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{{#Wiki_filter:}} | {{#Wiki_filter:9 ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 i DOCKET NOS. 50-327 AND 50-328 (7NA-SQN-TS-89-02) - | ||
i i | |||
LIST OF AFFECTED PAGES Unit 1 i 3/4 9-8 | |||
* B3/4 9-2 , | |||
Unit 2 3/4 9-9 B3/4 9-2 ! | |||
b 8 | |||
.i I | |||
A | |||
: s. > | |||
e | |||
) | |||
O * | |||
: e. | |||
* h e-e 900124042790011g7 pus nooexosoogig P 4 | |||
} | |||
. .2 _ . . _ .. . . - | |||
,. . __-~ ;;; z 3.. .J ' | |||
\ | |||
REFUELING OPERATIONS j 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION ( ' | |||
{L ALL WATER LEVELS 1 | |||
LIMITING CONDITION FOR OPERATION rP l | |||
\ | |||
3.9.8.1 At least one residual heat removal (RHR) loop shall be in operation. | |||
APPLICABILITY: MODE 6. | |||
ACTION: * | |||
: a. With less than one residual heat removal loop in operation, except ! | |||
as provided in b. below, suspend all operations involving an increase ! | |||
in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System. Close all containment penetrations providing direct access from the containment atmosphere to the , | |||
outside atmosphere within 4 hours. | |||
: b. The residual heat removal loop may be removed from operation for up to I hour per 8 hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs, | |||
: c. The provisions of Specification 3.0.3 are not applicable. | |||
( I SURVEILLANCE REQUIREMENTS . | |||
sl.t h less +han 276 hours since subcroficoloty, at ! | |||
4.9.f.l.) 0.0.0.1 AM least one residual heat removal loop shall be verified to be in pp operation and circulating reactor coolant at a flow rate of greater than or equal to 2500 gpm at least once per 12 hours. | |||
. .s ! | |||
Q. | |||
'I,K 4.*) . 6L ?. Hith greoler tha n or e vaIlo 278 hours since soberMic.aldy, at lces+ one residua l heat remova l loop shall be veriNed to be in ' | |||
ope ro sion and c.lrc.ulo}lry rectcic>r c.co lan4 al a flow rate of . | |||
greater tha n o r- e val to 2.coogpm a t. leas + once perg?. hours. | |||
.h | |||
' September 17, 1980 | |||
) | |||
3/4 9-8 SEQUOYAH - UNIT-1 i | |||
_ 4 i | |||
a_ . _ n; c - n.. -- ~- :- _ | |||
U: ' ' | |||
I l | |||
REFUELING OPERATIONS .I BASES 3/4.9.6 MANIPULATOR CRANE The OPERABILITY requirements for the manipulator cranes ensure that: | |||
: 1) manipulator cranes will be used for movement of drive rods and fuel assemblies, | |||
: 2) each crane has suf ficient load capacity to lift a drive rod or fuel assemoly, j and 3) the core internals and pressure vessel are protected from excessive , | |||
lifting force in the event they are inadvertently engaged during lifting operations. , | |||
3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA | |||
, , , The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures'that in the event this load is dropped: | |||
: 1) the aciOvity release will be limited to that contained in a single fuel - | |||
assembly, and 2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses. | |||
3/4.9.8 RESIDUAL' HEAT REMOVAL AND COOLANT CIRCULATION ( l The requirement that at least one residual heat removal (RHR) loop be in operation ensures that; 1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140'F - | |||
as required during the REFUELING MODE, and 2) sufficient coolant circulation is maintained through the reactor core to miniWe +ha a Har+e af incident and prevent boron stratification, pd tNSERT A] boron dilution , | |||
TP The requirement to have two RHR loops OPERABLE when there is less than A; 23 feet of water above the reactor pressure vessel flange ensures that a . | |||
single failure of the operating RHR loop will not result in a complete loss of t - Tl '. | |||
residual heat removal capability. With the reactor vessel head removed and E 23 feet of water above the reactor pressure vessel flange, a large heat sink if ' | |||
