ML20138A664

Proposed Tech Specs,Correcting Typos & Clarifying Statements Re Ventilation Exhaust Treatment Sys,Reactor Trip Sys Instrumentation Setpoints,Movable Control Assemblies, Operational Leakage & Chemical Treatment Ponds

ML20138A664
Person / Time
Site:	Catawba
Issue date:	03/07/1986
From:	DUKE POWER CO.
To:
Shared Package
ML20138A662	List: ML20138A657 ML20138A664
References
NUDOCS 8603140450
Download: ML20138A664 (21)

Text

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I DEFINITIONS t

{ SOURCE CHECK i

1.33 A SOURCE CHECK shall be the qualitative assessment of channel response i

when the channel sensor is exposed to a source of increased radioactivity.

STAGGERED TEST BASIS 1.34 A STAGGERED TEST BASIS shall consist of:

a.

A test schedule for n systems, subsystems, trains, or other designated ,

components obtained by dividing the specified test interval into n equal subintervals, and ,

b. The testing of one system, subsystem, train, or other designated  !

! component at the beginning of each subinterval.

i  ;

j TNERMAL POWER '

i i 1.35 THERMAL reactor coolant. POWER shall be the total reactor core heat transfer rate to the -

TRIP ACTUATING DEVICE OPERATIONAL TEST '

i

! 1.36 l A TRIP ACTUATING DEVICE OPERATIONAL TEST shall consist of operating the i Trip Actuating Device and verifying OPERA 8ILITY of alarm, interlock and/or

{ trip functiuns.  ;

The TRIP ACTUATING DEVICE OPERATIONAL TEST shall include adjustment, as necessary, of the Trip Actuating Device such that it actuates '

4 at the required Setpoint within the required accuracy, i

' UNIDENTIFIED LEAKAGE I l 1.37 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE -

l or CONTROLLED LEAKAGE. '

i

} UNRESTRICTED AREA I

1.38 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area i within the SITE SOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTFM i

i l 1.39 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed M I installed to reduce gaseous radiotodine or radioactive material in form in effluents by passing ventilation or vent exhaust gases the ugh hticulate 3 g en i i

adsorbers and/or HEPA filters for the purpose of removing lodines r particu- l

{ 1stes from the gaseous exhaust stream prior to the release to the e tenneen i

Such a system is not considered to have any effect on noble gas effluents.

Engineered Safety Features (ESF) Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

CATAWBA - UNITS 1 & 2 1-6 j M @ g= -

m -

n TABLE 2.2-1 (Continued) g F ACTOR TRIP SYSTEN INSTRUNENTATION TRIP SETPOINTS E

' )y- .

ITOTAL (ALLOWANCE

[ SENSOR LERROR E FUNCTIONAL UNIT (TA) Z (S) TRIP SETPOINT ALLOWA6LE VALUE d 18. Reactor Trip Sys Interlocks e-m a. Intermediate R N.A. N.A. N.A. 11 x 10 18 amps 16 x 10 11 amps Neutron Flux, P-6

b. Low Power Reactor Trips Block, P-7

1) P-10 input N.A. N.A. M.A. 110% of RTP* $12.2% of RTP*

2) P-13 input N.A. M.A. N.A. <10% RTP* Turbine <12.2% RTP* Turbine Impulse Pressure Impulse Pressure m Equivalent Equivalent E c. Power Range Neutron N.A. N.A. M.A.

Flux, P-8 $48% of RTP* 150.2% of RTP*

d. Power Range Neutron N.A. N.A. N.A.

Flux, P-9 169% of RTP* $70% of RTP*

e. Power Range Neutron M.A. N.A. N.A >10% of RTP*

Flux, P-10 17.8% of RTP*

f. Power Range Neutron M.A. M.A. N.A. $10% of RTP* 112.2% of RTP*

Flux, Not P-10

g. Turbiae Impulse Chamber N.A. N.A. N.A. <10% RTP* Turbine <12.2% RTP* Turbine Pressure, P-13 Impulse Pressure Impulse Pressure Equivalent Equivalent i 19. Reactor Trip Breakers N.A. M.A. N.A N.A. N.A.

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20. Automatic Trip and M.A. M.A. N.A. N.A. N.A.

Interlock Logic

" RIP = RATED IHERMAL POWER ,

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

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!- l l REACTIVITY CONTROL SYSTEMS '

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3/4.1.3 MOVABLE CONTROL ASSEM8 LIES GROUP HEIGHT 1

LIMITING CONDITION FOR OPERATION '

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1 3.1. 3.1 All full-length shutdown and control rods shall be OPERA 8LE and positioned within t12 steps (indicated position) of their group step counter demand position. I APPLICA81LITY: MODES la and 2*.

