ML20133M266

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Forwards marked-up Rev to Proposed Tech Specs Submitted on 850315,including Table 2.2-1, Reactor Trip Sys Instrumentation Trip Setpoints
ML20133M266
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 08/07/1985
From: Tucker H
DUKE POWER CO.
To: Adensam E, Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 8508130066
Download: ML20133M266 (40)
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Text

{{#Wiki_filter:'s DUKE POWER GoxPm j P.O. BOX 33180 ( CIIARIAYI"rE, N.C. 28242 l

retgpuoy, IIAL 11. TUCKER

(*** 21",C."mo August 7, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Catawba Nuclear Station, Units 1 and 2 Re: Docket Nos. 50-413 and 50-414

Dear Mr. Denton:

Please find enclosed revised pages for the proposed Catawba Units 1 and 2 These proposed Technical Specification changes Technical Specifications. 15, 1985 replace the corresponding pages previously included in my March submittal. l If you have any questions regarding this submittal, please contact Mr. Roger Ouellette at (704)373-7530. L Very truly yours, ff Hal B. Tucker RWO: sib Enclosures cc: w/o enclosures Mr. Jesse L. Riley Dr. J. Nelson Graca, Regional Administrator Carolina Environmental Study Group U. S. Nuclear Regulatory Commission 854 Henley Place Region II Charlotte, North Carolina 28207 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 w/ enclosures l NRC Resident Inspector Robert Guild, Esq. Catawba Nuclear Station P. O. Box 12097 Charleston, South Carolina 29412 Palmetto Alliance 2135 Devine Street Columbia, South Carolina 29205 \\ 8508130066 850807 \\ DR ADOCK 05000413 \\ PDR

n TABLE 2.2.-1 g REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS Ug TOTAL SENSOR ALLOWANCE ERROR [ FUNCTIONAL UNIT (TA) Z (S) TRIP SETPOINT ALLOWABLE VALUE 1. Manual Reactor Trip N.A. N.A. N.A. N.A. N.A. H 2. Power Range, Neutron Flux g a. High Setpoint

7. 5 4.56 0

$109% of RTP* $111.1% of RTP* b. Low Setpoint 8.3 4.56 0 525% of RTP* $27.1% of RTP* f 3. Power Range, Neutron Flux,

1. 6 0.5 0

55% of RTP* with 56.3% of RTP* with High Positive Rate a time constant a time constant 1 2 seconds 1 2 seconds 4. Power Range, Neutron Flux,

1. 6 0.5 0

55% of RTP* with 56.3% of RTP* with High Negative Rate a time constant a time constant 12 seconds 12 seconds 5. Intermediate Range, 17.0 8.4 0 525% of RTP* $31% of RTP* y Neutron Flux 6. Source Range, Neutron Flux 17.0 10-0 $105 cps 51.4 x 105 cps 7. Overtemperature AT 7.2 4.47 2.03 See Note 1 See Note 2 8. Overpower AT 4.3 1.3 1.2 See Note 3 See Note 4 9. Pressurizer Pressure-Low 4.0 2.21 1.5 11945 psig 11938 psig*** 10. Pressurizer Pressure-High 7.5 4.96 0.5 52385 psig $2399 psig 11. Pressurizer Water Level-High 5.0 2.18

1. 5 592% of instrument 593.8% of instrument span span 12.

Reactor Coolant Flow-Low 2.5 1.77 0.6 190% of loop 189.2% of loop design flow ** design flow **

  • RTP = RATED THERMAL POWER
    • Loop design flow = 96,900 gpm
      • Time constants utilized in the lead-lag controller for Pressurizer Pressure-Low are 2 seconds for lead and 1 second for lag.

Channel calibration shall ensure that these time constants are adjusted to these values.

i POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continued) .k 2. The Power Range Neutron Flux * - High Setpoints to less than or %j equal to 55% of RATED THERMAL POWER within the next 4 hours. h c. With the indicated AFD outside of the above required target band for more than I hour of cumulative penalty deviation time during the previous 24 hours and with THERMAL POWER less than 50% but graater than 15% of RATED THERMAL POWER, the THERMAL POWER shall not be increased equal to or greater than 50% of RATED THERMAL D POWER until the indicated AFD is within the above required target band. "T*he. plusion of&ac.;$cahn 3.0.</ are 71of aff calle 6-ofA*n b 4 ap de 50% d &4-red rHEAWr1L foWE4 SURVEILLANCE REQUIREMENTS 4.2.1.1 The indicated AFD shall be determined to be within its limits during g POWER OPERATION above 15% of RATED THERMAL POWER by: a. Monitoring the indicated AFD for each OPERABLE excore channel: g 1) At least once per 7 days when the AFD Monitor Alarm is OPERABLE, o and Q 2) At least once per hour for the first 24 hours after restoring .S the AFD Monitor Alarm to OPERABLE status, w3 b. Monitoring and logging the indicated AFD for each OPERABLE excore channel at least once per hour for the first 24 hours and at least 0, once per 30 minutes thereafter, when the AFD Monitor Alarm is o inoperable. The logged values of the indicated AFD shall be assumed C to exist during the interval preceding each logging. b 4.2.1.2 The indicated AFD shall be considered outside of its target band when ,o two or more OPERABLE excore channels are indicating the AFD to be outside the target band. Penalty deviation outside of the above required target band shall be accumulated on a time basis of: a. One minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels equal to or above 50% of RATED THERMAL POWER, and

  • Surveillance testing of the Power Range Neutron Flux Channel may be performed pursuant to Specification 4.3.1.1 provided the indicated AFD is maintained within the Acceptable Operation Limits of Figure 3.2-1.

