ML20205G448

Forwards Corrected Proof & Review Tech Specs,Including Mods to Changes Per 850507 Request Re Ice Condenser Door Spec

ML20205G448
Person / Time
Site:	Catawba
Issue date:	11/07/1985
From:	Tucker H DUKE POWER CO.
To:	Adensam E, Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8511130249
Download: ML20205G448 (13)

Text

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i .e D ~ ~q Duxe PowEn GOMPANY P.O. BOX 33189 CHARLOTTE, N.C. 20242 MAL B. TUCKER m, E=EO November 7, 1985 M ***

Mr.-Harold R. Denton, Director Office.of Nuclear Reactor Regylation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 Proof and Review Technical Specifications

Dear Mr.-Denton:

This letter is in response to your October 10, 1985 letter which transmitted the Proof and Review Technical Specifications for Catawba Units 1 and 2 and supplements my letter of October 30, 1985.

Attached are corrections to errors found by our ongoing review. Also enclosed are modifications to the changes requested in my May 7, 1985 letter concerning the ice' condenser door specification. These changes are necessary in order to clarify the intent of the change request. The intent was that the doors would be incap.atte of opening automatically only when they are blocked closed by some mec:;nical obstruction, not by ice, frost or some slight increase in door opening torque.

If you have any questions regarding this response please contact Mr. Roger W.

Quellette at (704)373-7530.

Very truly yours, S.

k Hal B. Tucker RWO:slb Attachment ec: Dr. J. Nelson Grace,_ Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 NRC Resident Inspector Catawba Nuclear Station \

k hIIj B51107 O

P 3' J

~ ~^ ~~

CONTAINMENT SYSTEMS-

. 1,'. ' ICE CONDENSER 000RS

~

l l

• ' LIMITING CONDITION FOR OPERATION 1

3:6.5.3 The ice condenser inlet doors, intermediate deck doors, and top deck

-doors shall be closed and OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

b ddP * * *P"% axbMy) 4 With one or more ice condenser doors open or otherwise ino -

i monitored at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the maximum ice bed temperature is 1 maintained less than or equal to 27"F; otherwise, restore the doors to their F closed positions or OPERABLE status (as applicable) within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least 30 following HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN hours,

h. (A)k one. or more ic.* d #

condenser clooc5 inof8f*N" (0

' -operun3 aubendcMy MShre aM doors M NE 1.hoge or b,. m flo r STA28f wikin lo bou.rs and 6 NOT Mod 9%,s % .fo\\own b heu.cs and in Coa M M " En b *?*U"]

SURVEILLANCE REQUIREMENTS "

• 4.6.5.3.1_ Inlet Doors - Ice condenser inlet doors shall be:

a.

Continuously monitored and determined closed by the Inlet Door Position Monitoring System, and b.

Demonstrated OPERABLE during shutdown at least once per 3 months during the first year after the ice bed is initially f My loaded and at least once per 6 months thereafter by:

AO

1) Verifying that the torque required to ini 11y op each door is less than or equal to 675 inch pound , ,

g Me. .f e p oa3 a d M O k is

2) Verifying that :p- ' .7, d each door is, fot paired by ice, frost,me debrig;c o a%c As%-hon .

3) Testing a sample of at least 25% of the doors and verifying that the torque required to open each door is less than 195 inch pounds when the door is 40 degrees open. This torque is defined as the " door opening torque" and is equal to the nominal door torque plus a frictional torque component. The doors selected for determination of the " door opening torque" shall be selected during to ensure four test that all doors are tested at least once intervals; a-CATAWBA - UNIT 1 3/4 6-36

'. n -

CONTAINMENT SYSTEMS --

l BASES y

3/4.6.5 ICE CONDENSER

~

The requirements associated with each of the components of the ice con-i

- denser ensure that the overa11' system will be available to provide sufficient p pressure suppression capability to limit the containment peak pressure tran-sient to.less than 14.7 psig during LOCA conditions.

3/4.6.5.1 ICE BED will: The OPERABILITY of the ice bed ensures that the required ice inventory (1) be distributed evenly through the containment bays (2) contain sufficient boron to preclude dilution of the containment sump following the

.LOCA, and (3) contain sufficient heat removal capability to condense the Reactor Coolant System volume released during a LOCA.

i with the assumptions used in the safety analyses.These conditions are consistent

+

The minimum weight figure of 1218 pounds of ice per basket contains a 10%

conservative allowance for ice loss through sublimation which is a factor of-10 higher than assumed for the ice condenser design. The minimum total weight of 2,368,652 pounds of ice also contains an additional 1% conservative allowance to account for' systematic error in the weighing instruments. In the event that

. observed subitmation rates are equal to or lower than design predictions after 2~

3 years of operation, the minimum ice baskets weight may be adjusted downward.