ACTION:

a. With one or more full-length rods inoperable due to being immovable i as a result of excessive friction or mechanical interference or '

known to be untrippable, determine that the SHUTOOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STAN08Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. I

b. With more than one full-length rod inoperable or misaligned from the , l group step counter demand position by more than *12 steps (indicated position), be in HOT STAN08Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

c. With one full-length rod trippable but inoperable due to causes other than addressed by ACTION a., above, or misaligned from its i group step counter demand height by more than t12 steps (indicated  !

position), POWER OPERATION may continue provided that within 1 hour:

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1. The rod is restored to OPERA 8LE status within the above alignment I requirements, or

2. The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within i 12 steps ,

of the inoperable rod while maintaining the red sequence and insertion limits o e 3.1-1. The THERMAL POWER level shall be restricted p suarpt to ecification 3.1.3.6 during subse-  ;

quent operation or Q '

3. The rod is declare able and the SHUTDOWN MARGIN require- '

ment of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that: ,

{

a) A reevaluation of each accident analysis of Table 3.1-1 is i performed within 5 days; this reevaluation shall confirm  !

that the previously analyzed results of these accidents  !

i remain valid for the duration of operation under these  ;

conditions; i b) The SHUT 00WN MARGIN requirement of $pecification 3.1.1.1 is l determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; "See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

i CATAWBA - UNITS 1 & 2 3/4 1-14 l

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TABLE 3.3-3 (Continued)

I k

> ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRtmENTATION l

6 l

MINIORM c TOTAL NO. CHANNELS CHAISIELS l

5 APPLICABLE FUIICTICIIAL UNIT OF CHANNELS TO TRIP OPERABLE N00ES ACTION O

- 16 iliary M ding Filteres l e. N t Operation m (Continued)

c. Safety Injection See Ites 1. above for all Safety Injection initiating functions and requirements.

17. Diesel Building Ventilation Operation

a. Manual Initiation 2 1 2 1,2,3,4 18

$ b. Automatic Actuation Logic w and Actuation Relays 2 1 2 1,2,3,4 21

$ c. Emergency Diesel Generator Operation See Ites 15. above for all Emergency Diesel Generator Operation initiating functions and requirements.

18. Engineered Safety features l Actuation System Interlocks

a. Pressurizer Pressure, 3 2 . 2 1,2,3 20 P-11

b. Pressurizer Pressure, 3 2 2 1,2,3 20 not P-11

c. Low-Low T,,g, P-12 4 2 3 1,2,3 20

d. Reactor Trip, P-4 2 2 -

2 1,2,3 22 l

e. Steam Generator Water 4/sta. gen. 2/sta. gen. 3/sta. 1, 2, 3 20 Level, P-14 in any gen. in operating each sim. gen. operating sta. gen.

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REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:

a. No PRESSURE BOUNDARY LEAKAGE,

b. 1 gpm UNIDENTIFIED LEAKAGE,

c. 1 gpm total reactor-to-secondary leakage through all steam generators and 500 gallons per day through any one steam generator,

d. 10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System,

e. 40 gpm CONTROLLED LEAKAGE at a Reactor Coolant System pressure of 2235 1 20 psig, and

f. 1 gpm leakage at a Reactor Coolant System pressure of 2235 1 20 psig -

from any Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1.

APPLICABILITY: H0 DES 1, 2, 3, and 4.

ACTION:

a. With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STAN08Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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b. With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE and leakage from Reactor Coolant System Pressure Isolation Valves, reduce the leakage .

rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANOBY  !

withirrtWh 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 h rs X

c. With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by

[6 use of at least two closed manual or deactivated automatic valves, or be in at least HOT STAN08Y 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 SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

j 1, ^

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• Unpr1i048 ith the React,or hours,Toolant SyjOctatfeI23,198,-epeItioninModev itted identifiedJsaksgirate>1gpm

< 5 gpm. l

/ w!f the Mentified leakage rate is not reduced to < 1 the ab inar  ;

the f will be f ac(d in COLD S(yIDOWN within the fo ng 6 hou CATAW8A - UNITS 1 & 2 3/4 4 20 I

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - . _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ^ - - - - - - - - - - ^ - - - - - - - - ' - - ~ ~--~ ~ ^ ^^' ~

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.6.2.1 Reactor Coolant System leakages shall be dem e thin each of the above limits by: 4.je

a. Monitoring the containment atmosphere seous at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; 3 radioactivity nitor

b. Monitoring the containment floor and eq !a=nts nventory and discharge at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />;

c. Measurement of the CONTROLLED LEAKAGE to the reactor coolant pump seals when the Reactor Coolant System pressure is 2235 1 20 psig at least once per 31 days. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4;

d. Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and

e. Monitoring the reactor head flange leakoff at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERA 8LE by verifying leakage to be within its limit:

a. At least once per 18 months,

b. Prior to entering MODE 2 whenever the plant has been in COLD

' SHUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more and if leakage testing has not been performed in the previous 9 months,

c. Prior to returning the valve to service following maintenance, repair or replacement work on the valve, and

d. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valve actuation due to automatic or manual action or flow through the valve.

