ML19345B050
| ML19345B050 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/14/1980 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19345B041 | List: |
| References | |
| NUDOCS 8011260034 | |
| Download: ML19345B050 (29) | |
Text
.
Attachment A O
FACILITY OPERATING LICENSE NO. DPR-73
(
DOCKET NO. 50-320 Replace the follow ng pages of the proposed Appendix "A" Technical Specifications i
with the enclcsed pages as indicated.
The revised pages contain vartical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document comleteness.
Pages 3.1-1 3.1-2 3.4-1 3.7-1 3.7-2 3.8-4 B 3/4 4-1 B 3/4 7-1 l
l s o, r a c o o3%
THREE MILE ISLAND - UNIT 2 i
~-.
t f
LIMITING CONDITIONS FOR OPERATION 1
3.1 WATER INJECTION COOLING AND REACTIVITY CONTROL SYSTEMS l
3.1.1 BORATION CONTROL BORON INJECTION i
3.1.1.1 At least two systems capable of injecting borated cooling water into 4
the Reactor Coolant System shall be OPERABLE
- with:
a.
One system comprised of:
1.
- Onr OPERABLE makeup pump.#
2.
One OPERABLE decay heat removal pump.
3.
An OPERABLE flow path from the BWST.
The BWST shall contain at least 100,000 gallons of borated water at a minimum temperature i
of 50*F and at a boron concentration of between 3000 and 4500 ppm.
b.
The second system comprised of-the Standby Reactor Coolant System Pressure Control System.
APPLICABILITY:
When fuel is in the reactor pressure vessel.
ACTION:
With one of the above required systems inoperable, restore the inoperable system to GPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
J BORON CONCEN' RATION i
3.1.1.2 The reactor coolant shall be maintained at a boron concentration of between 3000 and 4500 ppm and at a temperature above 50 F.
APPLICABILITY:
When fuel is in the reactor pressure vessel.
ACTION None except as provided in Specification 3.0.3.
i
- Botn systems sna11 be considered OPERABLE when aligried per procedures approved pursuant to Specification 6.8.2.
- All makeup pumps shall be made inoperable when valve DH-V1 or OH-V171 is open by racking out their electrical power supply circuit. breakers.
THREE MILE ISLAND -' UNIT 2 3.1-1 e
c-m-
~v--
1 DETe:e I
f i
THREE MILE ISLAND - UNIT 2 3.1-2
LIMITING CONDITIONS FOR OPERATION 3.4 REACTOR COCLANT SYSTEM REACTOR COOLANT LOOPS 3.4.1 The Reactor Coolant System shall be operatec in accordance with procedures approved pursuant to Specification 6.8.2.
APPLICABILITY:
RECOVERY MODE.
ACTION:
None except as provided in Specification 3.0.3.
SAFETY VALVES 3.4.3 All pressurizer code safety valves snali ce OPERABLE witn a lif: setting of 2435 PSIG 1%.
- APPLICAEILIrv:
RECOVERY MODE.
ACTION:
None except as provided in Specification 3.0.3.
3.4.9 PRESSURE / TEMPERATURE LIMITS REACTOR COCLANT SYSTEM 3.4.9.1 Tne Reactor Coolant System shall be maintainec at a T."9 of less tnan 280 F and at a pressure of less than 600 psig.
APPLICABILITY: When fuel is in the reactor pressure vessel.
ACTION:
None except as providea in Specification 3.0.3.
l
- Tne lif t setting pressure shall correspond to ambient conditions of the valve i
at nominal operating temperature and_ pressure.
t l
I THREE MILE ISLAND - UNIT 2 3.4-1 I
l l
?
I i
t LIMITING CONDITIONS FOR OPERATION 4
i i
n 3.7 ' PLANT SYSTEMS' 3.7.1 FEE 0 WATER SYSTEM i
3.7.1 - The long term "B" steam generator cooling sys'.em shall.be maintained in an OPERABLE status.
1 APPLICABILITY:
RECOVERY-MCCE.
ACTION:
Witn tne long term cooling "B"' steam generator cooling 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 />.
l l
3.7.2 SECONDARY SERVICES CLOSED COOLING WATER SYSTEM i
3,7.2 1 At least two secondary services closed cooling water system pumps and l
heat excnangers anc the associated flow path shall be OPERABLE with each pump i
capable of being powered from' separate busses.
l APPLICABILITY:
RECOVERY MODE.
