ML20054M874
| ML20054M874 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 06/28/1982 |
| From: | SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20054M869 | List: |
| References | |
| NUDOCS 8207150074 | |
| Download: ML20054M874 (104) | |
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ENCLOSUREil 4 l 1 - 1 i MARKED-UP PAGES 0F V. C. SUPMER, UNIT 1 i TECHNICAL SPECIFICATIONS, PR0OF AND REVIEW i i I f l i i 8207150074 820628 i I PDR ADOCK 05000395 i A PDR ._ _
,i
a 's i REACTIVITY CONTROL SYSTEMS
;j Fl_GW PATHS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.2 At least two of the following three baron injection flow paths shall be OPERABLE: 2
- a. The flow path from the boric acid tanks via a boric acid transfer puso or a gravity feed connection and a charging pump to the Reactor Coolant System. .
- b. Two flow paths from the refueling water storage tank via charging pumps to the Reactor Coolant System.
APPLICABILITY: MODES 1, 2, 3 and 4# ACTION: With only one of the above required boron infection flow paths to the Reactor Coolant System OPERA 8LE, restore at least two boron injection flow paths to the Reactor Coolant System to OPERA 8LE status within 72 hours or be in at least HOT STAN08Y and borated to a SHUTDOWN MARGIN equivalent to at least 2 percent delta k/k at 200*F within the next 6 hours; restore at least two J flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN
" within the next 30 hours. ,
SURVEILLANCE REQUIREMENTS 4 4.1.2.2 At least two of the above required flow paths shall be demonstrated ' OPERABLE: ;. L
- a. At least once per 31 days by verifying that each valve (manual, .!
,~ power operated or automatic) in the flow path that is not locked, ; sealed, or othenvise secured in position, is in its correct : position. f
- o. At least once per 18 months by verifying that the flow path required by Specification 3.1.2.2.a delivers at least 30 gpm to the Reactor l Coolant System. t
?!
I e . ( l g 340 f I s Only one baron injection flow path is required to be OPERABLE whenever the I.
/ temperature of one or more of the RCS' cold legs is less than or equal to D4*F. l 3 !
I t J . SUMMER -- UNIT 1 3/4 1-8 . MAR 3 1982
e os .,
.)
- REACTIVITY CONTROL SYSTEMS .
s i CHARGING DUMPS - OPERATING LIMITING CONDITION FOR OPfRATION
,3.1.2.4 At least two charging pumps shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4# . t ACTION: With only one charging pump OPERABLE, restore at least two charging pumps to OPERABLE status within 72 hours or be in at least HOT STAN08Y and borated to a - SHUTDOWN MARGIN equivalent to at least 2 percent delta k/k at 200*F within the l next 6 hours and in HOT SHUTDOWN within the following 6 hours; restore at least
; two charging pumps to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours.
l SURVEILLANCE REQUIREMENTS . 4.1.2.4.1 At least two charging pumps shall.ba demonstratea'0PERABLE by i verifying, on recirculation flow, a differential pressure across each pump of greater than or equal to 2472 psig is developed when tested pursuant to _ , Specification 4.0.5. ! 4.1.2.4.2 Allchargingpumps,excepttheaboverequirebOPERABLEpumps,shall j be demonstrated inoperable, at least once par ^31 days, whenever the tempera-l ture of one or more of the RCS cold legs.is less than or equal to 'F by - l verifying that the motor circuit breakers have been secured in th open position.
>Y A maximum of one. centrifugal charging pump shall be OPERABLE whenever the
'temoerature of cne or more of the RCS cold legs is less than or equal to gF. ,
43 , , _
^
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d SUN 9ER - UNIT 1 3/4 1-10 3P9 15 1982 J p
-t ;. u. - n - . - . . _ - __ _. - -- - _ -.... . -.__ .. - -.- - .._- -- _ . --
, e POWER OISTRIBUTION LIMITS 'f [ (, ,- l(( {[
3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FAu un LIMITING CONDITION FOR OPERATION 3.2.3 The combination of inoicated Reactor Coolant System (RCS) total flow : rata and R 3, R., shall be maintained within the region of allowable operation sho.,n en Figurt 3.2-3 for 3 loop operation. Where: H p# a* R ' 1 = 1.49 [1.0 + 0.2 (1.0 - P)] R)
- b. R 2 * [1-R8P(8U)]
g* p THERMAL POWER ,
, RATED THERMAL POWER
- d. h=MeasuredvaluesofFhobtainedbyusingthemovableincore F'
detectors to obtain a power distribution map. The measured ' values of F N shall be used to calculate R since Figure 3.2-3 includes measurement uncertainties of W for flow and 4% for incore measurement of Fh, and 3g[
- e. RBP (BU) = Ro.d Bow Penalty as a function of region average burnup as i shown in Figure 3.2-4, where a region is defined as those j~
assemblies with the same loading date (reloads) or enrichment , (first core). ; APPLICABILITY: MODE 1. I I ACTION: With the combination of RCS total flow rate and R), R 2 utside the region of acceptable operation shown on Figure 3.2-3: .. . ; i l a. Within 2 hours either: ' i
- 1. Restore the combination of RCS total flow rate and R , {
3 R t within the above limits, or ; 2
- 2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER .
and reduce the Power Range Neutron Flux - High trip setpoint to less tnan or equal to 55% of RATED THERMAL POWER within the next 4 hours.
/1 SUMMER - UNIT 1 3/4 2-8 !
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taeuiuw ndmoscou i I i 1 i I SUMMER - UNIT 1 3/4 2-11 1
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*'/ TABLE 4.3-1 (Continued)
TABL8! NOTATION y
* - With the reactor trip system breakers closed and the control rod drive systas capable of rod withdrawal.
t
# - Below P-6 (Intarmeffata Range Neutron Flux Interlock) setpoint.
M# - Below P-10 (Low Setpoint Power Range Neutron Flux Interlock setpoint. (1) - If not performed in previous 7 days.
*tuelt Cseques.Las chasasenw,above To tytse.G MAf toD'UrHA 15% of RATED THERMAL POWER. Adjustachannelgains, (2) - " :t M r..... oc.'.f, t.aceans.nwnscM awarti<tdif absoluta difference, greater than 2 percent.%c rwis;. s.4 Spac,##cAWMY.d./
D:- : incere to excore axial flux difference above 15%e of RATED }n 9.gg gO THERMAL POWER. Recalibrate the absolut diff is greater < 3than or equal to 3 percent. twA4 661au,wt 1 y , Neutron detectors may be excluded fres CHANNEL CALIBRATION. t. j' (4) - Detector plateau curves shall be obtained, evaluated and compared k 5 (5) T to manufacturer's data. For the Intarmodiata Range and Power Range h -- - Neutron Flux Channels the provisions of Specification 4.0.4 are not-applicable for entry into MODE 2 or 1.
+
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v (6) - Incore - Excore Calibration. h9 Each train shall be tested at least every 62 days on a STAGGERED TEST h (7) -
*3 (8) -
BASIS. With power greater than or equal to the interlock setpoint the required h{ N OPERATIONAL TEST shall consist of verifying that the interlock is in the . required state by observing the permissive annuciator window. I >$ - MW (9) - Monthly Surveillance in MODES 3*, 4" and 5" shall also include verification that permissives p-6 and P-10 are in their required stata for existing plant conditions by observation of the permissive annunciator window. (10) - Setpoint verification is not required.
~
(11) - At least once per 18 months and following maintenance or adjustment of the reactor trip breakers, the TRIP ACTUATING OEVICE OPERATIONAL TEST shall include an independent verification of the undervaltage and ._ shunt trips. 2 ' SUMMER - UNIT 1 3/43-1$ MR 3 582 5 e
o TABLE 3.3-3 (Continued)
; 50 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION c
5
-d MINIMUM TOTAL NO. CHANNELS CHANNELS APPLICABLE i
- FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
- f. Steam Line Pressure-Low 1 pressure / 1 pressure 1 pressure 1, 2, 3 19*
'l loop and 2 loops and 2 loops
, 2. REACTOR BUILDING SPRAY
- a. Manual 2 sets - 2 1 set 2 sets 1, 2, 3, 4 18 i switches / set 10 b. Automatic Actuation 2 1 2 1, 2, 3, 4 14
** Logic and Actuation
. i' Relays U
- c. Reactor Building 4 2 3 1, 2, 3 16
; Pressure--High-3 (Phase 'A' isolation aligns spray fee >'
system discharge valves and NaOH tank l suction valves) s 4e9
.d
<~
~ - . . I ..
~
E TABLE 3.3-3 (Continued) ENGINEERED SAFE 1Y f EAluRE ACluA110N SYSTEM INSTRUMENTAT10N m a C MININUM j'. CilANNELS APPLICABLE M TOTAL NO. CllANNELS 10 TRIP OPERABLE H00CS ACTION M FUNC110NAL UNIT OF CilANNELS
- 3. CONIAINHENT ISOLATION
- a. Phase "A" Isolation 2 1 2 1, 2, 3, 4 18
- 1) Manual
- 2) Safety injection See 1 above for all safety injection initiating functions and requirements.
- 3) Automatic Actuation ,
Logic and Actuation 1,2,3,4 14 Relays 2 1 2 i., 29 *^^? c^.'. O V ;
- b. Phase "B" Isolation 7 2 ! ? 1, 2, 3, 0 IS 5 <.. y r nu.v ~ 1,2,3,4 14 2
, \.1' 9.
J
.:f. % Automatic Actuation 2 1
$ Logic and Actuation Relays 2 3 1,2,3 16 AM Reactor Building Pressure--liigh-3 4
- c. Purge and Exhaust
? Isolation ,
-2 : 2 ; . 2, 3, t !?
-- 1 ) .t . - ?
1 1) Safety Injection See I above for all safety injection initiating functions and requirements. 2 3 1, 2, 3, 4 17 p W) Contalsment Radio- 4 activity- liigli is 3 y) Automatic Actuation 2 1 2 1,2,3,4 17
$ Logic and Actuation 8 Relays u
I O
,1
m j TABLE 3.3-4 m ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS E Total Q Functional Unit Allowance (TA) Z S_ Trip Setpoint Allowable Value
, 1. SAFETY INJECTION, REACTOR TRIP, FEE 0 WATER ISOLATION, CONTROL <
l R00H ISOLATION, START DIESEL f GENERATORS, CONTAINNENT COOLING FANS AND ESSENTIAL SERVICE WATER.
- a. Manual Initiation NA NA NA NA NA
- b. Automatic Actuation Logic NA NA NA NA NA w c. Reactor Building Pressure- 3.0 0.71 1.5 13.6 psig 13.86 psig
) High I
- d. Pressurizer Pressure--Low 13.1 10.71 1.5 11850 psig 11839 psig
- e. Differential Pressure 3.0 0.87 1.5/ 197 psig $106 psi Between Steamlines--High 1.5
- f. Steamline Pressure--Low 20.0 10.71 1.5 >675 psig
>635 psig II)
- 2. REACTOR BUILDING SPRAY
- a. M nual Initiation NA NA NA NA NA
- b. Automatic Actuation Logic NA NA NA NA NA and Actuation Relays
- c. Reactor Building Pressure- 3.0 0.71 1. 5 $12.05 psig 112.31 psig High 3 (Phase 'A' isolation aligns spray M system dis-y charge valves and NaOH tank suction valves)
= (1) Time constants utilized in lead lag controller for steamline pressure-low are as follows Q I 50 secs. T2
- 5 secs.
N A s i . fi . ,,
1
$ TABLE 3.3-4 (Continued)
E E ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS i e
' c Total
{ } Functional Unit Allowance (TA) Z S Trip Setpoint Allowable Value
- 3. CONTAINMENT ISOLATION
- a. Phase "A" Isolation
- 1. Nanual NA NA NA NA NA
- 2. Safety Injection See 1 above for all safety injection setpoints and allowable values i
; 3. Automatic Actuation Logic NA NA NA NA NA and Actuation Relays I
- b. Phase "B" Isolation
-1. --l%,. .! un "^
. Ha nn ;M 1 g f. Automatic Actuation NA NA NA NA NA to Logic and Actuation ej Relays p)l. Reactor Building 3.0 0.71 1. 5 512.05 psig 112.31 psig Pressure-liigh 3
- c. Purge and Exhaust Isolation
- 1. thr.a; ua NA un un u, m, 1K Safety Injection See 1 above for all safety injection setpoints and allowable values g )$. Containment Radioactivity NA NA NA 2X Background 2X Background High 3f. Automatic Actuation NA NA NA NA NA Logic and Actuation Relays 4 -
r-* tD rb
g TABLE 3.3-4 (Continued) ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS Total E Functional Unit Allowance (TA) Z_ S Trip Setpoint Allowable Value w
- 4. STEAM LINE ISOLATION
- a. Manual NA NA NA NA NA
- b. Automatic Actuation Logic NA NA NA NA NA and Actuation Relays
- c. Reactor Building Pressure- 3.0 0.71 1.5 -<6.35 -<6.61 High 2
- d. Steam Flow in Two Steamlines- 20.0 13.16 1.5/ < a function < a function defined High, Coincident with 1.5 3efined as as follows: A ap follows: A AP corresponding to 44%
4* corresponding of full steam flow to 40% of full between 0% and 20% Y steam flow load and then a ap O between 0% and increasing linearly i 20% load and to a op corre-t then a ap sponding to 114.0% 8 increasing of full steam i linearly to a flow at full load. op correspond-ing to 110% of full steam flow at full load Tavg - Low-Low 4.0 1.12 0.2 1553*F 1550.5*F 1635 psig II)
- e. Steamline Pressure - Low 20.0 10.71 1.5 1675 psig m (1) Time constants utilized in lead lag controller for steamline pressure low are as follows:
l R Ti 50 secs. T2 g# 5 secs. l e-. I w >, N a j ..
i TABLE 3.3-4 (Continued) m
' " . ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS i e E Total Q Functional Unit Allowance (TA) 7, S Trip Setpoint Allowable Value f e. Safety Injection See 1 above (all SI Setpoints) . g. Trips of Hain Feedwater NA NA NA NA NA Pumps i y l h. Suction transfer on Low NA NA NA 1442 f t. 41n.(2) 2441 f t. $ in. 4 Pressure
- 7. LOSS OF POWER w a. 7.2 kv Emergency Bus NA NA NA >5760 volts with >5652 volts with a
) Undervoltage (Loss of a 10.25 second 50.275secondtime w Voltage) time delay delay A
F b. 7.2 kv Emergency Bus NA ,NA NA 16576 volts 16511 volts with a Undervoltage with a 13.0 13.3 second time
. second time delay i i
delay ' i
- 8. AUTOMATIC SWITCHOVER TO -
CONTAINMENT SUMP i
- a. RWST Level Low-Low NA NA NA 118% 115%
l b. Automatic Actuation Logic NA NA NA NA NA l
' and Actuation Relays 1
4 l 4 (2) Pump suction head at which transfer is initiated is stated in effective water elevation in the ;
~ condensate storage tank. l w
43 g 1_ .m.... . . : . . _
.T . . . _.
INSTRUMENTATION TABLE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION . RESPONSE TIME IN SECONOS .
- 1. Manual
- a. Safety Injection (ECCS) Not Applicable
- b. Reactor Building Spray Not Applicable
- c. Containment Isolation Phase "A" Isolation Not Applicable
- N .
0"*r M L...uu iso sation - M /pp':d%
- d. Steam Line Isolation Not Applicable
- e. Feedwater Isolation Not Applicable
- f. Emergency Feedwater Not Applicable
- g. Essential Service Water Not Applicable
- h. Reactor Building Cooling Fans Not Applicable
- i. Control Room Isolation Not Applicable
- 2. Reactor Building Pressure-High
- a. Safety Injection (ECCS) 5,12(2)/27(1)
- b. Reactor Trip (from SI) 5, 3. 0
- c. Feedwater Isolation < 10.0
- d. Containment Isolation-Phase "A" 5,45.0(4)/55.0(5)
SUMMER - UNIT 1 - 3/4 3-29 APR 151982 i
~~.
1 i
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. ( ,, '.i i
$ IABIE 4.3-2 (Continued) ,
E Q) ENGINEERLil SAFETY FEAIURE ACTUATIDN SYSTEM INSIRUMENIATION ,
. SURVEltlANCE REQulREMENTS E TRIP t1 H0 DES FOR g ANALOG ACIDAllNG CilANNEL DEVICE MASTER SLAVE WillCil OPERATIONAL OPERATIONAL ACIUATION RELAY RELAY SURVEILLANCE CilANNEL CilANNEL CllECK CAllBRATION TEST TEST LOGIC IEST TEST TEST IS REQUIRED ,
FUNC110NAL UNIT
- 3. CONIAINHENI ISOLATION
- a. Phase "A" Isolation N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3, 4
- 1) Manual
- 2) Safety injection See 1 above for all Safety injection Surveillance Requirements
- 3) Automatic Actuatico N.A. N.A. N.A. N.A. M(1) M(!) Q 1, 2, 3, 4 .
ti Logic and Actuation 4
- Relays w
J, b. Phase "B" Isolation " m
-1, lL a:! M^ M .". . M.* M P^ M . .^ M . ^. I , 2, 3 '
] 1, 2, 3, 4 t ;i]El Automatic Actuation N.A. N.A. N.A. N.A. M(1) M(1) Q
- Logic and Actuation .
Relays H N.A. N.A. N.A. N.A. 1, 2, 3 g)() m Reactor Building S R Pressure--Illuh-llluh-liloh
- c. Purae and Exhaust isolation 3, 1) Automatic Actuation H.A. N.A. N.A. N.A. H(1) H(1) Q 1, 2, 3, 4 gg Logic and Actuation Relays 62
- 2) Containment Radio- S R H N.A. N.A. N.A. N.A. 1, 2, 3, 4 gj activity-liioh
- 3) Safety injection See 1 above for all Safety injection Survelliance Requirements.
o,
. i )
( ' ,,
. ~ .
I , E TABLE 3.3-10 (Continued) I i ACCIDENT HONITORING INSIRilHENIATION
, 9 ;
c HINIMUM 10TAL 3 H OF filANNELS I i
" CilANNELS OPERABLE INSTRIMENI i
Reactor Building HilR Sump Level 2 1 13. Reactor Building Level 2 1 14. Condensate Storage Tank Level 2 1 15. 4 '
- 16. Reactor Building Cooling unit Service Water Flow 2 1 I
- 17. Service Water Temperature-Reactor Building Cooling Unit 2 pairs 1 pair 4:' ' (Inlet and Discliarge)
Haeli Storage Tank Level 2 1 Y 18. I E 2
- 19. Reactor Coolant System Subcooling Margin Monitor 1
- 20. N Position Indicator 2/ valve" 1/ valve"
. 21 ORNiockValvePositionIndicator 1/ valve 1/ valve
!' k~cace- s s g . . - e.r.cr
- 22. ASafety Valve .^. : e= _4.c_.us .. K valve 1/ valve
- 23. In-Core Thermocouples 4/ core 2/ core
' quadrant quadrant
- 24. Reactor Vessel level 2 1 l
- o u a .
g Not required when the associated block valve is closed per Specification 3.4.4. {0 9 l
i
) ,
E TABLE 4.3-7 (continued) f zu ACCIDENT HONITORING INSTRUMENTAll0N SURVEIll ANCE REQUIREMENTS e C CilANNEL CilANNEL
$ CliECK CALIBRATION INSTRUMENT H H
- 12. Reactor Building Temperature l
H R
- 13. Reactor Building HilR Sump Level H R
- 14. Reactor Building level H R
- 15. Condensate Storage Tank Level .
Reactor Building Cooling Unit. Service H R ,
- 16. .
Water flow ,
% H R*
** 17. Service Water Temperature - Reactor Building
't Cooling Unit. (Inlet and Discharge) o R H
- 18. Na0ll Stora0e lank Level i M R
! 19. Reactor Coolant System Subcooling Margin Monitor
\ Senuestet. H* R"
- 20. TOHV Positton Indicator Gesset,ast_
l, 21. APORV Block Valve Position Indicator M R H R
. 22. W e alve Ac W ! I ^ ! e In-Core Thermocouples H R 23.
N N R M 24. Reactor Vessel Level u (O A g Not required when the associated block valve is closed per Specification 3.4.4.
' i i
- I. .
l* 'N-
)
- e i
E TABLE 3.3-12 lk x s RADI0 ACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION 4 U HINIMUM d CilANNELS DPERABLE ACTION i P' INSTRUMENT ?
- l. GROSS RADIDACTIVITY MONITORS PROVIDING ALARH AND AUTDMATIC I TERMINATION OF RELEASE t 36
- a. Liquid Radwaste Ef fluent Lipe - RH-LS or RH L9 1 32 1 '
Nuclear (Processed Steam Generator) Blowdowa Effluent [ M ~l. 7 "b. c. Lin#'llM=&f. or inHb=& RM-Li Steam Generator Blowdown Effluent Line 1 32
- 1. Unprocessed during Power Operation - RH-LIO or RM-L3 .
1 32
, . .{ , .
- 2. Unprocessed during Startup - RM-L3 Turbine Building Sump Effluent Line - RM-L8 1 33 Y d.
1
~,, 2. FLOW RATE HEASUREMENT DEVICES ^
1/ tank 34
- a. Liquid Radwaste Effluent Line - Tanks 1 and 2 34 i l
- b. Penstocks Minimus Flow Interlock ^^ 34
- c. C:,: den;;i " _!acr:1!: r Eff!eent L!ee 1 1 34 c,ak Nuclear Blowdown Effluent Line j o(,,ef Steam Generator (Unprocessed) Blowdown Effluent Line j
- 3. TANK LEVEL INDICATING DEVICES Condensate Storage' Tank 1 35 ,
- a. .
I
= l
'" ~3 Flow rate for the monitor RH-L9 is determined by adding flow rates for monitors RN-LS and RM-L7.
,, j^^Hinimum dilution flow is assured by an interlock terminating liquid waste releases if minimum dilution flow is not available.
Ml ro . <Ja_. * .
l
)
.. i
__ _. _ _ _ . .~__
=
l INSTRUMENTATION TA8LE 3.3-12 (Continued) TABLE NOTATION ACTION 31 - With the number of channels OPERA 8LE less than required by the Minimum Channels OPERA 8LE requirement, effluent releases may continue for up to 14 days provided that prior to initiating i a release:
- a. 'At least two independent samples are analyzed in accordance with Specification 4.ll.1;1:3 rand
- b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations ,
and discharge line valving; Othenvise, suspend release of radioactive effluents via this pathway.
- ACTION 32 - With the number of channels OPERA 8LE less than required by the Minimus Channels OPERA 8LE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for gross radioactivity (beta and gamma) at a limit of detection of at least 10 7 sicrocuries/ gram:
- a. At least once per 8 hours when t specific activity of l the secondary coolant is greater than 0.01 microcuries/ gram DOSE EQUIVALENT I-131.
- b. At least once per 24- hours when the specific activity of I the secondary coolant is less than or equal to 0.01 micro-curies / gram DOSE EQUIVALENT I-131.
~
ACTION 33 - With the number of channels OPERA 8LE less than required by the ~ Minimum Channels OPERA 8LE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 8 hours, grab samples.are collected and analyzed for gross radioactivity (beta and gamma) at a limit of detection of at least 10 7 microcuries/ gram. With the number of channels OPERA 8LE less than required by the h ACTION 34 - Minimum Channels OPERA 8LE requirement, effluent releases via [p thi:t pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours during actual releases. Pump curves may be used to estimate flow.
