ML20086D179
| ML20086D179 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/18/1991 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20086D177 | List: |
| References | |
| NUDOCS 9111260002 | |
| Download: ML20086D179 (21) | |
Text
~
,. y. ,
ENCLOSbn 3 l PLANT HATCH - UNIT 1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 i RE00EST TO REVISE TICHNICAL SPEClflCAT10M 10 DELElE UNDERVOLTAGF RELAY TABLE Paae Chance Instructions Remove Paag insert Pug [
11 ii 3.2-1 3.2-1 3.2-23b 3.2-23b 3.2-23c 3.2-23c 3.2-49a 3.2-49a 3.2-49b 3.?-49b 3.'L 68 3.2-68 ,
3.2-68a 3.2-68a i 3.9-4 3.9-4 3.9-12 3.9-12 e
002152 E3-1 9111260002 o1111s 7
- FTR ADOCK 03000321- g
...- - r F D R .- z-j :-
- v. ~
g y., , -
,,,,,,.y_ , _ . , _g , , . , , ,9 ,,.gy9 , .-,. , , , -.e ye p9 ,9- . g g- y _
-- _ . . _ _ ...____.__...__m.____ _ . _ _ _. _ _ _ _ . _ . _ _._ _ _ _ .
,. .=, -
SURVLlttANCE R[0glRlMENTS
__ _ LIM 111NG CONin DONS FOR OPERAll0N 3.2. PROT [CTIV[ INSTRUMENTAil0N (CONT') 4.2. PR0l[CilVC INSTRUMENTATION (CONT') 3.2-1 E. Instrumentation Which C. Instrumentation Which 3.2-1 Initiates or Controls the initiates or Controls the LPCI Mode of RHR LPCI Mode of RHR F. Instrumentation Which F. Inst.umentation Which 3.2-1 Initiates or Controls Initiates or Controls Core Spray Core Spray G. Neutron Monitoring G. Neutron Monitoring 3.21 Instrumentation Which Instrumentation Which initiates Control Rod Initiates Control Rod Blocks Blocks F. Radiation Monitoring H. Radiation Monitoring 3.2-1 i
$ystems Which limit Radio- Systems Which Limit Radio- !
activity Release activity Release j
\
- 1. Instrumentation Which int 1. Instrumentation Which Int- 3.2-1 '
tiates Recirculation Pump tlates Recirculation Pump Trip Trip J. Instrumentation Which Mon- J. Instrumentation Which Mon- 3.2-1 itors leakage into The itors leakage into The Drywell Drywell K. Instrumentation 'Jhich K. Instrumentation Which 3.2-1 Provides Surveillance Provides Surveillance Information Informdion L. Degraded Station Voltage L. Degraded $tation Voltage 3.2-1 Protection Instrumentation Protection Instrumentation M. (Deleted) 3.2-1 M. (Deleted)
I N. Instrumentation Which Arms N. Instrumentation Which Arms 3.2-1
.Lcw Low Set S/RV System Low Low set $/RV System 4.3. 3.3-1 3.3. REACTIVITY CONTROL REACTIVITY CONTROL A. Core Reactivity Margin A. Core Reactivity Margin 3.3-1 B. Inoperable Control Rods B, Operable Control Rod 3.3-1 Exercise Requirements C. Control Rod tiriu 3ystem C. Control P,od Drive System 3.3-2 D. Minimum Count Rate for D. Minimum Count Rate for 3.1-4 Rod Withdrawal Rod Withdrawal E .' Rod Worth Inventory E. Rod Vorth inventory 3.3-4 Determination Determination ,
F. Operation With a Limiting F. Operation With a Limiting 3.3-5 Control kod Pattern Control Rod Pattern HATCH - Oh!T 1 11 m.,o.m.w.au ,..
_ _ . . . _ . _ . . , .._.2. _ . _ _ . _ . . _ . . _ , - - - _ _ . _ , _ . . _ - , - _ _ _ . .- _ .. _ . - _ - - . , , , __
. . _ . . _ . . . _ _ _ _ _ _ _ _ _ . _ . ~ . _ -_ _ _ ._._.__. _ _ __
N UnnUG CONDM10NS t0R OPERA 110N $URVLlLLANCE R[QulREMEN15
)
3.2 PRoliCTIVf IN51RVMINTAT MN 4.2 [.R01[CTIVf IN51RUMitiLAl10!j fulinbility Jpaliabillif The Limiting Conditions for Operathn -lhe Surveillance Requirements apply to the' plant instrumentation apply to the instrumentation wnich performs a protective function, which performs a protective function.
Obiective Oh.iective The objective of the Limiting Condi- The objective of the Surveillance tions for Operation is to assure the Requirements is to specify the type operability of protective instrumen- and frequency of surveillance to tation. be applied to protective instru-mentation.
