ML17284A912
| ML17284A912 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 10/13/1999 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17284A911 | List: |
| References | |
| NUDOCS 9910290116 | |
| Download: ML17284A912 (17) | |
Text
t REQUEST FOR AMENDMENT TECHNICALSPECIFICATION 3.3.6.1 Marked-Up Version of Technical SyeciTication 3.3.6.1 and Associated Bases
'P91QP90116 q9iggg PDR ADGCK 05000397' PDR
Primary Containment lation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 4)
Primary Contaianent Isolation Instrunentation FUNCTION APPLICABLE COHD IT IONS MODES OR REFEREHCED OTHER
'EQUIRED FROM SPECIFIED CHAHHELS PER REQUIRED CONDITIONS TRIP SYSTEM ACTION C.1 SURVEILLANCE REQUIREMENTS, ALLOMABLE VALUE 4.
RNCU System Isolation (continued) d.
Heat Exchanger Room Area Temperature - High e.
Neat Exchanger Room Area Ventilation Differential Temperature - High f.
Pump Room Area Teaperature - High g.
Pm@ Room Area Ventilation Differential Temperature - High h.
RllCU/RCIC Line Routing Area Temperature High i.
RllCU Line Routing Area
~ Temperature - High Room 409, 509 Areas Room 408, 511 Areas 1,2,3 1 ~ 2I3 1,2,3 1I2I3 1,2,3 1,2,3 1 per room 1 per room 1 per room SR 3.3.6.1.3
< 1600F SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.3
< 70'F SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.3
< 180'F SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.3
< 100'F SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.3
< 180'F SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.6
< 175'F
< 180'F j.
Reactor Vessel Mater Level Low J.ow, Level 2 1,2,3 SR 3.3.6.1 '
SR 3.3.6.1.4 SR 3.3.6.1.6 2 -58 inches k.
SLC System Initiation l.
Manual Initiation 5.
~
Isolation a.
Punp Room Area Temperature High 1,2 1,2,3 2(c)
I'OOII!gg SR 3.3.6.1.6 NA SR 3.3.6.1.6 HA SR 3.3.6.1.3
< 150'F SR 3.3.6.1.4 SR 3.3.6.1.6 (continued)
(c)
SLC System Initiation only inputs into one of the two tri s stems.
(d) nly the i oard tri system r red in MODE 1, 2, and
, as applicp(le, when e outboar valve control transfer ed to the a ernate remo e shutdown nel and t)6 outboard alve is c osed.
WNP-2 3.3-57 Amendment No.
149
~ I
~,
l l'
Primary 'Containment lation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 4 of 4)
Primary Contaiment Isolation Instruaentation FUNCTION APPLICABLE MMES OR OTHER SPECIFIED CONDITIONS COND IT IOHS REFERENCED REQUIRED FRON CHANHELS PER REQUIRED TRIP SYSTEH ACTION C.1 SURVEILLANCE REQUIREHEHTS ALLOMABLE VALUE 5.
RHR SDC System Isolation (continued) b.
Pump Room Area Ventilation Differential Temperature High c.
Heat Exchanger Area Tesyerature - High SR 3.3.6.1.3 5 70'F SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.6 Room 505 Area Room 507 Ares Room 605 Area Room 606 Area d.
Reactor Vessel Mater Level - Low,
,Level 3 e.
Reactor Vessel Pressure - High 3,4,5 1,2,3 SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 S 140'F S 160'F c 150'F 5 140'F
?: 9.5 inches S 135 psig.~
f.
Hanual Initiation 1,2,3 SR 3.3.6.1.6 NA.
(d)
On the I ard trip ystem r ired in ES 1, 2, 3, as g licable,/hen the utboap6 valve c
trol is %ransferr to the lternate r te shutdy n panel hd the outboard val e is cP'osed.
Only one trip system required in NODES 4 and 5 with RHR Shutdown Cooling System integrity maintained.
WNP-2 3.3-58 Amendment No.
149
P 4
~elk, 0
tl
Pr imary Containment Isol ation Instr umentation 8 3.3.6.1 BAS)S APPLICABLE SAFETY ANALYSES,
- LCO, and APPLICABILITY 5.a 5.b 5.c.
Area Tem erature and Differential Tem erature Hi h
(continued) can preclude t e isolati function As no d (fo tnot (d) to b e 3.3,6,1-,
o y th in o d trip syste is re uired o be ERAB in ODES
, 2, an 3,
a app cable w en th outbo rd v
ve c
trol s tran erre to t e ltern te re te s
tdow pane and th outb ar d v lve i clos
. Th's low sine the v
ve is clos and 'ts ope ation s
ad nist ativel contr led pre ude o ening outbo rd v
ve w en re ctor pr ssure is gr ater an the R cut n pe miss e pre sure.
The Area Temperature and Differential Temperature - High Functions are only required to be OPERABLE in MODE 3.
In MODES 1, and 2, the Reactor Vessel Pressure High Function and other administrative controls ensure that this flow path remains isolated to prevent unexpected loss of inventory via this flow path.