~
,l ACTION 35 - With ther number of channels.0PERABLE less than required by the Minimum Channels OPERA 8LE requirement, liquid additions to this
- tank may continue for upr to 30 days. provided the tank liquid I Jg level is estimated during all liquid additions to the tank to k prevent overflow. . .
SUMMER - UNIT 1 .
.'3/4f3-69 MAR 3 11!82
. l.
TA8LE 3.3-12 (continued) TA8LE NOTATION ACT Oil 6- ' ith th er of channels OPERABLE less than re utred by the Channels OPERA 8LE requirement, efflugnt ases may c t(nue for up to 14 days pro ided guid Wilst ffluent Mon RM-L9 is OPEAA8LE'or rior initidti 'a release: . i
- a. NA(least tw independent samples a analyzed in ecificaf. ion 4.!'.I.1.3, and accendanca with
- b. Atk'en two ni ily qualified f members of the facility staff independedly verffy the release rate calculations'and discharge e. valving.
Otherwise, suspend reTease N N radioactive effluents via this pathway.
/
f LE less than required by the p\ 3 th the number of channels OPE ' inum Channels OPERABLE reqbicement, effluent releases via thts, pathway may continue for A to M days provided Liquid Waste Effluent Monitor RM-L9 OPERAELE or grab samples are analyzed for gross radioacti tyi(bata a d gamma) at a limit of detection of at least 10 7 picrocurie :
/ .
- a. At least once per 8. hours when the' s acific activity of the secondary coolant is greater n 0.01 microcuries/gn DOSE EQUIVALENT I- \
- b. At least once per 24 hours when the specific gravity of the secondary coolant is less than or al to k 0.01 mic ' curds /gm 005E EQUIVALENT I-131. -
I
- f *
, ._d -! - b A. . 0 ~ M--
Y?? V i
-- l t~
'/~ 'l l
j / ll -
,,;7s3 7;-
hl O W . Nhb __ l
)
. e.1 ( M 3 1982 SUteER - UNIT'1 3/4:3'70. i
s , i l
'^ TABLE 4.3-8 3
$ RADIDACTIVE LIQUID EFFLUENT HONITORING~INSTRUMENTAI10N SURVEltlANCE REQUIREHENTS !
C ANALOG CilANNEL 5'i SOURCE CilANNEL OPERATIONAL H CilANNEL CiiECK CALIBRATION TEST H CllECK INSTRUMENT
- 1. GROSS BETA DR GAMHA RADIDACTIVITY HONIIORS PROVIDlHG ALARH AND AUTOMATIC TERMINATION OF RELEASE
- a. Liquid Radwaste Effluent Line - RM-LS, RM-L9 D P R(3) Q(1)
P R(3) 40) l
- h. Nuclear Blowdown Etfluent Line - RH-L7M D D H R(3) Q(1)
- c. Steam Generator Blowdown Effluent Line'-
R RM .3, RM-LIO e !
- d. Turbine Building Scap-
'/ .. D H R(3) Q(1)
I p , Effluent Line - RH-LB
- 2. FLOW RATE HEASUREMENT DEVICES
- a. Liquid Radwaste Effluent Line - 0(4) N.A. R Q y-, . . . _ ,g
- b. Penstocks Minimum Flo3 Interlock ' D(4) N.A. R Q l
DM) MM. - - y-' c-tmTGe..e. ele Oc ineralizur Ef f hant Lbc , D(4) N.A. R- Q l C 4 Nuclear Blowdown Effluent Line b . Steam Generator Blowdown D(4) H.A. R Q 5 Etfluent Line - RH-L3, RH-L7, NH-L10 ;
- 3. TANK LEVEL INDICATING DEVICES ;
- a. Condensate: Storage Ianks D N.A. R l Q id
! i I
! t l
i '- i i! - -
s
' ~' .
- I TABLE 3.3-13 l E
4
$ RADIDACTIVE GASEQUS EFFlufMI HONITORING INSTRUMENTATION C ;
HINIMUM CilANNELS {- g INSTRUMENT OPERABLE APPLICABILITY;, ACTION. .
! f
- 1. WASTE GAS 110LDUP SYSTEM
- a. Noble Gas Activity Honitor - Providing .
* ;38 Alarm and Automatic Termination of Release 1 ,
i RM-A10 or RM-A3 i
- 2. WASTE GAS It0LDUP SYSTEH EXPLOSIVE GAS
- HONITC;;;NG SYSTEM i
** 2 44 f
- a. Oxygen Honitor/Recombiner . 2 k' ^^ 42 ;
- b. Ilydrogen Monitor /Recombiner 1
[e. ! y 3. MAIN PLANT VENT EXilAUST SYSTEM
- a. Noble Gas Activity Manitor - Providing *
' 40
- Alata and Automatic Termination of 1 Release from Wasta Gas ibidup System kH-A3 l" ' 43 l* *
- b. Iodine Sampler 1 ,
- c. Particulate Sampler 1
^ ! Kh
^ 39
- d. Flow Rate Heasuring Device 1 a: ^ 39
$ e. Sampler Flow Rate Heasuring Device 1 b
4Y) 4 O g
TABLE 4.3-9 (Continued) RADI0 ACTIVE GASEQUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS i b H ANALOG CHANNEL MODES IN WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE H INSTRUMENT CHECK CHECK CALIBRATION TEST REQUIRED
- 3. MAIN PLANT VENT EXHAUST SYSTEM
+
! a. Noble Gas Activity Monitor -
i RM-A3
- D M R(3) Q(2)
- b. Iodine Sampler W N.A. N.A. N.A. *
- c. Particulate Sampler W N.A. N.A. N.A.
- y d. Flow Rate Measuring Device D N.A. R Q
^
T e. Sampler Flow Rate Monitor D N.A. R Q l $
! 4. REACTOR BUILDING PURGE SYSTEM
- a. Noble Gas Activity Monitor - D P,M R(3) Q(1)
RM-A4
- b. Iodine Sampler W N.A. N.A. N.A. *
- c. Particulate Sampler W N.A. N.A. N.A. *
, d. Flow Rate Measuring Device D N.A. R T *
- e. Sampler Flow Rate Monitor D N.A. R A
- E-<
LD N .
. a
~
REACTOR COOLANT SYSTEM HOT SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.1.3 At least two of the Reactor- Coolant and/or residual heat removal (RHR) loops listed below shall be OPERA 8LE and at least one of these Reactor Coolant and/or RHR loops shall be in operation.** e I a. Reactor Coolant Loop A and its associated steam generator and Reactor Coolant pump,"
- b. Reactor Coolant Loop 8 and its associated steam generator and Reactor Coolant pump,*
- c. Reactor Coolant Loop C and its associated steam generator and Reactor Coolant pump,"
- d. Residual Heat Removal Loop A,
- e. Residual Heat Removal Loop S, APPLICABILITY: MODE 4 ACTION:
- a. With less than the above required Reactor Coolant and/or RHR loops OPERABLE, immediately initiate corrective action to return the required loops to CPERABLE status as soon as possible; if the remaining OPERABLE loop is an RHR loop, be in COLD SHUTDOWN within 24 hours.
- b. With no Reactor Coolant or RHR loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation. ;
Sw*F i - A Reactor Coolant puso shall not be started with one or more of the Reactor F unless Coolant System cold leg temocratures less than or equal to %a*nd/or 2) the
- 1) the cressurizer water volume is less than 1288 cuoic feet secondary water temoerature of each steam generator is less than 50*F
! above each of the RCS cold leg temperatures. ! == All Reactor Coolant pumps and decay heat removal pumos may be de-energized l for up to 1 hour provided 1) no operations are permitted that would causa dilution of the Reactor Coolant System boren concentration, and 2) core outlet temoerature is maintained at least 10*F below saturation temperature. 1 MAR J 7932 SUMMER - CNIT 1 3/a 4-3 i
l REACTOR COOLANT SYSTEM COLD SHUTOOWN - 1.00PS FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4 At least one residual heat removal (RHR) loops shall be OPERA 8LE and in operation *, and either:
- a. One additional RHR loop shall be OPERA 8LE , or g
- b. The secondary side water level of at least two steam generators shall be greater than 10 percent of wide range indication.
APPLICA8ILITY: MODE 5 with Reactor Coolant loops filled . ACTION:
- a. 'dith less than the above required loops OPERA 8LE and/or with less than the required steam generator level, immediately initiate corrective action to return the required 1 cops to OPERA 8LE status or to restore the required level as soon i
as possible.
- b. 'dith no residual heat removal loop in operation, suspend all operations involving a reduction in boron concen- .
tration of the Reactor Coolant System and immediately initiata corrective action to return the required residual hect removal loop to operation. SURVEILLANCE REQUIREMENTS 4.4.1.4.1.1 The secondary side water level of at least two steam generators , wnen required shall be determined to be within limits at least once per 12 hours. I 4.4.1.4.1.2 At least one RHR loop shall be determined to be in operation and circulating reactor coolant at least once per 12 hours. -
#0ne residual heat removal loop may be inoperable for up to 2 hours for surveillance testing provided the other RHR loop is OPERA 8LE and in .
operation. l 3ba "A Reactor Coolant pump shall not be started with one or mo of the Reactor Coolant System cold leg temoeratures less than or equal to 'F unless
- 1) the pressurizer water volume is less than 1288 cuoic feet and/or 2) the secondary water temperature of each steam generator is less than 50*F above each of the Reactor Coolant System cold leg temperatures.
The RHR pump may be de-energized for up to 1 hour provided 1) no operations are permitted that would cause dilution of the Reactor Coolant System baron concentration, and 2) core outlet temoerature is maintained at least 10*F below saturation temoerature. 3/4 4-5 E "~l SUMMER - UNIT 1
- 8 REACTOR COOLANT SYSTEM 3/4.4.3 PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.3 The pressurizer shall be OPERABLE with a water volume of less than or equal to 1288 cubic feet, (92% of indicated. span) and at least two groups of a pressurizer heaters each having a capacity of at least 125 kw.
APPLICA8ILITY: MODES 1, 2 and 3 ACTION:
- a. With one group of pressurizer heaters inoperable, restore at least two groups to OPERABLE status within 72 hours or be in at least HOT STANDBY within the next 6 hours and in HOT SHUTDOWN within the following 6 hours.
- b. With the pressurizer otherwise inoperable, be in at least HOT STANDBY -
with the reactor trip breakers open within 6 hours and in HOT SHUTDOWN within the following 6 hours. I SURVEILLANCE REOUIREMENTS 4.4.3.1 The pressurizer water volume shall be determined to be within its . limit at least once per 12 hours. - 4.4.3.2 The capacity of each of the above required groups of pressurizer l heaters snall be verified by energizing the heaters and measuring circuit ' current at least once per 92 da s. MP% fe49 4 pb 4.4.3.3 Thenpre su7izer heaters hall be demonstrated OPERABLE at least once per 18 months by manually j energizing the heaters. T* a (ow4.JL b & 4-*f.A. y pM l l [ 3/4 4-9
" 'I " 02 .
SUMMER - UNIT 1
l REACTOR COOLANT SYSTEM 3/4.4.9 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPEFATION 3.4.9.1 The Reactor Coolant System (except the pressurizer) temperature and ' pressure shall be limited in accordance with the limit lines shown on i Figures 3.4-2 and 3.4-3 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with;
- a. A maximum heatup of 100*F in any one hour period,
- b. A maximum cooldown of 100*F in any one hour period, and
- c. A maximum temperature change of less than or equal to 10*F in any one hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.
APPLICABILITY: At all times. ACTION: With any of the above limits exceeded, restore the temperature and/or pressure [ to within the limit within 30 minutes; perform an engineering evaluation to l determine the effects of the out-of-limit condition on the fracture toughness l properties of the Reactor Coolant System; determine that the Reactor Coolant l System remains acceptable for continued operation or be in at least HOT STANOBY , and pressure to less than withinthenext6hoursandreducetheRCST*V811owing30 200*F and 500 psig, respectively, within the hours. ._. SURVEILLANCE REQUIREMENTS 4.4.9.1.1 The Reactor Coolant System temperature and pressure shall be - determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations. 4.4.9.1.2 The reactor vessel material irradiation surveillance specimens shall be removed and examined, to determine changes in material properties, at the intervals required by 10 CFR 50, Appendix H in accordance with the schedule in Table 4.4-5. The results of these examinations shall be used to update Figures 3.4-2 and 3.4-3,4.3,4-y _/ APR 151982 SUMMER - UNIT 1 3/4 4-29
REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following overpressure protection systems shall
- be OPERABLE:
- a. Two power operated relief valves (PORVs) with a lift setting of less .
tgn e ual to :% ;;;i;;, r -tLa ef _a uf"f -k hM
~
- b. The Reactor Coolant System (RCS) depressurized with an RCS vent of greater than or equal to 2.7 square inches.
APDLICABILIW: MODE 4 when the temperature of any RCS cold leg is less than or equal to A *F,,, MODE 5, and MODE 6 with the reactor vessel head on. 5eo *r- - ACTION:
. With '
PORV operab , restore the i erabi PORV + OPE E ta swit 'n 7 days r epr su ize nd en h R th ou at ext 8 . ours.
%] 1 st a i squ nch (s) in th t,u w ta y2 In the event either he PORV)( ;r th. %: :: :(,) .. r~d *a # + ' ;;:tr
* 'C: , . . . . . .r an= Fani. , a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 -- within 30 days. The recort shall describet then' -
'M
.s.. ;.( .,; er, th: tr;c.;.;c.t and l
*[2 tr:n;t-a* -- ":.. .' we ; RV. v.
any corrective action necessary to prevent recurrence. k,The provisions of Specification 3.0.4 are not applicable. i JV 1 w .gm .w. u a
% = *4 > % +L 6 &
aw. . s. w SUMMER - UNIT 1 3/4 4-34 32 l
(3 so, 3't 6 a)
..~. ,
3oao MRTEtt I AL, 3ACIS
- B =AcrCut YBs.:5L. TNTEM. Sh' ELL Cu .= aic wr v.
S s
.DvirinL RT,vo7 = 30*F RTao.,. nfrex to EfPY:
[ w ** v4 7 = 107'r . .s y 3M T - e.2 *f
.C
-i :
12,,o (z.ro, z. o ao) j
% i b- I cc .
O ! 1500
/
f
,a-.. ~ ~
; ~(2.co,t.'Ic)
E
~g Icoo c
E (iro , 710) .
*E
( 70, ino) {r~.0,c,3o) 500 (t cc,57o) l 1 i- a 2oo
/To 00 150 300 so Ioo Ave -y a s% e.fa n C.ola.nt Syc +e m Lpea+ure(i=)
Fij a r e 3. 4 - + l RCS COLD OVERPR E SSllRI Z A TION PROTE C r/0N - I 2/Y- ? ~1SQ m
FMERGENCY CORE COOLING SYSTEMS 3/4.5.3 ECCS SUBSYSTEMS - T av3_ < 350*F LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsystem comprised of the following shall be OPERA 8LE: 1
- a. One OPERA 8LE centrifugal charging pump,#
- b. One OPERABLE residual heat removal heat exchanger,
~
- c. One OPERA 8LE residual heat removal pump, and
- d. An OPERABLE flow path capable of taking suction from the refueling water storage tank and capaele of being manually or automatically
! realigned to the suction to the RHR sumo during the recirculation phase of operation. APPLICABILITY: MODE 4. ACTION: I
~
- a. With no ECCS subsystem OPERA 8LE because of the inoperability of either the. centrifugal charging pump or. the' flow path from the refueling water storage tank, restore at least one ECCS-subsys+== ta OPERABLE status within 1 hour or be in COLD SHUTDOWN within the next 20 hours.
I ! b. With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS subsystem to OPERABLE status i or maintain the Reactor Coolant System T avg less than 350*F by use of alternate heat removal methods,
- c. In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describ- -
ing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected safety injection noIIIe snall be provided in this Special Aeport whenever its welve aceeds 0.70. o 306 f e A maximum of one centrifugal charging puso shall be OPERABLE whenever the temocrature of one or more of the RCS cold legs is less than or equal to )R(*F. l
.' C' te2 SUMMER - UNIT 1 3/4 5-7 4
a
-- -~. _- -. - - , -,. f -
l l EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REOUIREMENTS 4.5.3.1 The ECCS subsystem shall be demonstrated CPERA8LE per the applicable Surveillance Requirements of 4.5.2. 4.5.3.2 All charging pumps except the above required OPERA 8LE pumps, shall be - demonstrated inoperable at least once per 31 days whenever the temperature of
- one or more of the RCS cold legs is less than or equal to . by verifying that the motor circuit breakers have been secured in the pen position.
'3b6' f -
e
' ~ = - -
-....m...---
e
=
i 1 Y$ ,( ' '... . f SUMMER - UNIT 1 3/4 5-S l
} I
, /,
5
. ; , + I s '
CottrAINMENT SYSTDiS
\ ?
Cottr a c4ENT STRUCTURAL INTEGRITY" - LIMITNG CONDITIONS FOR OPERATION '
. . N
*3.5.1;6 The structural integrity of the contaf nment. shall be maintained at a leval consistent with the acceptance criteria in Specification 4.6.1.6.
APPLICABILITY: MODES 1, 2, 3 and 4.
- t' ACTION: s -
~
? ,
~' '
- a. With the serv.ctural' integrity of the conesimnc, not ccaforming to
; the requirements of Jpecification 4.6.1.6.1.b, perform an engineer-ing evaluation of the containment to demonstrate the acceptability
, of containment tandons virhin 72 hours;. otherwise... be in at least -
HCE STANDBY vithin the next 6 hours and in CCLD SHUTDOWN within the fol'.'owing 30 hours. s , s
- b. With the structural integrity of the contaf nment otherwise not, conforming to the requirements of Specification 4.6.1.6,,in lieu s
# of any other report required by Specification 6.9.r, prepara and xsubmit a Special Report to the Commission' pursuant to Spec 1 fica-
~
, tiet 6.9.2 within 30 days after completion of the inspection
+
t4 describing +the tendon condition, the condition of the concrete
','/
f (especia1Xpat tendon anchorages), the inspection procedurts, the tolerances on ' cracking, and the corrective actions taken. 1 * +
- . , * ?
5 # ZURVETLLANCE REQUIREMENTS
.f ,f l
l 4.o\1!6.1 The servetural integrity of the < containment tendons shall be,dcuen-
\' ,' '
l strated at the,end of one, thne and five years following the initial containment .
'reructur.a. integrity test and at five year indrvals' thareafter. ' The stw eerral integrity of the tendons shall be demovstrated by: -
, 3- ,e > ,
a. l r 4 Determining that for a representar1ve sample
- of at least 15 tendons ( .
I s ' (4 done ,5 vertical and 6 hoop) each has a'lif t off force greater than
)
or equal to 95% of its Base Value indicated in Table 4.~6-la.' ' IE tlie 114 off force of a selected tendon in a group lies b,ieween the 95:\ , 7 'j Bardt Valua and 90% of the Base value, one tandon on r sch ride of [>~ - chits tendon shall be checked for its lift off force.. ID the lift -off
~
2 fodes of the adjacent tendons are greater than or equal to 953 of ' their Base Values in Zahle 4.6-lb, the single deficiency she12 r5e,' consider,ed g unique and acceptable. Tor.cendon(s) not conforni.d,,'t.o 3 j , 5 ,.) N's *
/ '1 v ' ,. c ,
.o .
; / -
l, .1 d
/ , Fortive eae.i M.s'is[so inspectior%
that thethe tendons sample group shall willbe' c$ange selected on a random
,somewhat/for *nchbut representa-inspection; I
however, to develop a history of tendon performinca and to correlate the observed data, or.s esdon from each ,poup (dde, jverticali and hoop) may be
, kept urchanged after the initial selection.
b!O6020421 820526 s 3/4 6-8 LA PD% A00CM 03000395' ,s ' q , .y
- PDR ",
; ') ,
i 7 , y . . . .
l o
, -) l \
- 9. l C0!TTAINMDrr SYSTEMS SURVEILLANCE REOUIR_ N S (Continued) these requirements, a determination shall be made as to the cause of the occurrence and the tendon (s) shall be restored to the required level of integrity. .
If the lift-off force of the selected tendon lies below 90% of its Base 2
. Value, the tendon shall be completely detensioned and a determination made as to the cause of the occurrence.. .
( b. Determining that the average of the Normalized Lift Off Forces for each .. 1 tendon group (vertical, dome and hoop) is greater than or equal to the
=4n4=== required average tendon force for the group. The minimum re-quired average tendon force is 1195 kips for vertical tendons,1115 kips for dome tendons, and 1181 kips for hoop candons. The Noz-am14 red Lif t .
Off Force for a tendon is obtained by adding the Normalizing Factor appearing in Table 4.6-2 to tha lift off force. Failu'.e to comply with this requirement may be evidence of abnormal degradation of the contain-ment structurs. If the Normalized Lif t-Off Force of any tendon is less than the applicable minimum required average tendon force,,an investigation shall be conducted
, to determine the cause and extent of ~ occurrence. This investigation shall include as a minimum the measurement of lif t-off forces of tendons adjacent to the deficient tendon to determine if the average of the candon lift-off 1 forces in this region of the containment is equal to or greater than the
=4n4="= required average tendon force. Failure to comply with this re-quirement may'ba evidence of abnormal degradation of the containment structure.
- c. Datensioning one tendon in each group (dome, vertical and hoop) from the representative sample. One wire shall be removed from each detensioned tendon and av==4ned to determine: -
l 1. That over the entire length of the tendon wire, the wire has not undergone corrosion, cracks or damage to the extent that an abnormal - condition is indicated.
- 2. A minimum tensile strength vr.lue of 240,000 psi (guaranteed uliemate strength of the candon material) for at least three wire samples ~
(one from each and and one at mid-length) cut from each removed wire,
- d. Determining for each tendon in the above representative tendon sample, that an analysis of a sample of the sheathing filler grease is within the following limits:
l l 1. Grease Voids < 5% of net duct volume
- 2. Chlorides I 10 PPM
- 3. Sulphides '
3 10 PPM 4. Nitrates 3 10 PPM
- 5. Water Content i 10 by weight 3/4 6-9
,,, ,_.,y.w g ,
s-. _,- .,-- ---- w-- , - - - ,
,Yb s
$y
~.
i CONTAINME!Tr SYSTEMS c:
*RVEILLANCE REQUIREMENTS (Continued) j w
S If the inspections perfor: cad at 1, 3, and 5 years indicata no abnormal degradat1on t of the tendon system, the number of sample tendons may be reduced to 3 dome, 3 , vertical, and 3 hoop for subsequent inspections. Upcn the completion of the five g
+
1 year inspection, the results of the first three inspections shall be evaluated to determine if an abnormal condition is evident for the tendon system. Based ] on the conclusions of this evaluation, the sample tendons with their Base values 1 cnd Nomalizing yactors will be specified for all subsequent inspections. 2 ' j
.p 4.6.1.6.2 At the same inspection frequency as the tendons, the structural integrity of the end anchorages of all tendons inspected pursuant to Specification 4.6.1.6.1 and the adjacent concrete surfaces shall be determined by a visual inspection and -
verifying that no abnormal material or structural behavior is evident. 4.6.1.6.3 At the same inspection frequency as the Type A containment leakage rate ,, i test, the structural integrity of the exposed accessible interior and exterior eurfaces of the containment shall be determined prior to each Type A cont =f ment leakage rate test (Specification 4.6.1.2) by a visual inspection of these surfaces and verifying that no abnormal material or structural behavior is evident. . S
=e k
i i B I e
/
3/4 6 - 10 !