is available for core cooling. Thus, in the event of a failure of the d' operating RHR loop, adequate time is provided to initiat'e emergency procedures Q! | |||
to cool the core. ' | |||
3/4 9.9 CONTAINMENT VENTILATION SYSTEM ' | |||
The OPERABILITY of this system ensures that the containment vent and i pdrge penetrations will be automatically isolated upon detection of high ' | |||
radiation levels within the containment. The OPERABILITY.of this system is , | |||
required to restrict the release of radioa-tive material from the containmant . 4 atmosphere to the environment. [ . | |||
2 | |||
+ | |||
SEQUOYAH - UNIT 1 B 3/4 9-2 SEP 171980 .) | |||
y 4 | |||
,4 - | |||
-- +.n , , ,_ &' | |||
1 e , | |||
., INSERT A . | |||
The reduction of the minimum required flow rate after 278 hours following i subtriticality reduces the probability of losing an RHR pump by > | |||
air-entrainment from pump vortexing. This is a particular concern during i reduced RCS inventory operation. The 278-hour value is based on required i decay heat removal, and the 2000 gpm value is limited by cavitation in.the j control valve and valve chattering in the 10-inch check valve. ; | |||
4 l | |||
1 1 | |||
i i | |||
.p 9 | |||
I-t f | |||
4 I | |||
e t | |||
'I + | |||
6 | |||
'E | |||
( ! | |||
L l | |||
f | |||
, . e . | |||
f l | |||
: i. . . | |||
~..' | |||
i | |||
;[- l o - | |||
,w t: | |||
~; . a . .. .: __ . | |||
7-REFUELING OPERATIONS e | |||
(, 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION ALL WATER LEVELS LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one residual heat removal (RHR) loop shall be in, operation. | |||
APPLICABILITY: MODE 6. . | |||
ACTION: | |||
~ | |||
: a. With less than one residual heat removal loop in operation, 2xcept as provided in b. below, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration , | |||
of the Reactor Coolant System. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours. | |||
: b. The residual heat removal loop may be removed from operation for up to 1 hour per 8 hour period during the performance of-CORE ALTERATIONS in.the vicinity of the reactor pressure vessel hot legs. | |||
: c. The provisions of Specification 3.0.3 are not applicable. ; | |||
SURVEILLANCE REQUIREMENTS l With less than 2.76 hours since, suberHicalify > a k ; | |||
+.9.8.l.l 4.0.^.F AM least one residual heat removal loop shall be verified to be in e* | |||
operation and circulating reactor coolant at a flow rate of greater than or f equal to 2500 gpm at least once per 12 hours, s.2 | |||
'.\t 4 | |||
'f, | |||
: 4. % til.2. With 3 realer than or egual le 278 hsors since subtroWealdy , | |||
at Icos+ one. ' resids t heat e e move I Inp shau be veroned to bs in opera Ubn and cire.platiny reac. lor coola n t at 0 ll* W r* I* | |||
* t oP 3 realte ihan oe e veI do 2.000 ypen , ed leas + o n c e. p e r- ' | |||
I2 h ov r o. , | |||
* *^ | |||
' o SEQUOYAH - UNIT 2 3/4 9-9 - | |||
2 | |||
;~ -- . | |||
tr; 1 4! | |||
. j i | |||
REFUELING OPERATIONS BASES 3/4.9.6 MANIPULATOR CRANE l | |||
The OPERABILITY requirements for the manipulator cranes ensure that: | |||
: 1) manipulator cranes will be used for movement of drive rods and fuel | |||
* assemblies, | |||
: 2) each crane has sufficient load capacity to lift a-drive rod or fuel assembly, assembly, and 3) the core internals and pressure vessel are protected from , | |||
excessive lifting force in the event they are inadvertently engaged during lifting operations. | |||
3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA ! | |||
The restriction on movement of loads in excess of the nominal weight of a ' | |||
fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped . | |||
: 1) the activity release will be limited to that contained in a single fuel ' | |||
assembly, and 2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses. | |||