The Allowable Values are set low enough to detect a leak equivalent to 25 gpm.
This Function isolates the Group 6 valves.
S.d.
Reactor Vessel Water Level Low Level 3
Low RPV water level indicates the capability to cool the fuel may be threatened.
Should RPV water level decrease too far, fuel damage could result.
Therefore, isolation of some reactor vessel interfaces occurs to begin isolating the potential sources of a break.
The Reactor Vessel Water Level Low, Level 3 Function associated with RHR Shutdown Cooling System isolation is not directly assumed in any transient or accident analysis since bounding analyses are performed for large breaks such as MSLBs.
The RHR Shutdown Cooling System isolation on Level 3 supports actions to ensure that the RPV water level does not drop below the top of the active fuel during a vessel draindown event caused by a leak (e.g.,
pipe break or inadvertent valve opening) in the RHR Shutdown Cooling System.
Reactor Vessel Water Level Low, Level 3 signals are initiated from differential pressure switches that sense the difference between the pressure due to a constant column of continued WNP-2 8 3.3.6.1-27 Revision 16
4
Primary Containment Isolation Instrumentation 8 3.3.6.1 BAS)S APPLICABLE SAFETY ANALYSE
- LCO, and APPLICABILITY 5.d.
Reactor Vessel Water Level Low Level 3
(continued)
S, water (reference leg) and the pressure due to the actual water level (variable leg) in the vessel.
Four channels (two channels per trip system) of the Reactor Vessel Water Level Low, Level 3 Function are available and are r equi red to be OPERABLE to ensure that no single instrument f i lure can preclude the isolation functio~n s
no oo note
)
o e
.3.6 1- ),
o y the i oard t ip stem 's re ire to b
OPERA E in MOD S 1, 2, and as pplic le, w en e ou oard v
ve contr l is tr nsf rred t the ter ate emote s utdown p
el and he utboar valv is clo ed.
is is llowed s'e the alv is c
sed a
d it op ratio is ad nistrati ely con roll d to eclud ope ng t
e out oard v
ve when eactor res re is great th t e i
HR c issive essure.
Al
~<noted (footnote
(
to able 3.3.6. 1-1), only one trip syste9 is requi red to be OPERABLE in MODES 4 and 5 provided the RHR Shutdown Cooling System integrity is maintained.
System integrity is maintained provided the piping is intact and no maintenance is being performed that has the potential for draining the reactor vessel through the system.
The Reactor Vessel Water Level Low, Level 3 Function is only required to be OPERABLE in MODES 3, 4, and 5 to prevent this potential flow path from lowering reactor vessel level to the top of the fuel.
In MODES 1 and 2, the Reactor Vessel Pressure - High Function and administrative controls ensure that this flow path remains isolated to prevent unexpected loss of inventory via this flow path.
The Reactor Vessel Water Level Low. Level 3 Allowable Value was chosen to be the same as the RPS Reactor Vessel Water Level - Low, Level 3 Allowable Value (LCO 3.3'. 1) since the capability to cool the fuel may be threatened.
This Function isolates the Group 6 valves.
continued WNP-2 8 3.3,6.1-28 Revision 16
r q I
~l
Primary Containment Isol ation Instr umentation B 3.3.6.1 BASgS APPLICABLE SAFETY ANALYSES,
- LCO, and APPLICABILITY (continued) 5.e.
Reactor Vessel Pressure Hi h
The Shutdown Cooling System Reactor Vessel Pressure High Function is provided to isolate the shutdown cooling portion of the RHR System.
This interlock is provided only for equipment protection to prevent an intersystem LOCA scenario and credit for the interlock is not assumed in the accident or transient analysis in the FSAR.
The Reactor Steam Dome High pressure signals are initiated from two pressure switches.
Two channels of Reactor Steam Dome Pressure - High Function are=availabl'e and are required to be OPERABLE to ensure that no single instrument fai lure can reclude the isolation function.
noted (footn e (d to Tabl 3.3.6,
-1),
on y the i board rip sy tern is requir d to be OPERAB in MOD S 1, and 3, as ap licab e, when he outb ard val e contr 1 is ransfer ed to he alte nate r ote sh down p
el an the o
board alve s
cl ed.
T s is a
owed s'nce th valve is clo d
an its o
ration s
admi istrati ely co trolle to pr elude openin e outb ard val e when eactor pressu e is g eater than t e HR cut in per ssive essur The Allowable Value was chosen to be low enough to protect the system equipment from overpressurization.
This Function isolates the Group 6 valves.
5.f.
Manual Initiation The Manual Initiation switch and push button channels introduce signals into the RHR Shutdown Cooling System isolation logic that are redundant to the automatic protective instrumentation and provide manual isolation capability.
There is no specific FSAR safety analysis that takes credit for this Function.
It is retained for overall redundancy and diversity of the 'isolation function as required by the NRC in the plant licensing basis.
There are two switch and push buttons (with two channels per switch and push button) for the logic, one switch and push button per trip system.