A total of 16 hours operation may be accumulated with the AFD outside of the above required target band during testing without penalty deviation. CATAWBA - UNIl5144/b z 3/4 2-2 N-

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) b. One-half minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER. 4.2.1.3 The target flux difference of each OPERABLE excore channel shall be determined by measurement at least once per 92 Effective Full Power Days. The provisions of Specification 4.0.4 are not applicable. 4.2.1.4 The target flux difference shall be updated at least once per 31 Effective Full Power Days by either determining the target flux differcnce pursuant to Specification 4.2.1.3 above or by linear interpolation between the most recently measured value and 0% at the end of the cycle life. The provi-sions of Specification 4.0.4 are not applicable. I(L CATAWBA - UNIl51 Mb 2. 3/4 2-3

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continued) 2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours and reduce the Power Range Neutron Flux-High Trip Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours; and 3. Identify and correct the cause of the cut-of-limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the 'g g QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours or until verified at 95% or greater { RATED THERMAL POWER. h d. The provisions of Specification 3.0.4 are not applicable. GW SURVEILLANCE REQUIREMENTS N 4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within the b limit above 50% of RATED THERMAL POWER by: a. Calculating the ratio at least once per 7 days when the alarm is N OPERABLE, and 3 b. Calculating the ratio at least once per 12 hours during steady-state q operation when the alarm is inoperable. RA 4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75% of RATED THERMAL POWER with one Power Range channel

  • h inoperable by using the movable incore detectors to confirm that the normalized g

symmetric power distribution, obtained from two sets of four symmetric thimble locations or full-core flux map, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours. CATAWBA - UNIIf1 A4 2, 3/4 2-14 )

A' TABLE 3.2-1 DNB PARAMETERS s PARAMETER LIMITS Four Loops in Operation -kdicated o-=rtnr cnni e t ;,,i.e p 9-- -ar w J..d k:t:2 ^ s .u. ,', m. u i u c ??"^ .u. n

g g

LAl5EllT FROM NEXT 7 AGE -i

  • Limit not applicable during either a THERMAL POWER ramp in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step in excess of 10% of RATED THERMAL POWER.

CATAWBA - UNITr1 Mb y 3/4 2-16 4 e -e, -w yr-.. ---r-, ,,--,w -g- -w c, ,e --.-----,,--w. ,.m-

DUKE POWER COMPANY FormD0184 (6-81) a Dev./ Station Unit File No. Subject By Date Sheet No._of Problem No. Checked By Date WSWloM F6N @l._E 6N 2-/N I I I l } l l l l Average Temperature Meter average - 4 channels: 1 592.75'F - 3 channels: 5 592.44*F Computer average - 4 channels: 5 593.30*F - 3 channels: 1 593.05'F Pressurizer Pressure l Meter average - 4 channels: 1 2225.8 psign - 3 channels: 1 2229.1 psigt Computer average - 4 channels: 1 2221.0 psig@ l - 3 channels: 1 2223.5 psigt I i i I i I l l l l i l i }l I i t l l I i l l l II I I i l l l l j (- i I I i l I i i i-j i !i i i ,-p q -,-,y g-,-9qm -yg-m,w--y-,

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TABLE 3.3-1 (Continued) ACTION STATEMENTS (Continued) ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving positive reactivity changes. ACTION 5 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status.within 48 hours or open the Reactor trip breakers, suspend all operations involving positive reactivity changes and verify Valves NV-231, NV-237, NV-241, and NV-244 are closed and secured in position within the next hour. ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: a'. The inoperable channel is placed in the tripped condition within 1 hour, and b. The Minimum Channels OPERABLE requirement is, met; however, the inoperable channel may be bypassed for up.to 2 hours for surveillance testing of other channels per Specification 4.3.1.1. ACTION 7 - With'the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required ANALOG CHANNEL OPERA-TIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 ho'ur.- ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within 1 hour determine by observation of the associated permissive status light (s) that the interlock is in its required state .for the existing plant condition, or apply Specification 3.0.3. ACTION 9 - With the number of OPERABLE channels one less than the Minimum. Channels OPERABLE requirement, be in at least HOT STAN0BY within 6 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE. ACTION 10 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours or open the Reactor trip breakers within the next hour. ACTION 11 - With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within 1 hour. CATAWBA - UNIT 11 Mb a 3/4 3-6

b TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION s. 2 i MINIMUM c: TOTAL NO. CHANNELS CHANNELS APPLICABLE 35 FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION M (( 1. Safety Injection (Reactor g Trip, Phase "A" Isolation, Feedwater Isolation, Control Room Area Ventilation Opera-tion, Auxiliary Feedwater-Motor-Driven Pump, Purge & Exhaust Isolation, Annulus Ventilation Operation, Auxiliary Building Filtered Mea M 4e W ow Exhaust Operation, ki Emergency Diesel Generator Operation, Component Cooling Y Water, Turbine Trip, and 0; Nuclear Service Water Operation) a. Manual Initiation 2 1 2 1,2,3,4 18 b. Automatic Actuation 2 1 2 1,2,3,4 14 Logic and Actuation Relays c. Containment 3 2 2 1,2,3 15* Pressure-High d. Pressurizer 4 2 3 1, 2, 3# 19* Pressure-Low e. Steam Line Pressure-3/ steam line 2/ steam line 2/ steam line 1, 2, 3# 15* Low in any steam line 4__

f O ~ . TABLE 3.3-3 (Continued) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 5 MINIMUM e 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, 6-3/ pump 2/ pump 2/ pump 1,2,3 15 5222
2) X CAPS 5230, 5231, 523 p g 6-3/ pump 2/ pump 2/ pump 1, 2, 3 -