In addition, the number of ice baskets required to be weighed each 9 months may be reduced after.3 years of operation if such a reduction is supported by observed sublimation data.

3/4.6.5.2 ICE BED TEMPERATURE MONITORING SYSTEM The OPERABILITY of the Ice Bed Temperature Monitoring System ensures that the capability is available for monitoring the ice temperature. In the event the system is inoperable, the ACTION requirements provide assurance that the ice bed heat removal capacity will be retained within the specified time limits.

'_3/4. 6. 5. 3 ICE CONDENSER DOORS b The OPERASILITY of the ice condenser doors and the requirement that they t

y be maintained closed ensures that the Reactor Coolant System fluid released d during a LOCA will be diverted through the ice condenser bays for heat removal

.b and that excessive sublimation of the ice bed will not occur because of warm r intrusion.

3/4.6.5.4 INLET 000R POSITION MONITORING SYSTEM .

The OPERABILITY of the Inlet Door Position Monitoring System ensures that 1

the capability is available for monitoring the individual inlet door position.

' In the event the system is inoperable, the ACTION requirements provide assur-ance that the ice bed heat removal capacity will be retained within the spec-fied time limits.

CATAWBA - UNIT 1 B 3/4 6-5 L

3/4.6.5.' ICE 3 00NDENSER DOORS If an Ice Condenser Door is not capable of opening autmatically then systen function is seriously degraded and iwi=te action nust be taken to restore the opening capability of the door. Not capable of opening aut matically is defined as those conditions in which a door is physically blocked fre opening by installation of a blocking device or by obstruction frm tenporary or pemanent installed agii ==nt .

. \qairmek Ng LCA, hcSh et e riS k censf&

de ced<r 4e. doors 6opede lu+ capak of oreasoS uMd-Ky sin ee. -Me.re lypes <

cond-ns wiH resat+ c f a a clish $

y.A + m_g .% &m.

l 4

g , TABLE 2.2-1 (Continued)

] REACTOR T' RIP SYSTEM INSTRt31ENTATION TRIP SETPOINTS ,

TOTAL SENS0R ALLOWANCE ERROR I ] FUNCTIONAL UNIT (TA) Z (S) TRIP SETP0 INT ALLOWABLE VALUE d 13._ Steam Generator Water p -

4 m ., a. Unit 1 17 14.2 1.5 >17% of span >15.3% of span from 2

8' Level Low-Low from GK to 305 DE to 305 RTP*

l m ,. ) RTP" increasing increasing linearly

% ~ _ ._ _ _- linearly to to >53.2% of span

> 54.9% of span from 305 to 1005 RTP*

Trom 30% to 100K i RTP*

4 l b. Unit 2 17 14.2 1. 5 >17% of narrow >15.3X of narrow y range span range span m

14. Undervoltage - Reactor 8.57 0 1.0 >77% of bus ->76% (5016 vol,ts)

Coolant Pumps voltage (5082 volts) with a .

, 0.7s response time

15. Underfrequency - Reactor 4.0 0 1.0 >56.4 Nz with a >55.9 Hz

~

Coolant Pumps 5.2s response time i

16. Turbjoe Trip--

'a k. h jowontrol-Valve'E N.A. N.A. N.A. 1550 psig 1500 psig

,/ Pressur(Low (p;f 1 i /' b. Turbine Stop Valve Closure N.A. ' N.A. N.A. 11% open 11% open h

/ * '

' o , 17. Safety Injection Input I N.A. N.A. N.A. N.A. N.A.

j S from ESF

'\ '

• RT.P = RATED THERMAL,- POWEJt N

- e~

j j Tre.ssure Lov (.uo4 23

's __

TABLE 3.3-1 (Continued) 9 g REACTOR TRIP SYSTEM INSTRUMENTATION

' MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE.