- i e
(
- = :: i
' 1 i
TABLE 4.6-la
. BASE VALUE OF TENDON FORCE
.I
~ !
SURVEILLANCE TENDONS i INSPECTION PERIOD t i f, 2 !I 3 Base Value (kips) Tendoni Base Value (kips) Tendon Base Value (kips) I Tendon L l D-104 1275 D-125 1230' D-108 1287 I D-129 1245 D-219 1258 D-121 1225 '
.?
D-219 1265 D-228 1275 D-219 1254 { D-328 1287 D-324 1273 D-312 1271 V-23 1328 Y-23 1319 V-23 1313 . V 1309 V-30 1287 Y-37 1299 Y-67 1332 V-53 1316 V-60 1294 , Y-92 1299 V-76 1315 V-83 1314 V-115 1322 V-99 1309 V-106 1296 3AC 1324 3AC 1313 3AC 1307 , 8BA 1272 , 13BA 1283 8C3 1254 . 13C3 1284 18CB 1264 18BA 1254 28CB 1263 28BA 1264 28AC 1261 38AC 1256 33C3 1282~ 33BA 1277 . 38BA 1253 36AC 1278' 38C3 .1230 i e [ (aav. 2, s/21/a2' 6 -l 0 a.
. . O m-==
- r:
q'
! j
- l. .$
TABLE 4.6-lb : i bIj g BASEVkLUEOFTENDONFORCE- r ls +
~
ADJACENT TENDONS I-INSPECTION PERIOD ' 3 2 - TandonI Base value (kips) J 1 Tendon Base Value (kios) Tendon 1 Base Value (kins) 't D-107 1241 l D-124 1284' 1222 D-153 1245' 1262 D-109
- D-126 1250 D-120 1284 ,
D-IDS D-218 1288 ; 1296 D-122 1264 D-128 D-220 1291 - 0 1267 D-218 1281 D-I30 D-227 1270 - 1296 D-220 1286 ' D-218 D-229 1235 a 1299 D-311 1266 . D-220 D-323 1256 - 1244 D-313 1237 D-327 D-325 1227 1237 V-22 1295 , ' ' D-329 V-22 1300 ' 1306 V-24 1313 , V-22 V-24 1317 1320 V-36 1284 , , V-24 V-29 1301 1308' V-38 1293 , V-45 V-31 1327: 1322 V-59 1308 V-47 V-52 1316 ~. - 1309 V-61 1309 V-66 V-54 1298 -
*1309 V-82 1297 V-68 V-75 1304 1311 l V c' - 1309 1313 V-84 I 1327 V-77 V-105 1297 '
. V-98 1280 1307 -
1313 " 1300 V-107 ' 1320 V-100 2AC 1264 V-1 2AC 127G 1245 2AC 1277 1252 4AC 1264 4AC 1303 . '
'4AC 1267 7C3 1324 123A 9C3 1284 7BA 143A 1263 1292 17BA 1261 9EA 17C3 1271. !
12C3 1285 1287, 19BA 1287 , 1272 19C3 27AC 1297
- 14C3 1289 e 27BA 29AC 1254 27C3 1277[ 1272 1280 29BA 32BA 1259 -
19C3 1262 1283 32C3 34BA 1253 37AC 1232 1294 34CB 37C3 1276 39AC 1297 1294' 35AC 39CB 1291 373A 1275 1273 37AC 39EA : (Rav. 2, S/21/92) T, b' lob - ..
o , .g
* (.h p l
t l-G I 1 TABLE 4.6-2 ? b- 5
- t. y NORMELIZING FACTORS (N.F.) ,
i l INSPECTION PERIOD J 4 1 N.F. (kips) i A Tendon ' Tendon l N.F. (kips) L (kips) Tendon i N.F. D-108 -42 , D-125 36
-24
~ ,
D-121 40 / D-104 D-219 10
~
D-129 33 D-219 10 D-228 -28 D-219 10 D-312 -20
-21 D-324 -12 -15 7 D-328 -15 V-23
-15 7-23 V-37 -5 V-23 V-30 31 l V-46 11 V-60 11 '
-21 V-53 -24 -15 V-67 -11 V-83 25 7-76 V-106 7 V-92 7-99 5 Y V-115 -10 3AC -56
-56 3AC -56 26 '
3AC -26 8C3 - 18 133A 34 , 8BA 29 18BA i ,
-23 18C3 10 13C3 17 28AC 3 26 28BA -16 28C3 -17 - 333A 40 33C3 54 38AC .
0 38C3 , 40 36AC ; 38BA 4
.~
1 7 Y
, 6 L
6 1 i I 1 , (Rev. 1, 5/V82)
. ._.% .G. . loc
CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM ! LIMITING CONDITION FOR OPERATION 3.6.1.7 Each containment purge supply and exhaust isolation valve shall be , OPERABLE and:
- a. Each 36 inch containment purge supply and exhaust isolation valve shall be sealed closed. ,
l b. The 6 inch containment purge supply and exhaust isolation valves may l be open for less than or equal to 1000 hours per 365 days. APPLICABILITY: MODES 1, 2, 3, and 4. ACTION:
- a. With a 36 inch containment purge supply and/or exhaust isolation
- valve (s) open or not sealed close, close and/or seal close the open valve (s) or isolate the penetration (s) within 4 hours, otherwise be in at least HOT STAN0BY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
- b. With a 6-inch containment purge supply and/or exhaust isolation valve (s) open for more than 1000 hours per 365 days, close the open 6-inch valve (s) or isolate the penetration within 4 hours otherwise be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
- c. With a containment purge supply ~and/or exhaust isolation valve (s) having a measured leakage rate exceeding the limits of Surveillance Requirements 4.6.1.7.3 N restore the inoperable vavle(s) to OPERABLE status within 24 hours otherwise be in at least HOT STANDBY within the next 6 hours and in COLD SHUTOOWN within the '
following 30 hours. SURVEILLANCE REQUIREMENTS l i 4.6.1.7.1 Each 36 inch containment purge supply and exhaust isolation valves shall be verified to be: l a. Closed at least once per 24 hours, -
- b. Sealed closed at least once per 31 days.
4.6.1.7.2 The cumulative time that the 6 inch purge supply and exhaust isolation valves have been open during the past 365 days shall be determined at least once per 7 days. 4.6.1.7.3 At least once per 6 months on a STAGGERED TEST BASIS each WWd>td" I dM4k@$atetr containment purge supply and exhaust isolation valve with l resilient material seals shall be demonstrated OPERABLE by verifying that the i measured leakage rate is less than or equal to 0.05 L, when pressurized to Pa-SUMMER - UNIT 1 - 3/4 6-11 APR 151982
, .s , ,
s N TAL. 6-1 .N . y . i , CONTAINHENT ISOLATION VALVES fo a HAXIMUM Q VALVE NUMBER ISOLATION TIME 1 y A. PilASE "A" ISOLATION ' FUNCTION g (SEC)
. 1. 7501-AC CRDH Coolant Water Inlet Line 40
- 2. 7502-AC CRDH Coolant Water Inlet Line 40
- 3. 7503-AC CRDH Coolant Wated Outlet Line 40
- 4. 7504-AC CRDHCoolantWateqOutletLine 40
- 5. 503A-BD # Steam Generator A Blowdown Line 40'
! 6. 503B-BD # Steam Generator B'plowdown Line' 40
- 7. 503C-BD # Steam Generator C Blowdown Line 40
- 8. 8100-CS Reactor Coolant Pu'ap Seal Water Return 40 .
- 9. 8112-CS Reactor Coolant Pubp Seal Water Return 40
- 10., 8149A-CS Reactor Coolant To' Letdown lleat Exchanger. 40
- 11. 81498-CS Reactor Coolant To Letdown lleat Exchanger- 40 ,
- 12. 8149C-CS Reactor Coolant To Letdown lleat Exchanger 40 -
R 13, 8152-CS ReactorCoolantTo!LetdownlleatExchanger 40
- *' 14. 6797-FS Fire Service Delugh To Charcoal Filters 40 f 15. 6050A-IIR Normal Reactor Building Pressure Line 40
[ 16, 6054-liR ~ Normal Reactor Building Pressure Line j 40 17, 2660-IA Reactor Building Instrument Air Inlet Line 40
! 18. 2662A-IA Reactor Building Instrument Air Suction Line 40 l 19. 266211-IA Reactor Building Instrument Air Suction Line 40
- 20. 6242A-ND Reactor Building'Shmis DrInin 40 .
- 21. 6242B-ND Reactor Building Sump Drain 40 j 22. 8028-RC ,
, Pressurizer Relief Tank Hakhup Water Line 40 l 23. 8033-RC Pressurizer Relief Tank H2 Supply-Return Line, 40
- 24. 8047-RC Pressurizer Relief Tank N2 SUPP l y-Return Line 40
- 25. 8860-SI Full Line To Accuteulators 40
- 26. 8880-S1 Accumulator Nitrogen Supply 40
- 27. 8871-SI Accumulator Test Line ,
40
- 28. 896 kSI Accumulator Test Line 40
( 29. 9311A-SS Sampling Line Supply To Radiation Honitor~ 40
- 30. 93113-SS Sampling Line Supply To Radiation Monitor 40
.e 4
O e 9 eeeo-e ..m . *
- 4 ,e-==
" TABLE 3. . (Continued) -
i
)! .
- CONTAINMENT ISOLATION VALVES e
HAxinus g ISOLATION TIME H VALVE nut! DER A. PilASE "A" ISOLATION (Continued) FUNCTION (SEC) 9312A-SS Sampling Line. Supply Return From Radiation Monitor 40 31.
- 32. 9312B-SS Sampling Line Return Return From Radiation Monitor 40
- 33. 9339-SS Sample Return Line To PRT 40 ,
- 34. 9341-SS Sample Return Line To PRT 40
- 35. 9356A-SS Sampling Line From Pressurizer
- 40
- 36. 9356B-SS Sampling Line From Pressurizer 40
- 37. 9357-SS Sampling Line From Pressurizer ,
40
- 38. 9364B-SS Sampling Lines From Reactor Coolant Loop B 40-
- 39. 9365B-SS Sampling Lines From Reactor Coolant Loop B 40
- 40. 9364C-SS Sampling Lines From Reactor Coolant Loop C 40 *
- 41. 9365C-SS Sampling Lines From Reactor Coolant Loop C '40 -
- 42. 9387-SS Sampling Line From Accumulators 40 w 43. 9398A-SS # Sampling Line From Steam Generator A Blowdown 40 30 44, 9398B-SS f Sampling Line From Steam Generator B Blowdown 40 9398C-SS # Sampling Line From Steam Generator C Blowdown 40 p 45, ,
Reactor Coolant Drain Tank Vent llender 40 w 46. 7126-WL ca
- 47. 7150-WL Reactor Coolant Drain Tank Vent lleader 40
- 48. 1003-WL Reactor Coolant Drain Tank Discharge To Wasta 40
- 49. 7136-WL Reactor Coolant drain Ta'nk Discharge To Wasta 40 B. PilASE "B" ISOLATION
- 1. 9568-CC Component Cooling To R. C. Pumps Bearings 60
- 2. 9600-CC Component Cooling To R. C. Pumps 60
- 3. 9605-C Component Cooling From R. C. Pumpa Bearings 60
- 4. 9606-CC i Comlonent Cooling From R. C. Pumps Bearings 60 ,
- 5. 1633A-FW # Chemical Feed Line To Feedwater Loop A 60
- 6. 1633n-FW # Chemical Feed Line To Feodwater Loop B 60
- 7. 1633C-FW I Chemical Feed Line To Feedwater Loop C ,
60
" ~
C. REACTOR BUILDING PURCE SUPPLY AND EXilAUST ISOLATION
- 1. 0001 A-All : Reactor Building Purge Supply 5
- 2. 0001B-All Reactor Building Purge Supply 5
- 3. 0002A-All Reactor Building Purgo Exhaust 5 .
~ ~
g TABLE ^ (Continuzd) s ,
;{ .
j'] CONTAINHENT ISOLATION VALVES . - 1 VAINE NUMBER HAXIMUM C. REACTOR BUILDING PURCE SUPPLY ISOLATION T1HE ,
"3 AND EXilAUST ISOLATION (Continued) FUNCTION (SEC) e- ) , 4. 0002B-All Reactor Building Purge Exhaust 5
- 5. 6056-ilR Alternate Reactor Building Purge Supply Line 5
- 6. 6057-IIR Alternate Reactor Building Purge Supply Line 5
- 7. 6066-ilR Alternate Reactor Building Purge Exhaust Line 5 j 8. 6067-IIR Alternate Reactor. Building Purge Exhaust Line 5 D. HANUAL (1)
- 1. 8767-DN Demineralized Water Line N/A .
- 2. 8768-DN Demineralized Water I.ine N/A C
3 3.. 6772-FS Fire Service llose Reel Supply
- N/A j 4. 6773-FS Fire Service llose Reel Supply N/A -
- 5. 2679-IA Breathing Air Supply Line N/A t', 6. 2680-IA Breathing Air Supply Line N/A
! 7. 6587-NC .Hitrogen Supply To Steam Generators N/A t T 8. 8090A-RC Dead Weight Tester N/A El 9. 8090B-RC . Dead Weight Tester N/A
" 10. 2912-SA Reactor Building Service Air , N/A l 11, 6671-SF Refueling Cavity Drain Line N/A i
12, 6672-SF Refueling Cavity., Drain Isine N/A ,
- 13. 6697-SF Rcfueling Cavity Fill Line N/A
- 14. 6698-SF
- Refueling Cavity Fill Line. N/A
- 15. 7135-WL Reactor Coolant Drain Tank Discharge To Waste N/A E. REMOTE MANUAL (2)
- 1. 9602-CC , Component,Coolin'g To R. C. Pumps .
N/A l
- 2. 8102A-CS Seal Injection To Reactor Coolant Pump A N/A j 3. 8102B-CS Se'al Injection To Reactor Coolant Pump B -
N/A 4, 8102C-CS Seal Injection To Reactor Coolant Pump C N/A g e
.e-h -
. w TABLE 3.6-1 (Continued) .
CONTAINMENT ISOLATION VALVES . 8 . 6 . HAXIHUN N VALVE NUMBER ISOLATION TIME r- E. REMOTE MANUAL (Contin'ued) FUNCTION (SEC)
' t
- 5. 8107-CS charging Line To Regenerative Ileat Exchange .
N/A
- 6. 6050 B-IIR llydrogen Analyzer Return Line N/A .
- 7. 6051 A-IIR llydrogen Analyzer' Supply Line N/A
- 8. 6051B-IIR llydrogen Analyzer Supply Line N/A.
- 9. 6051C-IIR liydrogen Analyzer Supply Line N/A
- 10. 6052A-IIR llydrogen Analyzer Return Line N/A
- 11. 6052B-IIR llydrogen Analyzer Return Line N/A
- 12. 6053A-llR llydrogen Analyzer Supply Line N/A I
- 13. 60538-llR liydrogen Analyzer Supply Line . N/A
- 14. 8701A-Ril RilR Pump Suction From Reactor Coolant Loop A N/A *
- 15. 8701B-Ril RilR Pump Suction From Reactor Coolant Loop C N/A 16, 8801A-SI Boran Injection Tank To Reactor Coolant Loops N/A ig 17 88013-SI Boran Injection Tank To Reactor Coolant Loops N/A c' 18, 8811A-SI RllR Pump A Suction From Recirculation Sump N/A p
! 19. 8811B-SI Ri!R Pump B Suction From Recirculation Sump N/A g 20. 8884-SI liigh llead Safety Injection To Reactor Coolant Loops N/A u- 21. 8885-SI liigh llead Safety Injection To Reactor Coolant Loops N/A '
22, 8886-SI ' liigh llead Safety 'Injecti' no To Reactor Coolant Loops N/A
- 23. 8888A-SI Low Ilead Safety Injection To Reactor Coolant Loops N/A 1
24, 8888B-SI Low Ilead Safety Injection To Reactor Coolant Loops N/A j 25. 8889-SI Low licad Safety Injection To Reactor Coolant Loopa II/A
- 26. 3003A-SP Supply To Reactor Building Spray Nozzles N/A ,
- 27. 3003B-SP Supply To Reactor Building Spray Nozzles N/A
- 28. 3004A-SP Sprny Pump A Suction From Recirculation Sump N/A
- 29. 3004B-SP Spra'y Pump B Suction From Recirculation Sump ,
N/A .
- 30. 3103A-SW Service Water From Reactor Building Cooling Unit A_ - N/A 31, 3103D-SW Service Water From Reactor Building Cooling Unit B N/A
- 32. 3106A-SW Service Water To Reactor Building Cooling Unit A -
N/A
- 33. 3106B-SW Service Water To Reactor Bu,ilding Cooling Unit'.B , N/A
- 34. 3110A-SW Service Water To Reactor Building Cooling Unit A N/A 35, 31108-SW Service Water To Reactor Building Cooling Unit B N/A' S
h -a . _ . _ - __ _ _ . , _ . _ i .r ..
TAllLE (Continued) . . , 5
- CONTAINHENT ISOLATION VALVES HAXIHUN ISOLATION TIME
" VALVE NUMBER (SEC)
FUNCTION F. CHECK N/A 7541-AC CRDH Coolant Water Inlet Line N/A 1. CRDH Coolant Water Outlet Line N/A g 2. 7544-AC Component Cooling To R. C. Pump Bearings s 3. 9570-CC N/A H Component Cooling From R. C. Pump Bearings
- 4. 9689-CC Reactor Coolant Pump Seal Water Return .N/A
- 5. 8103-CS N/A Seal Injection,To R. C. Pump A . N/A
- 6. 8368A-CS Seal Injection To R. C. Pump B
- 7. 83688-CS N/A Seal Injection To R. C. Pump C N/A
- 8. 8368C-CS Charging Lii.e To Regenerative llent Exchanger *
- 9. 8381-CS N/A g.
11re Service Deluge To Charcoal Filters N/A
- 10. 6799-FS Instrument Air Supply To Reactor Building
!!. 2661-IA N/A .
Nitrogen Supply To steam Generators N/A
; 12. 6588-NC Pressurizer Relief Tank Hakeup Water Line
- 13. 8046-RC Service Air Supply To Reactor Building N/A 2913-SA N/A 14.
3009A-SP Supply To Reactor Building Spray Nozzles 't. - N/A ti 15.
16, 3009B-SP .
Supply To Reactor Building Spray Nozzles N/A Accumulator Nitrogen Supply T 17. 8947-SI N/A
- 18. 8861-SI Fill Line To A cumulators 9
El o
- g
- l
# Valve not subject to Type "C" leakage test.
(1) Hanual valves may be opened on an intermittent basis under adminstrative control. (2) Remotemanualvalvepositionsaremaintainedbyadministratihecontrol. L l' I i l e 9
.. . , I
m ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- 2. Verifying the fuel level in the fuel storage tank, 1
- 3. Verifying the fuel transfer pump can be startad and transfers :
fuel from the storage system to the day tank,
- 4. Verifying the diesel starts from ambient normal standby ,
condition and accelerates to at least 504 rps in less than or equal to 10 seconds. The generator voltage and frequency shall be 7200 + 720 volts and 60 + 1.2 Hz within 10 seconds after the start signal. The diesel generator shall be started
- for this test by using one of the following signals:
a) Manual. b) Simulated loss of offsite power by itself. c) Simulated loss of offsite power in conjunction with an ESF actuation test signal. d) An ESF actuation test signal by itself. e) Simulated degraded offsite power by itself. t
- 5. Verifying the generator is synchronized, loaded to greater than or equal to 4250 kW in less than or equal to 50 seconds, and ope' rates with a load greater than or equal to 4250 kW for at '
least an additional 60 minutes, O. At least once per 31 days and after each operation of the diesel where the period of operation was greater than or equal to I hour by removing accumulated water from the day tank.
- c. At least once per 92 days and from new fuel oil prior to addition to the storage tanks by verify,ing that a sample obtained in accordance with ASTM-0270-1975 has a water and sediment content of less than or equal to .05 volume percent and a kinematic viscosity
@ 40*C of greater than or equal to 1.9 but less than or equal to 4.1 wnen tested in accordance with ASTM-0975-77, and an impurity level of less than 2 mg. of insolubles per 100 ml. vnen tested in accordance with ASTM-02274-70.
- d. At least once per 18 months during shutdown by:
l 1. Subjecting the diesel to an inspection in acesrdance with procedures prepared in conjunction with its annufacturer's I recommendations for this class of stancby service,
- 2. Verifying the generator capability to reject a load of greater than or equal to 830 kw while maintaining voltage at 7200 720 volts and frequency at 60 + 1.2 Hz.
3/4 8-3 MAit - d2 ! SUMMER - UNIT 1
1 . . -- 1 ELECTRICAL POWER SYSTEMS i -n---- ,- y *n -"f A.C. SOURCES l h d, .4 '..~ .. J .i 4 .;J l SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
- a. One circuit between the offsite transmission network and the onsite Class lE distribution system, and
- b. One diesel generator with:
- 1. A day fuel tank containing a minimum volume of 300 gallons of fuel, i 2. A fuel storage system containing a minimum volume of 30,000 gallons of fuel, and l 3. A fuel transfer pump.
/
APPLICABILITY: MODES 5 and 6. ACTION: With less than the above minimum required A.C. ele:tricai power sources OPERABLE, immediately suspend all operations involving CORE ALTERATIONS positive reactivity changes, movement of irradiated fuel, or crane operation with loads over the fuel storage pool. ad ith'- O h;;r;, f:;rt:-"**-- :-d . ..t L.e .1;;;;<. ^ww i an v
<ye*-- th.susu . w . . w. . wuo. . ;r :;r ! to 2." ;qu... ..~h ;;..t. In addition, when in MODE 5 with the Reactor Coolant loops not filled, or in MODE 6 with l the water level less than 23 feet above the reactor vessel flange, immediately I initiate corrective action to restore the required sources to OPERABLE status as soon as possible.
SURVEILLANCE REOUIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1, 4.8.1.1.2 (except for requirement 4.8.1.1.2.a.5) and 4.8.1.1.3. 1 1 SUMMER - UNIT 1 3/4 8-8 m e a e
ELECTRICAL POWER SYSTEMS r, t ' ' v. c . . :. r. . " - n. ./ s asw.J L. . .. J . . d J .J ] 0.C. SOURCES l SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.2 As a minimum, one 125-volt battery bank and its associated full - capacity charger shall be OPERABLE. APPLICABILITY:_ NODES _S and 6. ACTION:
- a. With the required battery ban inoperable, immediately suspend all operations involving CORE ALT RATIONS, positive reactivity changes or movement of irradiated fuel; initiate corrective action to restore the required battery bank to OPERABLE status as soon as possible. = d .. .....
j '; ;. . , de . e . .-g =d . ;..; ;;. Low;ur wo a anc ays c.m ;.'.c x;h ;
- m. ,
ywo. . . u w. . . . . . . . -
- b. With the required full capacity charger inoperable, demonstrate the
... OPERABILITY of its associated battery bank by performing Surveillance Requirement 4.8.2.1.a.1 within one hour, and at least once per 8 hours thereafter.. If_any Category A limit in Table 4.8-2 is not met, declare the battery inoperable.