Soecifications fpnifications ,
The Limiting Conditions for Operation The check, functional test, and of the protective instrumentation af- calibration minimum frequency for fecting each of the following protec- protective instrumentation affect-tive actions shall be as indicated in ing each of the following protec-the corresponding LCO table, tive actions shall be as indicated in the corresponding SR table.
i Protettive Acti3n LCO lahit SR Table A.-Initiates Reactor Yessel 3.2-1 4.2-1 and Containment Isolation B. Initiates or Controls HPCI 3.2-2 4.2-2 C. Initiates or Controls RCIC 3.2-3 4.2-3 D. Initiates or Controls ADS 3.2-4 4.2-4
- E. Initiates or Controls the 3.2-b 4.2-5 LPCI Mode of RHR
-f. Initiates or Controls Core 3.2-6 4.2-6 Spray G. Initiates Control Rod Blocks 3.2-7 4.2-7 H. Limits Radioactivity Release 3.2-8 4.1 8
- 1. Initiates Recirculation Pump 3.2-9 4.2 9 Trip J. Monitors Leakage into the 3.2-10 4.2-10 Drywell K. Providos Surveillance 3,2-11 4.2-11 Information L. Degraded Station Voltage 3.2-12 4.2-12
,. Protection-Instrumentation l M. (Deleted) .
3.2-13 4.2-13 I
N. Arms the Low Low Set S/RV 3.2-14 4.2-14 System l
\ <
HAitii - UNIT 1 3.2-1 k:\wpttechsp\h\2P3-2&4. pro \?52-103 ,
i-
-r
]l .
% TABLE 3.2-12
-4
$~ DEGRADED STATION VOLTAGE PROTECTION INSTRUMENTATION i: e
'E Action to be Teken
[ Required Channels if the Number of l R.f. No. Instrument Opernble Required Tnp setting Regarred Operable
~
j leL (b) Charmels '
To Trip Chews is Net Vat i
i 1 4.16 kw Emergency Bus 2/ Bus 2/ Bus greater thers or equel to 2800 (c)
! Undervoltage Re!ay veits. At 2800 volts twne deley (Loss of Voltage will be less than or egaal to Condition) 6.5 ec.
2 4.16 kw Emergency Bus 2/ Bus 2/ Bus greeter then or equel to 3280 (c)
Undervottage Relay volts. At 3280 watts tune deley (Degraded Voltage will be less then or equal to Condition) 21.5 sec.
w N
NOTES FOR TABLE 3.2-12 N
w 7 e. The cetumn entitled "Ref. No.* is only for converwence so that e one-to-one refetionstup con be estabbshed between items in Table 3.212 and items in Table 4.2-12.
b .. This instrumentation is required to be operable during reactor startup, power operation. and het shutdown.
I V
- c. With the number of operabie channels one less then the required operable channois, operation eney proceed unti performance of the next requwed instrument functional test provided a trip segnal is pieced in the LOSP lock-out refey logic for the oppkceble inoperetde channel, f
c+
(D O
3*
in V
/
7
/
se T
w I
N t!E N
9 O *
/
N tri N
f w
O CD
- ~
5 B
E 5 et a E Q d z n b E
!c a
HATCH - UNIT 1 3.2-23c k:\wp\techsp\lP3-252. pro \252-108
~
T
=. .
.9 I TAERE 4.2-12
>4 DEGRADED STATION VOLTAGE PROTECTION INSTRUVENTATION
[
i Instrument Functional Instrument C
= Test Meremum C4& sten Ref. No. Instrument instrument Check
[ (a) (b)
Mrdmum Freaucacy Fecco* m Me Fraw m w
Once/menth Oncefoperetmg 1 4.16 kV Emerg*>rry Bus N/A cyt:le Undervottage Reisy
' Loss of Voltage Corwisteon)
Once/opeestmg N/A Once/rnonth 2 4.16 kV Emergency Bus cycle Urdervoltage Hetsy I
(Degraded Vcitage l Condit.on) ta l
- NOTES FOR TABLE 4.2-12 The column ..etitfed *Ref. No." is ordy for convervence so that e one-to.one relatensQ can tse estableshed between items in Tetde 3.2-12 and etems m Tet%e 4.2-12.
no e.
- b. Surveillance of this instramentation is required dunng reactor startup, power operation, and hot shutdown.
X.
K T
/
c*
O O
~T m
V
/
7
/
w T
(4 s
M (J1 N
9 O
/
M (11 N
4 w
O C3
s ,
S w
s
<1 a
w 0 a 1 5 "J T
e I
HATCH - UNIT 1 3.2-49b k:\wp\techsp\h\lP3-252. pro \252-88
-_ -. - - - . - - - _ - - - --_ - - _ - - - . - - . - - ~ - - - - -
ItASES FOR LIMITING CONDITIONS FOR OHRATION 3.2.J.4. Scintillation Detector for Monitorina Radiciodine (Continutd1 level reading is indicative of a leak in the nuclear system process barrier in the primary containment. A sample that is continuously drawn from the primary containment is collected on an iodine filter and monitored by a gann:a sensitive scintillation detector. Radiation levels are read out by a log rate meter and recorded on a strip chart located in the control room. A high radiation level alarm and a failure alarm are also provided and are annunciated in the control room. Also, a high-low flow alarm is annunciated in the control room.
