16 ky Emergency B s Underv ltage (Degraded Voltage) 5 8.4***

l

10. Steam Generator Level-Lew i

a. Steam Driven AFW Pum 5 180 i

b. Motor Driven AFW amo 5 180

11. Steam Generator AP-) h

a. Auxiliary F edwater Isolation 5 20.0 TABLE NOTATION Diesel gen rator starting anc secuence loa 'ng celays incluced.

Diesel enerator starting ano secuence loacin, delays not inclucec.

Offsi e power availacle. .

1

]

Re conse time measured frcm the inc;cence or Ine u. ervoltage

.ncition to tne diesel generator star: signal.

U) Heacer #ill time not inclucec.

,! i 1

2AL'!E5I 2LIFP3 - 135~ ~. 3/I 3-((

ET.e cman~. ic.kff

1 3/4.3 INSTRUMENTATION

( BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF)

INSTRUMENTATION The OPERABILITY of the protective and ESF instrumentation systems and bypasses ensure that 1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof exceeds its setpoint, 2) the specified coincidence logic is maintained, 3) sufficient redundancy is maintained to pemit a channel to be out of service for testing or maintenance, and 4) sufficient system i

functional capability is available for protective and ESF purposes from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that 'the overall system functional capability is maintained comparable to the ,

original design standards. The periodic surveillance tests perfomed at the minimum frequencies are sufficient to demonstrate this capability.

g The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident ,

analyses. No credit was taken in the analyses for those channels with l response times indicated as not applicable. '

Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) in place, onsite or offsite test measure. ts or 2 i i 'ng_2snigesentaeuarJLxit ertified raspons times. _ m ce Eme amah aRe CD&*ah1FSM Wee 7, ad*Yd&J h) Med*C

~

3/4.3.3 MONITORIN I T MENTATION 3/4.3.3.1 Radiation Monitoring Instrumentation The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual the radiation channels andsetpoint level trip 2) the alam or automatic action is initiated when is exceeded. -

(

CALVERT* CLIFFS - UNIT 1 B 3/4 3-1 Amendment No. 169

1 i

ATTACHMENT (2) t i

UNIT 2 TECIINICAL SPECIFICATION l

l REVISED PAGES 3/43-1 l

3/43-6 3/43-7 i

l 3/4 3-11 P

l 3/4 3-21 l

B 3/4 3-22  !

I B 3/4 3-31 I

l

t i

'3/4.3 INSTRUMENTATION i 3/4.3.1 REACTOR PROTECTIVE INSTRLMENTATION  !

LIMITING CONDITION FOR OPERATION  :

3.3.1.1 As a minimum, the reactor protect e instrumentation _chann ,

h-vpasses of Table 3.3-1 shall be OPERABLE *W'ith acsponse Ifmd c: : . .c=  !

r,m. :,.nn.,

APPLICABILITY: As shown in Table 3.3-1.  !

ACTION: As shown in Table 3.3-1.

SURVEILLANCE REQUIREMENTS f 4.3.1.1.1 Each reactor protective instrumentation channel shall be  ;

caonstrated OPERABLL by the perfomance of the CHANNEL CHECX, CHANNEL l CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at j the frequencies shewn in Table 4.3-1.  !

l  !

4.3.1.1.2 The logic for the bypasses shall be demonstrated OPERABLE prior to each reactor STARTUP unless perfomed during the preceding 92 days. The i total bypass function shall be demonstrated OPERABLE at least once per IB  !

months during CHANNEL CALIBRATION testing of each channel affected by i bypass operation.  !

D  !

4.3.1.1 ' The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip  !

functiokhall be demonstrated to be within its limit at least once per l lb months. Each test shall include at least one channel per function such that all channels are testec at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.

w

%f,a gefgs me e.renpf -Qent kspae h kc Gg -

1 o

Auta ::.: rI .;s: :  :. : :.  ::3 cram a.

c m/

H n

~~ - ~ . _ _ _ . .