15 Y 9. Containment Sump [ Recirculation E a. Automatic Actuation 2 1 2 1, 2,-3, 4 14 Logic and Actuation Relays b. Refueling Water Storage Tank Level-Low 4 2 3 1,2,3,4 16 Coincident With Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements. 10. Loss of Power a. 4 kV Bus Undervoltage-3/ Bus 2/ Bus 2/ Bus 1, 2, 3, 4 15* Loss of Voltage b. 4 kV Bus Undervoltage-Grid Degraded Voltage 3/ Bus 2/ Bus 2/ Bus 1, 2, 3, 4 15* 11. Control Room Area Ventilation Operation a. Automatic Actuation Logic and Actuation Relays 2 1 2 All 24

r o n TABLE'3.3-4 E! ~ 32 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 2 SENSOR Si TOTAL ERROR g; FUNCTIONAL UNIT ALLOWANCE (TA) Z (S) TRIP SETPOINT ALLOWABLE VALUE 3,

1. Safety Injection (Reactor Trip,

{} Phase "A" Isolation, Feedwater Isolation, Control Room Area Ventilation Operation, Auxiliary Feedwater-Motor-Driven Pump, Purge & Exhaust Isolation, Annulus Ventilation Operation, Auxiliary Building Filtered " ' " Exhaust Operation, Emergency Diesel Generator Opera-u, ]; tion, Component Cooling Water, Turbine Trip, and Nuclear /, Service Water Operation) u a. Manual Initiation N.A. N.A. N.A. N.A. N.A. b. Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A. and Actuation Relays c. Containment Pressure-High 8.2 0.71 1.5 5 1.2 psig 5 1.4 psig d. Pressurizer Pressure-Low 16.1 14.4 1.5 g 1845 psig 3 1839 psig l e. Steam Line Pressure-Low 4.6 1.31 1.5 g 725 psig 3 694 psig*

2. Containment Spray a.

Manual Initiation N.A. N.A. N.A. N.A. N.A. b. Automatic Actuation Logic N. A. N.A. N.A. N.A. N.A. and Actuation Relays c. Containment Pressure-High-High 12.7 0.71 1.5 5 3 psig 5 3.2 psig I I

r-TA8LE 3.3-4 (Continued) k ENGINEERED SAFETY FEATURES ACTUATION SYSTEM-INSTRUNENTATION TRIP SETPOINTS h ' SENSOR TOTAL ERROR FUNCTIONAL UNIT ALLOWANCE (TA)' Z (S) . TRIP SETPOINT ALLOWABLE VALUE~ 3' 15. Emergency Diesel Generator Operation (Diesel Building w ) Ventilation Operation, Nuclear t7 Service Water Operation) (Continued) C' b. Automatic Actuation Logic N.A. N.A. N.A. N.A. N.A. and Actuation Relays c. Loss-of-Offsite Power . N.A. N.A. N.A. 1 3500 V 2 3200 V d. Safety Injection See Item. I above for all Safety Injection Setpoints and Allowable Values.

16. Auxiliary Building Filtered

100 I --1-- i i I I o o 100 200 300 400 s00 INDICATED TEMPER ATURE (OF) FIGUP.E 3.4-3 REACTOR COOLANT SYSTEM 000LOGWN LIMITATIONS - /,PILICABLE UP TO 15 EFPY I Cf'llliBA - UNIT 51 M 2. 3/4 4-34 t n. n vii..u.. iv MT-SME 2212 MATERIAL PROPERTY BASIS COPPER CONTENT

CONSERVATIVELY ASSUMED TO BE 0.10 WT% (ACTUAL CONT NT =

0.07 WT%) RT INITIAL

CONSERVATIVELY ASSUMED TO BE 40*F (ACTUAL RT NDT ND ".33*F)

AFTER 16 EFPY : 1/4T,110*F DT 3/4T, 87"F CURVE PPLICABLE FOR HEATUP RATES UP TO 60*F/HR FOR THE SERVICE ERIOD UP TO 1 EFPY AND CONTAINS MARGINS OF 10*F AND 60 PSIG FOR P.0e IBLE INSTRUMEt ERRORS asso.o i:! IN I !.i - I i i 1 ill !I. i /ii i i ,:i i X it! j i l

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l l O.0 G. f, 800.0 200.0 300.0 900.0 500.0 lhotCalED itM E R a tu n t ( OtG.F l gure 1 Catawba Unit 2 Reactor Coolant System Heatup Limita-tions Applicable up to 16 EFPY a ...............o HT-SME 2212 MATERIAL PROPERTY BASIS COPPER CONTENT CONSERVATIVELY ASSUMED TO BE 0.10 WT% ( TENT = 0.07 WT%) RT INITIAL NDT CONSERVATIVELY ASSUMED TO BE 40*F (ACTU RTNDT

  • RT AFTER 16 EFPY : 1/4T,110*F NDT 3/4T. 87*F CURVE APPLICABLE FOR C00LDOWN RATES UP T0100*F/HR FOR HE SERVICE PERIOD UP TO 16 EFPY AND CONTAINS MARGINS OF 10*F AND OSSIBLE INSTRUMENT ERRORS 0 PSIG FOR 3003.3

