ML19343B956
| ML19343B956 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/10/1981 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18025B355 | List: |
| References | |
| NUDOCS 8102180378 | |
| Download: ML19343B956 (22) | |
Text
\\
J
)
ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION REVISIONS GROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 (DOCKET NOS. 50-259, -260, -296) i 810218 0564
. ~. _
j i
1 i
i 1
J.
i i
t I.
I 4
a i
.I I
t i
i UNIT 1 PROPOSED CHKiGES f
1 1
f I
)
1 1
i s
4 il
+
t 1
i I
h t
t J
&I f
a 1
l f
4
?
?
b i
4 i
i i
t T
l
?
i
- r i
1 l
3 l
1 d
s E
4
.mwe v e g y,,
w-9.p y wy cy s w..p,,,w-y,wr.p.,,,yy.ywr,,,..y.,y, ewe,32 y
- me, -- w +. v -w w,. p g e gir w w,. mmw em,, w -w,+ n - mn s,. - n ww w v e
wwww w-w ww--
,ers.=%--
i TABIE 3.2.F Strveillance Instnunentation l
l Minimum # of Operable Instnument Type Indication Channels Instnunent #
Instnunent and Range Notes 2
H M 37 Drywell H 0.1 - 20%
(1) 2 2
H M 39 Concentration 2
l l
l l
i 1
H M 38 32ppression Chamber O.1 - 20%
(1) 2 l
H Concentration j
y 2
l l
l w
4 l
2 PdI-64-137 Drywell to Suppression Indicator (1) (2) (5)
PdI-64-138 Chamber Differential O to 2 paid i
pressure -
l l
1/ Valve Relief Valve Tailpipe (6)
Thermocouple Temperature or l
Acoustic Monitor on l
Relief Valve Tailpipe l
-. _ ~. - _ _ - -. - _ _ __
wafts FOR TaStf 3.2.F_
(1) From and fter the date that one of these paraaetere is reduced to one indication, continued operation to permissible during the succeeding thirty days unless such instrumentation is sooner made operable.
(2) From and after the date that one of these parameters is not indi-cated in the control room, continued operation is permissible during the succeeding seven days unless such instruce'ntation la seoner made operabic.
(3) If the requirements of notes (1) and (2) canno't be set, either the requirements of 3.5.H ehall be ce9 plied vich or an orderly shutdown shall be initiated and the reactor shall be in a Cold Cendition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(4) These surveillance instruments are considered to be redundant to each other.
(5) If the requirements of notes (1) and (2) cannot be met, and if one of the indications cannot be restored in six (6) hours, an orderly shutdown shall be initiated and the reactor shall be in a Cold Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
r om and after the date that both the acoustic monitor and the (6) rtemperature indication on any one valve fails to indicate in the control roon, continued operation is permissible if within the next thirty days a Special Report is submitted to the Commission pursuant to specification 6.7.3.c describing the cause of the malfunction and plans for restoring the instrument (s) to operabic status.
D**D
- D 80
A TABLE 4.2.F MINIMUM TEST AND CALIBRATION FREQUCf3CY FOR SURVEILLANCE It1STRU!!ENTATION Instrument Channel Calibration Frequency Instrument Check 17 Relief valve Tailpipe NA Once/conth (24)
Thermocouple Temperature 18 Acoustic Monitor on Once/ cycle (25)
Once/conth (26)
Relief Valve Tailpipe E
F
NOTES FOR TABLES 6.2.A THROUCH 4.2.H (Continued) 14 Upscale trip 14 functionally tested during functional test tire as required by section 4.7.8.1.a and 4.7.C.1.c.
- 15. The flow bias comparator will be tested by putting one flow unit in
" Test" (producing 1/2 scram) and adjusting the test input to obtain comparator rod block. The flow bias upscale _y_ill be verified by observing a local upscale trip light during operation and verified that it will produce a rod block during the operating cycle.
16.
Performed during operating cycle. Portions of the logic is c.hecked more frequently during functional tests of the functions that produce a rod block.
17.
This calibration consists of removing the function from service and performing an electronic calibration of the channel.
18.
Functional test is limited to the condition where secondary containment integrity is not required as specified in sections 3.7.C.2 and 3.7.C.3.
19.
Functional tcat is limited to the time where the SCTS is required to meet the requirements of section 4.7.C.1.c.
20.
Calibration of the comparator requires the inputs from both recirculation loops to be interrupted, thereby renoving the flow bias signal to the APRM and RBM and scramming the reactor. This calibration can only be performed durtag an outage.
