ML19221A187
| ML19221A187 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 03/04/1979 |
| From: | Metropolitan Edison Co |
| To: | |
| References | |
| NUDOCS 7905190248 | |
| Download: ML19221A187 (6) | |
Text
e
. <,0 -
c.
\\
,/'
PLANT SYSTEMS
\\'
EMERGENCY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 Three independent steam generator emergency feedwater pumps and associated flow paths shall be OPERABLE with:
a.
Two emergency feedwate'r pumps, each capable of being powered from an OPERABLE emergency bus, and b.
One emergency seedwater pump capable of being powered from an OPERABLE steam supply system.
APPLICABILITY: MODES 1, 2 and 3*.
ACTION:
a.
With one emergency feedwater system inoperable, restore the inoperable system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.1.2 Each emergency feedwater system shall be demonstrated OPERABLE:
a.
At least once per 31 days on a STAGGERED TEST BASIS by:
1.
Verifying that each steam turbine driven pump ~ develops a discharge pressure of 1 1070 psig when the secondary steam supply pressure is greater than 200 psig.
Automatic actuation of emergency feedwater system may be blocked when OTSG steam Pressure < 800 psig.
THREE MILE ISLAND - UNIT 2 3/4 7-4 138 062 7905190'JL9 %
o v :
PLANT SYSTEMS
, SURVEILLANCE REQUIREMENTS (Continued) i s
2.
Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.
b.
At least once per 18 months, during shutdown, by:
1.
Verifying that each automatic valve in the flow path
. actuates to its correct position on an emergency feed-water actuation test signal.
2.
Verifying that each pump starts automatically upon receipt of an emergency feedwater actuation test signal.
=
HREE MILE ISLAND - UNIT 2 3/4 7-5
e PLANT SYSTEMS BASES 3/4.7.1.2 EMERGENCY FEEDWATER SYSTEMS The OPERABILITY of the emergency feedwater systems ensures that the Reactor Coolant System can be cooled down to less than 280*F from normal operating conditions in the event of a total loss of offsite power.
Each electric driven emergency feedwater pump is capable of delivering a total feedwater flow of 470 gpm at a pressure of 1133 psig to the entrance of the steam. generators.
Each steam driven auxiliary feedwater pump is capable of delivering a total feedwater flow of 940 gpm at a pressure of '.133 psig to the entrance of the steam generators. This capacity is sufficient to ensure that adequate feedwater flow is avail-able to remove decay heat and reduce the Reactor Coolant' System temperature to less than 28ChF where the Decay Heat Removal System may be placed into operation.
q " - '.:
- i. ' OPERASILITY of the condensate storage tanks with the mi mum water vot, ensures that sufficient water is available for c Idow~n of the Reactor me lant System to less than 280*F in the eve ' of a total loss of offsite g er or of the main feedwater system.
ihe minimum water volume is sufficient ' maintain the RCS at HOT STAP eY conditions for 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> with steam dis rge to atmosphere conc".ent with loss 'of offsite power. The contai.
water volume lim'. includes an allowance for water not usable because o. tank discha e line location or other physical characteristics.
3/4.7.1.4 ACTIVITY The limitations on second= j system speci ic activity ensure that the resultant offsite radia n dose will be limed to a small fraction of 10 CFR Part 100 limit
.n the event of a steam e rupture.
This dose includes the eff
.s of a coincident 1.0 GPM pri.. ry to secondary tube leak in the s
.m generator of the affected steam i ~ e.
These values are consi ent with the assumptions used in the sat analyses.
3/4.7.1.5.. IN STEAM LINE ISCLATION VALVES
. e OPERABILITY of the main steam line isolation valves ensures ' hat s' am generator blowdown will not continue indefinite 1{ in the event a
+'
'2
't ": -^:
l' : ~_::c-,
Thic restriction is recuirad 3
m__..
I k38 064 THREE MILE ISLAND - UNIT 2 S 3/4 7-2 O
1
.r-I +
u 1
~
PLANT SYSTEMS EMERGENCY FEEDWATER SYSTEM
,-,o..