ACTION:
4 With only one secondary services closed cooling water pump or only one secondary I
services heat exchanger GPERAB.E, restore the inoperable pump or heat exchanger 1
to CPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
4 3.7.3 CLOSED CYCLE COOLING WATER SYSTEM NUCLEAR SERVICES CLOSED CYCLE COOLING SYSTEM 3.-7.3.1 At least two independent nuclear services closed cycle cooling water pumps and heat exchangers and the associated flow path shall be OPERABLE with each pump capable of being powerec from separate emergency busses.
.A.PPLICASILITY:
REC 3VERY M00E.
L ACTION:
With only one nuclear services closed cycle cooling water pump or only one l
nuclear services heat excnanger OPERASLE, restore tne inecerable pump or heat j'
exchanger.to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
~
t b
i 1
THREE MILE ISLAND -' UNIT 21 3.7-1
- o 4
. ~..,...
' ~ '
~ ~ ' '
~ '
- LIMITING CON:!TIONS FOR OPERATION DE"AYHEATCLOSEDC00LINCWAIERSYSTEM 3.7.3.2 At least one decay neat closed cooling water loop sec11 be OPERABLE.
42?LICAE LITY:
RECOVERY MODE.
A TION:
Wi th nc ceca) neat closed cooling ater loop OPERABLE, restore tne inoperable 1000 t: 0;ERAELE status wintin 2A nours.
MIN: DECAY HEAT REMOVAL SYSTEM 3.7.3.3 T-o mini cecay heat removal pumps and neat exchange s and ne asscci-atec flow path shall be OPERABLE.
APC.:CAE:_
When fuel is in tne reactor pressure vessel A.ia,.
With one mini decay heat removal pump and/cr heat exchanger inocerable, a.
restore the inopera0le pump and/or neat excnanger to OPERABLE status witnin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
c.
With t c mini deca) neat removal pumps anc/or heat exchangees o* tne associated flow patn in0peracle, restore at least one pump and heat excnanger anc the asscciatec flow patn to CPERABLE states wi thin 24 nou*s Or aitnin tne next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> make a Dacku; cooling syste-(ei ner LTC "B" or " Loss te Amcient") OPERABLE.
t 3.T.4 NL^ LEAR SERVICE RIVER WATER SYSTEM 3.7.4.1 Two independent nuclear service river water loops shall be OPERAELE.
APOLICAEILITY:
RECOVERY MODE.
Mw Iib 9
'a"t
- ns nuclea service river water loop inoperable, reste e tne 'noceratie
'c c to 00ERAELE status witnia 72 nours.
l l
THREE MILE ISLAN - UNIT 2 3.7-2
TABLE 3.8-2 RESTORATION TIME MATRIX c
Restore One Restore Other Component Component (Hours)
(Hours)
I aa 24 72 i
E o r i
3 T;~
~
e c
hbl g3 g g ab 12 2
/
i 5t 3'i&
bb 12 72 i
No'e:
a and b above correspond to components describec in Specificatica 3.8.1.1 ite.T:s a anc b respectively.
l 3
THREE MILE ISLAND - UNIT 2 3.8-3
LIMI'ING CONDITIONS FOR OPERATION 39.2 ONSITE POWER DISTRIBUTION SYSTEMS 4
A.C.
DISTRIBUTICN 3.E 2.'
The following A.C. ele:trical busses shall te OPERAELE anc ene gi:ec
.i ti tie creakers open (unless closed in accorcance with procecures aoprovec pu-su'. to Specification 6.5.2) between redundant busses:
415; voit Emergency Eus # 2-1E and 2-3E 4;6.
volt Emergency Bus # 2-2E and 2-4E
- 160 volt Busses # 2-3 and 2-4 45 :-
vcit Emergency Bus # 2-11E, 2-12E an: 2-31E 4SC solt Emergency Sus # 2-21E. 2-22E anc 2-a E dE:
volt Busses # 2-31, 2-al, 2-32, 2-42, 2-3E. 2-36, 2-45, s.c 2 's l
12:
volt A.C. Vita' Buh # 2-1V 120 vc't A.C. Vital Bus # 2-2V 12:
vo'.t A.C. Vital Bus
- 2-3V 12; voit A.C. Vital Sus
- 2-4\\
....,... M..
st. 5tn*
m
..t i
tr less than tre above comolement of A.C. busses OPERABLE, restore the W4 ircperat'e bus to OPERAELE status witrin 8 nours.
THREE MILE ISLAND - UNIT 2 3.8-4
3/4.4 REACTOR COOLANT SYSTEM EASES 3/4.4.1 REACTOR COOLANT LOOPS Several alternative methods are available for removal of reactor decay heat.