$. Qi Tubes for Monitorina Noble Gnu A set of GM tubes contained in an instrument rack are used to monitor the release of noble gases in the drywell and torus. A high radiation level reading is indicative of a leak in the nuclear system process barrier in the primary containment. A sample that's continuously drawn from the primary containment is passed through a shielded sample chamber which contair.s the beta sensitive GM tubes. Radiation levels are read out by a log rate meter and recorded on a strip chart located in the control room.
A high radiation level alara and failure alarm are provided and are annunciated in the control room. Also, a high-flow alarm is annunciated in the control room.
K. Instrumentation Which Provides Surveillance Information (Table 3.2-111 for each parameter monitored, as listed in Table 3.2-11, there are two channels of instrumentation txcept for the control rod positions indicating system and the Post-Accident Effluent Monitors. By comparing readings between the two channels, a near continuous surveillance of instrument performance is available. Any significant deviation in readings will initiate an early recalibration, thereby maintaining the quality of the instrument readings.
The hydrogen and oxygen analyzing systems consist of two redundant, separate systems and are each capable of analyzing the hydrogen and oxygen content of the drywell-torus simultaneously. They are designed to be completely testable at both the analyzer rack and in the control room. With an oxygen concentration of less than 8 by volume, a flammable mixture with hydrogen is not possible.
L. Deoraded Station Voltaae Prottetton Instrumentation (Table 3.2-121 {
The undervoltage relays shall automatically initiate the disconnection of offsite power sources whenever the voltage setpoint and time delay limits have been exceeded. This action shall provide voltage protection for the emergency power systems by preventing sustained degraded voltage conditions due to the offsite power source and interaction between the offsite and onsite emergency power systems. The undervoltage relays have a time delay c.aracteristic that provides protection against both a loss of voltage end degraded voltage condition and thus minimizes the effect of short duration disturbances without exceeding the maximum time delay, including margin, I that is assumed in the FSAR accident analyses, i
HATCH - UNIT 1 3.2-68 X:\wp\tecnsp\h\2P3-2&4. prot 252-103
- s ,
BA$f $. FOR LIM 111i COND1110NS IOR OPERATION H. (Deleted) !
N. Instrumentation Which Arts low Low set System (Table 3.2-14)
The bases for these trip functions are found in the bases for Section 3.6.H.
page 3.6-21.
3.2.1 References
- 1. FSAR Appendix G Plant Nuclear Safety Operational Analysis
- 2. FSAR Section 7.3, Primary Containment and Reactor Vessel Isolation Control System
- 3. f5AR Section 14. Plant Safety Analysis
- 4. FSAR Section 6, Core Standby Cooling Systems
$. FSAR Section 14.4.4, Refueling Accident
)
1
- 6. FSAR Section 6.5.3, Inte rated Operation of the Core Standby Cooling Systems
- 7. FSAR 5ection 6.5.3.1, Ltquid Line Breaks
- 8. 10 CFR 100 i
HATCH - UNIT 1 3.2 0Ba K:\wp\techsp\h\2P3-284.proi252-103
M .
o l s ,
LIMillt6 CLf0111Lfj5 f 0R OPffA,lltf4 SV4yllLLR[LILWlRlillhlS l
4.9.A.6. [r:1r2inCMY91LilC_lD_{@U211 ALhrtElfG (Continued)
- b. Once every scheduled refueling outage, the ecergency 250 volt DC/600 volt AC inverters shall te subjected to a load test to dmonstrate operational readiness.