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1 e.,,_r w =a ::::e=n =o m w e.01 pp a=- may u ~ :::d 7 g rati,;..~ ,7.,-m-for 10 i _.. "^m m-d % CATAWBA - UNIIr1 Aan s 3/4 6-14 CONTAINMENT SYSTEMS ICE CONDENSER DOORS LIMITING CONDITION FOR OPERATION 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. OCTION: With one or more ice condenser doors open or otherwise inoperable, POWER OPERATION may continue for up to 14 days provided the ice bed temperature is monitored at least once per 4 hours and the maximum ice bed temperature is maintained less than or equal to 27 F; otherwise, restore the doors to their closed positions or OPERABLE status (as applicable) within 48 hours or be in at least HOT STAND 8Y within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.6.5.3.1 Inlet Doors - Ice condenser inlet doors shall be: Continuously monitored and determined closed by the Inlet Door a. Position Monitoring System, and \\% b. Demonstrated OPERABLE during shutdown at least once per 'I months t_ -- ; W ' '. _., ; ;,. : L = --.::= ;. ; - ' ; n; != ; 1, - _ i---J = =. by: 1) Verifying that the torque required to initially open each door is less than or equal to 675 inch pounds; 2) Verifying that opening of each door is not impaired by ice, frost or debris; 60% 3) Testing a sample of at least % 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 to ensure that all doors are tested at least once during desm test intervals; g Ildo CATAWBA - UNIV 1 A#b 2, 3/4 6-36 .~ 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam line Code safety valves associated with each steam generator shall be OPERABLE with lif t settings as specified in Table 3.7-2. APPLICABILITY: MODES 1, 2, and 3. ACTION: With four reactor coolant loops and associated steam generators in a. operation and with one or more main steam line Code safety valves inoperable, operation in MODES 1, 2, and 3 may proceed provided, that within 4 hours, either the inoperable valve is restored to OPERABLE status or the Power Range Neutron Flux High Trip Setpoint is reduced per Table 3.7-1; otherwise, be in at least HOT STANDBY within the next 6 hours and in MSHUTDOWN within the following %^q hot hours. b. C The provisions of Specification 3.0.4 are not applicable. SURVEILLANCE' REQUIREMENTS 4.7.1.1 No additional requirements other than those required by Specification 4.0.5. lL CATAWBA - UNIT (1 A#b 2. 3/4 7-1 L PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) ccwhon c. At least once per 1 onths or glit after any structural maintenance on the HEPA filter or h adsorber housings,;. T '^' s m - - g q __ - by: ....y___- 1) Verifying that' the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedure guidance in Regulatory Position C.5.a. C.5.c, and C.5.d* of Regulatory Guide 1.52, Revi-sions 2, March 1978, and the sytem flow rate is 6000 cfm 10%; 2) Verifying, within 31 days af ter removal, that a laboratory analysis of a representative carbon sample obtained in accor-dance with Regulatory Position 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, Revi-sion 2, March 1978, for a methyl iodide penetration of less than 1%; and 3) Verifying a system flow rate of 6000 cfm i 10% during system operation when tested in accordance with ANSI N510-1980. cabon d. After every 720 hours of shasepaAadsorber operation, by verifying, within 31 days after removal, that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position 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 iodide penetration of less than 1%; e. At least once per 18 months by: 1) Verifying that the pressure drop across the combined HEPA filters, carbon, t. al adsorber banks, and moisture separators is less than 8 inches Water Gauge while operating the system at a flow rate of 6000 cfm 1 10%; 2) Verifying that on a High Radition-Air Intake, or Smoke Density-High test signal, the system automatically isolates the affected intake from outside air with recirculating flow through the HEPA filtersandchspess4gorberbanks; re jQ 3) Verifying that the system maintains the control room at a positive pressure of greater than or equal to 1/8 inch Water Gauge at less than or equal to pressurization flow of 4000 cfm to^fhe cedml room esees during system operation; 4) Verifying that the heaters dissipate 25 + 2.5 kW when 3 i___d ^ _. i.. ..,,..n --iO C ^A,and % wi. =.yn;c n d ;: h_emd ir nd owAkry. ofru.J d c Jb, s :% m cc..tsat h s t Ci g sy A ch'Od bj @TWQ'th hh '.,vl'Lhw M4tn-%hs vy o@catig n CATAWBA - UNITf14@ 2L. 3/4 7-14 _ PLANT SYSTEMS JURVEILLANCEREQUIREMENTS(Continued) 60,000 { 3) operation when tested in accordance with carbon After every 720 hours ofghrn:1 adsorber operation c. within 31 days after removal, that a laboratory analysis of a, b Position C.6.b of Regulatory Guide 1.52, Revision of Regulatory Guide 1.52, Revision 2, Marc 1 , March 1978, iodide penetration of less than 1%; g d. At least once per 18 months by: co.rbon 1) Verifying that the pressure drop across the combined HEPA e filters, d.:.aa; adsorber banks, and moisture separators less than 8 inches Water Gauge while operating the syste of a flow rate of 30,000 cfm + 10's 'O O ,g E 2) Verifying that the system starts on a Safety Injection o test signal, and directs its exhaust flow through the HEPA ]g filters and d i d adsorbers, e i,j 3) cachen j Verifying that the system maintains the ECCS negative pressure relative to adjacent areas, pump room at a g 4) w Verifying that the filter cooling bypass valves can be manu j3 opened, and t cI. y g, 5) ecen d r.x with." C N 10 1980cVerifying that the heater g4 rr

e. [ After each complete or partial replacement of 'aliEPA by verifying that the cleanup system satisfies the in place n,

tration and bypass leakage testing acceptance criteria of l pene-1% in accordance with ANSI H510-1980 for a D0P t ( ess than operating the system at a flow rate of 30,000 cfm q C' ~6 4~ while b y3 10%,; 4 ' d so c