The provisions of Specification 4.0.4 are not appilcable for entry into MODE 3 o or 4.

CATAWSA - UNITS 1 & 2 3/4 4-21

CONTAINMENT SYSTEMS .

, SURVEILLANCE REQUIREMENTS (Continued) seal 4.6.1.9.3 At least once per 6 months na TAGG E0 TEST 8 ASIS, the inboard and outboard valves with resilient erfal in ach sealed closed containment  !

purge supply and exhaust penetratio for t ower compartment and the upper  !

compartment, or instrument room, or n Purge System shall be demonstrated i i

OPERA 8LE by verifying that the measured leakage rate is less than 0.05 L, when i

pressurized to P,.

4.6.1.9.4 At least once per 3 months the Containment Air Release and Addition  !

System valves with resilient material seals shall be demonstrated OPERA 8LE by i i

verifying that the measured leakage rate is less than 0.01 L, when pressurized  ;

to P,.  !

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F

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CATAWBA - UNITS 1 & 2 3/4 6-17  !

! l r

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l TA8LE 3.6-2a (Continued)

E y UNIT 1 CONTAlffENT ISOLATION VALVES 6

i MAXIfMM

! E VALVE fasGER FUNCTION ISOLATION TIfE (s) l O I

3. Manual

• NC-141 NC Pump Hz Drain Tank Pump Discharge M.A.

NC-142 NC P g Hz Drain Tank Pump Discharge N.A.

NI-3 Boron Injection Tank Line to Cold Legs N.A.

Fw-11 Refueling Water Pump Suctica N.A.

Fw-13 Refueling Water Pimp Suction M.A.

CF-91# Feedwater IA N.A.

CF-93# Fee &sater 18 N.A.

CF-95# Fee &sater IC N.A.

w CF-97# Fee &sater ID N.A.

1 CA-121# Aux. Fee &sater IA N.A.

. 8W-1# Aux. Fee &sater IA N.A.

4 CA-120# Aux. Feedwater 18 N.A.

BW-26# Aux. Fee &sater 18 N.A.

CA-119# Aux. Feedwater IC N.A.

8W-17f Aux. Fee &sater IC N.A.

CA-118# Aux. Fee &sater ID N.A.

8W-10# Aux. Feessater ID N.A.

SM-16# h in Steam 1A N.A.

SM-73#* h in Steam 1A N.A.

SM-105# h in Steam 1A M.A.

SM-121# Main 5 team 1A N.A.

SM-143# h in Steam 1A N.A.

SM-72#* h in Steam 18 N.A.

SM-1948 min Steam 18 N.A.

SM-120# h in Steam 18 N.A.

A 142# h in Steam IB . N.A.

A If in Steam 18 N.A.

17# h in Steam 18 N.A.

SM-18# h in 5 team IC N.A.

SM-71#* h in Steam IC N.A.

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l l TA8tE 3.6-2b (Continued)

! S g UNIT 2 CONTAllSENT ISOLATION VALVES t E l

l

• MAXIPRat l E VALVE InseER FUNCTION ISOLATION TIpE (s)

! O

'a l 3. Manual

• NC-141

" NC Pump Hz Drain Tank Pump Discharge N.A.

l NC-142 NC Pump N Drain Tank Pump Discharge NI-3 N.A.

Boron Injection Tank Line to Cold Legs M.A.

FW-11 Refueling Water Pump Section N.A.

FW-13 Refueling Water Pump Suction M.A.

CF-91# Feedmater 2A M.A.

! CF-93# Feessater 28 I N.A.

CF-95# Feedsater 2C N.A.

. CF-97# Feessater 20 N.A.

1 CA-121# Aux. Feedseter 2A N.A.

. 8W-1# Aux. Feedsater 2A N.A.

O CA-120e Aux. Feedsater 28 N.A.

• 8W-26# Aux. Feeduater 28 N.A.

CA-119e Aux. Feessater 2C N.A.

8W-17# Aux. Feedster 2C N.A.

CA-118e Aux. Feessater 2D N.A.

l 8W-10# Aux. Feedsater 2D N.A.

SM-16# Main Steam 2A N.A.

SM-73#* Main Steam 2A N.A.

SM-105# m in Steam 2A -

M.A.

SM-121# Main Steam 2A N.A.

SM-143# h in Steam 2A N.A.