These methods include use of the Mini Decay Heat Removal System, the
" Loss to Amcient" cooling moce, and operation of the Reactor Coolant System in the natural circulation mode with heat rejection via the long term "B" steam generator cooling mode.
Any one of these cooling methods provides adequate cooling of the reactor and each method is available for decay heat removal.
Procedures have been prepared and approved for use of these various cooling methoos.
- 3. 4. 4. 3 aar:TY VALVES Tse pressurizer coce safety valves operate to prevent tne RCS from being pressurizec above its Safety Limit of 2750 psig.
Each safety valve is designed to relieve 348,072 lbs per hour of saturated steam at tne valve's setpoint.
3/4.4.9 PRESSURE / TEMPERATURE LIMIT ine RCS pressure and temperature will be controlled in accordance witn aDoeovec procecures to prevent a nonductile failure of the RCS while at the same time permitting the RCS pressure to be maintained at a sufficiently high value te permi t operation of tne reactor coolant pumps.
THREE MILE ISLAND - UNIT 2 B 3/4 4-1
i 3/4.7 PLANT SYSTEMS BASES 3/4.7.1 FEEDWATER SYSTEM
~
The long term "B" steam generator cooling system is required to be main-l tained in an OPERABLE status since it is an alternative method for removing decay heat from the reactor coolant system.
3/4.7.2 SECONDARY SERVICES CLOSED COOLING WATER SYSTEM The secondary services closed cooling water system is required to be maintained in an OPERABLE condition since it is used to cool the "B" steam generator closed loop cooling system.
3/4.7.3 CLOSED CYCLE COOLING WATER SYSTEM 3/4.7.3.1 NLCLEAR SERVICES CLOSED CYCLE COOLING SYSTEM GPERABILITY of the nuclear services closed cycle cooling system is reauired during operation of the MDHRS since this system provides the heat sink for the MOHRS.
3/4.7.3.2 DECAY HEAT CLOSED COOLING WATER SYSTEM
[
The decay heat closed cooling water system is required to be maintained in an OPERABLE status since it is provided to remove heat from the DHR system which is being maintained OPERABLE in a backup status for possible core cooling.
3/4.7.3.3 MINI DECAY HEAT REMOVAL SYSTEM (MDHRS)
OPERABILITY of the MDHRS is required since it is an alternative method for removing decay heat from the reactor.
The MDHRS is provided with two pumos and two heat exchangers; one pump and one heat exchanger have adequate capacity for removing the present level of decay heat from the-core.
3/4.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM The nuclear service river water system uses river water to cool the nuclear services closed cycle cooling system, the secondary services closec l
cooling water system, anc cecay heat closed-cooling water system; therefore, it must be OPERABLE too.
This system rejects its heat to the river as the ultimate heat sink.
i
'THREE MILE ISLAND - UNIT 2 B 3/4 7-1
CONTAINMENT SYSTEMS BASES
.s
(
3/4.7.6 FLOOD PROTECTION The limitation on flood protection ensures that facility protective t
i actions will be taken in the event of flood conditions.
The limit of elevation 302 Mean Sea Level is baseo on the maximum elevation at which facility flood control measures provida protection to safety related equipment.
i 3/4.7.7 CONTROL ROCM EMER~ENCY AIR CLEANUP SYSTEM The OPERABILITY of the control room emergency air cleanup system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the eouipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations person?:el during and following all credible accicent conditions.
The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole bocy, or its equivalent.
This limitation is consistent with the eeavirements of General Design Criterion 19 of Appendix "A",
3/4.7.10 FIRE SUPPRESSION SYSTEMS i
The OPERABILITY of the fire suppression systems ensures that adecuate fire suporession capability is available to confine and extinguish fires occuring in any portion of the facility wnere safety related ecuipment is locatec.
The fire suppression system consists of the water system, spray anc/or sprinklees. Halon and fire hose stations.
The collective capability of the fire suppression systems is adequate to minimize potential damage to safety related equipment and is a major element i~ the facility fire protec-
- ion prog am.
Any two of the four main fire pumps provice comoined capacity greater than 3575 gpm.
In tne event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the affected equipment can be restored to service.
In the event '. hat the fire suporession water system becomes inoperable, immediate corrective measures must be taken since tnis system r.rovides the major fire suppression capability of the plant.
The requiremene for a Special Report to the Commission provides for timely evaluation of the acceptability of the corrective measures to provice adecca*a fire suppression capability for the continued operation of the nuclear planc.
- THREE MILE ISLAND - UNIT 2 B 3/4 7-2 2
, mn.