f. g after each complete or partial replacement of a chrecal f" b carbon b

bank, by verifying that the cleanup system satisfies the in E 8 { J.51 gadsorber penetration and bypass leakage testing acceptance criteria of l place than 1% in accordance with ANSI N510-1980 i 4 83 ) rate of 30,000 cfm i 10% carbon refrigerant test gas while operati for a halogenated h d [,$ j y ro-I '"E g63D % c{ b { P" gerifying, within 31 days after removal, that a 5 y5 ~j y j ( @Lg s dance with Regulatory Position C.6.b of Regulatory Guide 152 g Revision 2, March 1978, meets the laboratory testing crite i = of Regulatory Position C.6.a of Regulatory Guide 1.52 Ehi$g ra sion 2, March 1978, for a methyl iodide penetration of less C2 , Revi-

t. 4 o[1 c

than 1%j ~ CATAW8A '- UNITil Adb A. ,4d5 3/4 7-17 klANTSYSTEMS b 3 7.13 STANDBY SHUTDOWN SYSTEM ~ LIMI~T MG CONDITION FOR OPERATION sss see x 3.7.13 Th Standby Shutdown System (SSS) shall be OPERABLE. APPLICABILIT MODES 1, 2, and 3. ACTION 1 a. With the tandby Shutdown System inoperable, r store the inoperable equipment. OPERABLE status within 7 days or be in at least HOT STANDBY with'n the next 6 hours and in at 1 st HOT SHUTDOWN within the following 6 hours. b. With the total eakage from UNIDENTIFIE LEAKAGE, IDENTIFIED LEAKAGE and reactor cool t pump seal leakage reater than 26 gpm, declare the Standby Makeu Pump inoperable a a take ACTION a., above. c. The provisions of Sp ifications 3 0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS \\ / 4.7.13.1 The Standby Shutdown Syste iesel generator shall be demonstrated OPERABLE: a. At least once per 31 day by v rifying: 1) The fuel level i the fuel torage tank is greater than or equal to 67 inches, a 2) The diesel st rts from ambient onditions and operates for at least 30 min tes at greater than or equal to 700 kW. b. At least once r 92 days by verifying at a sample of' diesel fuel from the fuel storage tank, obtained in cordance with ASTM-0270-1975, is within t acceptable limits specified 'n Table 1 of ASTM-0975-1977 when check for viscosity and water and se iment; and c. At leas once per 18 months, during shutdown, by subjecting the diesel to an ' spection in accordance with procedures repared in conjunction with ts manufacturer's recommendations for the lass of service. 4.7.13.2 Th Standby Shutdown System diesel starting 24 vol battery bank and charger sh 1 be demonstrated OPERABLE: a. At least once per 7 days by verifying that: 1) The electrolyte level of each battery is above the p ates; and 2) The overall battery voltage is greater than or equal t 24 volts. CATAWBA - UNIT 1 3/4 7-39 QJC E RT /J E w )LANTSYSTEMS {$ $(( S EILLANCE REQUIREMENTS (Continued) \\ / b. At least once per 92 days by verifying that the specific gr ity is appropriate for continued servic-3 of the battery, and i c. A least once per 18 months by verifying that: 1) e batteries, cell plates, and battery racks s w no visual in ication of physical damage or abnormal det ioration, and 2) The b tery-to-battery and terminal connec ons are clean,

tight, d free of corrosion.

l 4.7,.13.3 The Standby Mak p Pump water supply shall e demonstrated OPERABLE by: a Verifying at least o ce per 7 days: a. 1) That the requireme ts of Spec' ication 3.9.10 are met and the boron concentration 'n the s orage pool is greater than or equal to 2000 ppm, or 2) That a contained borate water volume of at least 112,320 gallons with minimum boron con n ation of 2,000 ppm is available and capable of being ali ed to the Standby Makeup Pump. b. Verifying at least once per 92 days that the Standby Makeup Pump develops a flow of gr ter than or e ual to 26 gpm at a pressure greater than or equal to 2488 psig. 4.7.13.4 The Standby Shutdo System 250/125-Volt Battery Bank and its associated charger shall be emonstrated OPERABLE: At least once p r 31 days by verifying: a. 1) That th electrolyte level.of each batte is above the plates, and 2) The otal battery terminal voltage is great r than or equal to 25 /129 volts on float charge. L b. At le st once per 92 days by verifying that the spec'fic gravity is appr riate for continued service of the battery, and I c. At east once per 18 months by verifying that: The batteries, cell plates, and battery racks show no visual indications of physical damage or abnormal deteriorati , and 2) The battery-to-battery and terminal connections are clea

tight, free of corrosion and coated with anti corrosion material.

+ 2 CATAWBA - UNIT 1 3/4 7-40 A5 E g.T 4 E W PLANT S Qbb b bC ' SURVEILLANCE NTS (Continued) 4.7.13.5 The Steam Turbine ~ Auxiliary F water Pump and associated en components shall be demonstrated ABLE a east once per 18 months by veri-fying that the system functions as des from the Standby Shutdown System. 4.7.13.6 Each Standby Shutdown S em instrumen ion device shall be demonstrated OPERABLE by perfor nce of a CHANNEL C at least once per 31 days and a CHANNEL CALIBR ON at least once per 18 mo s. / 7 IL = L CATAWBA - UNIT 1 3/4 7-41 PLANT SYSTEMS 3/4.7.13 STANDBY SHUTDOWN SYSTEM LIMITING CONDITION FOR OPERATION 3.7.13 The Standby Shutdown System (SSS) shall be OPERABLE. APPLICABILITY: MODES 1, 2 and 3. ACTION: a. With less than the minimum SSS equipment in Table 3.7-4 OPERABLE, restore the inoperable equipment to OPERABLE within 7 days, or provide equivalent capability to achieve HOT STANDBY and restore the inoperable equipment to OPERABLE within 60 days, or be in HOT STANDBY within the next 12 hours and HOT SHUTDOWN within the following 24 hours. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.7.13.1 The provisions of Specification 4.0.4 are not applicable. 4.7.13.2 The Standby Shutdown System diesel generator shall be demonstrated OPERABLE: a. At least once per 31 days by verifying:

