ML20117H262

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Proposed Tech Specs Sections 3/4.4.9.2,3/4.9.11.1,3/4.9.11.2 & Associated TS Bases 3/4.4.9 & 3/4.9.11 to More Clearly Described RHR Sys Shutdown Cooling Mode Operation
ML20117H262
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 05/20/1996
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20117H247 List:
References
NUDOCS 9605280124
Download: ML20117H262 (22)
v • d • e


Text

{{#Wiki_filter:_ ,_ l l ! ATTACHMENT 2 I LIMERICK GENERATING STATION l UNITS 1 AND 2 i l Docket Nos. 50-352 l 50-353 i License Nos. NPF-39 NPF-85 l TECHNICAL SPEClflCATIONS CHANGE REQUEST l l No. 9612-0 l 1 LIST OF AFFECTED PAGES Unit 1 Unit 2 3/4 4-25 3/4 4-25 I 3/4426 3/4 4-26 l 3/4 9-17 3/4 9-17 3/4 9-18 3/4 9-18 l B 3/4 4-6 B 3/4 4-6

B 3/4 9-2 B 3/4 9-2 l

l t l 9605280124 960520 PDR ADOCK 05000352 P PDR

Unit 2 Mark-Up TS Pages

1 i l L REACTOR COOLANT SLTJfB 3 /4.4. 9 RESIDUAL HEAT REMOVAL HOT SHUTDOWN , LINITING CONDITION FOR OPERATION 

                       ..                 Two* shutdown cooling mode loops of the residual heat remoya.1 -{ftMR)

! system sha BLE and, unless at least one recirculat is in operation, at least on wn cooling mode loo in operation ** *** with each loop consisting of at -

a. One OPE pump, and y INSERT 1 l One OPERABLE RHR heat exchanger.

APPLICABILITY: OPERATIONAL CONDITION 3, with reactor vessel pressure less than the RHR cut-in pemissive setpoint. - -% .~-- -- I inde ACTION: C pendent RHR shutdown cooling subsystems _) _

a. With less than the above required """ ' _

amediately initiate corrective action to return the  ; 7 ---v- - ~y, Wee- to OPERABLE status as soon as possible. Within I hour required l if~ independent 

       ~^        --'v subsystemsj and at least once per 24 hours thereafter, verify the availability of at least one alternate method capable of decay heat removal for each inoperable                                                                        . .s ~Be in at least, COLD f %,           .n           -~.-~ SHUTDOWN'Twithin-24 hours.
                                                                                                                                                                   ~

inde e < independent w e .- ~ ~ b rRHR shutdown With'no'*""' '"" - cooling " '---subsystem _m, in operation, immediatil )g- - " _y 

                                                                                                                                                                        ;m~_d          pe initiate corrective action to return at least                                                          to operation as soon as possible. Within I hour establ                                               reactor coolant circt lation by an alternate method and monitor and pressure at least once per hour.                                                epator_coolanttemperatutt

(')independenisubs[sie7 1 

                                                                                                                                                                                   ~

SURVEILLANCE REOUiREMENTS _ /' ~^' # t i j 4.4.9.1 At least one __1m% ._-__ _ __ t wndependent 

                                                                                              , - -- ,. v - RHR shutdown cooling
                                                                                                                                                                           ,         sub W or alternate method shall be determined to be in operation and circulating
- ,_ _ reactor coolant atjeast oncepr 12 hours.

[ independent RHR shutdown cooling subsystem q 

   '%~-
                          *0ne """ " "--- ---[~~~ '#'- ; may be inoperable for up to 2 hours for l

surveillance testing provided the other asset-is-OPERABLE _and in operation. ' independentsubsystemi 

                         **The shutdown cooling pump may be removed from operation _for_up-to-2_ hours H

Lindependent%per-4-hour RHR shutdown cooling _ period-provided subsystemj g the other taugr is OPERABLE.s.,%,J b independent subsystem C . ~ e ***The may b'e removed-from-operation during hydrostatic testing. 

                      ****Whenever two or more RHR subsystems are inoperable, if unable to attain COLD i                            SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as l                            low as practical by use of alternate heat removal methods.                                                                               -

l 1 1 AUG 0 81995 i LIMERICK - UNIT 2 3/4 4-25 Amendment No. 61 l 1 , 

                                                                                                                                                    -                        . _ ,       i

REACTOR COOLANT SYSTEM 3/4.4.9 RESIDUAL HEAT REMOVAL HOT SHUTDOWN l LIMITING CONDITION FOR OPERATION l ! 3.4.9.1 Two (2) independent RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one (1) RHR shutdown cooling subsystem shall be in operation. * ** *** Each independent RHR shutdown cooling subsystem shall consist of at least:

a. One OPERABLE RHR pump, and
b. One OPERABLE RHR heat exchanger, not common to the two (2) independent subsystems.