Attachment A FACILITY OPERATING LICENSE NO. DPR-73
(
DOCr.ET NO. 50-320 Replace the following pages of the proposed Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages contain vartical lines indicating the area of change.
The corresponcing overleaf paces are also provided to maintain document cot eteness.
l Faces 3.1-1 3.1-2 3.4 1 3.7-1 3.7-2 3.5 4 E 3/4 4-1 B 3/4 7-1 THREE MILE ISLA'iD - UNIT 2 i
. _ -. ~ _
I LIMITING CONDITIONS FOR OPERATION i
3.1 WATER INJECTION COOLING AND REACTIVITY CONTROL SYSTEMS 3.1.1 BORATION CONTROL BORON INJECTION l
1.1.1.1 At least two systems capable of injecting borated cooling water into the Reactor Coolant System shall be OPERABLE
- with; i
i a.
One system comprised of:
l.
One OPERABLE makeup pump.#
j 2.
One OPERAB.E decay heat removal pump.
3.
An OPERABLE flow path from the BwST.
The BWST shall contain at least 100,000 gallons of borated water at a minimum temperature of 50*F and at a boron concentration of between 3000 and 4500 ppm.
l b.
The second system compaised of the Standby Reactor Coolant System i
Pressure Control System.
1 j
APDLICABILITY:
When fuel is in the reactor pressure vessel.
ACTION:
]
With one of the above required systems incperable, restore the inoperable system to OPERABLE status witnin 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
e I
t BORON CONCENTRATION 3.1.1.2 The reactor coolant shall be maintained at a boron concentration of between 3000 and 4500 ppm and at a temperature above 50 F.
APPLICABILITY: When fuel is in the reactor pressure vessel.
i ACTION None except as provided in Specification 3.0.3.
- Botn systems shall be considered OPERABLE when aligned per procedures approved pursuant to Specification 6.8.2.
- All makeup pumps shall be made inoperable when valve OH-VI or DH-V171 is open F
by' racking out their electrical power supply circuit breakers.
l THREE MILE ISLAND - UNIT 2 3.1-1
l
- ' ele:e:
THREE MILE ISLAND - UNIT 2
- 3.,. 2
LIMITING CONDITIONS FOR OPERATION 3.4 REACTOR COOLANT SYSTEM REACTOR COOLANT LOOPS 3.4.1 The Reactor Coolant Systen shall be operatec in accordance witn procedures approved pursuant to Specification 6.8.2.
APPLICABILITY:
RECOVERY MODE.
ACTION:
None except as provided in Specification 3.0.3.
SAFETY VALVE 5 3.4.3 All pressorizer code safety valves shall be OPERABLE ith a lift settiag of 2435 PSIG ; P..*
APPLICAEILITY:
RECOVERY MCCE.
ACTION:
None except as provided in Specification 3.0.3.
3.4.9 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM
- 3. 4. 9.1 Y e Reactor Coolant System shall be maintained at a T of less than 280 F and at a pressure of less than 600 psig.
avg APPLICABILITY:
When fuel is in the reactor pressure vessel.
ACTION:
None except as proviced in Specification 3.C.3.
'Tne lift setting pressure shall corresponc te ambient concitions of the valve at nominal operating temperature and pressure.
THREE MILE ISLAND - UNIT 2 3.4-1
L:u'. TING CON;ITICNS FOR OPERATION 37 PLANT SYSTEuS
- 3. 7.1 FEECWATER SYSTEM 3.7.1 Tre long term "E" steam ;ane-ator cooling system shall be maintainec in an OPERASLE status.
ADDL:CAE: L 't; RECOVERY MCCE.
ACTICN.
'wtr tre long term ceoling "B" steam generator cooling system inoperacle, estore tre 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 />.
3.7.2 SECONCADv SERVICES CLOSED CO0t.ING WATER SYSTEu
- 3. 7. C.1 At least t.o seconca*y services closed cooling water system pumps anc l
nest e :nangers anc the associatec flow path shall be OPERABLE with ea:n pump ca:at'e of being pc.erec from separate busses.
t AP:~ICAE:.ITY:
RECOVERY MODE.
ACT:CN witn on' One seconcary services closed cooling wate" pump or only one seconca".
services neo; ex:nanger CPERABLE, restore tne inoperacie pump or neat ex:nange-.
to 00ERAE.E status witnin 72 nours.
3.7.3 CLOSE0 cvCLE CCOLING WATER SYSTEM NUCLEa; $ERVICES CLOSE0 CYCLE COOLING SYSTEu 3.7.3.1 At least two independent nuclear services closed cycle cooling water
- um
- s anc neat exchangers and tne associated flow path snall be ODERABLE witn ea:n pum capable of being powerad from separate emergency busses.