SURVEILLANCE REOUIREMENTS 4.8.2.2 The above required 125-volt battery bank and charger shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.1.
~
r < d SUMMER - UNIT 1 3/4 8-12 m e
1 l . . ... ELECTRICAL POWER SYSTEMS ONSITE POWER DISTRIBUTION SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.3.2 As a minimum, the following electrical busses shall be energized in the specified manner: e
- a. One train of A.C. Emergency Busses consisting of two 7200 volt and three 480 volt A.C. Emergency Busses.
- b. Three 120 volt A.C. Vital Busses energized form their associated inverters connected to their respective O.C. Busses.
- c. One 125 volt 0.C. Bus energized from its associated battery bank.
APPLICABITLITY: MODES 5 and 6. ACTION: With any of the above required electrical busses no energized in the required
/ . manner, immediately reactivity changes,suspend all operations or movement involvin fuel, of irradiated CORE ALTERATIONS, initiate corrective positive action .
i ' to energize the required electrical busses in the specified manner as soon as
- possibles r4 M "*- 2 burr dar :::;r4'a M '?:c.; tr.c ZS w.ov qr # 1a'e+ '
O.' ;q cr; :--' u-nt SURVEILLANCE REOUIREMENTS
~
4.8.3.2 The specified busses shall be determined energized in the required manner at least once per 7 days by verifying correct breaker alignment and . . indicated voltage on the busses. i s' SUMMER - UNIT 1 3/4 8-15 M"i 151982 l
y > ) TABLE 3.8-1 (continued)
"h
=
, CONTAINHENT PENEIRATION CONDUCIOR OVERCURRENT PROTECTIVE DEVICE TEST SEIP0lNT CRllERIA E
EQUIP NO.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETP0lNT RESPONSE llHE 480 V SWGR. 30
- 1) XfN0067A-All PRIMARY XSWIA3/1C LONG TlHE S40 Amps i 46 Sec.
CRDH CLNG. SYS. FAN A Sil0RT TIME 2700 Amps 1 0.17 Sec. 3 INSTANT g Amps 1 0.09 Sec. XSWIA3 MAIN INCOMING BACKUP XSWIA3/48 LONG TlHE 4800 Amps 1 12 Sec. Sil0RT TlHE 7200 Amps < 0.50 Sec. INSTANT N/A N/A
$ BUS TIE TO XSWIC3 BACKUP XSWlA3/4C LONG TlHE 3000 Amps 5 12 Sec.
. Sil0RT TlHE 4500 Amps < 0.32 Sec.
g INSTANI N/A N/A 3o -
- 2) XfN00670-All PRIMARY XSWlA3/BA LONG TlHE S40 Amps 5,M-Sec. -
CDRM CLNG. SYS. FAN 0 Sil0RT TlHE 2700 Amps 1 0.17 Sec. INSTANI g Amps 1 0.09 Sec. XSWIA3 MAIN INCOMING BACKUP XSWlA3/4B LONG TlHE 4800 Amps < 12 Sec. : Sil0RI IIME INSTANT 7200 Amps N/A 7 0.50 Sec. N/A -] i r?.3 BUS TIE TO XSWIC3 BACKUP XSWIA3/4C LONG TIME 3000 Amps < 12 Sec. . Sil0RT TIME 4500 Amps 7 0.32 Sec. j
- 3) XCR0004-Fil PRIMARY XSWlA3/2C INSTANI LONG IIME N/A 744 Amps N/A
< 98 Sec.
f*i
,?i REACIOR BLOG POLAR CRANE Sil0RI TlHE N/A N/A '
2 INSTANT 4050 Amps 1 0.09 Sec.
-q l !
l XSWIA3 MAIN INCOMING BACKUP XSWlA3/48 LONG TIME 4800 Amps 1 12 Sec. j i Sil0RI TlHE 7200 Amps < 0.50 Sec. INSTANT N/A N/A e .
/
.I E TABLE 3.8-1 (continued)
I
. !U i ,
. CONTAINHENT PENETRATION CONOUCTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRITERIA E
4 1 1 EQUIP No.-SYS/DESCRIPil0N DEVICE LOCATION TEST SEIP0lNT RESPONSE 11HE
- 3) CONTINUE 0: !
BUS TIE TO XSWIC3 BACKUP XSWIA3/4C LONG TlHE 3000 Amps t 5 12 Sec. Sil0RT TlHE 4500 Amps < 0.32 Sec. INSTANT N/A N/A . 4) XFN0009A-All PRIMARY XSWlA3/2A LONG TlHE 360 Amps $ 30 Sec. , 1 R.B., REACTOR COMPART. Sil0RT IINE 1350 Amps ' CLNG FAN A 1 0.17 Sec. w INSTANT g Amps 1 0.09 Sec. f
) XSWIA3 MAIN INCOMING BACKUP -XSWlA3/4B LONG TIME 4800 Amps 1 12 Sec.
) cn Sil0RT TIME 7200 Amps < 0.50 Sec. j A o INSTANT N/A N/A BUS TIE 10 XSWIC3 BACKUP XSWlA3/4C LONG TIME 3000 Amps 5 12 Sec. ' Sil0RT TlHE 4500 Amps < 0.32 Sec. . INSTANT N/A N/A 5 j i S) XFN00678-All PRIMARY XSWlB3/20 LONG TlHE 525 Amps < 30 Sec. :m1 , j CRDH CLNG. SYS. FAN B Sil0RT TlHE 2250 Amps 30.17Sec. [rj INSTANT g Amps 5 0.09 Sec. . ! XSWIB3 HAIN INCOMING BACKUP XSWIB3/4B LONG TIME 9000 Amps < 12 Sec. ! .' ' I SlK)RT TlHE 9000 Amps 7 0.50 Sec. - j
- INSTANT N/A N/A I ."i- i j
EMERGENCY FEE 0 FR0H BACKUP XSWIB3/38 LONG TIME 4800 Amps < 12 Sec. $
'! 1 '
XSWIDB1 Sil0RI IINE 7 0.32 Sec. 6000 Amps -
a l INSTANT N/A N/A ' !., j i mg
- 6) XFN00098-All PRIMARY XSWlB3/3A LONG TlHE 525 Amps < 12 Sec.
R.B., REACTOR COMPARI. J l Sil0RT 11HE 1125 Amps. 7 0.17 Sec. l CING FAN B INSTANT 1500 Amps 30.09Sec. t
10 TABLE 3.8-1 (continued) '
- u
. CONTAINHENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICE TEST SEIP0lNT CR11ERIA E
EQUIP NO.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETPOINT RESPONSE TlHE
- 6) CONTINUED: -
goo ARP FU$f XPtl SY71 h 3.?S NINb* S 15WiB3 ruik iHCunii6 HA c BACKUP E W133/40 LONG I'".C - g000 .t+:. 1lRgec. ' 3"""' ans nn,
.'8"'- '""" N " 2"""-
nin nin iliRGENCY TEEC T;0M OACre." XS"lB2/3B L^" XSWIDB1 T!"I 4"00 ^r/E i 12 W ! j;;0{,}IMC maino. 0090 4 n, n j,9 02 k;- n, n - I
$ 7) XfN00067C-All PRIMARY XSWIC3/20 LONG TIME S40 Amps 1 30 Sec.
m CDRM CLNG. SYSTEM FAN C Sil0RT TIME 2700 amps 4 $ 0.17 Sec. s INSTANT -33F.r Amps < 0.09 Sec. zels - XSWIC3 HAIN INCOMING DACKUP XSWIC3/3B LONG TlHE 4800 Amps 1 12 Sec. Sil0RT TlHE 7200 Amps < 0.50 Sec. INSTANI N/A R/A N BUS TIE TO XSWIA3 33 I BACKUP XSWlA3/4C LONG TIME Sil0RT TlHE 3000 Amps 4500 Amps 1 12 Sec. ' E$ ,
< 0.32 Sec. ?
INSTANT N/A N/A i s) { l IM
- 8) HfN00978-All PRIMARY XSWIDBl/6D LONG TlHE S25 Amps < 30 Sec. : 1 R.B. CLNG. UNIT FAN XfN64B EMERGENCY HOTOR Sil0RT TIME 1500 Amps 7 0.17 Sec. f .!
INSTANT 2250 Amps 7 0.09 Sec. j. . XSWIDB1 MAIN INCOMING L3.o ' ~ a} BACKUP XSWIDBl/4B LONG TlHE 4668 Amps < 12 Sec. Sii0RT TlHE INSTANT 9000 Amps N/A 7 0.50 Sec. N/A f 'I'.Jl '7 , j N
- 9) MfN00968-All R.B. CLNG. UNIT FAN PRIMARY XSWIDBl/78 LONG TlHE Sil0RT TlHE 1260 Amps S400 Amps 5 30 Sec.
< 0.17 Sec.
Q ' XfN648 NORMAL H010R INSTANI -7300 Amps 7 0.09 Sec. Spoo t ut
3 I'
\ .
E TABLE 3.8-1 (continued) Y m
. CONTAINHENT PENETRATION CONDUCIOR OVERCURRENT PROTECTIVE DEVICE lEST SE1 POINT CRilERIA l @ .
EQUIP NO.-SYS/ DESCRIPTION DEVICE LOCATION IEST SETP0lNT RESPONSE TIME
- 9) CONTINUED:
(,3oo XSWIDB1 MAIN INC0HlhG BACKUP XSWlDBl/4B LONG TlHE 4666-Amps ' 1 12 Sec. Sil0RT TIME 9000 Amps < 0.50 Sec. INSTANT N/A N/A
- 10) MfN0096C-All PRIMARY XSWlDAl/SB LONG TIME 1260 Amps < 30 Sec.
R.B. CLNG. UNIT FAN Sil0RT TlHE 5400 Amps [0.17Sec. XFH65A NORMAL HOTOR INSTANI g Amps 1 0.09 Sec. N XSWIDA1 MAIN INCOMING BACKUP XSWlDAl/4B LONG TIME M Amps < 12 Sec. , o> Sil0RT TlHE 9000 Amps < 0.50 Sec. g INSTANI N/A N/A .
- 11) HFN0097C-All PRIMARY XSWIDAl/6C LONG T'lHE 525 Amps < 30 Sec. .
R.B. CLNG. UNIT FAN Sil0RT TIME 1500 Amps 7 0.17 Sec. I XfN65A EMERGENCY HDIOR INSTANT 2250 Amps 30.09Sec. l 43eo XSWIDAl MAIN INCOMING BACKUP XSW10Al/4B LONG TIME Sil0RT TlHE
-9066 Amps 9000 Amps 5 12 Sec.
< 0.50 Sec.
3[ f ;) l l INSTANI N/A N/A h, .}
- 12) MfN0096A-All PRIMARY XSW10A1/6B LONG TlHE 1260 Amps < 30 Sec. D R.B. CLNG. UNIT FAN Sil0RT TlHE 5400 Amps 7 0.17 Sec. , > -
XFN64A NORMAL HOTOR INS 1ANI g Amps 30.09Sec. f ,f ' [ l N Amps XSWIDA1 MAIN INCOMING BACKUP XSWIDA1/48 LONG TIME Sil0RT TlHE 9000 Amps
< 12 Sec.
7 0.17 Sec.
..f !
c, ,3 INSTANI N/A N/A a 2
%s
- 13) HfN0097A-All PRIMARY XSWIDAl/SC LONG TIME 525 Amps < 30 Sec. N
{ R.B. CLNG. UNIT FAN Sil0RT TlHE 1500 Amps 7 0.17 Sec. , XFN64A LHERGENCY H010R INSTANT 2250 Amps j0.09Sec.
- J
_ _ _ -.--._. - - --. - e -
-..*=-k--- .
\. i } . ! $ TABLE 3.8-1 (continued) ,
E ' g '
. CONTAINHENT PENETRATION CON 00CTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPolNT CRITERIA I E EQUIP No.-SYS/ DESCRIPTION DEVICE LOCATION TEST SElPOINT RESPONSE TIME
- 13) CONIINUED:
63ao
- XSWIDAl MAIN INCOMING BACKUP XSWlDA1/4B LONG TIME -9008 Amps 1 12 Sec. 1 i
Sil0RI TIME 9000 Amps < 0.50 Sec. INSTANT N/A N/A
- 14) MfM00960-All PRIMARY XSWIDB1/7C LONG TlHE 1260 Amps 1 30 Sec.
R.B. CLNG. UNIT FAN Sil0RT TIME S400 Amps 1 0.17 Sec. , XfN6SB NORMAL HOTOR INSTANT g Amps 5 0.09 Sec.
$ XSWIDB1 MAIN INCOMING BACKUP XSWlDBl/4B LONG TIME N Amps $ 12 Sec. l
- co Sil0RT llHE 9000 Amps < 0.50 Sec.
g INSTANT N/A N/A
- 15) MfH00970-All PRIMARY XSWIDBl/6C LONG TlHE S25 Amps < 30 Sec. ;
R.B. CLNG. UNIT FAN Sil0RT TlHE 1500 Amps 'T 0.17 Sec. XfN6SB EMERGENCY MOTOR INSTANT 2250 Amps 'N-1 0.09 Sec. : ! Gsoo :Y1 XSWIDBL HAIN INCOMING BACKUP XSWIDB1/4B LONG TlHE -9006-Amps i li Sec. Ej
; Sil0RT TINE 9000 Amps < 0.50 Sec. <>
INSTANI N/A N/A 3 F. )
- 16) XilR0004A-IIR PRIMARY XSWIDA2/SC LONG IIME 315 Amps < 12 Sec. : j 11 RECOMBINER PWR. PNL. Sil0RT TIME N/A N/A f,;, j l
TdRECOMBINERFEED INSTANT 900 Amps 5 0.09 Sec. [,l XSWIDA2 MAIN INCOMING BACKUP XSWIDA2/4B LONG TlHE 4000 Amps < 12 Sec. l Sil0RT TlHE 7200 Amps < 0.50 Sec. C' INSTANI N/A N/A ,j '
~ *
- 17) XI!R00048-ilR PRIMARY XSWIDB2/SC LONG TlHE 315 Amps < 12 Sec. u a llz RECOMBINER PWR. PNL. Sil0RT TlHE N/A N/A TO RECOMBINER FEED INSTANT 900 Amps 1 0.09 Sec.
( u . ..
I E TABLE 3.0-1 (continued) E
!a e
CONTAINHENT PENETRATION CONDUCTOR OVERCURRENT PR01ECTIVE DEVICE TEST SE1P0lNT CRITERIA E EQUIP N0.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETPolNT RESPONSE llHE
- 17) CONTINUED: '
XSWIDB2 MAIN INCOMING BACKUP XSWlDB2/4B LONG TlHE 4800 Amps < 12 Sec. SHORT. TIME 7200 Amps 7 0.50 Sec. lHSTANT N/A R/A 440 Vac CDRM PWR. CAB. LAC, CONTROL BANK A, -
- 18) HECllANISH 1 - 6
; y XCA1A-CR A59-fu13 PRIMARY XCA1A 1 -le Hillioins N/A
+
6 9 XCA1A-CR A59-ful? BACKUP XCA1A 1-le Hillfolms N/A XCA1A-CR ASl-ful PRIMARY XCA1A 1 1.4 Milliolas N/A XCA1A-CR AS7-ful BACKUP XCA1A > l'.4 Hilliolas N/A { XCA1A-CR A59-fu21 PRIMARY XCA1A 1-16 Hilliohms N/A XCA1A-CR A61-fu45 BACKUP XCA1A 1 Millioins N/A :
- 19) HECilANISH 2 -
c)m ' L i.l g,.' XCA1A-CR A59-fu14 PRIMARY XCA1A 1-le Hi'llichms N/A XCA1A-CR A59-fu18 BACKUP XCA1A 1 Hilliolas N/A .b .f , ' XCA1A-CR ASI-fu2 4-J PRIMARY XCA1A > 1.4 Hilliolas N/A I !l XCA1A-CR AS7-fu2 BACKUP XCA1A _1.4 Hillioles N/A f XCA1A-CR A59-fu22 PRIMARY XCA1A 1 dHillioins N/A j~f u XCA1A-CR A61-fu46 BACKUP XCA1A 1 40-Milliolas N/A
; s I E! IABLE 3.8-1 (continued) 3 9 CONTAINMENT PENETRATION CONDUCIOR OVERCURRENT PROTECTIVE DEVICE TEST SEIPOINT CRITERIA EQUIP NO.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETPOINT _ RESPONSE flHE CHDH PWR. CAB. LAC, CONTINUED:
- 20) HECilANISH 3 - -
XCA1A-CR A59-Ful5 PRIMARY XCA1A > Millioins N/A XCA1A-CR A59-Ful9 BACKUP XCA1A >dHillioins N/A , XCA1A-CR A52-Ful PRIMARY XCA1A > 1.4 Millioins N/A i XCA1A-CR A58-Ful BACKUP XCA1A > l.4 Milliolas _ N/A
$ XCA1A-CR A59-Fu23 PRIMARY XCA1A >MHil11olms N/A XCA1A-CR A61-Fu47 BACKUP XCA1A > W Hilliolas N/A :
- 21) HECilANISH 4 - I XCA1A-CR A59-Ful6 PRIMARY XCA1A L
> W Hilliolas N/A N
yJ XCA1A-CR A59-Fu20 BACKUP XCA1A >NHillfolms _ N/A
.., i
! XCA1A-CR A52-Fu2 lRIMARY XCA1A > 1.4 M1111olms N/A r;3 XCA1A-CR A58-Fu2 BACKUP XCA1A -> 1.4 Milliolms N/A
.i ! f j3 XCA1A-CR A59-Fu24 PRIMARY XCA1A l > W Hillioins N/A !
XCA1A-CR A61-Fu48 BACKUP XCA1A -> dHilliolas N/A ' t, . 440 Vac CDRM POWER CABINET 1AC, CONTROL DANK C, GROUP 1 uj . I 22) HECilANISH 1 -
~ f XCA1A-CR A60-Fu25 PRIMARY XCA1A >
Millioins N/A 6 XCA1A-CR A60-Fu29 BACKUP XCA1A > il& Hillioins N/A i ,
g TABLE 3.8-1 (cont.inued) E ' E CONTAINHENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRITERIA EQUIP NO.-SYS/0ESCRIPTION DEVICE LOCATION TEST SETPOINT RESPONSE TIME CRDH PWR. CAB. IAC, CONTINUED: - XCA1A-CR A53-Ful PRIMARY XCA1A > 1.4 Hilliohns N/A XCA1A-CR A57-Ful BACKUP XCA1A > 1.4 Millioins N/A i L i XCA1A-CR A60-Fu33 P;lIMARY XCA1A > 48-Hilliohns N/A L XCA1A-CR A61-Fu45 BACKUP XCA1A > 4& Hil11olms _ N/A w 23) HECilANISH 2 - (, D XCA1A-CR A60-Fu26 PRIMARY XCA1A > -le Hillioins _ N/A XCA1A-CR A60-Fu30 BACKUP XCA1A > Milliolms N/A XCA1A-CR A53-Fu2 PRIMARY XCA1A > l.4 Millioles _ N/A . XCA1A-CR A57-Fu2 BACKUP XCA1A ~> 1.4 Hillioles s. N/A
'N1'ys XCA1A-CR A60-Fu34 PRIMARY XCA1A > 48-Hilliolms N/A i.j L 'b '
XCA1A-CR A61-Fu46 BACKUP XCA1A -> 4& Milliohms N/A 1 '8 i l (:,
- 24) HECilANSlHS 3 - 4 l:
XCA1A-CR A60-Fu27 PRIMARY XCA1A > M Mi'111olms N/A f[; . XCA1A-CR A60-Fu31 BACKUP XCAIA > d Hilliohms N/A h,, XCA1A-CR AS4-Ful PRIMARY XCA1A > l.4 Millioins _ N/A l',' XCA1A-CR A58-Ful BACKUP XCA1A > l.4 Hillioles _ N/A %*
- g L ,
XCA1A-CR A60-Fu35 PRIMARY XCA1A > 1&Hillioins _ N/A
~
XCA1A-CR A61-Fu47 BACKUP XCA1A > d Hillioins _ N/A
\
m TABLE 3.8-1 (cont.inued) h
- 9 CONTAINHENT PENETRATION CONOUCIOR OVERCURRENT PROTECTIVE DEVICE TEST SEIP0lNI CRITERIA f a
EQUIP NO.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETPOINT RESPONSE TlHE , H CRDH PWR. CAB. LAC, CONTINUED:
- 25) HECilANISH 4 -
L - XCA1A-CR A60-Fu28 PRIMARY XCA1A 1 40 Hilliohns N/A 1 t. XCA1A-CR A60-Fu32 BACKUP XCA1A 140-Hillioins N/A ; l XCA1A-CR AS4-Fu2 PRIMARY XCA1A 1 1.4 Hillioins N/A l j XCA1A-CR AS8-Fu2 BACKUP XCA1A > 1.4 Milliohns N/A
$ XCA1A-CR A60-Fu36 PRIMARY XCA1A 14 Milliohns N/A XCA1A-CR A61-Fu48 BACKUP XCA1A 1 Hilliolas N/A ;
440 VAC CRDH POWER CABINET 1AC, SilulDOWN BANK A, GROUP 1 i
- 26) HECilANISH 1 -
A61-Fu41 N Hillioles XCA1A-CR PRIMARY XCA1A 1 u N/A [ XCA1A-CR A60-Fu37 BACKUP XCA1A 1 M Hilliolas N/A fJ.
J l
l XCA1A-CR ASS-Ful PRIMARY XCA1A 11.4 Hillioles N/A y j XCA1A-CH AS7-Ful BACKUP XCA1A 11.4 Hilliolas N/A l1 XCA1A-CR A61-Fu49 PRIMARY L F .' XCA1A 1 Hillioins N/A 8 -i s s .- XCA1A-CR A61-Fu45 BACKUP XCAIA 14& Milliolas N/A r,
- 27) HECllANISH 2 -
~
I k XCA1A-CR A61-Fu42 PRIMARY XCA1A 14& Hilliolas N/A j%j L XCA1A-CR I60-Fu38 BACKUP XCA1A 1 M Hillioles N/A
- , *I s 1 ee
~
1 ( I . I t i t g TABLE 3.8-1 (continued) i E l0 CONTAINHENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPolNT CRITERIA i I E EQUIP No.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETP0lNT RESIONSE TlHE A .