3.9.A.7. Loaic $vstems 4.9.A.7. Legic_5 n i n The following logic systems shall te operable: Th2 logic ,ystems shall be tested in the manne and frequency as folicws:
- a. The conmn accident signal logic syst m is operable. a. [atn division of the cmron accident signal logic system shall be tested every stneduled refueling outage to demonstrate that it will function on attuation of the core spray syst s to provide an automatic start signal to all 3 diesel generators,
- b. The urdervoltage relays and supporting system are operable. b.l. Once every scheduled refueling outage, the conditions urder which the undervoltage logic system is required shall te strulated with an undervoltage on each start bus to denunstrate that the diesel generators will start. The testing of the undervoltage logic shall deronstrate the operability of the 4160 volt load shedding and auto bus transfer circuits. The sinulations shall test both the degraded voltage and the loss of off-site power relays,
- t. Once per nonth, the relays which initiate energitation of the energency buses by the Diesel Generators when voltage is lost on the emergency buses will be l functionally tested,
- c. The cocron accident signal logic c.l. Once per operating tjcle each syst s , and undervoltage relays diesel generator shall be dem-and supporting system are operable, onstrated operable by simulating both a loss of off-site po.er and a degraded voltage condition in conjunction with an accider,t test signal and verifying:
MTCH - UNIT I 3.9-4 k : \wp\ t ech s p \h \ 3-9J 1252. p ro125248
v -- - - --- - - - -- - - - - - - - - - - - - - - - - -----
o
- c', - -
1 asis eon sauntsi ktot>1BfMLNI5 )
4.9.A.2.e. fuel Oil Trans.f1C h .1 l
following the monthly test of the diesels, the fuel oil transfer '
pmps shall te operated to refill the day tank and to check the :
operation of these ptsps. i 3 1Z51210 y21t DC Extuency Poer system (Plant Bitteries lA and IB)
The plant batteries may deteriorate with tine, but precipitous failure is unlikely. lhe type of surveillance described in this i specification is that which has been demonstrated through experience
- to provide an indication of a cell becoming irregular or inoperable long before it fails.
- 4. Eremency 4160 Volt Buses flE. IF. and IG)
The emergency 4160 volt buses (IE. IF, and 10) are munitored to assure readiness and capability of transmitting power to the emergency load, i
~
These buses distribute AC power to the required engineered safety feature equipment, lhe nomal feeds and backup to the emogency buses (IE,if,andIGlaretakenfromthestartupauxiliary transfomers. if neither startup auxiliary transfomer is available, buses lE IF, and IG will be energized frtn the standby diesel generators. l t
- 5. Ememency 600 Volt Buses flC and IDI l The ecergency 600 volt buses (IC and 10) are mnitored to assure readiness and capability of transmitting the emegency load.
- 6. [mergency 250 Volt DC to 600 Volt AC Inverters The emergency 250 volt DC to 600 volt AC inverters are monitored to assure readiness and capability of transmitting power to the emergency loads.
- 7. Looie Systems The periodic testing of the logic systems will vuify the ability of the logic systems to bring the auxiliary electrical systems to mnning standby readiness with the presence of an accident signal and/or a degraded voltage or LOSP signal.
The periodic testing of the relays which initiate energitation of-the emergency buses by the diesel generators when voltage is last on the energency buses will verify operability of these relays. l The periodic simulation of accident signals will confim the ability of the 600 volt load shedding logic system to sequentially shed and restart 600 volt loads if en accident signal were present and diesel generator voltage were the only source of electrical power.
D. RPS MG Sets The surveillance requirements for the RPS power supply equitment will ensure the timely detection of potential cceponent failures that might be caused by a sustained over-voltage or under-voltage conditions.
E. Ecferences
- 1. " Proposed IEEE Criteria for Class IE Electric Systems for Nuclear-Power Generating Stations" (IEE: Standard No. 308), June,1%9.
- 2. American Society for Testing and Materials,1970 Annual Book cf ASTM it.3ndards.Part17.
HAICH - UNii-1 3.9-12 k:\wp\techsp\h\39ul252. pro \252-83'
~
r p (; i g I >r i ,, >
o'.
I LIMITING CONDITIDN5 FOR OPERATION SURVEIELANCE REQUIREMENT 5 3.2. PROTECTIVE INSTRUMENTATION (CONT') 4.2. PROTECTIVE INSTRUMENTATION (CONT') 3.2-1 E. Instrumentation Which initiates E. Instrumentation Which 3.2-1 or Controls the LPCI Mode of RHR Initiates or Controls the f LPCI Mode of RHR F. Instrumentation Which Initiates F. Instrumentation Which In- 3.2 1 or Controls Core Spray itiates or Controls Core Spray G. Neutron Monitoring Instrumentation G. Neutron Monitoring Instru- 3.2-1 Which initiates Control Rod Blocks mentation Which Initiates Control Rod Blocks H. Radiation Monitoring Systems H. Radiation Monitoring Systems 3.2 1 Which Limit Radioactivity Release Which Limit Radioactivity Release
- 1. Instrumentation Which Initiates 1. Instrumentation Which Ini- 3.2-1 Recirculation Pump Trip tiates Recirculation Pump Trip J. Instrumentation Which Monitors J. Instrumentation Which Mon- 3.2-1 Leukage into The Drywell itors Leakage Into The Dry-well
)
K. Instrumentation Which Provides K. Instrumentation Which Provides 3.2-1
,c . Surveillance Infomation Surveillance Information c .. s
/ '
3.3. REACTIVITY CONTROL 4.3. REACT!YITY CONTROL 3.3-1 I
A. Core Reactivity Margin A. Core Reactivity Margin 3.3-1 i B. Inoperable Control Rods B. Operdble Control Rod Exercise 3.3-1 Requirements C. Control Rod Drive System C. Control Rod Drive System 3.3-2 ,
D. Minimum Count Rate for D. Hinth.um Count Rate for 3.3-4 Rod Withdrawal Rod Withdrawal i
{
\
E. Rod Worth Inventory Detemination E. Rod Worth Inventory Detemination 3.3-4
/
f) l F. Operation With t Limiting F. Operation With a Limiting 3.3-5l/
\ Cor. trol Rod Pattern Contr al Rod Pattern /
\ - - .- l
\ ' t. . e,u- e c ., , ;. . . ea, tu..,
w . _ . -, v . , _ 1 f"t" "d ;'d"'
Nt- sh
'~
g 3M
!l 1
l, i
- (, , .naj n. 1 w .4) /
l
'{..