1) The fuel level in the fuel storage tank is greater than or equal to 67 inches, and
2) The diesel starts from ambient conditions and operates for at least 30 minutes at greater than or equal to 700 kW.

b. At least once per 92 days by verifying that a sample of diesel fuel from the fuel storage tank, obtained l in accordance with ASTM-D270-1975, is within the acceptable limits specified in Table 1 of ASTM-D975-1977 when checked for viscosity and water and sediment; and c. At least once per 18 months by subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for the class of service. l CATAWBA - UNITS 1 and 2 3/4 7-39 ( PLANT' SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 1 4.7.13.3 The Standby Shutdown System diesel starting 24-volt battery bank and charger shall be demonstrated OPERABLE: a. At least once per 7 days by verifying that:

1) The electrolyte level of each battery is above the plates; and
2) The overall battery voltage is greater than or equal to 24 volts, b.

At least once per 92 days by verifying that the specific gravity is appropriate for continued service of the battery, and c. At least once per 18 months by verifying that:

1) The batterics, cell plates, and battery racks show no visual indication of physical damage or abnormal deterioration, and
2) The battery-to-battery and terminal connections are clean, tight, and free of corrosion.

4.7.13.4 The Standby Makeup Pump water supply shall be demonstrated OPERABLE by: a. Verifying at least once per 72 hours that IDENTIFIED LEAKAGE, UNIDENTIFIED LEAKAGE, and Reactor Coolant Pump Seal leakoff do not exceed a total of 26 gpm. b. Verifying at least once per 7 days:

1) That the requirements of Specification 3.9.10 are met and the boron concentr.ation in the storage pool is greater than or equal to 2000 ppm, or
2) That the refueling water storage tank is capable of being aligned to the Standby Makeup Pump.

c. Verifying at each COLD SHUTDOWN, but not more than once every 92 days, that the Standby Makeup Pump develops a flow of greater than or equal to 26 gpm at a pressure greater than or equal to 2485 psig. 4.7.13.5 The Standby Shutdown System 250/125-Volt Battery Bank and its associated charger shall be demonstrated OPERABLE: a. At least once per 31 days by verifying: CATAWBA - UNITS 1 and 2 3/4 7-40 a PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

1) That the electrolyte level of each battery is above the plates, and
2) The total battery terminal voltage is greater than or equal to 258/129 volts on float charge.

b. At least once per 92 days by verifying that the average specific gravity is greater than or equal to 1.200. At least once per 18 months by verifying that: c.

1) The batteries, cell plates, and battery racks show no visual indications of physical damage or abnormal deterioration, and
2) The battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anti-corrosion material.

4.7.13.6 The Steam Turbine Driven Auxiliary Feedwater Pump and associated components shall be demonstrated OPERABLE in accordance with portions of Specification 3/4.7.1.2 applicable to SSS. 4.7.13.7 The "C" solenoid shall be demonstrated OPERABLE and capable of being deenergized to open valve.SA48ABC to provide steam supply to the turbine driven auxiliary feedwater pump at least once per 18 months. 4.7.13.8 Standby Shutdown System instrumentation shall be demonstrated OPERABLE by performance of surveillance requirements listed in Table 4.7-2. l-CATAWBA - UNITS 1 and 2 3/4 7-41 l' n EI TABLE 3.7-4 STANDBY SHUTDOWN SYSTEM El MINIMUM EOUIPMENT I b INSTRUMENT READ 0UT LOCATION MINIMUM CHANNELS OPERABLE U Reactor Coolant Pressure SSF Control Panel 1 !b Pressurizer Level SSF Control Panel 1 N Steam Generator Level SSF Control Panel 1/S.G. Incore Temperature SSF Control Panel 1* Standby Makeup Pump Flow SSF Control Panel 1 w I, EQUIPMENT LOCATION N Diesel Generator and associated switchgear SSF Diesel starting 24-Volt battery bank and charger SSF Standoy makeup pump and water supply Containment / Spent Fuel Pool 250/125 V battery bank, associated charger, and associated swithchgear SSF Steam Turbine Driven Auxiliary Feedwater Pump Auxiliary Building Solenoid "C" to valve SA 48 ABC Interior Doghouse

  • Capable of being connected at SSF Control Panel.

w. p-i TABLE 4.7-2 STANDBY SHUTDOWN SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS I INSTRUMENT CHANNEL CHECK CHANNEL CALIBRATION Reactor Coolant Pressure M R Pressurizer Level M R . Steam Generator Level M R .Incore Temperature M R Standby Makeup Pump Flow N/A R i i i. l l l CATAWBA - UNITS 1 and 2 3/4 7-43 L L 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION LIMITING CONDITION FOR OPERATION l 3.9.1 The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met either: A K,77 of 0.95 or less, or a. b. A boron concentration of greater than or equal to 2000 ppm. APPLICABILITY: MODE 6.* ACTION: With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or its equivalent until K is reduced to less than or equal to 0.95 or the boron concentration is r$Nored to greater than or equal to 2000 ppm, whichever is the more restrictive. SURVEILLANCE REQUIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to: a. Removing or unbolting the reactor vessel head, and b. Withdrawal of any full-length control rod in excess of 3 feet from its fully inserted position within the reactor vessel. 4.9.1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis at least once per 72 hours. 4.9.1.3 Valves NV-231, NV-237, NV-240, NV-241, and NV-244 shall be verified closed and secured in position by mechanical stops or by removal of air or electrical power at least once per 31 days.