.-. CRDH PWR. CAB. LAC, CONTINUED:
j XCA1A-CR ASS-Fu2 PRIMARY XCA1A 11.4 Hillioles N/A f XCA1A-CR AS7-Fu2 BACKUP XCA1A 1 1.4 Millioins N/A XCA1A-CR A61-FuSO PRlHARY XCA1A 1 Hillioins N/A XCA1A-CR A61-Fu46 BACKUP XCA1A 1 NHillioins N/A
- 28) HECilANISH 3 - 6 '
y XCA1A-CR A61-Fu43 PRIMARY XCA1A 1 -l& Hilliohns N/A i NMillioins , XCA1A-CR A60-Fu39 BACKUP XCA1A 1 N/A XCA1A-CR AS6-Ful PRIMARY XCA1A 1 1.4 Millioins N/A XCA1A-CR AS8-Ful BACKUP XCA1A 1 1.4 Millioins N/A 3 .?O XCA1A-CR A61-FuS1 PRIMARY XCA1A 1 de Hilliolms N/A Ej j XCA1A-CR A61-Fu47 BACKUP XCA1A 1 Milliohns N/A ~I C)
- 29) HECilANSlHS 4 - g, -
~
XCA1A-CR A61-Fu44 PRIMARY XCA1A > 44 Hi.111olms N/A [.i XCA1A-CR A60-Fu40 BACKUP XCA1A 1 Hillioins N/A Ifh XCA1A-CR AS6-Fu2 PRIMARY XCAIA 11.4 Hillioins N/A , ' 'l XCA1A-CR AS8-Fu2 BACKUP XCA1A > 1.4 Hillioins N/A N XCA1A-CR A61-FuS2 PRIMARY XCA1A Millioles N/A 1 to XCA1A-CR A61-Fui8 BACKUP XCA1A 1 3& Millioins N/A et
. I I
u. C TABLE 3.8-1 (continued) ! . E ' Q CONTAINHENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICE TEST SETP0lNT CRITERIA . i E QUIP NO.-SYS/ DESCRIPTION DEVICE LOCAT 0N TEST SETPOINT RESPONSE TlHE . q . i' g 440 VAC CRDH POWER CABINET 2AC, SilUIDOWN BANK A, GROUP 2
- 30) HECilANISH 1 -
l L 1 XCA2A-CR A59-Fu13 PRIMARY XCA2A 1 M Hillioles N/A L XCA2A-CR A59-Fu17 BACKUP XCA2A 1 M Hilliotas N/A , t XCA2A-CR A51-Ful PRIMARY XCA2A 1 1.4 Milliolas N/A ! i - j XCA2A-CR A57-Ful BACKUP XCA2A 1 1.4 Hilliolas N/A L , 1:' XCA2A-CR A59-Fu21 PRIMARY XCA2A 14& M1111olms N/A i
? XCA2A-CR Adi-Fu45 4 .
U$ BACKUP XCA2A 1 M Hillioins N/A
) 31) HECilANISH 2 -
L
- XCA2A-CR A59-Fu14 PRIMARY XCA2A > de Hillioins
_ N/A _ XCA2A-CR A59-Fu18 BACKUP XCA2A > N/A Millioins
.7]
t ) XCA2A-CR A51-fu2 PRIMARY XCA2A 1 1.4 Hilliotas N/A [4, , XCA2A-CR A57-Fu2 BACKUP XCA2A 1 1.4 Millioins N/A I> ' s -
- )
XCA2A-CR A59-Fu15 PRIMARY XCA2A 1 -le Hilliotas N/A [Q XCA2A-CR A59-Ful9 BACKUP XCA2A 1 Hil11olms N/A ! r
- 32) HECilANISH 3 - # '
t >
- XCA2A-CR A59-Fu15 Q. 's }
PRIMARY XCA2A %' 1 W Hilliolms N/A XCA2A-CR A59-Fu19 BACKUP XCA2A > d M1111olms N/A
# 1 k g
o t m c TABLE 3.8-1 (continued) E
! s CONIAINHENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRITERIA -
E EQUIP NO.-SYS/ DESCRIPTION DEVICE 10 CATION TEST SETPOINT RESPONSE TlHE
' CRDH PWR. CAB. 2 AC, CONTINUE 0:
XCA2A-CR A52-Fu11 PRIMARY XCA2A 1 1.4 Millioins N/A XCA2A-CR A58-Ful BACKUP XCA2A 1 1.4 M1111olms N/A
' 3 6
j XCA2A-CR A59-Fu23 PRIMARY XCA2A 1 le M1111olms N/A s XCA2A-CR A61-Fu47 BACKUP XCA2A 1 1& M1111olms N/A w 33) HECilANISH 4 - < (, 1 XCA2A-CR A59-Ful6 PRIMARY XCA2A 2 -te- Hillioins N/A i j j XCA2A-CR A59-Fu20 BACKUP XCA2A 1 Hillioins N/A l XCA2A-CR A52-Fu2 PRIMARY XCA2A 1 1.4 M1111olms N/A , XCA2A-CR A58-Fu2 BACKUP XCA2A 1 1.4 Milliohns N/A ; 4 t; XCA2A-CR A59-Fu24 PRIMARY XCA2A 1 de Hillioins N/A l,.j XCA2A-CR A61-Fu45 BACKUP XCA2A > M1111olms N/A 'C* i e 440 VAC CRDH POWER CABINET 2 AC, CONTROL BANK C, GROUP 2 * (I I- 8
- 34) HECilANISH 1- i.
XCA2A-CR A60-F25 PRIMARY XCA2A 1 M1111olms N/A l T ,;f XCA2A-CR A60-Fu29 BACKUP XCA2A 1 dM1111olms N/A $ XCA2A-CR A53-Ful PRIMARY XCA2A 1 1.4 Mil 11olms N/A j ~~~~- - XCA2A-CR A57-Ful BACKUP XCA2A 1 1.4 Millioins N/A 1 e _,_.m.ww== e.w, ==>w e*N-**^- * - - " ='"#'" * - *"*-T*
~ .
~
4.- y ,
%,v \
" ~
s y , , , s - - ( ,c-*- t N, - - ,
.
04ENT PEMETRAQM CONDUC1GR OVERCURRENT PROTECTIVE DEVICEsRST SEIPalhT CRITERIA., lt \" ,g m.' 's - %, + . " " - d EQUIP NO.-SYS/DESCRIfT10N DEVICE ' LOCATION TEST SETPOINT ., . RESPONSE TIME s . H - . ' i i CRilH PWII.' CAB. 2 AC, CONTINUED: 4 y MCA2A-CR A60-Fu33 PRIMARY XCA2A N/A ) 3 46 Mil 11olms ; XCd2A-CR A61-Fu45 BACKUP XCA2A - > M1111olms . N/A v :. _, s ,' 35) MECWMJSM 2 - ~- ' ' -' ! XCA2A'CR A60-Fu26 PRIMARY XCA2A ~ > M11110tus N/A x- 6 _ XCA2A-CR A60-Fu30 BALK 8!P . ~ - XCA2A- ' > 18 Milliotas N/A i w - %,J h s 'XCA2A-CR .A53-Fu2 PRIMARY ~ ;XCA2A > 1.4 Millioins P8/A I u .. - f ' . _' M %,, XCA2A-CR ,.A57-Fu2 BACKUP XCA2A -> 1.4 Millichsis N/A f
- i. .; , s ~_
s L'- XCA2A-CR t.60-Fu34 PRIMARY XCA2A > -l& M1111olms , N/A ia s XCA2A-CR A60-u45 BACKUP ;XCA2A >. Millioins N/A C a'] , 7
- 1 i
- 36) MECilANISM 3 - c ( ) l
.,XCA2A-CR A60-Fu27 PRIMARY XCA2A > 16 Milliotas N/A 1, ;* l XCA2A-CR A60-Fu31 BACKUP XCA2A > d Millioles N/A I
- l I : I *
.'. I % XCA2A-CR 1-Ful PRIMARY XCA2A 1 1.4 Nilliotas N/A . 4.J i XCA2A-C!t' 'ALS-Ful BACKUP XCA?A > 1.4 Millioins N/A :.J 4 XCA2A-CR A60-Fu35 , PRIMARY XCA2A > Milliotas N/A f$ 's s - t I XCA2A-CR A61-Fu17 BACKUP XCA2A -> -18 Millioles N/A L ' & es ( g TABLE 3.8-1 (continued) . 4 * $ CONTAINMENT PENETRATION CONDUCTGR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRITERIA i E EQUIP NO.-SYS/ DESCRIPTION DEVICE 10 CATION TEST SETPOINT RESPONSE TIME ?1 e CRDM POW. CAB. 2AC, CONTINUED: , 37) MECilANISM 4 - L i XCA2A-CR A60-Fu28 PRIMARY XCA2A 1 1& Milliotas N/A l L ' XCA2A-CR A60-Fu32 BACKUP XCA2A 1-le Milliolas N/A i XCA2A-CR AS4-Fu2 PRIMARY XCA2A 1 1.4 Milliches N/A XCA2A-CR A58-Fu2 BACKUP XCA2A 1 1.4 Milliotes N/A b y XCA2A-CR A60-Fu36 PRIMARY XCA2A ) 1 -le Milliolms N/A i T XCA2A-CR A61-Fu48 BACKUP XCA2A > Milliohns N/A x - 440 VAC CRDM POWER CABINET 2AC, SIRIIDOWN BANK A, GROUP 2
- 38) MECilANISM 1 - i g . _ _ .
XCA2A-CR A61-Fu41 PRIMARY XCA2A 1 -le Millioins N/A f 5j XCA2A-CR A60-Fu37 BACKUP XCA2A 1 sh Milliotas N/A , i XCA2A-CR ASS-Ful -1 i PRIMARY XCA2A 1 1.4 Milliohns N/A p, , XCA2A-CR A57-Fu2 BACKUP XCA2A ! 1 1.4 M111(ohns N/A [.j XCA2A-CR A61-Fu19 PRIMARY XCA2A I 6 1 -le M1111olms N/A gf.J g, - c. l , XCA2A-CR A61-Fu45 BACKUP XCA2A l 1 le Mil 1(olms N/A g ;3 . e i ' i
- 39) MECilANISH 2 - i dj l' i & ,
XCA2A-CR A61-Fu42 PRIMARY XCA2A i 1 le Hilliohns N/A XCA2A-CR A60-Fu38 BACKUP XCA2A 1lhMilliohns N/A i $ TABLE 3.8-1 (continued) I El
- . CONTAINMENT PENETRATION CON 00CTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRITERIA i C ,
2 I f EQUIP NO.-SYS/ DESCRIPTION DEVICE 10 CATION TEST SETPOINT RESPONSE TIME CRDM PWR. CAB. 2 AC, CONTINUED: XCA2A-CR A55-Fu2 PRIMARY XCA2A 1 1.4 M1111olms N/A XCA2A-CR A57-Fu2 BACKUP XCA2A 1 1.4 Milliotas N/A XCA2A-CR A61-FuSO PRIMARY XCA2A 1 M1111olms N/A i 6 XCA2A-CR A61-Fu46 BACKUP XCA2A 1 -W Milliohns N/A w 40) MECllANISM 3 - _g ; j ) XCA2A-CR A61-Fu43 PRIMARY XCA2A 1 str M1111olms N/A on L O u XCA2A-CR A60-Fu39 BACKUP XCA2A 1 M M1111olms N/A XCA2A-CR A56-Ful PRIMARY XCA2A 1 1.4 Millioles N/A
- XCA2A-CR A58-Ful BACKUP XCA2A 1 1.4 Millioins N/A 7 G T XCA2A-CR A61-FuS1 PRIMARY XCA2A 1 4& Millioins N/A [j b i XCA2A-CR A61-Fu47 BACKUP XCA2A 1 1& Mil 11olms N/A '
i
- 41) MECilANISH 4- g, .
XCA2A-CR A61-Fu44 PRIMARY XCA2A > @ Milliotas N/A l yj XCA2A-CR A60-Fu40 BACKUP XCA2A > Millioins N/A .f.'.'.; XCA2A-CR A56-Fu2 PRIMARY XCA2A 1 1.4 Milliohns N/A [. l XCA2A-CR A58-Fu2 BACKUP XCA2A 1 1.4 Mil 11olms N/A , G .__ XCA2A-CR A61-FuS2 PRIMARY XCA2A 1 48 Milliotas N/A b XCA2A-CR A61-Fu48 BACKUP XCA2A 1 te Milliohns N/A g TABLE 3.8-1 (continueil) I !' CONTAINHENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICE TEST SE1 POINT CRITERIA E y EQUIP NO.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETPOINT RESPONSE TIME e j 440 VAC CRDM POWER CABINET 180, SliUIDOWN BANK B GROUP 1
- 42) NECilANISH I -
XCA1B-CR A59-Ful3 PRIMARY XCAIB 1 Mil 11olms N/A XCA18-CR A59-Fu17 BACKUP XCA1B 1 Milliotas N/A XCA18-CR ASI-Ful PRIMARY XCA1B 1 1.4 Milliotas N/A XCA18-CR A57-Ful BACKUP XCA1B 1 1.4 Milliotas N/A % 6 { e XCAIB-CR A59-Fu21 PRIMARY XCAIB 1 -le M111 totes L N/A i % XCAlB-CR A61-Fu45 BACKUP XCA1B 1 M Millioins N/A
- 43) MECllANISM 2 -
g -. XCAID-CR A59-Ful4 PRIMARY XCA1B -> M-Millioles N/A .-a, . XCA18-CR A59-Fu18 BACKUP XCA1B 1 Millioins N/A i s l XCA18-CR A51-Fu2 PRIMARY XCA1B > 1.4 Milliolas N/A i,. XCA18-CR A57-Fu2 BACKUP XCAIB ~> 1.4 Milliotas N/A k j: XCAIB-CR A59-Fu22 PRIMARY XCA1B > N Milliotas N/A ,h* j ; 6 : XCA18-CR A61-Fu16 BACKUP XCAIB > 48 M1111olms N/A
- j. .]
- 44) MECilANISM 3 -
to M l XCA18-CR A59-Fu15 PRIMARY XCA18 > -le Milliotas N/A I l 6 XCAIB-CR A59-Fu19 BACKUP XCAIB > iftr Millioins N/A l I l i E TABLE 3.8-1 (continued) E El e - CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT LR!TE Q E EQUIP NO.-5YS/ DESCRIPTION DEVICE LOCATION TEST SETPOINT RESPONSE TIME CRDM PWR. CAB. 180, CONTINUED: j XCA18-CR A52-Ful PRIMARY XCA18 > 1.4 Milliotas N/A XCA18-CR A58-Ful BACKUP XCA18 1 1.4 Millioins N/A ! XCAill-CR A59-Fu23 PRIMARY XCA18 1 Milliotas N/A XCAlB-CR A61-Fu47 BACAUP XCA18 1 M1111olms N/A w 45) MECilANISM 4 - 6 ) XCA18-CR A59-Ful6 PRIMARY XCA18 1-18 Milliotas N/A co _4 i a m XCA18-CR A59-Fu20 BACKUP XCA18 11tr Millioins N/A i XCA18-CR A52-Fu2 PRIMARY XCA18 1 1.4 Milliotas N/A f XCAIB-CR A58-Fu2 BACKUP XCA18 1 1.4 M1111olms N/A I3 6 ' ) XCA18-CR A59-Fu24 PRIMARY . .*. ' XCA18 1-18 MiIliotas N/A f'.1 XCAlB-CR A61-Fu48 BACKUP XCA18 > Millioins N/A : 's 3 440 VAC CROM POWER CABINET, CONTROL BANK D, GROUP 1 , ~ {,,
- 46) MECilANISM 1 - b '
L2 XCA18-CR A60-Fu25 PRIMARY XCA18 1 18 Millioins N/A - ,]
- c. . ,
XCA18-CR - A60-Fu29 BACKUP XCA18 1-18 Milliotas N/A ' .3 N XCA18-CR A53-Ful PRIMARY XCA18 11.4 Hillioins N/A : - 2 XCA18-CR A57-Ful 8ACKUP~ XCA18 1 1.4 Mil 11olms N/A 4 0 .m E TABLE 3.8-1 (continued) E ;) CONTAINHENT PENETRATION CON 00CTOR OVERCUNRENT PROTECTIVE DEVICE TEST SETPOINT CRITERIA E EQUIP NO.-SYS/ DESCRIPTION fsEVICE LOCATION TEST SETPOINT RESPONSE TlHE CRDH PWR. CAB. 180, CONTINUED: j XCA18-CR A60-Fu33 PRIMARY XCAlB 1 M111tolas N/A 6 XCA1B-CR A61-Fu45 BACKUP XCA1B 1 W Hilliolas N/A
- 47) HECilANISH 2 -
XCA18-CR A60-Fu26 PRIMARY XCAlB ( 1 -10 Mil 11olm s N/A XCA18-CR A60-Fu30 BACKUP XCAIB 1 Millioins N/A m XCAIB-CR AS3-Fu2 PRIMARY XCAIB 1 1.4 Millioins N/A XCA18-CR AS7-Fu2 BACKUP XCA1B 1 1.4 Mil 11olms N/A XCA1B-CR A60-Fu34 PRlHARY XCAIB 1 Millioins N/A , XCAIP-CR A61-Fu46 BACKUP XCA1B > Millioins N/A .' ]
- r. )
- 48) HECilANISH 3 - _4 f . _ ,)
XCA1B-CR A60-Fu27 PRIMARY XCA1B > -10 Millioins G N/A *.[,,' XCA18-CR A60-Fu31 j* BACKUP XCA18 1 18 Hi,111olms N/A . > XCAIB-CR AS4-Ful PRIMARY XCAIB 1 1.4 Millioins N/A I i. $. .j. *j XCA18-CR AS8-Ful BACKUP XCA1B 1 1.4 Mil 11olms N/A ,,.,, 6 i> XCA18-CR A60-Fu35 PRIMARY XCAlB 1-18 Hilliolms N/A > XCA18-CR A61-Fu47 Hilliohns BACKUP XCA1B 1 N/A I W. I E TABLE 3.8-1 (continued) E 9 . CONTAINHENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPolNT CRITERIA E EQUIP No.-SYS/DESCRIP' ION DEVICE LOCATION TEST SETP0lNT RESPONSE 11ME CRDM PWR. CAB. 1B0, CONTINUED:
- 49) MECilANISM 4 - L XCAlB-CR A60-fu28 PRIMARY XCAlB > 48 M1111olms N/A XCAlB-CR A60-Fu32 BACKUP XCA1B > M1111olms N/A XCAlB-CR AS4-Fu2 PRIMARY XCAlB > 1.4 Millioins N/A XCAla-CR A58-fu2 BACKUP XCAlB > 1.4 Milliotes !!/A f' u L
) XCA18-CR A60-fu36 PRIMARY XCAIB > 48 Milliotas N/A w L g XCAlB-CR A61-Fu48 BACKUP FCAIB > 48 M1111olms N/A 440 VAC CRDM POWER CABINET 180, SiluTDOWN BANK B, GROUP 1
- 50) MECilANISM 1 - L XCAlB-CR A61-fu41 PRIMARY XCAlB > 48 Milliotas N/A N-
~~ (, .~.0 XCAlB-CR A60-Fu37 BACKUP XCAlB > 18 Mil 11olms N/A Ej ( ) XCA18-CR ASS-ful PRIMARY XCAlB -> 1.4 Milliotas N/A 'J C, XCAlB-CR A57-ful BACKUP XCAlB > 1.4 Milliot.ms N/A : s XCAIB-CR A61-fu19 PRIMARY XCAlB M1111olms N/A , XCAlB-CR A61-Fu45 BACKUP XCAlB >hMillioins N/A
- 51) MECilANISH 2 - k$
XCAlB-CR A61-Fu42 PRIMARY XCAIB > Millioles N/A %* u ' XCAlff-CR A60-fu38 BACKUP XCAIB >, Mil 11olms N/A I et g TABtE 3.8-1 (continued) 4 CONTAINHENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRITERIA E . 4 EQUIP NO.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETPOINT RESPONSE TIME s-> CRDH PWR. CAB. 180, CONTINUED: XCAlB-CR A55-Fu2 PRIMARY XCAIB 1 1.4 Milliotas N/A XCA18-CR A57-Fu2 BACKUP XCA1B 1 1.4 Milliotas N/A XCAIB-CR A61-FuSO PRIMARY XCA1B > Millioins N/A ~L XCA18-CR A61-Fu46 BACKUP XCAlB 1 -l& Hil1folm s N/A
- 52) HECilANISH 3 - 4 y XCAlB-CR A61-Fu43 PRIMARY XCA18 1 -le Hilliohns N/A
- L XCAlB-CR A60-Fu39 BACKUP XCAIB 1 W Hilliolas N/A m
XCAlB-CR A56-Ful PRIMARY XCAIB 1 1.4 Millioles N/A 17 XCAIB-CR ASS-Ful BACKUP XCA1B 1 1.4 Milliohns N/A [j _g L i XCAlB-CR A61-FuS1 PRIMARY XCAlB 1 le Hilliohns N/A '1-c fN XCAlB-CR A61-Fu47 BACKUP XCAIB 1 W Hilliohns N/A 3 s -3 '
- 53) HECilANISH 4 - L .' - ~ 8 XCAlB-CR A61-Fu44 PRIMARY XCAlB > le Hilliohes N/A I ~j XCAlB-CR A60-Fu40 BACKUP XCAlB 1 Hilliohns N/A
[0] %s XCA18-CR A56-Fu2 PRIMARY XCAlB 1 1.4 Milliolms N/A N ; XCAlB-CR A58-Fu2 BACKUP XCAlB 1 1.4 Milliohns N/A XCAIB-CR A61-FuS2 PRIMARY XCAIB 1 Millioles N/A XCAID-CR A61-Fu48 BACKUP XCAlB 1 Hilliohns N/A l I E TABLE 3.8-1 (continued)
- u
. CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRITERIA 4, g I EQUIP NO.-SYS/ DESCRIPTION DEVICE 10 CATION TEST SETPOINT RESPONSE TlHE 440 VAC CRDM POWER CABINET 2 80, CONTROL BANK 8, GROUP 2
- 54) MECilANISM 1 - L t 1 XCA28-CR A59-Fu13 PRIMARY XCA28 1-14 M111totas N/A XCA28-CR A59-Fu17 BACKUP XCA28 2 -lh Milliotas N/A XCA28-CR A51-Ful PRIMARY vrA28 1 1.4 Milliotas N/A XCA28-CR A57-Ful BACKUP XCA28 1 1.4 Milliotas N/A
(, j $ XCA28-CR A59-Fu21 PRIMARY XCA28 - 1 le Millioins N/A , XCA28-CR A61-Fu45 BACKUP XCA28 > Millioins N/A w , i
- 55) HECalANISM 2 - 1 (,
XCA28-CR A59-Fu14 PRIMARY XCA28 ( 1 -l& Millioins N/A j XCA28-CR A59-Fu18 BACKUP XCA28 1 Milliolms N/A bI 8 4 XCA28-CR A51-Fu2 PRIMARY XCA28 1 1.4 Milliotas , N/A XCA28-CR AS7-Fu2 8ACKUP XCA28 1 1.4 Milliotas N/A l,s t, .: ;s XCA28-CR A59-Fu22 PRIMARY XCA28 1 1& Ml11 tolas N/A j.j XCA28-CR A61-Fu46 BACKUP XCA28 1 Millioins N/A t .J ', 56) MECilANISM 3 - (, 3J i XCA28-CR A59-Ful5 PRIMARY XCA28 1 4 Millioins N/A N I XCA28-CR A59-Ful9 BACKUP XCA28 _ (, I W 1 te M1111olms N/A l l s b E TABLE 3.8-1 (continued) - E E . CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRIIERIA E EQUIP NO.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETPOINT RES)0NSE TIME CROM PWR. CAB. 2 80, CONTINUED: XCA28-CR A52-Ful PRIMARY XCA28 1 1.4 Millioins N/A XCA28-CR A58-Ful BACKUP XCA28 1 1.4 Millioins N/A (, XCA28-CR A59-Fu23 PRIMARY XCA28 1 -I t M i l 1 1 ol m s N/A XCA28-CR A61-Fu47 BACKUP XCA28 1 Milliotas N/A w 57) MECllANISM 4 - t, ) XCA28-CR A59-Ful6 PRIMARY XCA28 1 & Milliotas N/A XCA28-CR A59-Fu20 BACKUP XCA28 1 Millioins N/A XCA28-CR A52-Fu2 PRIMARY XCA28 1 1.4'Hilliotas N/A ' XCA28-CR A58-Fu2 BACKUP XCA28 1 1.4 M111tolas N/A [j XCA28-CR A59-Fu24 PRIMARY XCA28 M1111olms N/A 1 . XCA28-CR A61-Fu48 BACKUP XCA28 1AkHilliotas N/A 1 440 VAC CRDM POWER CABINET 280, CONTROL BANK D GROUP 2 , j,
- 58) MECilANISM 1 -
g C.j XCA28-CR A60-Fu25 PRIMARY XCA28 1 -18, M1111olms N/A , ,' XCA28-CR A60-Fu29 BACKUP XCA28 1 N M1111olms N/A ,$ XCA28-CR A53-Ful PRIMARY XCA28 1 1.4 Millioins N/A I- _ _ . XCA28-CR A57-Ful BACKUP XCA28 1 1.4 Millioins N/A { !- : ~ gJ") d. '- ) j- j:
- Ci '
- [* . E' '!
