05000483/LER-1991-001, Proposed Tech Specs,Revising Tables 4.3-1 & 4.3-2 to Address Compliance Problem Raised in LER-91-001-00,dtd 910401 Re OT Delta-T & OP Delta-T Channel Calibrs at Beginning of Each Cycle During Startup Testing

Proposed Tech Specs,Revising Tables 4.3-1 & 4.3-2 to Address Compliance Problem Raised in LER-91-001-00,dtd 910401 Re OT Delta-T & OP Delta-T Channel Calibrs at Beginning of Each Cycle During Startup Testing

ML20077M389
Person / Time
Site:	Callaway
Issue date:	08/07/1991
From:	UNION ELECTRIC CO.
To:
Shared Package
ML20077M384	List: 05000483/LER-1991-001, Proposed Tech Specs,Revising Tables 4.3-1 & 4.3-2 to Address Compliance Problem Raised in LER-91-001-00,dtd 910401 Re OT Delta-T & OP Delta-T Channel Calibrs at Beginning of Each Cycle During Startup Testing
References
NUDOCS 9108130325
Download: ML20077M389 (6)

LER-2091-001, Proposed Tech Specs,Revising Tables 4.3-1 & 4.3-2 to Address Compliance Problem Raised in LER-91-001-00,dtd 910401 Re OT Delta-T & OP Delta-T Channel Calibrs at Beginning of Each Cycle During Startup Testing

Event date:
Report date:
4832091001R00 - NRC Website

text

-. . _ - _ _ - - - _

ULNRC- 2456 ATTACHMENT 3 DRAFT TECHNICAL SPECIFICATION MARK-UPS Technical Specification 4.3.1.1, Pages 3/4 3-9 Table 4.3-1 3/4 3-10 3/4 3-12a Technical Specification 4.3.2.1, Pages 3/4 3-36 Table 4.3-2 3/4 3-37 910s130325 910807 PDR ADOCK05000,p3 P

TABLE 4.3-1 r-- REACTORTRIPSYSTEMIN5TRUMENTATIONSURVEILLANCEREQUIREMENTS V TRIP E

" ANALOG ACTUATING MODES FOR DEVICE WillCH

' CHANNEL OPERATIONAL ACTUATION SURVEILLANCE CilANNEL CilANNEL OPERATIONAL E CALIBRATION TEST TEST LOGIC 1EST 15 REQUIRED CilECK Z FUNCTIONAL UNIT R(16) H.A. 1, 2 , 3 * , 4 * , '.

e.

Nanual Reactor Trip N.A. H.A. ', N.A.

1.

2. Power Range, Neutron Flux N.A. N.A. 1, 2 liigh Setpoint 5 D(2, 4), Q(14) a.

M(3, 4),

Q(4,6),

R(4,'5) Ifff, 2 S/U(1) N.A. N.A.

b. Low Setpoint S R(4)

Q(14) H.A. H.A. 1, 2 t' 3.. Power Range, Neutron flux, N.A. R(4)

• liigh Positive Rate w

4. Deleted N.A. N. A. Iff#, 2 Intermediate Range, S R(4, 5) S/U(1) 5.

g Neutron Flux N.A. 2ff, 3, 4, 5

<v R(4,5,12) S/U(1),Q(9,14) N.A.

y 6. Source Range, Neutron flux 5 N.A. 1, 2

+ 7. Overtemperature AT S R(/d

^

Q(14) N.A. l N.A. N.A. 1, 2 P

2

8. Overpower AT S R (/D Q(14)

A

~ N.A. H.A. I S R Q(14)

9. Pressurizer Pressure-Low N.A. N.A. 1, 2

~

Pressurizer Pressure-fligh 5 R Q(14) 10.

H.A. H.A. I Pressurizer Vater Level-fligh 5 R Q(14) 11.

I N. A. N.A.

5 R Q(14)

12. Reactor Coolant flow-Low

y w;,g;.

. 7 3 .-

y, .

{._

v g ^.7.;

~'

v y ,-[

TABLE 4.3-1 (Continued) J [

g. REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS-F E' g TRIP, ,

t 3 ANALOG ACTUATING: MODES'

., ,c CHANNEL ~ DEVICE FOR WilCH -

' ~

c CHANNEL" CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE' E FUNCTIONAL UNIT CilECK CALIBRATION- : TEST- TEST LOGIC TEST IS REQUIRED L

-4

. .t

! 13. Steam Generator Water .

Level Low-Low i a. Steam Generator-Water .5: R Q (14,15) N.A. N.A. 1, 2 i

Leve) Low-Low.(Adverse-Containment Environment) w b. ater S R Q (14,15) N.A. N.A. 1, 2 :

} Steam Generator W(Nomal Level Low-Low i Containment Environment) .

m. >

U c. Vessel AT (Power-1 . S R O f) Q (14,15) N.A. N.A. 1, 2 Power-2) 4 . .t

d. Containment Pressure- S R. Q (14,15) N.A. N. A. - 1, 2 l Environmental. Allowance '

Modifier.

k

14. Undervoltage - Reactor Coolant Pumps -

N.A. R N.A. Q (14,15) N.A. .1 k 15. Underfrequency " Reactor N.A. R N.A. Q (14) .N.A. 1 2 Coolant Pumps t 0

~ 16. Turbine Trip -

a. Low Fluid Oil Pressur'e N.A. R N.A. S/U (1,10) N.A. 1 i

b. Turbine Stop Valve EN.A. R .N.A. S/U (1,10)' N.A. ~1 Closure .

l. ,

5 i j r

.t

- ,,1 . .;, ,

TABLE 4.3-1 (Continued)

TABLE NOTATIONS (10) Setpoint verification is not required.