21.
Logic test is limited to the time where actual operation of the equipment is permissible.
22.
One channci of either the reactor zone or refueling tone Reactor Building Ventilation Radiation Monitoring System may be administrative 1y bypassed for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for functional testing and calibration.
23.
The Reactor Cleanup System Space Temperature monitors are RTD's that feed a temperature switch in the control room. The temperature evitch may be tested monthly by using a simulated signal. The RTD itself is a highly reliable instrument and less frequent testing is necessary.
24.
This instrument check consists of comparing the thermocouple readings for all valves for consistence and for nominal expected values (not required during refueling outages).
25.
During each refueling outage, all acoustic monitoring channels shall be calibrcted. This calibration includes verification of accelerometer response due to mechanical excitation in the vicinity of the sensor.
26.
This instrument check consists of comparing the background signal levels for all valves for consistency and for nominal expected values (not required during refueling outages).
110 rh en e3
.'eg o Ju Ju k// h J o o Ju
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
^
).6.C Coolant t.c a k a ge 4.6.C Coolant 1.cak ige 3.
If the condition in 1 or 2 above cannot be met, an orderly shutdown shall be initiated and the react or shall be shut-D.
Safety and Relief Valves down in the Cold Condition vithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
1.
At least one scfety valve and approximately one-half of all D.
Safety and Relief Valves relief valves shall be bench-checked or replaced with a 1.
When more than one valve, bench-checked valve each opera-is known to ting cycle. All 13 valves be failed, an ordery shut-vill have down shall be initiated and been checked or replaced upon the reactor depressurized to the comolecion of every second less than 105 psig within 24 cycle.
hours.
2.
Once durine each operating cycle, each relief valve shall be manually opened until thermocouples and acoustic monitors downstream of the valve indicate steam is flowing f rom the valve.
1.
The integrity of the relief valve bellows shall be continuously monitored.
4.
At least one relief valve shril be disassembled and inspected each operating cycle.
E.
Jet Pumps E.
Jet Pumps 1.
Whenever the reactor is in the 1.
Whenever there is recirculation startup or run modes, all jet flow with the reactor in the pumps shall be operable. If startup or run modes with both it is determined that a jet recirculation pumps running, pump is inoperable, or if two jet pump operability shall be or more jet pump flow instru-checked daily by verifying that ment failures occur and can-the following conditions do not not be corrected within 12 occur simultaneously:
hours, an orderly shutdovn shall be init iat ed.ind the a.
The two recirculation loops reactor shall be uhutdown in have a flod imbalance of the Cold Condition within 24 15% or more when the pumps hours.
are operated at the same speed.
i 181 D9'D "O
T YQ' d-
.1 k m o
6.0 An:t:N;qa ATIVE coNTROM B.
Source Tests Rasults of required leak tests performed en sources if the tests reveal the presence of 0.005 microcurie or more of removable contanina tion.
C.
Soecial Hapo_rM (in writing to the Director of Regional Office of Inspection and Enforcement).
1.
Reports on the follcwing areas shall be subinitted as noted:
a.
Secondary containment 4.7.C within 90 Leak aate Testing (5) days of Completion of each test.
b.
Patique Usage 6.6 Annual Evaluation Operating Report c.
Seismic Instruantation
- 3. 2.J. 3 Within 10 d3ys Inoperabili ty af ter 30 days of inoperability d.
Relief Valve Tailpipe 3.2.F Within 30 days Instrumentation after inoperability of ther=ocouple and acoustic toonitor on one valve.
356
i i
d 4
4 r
i 1
UNIT 2 l
PROPOSED Cl!ANGES 1
i i
1 4
8 l
1 h
5 9
7 b
t r
i T
't l
I a
?
k 5
9 6
1 J
L I
)
-^1 = :v ev y=Epr -e wg g waeu rgee-g e--'
q=pw-whg grw gug-a-p qv p Wgwwe-gtv-me=*Pyvp,----3--ap-h-gy-gqulq-
$-Pn g rw Ng-+ g m g.v-muy,+d-e emrppp,q.4--pqh-e v y
- g.yy yw p ew e+4-mw-ege---pyms,We'ag ge sp ygg-'w-vs' F qva y s @g.