A:L:CAE:_: Y:
RECOVERY MODE.
AC':Ck i
only ore nuclear services closee cycle cooling wate" pum: or oni) ce t
a n :les sersites neat excnanger ODERAELE, restore tne in::eratie cump or u
neat entmange-to OPERAS.E status witnin 72 nours.
{
THREE M:LE ISLAND - UNIT 2 3.7-1
l D
.a L!ul'ING CCND:iIONS FCR OPERAi!CN
~ C..
C_E :AY HEAT CLOSED COOLING WATER SYSTEM 3.7.3.2 At least one decay heat closed cooling wate-loop shall be OPERAELE.
A ;mI::E!L:Tv:
RECOVER) MSDE.
.--,c, eV a t no ceca, heat closed cooling water loop OPERABLE, resto-e the incpe acle loco te C:ERAE.E status wintin 24 nours.
CECc WE'T REMOVAL SYSTEM 3.7.3.2 T-3 mini decay neat remaval pumps anc neat excnangers anc the asscci-a:ec c Dai sna be OPERABLE.
A;;.::aE: :'-
When fuel is in the reacter Dressure vesse'
~....
a
'ni th cne mini decay heat removal puTp and/cr neat exc".angee incpe*able, restore the inocerable pum; and/or neat excnange* to OPERAELE status aitnin 72 nours.
aitn t.c mini decay heat removal pumps and/or heat enchaagers ce O,
the associated flow path inoperable, restore at least cre pum; an; neat entmanger anc the associated fic. path to CPERAELE status aitnin 24 hc.'s or witni9 tre next 4E nours maAe a tack.c cccli ng syste-(e't'er cTC "B" or " Loss to Am0iert") OPERAE.E.
3
'.4 N.:.E AR SER'.' ICE R:vER WATER SYSTEM 3 7.4.1 70 independent nuclear service river water locos snail ce OPERAELE.
A??L CAEIL:TY.
RECOVERY MODE.
n.
alt-cae ruclea service river water loop inoperacle, resto e tne 4 9ecerac'e iccc te 0?E;AE.E status.' thin 72 nou s.
THREE MILE ISLAND - UN:T2 3.7-2
TABLE 3.8-2 RESTORATION TIME MATRIX Restore One Restore Otner 1
Component Component (Hours)
(Hours) l aa 24 72 bo $b 2 ?_ 2 h, ab 12 72 e c f
E E.,'
e 3l6 3
bb 12 72 Note:
a anc b above correspond to corrponents described in Specifi:atico 3.8.1.'. items a and D respectively.
i THREE MILE ISLAND - UNIT 2 3.8-3
LIU! TING CONDITIONS FOR OPERATION 3.2.2 CNSITE POWER DISTRIBU ION SYSTEM 5 T
A :.
DISTRIBUTION 3.E.2 1 The folic.ing A.C. electrical busses sna te OPERABLE and energi:ec with t1e creakers open (unless closec in accorcance with procedures approvec pu-swant to Specification 6.E.2) Det.een redundaat busses:
4160 vo't Emergency Bus
- 2-1E and 2-3E 4160 vel Emergency Bus a 2-2E anc 2-4E 416:
volt Busses # 2-3 and 2-4 450 volt Emergency Bus a 2-11E, 2-12E anc 2-31E 45C voit Eme gency Bus a 2-21E, 2-22E anc 2-41E 4EC voit Susses
- 2-31, 2-41, 2-32, 2-42, 2-35, 2-36, 2-45, anc 2-46 l
120 vc!! A.C. Vital Sus a 2-IV 121 volt A.C. Vital Bus # 2 - 2 '.
12:
volt A.C. Vital Bus # 2-3\\
120 vcit A.C.
V4 a! Eus 8 2 - 4 ',
- E, v, s... '
y...
t,
- a. f,, -
Witn less inan the above com;'eme-of A.C. tusses OPERABLE, restore tne incoeratie ous to OPER4E;E status
.'t-i-5 nours.
THREE MILE ISLAND - UNIT 2 3.8-4
3/4.4 REACT 00 COOLANT SYSTEM BASES 3/4.4.1 REACTOR COOLANT LOOPS Several alternative methods are available for removal of reactor c~ecay heat.
These methods include use of the Mini Decay Heat Removal System, the
" Loss to Amoient" cooling mode, and operation of the Reactor Coolant System in the natural circulation mode with heat rejection via the long term "B" steam generator cooling moce.