\ 'k
.,. tu m. A 7 -o e, i . o -.,t+. mm, -
, I
( ,c l1 ' y a tem %o
- c. ;; s u- L
,e.,
\
j 5
~
p.-
HATCH - UNIT 1 11 l
t LtMITING CONDITIONS FOP OPERATION SURVEILL ANCE RE0VIREMENTS 3.2 PROTEtilvf INSTRUMENTATION 4.2 PROT 1[TivE INSTRUMENTATION Applicability hyMtability The Limiting Conditions for Operation The Surveillance Requirements apply to the plant instrumentation apply to the instrumentation which performs a protective function, which performs a protective function.
Objective Obiective The objective of the Limiting Condi- The objective of the Surveillance tions for Operation is to assure the Requirements is to specify the type operability of protective instrumen- and frequency of surveillance to tation. be applied to protective instru-mentation.
ipecifications Specifigations The Limiting Conditions for Operation The check, functiooal test, and of the protective instrumentation af- calibration minimum frequency for fecting each of the following protec- protective instrumentation affect-tive actions shall be as indicated in ing each of the following protec-the corresponding LCO table. tive actions shall be as indicated in the corresponding SR table.
protective Action LCO Table SR Table A. Initiates Reactor Vessel 3.2-1 4.2-1 and Containment Isolat. ion B. Initiates or Controls HPCI 3.2-2 4.2-2 C. Initiates or Controls RCIC 3.2-3 4.2-3 t
D. Initiates or Controls ADS 3.2-4 4 . 2 -4 E. Initiates or Controls the 3.2-5 4.2-5 LPCI Mode of RHR l F. Initiates or Controls Core 3.2-6 4.2-6 i Spray l G. Initiates Control Rod Blocks 3.2-7 4.2-1 H. Limits Radioactivity Release 3.2-9 4.2-8
- 1. Initiates Recirculation Pump 3.2-9 4.2-9 Trip J. Monitors Leakage into the 3.2-10 4.2-10 Drywell K. Provides Surveillance 3.2-11 l 4.2-11 i
/ L. D.information Initiates Disconnection-of 3.2-12 4.2-12
/ -Of f site-90 wee-Sources-
{ M. Initiates-Energintion-by Wme 3.2-13 4.2-13 ens ite-Powee-40ertes-l H. Arms the Lo'w Low Set S/RV 3.2-14 4.2-i4 System l ,-
l t /iby e.h.k ht6 Mr a .3 v
( b ct u 6 s hs ., <, t t a s HATCH - UNIT 1 3.2-1 Amendment-Nor 88 103 i-
{)!l 1ll t
n ee erl H kob a at Trro eeN ebp bmOs ) )
u i c c oNd ( ( d t es e .
erl h n e nhie s w dh otun i o et i qn l d e t r' ea b t cn ciRh a u oi A C t h r s s pd e e t yc c o aa y y b h ml p
a a n d n 0eo l
0eo l
a c
n a ii os 0dt 8dt t 8
2el 2
3el ip ,
n ra al ma ma h o N
- oiu oi et s i en pg ttq ttq n t oi 0 e e o a s 4 l s l s i r ,
T g atr atr t e sp f
" n ul o ul o a p li E ' i qo qo l o er M
Y' t evn evna e nt M t a r r n O "
S e r0h r0h e aa C S o0t o8t e w h S
p 8 2 n o cd 4 . n2s n3s o p e 0SE i r
a s a s - ed EC hte hte. o , li
.% T tAl tAl t p bv HR
. c - u ao TU r ec r e.bs ee e t rr
- O e.be n r ep 2 GS 1 E k ts atl s ts atl 5 o
t a p ot 2 AE?R N
- eil 5 el l 2 a s s .
rii roi1 1 del 4W k gvv6 gvw2 - t r ete 3 T0 2 a o r n 4
- h t il n E M - 3 t c uaa L 4E % a qnh B 3 E e eoc A H4 t
~
sd . . L o, s r ri T CS + I ep B 2 te 4F eri s
A e1 g ecl inr hnb 4
. nir s T c MW !' nut aq et u r2 tua 0 B R e. fr 4 F- heo / / O in a u natpe 0O CRT 2 2 F n d 4 - m ee hno T
s.