r TABIE 3.2.F Surveillance Instrumentation
' Minimum # or Operable Instnunent Type Indication Channels Instnament #
Instrument and Range Notes
'2 II H 94 Drywell and' Torus 0.1 - 20f, (1) 2 Ilydrogen H M 104 Ccncentration 2
1 l
a j
2 PdI-64-137 Drywell to Suppression Indicator (1) (2) (5)
PdI-64-138 Chamber Differential O to 2 paid pressure -
1/ Valve Relief Valve Tailpipe (6)
'lliermocouple Temperature or Acoustic Monitor on Relief Valve Tailpipe 4
I m
r
d TABLE 4.2.F mil 3IMUM TEST AND CALIBRATION FREQUEt!CY FOR SURVEILLANCE INSTRUMENTATION Instrument Channel Calibration Frequency Instrument Check 17 Relief valve Tailpipe NA Once/nonth (24)
Thermocouple Temperaturc 18 Acoustic Monitor on Once/ cycle (25)
Once/ month (26)
Relief Valve Tailpipe 5
M' i
WOTtS FOR TABLF. 3.2.P_
(1) From and after the date that one of these parameters is reduced to one indication, continued operation is permis'sible during the succeeding thirty days unless such instrumentation is sooner cade operable.
(2) Fron and after the date that one of these parameters is not indi-cated in the controi rocci, continued operation is pernissible during the succeeding seven days unless such inctrume'ntation is scener saade operable.
(3) If the require =ents of notes (1) and (2) ennno't be cet, either the requirements of 3.5.H ehall be ec iplied with or an orderly shutdown shall be initiated and the reactor shall be in a Cold Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(4) These surveillance instruments are considered to be redundant to each other.
(5) If the requirements of notes (1) and (2) cannot be met, and if one of the indications cannot be restored in six (6) hours, an orderly shutdown shall be initiated 'and the reactor shall be in a Cold Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(6) From and af ter the date that both the acoustic monitor and the temperature indt.ation on any one valve fails to indicate in the control room, continued operation is permissible if within the next thirty days a Special Report is submitted to the Commission pursuant to specification 6.7.3.c describing the cause of the malfunction and plans for restoring the instrument (s) to operabic status.
w I
D**D D 'yg so 20 kinL, ww o
NOTES FOR TABLES 4.2.A THROUCll 4.2.H (Continued) 14 Upscale trip is functionally tested during functional test time as required by section 4. 7. B.1.a and 4. 7.C.l.c.
Theilowbiascomparatorwillbetestedbyputtingoneflowunitin 15.
" Test" (producing 1/2 scram) and adjusting the test input to obtain comparator rod bicck. The flow bias upscale _.will be verified by observing a local upscale trip light during' operation and verified that it will produce a rod block during the operating cycle.
16 Performed during operating cycle. Portions of the logic is c.hecked more frequently during functional tests of the functions that produce a rod block.
17.
This calibration consists of removing the function from service and performing an electronic calibration of the channel.
18.
Functional test is limited to the condition where secondary centainment integrity is not required as specified in sections 3.7.C.2 and 3.7.C 3.
19.
Functional tent is limited to the time where the SCTS is required to meet the requirements of section 4.7.C.l.c.
20.
Calibration of the comparator requires the inputs from both recirculation loops to be interrupted, thereby removing the flov bias signal to the APRM and RBM a,d scramming the reactor. This calibration can only be performed during an outage.
21.
Logic test is llmited to the time where actual operation of the equipment is permissible.
22.
One channel of either the reactor zone or refueling zone Reactor Building Ventilation Radiation Monitoring System may be administratively bypassed for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for functional testing and calibration.
23.
The Reactor CIcanup System Space Temperature monitors are RTD's that feed a t empe ra t u re switch in the control room.
The temperature switch may be tested monthly by using a sinulated signal. The RTD itself is a highly reliable instrument and less frequent testing is necessary.
24.
This instrument check consists of comparing the thermocouple readings for all valves for consistence and for nominal expected values (not required during refueling outages).
25.
During each refueling outage, all acoustic monitoring channels shall be calibrated. This calibration includes verification of accelerometer response due to mechanical excitation in the vicinity of the sensor.
26.
This instrument check consists of comparing the background signal levels for all valves for consistency and for nominal expected values (not required during refueling outages).
110 1
9@
3~Y
,j. k b
gg 6
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIRE 5ENTS 3.6.C Coolant Leakavf 4.6.C Coolant Leakage 3.
If the condition in 1 or 2 above cannot be eet, an orderly shutdown shall be initiated and the reactor shall be shut.
D.
Safety and Relief Valves down in the Cold Condition withia 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br />.
1.
At least one safety valve and approximately one-half of all D.