Any one of these cooling methods provides adequate cooling of the reactor and each method is available for cecay heat removal.
Procedures have been prepared and approved for use of these various cooling methods.
3/4.4.3 SAFETY VALVES The pressurizer Code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2750 psig.
Each safety valve is cesignec to relieve 348,072 lbs per hour of saturated steam at the valve's setpoint.
3/4. 3. 9 PRESSURE / TEMPERATURE LIMIT The RCS pressure and temperature will be controlled in accordance witn approvec procecures to prevent a nonductile failure of the RCS while at the same time permitting the RCS pressure to be maintained at a sufficiently high value to permit operation of the reactor coolant pumps.
THREE MILE ISLAND - UNIT 2 8 3/4 4-1 l
l
3/4.7 PLANT SYSTEMS BASES e
3/4.7.1 FEEDWATER SYSTEM The long term "B" steam generator cooling system is required to be main-tained in an OPERABLE status since it is an alternative method for removir.g ceca > beat from the reactor coolant system.
3/4.7.2 SECONDARY SERVICES CLOSED COOLING WATER SYSTEM The secondary services closed cooling water system is required to be maintained in an CPERABLE condition since it is used to cool the "B" steam generator closed loop cooling system.
3/4.7.3 CLOSED CYCLE COOLING WATER SYSTEM 3'4.7.3.1 NUCLEAR SERVICES CLOSEC CYCLE CDOLING SYSTEM OPERABILITY of tne nuclear services closed cycle cooling system is required during operation of the MDHR$ since this system Drovices the heat sinA for the MDHRS.
3/4.7.3.2 DECAY HEAT CLOSED COOLING WATER SYSTEM Ine ceca) heat closed cooling water system is requirec to ce maintained in an OPERABLE status since it is providec to remove heat frem tne DHR system which is bei.1g maintained OPERABLE in a backup status for pessible core ccoling.
3/4.7.3.3 MINI DECAY HEAT REMOVAL SYSTEM (MDHRS)
OPERABILITY of the MDHRS is required since it is an alternative methoc for removing decay heat from the reactor.
The MDHRS is provicec with two pumps and twn heat exchangers; one pump and one heat exchanger have aceouate capacity for removing the cresent level of decay heat from the core.
3/4.7.4 NUCLEAR SERVICE RIVER WATER SYSTEM The nuclear service river water system uses river wate-to cool the nuclear services closed cycle cooling system, tre seconcary services cicsed cooling water system, and decay heat closec cooling water system; therefore, it must be OPERABLE too.
Tnis system rejects its heat to the river as tne ultimate heat sink.
THREE MILE ISLAND - UNIT 2 B 3/4 7-1
e CONTAINMENT SYSTEMS BASES I
3/4.7.6 FLOOD PROTECTION i
The limitation on flood protection ensures that facility protective e
i actions will be taken in the event of flood conditions.
The limit of elevation 302 Mean Sea Level is based on the maximum elevation at which facility flood control measures provide protection to safety related eovipment.
i 3/4.7.7 CONTROL ROCM EMERGENCY AIR CLEANUP SYSTEM The OPERABILITY of the control room emergency air cleanup system ensures t
that 1) the amDient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and following ill credible accident conditions.
The OPERAEILITY of this system in conjunction with control room design provisions is based on limiting the raciation exposure to personnel occupying the control room to 5 rem or less -nole body, or its equivalent.
This limitation is consistent with the requirements of General Design Criterion 19 of Appendix "A",10 CFR 50.
3/4.7.10 FIRE SUPPRESSION SYSTEMS The OPERABILITY of the fire suppression systems ensures that adequate fire suppressior capability is available to confine and extinguish fires occuring in any portion of the facility where safety related ecuipment is locatec.
The fire suppaession system consists of the water system, spray and.'or sprinAlers, Halon and fire hose stations.
The collective capability cf the fire suppression systems is acecuate to minimize potential damage to safety related equipment and is a major element in the facility fire protec-tion program.
Any two of the four main fire pumps provide com0ined capaci ty greater tnan 3575 gpm.
In the event that portions of the fire suppression systems are inoperable, 3
alternate backup fire fighting equipment is required to be made available in the affected areas until the affected equipment can be restored to service.
In the event that the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides tne major fire suppression capability of the plant.
The requirement for a Special Report to the Commission provides for timely evaluation of the acceptability of the corrective measures to provide adequate fire suppression capacility for the continued operation of the nuclear plant.
I THREE MILE ISLAND - U7IT 2 B 3/4 7-2
Replace the following pages of the Recovery Operations Plan with the enclosed pages as inoicated. The revised pages contain vertical lines indicating.the area of change. Tne corresponding overleaf pages are also providea to maintain do ument completeness.