e-E_ M H A E I S R N E O T P I S A A A A A A A A A A A A A A R E / / / / / / / / / / / / / / C R N N N N N N N N N N N N N N . T N I ~ O _ P _ T E S T S E T E s s s s C s s s s u i a s s s s s s I T a n n h a n m V N l h i l m l o c m m m i o l o a n E I o o o o i i l o l o l o l o i 1 l o i o D O i i i 1 l l 1 t 1 1 l 1 i i P l l l 1 l l 1 1 1 1 l l l l E T l l l l i i 1 1 l l i i l l ) V E i i i i MM 1 i i i H H i i d e I T S H H H M M H H M M H _ 4 4 - 4 4 _ u C T (,e G& 68 (,t - i n E 1 S E l- & 1 1 1 . i- 1 'l - s84 t O T 1 1 1 1 1 1 1 1 2 1 1 1 1 1 n R o P c ( T N 1 E - R 8 R U N _ 3 C O R I B 8 8 8 B 8 8 B B 8 8 B B 8 E E T 2 2 2 2 2 2 2 2 2 2 2 2 2 2 L V A A A A A A A A A A A A A A A B O C C C C C C C C C C C C C C C A O X X X X X X X X X X X X X X T R L O T C U D N , O C Y Y Y Y Y Y Y E :R P R P R P R P R P R P R P N C DA U A U A U A U A U A U A U O I EM K M K M K M K M K M K M K I V UI C I C I C I C I C I C I C T E NR A R A R A R A R A R A R A A D IP B P B P B P B P B P B P B R T T N E O N C3 5 6 0 4 5 7 1 5 7 E ,3 4 2 3 2 2 3 4 2 3 l l 3 4 P N u u u u u u u u u u u u u u O 0F F F F F F F F F F F F F F T I B - - - - - - - - - - - - - - N T 0 1 0 0 3 7 0 1 0 0 4 8 0 1 E P 26 6 6 6 5 5 6 6 6 6 S 5 6 6 M N I I R C B .A A A A A A A A A A A A A A A S A T E C 2 3 N D R R R R R R R R R R R R R R _ O / S .C C HC C C C C C HC C C C C C _ C R - - S - - - - - - S - - - - - - _ Y W0 8 I 8 8 8 8 8 8 I 8 8 8 8 8 8 _ S P2 2 N2 2 2 2 2 2 N2 2 2 2 2 2 . - A A AA A A A A A lAA A A A A A HC C HC C C C C C i C C C C C C DX _ O. X CX X X X X X CX X X X X X _ N R E E _ C H H _ P I U ) ) Q 9 0 E 5 6 EE!D . E o j. c 4 ( 1 - E TABLE 3.8-1 (continued) E !D e CONTAINHENT PENETRATION CONDUCTOR OVERCURRENT PROIECTIVE DEVICE TEST SETPOINT CRITERIA E EQUIP NO.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETPOINT RESPONSE TlHE CRDH PWR. CAB. 2 BD, CONTINUED: ; 61) HECilANISH 4 - (, XCA28-CR A60-Fu28 PRIMARY XCA2B 1 M1111olms N/A XCA28-CR A60-Fu32 BACKUP XCA2B 1ikHillioins N/A XCA28-CR AS4-Fu2 PRIMARY XCA2B 1 1.4 Millioins N/A XCA28-CR A58-Fu2 BACKUP XCA2B 1 1.4 Millioins N/A l XCA28-CR A60-Fu36 PRIMARY XCA2B 1 dHillioins N/A ! m XCA28-CR A61-Fu4B BACKUP XCA2B 1 % Hillioins N/A I [ . 440 VAC CRDH POWER CABINET 2BD, SllUIDOWN BANK D, GROUP 2
- 62) HECilANISH 1- 4, ?
XCA28-CR A61-Fu41 PRIMARY XCA28 1 de Hillioins N/A XCA28-CR A60-Fu37 & CJ BACKUP XCA2B 1 -le- Hillioles N/A f, ,j i *3 i XCA28-CR ASS-Ful PRIMARY XCA28 1 1.4 Hillioins N/A C1 i ' :- j l XCA28-CR A57-Ful [ BACKUP XCA2B 1 1.4 Millioins N/A ff.! A61-Fu49 G I'v XCA28-CR PRIMARY XCA2B 148 Mil 11olms 4 N/A C} . XCA28-CR A61-Fu45 BACKUP 2 W Hillioins f] , XCA2B N/A s i 63) HECilANISH 2 - g "4 XCA28-CR A61-Fu42 PRIMARY XCA2B 1 18- Millioins N/A I , XCA28-CR A60-Fu38 BACKUP XCA2B 1 M1111olms N/A l t 4 ( E TABLE 3.8-1 (continued) I !0 CONTAINMENT PENETRATION CON 00CTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRITERIA E EQUIP NO.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETPOINT RESFONSE TIME , CRDM PWR. CAB. 2 BD, CONTINUED: ! XCA28-CR A55-Fu2 PRIMARY XCA2B 1 1.4 Hilliotas N/A ! XCA28-CR A57-Fu2 BACKUP XCA2B > 1.4 Millioins N/A , XCA28-CR A61-Fu50 PRIMARY XCA2B > Milliotas N/A
- G l
XCA28-CR A61-Fu46 BACKUP XCA28 > W Hilliohns N/A w 64) MECilANISM 3 - L -- i ) XCA28-CR A61-Fu43 PRIMARY XCA2B -> W Milliolas N/A T3 i m i w XCA28-CR A60-Fu39 BACKUP XCA2B 6 -> 18 Millioins N/A r; 3 i y XCA28-CR A56-Ful PRIMARY XCA2B > 1.4 Milliohns N/A D XCA28-CR A58-Ful BACKUP XCA28 > 1.4 Mil 11olms N/A k g .ff) 7 XCA28-CR A61-FuS1 PRIMARY XCA2B -> & Milliotas N/A .F ..:f XCA28-CR A61-Fu47 BACKUP XCA2B 1 NMilliohns N/A [/.}
- 65) MECilANISM 4 - g, 2.$ j XCA28-CR A61-Fu44 PRIMARY XCA2B 1 -1& Milliohns N/A l
XCA28-CR A60-Fu40 BACKUP XCA2B > M1111olms N/A XCA28-CR A56-Fu2 PRIMARY XCA28 > 1.4 Milliohns N/A XCA20-CR A58-Fu2 BACKUP XCA2B > 1.4 Millioins N/A 6 XCA28-CR A61-Fu48 PRIMARY XCA2B > M Milliolms N/A XCA28-CR A61-Fu48 BACKUP XCA2B > M1111olms N/A 4 . ._____. _ .. . A t . ~, T ( - - .) -l , e vi c TABLE 3.8-1 (cont.inued) I S CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CR11ERIA . D - c EQUIPN0.-hYS/0ESCRIPTION. DEVICE LOCATION TEST SETPOINT RESIONSE TlHE h 125 V%C
- 66) OPN0007C-E0 PRIMARY yo, S,,, .
" DPNIHX/14 120 Amps ~< 00 2, . Emergency LIG. PNL. 7 gror51 g,1. (suse) 7.1.<l /pgittio},m s x BACKUP OP;0! X/".2 1500 f.;+; .; 2^-(AR;. l l > 120 VAC HISC. Jaa i
- 67) X8J0002-IC/INCORE PRIMARY APN1FX1/25 45 Amps 5 4fr Sec.
TilERH0C00PLE REF. JUNCT. x pas 461 (russ) t 4/ ni//nfus y BOX 2 BACKUP -APNITX1/27 05 f- ; < /A 50 E;. 1 '
- 68) XBJ0007-IC/INCORE .z s a TilERMOC00PLE REF. PRIMARY APN1FX1/24 45 Amps w
5 4tr Sec. JUNCT. BOX 1 XPdFabi (Fuss) 2 h BACKUP -APNIFX1/27 05-{ f2"'Sh;////o/aser ' N/A E r r - - l.. ; w - I { 69) XPN7060-CR/R00 POSITION INDICATION PRIMARY 'APN1FC1/2 X PN5272. (Fvs() 120 Amps Z 1if /rli///p4, 5 too 1 -att Sec. N i PNL. 1 . BACKUP A.^HITA/20 450 f +; 11/A 0 R;. - y lN.. ; T ;i) - 3 l C..) -BAEKUP AP" ifs /25 150 A;+; J 153 k;. [j (c.-ers. reed) c., zoo *-
- 70) XPN7061-CR/R00 POSITION PRIMARY INDICATION PNL. 2 APNIFC1/4 x PM s27L 120 Amps 21il sviilliohms 5 -38 Sec. le
..- l BACKUP APNITA/25 (Fost) 450 f.;+;. 1 1N/A ] k;. i.j (No. ? T; 4)- Q 0A=0? Aentfe/20 450 ?_#2 11502;. Il i ( S rg. T;;d)- %3 . n* .'
- 71) APN5915-EV/IRANSHITTER PRIMARY 100 APN5906/25 60 Amps 14tr Sec.
PWR. SUPPLY CAB. NO. 3 h E[ (FJi///ofge s BACKl!P APd5'll5 (Fuse) - XI?S'J00 :; tee-G L.. ; f 4)- SA00000"0 APNIFX/25 375 A;+; 1 150 S;. ( 6 .v. 6 e) . I .. s T \, # i ! E ABLE 3.8-1 (cont.inued)
- 1 E i- - @
. CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRITERIA I E EQUIP No.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETPOINT RESPONSE TIME 460 VAC HISC.
- 72) PRESS. IITR. GROUP 23,49,50 -RC PRIMARY APN4101/1 270 Amps 1 75 Sec.
; BACKUP APN4101/MN. Amps 1-M Sec. i
- 73) PRESS. IITR. GROUP 28, 55, 56 -RC PRIMARY APN4101/2 270 Amps 5 75 Sec.
BACKUP APN4101/HN. Amps 5 Sec.
- g 74) PRESS. IITR. GROUP 29, 57, 58 -RC PRIMARY APN4101/3 270 Amps 5 75 Sec.
m BACKUP APN4101/HN. Amps 1-F Sec.
- 75) PRESS. IITR. GROUP 26, 53, 54 -RC PRIMARY APN4101/4 270 Amps 5 75 Sec.
BACKUP APNfl01/HN. Amps 5 -F Sec.
- 76) PRESS. IITR, GROUP 21, 47, 48 -RC PRIMARY APH4101/5- 270 Amps Voso 1 75 Sec.
I h L3 l BACKUP APN4101/HN. -9400 Amps 1 -360 Sec. (,8
- 77) PRESS. IITR. GROUP 1, 2, 22 - RC PRIMARY APN4191/6 270 Amps 5 75 Sec. f*
BACKUP APH4101/iti. Amps < Sec. 8*J
- 78) PRESS. IITR. GROUP 5, 6, 27 -RC PRIMARY APN4101/7 270 Amps 1 75 Sec. ; IJ BACKUP APN4101/MN. #aps 1 Sec. ho')
- 79) PRESS. IITR. GROUP 3, 4, 35 -RC PRIMARY APN4101/8 270 Amps 1 75 Sec.
</00o / l BACKUP APH4101/HN. 3400 Amps 1 -360- Sec.
- ! tl \ ,
~ ]Tj*8 s i
- s. ) ~I ?L 7-l~F:
2j:] E M I E T . . . . . . . . . c . c . c . c . c . c . c . c E c e c e c e c e c e c e c e c e S e S e S e S e S e S e S e S e S N S S S S S S S S /fr O /6 / /0 I6 18 A S I' 5 7 5 3-S 7 h-S 7 6 2 5 7 0 2 5 7 lL 5 0 S S 0 I E - 2 7 2 7 7 9-R R 1 5 1 1 5 1 $ <- 1 i 5 1 5 1 < 5 E T I R . C T . N I O T P N T I s s s s s s s s E O s p s p s p s p s p s p s p s p S P p m p m p m p m p m p m p m p m T m A m A m A m A m A m A m A m A T E A A A A A A A A S S & o0 *0 o0 o0 o0 o& E T 0 o6 0 ,o0 0 .0 f, 0 o0 0 o0 0 e0 7 o5 0 0 08 T S 7 %4 4 7 2 y 4 7 2f 7 o5 2f. 7 o5 2 g. 2f 7 7 06 E E 2 - . 2 2V4 C T I V E D E ) V ' d I . . . . . . . e T N 0 N N N N N N N u C 9 H 1 M 1 H 2 M 3 H 4 M 5 M 6 H n E / / 1/ / 1/ / 1 / /2 / /2 / / / 2/ / 2 / i T N 1 2 2 2 2 2 2 2 2 t O O 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 n R I 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 o P T 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 c A N N N N N N N N N N N N N N N N ( T C P P P P P P P P P P P P P P P P N O A A A A A A A A A A A A A A A A 1 E L - R 8 R U 3 C R E E L V B O Y Y Y Y Y Y Y Y A E R P R P R P R P R P R P R P R P T R C A U A U A U A U A U A U A U A U O I M K M K M K M K M K M K M K M K T V I C I C I C I C I C I C I C I C C E R A R A R A R A R A R A R A R A U D P B P B P B P B P B P B P B P B D N O C C C C C C R C C R R R R R R N C - - - - - - - O R I - 2 2 5 8 0 6 2 T 5 4 4 6 7 7 7 A 0 R 3 , , , , , , , T : 1 8 0 7 9 5 1 E D , 5 1 2 6 6 7 7 N E8 E U , , , , , , , P N N , 4 7 9 8 9 4 1 O I 7 2 1 1 3 3 4 4 T I T N T NP P P P P P P P E P OU U U U U U U U M I CO .O O O O O O O ' N R R R R R R R R R I C . G G G G G G G G A S C T E S . . . . , . . . N D I R R R R R R R R O / MT I T T T T T T C S H H I I I I I I I I I I I I Y C S A . . . . . . . . - VS S S S S S S S S S S S S S S S O. 0E E E E E E E E N 6R R R R R R R R , 4P P P P P P P P P _ I U ) ) ) ) ) 1, Q 0 1 2 3f) V )2 s% (, l i f 7 )i E 8 8 8 S 4 ( f t f 8 ENEe g y* 9 +* ! , , l ,! ,l ' ; ! :f ' ; I ' , : ~ i i ; I E TABLE 3.8-1 (continued) I , 5
- . CONTAINNENT PENETRATION CON 00CTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRI1ERIA E
j EQUIP NO.-SYS/0ESCRIPTION DEVICE LOCATION TEST SETPOINT RESPONSE TINE ,
- i t 460 VAC MISC. CONTINUED
IV) PRESS. IITR. GROUP 43, 73, 74 -RC PRIMARY APN4102/7 270 Amps 5 75 Sec. BACKUP 'APN4102/MN. Amps Sec. i 9 , , f)s) PRESS. HTR. GROUP 15,16, 40 -RC PRIMARY APN4102/8 270 Amps 1 75 Sec. , BACKUP APN4102/Hil. Amps 5 Sec. c., 49) PRESS. IITR. GROUP 46, 77, 78 -RC PRIMARY APN4102/9 270 Amps N 1 75 Sec. i deoo / co BACKUP APN4102/MN. -M8e Amps $ ftwr Sec. j 9) PRESS. HIR. GROUP 9,.10, 32 -RC PRIMARY APN4103/1 270 Amps ' 5 75 Sec. sao 3. : ; BACKUP APN4103/MN. Amps 1 1-35tr Sec. c3 fW) PRESS. IITR, GROUP 11, 12, 35 -RC PRIMARY L '8* APN4103/2 270 Amps -< 75 Sec. !l ' s. ., 2 C BACKUP APN4103/MN. -E400 Amps : > j 3 5 950 Sec. ,; 97) PRESS. HTR. GROUP 31, 59, 60 - RC PRIMARY L-APN4103/3 270 Amps i 75 Sec. [.. j l BACKUP APN4103/MN.. 3ooo 240& Amps 2 CJ $ GS8 Sec. q ,, , PRESS. IITR. GROUP 36, 65, 66 -RC i ) PRIMARY APN4103/4 270 Amps %3 '< 75 Sec. 3ooo 2 BACKUP APN4103/MN. -3400 Amps 5 GS& Sec. _. 9 PRESS. IITR. GROUP 13, 14, 37 -RC PRIMARY APN4103/5 270 Amps 5 75 Sec. BACKUP . z APN4103/MN. Amps i SS& Sec. ' l . i TABLE 3.8-1 (continued) !E , e CONIAINHENT PENETRATION CONDUCIOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRITERIA ' i E EQUIP No.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETPolNT RESPONSE TIME L 460 VAC HISC. CONTINUED: 9f) PRESS. IITR. GROUP 33, 61, 62 -RC PRIMARY APN4103/6 270 Amps ' 5 75 Sec. 3 0a* 2-BACKUP APN4103/HN. f46& Amps 5 956 Sec. PRESS. IIIR. GROUP 34, 63, 64 -RC PRIMARY APN4103/7 270 Amps 5 75 Sec. l 3 eoo % BACKUP APN4103/HN. -e466 Amps 5 -350 Sec. I w j 480 VAC HOTOR CONTROL CENTERS ) 44 XfH0066A-All/RB CilARC0AL PRIMARY XHCIA3X/10GK 1500 Amps N/A , 9 CLEANUP UNIT FAN A g 20a -l BACKUP XHCIA3X/10GK 210 Amps r- -- -- - 9 5 Sec. *t. J I W() XPP0138-ND/ LEAK PRIMARY XHCIA3X/41L 225 Amps N/A 8 . DETECTION SUHP PUMP [3. ., BACKUP XHCIA3X/41L 4S Amps 5 100 Sec. r3 ) XD0 0001-IC/ TERM. BOX FOR INCORE NEUIRON DETECTOR DRIVES A,B,C.D,E PRIMARY XHCIA3X/3EG 45 Amps 5 100 Sec. [. F'j a . BACKUP XHCIA3X/3EG, 45 Amps s, . 3 g 5 100 Sec. j 'A . 10jl) XVG9593A-CC/H0V REACT. COOL PRIMARY XHCIA3X/91H Pump A TilERHAL Barrier 33 Amps N/A (m f., j BACKUP XHCIA3X/91H 45 Amps /so W ; 5 -36 Sec. L l t .e . .h E TABLE 3.8-1 (continued) I @ CONTAINHENT PENETRATION CONDUC10R OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRITERIA E EQUIP NO.-SYS/ DESCRIPTION DEVICE ' LOCATION TEST SETPOINT RESPONSE T1HE 4 ' e + 480 VAC HISC. CONTINUED: ' 14l) XPP0149-SW/DRPI COOLING PRIMARY XHCIA3X/llAD 225 Amps N/A UNIT BSTR. PUNP BACKUP XHCIA3X/llAD 45 Amps 1 100 Sec. , 3 it ; 10% XFN0068 / SECONDARY COMPT. PRIMARY XHCIA3X/llEli 720 Amps N/A 6 (LOOP A LG. FAN A BACKUP XHCIA3X/llEli 150 Amps 1 200 Sec. R 10 XFN0069A-All/ SECONDARY COMPT. PRIMARY XHCIA3X/10CF 720 Amps N/A * (LOOP B) CLG. FAN A , cn b BACKUP XHCIA3X/10CF 150 Amps 1 200 Sec. i 5 . log) XFN0070A-All/ SECONDARY COMPT. PRIMARY XHCIA3X/9A0 720 Amps N/A (LOOP C) CLG. FAN A g BACKUP XHCIA3X/9AD 150 Amps 5 200 Sec. {]
- 10f) XPP0051A-WL/R.C. DRAIN PRIMARY XHCIA3X/6CG 720 Amps N/A I -l TANK - PUMP A g,3 1
BACKUP XHCIA3X/6CG. 210 Amps 5 200 Sec. 'i"j i iqs) XPP0059A-N0/INCORE INSTR. PRIMARY XHCIA3X/4AD 225 Amps N/A }.- ! CilASE SUHP PUHP A , r.~) . i !, l 1 BACKUP XHCIA3X/4AD 45 Amps 1 100 Sec. g _ '<. i 107) XPPollSA-ND/R.B..SUHP PRIMARY XHCIA3X/4Eli 87 Amps N/A j PUNP A l BACKUP XHCIA3X/4Eli 45 Amps 1 100 Sec. l I +# l t ' E TABLE 3.8-1 (continued) I !D . CONTAINHENT PENElRAfl0N CONOUCTOR OVERCURRENT PROTECTIVE DEVICE TEST SE1PolNT CRITERIA i j EQUIP NO.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETPOINT RESPONSE TIME 9 480 VAC HCC*, CONTINL'ED: 8
- 148) XTF9003-EH/ RECEPTACLE PRIMARY XHCIA3X/1AC 240 Amps -< 200 Sec. ;
TRANSFORMER 3 ' BACKUP XHCIA3X/ LAC 240 Amps 1 200 Sec. 1 ) XVG9576-CC/H0V, PRIMARY XHClB2X/SIM 225 Amps N/A ISOLATION RCDT BACKUP 60 Amps 5 100 Sec. w I ! ) lld)XVG9583-CC/H0V, PRIMARY XHCIB2X/3AE 225 Amps N/A co GATE EXCESS LEIDOWN llX di ' j BACKUP XHClB2X/3AE 45 Amps 5 100 Sec. 11/) XFH00078-All/ REFUELING WATER PRIMARY XHClB3X/9AD 87 Amps N/A SURFACE SUPPLY FAN B ; N BACKUP XHClB3X/9AD 45 Amps $ 100 Sec. 73 I H - 11h)XFH00668-M/R.B.CllARC0AL CLEANUP UNIT FAN B PRlHARY XHC183X/10FJ 1,500 Amps N/A f.Il *1. j i 4 BACKUP XHC183X/10FJ 210 Amps 5 200 Sec. ( t
- f:3 u.