! E FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE M00ES ACTION

! M w

10. Pressurizer Pressure-High 4 2 3 1, 2 6#

i .

g 11. Pressurizer Water Level-High 3 2 2 1 7#

12. Reactor Coolant Flow-Low

a. Single Loop (Above P-8) 3/ loop 2/ loop in 2/ loop in 1 7#

any oper- each oper-i ating loop ating loop

) b. Two Loops (Above P-7 and 3/ loop 2/ loop in 2/ loop 1 7#

below P-8) two oper- each oper-  ;

l 1:'

+ ating loops ating loop

, 't* 13. Steam Generator Water 4/sta 2/sta gen 3/sta gen 1, 2 6# $

1 Level--Low-low gen in any each O o

operating operating M sta gen -

sta gen 9'

o

14. Undervoltage-Reactor Coolant j Pumps (Above P-7) 4-1/ bus 2 3 1 6# $

g

15. Underfrequency-Reactor Coolant 4-1/ bus 2 Pumps (Above P-7) 71 3 1 6# Qo

' 16. Turbi e rip

a. Control Valve EH Pres ure ( 2 3 1#### 7#

I

b. urbine Stop Valve C1dsure V ._. 4 ~ )' 4 1 1#### 11#

17. Safety Injection Input D 1

a g

@ from ESF

- ~ 2 1 2 1, 2 9

• E

,E:an i

% (' LOQ

• Y w

f -

s he MA k he re/

d 2.h ,,~'

I

l TA8LE 3.3-2 (Continued)

' 9 5;! -

REACTOR TRIP SYSTEN INSTRtMENTATION RESPONSE TIES '

i 5 FUNCTIONAL UNIT RESPONSE TINE i E '

i Q

12. Low Reactor coolant Flow i a. Single Loop (Above P-8) < 1 second R

o

b. Two Loops (Above P-7 and below P-8) 7 1 second

' N

13. Steam Generator Water Level-Low-Low < 2.0 seconds

14. Undervoltage-Reactor Coolant Pumps 5 1.5 seconds .

i

! 15. Underfrequency-Reactor Coolant Pump b 5 0.6 second h o

16. Turbine Trip -

a. h Control Valve EN Pre s tini  ; N.A. -

ine Stop Valve Closu e j

6,' b.

" N.A.

s

17. Safety Injection Input from ESF N.A. '

18. Reactor Trip System Interlocks N.A.

8o

19. Reactor Trip Breakers N.A.

20. Automatic Trip and Interlock Logi N.A. g r M

/LoQ 2nm ja u I w .y %\ve C.A Pussa e b )-

- r- m -_

e i 3 cm gg w w .

I

l 1.

4

~

9 TABLE 4.3-1 (Continued) f

W REACTOR TRIP SYSTEN INSTRLMENTATION SURVEILLANCE REQUIREENTS

• f '

4 TRIP

' ANALOG ACTUATING N00ES FOR E CNANNEL DEVICE Q WICN CNANNEL C::A*,"!EL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE i FUNCTIONAL UNIT CNECK

[ CALIBRATIGM TEST TEST LOGIC TEST IS REQUIRED 4

g 13. Steam Generator Water Level- S R M N.A. M.A. 1, 2 Low-Low l 14. Undervoltage - Reactor Coolant N.A. R N.A. M N.A. 1 l Pumps .

j N.A.

15. Underfrequency - Reactor) R N.A. M N.A. 1 j Coolant Pumps -

Lc0 t' 16. TurbinesTrip  ?

i

• a. h t ntro 9 alv 3 i  !

Y esser 4 p t N.A. R N.A. S/U(1,10) N.A. 1#

b. Turbine Stop Valve N.A. R N. A. S/U(1,10) N.A. 1#

Closure g

17. Safety Injection Input from N.A. N.A.

ESF N.A. R N.A. 1, 2 g cs

18. Reactor Trip System Interlocks o

7

a. Intermediate Range

, Neutron Flux, P-6 N.A. R(4) M N.A. N.A. 2##

t

b. Low Power Reactor i

Trips Block, P-7 N.A. R(4) M(8) N.A. N.4 c 1 ,

i c. Power Range Neutron a Flux, P-8 N.A. R(4) N(8) N.A. N.A. 1 Q d. Low Power Range Neutron Flux, P-9 ^ . N.A. R(4) N(8) N.A. N.A. I

! w ,

N f g M h hWE. O }

x ressor '(.ttn44 .

- ~ - -

0 l

i

• TABLE 3.3-3 (Continued) f l

W ~

i ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION .

s e

MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE

} FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

[ 8. Auxiliary Feedwater (Continued)

> g. Auxiliary Feedwater {

) $ Suction Pressure-Low  !