Pages 4.1-1 4.1-2 4.7-1 4.7-2 l
THREE MILE ISLAND - UNIT 2 i
e SURVEILLANCE REQUIREMENTS i
c 4.1 WATER INJECTION COOLING AND REACTIVITY CONTROL SYSTEMS 4.1.1 BORATION CONTROL BORON INJECTION 4.1.1.1 Two systems capable of injecting borated cooling water into the i
Reactor Coolant System shall be demonstrated OPERABLE:
l
]
a.
Deleted.
l b.
At least once per 31 days by verifying that each accessible (per i
occupational exposure considerations) valve (manual, power operated or automatic) in each flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
At least once per 31 days (when makeup pump is required OPERABLE) by l
c.
verifying (per occupational exposure considerations), that on recircu-lation flow, the makeup pump required by Technical Specification 3.1.1.1 develops a discharge pressure of greater than or equal to 1125 psig and that each pump operates for at least 15 minutes, i
j d.
At least once per 31 days by verifying (per occupational exposure I
considerations), that on recirculation flow, the decay heat removal i
pump required by Technical Specification 3.1.1.1 develops a discharge i
pressure of greater than or equal to 151 psig and that each pumo operates for at least 15 minutes.
l l
e.
Deleted.
)
]
f.
At least once per 7 days when valve OH-V1 or OH-V171 is open by 4
verifying that the makeup pump electrical power supply circuit l
breakers are " racked out."
j g.
At least once per 7 days by:
1.
Deleted.
2.
Verifying the boron concentration in the BWST is between 3000 and 4500 ppm.
3.
Deleted.
i 4.
Verifying the contained borated water volume of the SWST is at least 100,000 gallons.
5.
Deleted.
'THREE MILE ISLAND - UNIT 2 4.1-1 Change No. 4
.~. -. - - -..
. - =. -.
I l.
SURVEILLANCE REOUIREMENTS t
BORON INJECTION (Continued) h.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the BWST temperature is at 4
least 50*F when the outside air temperature is less than 50"F.
i.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (when system is in operation) by j
verifying that the standby reactor coolant system pressure control system:
I 1.
Surge tank water volume is filled to-between 55% and 80% of i
tank capacity and the tank is pressurized to the operating RCS i
pressure 2 25 psig but not higher than 600 psig.
2.
Isolation valves on the discharge side of the water filled tank nearest the reactor coolant system are open.
3.
The in-service nitrogen supply bank is pressuri:ed to between 225 and 400 psig.
j.
At least once per 7 days by verifying that the standby reactor l
coolant system pressure control system water filled tanks, the surge tank, and the degassed water supply tank contain borated water with:
1.
A boron concentration of tetween 3000 and 4500 ppm.
2.
A dissolved gas concentration of less than 15 sec/kg of water.
At least once per 31 days by verifying that the standby reactor
[
x.
coolant system pressure control system isolation valve on tne dis-Charge. side of the water filled tank nearest the reactor Coolant system closes automatically on a tank low level test signal.
4
'THREE MILE ISLAND - UNIT 2 4.1-2 Change No. 4 1
.g r.
r.
o SURVEILLANCE REQUIREMENTS 4.7 PLANT SYSTEu5
(
4.7.1 FEE 0 WATER SYSTEM 4.7.1.1 Deleted.
4.7.1.2 Deleted.
- 4. 7.1. 3 The "B" steam generator closed loop cooling system shall be demons-trated OPERABLE at least once per 31 days by starting (unless already operating) the pump and verifying a flow rate of at least 2000 gam when operating in the recirculation mode.
4.7.2 SECONDARY SERVICES CLOSED COOLING WATER SYSTEM 4.7.2.1 The secondary services closed cooling water system shall be demons-trated OPERABLE at least once per 31 days by verifying inat each of tne three pumps start and operate (unless already operating) for at least 15 minutes.
- 4. 7. 3 CLOSED CYCLE COOLING WATER SYSTEM NUCLEAR SERVICES CLOSED CYCLE COOLING SYSTEM 4.7.3.1 Each nuclear services closed cycle cooling water loop shall be demons-trated OPERABLE:
a.
At least once per 31 days by:
1.
Verifying that each pump starts anc operates (unless alreacj ooerating) for at least 15 minutes and that during pumo operatio:.
the "A" pump develops a dif ferential pressure of at least 62.1 psic, the "B" pump develops a differential pressure of at least 63.1 psid, and the "C" pump develops a differential pressure of at least 64.1 psid.