Ild's XXP00598-N0/INCORE INSTR. PRIMARY XHCIB3X/3Eli 225 Amps N/A .~3 CllASE SUHP PUMP B .f"4 BACKUP XHC183X/3Eli 45 Amps $ 100 Sec. S l . .j ,s, ll#) XPP0ll58-N0/R.B. SUMP PRIMARY XHCIB3X/31L 87 Amps N/A ~ . , - PUMP B j / BACKUP XHClB3X/31L 45 Amps i 100 Sec. I. , - s \,-. ., , i . ; t
- v. TABLE 3.8-1 (continued) c i
] , G CONTAINHENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRilERIA e l E EQUIP NO.-SYS/0ESCRIPTION DEVICE LOCATION TEST SETF0 INT RESPONSE TIME " i e (, 480 VAC HCC, CONI ~INUED: , 11X) APN4005-EH/480 VAC PRIMARY XHC183X/SCE 270 Amps 1 200 Sec. POWER PNL.-FEEDER l BACKUP XHC183X/SCE 270 Amps i 200 Sec. l 1 240 Amps 115) XTf8009-EH/ TRANSFORMER FOR PRIMARY XHC183X/SilJ 1 200 Sec. ' LIGilTING PNL. 9 (NORMAL LTG.) i I XHCIB3X/SILI 240 Amps ' BACKUP 1 200 Sec. t' 1 ) XFN00688-All/ SECONDARY COMPT. PRIMARY XHCIB3Y/3AD 720 Amps N/A * (LOOP A)CLG FAN B '? . $ BACKUP XHC183Y/3AD 180 Amps 5 200 Sec. . 1 XfN00698-All/ SECONDARY COMPT. PRIMARY XHC183Y/3Eli 720 Amps N/A l (LOOP B) CLG FAN B ._ i l to BACKUP XHCIB3Y/3Eli 180 Amps i 200 Sec. ] ( .) 119) XFN00708-All/ SECONDARY COMPT. PRIMARY XHClB3Y/31L 720 Amps N/A L ') l (LOOP C) CLG. FAN B l f.1 BACKUP XHC183Y/3IL. 180 Amps . ~< 200 Sec. : ; ! I ):1 12A) APN4012-EH/ WELDING RECEPT. PRIMARY XHC183Y/7GL 600 Amps i 300 Sec. ,l 6 PWR. PNL. , (. l, BACKUP XHC183Y/7GL 600 Amps 1 300 Sec. [l 2 %s i 121) APN4013-EH/WELDlHG RECEPT. PRIMARY XHCIB3Y/%L 600 Amps 1 300 Sec. M i PWR. PNL. _ i i BACKUP XHCIB3Y/SGL 600 Amps < 300 Sec. l 0 4 4 em ~ f I ! l i E TABLE 3.8-1 (continued) I I E O e CONTAINHENT PENETRATION CONDUCTOR OVERCURRENT PR01ECTIVE DEVICE TEST SETPOINT CR11ERIA i E ! EQUIP N0.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETP0lNT RESPONSE TlHE 3 480 VAC HCC, CONTINUED: I?/) R.C. PUNP C llEATER-RC PRIMARY XHCIB3Y/ SAD 225 Amps N/A i BACKUP XHCIB3Y/ SAD 45 Amps 5 100 Sec. 1 R.C. PUNP C, Olt LIFT PHP -RC PRIMARY XHCIB3Y/ Sell 450 Amps N/A BACKUP XHCIB3Y/SEH 75 Amps 5 100 Sec. S w IPA) XPP00 SIB-WL/R.C. DRAIN PRIMARY XHCIB3Y/8GK 720 Amps N/A D TANK PUNP B m 200 : BACKUP XHCIB3Y/8GK 210 Amps h (* 3 5-9fr Sec. 125) X1F8008-EH/ TRANSFORMER FOR PRIMARY XHCIB3Y/4Hf 240 Amps 1 200 Sec. __ LIG. PNL. 8, UNDERWATER LIGilTING .g BACKUP XHC183Y/41tJ 240 Amps 5 200 Sec. : ; 7 8 3 l ,j 12X) XVG95938-CC/H0V, RC PUMP B PRIMARY XHCIB3Y/4AE 225 Amps N/A TilERHAL BARRIER , f. ,, l
- BACKUP XHClB3Y/4AE 45 Amps < 100 Sec. 1 s -
17/) XFN0068C-All/ SECONDARY COMPT. PRIMARY XHCIC3X/8AE* 1500 Amps N/A i.a (LOOP A) CLG FAN C - 6ACKUP XHCIC3X/8AE 210 Amps -< 200 Sec. t ! 9 .,, ,. '"'~* 124) R.C. PUMP B llEATER -RC PRIMARY XHCIC3X/ Sell 225 Amps N/A BACKUP XHCIC3X/ Sell 45 Amps 1 100 Sec. l' l ! 0 $ j ** . - - - i '3 ( , I E TABLE 3.8-1 (continued) I = ! ! . CONTAINHENT PENETRATION CON 00CTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRITERIA E EQUIP NO.-SYS/ DESCRIPTION DEVICE LOCATION TEST SEIPOINT RESPONSE TIME 30 480 VAC HCC, CONTINUED: 199) R.C. PUNP B OIL LIFT PUNP -RC PRIMARY . XHCIC3X/6 Ell 450 Amps N/A ; ; BACKUP XHCIC3X/6Eli 75 Amps 5 100 Sec. I 138) XFN0069C-All/ SECONDARY COMPT. PRIMARY XHCIC3X/2Eli 720 Amps N/A (LOOP B)CLG. FAN C BACKUP XHCIC3X/2Eli 150 Amps 1 200 Sec. l w 2 ) IST) XFN0070C-All/ SECONDARY COMPT. PRIMARY XHCIC3X/21L 720 Amps N/A !' m (LOOP C) CLG FAN C BACKUP XHCIC3X/2IL 150 Amps 1 200 Sec. ; 3 ' 137) XIF8006-EH/ TRANSFORMER FOR PRIMARY XHCIC3X/4CE 240 Amps 1 200 Sec. l LIG. PNL. 6, NORMAL LIGilTING BACKUP XHCIC3X/4CE 240 Amps 1 200 Sec. 4 : , 13J) XVG9593C-CC/H0V, R.C. PRIMARY XHCIC3X/41H 225 Amps N/A C .)I I
- PUNP C TilERHAL BARRIER i, ; '
BACKUP XHCIC3X/41H 45 Amps 5 100 Sec. *D $ ,1 13#) XFN0107-VL/ CONTROL R00 POSIT. DATA CAB. CLG FAN PRIMARY XHCIC3X/2AD 450 Amps N/A sy fd f N BACKUP XHCIC3X/2A0 75 Amps 1 100 Sec. g,., 4 ( s 13ff) R.C. PUNP A ilEATER -RC PRIMARY XHCIC3X/ SAD 225 Amps N/A (! t BACKUP XHCIC3X/ SAD 45 Amps $ 100 Sec.[ j l E $ m ' l c i I TABLE 3.8-1 (continued) ' g ' s CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROIECTIVE DEVICE TEST SETPOINT CRITERIA E EQUIP No.-SYS/ DESCRIPTION DEVICE LOCATION TEST SElPOINT RESPONSE TIME 1 480 VAC MCC, CONTINUED: ' 13#) R.C. PUMP A OIL LIFT PUMP -RC PRIMARY XMCIC3X/6A0 450 Amps N/A BACKUP XMCIC3X/6A0 75 Amps $ 100 Sec. 13bXFN0007A-AN/REFUELINGWATER PRIMARY XMCIC3X/3Eli 87 Amps N/A SURFACE SUPPLY FAN A BACKUP XMCIC3X/3 Ell 45 Amps ,, w 5 100 Sec. L D 139) XFN0008-All/ REFUELING WATER PRIMARY XMCIC3X/3IL 720 Amps N/A j 9 SURFACE EXilAUST FAN BACKUP XMCIC3X/3IL 150 Amps 1 200 Sec. ;. 9 140) XVG9605-CC/MOV - R.8. PRIMARY XMCIDA2X/31H 45 Amps -< 100 Sec. l BACKUP 5 XMCIDA2X/31M 45 Amps 5 100 Sec. .M, I 141) XVG8701A-Ril/RilR LOOP 1 PRIMARY XHCIDA2X/7FJ 225 Amps N/A a I$ INLET ISOLATION VLV. J : ] BACKUP XMCIDA2X/7FJ 45 Amps $ 100 Sec. , ;
- 142) XVG8808A-SI/ ACCUMULATOR A PRIMARY il;-.i XMCIDA2X/8AE 300 Amps ISOLATION VLV. 1 200 Sec. ; ,,1 i
BACKUP XMCIDA2X/8AE 300 Amps 1 200 Sec. ["j f' s .%. g 1 'N i, s. E i ' TABLE 3.8-1 (continued) Y m CONTAINHENT PENETRATION CONDUCTOR OVERCURRENT PROIECTIVE DEVICE TEST SETPolNT CRITERIA E EQUIP No.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETPOINT RESPONSE TlHE 480 VAC HCC, CONTINUED: 143) XVG8808C-SI/ACCUMULA10R C 7 PRIMARY XHCIDA2X/8Fjif 300 Amps
- ISOLATION VLV. 5 200 sec. ,
1 j BACKUP XHCIDA2X/8FJ 300 Amps 1 200 sec. 144) XVG8000B-RC/ PRESS. PRIMARY XHCIDA2X/61H 225 Amps N/A RELIEF ISOLATION VLV. w BACKUP XHCIDA2X/61H 45 Amps D 1 100 sec. m 145) XVG3108A-SW/R.B. PRIMARY XHCIDA2Y/16IN 45 Amps g Recirc. Unit A -Isolation V1v. 1 100 sec. BACKUP XHCIDA2Y/161H 45 Amps 1 100 sec. t 146) XVG31088-SW/R.B. PRIMARY XHCIDA2Y/ISCG 45 Amps i -< 100 sec. @] 1 Recirc. Unit B - Isolation Viv. + i ca BACKUP XHCIDA2Y/ISCG 45 Amps 1 100 sec. l, , ' 147) XVG3109A-SW/R.B. PRIMARY XHCIDA2Y/1 Sill 45 Amps < 100 sec. C#
- Recirc. Unit A - Isolation Vlv. ,
f BACKUP 45 Amps XHCIDA2Y/ISill 5 100 sec. i.j . l 148) XVG31098-SW/R.B. PRIMARY XHCIDA2Y/14CG 45 Amps Recirc. Unit 8 - Isolation Viv. 1 100 sec. , ( ) ~> BACKUP XHCIDA2Y/14CG 45 Amps "' d 3 100 sec.L J. en ,! h m , c- TABLE 3.8-1 (continued) I 5 -e . H CONTAINMENT PENETRATION CON 00CTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRITERIA EQUIP NO.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETPOINT RESPONSE TIME 480 VAC MCC, CONTINUED: 149) XVT8112-CS/ SEAL WATER PRIMARY l XMC10A2Y/3IM 45 Amps 1 100 Sec. ., RElliRN ISOLATION VLV. BACKUP XMCIDA2Y/31M 45 Amps ca 1 100 Sec. ) 150) XVG87018-Ril/RilR LOOP 3 PRIMARY XHCIDA2Y/181M 225 Amps N/A m INLET ISOLATION VLV. ; i <k BACKUP XMC1DA2Y/18IM 45 Amps 1 100 Sec. IST) XVG8000C-RC/ PRESS. RELIEF PRIMARY XMCIDB2X/8Dil 225 Amps N/A ISOLATION VLV. , 1 1 BACKUP XHC1DB2X/80ll 45 Amps 1 100 Sec. i 152) XVG3100C-SW/R.B. RECIRC PRIMARY c'J XHC1082Y/18IM 45 Amps 1 100 Sec. c:.3 UNIT C ISOLATION VLV. l f.j'j i BACKUP XHCIDB2Y/181H 45 Amps 1 100 Sec. 8D L'> 153) XVG31080-SW/R.B.RECIRC. PRIMARY XMC1082Y/19IM 45 Amps UNIT 0 ISOLATION VLV. 1 100 Sec. [~ , y.; j BACKUP XHCIDB2Y/191H 45 Amps 1 100 Sec , l e 154) XVG3109C-SW/R.B. RECIRC t > PRIMARY XHClDB2Y/20 IM 45 Amps UNIT C ISOLATION VLV. " -< 100 Sec. %J -"'4 BACKUP XMCIDB2Y/20lM 45 Amps 1 100 Sec. ' I I O s E TABLE 3.8-1 (continued) I . H1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRITERIA b . EQUIP NO.-SYS/0ESCRIPTION DEVICE ] LOCATION TEST SETPOINT RESPONSE TIME 480 VAC HCC, CONTINUED: 155) XVG 31090-SW/R.B. RECIRC. PRIMARY XHCIDB2Y/211H 45 Amps UNIT D ISOLATION VLV. 1 100 Sec. BACKUP XHCIDB2Y/211H 45 Amps 5 100 Sec. 156) XVG 8702A-Ril/RilR LOOP 1 PRIMARY XHC1DB2Y/4AE 225 Amps N/A INLET ISOLATION VLV. w BACKUP XHCIDB2Y/4AE 45 Amps D 0 -< 100 Sec. ~ co 157) XVG 8702/-Ril/RilR LOOP 3 PRIMARY XHCIDB2Y/4Fg$ 225 Amps N/A ? J. INLEl ISOLATION VLV. ;f BACKUP XHCIDB2Y/4FJ 45 Amps $ 100 Sec. % 158) XVG 8808B-SI/ ACCUMULATOR 8
- TI
' PRIMARY XHCIDB2Y/161H 300 Amps -< 200 Sec. l ISOLATION VLV. Q BACKUP XHCIDB2Y/161H 300 Amps 5 200 Sec. j g) I 159) XVG 8000A-RC/ PRESS. RELIEF PRIMARY XHCIDB2Y/3IM 45 Amps ISOLATION VLV. N/A f3 - "f s. BACKUP XHCIDB2Y/31H 45 Amps 1 100 Sec. L :j 160) XVG 8095A-RC/ REACTOR llEAD VENT PRIMARY XHCIDA2X/SlH 225 Amps N/A f !e cn VLV. 10 PRESS. RELIEF TANK '! .s. BACKUP XHCIDA2X/SIM 45 Amps 1 100 Sec 4 9 4 E TABLE 3.8-1 (continued) 3 : E! CONTAINHENT PENE1 RATION CONDUCIOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRITERIA ; E i EQUIP No.-SYS/ DESCRIPTION DEVICE LOCATION TEST SETPOINT RESPONSE TIME I 480 VAC HCC, CONTINUED: 161) XVG 80958-RC/ REACTOR llEAD VENT YM VLV. TO PRESS. RELIEF TANK PRIMARY XHCID82Y/23FJ yAmps WA BACKUP XHCIDB2Y/23FJ 60 Amps 5 100 Sec. 162) XVG 8096A-RC/ REACTOR llEAD VENT PRIMARY XHCIDA2X/7AE 22S Amps N/A VLV. TO PRESS. RELIEF TANK BACKUP XHCIDA2X/7AE 60 Amps 1 100 Sec. l m 163) XVG 80968-RC/REAC10R HEAD VENT PRIMARY XHCIDB2Y/121H 225 Amps N/A h VLV. TO PRESS. RELIEF TANK BACKUP XHCID82Y/121H 60 Amps $ 100 Sec. W. I *Tp : M) XVG 7503-Ac.[c4pm CootanG W ATE st ou TLET V t.V. TRIMARf )(hCJ DA2)(/111M 225 Amps gg w,, 3/lcxuP 60 Amps & 100 3ec. Xmcf D42X/11IM Ll ns) xvs vso2-AC/CKm consa* Paisen 22s A e s N/A ! WhTER yNLif VLV. xmez.os2x/7xm ,s . ,,, Backup (,o Amf5 S ### A#C- ,' 8 XMCI DS 2X[7Im l---- J. O t 0 ~ ' , ^;G f,;' ~ M j ~ q J . a. o . -s! : .g -d. / . L , 'l t - 1 */ - ,1 , , s , o* . ,1 ; 'j s4 t 8 \. , e L ?* - g Q 'l s es , ,, -: / '? - r r s:e ., f
- RADI0 ACTIVE EFFLUENTS
/, M-- "' c GAS ST'JRAGE TANKS [IIbuf{~OQyn^1 "k
- M f.1
,1 , <~ff ..< , - - , , { LIMITING CONDITION FOR' OPERATION . , i s' ' , ~ l 3.11.2.6 c The quantity of radioactivity contained in each gas storage (tank . ^ p .r shall be liiai;.ed to less taan or equal f,o150,000 curies noble gases,(ponsidered t , a Je-133). . . 1 ; '., e / / j 4 - i
- r
}/ APPLIC,%ILIT M At a?I' timeis. / # ) ' > ' / 3 - M ,4 /j- ,f , t _ - +/ [.f e ' ACTION: J . G. ' y . = ., . . ,: ) ,
- a. %ithThe quantity of radioacti#jaaterial in any gas st'c'rwe tank .
s exceeding the above limiti,irmediately , suspend all aMitions of ,/<. radioactive material to the t.tnk anc'Nithin *~# 48 hours reduce the tant 'r - a ( ;f , c7 . contents to within the lid t.~ f I . /4 r a . -l ' J The provisions of Specifications 3d.Y an\ 8d 1.0.4 are not applicable. b. , / - : o ' i . ,e /* > i ./ ' '#s( ) SLEVEILLANCE REQUIREMENTS --- - ? ' '! ' tr *
- o j p.r _ _ _ _ , .w-r-e-----------
4.;11.2.6 The quantitv of radioacihu restepal contained in each gas 'sli;oragei .s ' tank ishall be deterniisd to be 'dthin t;1e above 7indt at least once Der,24 5 hourt whe6 radToactive 4.eterials are being]iddec'to tne tank. 'i//,, J - , e ,j,, ., e i . J ^' ; 4 ,1 / .. , 4 ,'< f , , ( ') l ,;.n l j . ,, ; %4 + -f . f! i I.< / ,. f, a .l , ',,/ .-r ' \ ; J , j p' ,.*A t i f * !$ a ~ -a -j , s s, i, s / ,. , .< e: y l ' # ~*- '/ '/ J ' ! j i f ,e # n ' i Ej J i / ){p l ,, P r i j . . } t i '%. t , ,/ q . ., / nr , luu' ./ ~ ,. l , ' , ;; o \ \ $ s , s' y . .r'
- 3. j ~ ! je i < A s l -,<Jf-j +, g r i
.[# JrI ,e j ~ j ,y .,. ,, - r - S j t O + Y ? / ~\ ,, f, I , ,' ' # ' /' , .
- p. '\ '
l . , l71 w.f 't [ SijMMER - UNIT 1 3/4 11 I.8 - , - . r, = ,. ; t, j# c - ~ ~ - POWER DISTRIBUTION LIMIT BASES HEAT FLUX HOT CHANNEL FACTOR and RCS FLOWRATE and NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued)
- c. The control rod insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are maintained.
- d. The axial power distribution, expressed in terms of AXIAL FLUX t
DIFF,ERENCE, is maintained within the limits. F N will be maintained within its limits provided conditions a. through
- d. above are maintained. As noted on Figures 3.2-3 and 3.2-4, RCS flow rate and F may be " traded off" against one another (i.e. , a low measured RCS flow rsteisacceptableifthemeasuredFhisalsolow)toensurethatthe calculated DNBR will not be below the design DNBR value. The relaxation of N as a function of THERMAL POWER allows changes in the radial power shape F
for all permissible rod insertion limits. R , as calculated in 3.2.3 and used in Figure 3.2.3, accounts for F" t less than or equal to 1.49. This value is used in the various accident N influences parameters other than DNBR, e.g., peak clad analyses where F temperature and thus is the maximum "as measured" value allowed. R2 , as l defined, allows for the inclusion of a penalty for rod bow on DNBR only. Thus knowing this "as measured" values of Fh and RCS flow allows for " tradeoffs" in excess of R equal to 1.0 for the purpose of offsetting the rod bow DNBR penalty. When an F measurement is taken, an allowance for both experimental error q ~ and manufacturing tolerance must be made. An allowann of 5% is appropriate for a full core map taken with the incore detector flux mapping system and a 3% allowance is appropriate for manufacturing tolerance. The radial peaking factor Fxy(Z) is measured periodically to provide assurance that the hot channel factor,0F (Z), remains within its limit. The limit for Rated Thermal Power (F x ) as provided in the Radial Peaking R F Factor Limit Report oer specification 6.9.1.14 was determined from expected power control maneuvers over the full range of burnup conditions in the core. When RCS flow rate and F are measured, no additional allowances are H necessary prior to comparison with the limits of Figures 3.2-3 and 3.2-4. N have been Measurement errors of Dita.% for RCS total flow rate and 4% for F allowed for in determination of the design DNBR value. [YO B 3/4 2-4 : SUMMER - UNIT 1 l _ ._ . . ,_ _ _ . - - _ _ . _ _ _ _ __. - . - _ _ I . j -l$J5TU M6 M (uA - 6 HSE 3 M b % /Are(d Q sag @gy SYSM 1 AbMu%%tri ( kf.a.O Several automatic logic functions included in this specification are not necessary for Engineered Safety Feature System actuation but their functional capability at the specified setpoints enhances the overall reliability of the Engineered Safety Features functions. These automatic actuation systems are purge and exhaust isolation from high containment radioactivity, turbine trip ' and feedwater isolation from steam generator high-high water level, initiation of emergency feedwater on a trip of the main feedwater pumps, automatic transfer of the suctions of the emergency feedwater pumps to service water on low suction pressure, and automatic opening of the containment recirculation sump suction valves for the RER and spray pumps on low-low refueling water storage tank level. h l G 3/q 3-n 1 - - - - - . . _ _ ~__ - 3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 .' REACTOR COOLANT LOOPS A-10 COOLANT CIRCULATION The plant is designed to operate with all reactor coolant loops in operation, and maintain DNBR above 1.30 during all normal operations and anticipated transients. In MODES 1 and 2 with one reactor coolant 1000 not in operation this specification requires that the plant be in at least HOT STANOBY within 1 hour. In MODE 3, a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, single failure considerations require that two loops be OPERABLE. In MODE 4, and in MODE 5 with reactor coolant loops filled, a single reactor coolant loop or RHR loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops (either RHR or RCS) be OPERA 8LE. . In MODE 5 with reactor coolant loops not filled, a single RHR loop provides ~ sufficient heat removal capability for removing decay heat; but single failure considerations, and the unavailability of the steam generators as a heat removing component, require that at least two RHR loops be OPERABLE. The operation of one Reactor Coolant Pump or one RHR pump provides adequate . flow to ensure mixing, prevent stratification and produce gradual reactivity ' changes during boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with boron reduction will, therefore, be within the capability of operator recognition and control. , f 30s o? The restrictions on starting a Re# tor Coolant Pump with one or5here RCS cold legs less than or equal to $P5?F are provided to prevent RCS - pressure transients, caused by energy additions from the secondary system, which could exceed the limits of Appendix G to 10 CFR Part 50. The RCS will be protected against overpressure transients and will not exceed the limits of Appencix G by either (1) restricting the water volume in the pressurizer and _ thereoy providing a volume for the primary coolant to expand into, or (2) by restricting starting of the RCPs to when the secondary water temoerature of eacn steam generator is less than 50*F above eacn of the RCS cold leg temperatures. ~, SUMMER - UNIT 1 3 3/4 4-1 4 i REACTOR COOLANT SYSTEM BASE 5 PRESSURE / TEMPERATURE LIMITS (Continued) The second portion of the heatup analysis concerns the calculation of pressure-temperature limitations for the case in which a 1/4T deep outside surface flaw is assumed. Unlike the situation at the vessel inside surface, 1 the thermal gradients established at the outside surface during heatup produce stresses which are tensile in nature and thus tend to reinforce any pressure stresses present. These thermal stresses, of course, are dependent on both the rate of heatup and the time (or coolant temperature) along the heatup - ramp. Furthermore, since the thermal stresses, at the outside are tensile and increase with increasing heatup rate, a lower bound curve cannot be defined. Rather, each heatup rate of interest must be analyzed on an individual basis.
