ML20138A097
| ML20138A097 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/03/1986 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20138A093 | List: |
| References | |
| TAC-61054, TAC-61280, NUDOCS 8603140032 | |
| Download: ML20138A097 (13) | |
Text
.
LIST OF TABLES (Consluded)
M Title Pace 1
3.7-2 Testable Penetrations with Double 0-Ring Seals 3.7-21 3.7-3 7estable Penetrations with Testable Bellows 3.7-22 3.7-4 Primary Containment Testable Isolation Yalves 3.7-23 3.13-1 Fire Detectors 3.13-2 3.13-2 Fire Hose Stations 3.13-9 3.14.1-1 Radioactive Liquid Effluent Monitoring 3.14-2 Instrumentaticn 3.14.2-1 Radioactive Gaseous Effluent Monitoring 3.14-7 Instrumentation 4.14.1-1' Radioactive Liquid Effluent Monitoring 3.14-4 Instrumentation Surveillance Requirements 4.14.2-1 Radioactive Gaseous Effluent Monitoring 3.14-11 Instrumentation Surveillance Requirements 4.15.1-1 Radioactive Liquid Effluent Sampling and 3.15-2 Analysis Program C
4.15.2-1 Radioactive Saseous Waste Sampling and 3.15-10 Analysis Program 3.16.1-1 Radiological Environmental Monitoring Program 3.16-4 3.16.1-2 Reporting Levels for Radioactivity Concentra-3.16-7 tions in Environmental Samples 4.16.1-1 Lower Limit of Detection 3.16-8 6.2.2-1 Minimum Shift Crew Composition 6-4 6.9.1.7-1 Environmental Radiological Monitoring Program 6-18 Sununary 6.9.2-1 Special Reporting Requirements 6-19 HATCH - UNIT 1 1x s
i C
B603140032 860303 PDR ADOCK 05000321 P
- + -
r S.
0)erating Cycle - An operating cycle is the interval between tie end of one scheduled refueling outage and the end of the next subsequent scheduled refueling outage for the same unit.
T.
Primary Containment Integrity - Primary containment integrity means that the drywell ano suppression chamber are intact and all the following conditions are satisfied:
1.
All'non-automatic containment isolation valves on lines connected to the reactor coolant system or containment which are not required to be open during accident conditions are closed. These valves may be opened to, perform operational activities.
2.
At least one door in the personnel airlock is closed and sealed.
3.
All automatic containment isolation valves are either operable or at least one automatic containment isolation valve in each line having an inoperable valve is deactivated in the isolated position.
4.
All blind flanges and manways are closed.
U.
Protective Action - A protective action is an action initiated by the protective system when a limit is reached. A protective action can be at a channel or system level and is essential to l
the accomplishment of a safety action.
V.
Protective Function - A protective function is the monitoring of one or more plant variables or conditions and the associated initiation of intra-system actions which eventually result in protective action.
W.
Rated Thermal Power - Rated thermal power means the reactor is operating, at a steady state power of 2436 megawatts thermal.
This is also referred to as 100 percent thermal power.
X.
Reactor Mode - The reactor mode is established by the Mode switch position. The switch positions are REFUEL, SHUTDOWN, START & H0T STANDBY and RUN; thus the four possible reactor modes are: Refuel Mode, Shutdown Mode, Start & Hot Standby.
Mode, and Run Mode.
Y.
Reactor Power Operation - Reactor power operation is an operation with the Mode Switch in the START & H0T STAncev or RUN position with the reactor critical and above 1% of rated thermal power.
HAIG - UNIT 1 1.0-4 h m.
m
~
lg s
6 t
ne n
wv m d r
e ol e n a
m da.
yt o
n 1
tvm bs2c 1
2
,5 v
u e dy e i
p Sp a
p hnt nspst p
sos a u n u
~
u Tud t
u o
Gon n o
iy ttode o
r Sra o r
ets snrnm r
G G
c.
G hc eGan. G
.s e
tuR em' i
k sn hsnsyn sn
.sH htsnan sn r
eo teoero eo s R taeoto eo a
ti titai ti eg etini ti
.m at satadt at tne sratot at l a aih ttiacal t l, i a e
ia tiaina
- tl ll t r
tl R
tl rtl tol i o oo asioyo i o v
o aioico ins tnsnes ns sof tansrs ns ico S gii a i Siiisi ii ii Ii s
dV aI
- s oS fsp nr lM iii e
e e
eou e
r yv 4h yv 4 yvCo yv 4 ye l s e 2 e h e 2 l
nst-e 2t l
l w
l keh -
rin rin rin rin ro el ehwneg ehwn ehw4 n ehwn el ant) dcoitn dcoi dco2 w dcoi dc.
tnoc radhai radh rad o
radh r s Y
ab(
o ttl1 o
tt o tn d o
tt odr R
eh duioo dui dui t
dui nu A
bcrs nnhwso nnhw nnhh u nnhw nao M
om aaS ic aaS
. aast h aaS a h n
n offe n
n s.