APPLICABILITY: OPERATIONAL CONDITION 3, with reactor vessel pressure less than the RHR cut-in permissive setpoint. ACTION:

a. With less than the above required independent RHR shutdown cooling subsystems OPERABLE, immediately initiate corrective action to return the required independent subsystems to OPERABLE status as soon as possible.

Within 1 hour and at least once per 24 hours thereafter, verify the availability of at least one alternate method capable of decay heat removal for each inoperable independent RHR shutdown cooling subsystem. Be in at l least COLD SHUTDOWN within 24 hours.****

b. With no independent RHR shutdown cooling subsystem in operation, l immediately initiate corrective action to return at least one (1) independent subsystem to operation as soon as possible. Within 1 hour l establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature and pressure at least once per hour.

SURVEILLANCE RE0VIREMENTS 4.4.9.1 At least one independent RHR shutdown cooling subsystem or alternate method l shall be determined to be in operation and circulating reactor coolant at least once per 12 hours.

  • One independent RHR shutdown cooling subsystem may be inoperable for up to 2 hours for surveillance testing provided the other independent subsystem is OPERABLE and in operation.
 **      The shutdown cooling pump may be removed from operation for up to 2 hours per 8-hour period provided the other independent subsystem is OPERABLE.            l
 ***    'The independent RHR shutdown cooling subsystem may be removed from operation       l during hydrostatic testing.
 ****    Whenever two or more RHR subsystems are inoperable, if unable to attain COLD l         SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as low as practical by use of alternate heat removal methods.

LIMERICK - UNIT 2 3/4 4-25

1 l REACTOR COOLANT SYSTEM COLD SHUTDOWN . ' LIMITING CONDITION FOR OPERATION i 3.4.9.2 Two* shutdown cooling mode loops of the residual heat removal (RHR) l ystem shall be OPERABLE and, unless at least one recirculation pump is in l ration, at least one shutdown cooling mode loop shall be in operation ** *** wi each loop consisting of at least: One OPERABLE RHR pump, and i

b. One OPERABLE RHR heat exchanger.

APPLICABILITY: OPERATIONAL CONDITION 4. i ACTION:

a. With less han the above required RHR shutdown co ing mode loops OPERABLE, w hin 1 hour and at least once per 2 hours thereafter, verify the av lability of at least one alter te method capable I of decay heat r val for each inoperable shutdown cooling mode loop.
b. With no RHR shutdown oling mode loop n operation, within I hour establish reactor coola . circulatio y an alternate method and monitor reactor coolant eratur and pressure at least once per hour.

HMSEFrr 2 , SURVEILLANCE REOUIREMENTS 4.4.9.2 At least one shutdown c Iingmode p of the residual heat removal system or alternate method shall b determined to in operation and

circulating reactor coolant at 1 st once per 12 ho .
                    *0ne RHR shutdown         oling mode loop may be inoperable for up o 2 hours for sur,veillance tes ng provided the other loop is OPERABLE and i operation.
                **The shutdown ooling pump may be removed from operation for up to                            hours per 8-hour eriod provided the other loop is OPERABLE.
             ***The sh down coeling mode loop may be removed from operation during j                     hydro atic testing.

i AUG 0 81995 LIMERICK - UNIT 2 3/4 4-26 Amendment No. 61

l 

              ' REACTOR COOLANT SYSTEM BASES j                                               .     .
3/4.4.7 MAIN STEAM LINE ISOLATION V'LVES A i

Double isolation valves are provided on each of the main steam lines to minimize the potential leakage paths from the containment in case of a line break. Only one valve in each line is required to maintain the integrity of the i containment, however, single failure considerations require that two valves be OPERABLE. The surveillance requirements are based on the operating history of this type valve. The maximum closure time has been selected to contain fission products and to ensure the core is not uncovered following line breaks. The minimum closure time is consistent with the assumptions in the safety analyses to prevent pressure surges. 3/4.4.8 STRUCTURAL INTEGRITY i The inspection programs for ASME Code Class 1, 2, and 3 components ensure that i the structural integrity of these components will be maintained at an acceptable level throughout the life of the plant. Components of the reactor coolant system were designed to provide access to permit inservice inspections in accordance with Section XI of the ASME Boiler and Pressure Vessel Code 1971 Edition and Addenda through Winter 1972. The inservice inspection program for ASME Code Class 1, 2, and 3 components will be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a(g) except where specific written relief has been granted by the NRC pursuant to 10 CFR 50.55a(g)(6)(i). Additionally, the Inservice Inspection Program conforms to the NRC staff positions identified in NRC Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping," as approved in NRC Safety Evaluations dated March 6, 1990 and October 22, 1990. 3/4.4.9 RESIDUAL HEAT REMOVAL - A single shutdown cooling mode loop provides sufficient heat remo capabi removing core decay heat and mixing to assure ac temperature indication, howe ingle failure considerations at two loops be OPERABLE or that alterna s capable of d eat removal be verified available by either calculation es a review of component and system availability to verify that an ate by demonstration, and t removal method is available) or , alternate method of c ixing be operational. l lNSERT 5 AIXi 0 81995 LIMERICK - UNIT 2 B 3/4 4-6 f.aadr.mnt No. 72, 61