2.
Verifying that each accessible (per occupational exposure considerations) valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sea ec or otherwise secured in position, is in its correct position.
b.
At least once per 92 days by cycling each testacle valve in tne fica patn through at least o.le complete cycle of full travel.
l THREE MILE ISLAND - UNIT 2 4.7-1 Change No. 4
e' 5URVEILLANCE REOUIREMENTS
~
DECAY HEAT CLG5ED COOLING WATER SYSTEM
(
4.7.3.2 The decay neat closed cooling water loop required b:, Technical Acecification 3.7 3.2 shall ce demonstrated OPERABLE:
a.
At least once per 31 cays by:
l.
Verifying the required Dump starts and operates (unless alreacy operating) for at least 15 minutes and that durirg pump operation:
(a) the "A" pump cevelops a differential pressure of at least 30.6 psid at a flo. of 249; gem and (b) the "B" pump develops a
~
differential pressure of at least 30.6 psic at a flow of 2527 gpm.
2.
Verifying that eacn accessible (per occupational exposure consicerations) valve (manual, power operatec or automatic) l servicing safety related equipment tnat is not locked, sealed or otnerwise securec in position, is in its correct position.
1 b,
At least once per 92 days by cycling each testable valve in the flo.
patn througn at least one complete cycle of full travel.
MINI DECAY HEAT REMOVAL SYSTEM (MDMR5) 4.7.3.3 The MDHR5 shall be demonstratec OPERABLE by performing inservice tests cf eacn MOHR5 pump and each MDnRS valve in tne. flow patn in accoro;nce with Section x! of the ASME Boiler anc Pressure Vessel Code and applica 1e accenca as recui ed cy 10 CFR 50, Section 50.55a(g), except where soecific i
.ritten relief has teen granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(5)(i).
i 4
4 i
1 i
THREE MILE ISLAND
. UNIT 2 4.7-2 Change No. A i
.g
UNITED STATES OF AMERICA NUCLEAR REGULATORY C0f1tilSSION BEFORE THE ATO"IC SAFETY AND LICENSING SOARD In tne Matter of
)
)
METRCPOLITAN EDISON COMPANY, ET AL.
)
Docket No. 50-320 OLA
)
(Three Mile Island Nuclear Station,
)
Urit 2)
)
CERTIFICATE OF SERVICE I hereby certify that copies of, "NRC STAFF NOTICE OF ISSUANCE OF AN AMENDMENT OF ORDER AND MOTION TO CONFORM PROPOSED TECHNICAL SPECIFICATIONS IN ACCORDANCE THEREWITH," dated November 20, 1980, in the above-captioned proceeding, has been served on the following, by deposit in the United States mail, first class, or, as indicated by an asterisk, tnrough deposit in tne Nuclear Regulatory Commission's internal mail system, tnis 20tn day of November, 1980:
Jonn F. Wolf, Esq., Chairman Mr. Steven C. Snolly 3409 Snepnerd Street 304 South Market Street Cnevy Cnase, Maryland 20015 ilechanicsburg, Pennsylvania 17055
- Dr. Oscar H. Paris Mr. William A. Lochstet U.S. Nuclear Regulatory Commission 119 E. Aaron Drive Atonic Safety and Licensing Board Panel State College, Pennsylvania 16801 Washington, D.C.
20555 Dr. Judith H. Johnsrud
- Mr. Frederick J. Shon Environmental Coalition on Nuclear U.S. Nuclear Regulatory Commission Power Atomic Safety and Licensing Board Panel 433 Orlando Avenue Wasnington, D.C.
20555 State College, Pennsylvania 168C1 Karin W. Carter George F. Trowbridge, Esc.
Assistant Attorney General Shaw, Pittman, Potts and Trowbridce 505 Executive House 1800 M Street, N.W.
P.O. Box 2357 Washington, D.C.
20036 Harrisburg, Pennsylvania 17120 Ms. Karen Lee t'. iller Ms. Mary H. Douglas c/o The Top Root Soutique 2721 Mill Roao 414 North Third Street Grantham, Pernsylvania 17027 Harrisburg, Pennsylvania 17101
]
o. " Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Corr.ission Washington, D.C.
20555
- Atomic Safety and Licensing Appeal Panel U.S. Nuclear Regalatory Commission Wasnington, D.C.
20555
- 3ecretary U.S. f,uclear Regulatory Connission ATTN:
Chief, Docketing & Service Br.
Washington, D.C.
20555
(
s Lawrence '. Chandler Counsel for NRC Staff