3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in operation ensures that; 1) sufficient cooling capacity is available to remove ' | |||
decay heat and maintain the water in the reactor pressure vessel below 140*F as required during the REFUELING MODE, and 2) sufficient coolant circulation is maintained thru the reactor core to mini 'n th; c "ade af ron dilution | |||
; incident and prevent boron stratification. Add /NS GRT' . | |||
The requirement to have two RHR loops OPERABLE when there is less than 9 23 feet of water above the reactor pressure vessel flange ensures that a dl single failure of the operating RHR loop will not result in a complete loss of M residual heat removal capability. With the reactor vessel head removed and ? | |||
l 23 feet of water above the reactor pressure vessel flange, a large heat sink 4 is available for core cooling. Thus, in the event of a failure of the operating ' | |||
d RHR loop, adequate time is provided to in!tiate emergency procedures to cool | |||
! the core. | |||
* t . | |||
1; t 3/4.9.9 CONTAINMENT VENTILATION SYSTEM ii. | |||
( | |||
The OPERABILITY of this system ensures that the containment vent and | |||
* purge penetrations will be automatically isolated upon. detection of high radiation levels within the containment. The OPERABILITY of this' system is . .. | |||
required to restrict the release of' radioactive material from the containment: ; | |||
atmosphere to the environment. | |||
j SEQUOYAH - UNIT 2 B 3/4 9-2 j | |||
~* | |||
d' 2, | |||
l L _ | |||
_ _ u _ + u} | |||
~ | |||
INSERT A The reduction of the minimum required flow rate after 278 hours following suberiticality reduces the probability of losing an RHR pump by air-entrainment from pump vortexing.. This is a particular concern during reduced RCS inventory operation. The 278-hour value is based on required decay heat removal, and the 2000 gpm value is limited by cavitation in the control valve and valve chattering in the 10-inch check valve. | |||
i i | |||
e e | |||
'l I | |||
. .f I | |||
5 i | |||
t i | |||
: s. 6 6 h' | |||
1, | |||
-t | |||
*$l | |||
' )I .[t, o, | |||
<l j | |||
j, t | |||
( | |||
i . | |||
=, | |||
i. | |||
l - j. | |||
.' 44 | |||
' ^ | |||
l | |||
! ,-- , 1, i ,-W | |||
,}} |
Latest revision as of 16:11, 17 February 2020
ML20005H325 | |
Person / Time | |
---|---|
Site: | Sequoyah |
Issue date: | 01/12/1990 |
From: | TENNESSEE VALLEY AUTHORITY |
To: | |
Shared Package | |
ML20005H323 | List: |
References | |
NUDOCS 9001240427 | |
Download: ML20005H325 (7) | |
Text
9 ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION CHANGE SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 i DOCKET NOS. 50-327 AND 50-328 (7NA-SQN-TS-89-02) -
i i
LIST OF AFFECTED PAGES Unit 1 i 3/4 9-8
- B3/4 9-2 ,
Unit 2 3/4 9-9 B3/4 9-2 !
b 8
.i I
A
- s. >
e
)
O *
- e.
- h e-e 900124042790011g7 pus nooexosoogig P 4
}
. .2 _ . . _ .. . . -
,. . __-~ ;;; z 3.. .J '
\
REFUELING OPERATIONS j 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION ( '
{L ALL WATER LEVELS 1
LIMITING CONDITION FOR OPERATION rP l
\
3.9.8.1 At least one residual heat removal (RHR) loop shall be in operation.
APPLICABILITY: MODE 6.
ACTION: *
- a. With less than one residual heat removal loop in operation, except !
as provided in b. below, suspend all operations involving an increase !
in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System. Close all containment penetrations providing direct access from the containment atmosphere to the ,
outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- b. The residual heat removal loop may be removed from operation for up to I hour per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs,
- c. The provisions of Specification 3.0.3 are not applicable.
( I SURVEILLANCE REQUIREMENTS .
sl.t h less +han 276 hours0.00319 days <br />0.0767 hours <br />4.563492e-4 weeks <br />1.05018e-4 months <br /> since subcroficoloty, at !