i I
endorn. endo endw endo eo8 R
to t
twli ow twli twl eg twli ti P
ts atn aoon tn aoot nrey aoot om aoot dCo ai idCis ici 0
oems idCisde idCis l
tt dr tuh i
I ib tt drtt tt dr tt i loo iuenu idt I
uenuus iuenu iuet A
tmt i
nhhoo nei cuo nhh o oh y nhhoo nhhi so I
std ic stCh I rw L
Ann stCh stChss i
i I
ESS E
V l
RN s
a OO e
m Ti g
s h
r CT.
n e
s c
o h
e n
nrd AA i
g en 1
EL.
t c
h i
swu
- RO t
n c
i s
g eoo n
5 S
e i
2 SI S
i mpr p
i 5
. 1 s
ig 3 E 5
2 5
p tlk TT p
8 5
1 3
l c e AN i
l IE r
1 2
3ua b TM T
2 2
- 2 5
1 5fb N
a I
T NI IAT HN
)
CO b
IC despi H
el li W
rberm ante 2
2 2
1 2
2 i
1 urn t
10 qears 1
ephey T
R O C pS A
T N
E
) -
M e
3e U
r g
w-n o
R u
l T
nt ea
)
L)
S oa vR 2
1 e
w w
N il tc Lw ol ol I
n (o
Le Le i
. pd e r
v v
h h
h inm wr we we g
g ig roo oa oL oL i
i TCN LN L(
L(
H H
H g
en e
ri r
e ul u
n le so s
iL s
so s
sl eC e
t' ee r
r m
n Vv Pn P
an e
e w
eo m
rL ro l
ti u
o od st l
r tr tt) e a
t ce cue w ni s
at ahd y id n
ea eSo r aa RW RIM D
MR I
f
.)
eoa 1
2 3
4 l
Rl(
%eo*
8 c2q *-
.N m p;L l
{l lll.I f
I,lll l
I l
- lll,
/
Table 3.2-1 (Cont. )
2-Required g Ref.
Trip Ope rab le Action to be taken if
. n Mo.
Instrument _
Condition
. Channels Trip Setting number of channels is n
2 (a) leomenc la ture.
per Trip not met for both trip Rema rks l~
System (b) systems (c).
l.
i
.E
-4
-5 Main Steam Line Lov 2
2825 psig Initiate an order'1y load initiates Group 1
~
Pressure reduction and close isolation. Only MSIVs within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, required in Ruti mode, therefore activated wien Mode Switch Is l
RUN position.
~
l
(
6 Main Steam Line High 2-1140% rated flow.-
Initiate an orderly load initiates Group 1 i
Flow
($120 psid) reduction and close MSIVs isolation, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />..
reduction and close MSIVs. ' initiates Group'1
~
7 Main Steam Line High 2
5200*F Initiate an orderly load Iselation, Tunnel Temperature within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
8 Reactor Water High 1
20-80 gpe.
Isolate reactor water Final trip setting Cleanup System cleanup system.
will-be determined Dirrerential Flow during startup test p rog ram.
W 9
Reactor Water High 2
100-150*F isolate reactor water Final trip setting to Cleanup Equipment cleanup system, will be determined L
Room Temperature during startup test p rog ram, f
10 Reactor Water High 2
0-100*F isolate reactor water Final trip setting Cleanup Equipment cleanup system.
will be determined Room Dirrerential during startup test Tempera ture p rog ram.
11 Condenser Vacuum Low 2
27" Hg. vacuum initiate an orderly load initiate Group 1 reduction and close MSIVs isolation within 8 hrs.
I J
i
_s Notes for Table 3.2-1
-h y
The column entitled "Ref. No." is only for convenience so that a one-to-one relationship can be established.
n a.
(
Z between lines in Table 3.2-1 and items in Table as.2-1.
e l
b.
Primary containment iitcgrity shall be maintained at all times prior to withdrawing control rods for the purpose of going critical, when the reactor is critical, or when the reactor water temperature is above c2 212*F and fuel is in the reactor vessel except while performing low power physics tests at atmospheric H
pressure as power levels not to exceed 5 MWt.
When primary containment integrity is required, there shall be two operable or tripped trip systems for
- each function ~.
c.
If the number of operable channet s cannot be met f'or one of the trip systems, that trip system shall be tripped, stowever, one trip signal channel of a trip system may be inoperable for up to two (2)* hours duririg periods of required surveillance testing without tripping the associated trip system, provided that the other remaining channel (s) monitoring that same parameter within that trip system is (are) operable.
1 l
N e
N e
Jh e
l l
4
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.7.C.1.
Surveillance While Integrity Maintained (cont'd) b.
Secondary containment capability to 3.7.C.2 Violation of Secondary maintain a minimum 1/4-inch of wate containment Integrity vacuum under calm wind ( 5 mph) conditions with eacn filter train a.
Without Hstch-Unit 1 second-flow rate not more than 4000 cfm ary containment integrity, shall be demonstrated at each restore Hatch - Unit 1 sec-refueling outage, prior to refuelin ondary containment integ-rity within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or per-form the following (as appli-2.