S vl e ten A E nb l mi T
N t T O
oa cT os su sre I E h des N r etl M I el l rn ep l sb
% irbe an s s oi na Ti urn f o eic u u s n i E s qea D B ys i s
e odl M t e ph / / e b ep 4 R O C_ 2 2 lnt srp oi o li a
% sd t eu nqe m~ in
~
d neh
)
s s a er art t
B u u ".2 i hctr y
B y
o1 u xo q
ya cl e neg yae cl g N-2 e r b leef n c
t n
nea r3 aei era eRt e s rhg e g t g l Re i eto m rel ego reo " l p n
i t) e gV b of' rb maV) ma ) da o oy t( Et n Etdn eT i r a s l ro l eo t oel I
n vooi vodi kv t kvat ltn ii t a
rnr ce rsi 6esd 6 e gd rri t n ea ns e bmt 1 don nLo 1 den
. nDo eme mu mru uoo 8
4 U(C 4U(c nt r nf -
mi t rk u s eec l n n h po oe i t l ce l o
et i w s hip ttS N he h inO
.e l
1 2 Tb T WuL ff e . . .
R a b c h4n ' cZ Z '-
ao
- t. * , ' U cr n3 m +r 2O. e T. a o? .
11 Iilll!I lI llil
7AstE-3re-1 F ,
-4NsieuME F .. M,
- C-USAMS T 4ATEG-EMERG42ATION -BV-g g
- . tT & POuED 5 PCEO O
Z (/J b. 3 I a d c_ ,o d d e.T t5)
Action to be Taker Required Required Channels if the Numbp Vof Operable Required Trip Setting Requi red 4pe ra b le instrument E
Re f. No, I a IN ibI ChanneIs To T ria _ Charinef's Is Not Mel 1 Sta rt up auxilia ry 2 1 Trip Setting (c) greater than or transformer 1C eqtea l to 3280 loss df-v_oltage condition volts. At 3280 volts trip of
.-elay will be
.- Instantaneous N / (no time delay).
N 5(,
/ '
N
,/ ' MOTES FOR TABLE 3.2-13 \
- a. The column entitled "Ref. No." iranly for convenience so that a one-to-one 'rsTationship N w
can be established between items in Table 3.2 _3-on 1 items in Table 4.2-13.
,ta) b. T h i s i n s t riemen ta t i ert.J uired to be operable durireg reactor startup, power opera t ion, Antthot shutdown, ro
'N
- c. With the nuplae/cf r operable channet s one less than the required operable channels, operation may proceed y
e p roviderinfie relay is removed from its case. Removing the relay accomplishes the same action as an operable, c) re l ay'6pe ra t i ng to open i t s t ri p c i rets i t.
,aY l
l 3
3 et 2
O
.Tu O
O2 W
V w
., A TABLE 4.2-12 ,
b
-4 f ft9ffMfMfti AHUM-MitOH-4Mt-i"f ATEG-IHE-1)f SCOttNE4}HO4 C Of f s: T E . C"!! n 00"nC[0
@ ,** h 3 bnt la s to wT s t .'
- s s D,_7 31,4 Jt.t..~ \/.M* 3 s t InstN functional Instriement instrteent Check Test Ministem Ca l ib ra t ion c Re f. No. I n s t rismen t F rentrency Minimoe Freqtrency Minietam Freateency 3 (s) (b)
-4 Once/ month Once/ ope ra t ing 1 4.16 kv Emergency Bus N/A cycle
" UndervoItage ReIay (Loss of Voltage Condition)
Once/ month Once/ opera t ing 2 4.16 Kv Emergency Bus N/A cyc'7 Undervol tage Relay (Degraded Voltage Condition)
NOTES FOR TABLE 4.2-12
. a. The column entitled "Rer. No." is only for convenience so that a ene-to-one relationship can be N
e established between items in Table 3.2-12 and items in Table 4.2-12.
b us b. Survolitance or thir instrismentation is requi red during reactor sta rtisp, power operat ion, and hot
- shutdown.
e h
c, 3
rt 2
.O CO
_. w -
J w _
s
a
-YABtr *:.2-?? ,
I 44GTRUM&M*AT40" "'! Cu !y9yraigs gyEngayaram av M 4)*tS! !E Pa '!" EOU"CES x CT M 2 tar tw b,- .istst M a
instrument Functional I n s t rtemen t c Ref No. In s t rtiment 87strisment Check Test Minimum Ca l i b ra t ion z fat [b1 Ministem f requency f rectiency Miniette Frequane 1 tettup N/A Once/ Month pe ra t ing auxilla h # cycle t rans f o rme r 15 loss of voltJ9e condition N s
/'~s' p f ' NOTES FOR TABLE 8.2-13 4 a.