LIMfTINGCONDITIONFOROPERATION 3.7.1.2 Three independent steam generator emergency feedwater pumps and associated flow paths shall be OPERABLE with:
Two emergency feedwate'r pumps, each capable of being powered a.
frcm an OPERABLE emergency bus, and b '.
One emergency feedwater pump capable of being powered from an OPERABLE steam supply system.
APPLICABILITY: MODES l',
2 and 3*.
ACTION:
~
a.
With one emergency feedwater system inoperable, restore the inoperable system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Id$)
SURVEILLANCE REOUIREMENTS 4.7.1.2 Each emergency feedwater system shall be demonstrated OPERABLE:
a.
At least once per 31 days on a STAGGERED TEST BASIS by:
1.
Verifying that each steam turbine driven pump' develops a discharge pressure of g 1070 psig when the secondary steam supply pressure is greater than 200 psig.
- Automatic actuation of emergency feedwater systen may be blocked when OTSG steam Pressure < 800 psig.
138 065 THREE MILE ISLANO - UNIT 2 3/4 7-4
e
~-
PLANT SYSTEMS i
. SURVEILLANCE REQUIREMENTS (Continued) l 2.
Verifying that each valve (manual, power operated or automati:) in the flow path that is not locked, sealed
, or otherwise secured in position, is in its correct posi tion.
b.
At least once per 18 months, during shutdown, by:
1.
Verifying that each automatic valve in the flow path
. actuates to its correct position on an emergency feed-water actuation test signal.
2.
Verifying that each pump starts automatically upon receipt of an emergency feedwater actuation test signal.
. THREE MILE ISLAND - UNIT 2 3/4 7-5 138 066
e 6 -
L' PLANT SYSTEMS BASES 3/4.7.1.2 EMERGENCY FEEDWATER SYSTEMS _
The OPERABILITY of the emergency feedwater systems ensures that the Reactor Coolant System can be cooled dcwn to less than 280*F frcm normal operating conditions in the event of a total loss of offsite power.
Each electric driven emergency feedwater pump is capable of delivering a total feedwater flow of 470 gpm at a pressure of 1133 psig to the entrance of the steam. generators.
Each steam driven' auxiliary feedwater pump is capable of delivering a total feedwater flow of 940 gpm at a pressure of 1133 psig to the entrance of the steam generators. This capacity is sufficient to ensure that adequate feedwater flow is avail-able to remove decay heat and reduce the Reactor Coolant' System temperature to less than'280hF where the Decay Heat Removal System may be placed into operation.
O ' '.:
"*":::::f T: :T:7.:: ~7 '. ::
s/
OPERABILITY of the condensate storage tanks with the mi., mum water vo u ensures that sufficient water is available for ldow'n of
"==
the Reactor lant System to less than 280*F in the eve ' of a total loss of offsite er or of the main feedwater system.
ihe minimum water volume is sufficient maintain the RCS at HOT STA ' oY conditions for 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> with steam dis
'rge to atmosphere conc' ent with loss'of offsite power. The contaii water volume lim'. includes an allowance for water not' usable because o. tank discha e line location or other physical characteristics.
3/4.7.1.4 ACTIVITY The limitations on second system spec ic activity ensure that the resultant offsite radia+ n dose will be li. "+ed to a small fraction of 10 CFR Part 100 limite n the event of a steam
~ e rupture. This dose includes the eff es of a coincident 1.0 GPM pri. ry to secondary e.
These tube leak in the s' m generator of the affected steam values are consi ent with the assumptions used in the sa analyses.
3/4.7.1.5 IN STEAM LINE ISOLATION VALVES e OPERABILITY of the main steam line isolation valves ensures ' hat s'amgeneratorblowdownwillnotcontinueindefinitel{intheevento
+a
' # ' t ": ::c
_3 m ;.. :
upt;-
This restriction is recuivad
?
I THREE MILE ISLAND - UNIT 2 S 3/4 7-2 138 067