Surveillance After Integrity Violated cable):
(1) Suspend irradiated fuel and/or fuel cask handling After a secondary containment viola-in the Hatch-Unit 1 sec-tion is determined the standby gas ondary containment.
treatment system will be operated immediately after the affected zones (2) Be in at least Hot Shutdown are isolated from the remainder of within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and the secondary containment. The meet the Conditions of ability to maintain the remainder 3.7.C.1.a. within the next 24 of the secondary containment at hours.
1/4-inch of water vacuum pressure under calm ( 5 mph) wind conditions b.
Without Hatch-Unit 1 secondary shall be confirmed.
containment, refer to the follow-ing Hatch-Unit 2 Technical Specification, for LC0's to be followed for Hatch-Unit 2:
(1) Section 3.6.5.1.
(2) Section 3.9.5.1.
)
D.
Primary Containment Isolation Valves D.
Primary Containment Isolation Valves 1.
Valves Required to be Operable 1.
Surveillance of Operable Valves During reactor power operation, Surveillance of the primary con-all primary containment isolation tainment isolation valves shall be valves (applicable valves will be performed as follows:
identified in plant procedures) and all reactor coolant system instru-a.
At least once per operating ment line excess flow check valves cycle the operable isolation shall be operable except as stated valves that are power operated in Specification 3.7.D.2.
and automatically initiateri shall be tested for simulated automatic initiation and closure times.
HATCH - UNIT 1 3.7-13
l 1
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.7.D.l.
Surveillance of Operable Valves (continued) b.
At least once per operating cycle the reactor coolant system instrument line excess flow check valves shall be tested for proper operation.
c.
At least once per quarter:
(1) All normally open power-operated isolation valves except for the main steam line power-operated iso-lation valves) shall be fully closed and reopened.
(2) With the reactor power less than 75% of rated, the main steam line isolation valves shall be tripped (one at a time) and closure time of between 3 and 5 seconds verified.
d.
At least once per week the main steam line power-oper-ated isolation valves shall be exercised one at a time by partial
- closur, and subsequent reopening.
3,7.D.2.
Operation with Inoperable Valves 2.
Surveillance of Lines with an Inoperable Valve In the event any isolation valve Whenever an isolation valve is becomes inoperable, reactor power inoperable, at least one other operation may continue provided at isolation valve in each line having s
least one isolation valve in each an inoperable isolation valve shall line having an inoperable valve is be verified to be deactivated in deactivated in its isolated position.
its isolated position daily.
3.
Shutdown Requirements If Specification 3.7.D.1 and 3.7.D.2 cannot be met, an orderly shutdown shall be initiated and the reacter shall be brought to Hot Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and shall be in the Cold Shutdown Condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
HATCH - UNIT 1 3.7-14
T DELETE HATCH UNIT I 3.7-16
I I
DELETE HATCH - UNIT I 3.7-17
I DELETE HATCH --UNIT I 3.7-18
4 DELETE i
f
\\
l HATCH - UNIT 1 3.7-19
/
I J
/
./'
e k
)
t s
i I
f i
i DELETE i
l mica. our i 3.7-20
n P
BASES FOR LIMITING CONDITIONS FOR OPERATION 1
'3.7,0.
Primary Containment Isolation Valves Double isolation valves are provided on lines penetrating the primary con-tainment and open to the free space of the containment. Closure of one of
-the valves.in each line would be sufficient to maintain the integrity of the system. Automatic initiation is required to minimize the potential leakage paths from the containment in the event of a loss-of-coolant accident. The primary containment isolation signals are grouped as described below.
Group 1 process lines are isolated by reactor vessel water level low low low (Level 1) in order for removal of decay heat subsequent to a scram, yet isolate in time for proper operation of the core standby cooling systems.
Group 2 isolation valves are not normally in use and are closed by reactor
. vessel water level low (Level 3) or drywell pressure high.
It is not desirable to actuate the Group 2 isolation signal by a transient or spurious signal.
Group 3 and 4 process lines are designed to remain operable and mitigate the consequences of an accident which results in the isolation of other process lines. The signals which initiate isolation of Group 3 and 4 process lines are therefore indicative of a condition which would render these other lines inoperable.
Group 5 process lines are normally in use and it is therefore not desirable to cause spurious isolation due to high drywell pressure resulting from non-safety related causes. To protect the reactor from a possible pipe break in the system, isolation is provided by high temperature in the clean-up system area or high flow difference through the cleanup system. Also since the vessel could potentially be drained through the cleanup system,
'a low level isolation is provided.
Group 6 isolation valves are not normally in use and are closed by reactor vessel water level low (Level 3) and reactor steam dome pressure low per-missive.
1 The primary containment is penetrated by several small diameter instrument lines connected to the reactor coolant system. Each instrument line con-tains a 0.25 inch restricting orifice inside the primary containment, a manually operated root valve outside the primary containment, and an excess flow check valve outside the primary containment.
i HATQi UNIT 1 3.7-35 L
..-