The column entitJ c45Re . No." is only for convenience so that a one-to-one relatidh%4p x can be estabt ished between 11e w in Tabis 3.2-13 and items in Table ta.2-13. 'N tr ( Surveillance
_ # ' , of this instrumentation is required during reactor sta rttip. power operation, and hot NshuD2ewa y e
W e
Zm O
cr C1.
3 (D
3 r+ -
2
.O W
1 BASES FOR LIMITING CONDITIONS FOR OPERATION 3.2.J.4. Scintillation Detector For Monitorino Radiciodine (Continued) level reading is indicative of a leak in the nuclear system process barrier in the primary containmen+.. A sample that is continuously drawn f rom the primsry containment is collected on an iodine filter and f monitored by a gantna sensitive scintillation detector. Radiation levels are read out by a log rate meter and recorded on a strip chart located in the control room. A high radiation level alam and a failure alam are also provided and are annunciated in the control room. Also, a high-low flow alarm is annunciated in the control room.
t
- 5. GM iubes for Monitorino Noble Cases A set of GM tubes contained in an instrument rack are used to monitor the release of noble gases in the drywell and torus. A high radiation level reading is indicative of a leak in the nuclear system process barrier in the primary containment. A sample that's continuously drawn f rom the primary containment is passed through a shielded sample chamber which contains the beta sensitive GM tubes. Radiation levels are read out by a log rate meter and recorded on a strip chart located in the control room.
A high radiation level alarm and failure alarm are provided and are annunciated in the control room. Also, a high-flow alarm is annunciated in the control room.
K. Instrumentation Which Provides Surveillance Information (Table 3,2-11)
I For each parameter monitored, as listed in Table 3.2-11, there are two channels of instrumentation except for the control rod positions indicating system and the Post-Accident Effluent Monitors. By compa ~ ring readings between the two ;hannels, a near continuous surveillance of instrument l perf orniance is available. Any significant deviation in readings will initiate an early recalibration, thereby maintaining the quality of the instrument resdings. ~
The hydrogen and oxygen analyzing systems consist of two redundant, separate systems and are each capable of analyzing the hydrogen and oxygen content of the dryhell-torus simultaneously. They are designed to be completely testable at both the analyzer rack and in the control room. With an oxygen concentration of less than U by volume, a flanrnable n.: C*ure with hydrogen is not possible.
">c e .A arm v. tt y P. .Te . . . Nws.N i. n )
I. . 4cstrumntation Which4 nit 4ctes -Olscone eetiomf-Of f s4te-powe&Soureef l (Table 3.2-12)
The undervoltage relays shall automatically initiate the disconnection of of f site power sources whenever the voltage setpoint and' time delay limits have been exceried. This action shall provide voltage protection for the g l emergency power systeas by pteventing sustained degraded voltage conditions 1 I
pue to the qifsite power sour,ce and interaction between the offsite and onsite emergency power systems. The undervoltage relays have a time delay characteristic that provides protection against both a loss of voltage and i degraded voltage condition and thus minimizes the effect of short duration disturbances without exceeding the maximum time delay, including margin, that is assumed in the FSAR accident analyses, g l
HATCH - UNIT 1 3.2-68 Amendment No. (2, SS,108
~ . . . - . _ . - .
t .
a', -
,' . I BASES FOR LIMITING CONDITIONS FOR OPIRATION ,
i M. I n s t rume n t a t ion - Wh i c h-l a t t ia t e s - E ne re i ra t 46n- by - On s i t e-eewe e- Sou rc es -( Tab l e- i 31-131- (a ht.I J
/
The-an'dervoltage relays shall automatically trip the loss of of f site poyw -
(LOSP) lockout relays if voltage is lost on the emergency buses Ja d-1W voltage is sentedgstart-up transformer 1C ($UT 1C). Th,11,4M kout will, i if a loss of coolant arcid (LOCA) has previously pceofred. cause energitation of the emergenc 4160 volt buses by-th,,e Diesel Generators (0/Gs). If the LOSF and LOCA occur'signittheously, the lockout relay will provide a ptrmissive allowing D/fs.edTifut bPeake y losure when the D/G voltage is up to normal. Vundervoltage relays Vill bave no time delay.
The absence of ting,de provides a faster response time'if-the diesel generator hai heen previously initiated and prevents an additicial--
de1a J ,AF-11 has not. This scheme prevents the connection of the D/G to.
,effsite power source. t N. Instrumentation Which Arms low low Set System (Table 3.2-141
'he bases for these trip functions are found in the bases for Section 3.6.H.
page 3.6-21.