SM-72#* h in Steam 28 N.A.

SM-104# h in Steam 28 N.A.

SM-120e Main Steam 28 N.A.

I SM-142# Main Steam 28 . N.A.

$1#

SM-17e h in Steam 28 Main Steam 23 N.A.

N.A.

SM-18e Main Steam 2C N.A.

l SM-71F* Main Steam 2C N.A.

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l PLANT $YSTEMS i

3/4.7.7 AUXILIARY BUILDING FILTERED EXHAUST $YSTEM f

t!MITING CONDITION FOR OPERATION 3.7.7 The Auxiliary Building Filtered Exhaust System shall be OPERA 8LE. I APPLICA81LITY: MODES 1, 2, 3, and 4.

. AC7 ION:

With the Aux 111ery Butiding Filtered Exhaust System inoperable, restore the inoperable system to 0PERA8LE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least NOT STAN08Y 30 hours. 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 $NUTD0WN within the following -

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$URVEILLANCE REQUIREMENTS

. i 4.7.7 The Auxillary Building Filtered Exhaust System shall be demonstrated  !

OPERA 8LE:

• carbn

a. At least once per 31 days b A tiatin j

through the NEPA filters d 2:c:::! rom control room, flow

% ebe1s and verifying that the j system operates for at le et 10..rentinuous hours with the heaters operating; .

on (

i b. At least once per la he orf(car 1) after y structural maintenance on the HEPA filter adsorbe r ousings, or (2) following

' painting, fire, or chemicel_re; lease'in any ventilation zone: t :::! ,

communicating with me system by  !

1) Verifying that the cleanup system satisfies the in place penetrat'en and bypass leakage testing acceptance criteria of l 1ess than 15 (Unit 1), 0.055 (Unit 2) and uses the test proce- i i

dure guidance in Regulatory Positions C.S.a. C.S.c. and C.S.d*  !

'* of Regulatory Guide 1.52. Revision 2. March 1978, and the system  !

flow rate is 30,000 cfm 1 105; i

i 2) Verifying, within 31 days after removal, that a laboratory 1 analysis of a representative carben sample obtained in accor-dance with Regulatory Position C.6.b of Regulatory Guide 1.52,  ;

Revision 2, Merch 1978, meets the laboratory testin '

of Regulatory Position C.S.a of Regulatory Guide 1.g 52.criteria Revi- i sten 2 March 1978, for a methyl fodido penetration of less than 158 and j "The requirement for reducing refrigerant concentration to 0.01 ppe may be  !

satisfied by operating the system for 10 heves with heaters on and operating. t CATAWBA - UNITS 1 & 2 3/4 7 17 I i i

PLANT SYSTEMS SURVE!LLANCE REQUIREMENTS (Continued)

3) Verifying a system flow rate of 30,000 cfm + 10% during system i operation when tested n-:;&W...a witAANI! N510-1980.

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c. After every 720 hour0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of ?rn:!,6dsorbar_ darboo within 31 days af ter r ope) ration, by vertfying, a O nit ~a' laboratory analysts of a representative carbon sample obtained in accordance with Regulatory  ;

Posit 1on C.6.b of Regulatory Guide 1.52 Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52. Revision 2 March 1978, for a methyl lodido penetration of less than 1%;

d. At least once per 18 me by:

carben

! 1) Veri fy at the pressur rop across the combined HEPA l ffite I

less edsorbef banks, and moisture separators of l inches 1 ster Gauge whfie operating the system at a flow rate of 30,000 cfm 110%,

2) Verifying that the system starts on a Safety Injection test sign framf11reets its exhaust flow through the HEPA ffIters ndshapeeshadsdPtHrrs carbon *

3) Verifying that he system main ne the ECCS pump room at a negative pressure relative to adjacent areas, 4)

Verifying opened, that the filter cooling bypass valves can be manually and l

5) Verifying that the heaters dissipate 40 t 4 kW.

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e. \

Af ter each complete or partial replacement of a HEPA filter bank  !

by verifying that the cleanup system satisf fes the in place pene, tration and bypass leakage testing acceptance criterla of less than ,

l 1% (Unit 1), 0.05% (Unit 2) in accordance with ANS! N510 1980 for a  !

00P test aerosol while operating the system at a flow rate of 30,000 cfm 1 10%; and ^  !

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f. earken i Af ter asch complete or partial replacement f a shorese&

bank, by verifying that the cleanup system atisfferthe[adsorber in place penetration and bypass leakage testing acceptance criteria of less than 1% (Unit 1), 0.054 (Unit 2) in accordance with ANS! N510 1960 for a halogenated hydrocarbon refrigerant test the system at a flow rate of 30,000 cfm 210%. gas while operating 1

l l CATAWBA - UNITS 1 & 2 3/4 7 18 l

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i l ELICTRICAL POWER !YSTEMS 4

! SURVIILLANCE asaurasuggyg (Cantinued)

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} 2) Verifyfng the fuel level in the fuel storage tank, i

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3) {

j Vertfyfng the fuel transfer valve can be operated to allow  !