4.9.f.l.) 0.0.0.1 AM least one residual heat removal loop shall be verified to be in pp operation and circulating reactor coolant at a flow rate of greater than or equal to 2500 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
. .s !
Q.
'I,K 4.*) . 6L ?. Hith greoler tha n or e vaIlo 278 hours0.00322 days <br />0.0772 hours <br />4.596561e-4 weeks <br />1.05779e-4 months <br /> since soberMic.aldy, at lces+ one residua l heat remova l loop shall be veriNed to be in '
ope ro sion and c.lrc.ulo}lry rectcic>r c.co lan4 al a flow rate of .
greater tha n o r- e val to 2.coogpm a t. leas + once perg?. hours.
.h
' September 17, 1980
)
3/4 9-8 SEQUOYAH - UNIT-1 i
_ 4 i
a_ . _ n; c - n.. -- ~- :- _
U: ' '
I l
REFUELING OPERATIONS .I BASES 3/4.9.6 MANIPULATOR CRANE The OPERABILITY requirements for the manipulator cranes ensure that:
- 1) manipulator cranes will be used for movement of drive rods and fuel assemblies,
- 2) each crane has suf ficient load capacity to lift a drive rod or fuel assemoly, j and 3) the core internals and pressure vessel are protected from excessive ,
lifting force in the event they are inadvertently engaged during lifting operations. ,
3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA
, , , The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures'that in the event this load is dropped:
- 1) the aciOvity release will be limited to that contained in a single fuel -
assembly, and 2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses.
3/4.9.8 RESIDUAL' HEAT REMOVAL AND COOLANT CIRCULATION ( l The requirement that at least one residual heat removal (RHR) loop be in operation ensures that; 1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140'F -
as required during the REFUELING MODE, and 2) sufficient coolant circulation is maintained through the reactor core to miniWe +ha a Har+e af incident and prevent boron stratification, pd tNSERT A] boron dilution ,
TP The requirement to have two RHR loops OPERABLE when there is less than A; 23 feet of water above the reactor pressure vessel flange ensures that a .
single failure of the operating RHR loop will not result in a complete loss of t - Tl '.
residual heat removal capability. With the reactor vessel head removed and E 23 feet of water above the reactor pressure vessel flange, a large heat sink if '
is available for core cooling. Thus, in the event of a failure of the d' operating RHR loop, adequate time is provided to initiat'e emergency procedures Q!
to cool the core. '
3/4 9.9 CONTAINMENT VENTILATION SYSTEM '
The OPERABILITY of this system ensures that the containment vent and i pdrge penetrations will be automatically isolated upon detection of high '
radiation levels within the containment. The OPERABILITY.of this system is ,
required to restrict the release of radioa-tive material from the containmant . 4 atmosphere to the environment. [ .
2
+
SEQUOYAH - UNIT 1 B 3/4 9-2 SEP 171980 .)
y 4
,4 -
-- +.n , , ,_ &'
1 e ,
., INSERT A .
The reduction of the minimum required flow rate after 278 hours0.00322 days <br />0.0772 hours <br />4.596561e-4 weeks <br />1.05779e-4 months <br /> following i subtriticality reduces the probability of losing an RHR pump by >
air-entrainment from pump vortexing. This is a particular concern during i reduced RCS inventory operation. The 278-hour value is based on required i decay heat removal, and the 2000 gpm value is limited by cavitation in.the j control valve and valve chattering in the 10-inch check valve. ;
4 l
1 1
i i
.p 9
I-t f
4 I
e t
'I +
6
'E
( !
L l
f
, . e .
f l
- i. . .
~..'
i
- [- l o -
,w t:
~; . a . .. .: __ .
7-REFUELING OPERATIONS e
(, 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION ALL WATER LEVELS LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one residual heat removal (RHR) loop shall be in, operation.
APPLICABILITY: MODE 6. .
ACTION:
~
- a. With less than one residual heat removal loop in operation, 2xcept as provided in b. below, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration ,
of the Reactor Coolant System. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- b. The residual heat removal loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period during the performance of-CORE ALTERATIONS in.the vicinity of the reactor pressure vessel hot legs.