REFUELING OPERATIONS 3/4.'9.11 RESIDUAL HEAT REMOVAL AND'C00LANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.11.1 At least one shutdown cooling mode loop of the residual heat removal RHR) system shall be OPERABLE and in operation

  • with at least:
a. One OPERABLE RHR pump, and
b. One OPERABLE RHR heat exchanger.

APPLICABIL  : OPERATIONAL CONDITION 5, when irradiated fuel is n the reactor vessel and th water level is greater than or equal to 22 feet a ve the top of the reactor essure vessel flange. ACTION:

a. With no RH hutdown cooling mode loop OPE BLE, within I hour and at least once er 24 hours thereafter, y ify the availabilty of at least on 1 ternate method capab of decay heat removal.

Otherwise, suspe all operations i lying an increase in the reactor decay heat ad and establ h SECONDARY CONTAINMENT INTEGRITY within 4 hours.

b. With no RHR shutoawn coo de loop in operation, within I hour establish reactor coolant culation by an alternate method and monitor reactor coolant ture at least once per hour.

INSERT 3 SURVEILLANCE RE0VIREMENTS 4.9.11.1 At least one hutdown cooling mode loop o the residual heat removal system or alternate me od shall be verified to be in o ration and circulating reactor coolant at 1 st once per 12 hours. 

 *The s tdown cooling pump may be removed from operation for up to 2 h            s per     hour period.

A AUG 0 8 Es5 LIMERICK - UNIT 2 3/4 9-17 Amendment No. 61 J

I 

    ' REFUELING OPERATIONS LOW WATER LEVEL         .   .

l LIMITING CONDITION FOR OPERATION i 3.9.11.2 Two shutdown cooling mode loop of the residual heat removal (RHR) system shall be OPERABLE and at least one loop shall be in operation,* with i ach loop consisting of at least: I i l

a. One OPERABLE RHR pump, and
b. One OPERABLE RHR heat exchanger.

APPLICABILI  : OPERATIONAL CONDITION 5, when irradiated fuel i in the reactor vesse and the water level is less than 22 feet above t top of the reactor pressur vessel flange. ACTION:

a. With less t n the above required shutdow cooling mode loops of the RHR system 0 BLE, within I hour and least once per 24 hours thereafter, ver the availability o at least one alternate method capable o ecay heat remova for each inoperable RHR shut-down cooling mode 1 p.
b. With no RHR shutdown co ing e loop in operation, within I hour establish reactor coolant culation by an alternate method and monitor reactor coolant t rature at least once per hour.

l INSERT 4 SURVEILLANCE REOUIREMENTS l 4.9.11.2 At least one utdown cooling mode loop f the residual heat removal system or alternate met d shall be verified to be in eration and circulating reactor coolant at le t once per 12 hours. l 

     *The sh    own cooling pump may be removed from operation for up to 2        rs per 8- our period.

l AUG 0 81995 LIMERICK - UNIT 2 3/4 9-18 Amendment No. 61

t 

         ' REFUELING OPERATIONS BASES 3/4.9.6 REFUELING PLATFORM                            .

The OPERABILITY requirements ensure that 1) the refueling platform will be used for handling control rods and fuel assem(blies within the reactor pressure vessel, (2) each hoist has sufficient load capacity for handling fuel assemblies i and control rods, (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during i lifting operations, and (4

being loaded into a unrodde)d cell. inadvertent criticality will not occur due to fuel 3 /4. 9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL l

The restriction on movement of loads in excess of the nominal weight of a i fuel assembly and associated lifting device over other fuel assemblies in the storage pool ensures that in the event this load is dropped 1) the activity i release will be limited to that contained in a single fuel assembly, and 2) any 3 possible distortion of fuel in the storage racks will not result in a critical i array. This assumption is consistent with the activity release assumed in the j safety analyses. i 3/4.9.8 a1d 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL j STORAGE P00L 1 The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released

from the rupture of an irradiated fuel assembly. This minimum water depth is j consistent with the assumptions of the accident analysis.