Safety and Relief valves relief valves shall be bench-checked or replaced with a l
1.. When more than one relief bench-checked valve each opera-valve or one or more safety ting cycle. All 13 valves (2 valves are known to be safety and 11 relief) vill have failed, an orderly shutdown been checked or replaced upon shall be initiated and the the conolecion of every second reactor depressurized to C7Cl*-
less than 105 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
Once during each operating cycle, each relief valve shall be manually opened until thernoccuples and acoustic monitors dounstrean of the valve indicate steam is flowing from the valve.
3.
The integrity of the relieff safety valve bellows shall be continuously monitored.
4.
At least one relief valve shall be_ disassembled and inspected each operating cycle.
E.
Jet Pumps E.
Jet Pumps 1.
Whenever the reactor is in the 1.
Whenever there is rceirculation startup or run modes, all jet flow with the reactor in the l
pumps shall be operable. If startup or run modes with both it is determined that a jet recirculation punps ru.ning, j
pump la inoperable, or if two jet pump operability chall be or more jet pump flow instru-checked daily by verifying that ment failures occur and can-the following conditions do not not be corrected within 12 occur simultaneously:
[
hours, an orderly shutdown j
ahall be initiated and the a.
The two recirculation loops reactor shall be shutdown in have a flow imbalance of the Cold Condition within 24 15: cr more when the pu:ps hours.
are operated at the same speed.
181 l
mm
^o D
_A.
=
oe e
l t
6.0 AJ:tINI5TRATIVE cont 90Ls B.
Source Tests Results of required leak tests performed en sources if the tests reveal the presence of 0.005 microcurie or more of removable cortumination.
C.
Sorcial R alp rt s (in writing to the Director of Degional Of fice of Inspection and Enforcement).
1.
Reports on the following areas shall be submitted as noted:
a.
Secondary Containment 4.7.C Within 90 Leak Rate Testing (5) days of completion of each test, b.
Patigue Usage 6.6 Annual Evaluation Operating Report c.
Seismic Instrumentation
- 3. 2.J. 3 Within 10 d3ys Inoperability af ter 30 days of inoperability d.
. Relief Valve Tailpipe 3.2.F Within 30 days Instrumentation after inoperability of thermocouple and acoustic monitor on one valve.
356
i J
UNIT 3 3
PROPOSED CF.ANGES t
i 1
4 4
i 1
.t i
i w
1 1
6 5
}
s t
1:
s
- w...
w,-se.,,,. +
..,,,+--,-r-,.
-,,-,-.,--,wr--,,,-,
p-c.,-
.-,+w-.,.w,,,..w m,
.p ww.
-,or-,
,-y--.--.--w-.w,,,,-.r,,+
4 i
4 e
TABIE 3.2.F Surveillance Instrumentation Minimum.# of.
. Operable Instnutent Type Indication Channels' Instrument'#
Instrument and Range Notes
., 2
!! M - 76 ' 94 Drywell and Terus 0,1_ gof, (1) 2 Ilydrogen H M 104
-Ccncentration 2
E 4
1 2
t
.2
.PdI-64-137 Drywell to Suppression Indicator
-(1) (2) (5)
'PdI-64-138
. Chamber Differential O to 2 paid pressure -
g i
1/ Valve Relief Valve Tailpipe (6)
-Thermocouple Temperature
'or Acoustic Monitor on Relief Valve Tailpipe t
9 i
Wo?ES FOR T AEl.E J. 2 F_
(1) Troa and after the date that one of these para-eters is reduced to one indication, continued cperation is permissible-during the succeeding thirty days unless such instru:nestation is sooner nade operable.
(2) Tron and after the date that one of these parsneters is not indi-cated in the control roce, continued operatien is permissible
~
during the eucceeding seven days unless such instrue.entation is seoner made operable.
(3) If the require =ents of notes (1) end (2) canno't be met, either the require-ents of 3.5.H ehall be cc plied with or an orderly shutdo n shall be initiated and the reactor shall be in a Cold Ccoditics within 2f. hours.
(4) These surveillante instruments are considered to be redundant to each cther.
(5) If the require =ents of notes (1) and (2) cannot be =ct, and if one of the indications cannot be restored in six (6) hours, an orderly shutdown shall be initiated and the reactor shall be in a Cold Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(6) Fron and after the date that both the accustic monitor and the te=perature' indication on any one valve fails to indicate in the control room, continued or > ration is permissible if within the next thirty days a Special teport is submitted to the Commission pursuant to specification 6.7.3.c describing the cause of the malfunction and plans for restoring the instrucent(s) to operable status.