'd TABLE 3.3-2 w

.a '

u q REACTOR PROTECTIVE INSTRtlFIENTATION RESPONSE TIFIES u

? O g f!!!K!!9!LAL U!!!! RESPONSE TIFIE h tot C

1. flanual Reactor Trip Not Applicable c:

h

-4

,] 2. Power level - lii9h 5 0.40 seconds *' d 5 12.0 seconds " $

il . Reactor Coolant flow - 1.uw $ 0.50 s onds

4. Pressurizer Pressure - liigh < . O seconds

5. Containment Pressure - liigh < 0.90 seconds

6. Steain Generator Pressure - Low _

.90 seconds

, 7. Steam Generator llater Level - Low $ 0.90 conds

8. Axial Flux Of fset 5 0.40 secon and 512.0 seconds "

9. a. Thennal flargin/ Low 1 essure 5 0.90 seconds *' an < 12.0 seconds "

b. Steam Generato Pressure Di fference - liigh 5 0.90 seconds

1. 10. l.oss of load Not Applicable N

'l 11. Illile Rary e l.09arithmic Neutron Flux tionitor Not Applicable 3

ai s

M

3/4.3 INSTRUMENTATION '

TABLE 3.3-2 (Continued)

TABLE NOTATION Neutron detect are exempt from Response Tim esting. Response Time of the neutr flux signal portion of ' e channel shall be measured from detecto output or input ~ first electronic component in channel. ,

Response Time does not include ontribution of RTDs.

RTD Response Time only. iis value equivalent to the time interval required for .e RTDs output achieve 63.2% of its total change when subject to a step change in D temperature.

, s t

l l

n

.:L!:s* :_:FF3 .N:' :  : er.c en- ic,gjp l

5

. i 3/4.3 -INSTRUMENTATION

~

3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPEMTION i

f 3.3.2.1 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and bypasses shown in Table 3.3-3 shall be ,

OPERABLE with their trip setpoints set c nsi t nt with the values h in he T n Set oint column of Table 3.3-4. and 9th _sponse mes as snc,n :n--

TeMe 3.3 _.

! APPLICABILITY: As shown in Table 3.3-3.

ACTION

6

a. With an ESFAS instrumentation channel trip setpoint less i 1

conservative than the value shown in the Allowable Yalues column  :

1 of Table 3.3-4, declare the channel inoperable and apply the j 1 applicable ACTION requirement of Table 3.3-3 until the channel is j restored to OPERABLE status with the trip setpoint adjusted ,

consistent with the Trip Setpoint value.

j i i b. With an ESFAS instrumentation channel inoperable, take the ACTION  !

shown in Table 3.3-3. l

)

i

A

j SURVEILLANCE REQUIREMENTS l

4.3.2.1.I Each ESFAS instrumentation channel shall be demonstrated j OPERABLE by the perfomance of the CHANNEL CHECX, CHANNEL CALIBRATION and l CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies  :

shcwn in Table 4.3-2.  !

4.3.2.1.2 The logic for the bypasses shall be demonstrated OPERABLE during the at pcwer CHANNEL FUNCTIONAL TEST of channels affected by bypass  ;

oceraticn. The total bypass function shall be demonstrated OPERABLE at I

least once pa- 18 months during CHANNEL CALIBRATION testing of each channel j affected cy Oypass operation.  !

l 4.3.2.I.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function snall be demonstrated to be within the l'mit at least once per 18 months. Each test shall incluce at least one channel per function such 1

I tnat all channels are tested at least once every N times 18 months where N is the total numcer of recundant enannels in a specific ESFAS function as shcwn in the " Total No. of Channels" Column of Tacle 3.3-3.

i 2

l l

CALVE .T

L:FFI '2C I I/2 2 ~_ imer.cmer.: 1c - U/-

l.

e - - e--. m gi.i -m .c.w. gt

(3/4.3 INSTRUMENTATION 1

TABLE 3.3-5  :

ENGINEERED SAFETY FEATURES RESPONSE TIMES l

l INITIATIN SIGNAL AND FUNCTION RESPONSE IME IN SECONDS l i

I. Manual  !

a. SIAS J Safet Injection (ECCS) Not Applicable

b. CSAS Containmen Spray Not Applicable i

c. CIS Containment Is ation ntt Applicable

d. RAS Containment Sump R ircu tion Not Applicable  ;

e. AFAS  !