Four channels of the Manual Initiation Function are available and are required to be OPERABLE in MODES 1, 2,
and 3 since these are the MODES in continued WNP-2 B 3.3.6.1-29 Revision 16 tL (gs
C l
Primary Containment I sol ation Instr umentati on B 3.3.6.1 BASES APPLICABLE SAFETY ANALYSES,
- LCO, and APPLICABILITY 5.f.
Manual Initiation (continued) which the RHR Shutdown Cooling System Isolation automatic Functions are required to be OPERABLE.
While certain automatic Functions are required in MODES 4 and 5, the Manual Initiation Function is not required in MODES 4 and 5,
since there are other means (i.e.,
means other than the Manual Initiation switch and push buttons) to manually isolate the RHR Shutdown Coolin System from the control room n
e ootno e
d) to a
e
.3.
- ),
on the
~nboa d trip s stem is r
uired to e
OPERA E in MO ES 1, 2,
a d 3, as pplicable when the utboard alve co trol is tra sferred o the alt mate rem e shutd n panel and th ou board v
ve is clo ed.
This is allow d since he val i
closed nd its op ration is administ atively ontrol ed o precl de openin the outbo rd valve when re ctor pr ssure is gr ea er than t RHR cut n 'permis ive pre sure.
There is no Allowable Value for this Function, since the channels are mechanically actuated based solely on the position of the switch and push buttons.
This Function isolates the Group 6 valves.
ACTIONS A Note has been provided to modify the ACTIONS related to primary containment isolation instrumentation channels.
Section 1.3, Completion Times, specifies that once a
Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition discovered to be inoperable or not within limits will not result in separate entry into the Condition.
Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure.
with Completion Times based on initial entry into the Condition.
- However, the Required Actions for inoperable primary containment isolation instrumentation channels provide appropriate compensatory measures for separate inoperable channels.
As such, a Note has been provided that allows separate Condition entry for each inoperable primary containment isolation instrumentation channel.
continued WNP-2 B 3.3.6.1-30 Revision 16
REQUEST FOR AMENDMENT TECHNICALSPECIFICATION 3.3.6.1 Replacement Pages for Technical Specification 3.3.6.1
Primary Containment Iso ation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 4)
Primary Contairment Isolation Instrwentation FUNCTION APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED CONDITIONS TRIP SYSTEM ACTION C.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 4.
RWCU System Isolation (continued) d.
Heat Exchanger Room Area Temperature High e.
Heat Exchanger Room Area Ventilation Differential Temperature High f.
Pump Room Area Temperature High g.
Pump Room Area Ventilation Differential Temperature High h.
RWCU/RCI C Line Routing Area Temperature High 1I2I3 1,2,3 1,2,3 1 per room 1,2,3 1 per room 1,2,3 SR 3.3.6.1.3
< 160'F SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.3 S 70'F SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.3 5 180oF SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.3
< 100'F SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.3
< 180'F SR 3.3.6.1.4 SR 3.3.6.1 '
i.
RWCU Line Routing Area Temperature High Room 409, 509 Areas Room 408, 511 Areas 1,2,3 1 per room SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.6
< 175'F S 180'F j.
Reactor Vessel Water Level Low LoM, Level 2 k.
SLC System Initiation le Manual Initiation 5.
Pump Room Area Temperature High 1,2,3 1.2 1I2I3 2(c) 1 per room SR 3.3.6.1.2
> -58 inches SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.6 NA SR 3.3.6.1.6 NA SR 3.3.6.1.3
< 150'F SR 3.3.6.1.4 SR 3.3.6.1.6 (continued)
(c)
SLC System Initiation only inputs into one of the two trip systems.
WNP-2 3.3-57 Amendment No. 449
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 4 of 4)
Primary Containment Isolation Instrunentation FUNCTION APPLICABLE HODES OR OTHER SPECIFIED CONDITIONS CONDITIONS REFERENCED REOUIRED FROH CHANHELS PER REQUIRED TRIP SYSTEH ACTION C.1 SURVEILLANCE REOUIREHENTS ALLOHABLE VALUE 5.
RHR SDC System Iso let ion (continued) b.
Pump Room Area Ventilation Differential Temperature High c.
Heat Exchanger Area Temperature High 1 per room 1 per room SR 3.3.6.1.3 5 70'F SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.3 SR 3.3.6.1.4 SR 3.3.6.1.6 Room 505 Area Room 507 Area Room 605 Area Room 606 Area d.
Reactor Vessel llater Level Low, Level 3 e.
Reactor Vessel Pressure High 3,4,5 1.2.3 2(d)
SR 3.3.6.1.1 SR 3.3.6.1 '
SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6
< 140'F
< 160'F 5 150'F S 140'F h 9.5 inches
< 135 psig f.
Hanual Initiation 1,2,3 SR 3.3.6.1.6 HA (d)
Only one trip system required in NODES 4 and 5 with RHR Shutdown Cooling System integrity maintained.
WNP-2 3.3-58 Amendment No. 449
0
~
~