83 D**
- D 9"l i
al 60 d@U \\.P a
4 TABLE 4.2.F MINIMUM TEST AND CALIBRATION FREQUE!!CY FOR SURVEILLANCE It1STRU!tENTATION Instrument Channel Calibration Frequency Instrument Check 17 Pelief valve Tailpipe NA Once/ month (24)
Thermo~couplc Temperature 18 Acoustic Monitor on Once/ cycle (25)
Once/ month (26)
Relief Valve Tailpipe
~o;'
I
NOTES FOR TABLES 4.2.A THROUCH 4.2.H (Continued)_
14 Upscale trip 14 functionally tested during functional test time as required by section 4.7.B.I.a and 4.7.C.l.c.
- 15. Theklowbiascomparatorwillbe tested by putting one flow unit in
" Test" (producing 1/2 scram) and adjusting the test input to obtain comparater rod block. The flow bias upscale y_ill be verified by observing a local upscale trip light during operation and verified that it will produce a rod block during tre operating cycle.
16.
Perforned during operating cycle. Portions of the logic is c.hecked more frequently during functional tests of the functions that produce a rod block.
17.
This calibratian consists of removing the function from servie.e and performing an electronic calibration of the channel.
18.
Functiona) test is limited to the condition where secondary containment integrity is not required as specified in sections 3.7.C.2 and 3.7.C.3.
19.
Functional tent is limited to the time where the SCTS is required to meet the requirements of section 4.7.C.1.c.
20.
Calthrsiton of the comparator requires the inputs from both recirculation loops to be interrupted. thereby removing the flow bias signal to the APRM and RBM a id scramming the reactor. This calibration can only be performed during an outage.
21.
Logic test is limited to the time where actual operation of the equipment is permissible.
22.
One channel af either the reactor zone or refueling zone Reactor Building Ventilation Radiation Monitoring System may be administratively bypansed for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for functional testing and calibration.
23.
The Reactor Cicanup System Space Temperature nonit rs are RTD's that feed a temperature switch in the control room.
The temperature switch may be tested monthly by using a 'trulated signal. The RTD itself is a highly reliable instrument and Ic.
'requent testing is necessary.
24.
This instrument check con.
- s of comparing the thereoccuple readings for all alves for consistence and for nominal expected values (not required during refueling outages).
25.
During each refueling outage, all e.coustic monitoring channels shall be calibrated. This calibration includes verification of accelerometer response due to mechanical excitation in the vicinity of the sencer.
26.
This instrument check consists of comparing the background signal levels for all valves for ccasistency and for nominal expected values (not required during refueling outages).
107 D**D 90 3'lh
.I m MA Xfnk=
L r
i LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIRDfENTS
- 1. 6
_Pf ! M A fd Y SYSTEM BCUNDARY
- 4. 6 PRIMARY SYSTEM BOUNDARY D.
Safety and Relief valves D.
Safety and Re1ief valves 1.
At least one safety 1
When nne or more valve and valves, saf ety or approximately one-relief, is known to half of all relief be failed, an orderly valves shall be shutdown shall be bench-checked or initiated and the replaced with a reactor depressurized bench-checked valve to less than 105 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
each operating cycle.
All 13 valves (2 saf ety and 11 relief) will have been checked or replaced upon the completion of every second cycle.
2.
Once during each operating cycle, each relief valve shall be nanually opened until thernocouples and acoustic nonitors downstrean of the valve indicate steam is flowing from the valve.
3.
The-integrity of the relief /saf ety valve t
bellows shall be continuou sly ricnitor ed.
4
-At least one relief
. valve shall be disassembled and inspected'each operating cycle..
l i
f i
t L
l l
l D "
}D C}D ]Y 192 W b Ju o ju if
6.0 ADMINISTRATIVE CONTROLS B.
Source ?ests j
Results of required leak tests performed on sources if the tests reveal the presence of 0.005 microcurie or more of removable contamination.
C.
Special Reports (in writing to the Director of Regional Of fice of Inspection and Enforcement).
1.
Reports on the following areas shall be submitted as noted:
~
a.
Secondary Containment 4.7.C Within 90 Leak Rate Testing (5) days of completion of each test.
b.
Fatigue Usage 6.6 Annual Evaluation Operating Report C.
Relief Valve Tailpipe 3.2.F Within 30 days Instrumentation after inoperability of thermocouple and acoustic monitor on one valve.
l t
7 m ee.
p 386 l
l i
I 4
r
- - -