(11) Following maintenance or adjustment of the Reactor trip breakers, the TRIP ACTUATING DEVICE OPERATIONAL TEST shall include indeper. dent verifi-cation of the Undervoltage and Shunt trips.

(12)' At least once per 18 months during shutdown, verify that on a simulated Boron Dilution Doubling test signal the normal CVCS discharge valves will close and the centrifugal charging pumps suction valves from the RWST will open within 30 seconds. -

(13) Deleted I (14) Each channel shall be tested at least every 92 days on a STAGGERED TEST BASIS.

(15) The surveillance frequency and/or H0 DES specified for these channels in Table 4.3-2 are more restrictive and, therefore, applicable.

(16) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the Undervoltage and Shunt Trip circuits for the Manual Reactor Trip function. The test shall also verify the OPERABItlTY of the Bypass Breaker trip circuit.

(17) Local manual shunt trip prior to placing breaker in service.

(18) Automatic Undervoltage Trip.

(tq) TAe fr w irfm r of f eci$fc f N m 4.d.+ arc ned afflIuU*

foc en+y inh /HobE r 2 so- .

CALLAWAY - UNIT 1 3/4 3-12a Amendment No.19, fA./3# , 57 1

I v

v v TABLE 4.3-2 (Continued)

E ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS g TRIP G ANALOG ACTUATING MODES

_, CilANNEL DEVICE MASTER SLAVE FOR WillCll CllANNEL Cil/NNEL OPERATIONAL OPERATIONAL ACTUATION RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CllECK CALIBRATION TEST TEST LOGIC TEST TEST TEST IS REQUIRED

6. Auxiliary feedwater (Continued)

c. Automatic Actuation Logic and Actuation Relays (BOP ESFAS) N.A. N.A. N.A. N.A. M(1)(2) N.A. N.A. 1, 2, 3

$ d. Steam Generator Water m Level Low-Low a

m I

1) Steam Generator Water Level Low-Low

( Adverse Containment Environment) S R H N.A. N.A. N.A. N.A. 1, 2, 3

2) Steam Generator Water Level Low-Low (Normal Containment

,I Environment) S R H N.A. N.A. N.A. N.A. 1, 2, 3 a

Ei

3) Vessel AT

$ (Power-1, Power-2) S R (4) H H.A. N.A. N.A. N.A. I,2,3

== A P 4) Containment Pressure - i

=

Environmental Allowance Modifier S R H N.A. N.A. N.A. . N.A. 1,2,3

e. Safety Injection See item 1 above for all Safety Injection Surveillance Requirements.

. & .g : U ' ,.

^

TABLE 4.3-2 (Continued)L

.g .

ENGINEERED SAFETY FEATURES ACTUAll0N SYSTEM INSTRUMENfATION C ~

SURVEILLANCE REQUIRthENTS E .

-< ~ l LIRIP-

~

,, ANALOG .AC10ATING . N00ES ji CHANNEL' DEVICE- MASTElt ' SLAVE FOR WflCH

'j CilANNEL -CllANNEL OPERATIONAL. OPERATIONAL . ACTUATION . RELAY RELAY SURVEILLANCE p fUNCIIO!!AL UNIT CllECK CAtlHRATION 1EST TEST LOGIC TEST- TEST' TEST 15 REQUIRED

9. Control l loom isolation

a. Manual In{Llation N.A. H.A. N.A. A N.A. N.A. N.A. All ' L

b. Automatic' Actuation N.A. N.A. N.A. N.A. N(1) N(1) Q(3) 1, 2, 3, 4 togic and Actuation Relays (55PS)

c. Automatic Actuation log lc and Actuallon Q

• Relays (80P ESFAS) N.A. H.A. N.A. N.A. M(1)(2) N.A. N.A. All

- Y j ti d. Phase "A" Isolation See Itesi 3,s. above.for all Phase "A" Isolation Surveillance Requirements.

10. Solid-State toad Serguencer N.A. N.A. N.A. N.A. N(1)(2) N.A. M.A. 1, 2, 3, 4

11. Engineered Safety features Actuation System Interlocks

a. Pressurizer Pressure, N.A. R' H N.A. N.A. M.A. M.A. 1, t. 3-P-11 g b. Neactor 1 rip, P-4 .N.A. H.A. H.A. A M.A. N.A. N.A. 1, 2, 3 S

TABLE NOTATIONS S (1) 't'ach train shall be tested at least every 62 days on a STAGGERED TEST BASIS. *^*

= (2) Continuity check may be excluded from the ACTUATION LOGIC IEST.

f (3) Except Relays f 602, K620 K622 K624 k630. K740, and K741, which shall be tested at least once per 18 months ca ' during refuellig and during each COLD SilUIDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless they.have been tested within the previous 90 days.,

4 lhe. spec l fled 18 monti frequency's.ay be waived for Cycle I provided the surveillance is performed prior to restart following the first refueling outage or June 1, .1986, whichever occurs first. The provisions of Specification 4.0.2 are reset Iros erformance of this surveillance.

(+) 76 previstent sf SpeerNc= % 4.6.5 are sapp /:cdle En enby nh i Moscr 3,2,s, f.

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