^

1)_, CAPS 5220, 5221, N / pump 2/ pump 2/ pump 5222 1, 2, 3 15

2) _ CAPS 5230, 5231,  !

5232, )(3/ pump 2/ pump 2/ pump 1,2,3 15 t

9. Containment Sump Recirculation  !

R

• a. Automatic Actuation 2 1 2 1,2,3,4 14 Logic and Actuation Y Relays M

b. Refueling Water Storage o

Tank Level-Low 4

. o  ! ~

2 3 1,2,3,4 16 Coincident With [.

Safety Injection :o See Item 1. above for all Safety Infection initiating functions and y requirements.

10. Loss of Power ,

a. es 4 kV Bus Undervoltage- 3/ Bus 2/ Bus 2/ Bus 1, 2, 3, 4 15* D Loss of Voltage n

, M

b. 4 kV Bus Undervoltage- *

. Grid Degraded Voltage 3/ Bus 2/ Bus 2/ Bus I, 2, 3, 4 25*c . ,

11. Control Room Area  !

o Ventilation Operation

a. Automatic Actuation Logic N  !

and Actuation Relays 2 1 2 All 24 i i

i f

L - ______- ________ _ -. __ _ --

1 i

l TABLE 3.3-11 (Continued) h FIRE DETECTION INSTRt# TENTS

! l FIRE MINIMUM INSTRt90ENTS OPERA 8LE*

j ZONE DESCRIPTION LOCATION SMDKE FLAME HEAT FUNCTION **

1 l "

180 Filter 8ed Unit 28 Reactor 81dg.8el. E1.565 + 3 2 0 2 A l 181a Annulus E1.561 + 0 0 0 1 A i g 181b Annulus E1.583 + 0 0 0 1 A l 181c Annulus E1.604 + 0 0 0 1 A

181d Annulus

• E1.629 + 5 0 0 1 A i 181e Annulus E1.649 + 5 0 0 1 A

181f Annulus E1.664 + 0 0 0 1 A

! 182a Annulus E1.561 + 0 0 0 1 A 182b Annulus E1.583 + 0 0 0 1 A i 182c Annulus ~l. VJ+6 E1.604 + 0 0 0 1 A E1.629 + 5

! w 182d Annulus 0 0 1 A

! > 182e Annulus .[L(beb hdZ 3 1.649 + 5 4 0 o 6 A

! w f Annu M-b 1.664 + 0 g l (13 A i .

Aisle es -7 .522 + 0 i 3 Aux. Batt. Room AA-55 E1.554 + 0 4 0 4 A  !

214 Aux. Cont. Pwr. Batt. AA-59 E1.560 + 0 4 0 4 A 4

215 D/G Corridor 88-45 E1.556 + 0 3 0 3 A i

O 216 D/G Corridor AA-45 E1.556 + 0 2 0 2 A

] 217 D/G Corridor (Unit 2) CC-71 E1.560 + 0 3 0 3' A '

218 D/G Corridor (Unit 2) 88-71 E1.560 + 0 2 0 2 A on

. 219 Mech. Pene. Room -

HH-52 E1.577 + 0 6 0 6 A l 220 Mech. Pene. Room JJ-62 E1.577 + 0 6 0 6 A no

! 222 Airlock Access JJ-51 E1.605 + 10 1 0 1 A :o i 224 Airlock Access (Unit 2)

JJ-63 E1.605 + 10 1 0 1 4 Q i 225 RN Pump Structure West Section E1.600 + 0 8 0 8 A Mi 226 RN Pump Structure East Section E1.600 + 0 8 0 8 A E -

p o ~'

o 231 Reactor 81dg. (UniL1) 260*-303* E1.668 + 10 10 0 0 A i "e

-- 232 Reactor 81dg. (Unit 2) 260*-303* 8el. E1.668 + 10 10 0 ,

O 0

A  %

I 184 HVAC Duct for Rooms 331 and 332 FF-53 E1.j43 + 0 1(Duct) 0 A l w HVAC Duct for Rooms 203, 205 20-60 E1.543 + 0 0 0 185 1(Duct) A [

g sn 205A, 206A, 2068, 207 and 209A . ,

i l I

CONTAlNNENT SYSTEMS PRoopggy, $i

• SURVEILLANCE REQUIREMENTS (Continued) 4.6.1.9.3 At least once per 6 months on a STAGGERED TEST BASIS, the inboard and outboard valves with resilient material in each sealed closed containment purge supply and exhaust penetration for the lower compartment and the upper compartment, or instrument room, or Hydrogen ^ Purge System shall be demonstrated OPERA 8LEtoby pressurized P,.verifying that the measured leakage rate is less than 0.05 L, when