  • The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

CATAWBA - UNIIf1 A@-2 3/4 9-1 e REFUELING OPERATIONS SURVEILLANCE REQUIREMENTS (Continued) 4.9.4.2 The Reactor Building Containment Purge System shall be demonstrated OPERABLE: cAdon a. At least once per 31 days by initiating flow through the HEPA filters and i.... ' adsorbers and verifying that the system operates for at least 10 continuous hours with the heaters operating; carbon b. At least once per 18 months or @t( after any structural maintenance on the HEPA filter or " 1' adsorber housings, ^- (2) ';'.' - -3 ' '} ?!:b' ' {j ' ' ' ' ~ ~ 1) Verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedures guidance in Regula-tory Positions C.5.a, C.S.c, and C.5.d* of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 25,000 cfm 10% (both exhaust fans operating); 2) Verifying within 31 days after removal, that a laboratory analysis of a presentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revi-(( sion 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 iodide penetration of less than 6%; and 3) Verifying a system flow rate of 25,000 cfm i 10% (both exhaust fans operating) during system operation when tested in accordance with ANSI N510-1980. cubon After every 720 hours of **em!we4 adsorber operation, by verifying, c. within 31 days after removal, that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position 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 iodide penetration of less than 6%; I d. At least once per 18 months by: -Cohon 1) Verifying that the pressure drop across the combined HEPA fil-ters, t.;--' adsorber banks, and prefilters is less than 8 inches Water Gauge while operating the system at a flow rate of 25,000 cfm i 10% (both exhaust fans operating); and EMN - 7[ - m;. mms muown m. m a a

u. a pga _= g D

~ .m. 5 . MMir! Wmmi; N iv. l i., wi t r. ne m., 4 ,m nf., ym... vo m CATAWBA - UNIlf1 MD z 3/4 9-5 t i ] l REFUELING OPERATIONS i SURVEILLANCE REQUIREMENTS (Continued) 2) Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accor-dance with Regulatory Positions 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 iodide penetration of less than 1%; and 3 3,13 o 3) Verifying a system flow rate of.5GgSSS:cfm i 10% during system operation when tested in accordance with ANSI N510-1980. CorNon After every 720 hours of e$wevet adsorber operation in any train by c. verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regula-tory Position 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 iodide penetration of less than 1%. d. At least once per 18 months for each train by: I(k cacbon 1) Verifying that the pressure drop across the combined HEPA

filters, adsorber banks, and moistere separators is less than 8 inches Water Gauge while operating the system at a flow rate of 16,565 cfm i 10%