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fuel to be transferred from the storage system to the day tank,  ;

4) Verifying the diesel starts free ambient conditten and to at least 441 rpe in less than er aquel to 11 second .* ler tes 4

I The generater weltage and frequency shas1 be 4140 + 4 vel l

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} and 60 + 1.2 Na within 11 seconds after the rtart Ifene .  :

The diesel generater shall be started for this test by using one of the following sfgnals:  !

I l a) Manual, or i b) l'

' $1eulated less of affafte power by 1teelf, or i

c) SimulatedlessofoffsitepowerinconjunctfenwithanESF j Actuetten test afgnal, or .

d) An ESF Astuatfen test signal by itself. j S) l Verifying the senerater fs synchronised leaded to areater than 1 or egual to 5460 kW but less than er egu,al to 8750 kW in less  !

j than er equal to 60 seconds, and operates for at least 60 minutes, aW ,,

I 4)

I Verifying the diesel generater is alfened to provide standby power to the associated energency busses, b.

i At least once per 31 days and after each operation of the diesel j

j where the period of operation was greater than er equal to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> by checking for and removing accumulated water free the day tank; i j c. j J At least once per 31 days by checking for and removing accumuj'eted water free the fuel e11 storage tanks; *  !

! d. i By verifying that the Cathodic Protection System is OPE Lfkb t

verifyfng: -

1) At least once per 60 days that cathodic protection rectifiers are OptRA8LE and have been inspected in accordance with the

{ manufacturer's inspectfen procedures, and 1

2) At least once per 12 senths that adequate protection fres i

corrosion is provfded in accordence with eenufacturer's  ;

j inspection procedures.

1

e. gy samp1fng new fuel ei1 fn accordence wfth ASTN 040l? prier to

}

addition to storage tanks and I -

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1 gaaetstei start I

' performed at least on W per( w daye- 4 thees-supeo684ense * -'i11see.)from!

Mi-etime t engine starts for the purpose of thfa surveillance testing may be preceded by en engine prelube period and/or other wormuy precedures recommended by the  ;

manufacturer se that mechanical stress and wear en the diesel engine is

etnfofsed.  ;

i CATAWBA - UNITS 1 & 2 3/4 8-3 i

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l REFUELING OPERATIONS 3/4.9.4 CONTAINMENT SUILDING PENETRATIONS '

LIMITING CON 0! TION FOR OPERATION I

3.9.4 The containment building penetrations shall be in the following status:

a. The equipment hatch closed and held in place by a minimum of four bolts, i

b. A minimum of one door in each airlock is closed, and i c. Each penetration providing direct access from the containment 1

atmosphere to the outside atmosphere shall be either:

1) Closed by an isolation valve, blind flange, or manual valve, or l

2) Exhausting throu Purge System HEPkh filters an OPERA 8kt'Re E 8utiding Containment dshoweehadsorbers ,

i APPLICA811,ITY:

carben During CORE ALTERATIONS o movement of ittadiat fuel within the containment.

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building.

l SURVE!LLANCE REQUIREMENT $

1 4.9.4.1 Each of the above required containment buf1 ding penetrations shall be .

l

' determined to be either in its closed / isolated condition or exhausting through  !

an OPERA 8LE Reactor Building Containment Purge System with the capability of l being automatically isolated upon heater failure within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the  ;

. start of and at least once per 7 days during CORE ALTERATIONS or movement of  !

irradiated fuel in the containment building byr l l a. Verifying the penetrations are in their closed / isolated condition, j or i

b. Verifying the upper and lower containment purge supply .tnd exhaust valves close upon a High Relative Humidity test signal. L I

l I

l CATAWgA - UNITS 1 & 2 3/4 9 4

l TAOLE 4.11-1 (Continued)

TABLE NOTATION $

(1)The LLD isofdefined, as the smallest concentration radioactivefor purposes material in a sampleof these that wspecifications lIl yiel count, above system background, that will be detected with 964 probabillty with only 55 probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical

separation:

4.66 s

! LLO = M l

E

• V

• 2.22 x 'X 1

Where:

\*Y.4xp(-Aat)  ;

1 LLO = the "a priert" lower limit of detection (microcurie per unit mass or volume),

s b = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per I

1 minute),

t i

l E = the counting efffciency (counts per disintegration),

l V = the sample site (units of mass or volume),

2.22 x 10e = the number of disintegrations per minute per aferocurie.