- c. The provisions of Specification 3.0.3 are not applicable. ;
SURVEILLANCE REQUIREMENTS l With less than 2.76 hours8.796296e-4 days <br />0.0211 hours <br />1.256614e-4 weeks <br />2.8918e-5 months <br /> since, suberHicalify > a k ;
+.9.8.l.l 4.0.^.F AM least one residual heat removal loop shall be verified to be in e*
operation and circulating reactor coolant at a flow rate of greater than or f equal to 2500 gpm at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, s.2
'.\t 4
'f,
- 4. % til.2. With 3 realer than or egual le 278 hsors since subtroWealdy ,
at Icos+ one. ' resids t heat e e move I Inp shau be veroned to bs in opera Ubn and cire.platiny reac. lor coola n t at 0 ll* W r* I*
- t oP 3 realte ihan oe e veI do 2.000 ypen , ed leas + o n c e. p e r- '
I2 h ov r o. ,
- *^
' o SEQUOYAH - UNIT 2 3/4 9-9 -
2
- ~ -- .
tr; 1 4!
. j i
REFUELING OPERATIONS BASES 3/4.9.6 MANIPULATOR CRANE l
The OPERABILITY requirements for the manipulator cranes ensure that:
- 1) manipulator cranes will be used for movement of drive rods and fuel
- assemblies,
- 2) each crane has sufficient load capacity to lift a-drive rod or fuel assembly, assembly, and 3) the core internals and pressure vessel are protected from ,
excessive lifting force in the event they are inadvertently engaged during lifting operations.
3/4.9.7 CRANE TRAVEL - SPENT FUEL PIT AREA !
The restriction on movement of loads in excess of the nominal weight of a '
fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped .
- 1) the activity release will be limited to that contained in a single fuel '
assembly, and 2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the accident analyses.
3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION The requirement that at least one residual heat removal (RHR) loop be in operation ensures that; 1) sufficient cooling capacity is available to remove '
decay heat and maintain the water in the reactor pressure vessel below 140*F as required during the REFUELING MODE, and 2) sufficient coolant circulation is maintained thru the reactor core to mini 'n th; c "ade af ron dilution
- incident and prevent boron stratification. Add /NS GRT' .
The requirement to have two RHR loops OPERABLE when there is less than 9 23 feet of water above the reactor pressure vessel flange ensures that a dl single failure of the operating RHR loop will not result in a complete loss of M residual heat removal capability. With the reactor vessel head removed and ?
l 23 feet of water above the reactor pressure vessel flange, a large heat sink 4 is available for core cooling. Thus, in the event of a failure of the operating '
d RHR loop, adequate time is provided to in!tiate emergency procedures to cool
! the core.
- t .
1; t 3/4.9.9 CONTAINMENT VENTILATION SYSTEM ii.
(
The OPERABILITY of this system ensures that the containment vent and
- purge penetrations will be automatically isolated upon. detection of high radiation levels within the containment. The OPERABILITY of this' system is . ..
required to restrict the release of' radioactive material from the containment: ;
atmosphere to the environment.
j SEQUOYAH - UNIT 2 B 3/4 9-2 j
~*
d' 2,
l L _
_ _ u _ + u}
~
INSERT A The reduction of the minimum required flow rate after 278 hours0.00322 days <br />0.0772 hours <br />4.596561e-4 weeks <br />1.05779e-4 months <br /> following suberiticality reduces the probability of losing an RHR pump by air-entrainment from pump vortexing.. This is a particular concern during reduced RCS inventory operation. The 278-hour value is based on required decay heat removal, and the 2000 gpm value is limited by cavitation in the control valve and valve chattering in the 10-inch check valve.
i i
e e
'l I
. .f I
5 i
t i
- s. 6 6 h'
1,
-t
- $l
' )I .[t, o,
<l j
j, t
(
i .
=,
i.
l - j.
.' 44
' ^
l
! ,-- , 1, i ,-W
,