g 2) Verifying that the system maintains the spent fuel storage pool area at a negative pressure of greater than or equal to inch Water Gauge relative to the outside amosphere during system operation, 3) Verifying that the filter cooling bypass valves can be manually opened, and 4) Verifying that the heaters dissipate 8018 kW.. D t::td i+ _--_ ~____ ...-----_7 any sbb Aab*ENNhNu h "5I"3,oe Ar e. Aftergeach complete or partial replacement of a HEPA filter bank in any train, by verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% in accordance with ANSI N510-1980 for a 00P test aerosol while operating the rate of 16,565 cfm i 10%; and anj druciumi maMenees on h hs stem at a flofter b ee ba er hous/y f e a carfo P n f. After/eachcompleteorpartiaTreplacementofacrxSadsorber bank in any train, by verifying that the cleanup system satisfies the in place penetration and bypass leakage testing acceptance criteria [ of less than 1% in accordance with ANSI N510-1980 for a halogenated ( hydrocarbon refrigerant test gas while operating the system at a flow rate of 16,565 cfm i 10% and f CATAWBA - UNITS 1 An z. P" 3/4 9-15 Srp.S This speikcaben d3limles -lAe appliaO/ ofeach spei$ca/su f h ad1 ad 41/z opedon. APPLICABILITY BASES met without regard for allowable deviations and out-of-service provisions contained in the ACTION statements. The intent of this provision is to ensure that facility operation is not initiated with either required equipment or systems inoperable or other speci-fled limits being exceeded. Exceptions to this provision have been provided for a limited number of specifications when STARTUP with inoperable equipment would not affect plant safety. These exceptions are stated in the ACTION statements of the appropriate specifications. 4.0.1 This specification provides that surveillance activities necessary to ensure the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL MODES or other conditions for which the Limiting Condi-tions for Operation are applicable. Provisions for additional' surveillance activities to be performed without regard to the applicable OPERATIONAL MODES or other conditions are provided in the individual Surveillance Requirements. Surveillance Requirements for Special Test Exceptions need only be performed when the Special Test Exception is being utilized as an exception to an individual specification. 4.0.2 The provisions of this specification provide allowable tolerances for performing surveillance activities beyond those specified in the nominal surveillance interval. These tolerances are necessary to provide operational flexibility because of scheduling and performance considerations. The phrase "at least" associated with a surveillance frequency does not negate this allowable tolerance value and permits the performance of more frequent surveillance activities. The tolerance values, taken either individually or consecutively over three test intervals, are sufficiently restrictive to ensure that the reliability associated with the surveillance activity is not significantly degraded beyond that obtained from the nominal specified interval. 4.0.3 The provisions of this specification set forth the criteria for determination of compliance with the OPERABILITY requirements of the Limiting Conditions for Operation. Under this criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified time interval. Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the Surveillance Requirements. Items may be determined inoperable during use, during surveillance tests, or in accordance with this specification. Therefore, ACTION statements are entered.when the Surveillance Requirements should have been performed rather than at the time it is discovered that the tests were not performed. l CATAWBA - UNITfl # o r-B 3/4 0-2 l o W REACTOR COOLANT SYSTEM 5 't BASES %e g SAFETY VALVES (Continued) %u relief capability and will prevent overpressurization. In addition, the Overpressure Protection System provides a diverse means of protection against Q g overpressurization at low temperatures. O Q~ 9, h prevent the Reactor Coolant System from being pressurized above D(f gE n, Limit of 2735 psig. The combined relief capacity of all of these valves is fv% greater than the maximum surge rate resulting from a complete loss-of-load U 4 assuming no Reactor trip until the first Reactor Trip System Trip Setpoint is N D reached (i.e., no credit is taken for a direct Reactor trip on the loss-of-load) \\ and also assuming no operation of the power-operated relief valves or steam 3 t dump valves. 4 * -e ] $ =_ Demonstration of the safety valves' lif t settings will occur only during 2 4 0 shutdown and will be performed in accordance with the provisions of Section XI g y of the ASME Boiler and Pressure Code. K 3/4.4.3 PRESSURIZER N *t th The limit on the maximum water volume in the pressurizer assures that the tq g parameter is maintained within the normal steady-state envelope of operation ) g assumed in the SAR. The limit is consistent with the initial SAR assumptions. ) g The 12-hour periodic surveillance is sufficient to ensure that the parameter % is restored to within its limit following expected transient operation. The Yw" maximum water volume also ensures that a steam bubble is formed and thus the x D Reactor Coolant System is not a hydraulically solid system. The requirement that a minimum number of pressurizer heaters be OPERABLE enhances the capability u w 3 $ of the plant to control Rea: tor Coolant System pressure and establish natural 8: b 1 circulation, wA hh[3/4.4.4 RELIEF VALVES wq hw The power-operated relief valves (PORVs) and steam bubble function to relieve Reactor Coolant System pressure during all design transients up to and u3 including the design step load decrease with steam dump. Operation of the Ys % PORVs minimizes the undesirable opening of the spring-loaded pressurizer Code i g $ safety valves. Each PORV has a remotely operated block valve to provide a , q -e. positive shutoff capability should a relief valve become inoperable. g g 3/4.4.5 STEAM GENERATORS D+ ensure that the structural integrity of this portion of the Reactor Coolant The Surveillance Requirements for inspection of the steam generator tubes System will be maintained. The program for inservice inspection of steam 5 generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1. l 4 Inservice inspection of steam generator tubing is essential in order to main-ne tain surveillance of the conditions of the tubes in the event that there is ) evidence of mechanical damage or progressive degradation due to design, manu-J CATAWBA - UNIIf1AND z. B 3/4 4-2 I o PLANT SYSTEMS BASES 3/4.7.13 STANDBY SHUTDOWN SYSTEM TheStandbyShutdownSystem(SSS)isdesignedtomitigatetheconsequences of certain postulated fire incidents by providing capability to maintain HOT STANDBY conditions and by controlling and monitoring vital systems from locations external to the main control room. This capability is consistent with the requirements of 10 CFR Part 50, Appendix R. The Surveillance Requirements ensure that the SSS systems and components are capable of performing their intended functions. The required level in the SSS diesel generator fuel storage tank ensures sufficient fuel for 72 hours uninterrupted operation. It is assumed that, within 72 hours, either offsite power can be restored or additional fuel can be added to the storage tank. Altnough the Standby Makeup Pump is not nuclear safety-related and was not designed according to ASME code requirements, it is tested quarterly to ensure its OPERABILITY. The Surveillance Requirement concerning the Standby Makeup Pump water supply ensures that an adequate water volume is available to supply the pump continuously for 72 hours. The equivalent shutdown capability provided when the SSS is inoperable depends on the specific equipment involved and, therefore, should be sufficient to assure that the intended shutdown actions can be accomplished, or that fires can be reasonably precluded during that time for which SSS equipment would otherwise be required, consistent with the SSS design basis. Any temporary procedures or special fire watch patrols established to provide this equivalent capability shall be reviewed and approved prior to implementation in accordance with Section 6.0 of the Technical Specifications. CATAWBA - UNITS 1 and 2 B 3/4 7-8 L 4,,IQ.5 Eecot'ds oF Q J Aaswanca activilies eegweed G -Me Ore ~ lod GuaN Assur31ce Martaa{ s l{ Se rebd el Scr a period of kmc a s recsmmended 64 iwsz AMs.z.9-M74 ADMINISTRATIVE CONTROLS f RECORD RETENTION (Continued) l..% Records of secondary water sampling and water quality; and vn.% Records of analyses required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed. 6.11 RADIATION PROTECTION PROGRAM 6.11 Procedures for personnel radiation grotection shall be prepared consistent with the requirements of 10 CFR Part 20 arTd shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure. 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is equal to or less than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radiation penetrates shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation

g protection procedures (e.g., Health Physics Technician) or personnel continu-(

ously escorted by such individuals may be exempt from the RWP issuance require-ment during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mR/h, provided they are other-wise following plant radiation protection procedures for entry into such high radiation areas. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following: A radiation monitoring device which continuously indicates the a. radiation dose rate in the area; or b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been estab-lished and personnel have been made knowledgeable of them; or An individual qualified in radiation protection procedures with a c. radiation dose rate monitoring device, who is responsible for pro-viding positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Station Health Physicist in the RWP. CATAWBA - UNI 151AdA L 6-21}}

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