Y = the fractional radiochemical yield, when applicable, j

k

• the radioactive decay constant for the particular radionucifde g JW),and  !

I 'At = the elapsed ti -

the midpoint of sample collection and the time of coun ng({

fypical values of ,VTY3ndatshouldbeusedinthecalculation.

It should be recognized that the LLO is defined as an a orfarf before the fact) Ilmit representing the capability of a measuremen',sy(stem and  !

not as an 3 costeriorf (after the fact) limit for a particular measurement.

l (2)A batch release is the discharge of liquid wastes of a discrete volume. ,

i Prior to samp1tng for analyses, each batch shall be isolated, and then '

l thoroughly miaod to assure representative sampling.

CATAWBA UNITS 1 & 2 3/4 11 3 l

RADI0 ACTIVE EFFLUENTS CHEMICAL TREATMENT PON05 LIMITING CONDITION FOR OPERATION 3.11.1.5 The quantity of radioactive material contained in each chemical treatment pond shall be Ilmited by the following expression:

A

~

ya j < 1. 0 excluding tritium and dissolved or entrained noble gases, Where:

Aj = pond inventory Ilmit for single radtonuclide "j", in Curles:

, C) = 10 CFR Part 20. Appendix B Table !!, Column 2, concentration for singleradionucIlde"j",mIcrocuries/ml; l

V = design volume of Ifquid and slurry in the pond, in gallons; and

, 264 = conversion unit, microcuries/ Curie per milliliter / gallon.

APPLICA8ILITY: At all times. * '

ACTION:

a. With the quantity of radioactive material in any of the above listed ponds exceeding the above limit, immediately suspend all additions of radioactive material to the pond and initiate corrective action to reduce the contents to within the Ilmit,

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVE!LLANCE REQUIREMENTS 4.11.1.5 The quantity of radioactive material contained in each batch of resin / water slurry to be transferred to the chemical treatment ponds shall be determined to be within the above limit by analyzing a representative sample of the batch to be transferred to the chemical treatment pefidsgshal be limited by the expression:

y I

b < 0.006 j Cj Where:

cI=enteringtheUNRESTRICTEDAREAchemicaltreatmentponds,inradioa microcurles/ milliliter; and C 10 CFR Part 20, Appendix 8 Table !! Column 2 concentration for 3=singleradionuclide"j",inmicrocurIes/ml1111 Iter.

CATAW8A = UNITS 1 & 2 3/4 11 8

l TABLE 4.11 2 (Continued) '

t TABLE NOTATIONS (1) The LLO is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a not count, above system background that will be detected with 955 probability l withonly55grobabilityoffalselyconcludingthatablankobservation represents a real" signal.  !

l For a particular measurement system, which may include radiochemical separation.

4.H s b LLO = -

E V 2.22 x 108

• Y

• emp (-Aat)

L Where: '

t LLD = the "a priori" lower limit of detection (microcurie per unit j massorvolume),

t sh = the standard deviation of the background counting rate or of

{

l the countire rate of a blank sample as approortate. (countsper l minute), , L L' = the counting efficiency (counts per disintegra' on).

V = the sample size (units of mass cr volume),

l 2.22 x 108 = the. number of disintegrations pi minute per microcurie.

Y = the fractional radiochemical yield, when applicable,

'A a-the radioactive decay constant for the particular radionuclide

f. * ' J) c

" A N the elapsed time-betwee the midpoint of sample collection and the time of cou g, Typical values of E, V, Y, and At should be used in the calculation.

1' It should be recognized that the LLO is defined as an g ri ri (before

! the fact) limit representing the capability of a measuremen system and not as an 3 nosteriori (after the fact) limit for a particular measurement.

CATAWBA = UNITS 1 & 2 3/4 11-11

____________________________m._ . . _ __

RA0!0 LOGICAL ENVIRONMENTAL MONITORING LIMITING CON 0! TION FOR OPERATION ACTION (Continued) Q

c. With milk or fresh }sf y _ _ Zr_' amples unavalla le from one or more of the sagle(1grations requbd_by-TetTe'3.12-1, identify specific locations for obtiinirig replacement samples and add them within 30 days to the Radiological knvironmental Monitoring Program given in the 00CM. The specific locations from which samples were i unavailable may then be deleted from the monitoring program. Pursuant to Specification 6.14, submit in the next Semiannual Radioactive i

Effluent Release Re a revised figure (s) port anddocumentation for a change table for the 00CM in the reflecting the new 00CM including loca- j i

tion (s) with supporting information identifying the cause of the

,* unavailablltty of samples and justifying the selection of the new i location (s) for obtaining samples.

d. The provisions of $pecifications 3.0.3 and 3.0.4 are not applicable.

l I

$URvt!LLANCE R?QUIREMENT$

i 4.12.1 The radfological environmental monitoring samples shall be collected pursuant to Table 3.12 1 from the specific locations given in the table and i

figure (s) in the 00CM, and shall be analyzed pursuant to the requirements of Table 3.12-1 and the detection capabilities required by Table 4.12-1. i l

l l ,

i l

l 1

CATAWBA - UNITS 1 & 2 3/4 12 2

TABLE 4.12 1 (Continued)

TABLE NOTATIONS (1) This Ifst does not mean that only these nuclides are to De considered.

Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.

(2) Required detection capabilities for thermoluminescent dosimeters used for environnental measurements shall be in accordance with the recommenda-tions of Regulatory Gutde 4.13.

(3) The LLO is defined, for purposes of these specifications, as the smallest concentrations of radioactive material in a sample that will feld a net count, above system background, that will be detected with 95 probability withonly5%grobabilityoffalselyconcludingthatablankobservation represents a real" signal.

For a particular measurement system, which may include radiochemical separation: - ,

4. 6 s h LLD =

E V a 2.22 - Y

• exp( AAt) .

Where:

LLO = the "a priori" lower limit of detection (picoCurles per unit massorvolume),

s b = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute).

E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22 = the number of disintegrations per minute per picocurie, Y = the fractional radiochemical yield, when appitcable,

• I bee 'h ~

= the~ radioactive decay constant for the particular radionuclide

% (M), and]

At = the elapsed time between environmental collectionGr~end of s the sample collection period, and time of counting (g.,, ,

Typical values of E V, Y and at should be\used in n.the caliulati_o CATAWBA UNITS 1 & 2 3/4 12 11

. -i 1

INSTRUMENTATION  !

SASES l

REACTOR TR'P SYSTI M and ENG NEERED SAFETY FEATURES ACTUATION $Y$ TEM 1 IN5TRURENThTIQN i; Continued) spray pumps start and automatic valves position, (6) containment isolation, (7) steam Ifne isolation, (8) Turbine trip (9) auxiliary feedwater pumps l

start and automatic valves position (10) nuclear service water pumps start and automatic valves position, and (11), component cooling pumps start and automatic valves position.

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

P-4 Reactor tripped - Actuates Turbine trip, closes main feedwater i valves on T,,, below setpoint, prevents the opening of the main i

feedwater valves which were closed by a safety Injection or High Steam Generator Water Level signal, allows safety injection block to that components can be reset or tripped.

I Reactor not tripped - prevents ma y 1 block of Safety Injec to . ,(ne  !

l P-11 Defeats the manual block of N e'ty Injection actuation [o'n n m-. H' i i - Iow ste Ine pressure and defeats steam line hp To at on o W t ' n steam lin pressure rate. Defeats the manual

" block of the motor driven auxiliary feedwater pumps on trip of m feedwater pumps and low low steam generator water level.

I P 12 i

On decreasing reactor coolant loop temperature, P-12 automatically blocks steam dump and allows manual bypass of steam dump b1cck for the cooldown valves only. On increasing reactor coolant loop temper-4ture, P 12 automatically defeats the manual bypass of the steam dump block. I 1

l P 14 On increasing steam generator level, P 14 automatica11y trips all '

feedwater isolation valves control valve modulation. , pumps and turbine and inhibits feedwater 3/4,3,3 MONITORING INSTRUMENTAfl0N 3/4,3,3,1 RADIATION MONITORING FOR PLANT OPERATIONS ,

The OPERASILITY of the radiation monitoring instrumentation for plant I operations ensures thatt (1) the associated action will be initiated when the

radiation level monitored by each channel or combination thereof reaches its Setpoint. (2) the specified coincidence logic is maintained, and (3) suff t-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 enceeded. If they are, the signals are l combined into logic matrices sensitive to combinations indicative of various accidents and abnormal conditions. Once the required logic combination is l

i completed, the system sends actuation signals to initiate alarms or automatic isolation action and actuation of Emergency Exhaust or Venttiation Systems.

CATAWBA - UNITS 1 & 2 8 3/4 3 3 i

TABLE 6.2-1 HINIMUM SHIFT CREW COMP 05tTION P05! TION NUMBER OF IN0!V10VALS REQUIRED TO FILL P051T10N One Unit in Mode Both Units in 1, 2, 3 or 4 and Both Units in H00E 5 or 6 One Unit in Mode 5 MODE 1, 2, 3, or 4 or Defueled or 6 or Defueled 55 1 1 1 SRO 1 None## 1 R0 3# 2# 3#

NEO 3# 3# 3#

STA 1 None 1 55 -

Shift Supervisor with a Senior Operator license SRO Individual with a Senior Operator license R0 -

Individual with an Operator license NE0 Nuclear Equipment Operator '

• STA Shif t Technical Advisor The Shif t Crew Cc position may be one less than the minimum requiremehts of Table 6.2 1 for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shif t crew composition to within the minimum requirements of Table 6.2 1. This provision does not permit any shift crew position to be unmanned upon shif t change due to an oncoming shif t crewman being late or absent.