3.2.1 Peferences
- 1. FSAR Appendix G. Plant Nuclear Safety Operational Analysis
- 2. FSAR Section 7.3, Primary Containment and Reactor Yessel Isolation Control Systr.a
- 3. FSAR Section 14. Plant. Safety Analysis .i
- 4. FSAR Section 6 Core Standby Cooling Systems
- 5. FSAR Section 14.4.4, Ref ueling Accident
- 6. FSAR Section 6.5.3, integrated Operation of the Core Stendby Cooling l Systems
- 7. FSAR Section 6.5.3.1, Liquid Line Breaks 8, 10 CFR 100
?
i HATCH - UNIT 1 3.2-68a Amendment No. 88,103
7 e
?
- .e . -
~
LIMITING CONDITIONS FOR OPERAll')N
.SURVElLLANCE REOUIREMENTS 4.9.A.6. Emeroencv 250 Volt DC to 600 Volt AC Inverters (Continued) )
- b. Once every scheduled refueling .
outage, the emergency 250 volt DC/600 volt AC inverters shall be subjected to a load test to demonstrate operational readiness.
)
3.9.A.7. Logic Systems 4.g.A.7. Locic Systems The following logic systems shall The logic systems shall be tested in be operable: the manner and f requency as f allows:
- a. The conrnon accident signal a. Each division of the conrnon )
logic system is operable. accident signal logic system shall be tested every scheduled refueling outage to demonstrate that it will function on actuation of the core spray system to provide an automatic start signal to all 3 diesel generators,
- b. The undervoltage relays and b.1. Once every scheduled refueling supporting system are operable, outage, the conditions under which the undervoltage logic system is required shall be simulated with an undervoltage on each start bus to i demonstrate that the diesel generators will start. The testing i of the undervoltage logi: shall demonstrate the operability of the 4160 volt load shedding a'id auto bus transfer circuits. Ti e simulations shall test both the degraded voltage and the 1)ss of off-site power relays.
- 2. Once per month, the relays which initiate'energiration of the emergency buses by the Dicael Generators when voltage is lost on
_the emergency buses.and-start-up-Gransfemee_lCdwill'be~~
functicha1Ty tested.
~
! c. The conrnon accident signal logic c.). Once per operating cycle each system, and undervaltage relays diesel generator shall be dem-and supporting system ars operable. onstrated operable by simulating both a loss of off-site power and a degraded voltage condition in conjunction with an accident test signal and verifying: )
)
j;\g,hlt<!gf/f $ 0
^
HATCH - UNIT 1 3. 9 -a Amendment-No. #I, A A, Y
BASES FOR SURVEILLANC[ REOUIREMENTS 4.g. A.2.e. Fuel Oil Transfer Punes Following the monthly test of the diesei;, the fuel oil transfer /
purgs shall be operated to refill the day tank and to check the operation of these pumps.
- 3. 125/250 Volt DC Emeroency Powea System (Plant Batteries 1A and 18)
The plant batteries may deteriorate with time, but precipitous b failure is unlikely. The type of surveillance described in this F specification is that which has been demonstrated through experience to provide an indication of a cell becoming irregular or inoperable long before it fails.
- 4. Emercenev 4160 Volt Buses ( R. 1F. and 1G)
The emergency 4160 volt buses (IE.1F, and 16) are monitored to assure readiness ard capability of transmitting power to the emergency load.
These buses distribute AC power to the required engineered safety feature equipment. The normal feeds and backup to the emergency buses (1E.1F and 16) are taken from the startup auxiliary l transformers. If neither startup auxiliary transformer is available. buses 1E,1F, and 1G will be energized from the standby diesel generators.
- 5. Emercener 600 Volt Buses fic and 10)
The emergency 600 volt buses (1C and 10) are monitored to assure readiness and capability of transmitting the emergency load.
I
- 6. Emercenev 250 Volt DC to 600 Volt AC Inverters The emergency 250 volt DC to 600 volt AC inverters are monitored to assure readiness and capability of transmitting power to the emergency loads.
7 ', Loaic Systems The periodic testing of the logic systems will verify the ability of the logic systems to bring the auxiliary electrical systems to running standby readiness with the presence of an accident signal and/or a degraded voltage or LOSP signal.
The periodic testing of the relays which initiate energization of the emergency buses by the diesel generators when voltage is lost on
_ _ %startup transformer 4C will verify operability of these relays.
(% e , y o, HZo The periodic simulation of accident signals will confirm the ability of the 600 volt load shedding logic system to sequentially shed and i restart 600 volt loads if an accident signal were present and diesel generator voltage were the only source of electrical power.
The surveillance requirements for the RPS power supply equipment will ensure the timely detection of-potential component failures that might be' caused by a sustained over-voltage or under-voltage conditions.
E. References
- 1. ' Proposed IEEE Criteria for Class 1E Electric Systems for Nuclear h Power Generating Stations' (l[EE Standard No. 308), June,1969.
- 2. American Society for Testing and Materials, 1970 Annual Book of ASTM ,
Standards, Part 17.
HATCH - UNIT 1 3.9-12 Amendnient /cbf kLy\Wj(MW
- Hj
-