Auxiliary. Feedwater i iation Not Applicable i

. 2. Pressurizer Pressure-Lc a

a. Safety Injectio (ECCS) 5 30*/30**  !

3. Coniainment Pressu e-Hich  ;

a. Safety In' tion (ECCS) $ 30*/30**

l b. Contain ent Isolation 5 30 i i c. Cont nment Fan Coolers 5 35*/10** -

i j 4. Contain..ent Pressure-Hich l f a. ontainment Spray 5 60 60** W l 5

j 5. Co tainment Radiation-Hich '

1 j . Containment Purge Valves Isolation 57

^

l i \

j CALVERT CLIFFS - UNIT 2 3/4 3-21 AmencmentNo./g*

L- .- -

3/4.3 INSTRUMENTATION TABLE 3.3-5 (Continued)

ENGINEERED SAFETY FEATURES RESPONSE TIMES l

l INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS i

6. St m Generator Pressure-Low ,

\ i

a. Main Steam Isolation .9  ;

b. Fe\

e water Isolation -5 _80  ;

7. Refueline ater Tank-Low

a. Contain. ent Sump Recirculation i 5 80

8. Reactor Trio  ;

a. Feedwater F1 'w Reduction to 5% 5 20 I

9. Ioss of Power  !

a. 4.16 kv Emergenc Bus Un ervoltage  ;

(Loss of Voltage) 5 2.2***  !

n.

b. 4.16 kv Emergency Undervoltage (Degraded Voltage 5 8. 4,,,

10. Steam Generator Level. Low

a. Steam Driven Pump 5 180  :

b. Motor Driv AFW Pump 5 180 1

l 11. Steam Generat. r AP-Hich

/

a. Auxil'ary Feedwater Isolation -

5 20.0 TABLE NOTATION Diese generator starting and sequence loadi delays included.

Die el generator starting and sequence loading elays not included.

Of site power available.

.esponse time measured from the incidence of the unde voltage condition to the diesel generator start signal.

(1) Header fill time not included. i CALVERT CLIFFS - UNIT 2 3/4 3-22 AmencmentNo.((

i

i 3/4.3 JNSTRUMENTitTION

/ BASES 3/4.3.1 and 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESF) '

INSTRUMENTATION The OPERABILITY of the protective and ESF instrumentation systems and bypasses ensure that 1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof exceeds its setpoint, 2) the specified coincidence logic is maintained, 3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance, and 4) sufficient system functional capability is available for protective and ESF purposes from diverse parameters.

~

The OPERABILITY of these systems is required to provide the overall reliability, redundance and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that-the overall system functional capability is maintained comparable to the  !

original design standards. The periodic surveillance tests perfonred at the minimum frequencies are sufficient to demonstrate this capability.

l lD l

The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses. N' credit was taken in the analyses for those channels with response tine. 'ndicated as not applicable.

I Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) in place, onsite or offsite test measure or ut zin eplacg@gnsors_ with _reyj;h --

times

&sPwe, Vine /; mils Aee coNJa4D 'n)Srt CAN4e 7, pad upd44dM occoedmke l 3/4.3.3 MONITORING INSTRUMENTATION & A toCFA2.7/le.).

i 3/4.3.3.1 Radiation Monitorino Instrumentation The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by-the individual the channels radiation andsetpoint level trip 2) the alarm or automatic action is initiated when is exceeded.

CALVER1 CLIFFS - UNIT 2 B 3/4 3-1 AmendmentNo.[3V