During any abtence of the Shift Supervisor from the control room while the unit is in H00E 1, 2, 3, or 4 an individual (other than the Shift Technical Advisor") with a valid Senior, Operator license shall be designated to assume the control room command function. During any absence of the Shift Supervisor from the control room while the unit is in H00E 5 or 6 an individual with a valid Senior Operator license or Operator Ilcense shall be designated to assume the control room command function.

'On occasion when there is a need for both the Shif t Supervisor and the SRO to be absent from the control room, the STA shall be allowed to assume the control providedroomthattcommand function and serve as the SR0 in the control room (1) the Shift Supervisor is available to return to the control room within 10 minutes, (2) the assumption of SR0 duties by the STA be limited to periods not in excess of-15 minutes duration and a total time not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> du ing any 4=4mse shtf t, and (3) the STA has a Senior Operator license on the(unite '

1. At least one of the required individuals must be assigned to the designated position for each unit.

1. 1. At least one licensed Senior Operator or Itcensed Senior Operator Limited to Fuel Handling must be pressnt during CORE ALi[RAi!0NS on either unit, who has no other concurrent responsibilities.

CATAWGA

• UNITS 1 & 2 65

I ADMINISTRATIVE CONTROLS r

SEMIAlelWAL RADICACTIVE EFFLUENT RELEAlf REPORT (Continued)

The Radioactive Effluent Release Reports shall include the fellowing informa-  !

tien for each class of selfd waste (as deffned by 10 CFR Part 41) shipped  ;

offsite during the report perled: i

a. Total Cc.itainer volume,

b. Total curie quantity (specify whether determined by measurement or estfaste), ,

i

c. Principal radienuclides (spectfy whether determined by measurement er estimate),  !

j

d. Sources of weste and processing employed (e.g., dowatered spent resin, compacted dry weste, evaporater bettees),  ;

y e.

Type of container (e.g., LSA, Type A, Type 8, large quantity), and I

f. Solidification agent er absorbent (e.g., cement uros formaldehyde), f ThTeeatennusLAadfesctive Effluent Release Report to be submitted withfn '

O

$ 60 days af u January I'ef-eech year shall incluu an annual summary of hourly I meteorological da_ cellected'ever the provisus 3 ser. Thfs annual summary may be either in the e en hev -hour 1f atfng an magnetic tape ef itfnd speed, l

windWitgrafon,ateesphori Ifty and prec<pftatfen (ff measured), or in }

the form of iet at.esphericsta.ntTreguencydistributlensofwindspeed,winddirection,and inty.- This same re rediation deses due to the redisectiv,e,t shanand e 1iquid fnciude gaseous an assess.ent of the effluents released l from the unit er statien during the provieus calender year. Thfs same report l

shall aise include an assessment of the radfation doses from radioactive i 11guld and geseous effluents to NEMERS OF THE PUOLIC due to their activities fnside the SITE SOUNDARY (Figure 5.1-3) during the report perfed. All assump- l tiene used In mekIng these assessmente, f.e., specfffc actfvity, espesure time and location shall be ineluded in these reports. The meteorelsefcal i conditfens concurr,ent wfth the tfme ef release ef radieactive meterials in j gaseous effluents, as determined by sampling frequency and measurement, shall 1 be used for determining the geseous pathway deses. The assessment of radiatten  ;

deses shall be performed in accordance with the methodology and parameters in i the OFFSITE DOSE CALCULAfl0N MANUAL (00CM). I The Semiannual Radioactive Effluent Release Report to be submitted within '

60 days after January 1 of each year shall aise include an assessment of radiatten deses to the Ifhely aest esposed NEMBER OF THE PUBLIC from reactor releases and other nearty wrentum fuel cycle sources, including deses from primary effluent '

pathways and direct radiatten, for the prevleus calender year to show conformance vith 40 CFR Part 1g0 "Envirennental Radiatien protectien Standards fer Nuclear j Power Operetien". Acceptable methods for calculating the dose conteibutien fren '

Ilguld and gaseous effluents are given in Regulatory Guide 1.10g, Rev.1  !

Octeter 1977. i

• In lieu of submission with the Sealannual Radioactive Effluent Release Report, )

the licensee has the option of retaining this summary of required meteorelegical  ;

data en site in a file that shall be provided to the MC upon request. j CATAbe4 - UNITS 1 4 i Gale  !

I j