/

_4 N E 4 At least once per 3 months the Containment Air Release and Addition

{thatthejmeasuredleakagerateislessthan0.01L,Syst.enAwi when pressurized to P,.

h res VAlVCS

. ~

CATAWBA - UNITS 2 AND 2 3/4 6-17 JUL 181985 OCT 7 1985 0

TABLE 3.8-la (Continued) REVIEW COPY UNIT 1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVIC DEVICE NUMBER & LOCATION SYSTEM POWERED 2.- 600 VAC MCC (Continued) .

IMXR-F018 Primary Bkr Incore Instrument Roon Ventila-Backup Fuse tion Unit 18 Fan Motor IMXR-F02B Primary Bkr Control Rod Drive Vent Backup Fuse Fan Motor ID IMXR-F03A Primary Bkr Lower Containment Ventilation Backup Fuse Unit ID Fan Motor IMXR-F04C Primary Skr Upper Containment Ventilation Backup Fuse Unit ID Fan Motor IMXY-F02A Primary Bkr NC Pump 1A 011 Lift Pump Motor 1 Backup Fuse 7 -c .1MXY-F028 ~ - - N

"' '" '" """ p ^

BIekup Fuse P"*"~'

- o(hb Fu.x -

IMXY-F03A

' Primary Bkr Que. h@u.te d.KCPLO WS Reactor Coolant Drain Tank Pump Backup Fuse n5to n

~

IMXY-F030 Primary Bkr Ice Condenser Refrigeration 4

Backup Fuse Floor Cool Pump Motor IA IMXY-F05A Primary Bkr Lighting Transformer Backup Fuse ILR8 IMXY-F058 Primary Bkr Lighting Transformer-Backup Fuse ILR11 .

9 CATAWBA - UNITS 1 AND 2 3/4 8-35

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

- . - - ~ ~

PROOF & REVIEW COPY f

INSTRUMENTATION BASES REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)

The Engineered following functions: Safety Features Actuation System interlocks perform the .

P-4 Reacter tripped - Actuates Turbine trip, closes main feedwater valves on T,,, below Setpoint, prevents the opening of the main feedwater valves which were closed by a Safety Injection or High Steam Generator Water Level signal, allows safety injection block so that components can be reset or tripped.

Reactor not tripped prevents manual block of Safety Injection.

1 P-11 Defeats the manual block of Safety Injection actuation on low pres-

• surizer pressure and low steam ifne pressure and defeats steam line isolation on negative steam line pressure rate. Defeats the manual block of the motor-driven auxiliary feedwater pumps on trip of main f tar pumps and low-low steam generator water level, i

4 Je t P-12 0 asing reactor coolant loop temperature, P-12 automatically blocks steam dump and allows , ~ i sbypass of steam dump block for

' the cooldown valves only. n reasing reactor coolant loop temper-ature, P-12 automatically efe t manual bypass of the steam dump block. -

[ P-14 On increasing steam generator level, P-14 automatica~11y trips all feedwater isolation valves, pumps and turbine and inhibits feedwater control valve modulation.

3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING FOR PLANT OPERATIONS 4

The OPERABILITY of the radiation monitoring instrumentation for plant operations ensures that:

(1) the associated action will be initiated when the i radiation level monitored by each channel or combination thereof reaches its

• i Setpoint. (2) the specified coincidence logic is maintained, and (3) suffi-

! cient redundancy is maintained to permit a channel to be out-of-service for testing or maintenance. The radiation monitors for plant operations senses radiation levels in selected plant systems and locations and determines whether or not predetermined limits are being exceeded. If they are, the signals are combined into logic matrices sensitive to combinations indicative of various i i

accidents and abnormal conditions. Once the required logic combination is i J

completed, the system sends actuation signals to inftfate alarms or automatic i isolation action and actuation of Emergency Exhaust or Ventilation Systems, t

i

' ' CATAWBA - UNITS 1 AND 2 8 3/4 3-3 jyt.18 0 01 7#

t

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