- Following the generation of pressure-temperature curves for both the steady-state and finite heatup rate situations, the final limit curves are produced as follows. A composite curve is constructed based on a point-by-point comparison of the steady-state and finita heatup rata data. At any given temperature, the allowable pressure is taken to be the lesser of the -
three values taken from the curves under consideration. The use of the composite curve is necessary to set conservative heatup limitations because it is possible for conditions to exist such that over the course of the heatup camp the controlling condition switches from the inside to the outside and the pressure limit must at all times be based on analysis of the most critical criterion. Finally, the composite curves for the heatup rata data and the cooldown rate data are adjusted for possible errors in the pressure and temperature sensing instruments by the values indicated on the respective curves. Although the pressurizer operates in temperature ranges above those for which there is reason for concern of non-ductile failure, operating limits ' are provided to assure compatibility of operation with the fatigue analysis performed in accordance with the ASME Code requirements. .300 Y The OPERABILITY of two PORVs or an RCS ven opening of at least 2.7 souare _ inches ensures that the RCS will be protected rom pressure transients wnich could exceed the limits of Appendix G to 10 R part 50 when one or more of the i RCS cold legs are less than or equal to 2947 Either PORV has adequate relieving capability to protect the RCS from overpressurization when the l transient is limited to either (1) the start of an idle RCP with the secondary ! water temperature of the steam generator less than or equal to 50*F above the RCS cold leg temperatures or (2) the start of a HPSf pump and its injection l into a water solid RCS. l I v.r. - .. SUMMER - UNIT 1 3 3/4 4-la i i ~ EMERGENCY CORE COOLING SYSTEMS ON' h 'Dw,,' % rw 1 46dj %ff , BASES ECCS SUBSYSTEMS (Continued) 3gV The limitation for a maximum of one centrifugal charg ng pump to be OPERA 8LE and the Survei] lance Requirement to verify all cha ging pumps except the required OPERA 8LE charging pump to be inoperable below F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV. The Surveillance Requirements provided to ensure OPERA 8ILITY of each component ensures that at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERA 8ILI1Y is maintained. Surveillance requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1) prevent total pump flow.from exceeding runout conditions when the system is in its minimunr resistance configuration, (2) provide the proper flow split between injection points in accordance with the assumptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level of total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses. 3/4.5.4 BORON INJECTION SYSTEM The OPERABILITY of the baron injection system as part of the ECCS ensures that sufficient negative reactivity is injected into the core to counteract any positive increase in reactivity caused by RCS system cooldown. RCS cooldown can be caused by inadvertent depressurization, a loss-of-coolant accident or a steam line rupture. The limits on injection tank minimum contained volume and boren concentration ensure that the assumptions used in the steam line break analysis - are met. The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics. 1 The OPERABILITY of the redundant heat tracing channels associated with the baron injection system ensure that the solubility of the baron solution will be maintained above the solubility limit of 135*F at 22,500 ppm baron. 3/4.5.5 REFUELING WATER STORAGE TANK The OPERA 8ILITY of the Refueling Water Storage Tank (RWST) as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA. The limits on RWST minimum volume and boren concentration ensure that 1) sufficient water is available within contain-ment to permit recirculation cooling flow to the core, and 2) the reactor will remain subcritical in the cold condition following mixing of the RWST and the l l l SUMMER - UNIT 1 8 3/4 5-2 I l , e . CONTAINMENT SYSTEMS BASES 3/4.6.1.4 INTERNAL PRESSURE The limitations on reactor building. internal pressure ensure that 1) the reactor building structure is prevented from exceeding its design negative . pressure differential with respect to the outside atmosphere of 3.0 psig and
- 2) the reactor building peak pressure does not exceed the design pressure of 57 psig during steam line break conditions.
The maximum peak pressure expected to be obtained from a steam line break
- event is 47.1 psig. The limit of 1.5 psig for initial positive containment pressure will limit the total pressura to 47.1 psig which is less than design pressure and is consistent with the accident analyses.
3/4.6.1.5 AIR TEMPERATURE The limitations on reactor building average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for a steam line break accident. i 3/4.6.1.6 REACTOR BUILDING STRUCTURAL INTEGRITY is limitation ensures that the structural integrity of the containm ained comparable to the original design standards for
- ife of will be the facility. a tural integrity is required to ensure tha containment will withstand the max. pressure of 47.1 psig in the t of a steam line of containment n lift off force, the break accident. The measur e visual examination of tendons, tensile tests of the tendon wires stran ,
or surfaces of the containment, and anchorages and exposed interior and trate this capability. the Type A leakage test are s sient to o . The surveil requirements for demonstrating tn . *ainment's structural integrity n conoliance with the recommendations of Regula cuide 1.35 "Inse ' e Surveillance of Ungrouted Tendons in Prestressed Concrete c inment ~ ctures", January 1976. See ne.xt ?"1C. '32 SUMMER - UNIT 1 B 3/4 6-2 - - . _ . . _=. . . 1 40 CONTAINMENT SYSTDfS , t 2 BASES 3/4.6.1.6 REACTOR BUILDING STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the containment will withstand the ==r1=nne pressure of 47.1 psig in the event of a steam line break accident. The measurement of conc =fn=ent tendon lift off force, the tensile . tests of the tendon wires, the visual aw==ination of tendons, anchorages and t exposed interior and exterior surfaces of the containment, and the Type A leakage - test are sufficient to demonstrace this capability. . The ' tendon lift o'ff forces are evaluated to ensure that 1) the rate of tendon force loss is within predicted limits, and 2) a minimum required prestress level . exists in the conc =inment. In order to assess the rate of force loss, the lift off force for a tendon is compared with the force predicted for the tendon times a reduction factor of 0.95. This resulting force is referred to as the 95% Base Value. The predicted tendon force is equal to the original stressing force minus losses due to elastic shortening of the tendon, stress relaxation of 2' the tendon wires, and creep and shrinkage of the concrete. The 5% reduction on the predicted force is intended to compensate for both uncertainties in the prediction techniques for the losses and for inaccuracies in the lift-off force measurements. In order for'the tendon lift off force to Be indicative of the level of pre-stress force in the conc =4nment,_each-measured-force-must-be adjusted--for the knova differences which exist among the tendons due to original stressing force and elastic shortening loss. This adjustment is accomplished through the use of a No==14 Has Factor (NF (c)). This fmanr _is added to tha~1ift- off forca, which results in the Normalized Lift Off Force. The Normalizing Factor is given by: ~ NF i (c) = {Fave(o) - F i (o)} {l - 100 } + AFas { 2N 1} {F,y,(o) - F t(o)} is the group average lock-off force at original stressing, _ minus the original stressing force for the specific tendon. SR(t) is stress relarmeion (percent) which occurs at time e after original ._ stressing. AF is the total elastic shortening tendon force loss. n is the stressing sequence comprising the specific tendon. N is the total number of stressing sequences for the group of tendons which comprise the specific tendons.
- i refers to the specific tendon.
t refers to the time after original' stressing of the current inspection period. l The surve'illance requirements for demonstrating the containment's structural l integrity are in compliance with the recommendations of Proposed Revision 3 to Regulatory Guide 1.35, " Inservice Inspection of Ungrouted Tendons in Prestressed B 3/4 6-2a, *: t CONTAINMENT SYSTEMS BASES (Continued) Concrete Containments, " April 1979, except that in place of the Lower Limit and 90: Lower Limit defined by these Regulatory Guides, the 95: Base value and 90: 2 Base Value, respectively, are used. t i l l i 1 a as , aa .m.ve W previws f(5t- u l pqtt . eamet ent ; .switalh4 , ! l ausstiset statties , l
- 0
== C a eYas-. / N l h / s( 4 734 seitging - Y i , I.c,.,, O , .+ , eeuw O ":" . . . === - i M%
- "% y I
,,0, ,, _S$*O 9' "' sinut r.::" i - e l's'" N:s \ - 6 e _:. :r,== . ,. s .4_ }.. ==, uniset esions O ,,,,J inriewsiirs seitsin 8- + i = e J --o . O A, .to e m' m LJ-o. N - ==,;.,;=-~ O - ao un r n n rwein uwesta AI .O .n l V I . I i r=3 , SOUTH CAROLINA ELECTRIC & GAS CD. VIRGIL C.SUt.WER NUCLEAR STATION Fotentially Radioactive Caseous NOTE: See. Figure 5.1-4 for sita bounda y Waste Relasse Points for gaseous effluents FIGURE 5.1-3 S N - UNIT 1 5-4 / qh - , ,, ,_ anm a us p,t 97f.ra % "I Pw.-s7 V. ^ {- Slf? AAfA s 22cc ACPTs f \; _ ,- ~ _ ._5 _ - \ M is .- = t C'. E. - tfi '!~ 1Asnrtet.3 . MONTICELLO RESERVOIR auwat3 '.*. sicmacc::. . FAc:t.17T::3. " H 1 { 1 l ,su ' ,g:.:. . - -, y. C, , Y l lf f , ( :I _m i og d [ AuXII lARY z' ". Sult.ctNG ';_.3m a4, ' _ au , j v [\ ~ T . 15 -F' "o 3 _ / b g scavics WATER -- y .? , PCNC . .' iL N , ,,c = . AW * ""i!1 . e ^ / suss 7 cu cT Anag -i: ,5::::::g j ., - -- j:s ' ' i.!% z:: / _h 7 I f,Jr .euuu,(' N w n wT poco l i N'mcuAntAsu ,/ - - .@sNe ( i/ ~ ( l e e scaa. m erre 2 o; .J os .sco moo . = N Ej E ueuvo er'_r2sts: SOUTH CAROLINA ~L3C'31C & GAS C:2. h FAIRFIEL3 PUMST3 sTCMAct FACH.!TY PENSTCCX3 w ucuso waste 790ctssINC sys ts '1 (s) 89ccI3sts s? tau cENERATCM st.cwcewN @CIRCULATU:G *Arzx casexAact cauri, Loescien of Iieuid (~ - w uupacerssz3 s rau cracat:cn st.cwecwn ls4 M NC aelease ?ci=cs % ccM *AAINS nM eees ret.EAtst: . YIGU - *g h
- QSITE BowvMRf PoM GMEcus RELDf5ES \
MER.- UNIT 1 *" , g 4. . =- _ , T@ PR8SF &IBiBY COPY ~ l 6.0 ADMINISTRATIVE CONTROLS - 6.1 RESPONSIBILITY . . . . 6.1.1
- The Mana.ger, Virgil C. Summe,r Nuclear' Stat; ion shall be iesponsible for .
overall unit operation and shall delegate in, writing.the succession to this- - responsibility during his absence. ~' * - 6.1".~2 The Shift Supervisor shall be responsible for unit operations. .A . management directive to this .effect, signed by the Vice Presidentj..d ".ng L ;. t-:.e -Nuclear Operations, sha}} be reissued to all station personnel on an
- annual basis. ' -
6.2 ORGANIZATION 0FFSITE . ~ 6.2.1 The offsite orga5ization for unit management and technical support shall be as shown on Figure 6.2-1. ~ UNIT.' STAFF . v' 6.2.2 The uniti organization shall be as shown on F.igure 6.2-2 and: '
- a. Each on-duty shift shall be composed of'at least the minimuni shift crew composition shown in Table 6.2-1. p
- b. At lasst one licaa**dJeactorJlperator .shall be in the control room when fuel is in the reactor. In addition, while the unit is in
~ HODE 1, 2, 3 or 4, at least one Licensed Senior Reactor Operator , shall be in.the Control Room.. - .' c. A health physics technician # shall be .on site when fuel is in the - - I reactor.
- d. All CORE ALTERATIONS shall be observed and directly supervised by either. a licensed ' Senior Reactor Operator or Senior Reactor Operator Limited to Fue1 Handling who has no other concurrent responsibilit-ies '
during this operation. , , , . ~' ~- - a ... .
- e. A site Fire Spigade of at least 5 members shall be maintained onsite at all times. The Fire Brigade shall not include the Shift Supervisor and the other 2 members of the minimum shift crew necessary for safe shutdown of the unit and any pe.rsonnel. required for other dssential functions during a fire emergency.
s , "The health physics technician and Fire Brigade composition may be less than i the minimum requirements for a period of time not be axcaed 2 hours in order ; to accommodate. unexpected absence provided immediate action is taken to fill
- t the required positions. ,
. 8 , - _ _ . - . . _ . - , _ . - , . , . , _ , - _ , . . . _ _ - . . . , _.--.,--o-,, ,.---__w-- ._,-..--.,--m.-- . , _ - _ . - . _ . . . . -,-- .,,m. -- - - - _ , - - .,- I le * ~. . r:Es tt>CitT
- p _
AIID Clllr.T g/CAAtleS
- i l , 3 '.
*. iciu!"^C OFFICER . . .3 . . . C3 - ;l ' .O ' j li I
- EXECUTl"E f
. i f , EXECUTIVE VICC FRESIDENT VICF. rRd51 DENT ,orgpAT1 1 TIS g, y,, pngf,,7 I . m , AO^:' ' ' "" e uen pggges gg _ 2 f a saste' Of e rs rt *M j I = * * ~a .llli
- I
#~ % , VICE FRESIDCHT -553>lc 4 *~ & CRDur EXECUTIVE VICE PRESIDENT VICE FRE51 DENT c * ' ,RATEJZZL'C'0:'/ - . .. ; T -.. ; .. . . . .; ; ^.-^;T Z :^;M';" Q ru:CitA51HG 4 D'ClHEERillG & IIUCLEAR OPERATIOH5 TJ 4 KCr. '" " C0HSTRUCT10H N e . i_ e - ) e . . l 6 l . EUCLEAR "',; ^ ^ " ^ ' i. .^'I IlUCLEAR : . NUCLEAR . EDUCATl05 ENCINEEAINC QUALITY CollTROL, flUCLEAR OPERAT1055 & TRAlsisc i SERVICES . & LICD15tHC i 1 FURCitA51 1G l 4 CottSTRUCTIOll 1 . , 1 - I 3 L . .w l I J. ~ o l i Vfiga'" - i p l'UCt. EAR -" IluCLEAR ritTSICS & NUCLEAR iluCLEAR OrERATIONS OPERATlotti TEclihlC.N i HUCLEAR (8UCLEAR f FUEL EllVIROllllENTAL Tulttil;G Tulpit:C; i QUALITY ColsTROL QUALITY ASSURANCE llAllACDIEffi yg.ggg LICENSINC EttCINEERIHC SECURITY STATT Surr0R'.] _ i CFf 5tf C .s -- - . .* ,5
- lil0EFENDENT ,
s IWIAGER - 5AIETT
- N V. C. SIRetER l*
- El8CINEERING HUCLEAR STATION
- l, C80Ur I . .. .
STAT 10%. STATlors e STATI0tt STAT 10ll STATION
- OrERAT0A Curi QUALITY QUALITY $ECURITT .
TRAlsit:c IulN!!#*lI CollTROL ASSURANCE , PIGURE G'.21 SOUTH CAROLINA ELECTRIC AND GAS COMPANY 1 ( VIRGIL C. SUMMER NUCLEAR STATION l OFFSITE ORGANIZATION 1 - ,.
- I
= . . Nale: This organlaallon may be used for major maintenance and modificallon. ** ' .!, . I * ~ _ q ., .. 5_ _ . .,, l ?R00F & !!EtREWto?Y. l ADMINISTRATIVE CONTROLS - . .~ - ~ 6.5.2 NUCLEAR SAFETY REVIEW COMMITTEE (NSRC) . .. >- FUNCTION - - 5.5.2.1' The~ Nuclear Safety Review t.ommittee shalI. function to provide . ' "' . ~ independent review and audit of designated activities in the areas of: ~ nuclear power plant operations
- a. - -
. ,b: nuclear engineering . . 'c. chemistry and radiochemistry / .
- d. metallurgy -
.~ . ~
- e. instrumentation and con. trol .
- f. radiological safety ~
- g. mechanical and electrical engineering :
- h. quality assurance practices -
COMPOSITION . 6.5.2.2 NSRC l ~ appointed bytalk consist of a Chairma'n an h tfi'eiYice President 2-d C- u; :.gops"c'.x .. .... or more other members Operations. No more than a mincrity of the members of the NSRC shall have line responsibility for the operation of the unit. .. , ~ l The HSRC members shall hold a Bachelor's degree in an engir.eering'or ' physical- ! science field or equivalent experience and a minimum of five years of technical experience of which a minimum of three years' shall be in one or more of the disciplines of 6.5.2.la through h. In the aggregate, the membership of the . committee'shall. provide specific practical experience in the m'ajority of the - disciplines of 6.5.2.la through h. .s . ' ~ -ALTERNATES . - su one 6.5.2.3 All alter President rd "*-"patypembers - _n =ti 1: "tr'::r shall be appointed Operations; however, in writing no moreby.the7Vice than two alter' nates shall participate as voting members in NSRC activities at any one timet ,r . . CONSULTANTS - 6.5.2.4 Consultants shall be utilized as determined by the NSRC Chairman to provide expert advice to the NSRC. 6-3 ~ .i ADMINISTRATIVE CONTROLS '0ITS
- 5.2.8 Th NSRC shall have cognizance of the audits -1isted below. Audits may l
be performed by using established SCE&G groups such as the ISEG and QA or by outside groups as determined by'the NSRC. Audit reports or summaries will be the i basis for NSRC action:
- #. a.
The conformance of unit operation to provisions contained within the
- _ '. Technical Specifications and applicable license conditions at least once per 12 months. *
- b. The performance, training and qualifications of the entire unit '
staff at least once per 12 months. . c. The results of actions ~tiken to correct deficiencies. occurring in _ unit equipment, structures, systems or method' of operation that , ~ affect nuclear safety at least once per 6 months. ~
- d. The perfo~rmancifor adiv;Gu requi' red by t'he Operational Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months. .
e. The Emergency Plan and im~plementing procedures at least once per 24 months. _
- f. ' The Security Plan and implementing procedures at least once per
,.- 24, months. : _g. - Any_oggg,ar_ea_ of_ unit _operap,i,ogconsidered appropriate by the NSRC or theAVice President, rd 5 -; r-""- "" ' '- Operations.
- h. The Fire Protection Program and implementing procedures at least
.once per 24 months.
- i. An independent fire protection and ' loss prevention inspection and audit shall be performed. annually utilizing either qualifi'ed offsite licensee personnel or a qualified outside firm.
.t. An inspection and audit of the fire protection and loss prevention ~ program shall be performed by an outside qualified fire consultant at intervals no greater than 3 years.
- k. Th'e radiological environmental monitoring program and the results thereof .at least once per 12 months.
- 1. The OFFSITE DOSE CALCULATION MANUAL 'and; implementing procedures at least once per 24 months. '
- m. rocedure The PROCESS solidification CONTROL of radioactive PR0 GRAM wastes at leastand implementing 24 months. p'once per.s
'n. The performance of activities required by the Quality Assurance Program to meet' the criteria of Regulatory Guide 4.15, Revision 1, February 1979 at least once per 12 months. JHORITY 34,, 6.5.2.9 The NSRC shall report to and advise thetVice President ad Cr=p b '" k.i.., t 'm Operations on those areas of responsibility specified in Sactions 6.5.2.7 and 6.5.2.8. ^ l . ,k.lf . . .___ i - l ADMINISTRATIVE CONTROLS CORDS .. ~ ' 6.5.2.10 Records of NSRC activities shEl be prepared, approved and distributed as indicated below: .
- a. Minu .of each MSRC meeting #N"" allpe prepared, J-
~ to Ice President W "- "- " 'approved and fowarded ^" Operations within ,, . 14 days following each meeting. - . i.
- b. Reports of reviews encompassed by Sect ,o.n,,j.5.2.7 above, shall be ;,
prepared, approved and forwarded to th)etV1ce President M C g fews' r -. - w. n .-u- Operations within 14 days following completion of . the review. .
- c. Audit summary reports ence=pasgd.by Section 6.5.2.8 above, shall be .
forwarded to the NSRC and to theWice President M Cr:4 O n *f r e j",# *' j b.. Operations. Full audits shall be forvarded to the management ' positions responsible for the areas audited within 30 days after - '-~ completion of the audit by the auditing organ,izatlin. - 6.5.3 TECHNICAL REVIEW AND CONTROL , * , ~ . . ACTIVITIES . 6.5.3.1 Activities which affect nuclear safety shall be conducted as follows: ~' - a. Procecures required by Technical Specification 6.8 and other procedures which affect . plant nuclear safety, and changes @ . WT-';-Sh*hMhereto, shall be prepared, reviewed and approved. Each such procedure or peg'cedure change shall be reviewed by an incividual/ group other than the individual / group which prepared the pixeGre or vroredure t:hange, but who any be from the same organization as the individual / group which prepared the procedure or procedure change. Procedures other than Ad:;;inistra- ' tive Procedures will be approved as delineated in writing by the ' Station Manager. The Station Manager will approve administrative . procedures, security implementing procedures and emergency plan implementing procedures. Te=porary approval to procedures which clearly do not change th: intent of the approved procedures can be made by two members of tt.e plant management staff, at least one of Ehom holds a Senior Reactor Operator's License. For changes to procedures which may involve a change in intent of.the approved -' procedures, the person authorized above to approve the procedure , shall approve the change. M'
- b. Proposed changes or mcdifications to plant nuclear safety-related structures, systems and ccmponents shall be reviewd as designated by ~
the Station Manager. Each such modification shall be dyigned as authorized by Nuclear Engineering and shall be reviewed by an indivicual/ group other tnan the incividual/ group which designed the-modification, but who may be from the same organization as the individual / group which designed the modifications. Implementation of modifications to plant nuclear safety-related structures, systems and components shall be concurred in by the Station Manager. }&R 0 3 E 6-11 ';: *. ;, 1132 SUMMER - UNIT 1 ENCLOSURE 2 INFORMATION REQUIRED FROM THE APPLICANT TO COMPLETE THE TECHNICAL SPECIFICATIONS FOR V. C. SUMMER, UNIT 1 Specification 4.8.1.1.2.c - Diesel generator fuel oil sampling program - 1. Specific gravity of oil.
- 2. Specification 3/4.2.3 " Reactor Coolant System Flow Rate..." - revised Figure 3.2-3 including measurement a uncertainty of + 3.5% for flow.
l l l l I l i i ENCLOSURE 3 PROPOSED TECHNICAL SPECIFICATIONS UNDER REVIEW BY THE STAFF
- 1. Specification 3/4.3.3.3, " Seismic Instrumentation" - Applicant's proposal e
dated May 24, 1982
- 2. Specification 3/4 8.3, "0nsite Power Distribution Systems" - Applicant's proposal dated May 24, 1982.
- 3. Specification 3/4 12.1, " Monitoring Program" - Applicant's proposal dated June 14, 1982 1
l l .-}}