I 3/4.9.10 CONTROL R0D REMOVAL I i

These specifications ensure that maintenance or repair of control rods or  ;

control rod drives will be performed under conditions that limit-the prob' ability j of inadvertent criticality. The requirements for simultaneous removal of more

than one control rod are more stringent since the SHUTDOWN MARGIN specification provides for the core to remain subcritical with only one control rod fully withdrawn. -

3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION INSERT 6 The requirements that at least one residual heat removal loo) be OPERABL or t an alternate method capable of decay heat removal be ver find av le by either culation (which includes a review of com>onent and system a ability to verify tha alternate decay heat removal method s available) or demonstration, and that an al ate method of coolant mixing be operational res that 1) sufficient cooling acity is available to remove decay h and maintain the water in the reactor pr re vessel below 140*F and 2) cient coolant circulation would be available through reactor core to assu ecurate temperature indication and to distribute and )revent s tification a poison in the event it becomes necessary to actuate tie standby 1 e ol system. The requirement to have two tdown ing mode loops OPERABLE when there is less than 22 feet of water ve the reactor 1e1 flange ensures that a single failure of the ope, ng loop will not resul<. a complete loss of resid-ual heat removal cap Tity. With the reactor vessel he emoved and 22. feet of water above t eactor vessel flange, a large heat sink vailable for core coolin hus, in the event a failure of the operating RHR , adequate time is vided to initiate alternate methods capable of decay heat val or ency procedures to cool the core. AUG U 5 m3 LIMERICK - UNIT 2 B 3/4 9-2 Ane*=t No. 50, 61

. 1 1 l I 1 Unit 1 Mark-Up TS Pages l l l l i i

RIACTORCOOLANTSYSTEM 3/4.4.9 RESIDUAL HEAT REMOVAL HOT SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4. . Two* shutdown cooling mode loops of the residual heat removal system shall e E and, unless at least one recirculatio s in operation, at least one s cooling mode loop sh 1.1 -infin operation ** *** with each loop consisting of at leas .

a. One OPERABL mp, and l
y. One OPERABLE RHR heat exchanger.

APPLICABILITY: OPERATIONAL CONDITION 3, with reactor vessel pressure less than the RHR cut-in permissive setpoint. ys.-. -, - -me _ dent RHR shutdown cooling subsystems ) 

                         . With less than the above required 3 7                           -

PERA ediately initiate corrective action to return the required to OPERABLE status as soon as possible. Within I hour 

    ~ ~-

and at least once per 24 hours thereafter, verify the availability l f_ independent% subsystems hf at least one-__?' _ each inoperable ""^ d _ i alternate method capable of decay hea 

                                                                           =    1 f---   . B J ,iq,at_le_as LGOLQ _
         - N SHUTDOWN-vithir24sho                                        p dentRHbutdowncoolingsubsystem.

independent RHR shutdown cooling " ' -- subsystem q,urs. s~^ br~1(1 t h 'no'""" M "' TinoperatioliTmmediati1F t initiate corrective action to return at least ong,.4 amp-to operation as soon as possible. Within I hour establi eactor coolant circu-lation by an alternate method and monitor eactorcoolanttegerature and pressure at least once per hour. 

                                                         ^           ^              hl)independentsubsystem]             l SIRVEILLANCEREQUIREMENTS
                                                 . r "i                            ^~#^"                   C i

4.4.9.1 At least one .c %ndependent= , . _ _ RHR shutdown cooling subsystem -. ad - my=*== or alternate method shall be determined to be in operation and circulating-- reactor coolarlt atjeas* 'nce,per g hours. _ ([ independent R shutdown cooling subsyst 

                    *0ne T"" ~'" " - % 4             *$ay'brinbpfrable for up to 2 hours for surveillance testing provided the other                -is OPERABLE-andsin-operation.
                                                                                / independent subsystem 7 g~-'---         **The shutdown cooling pump may be removed from operation-for-up to-2-hours per-8-hour-peried-provided-the other is:0PERABLE.                      s independent subsystem j independent         RHR""" " shutdown
                                 - - - - ' ' -cooling      subsystem G'- may be re,iiloVed-from-ope s ~-~ * *
  • The - - :: _

hydrostatic testing. 

                ****Whenever two or more RHR subsystems are inoperable, if unable to attain COLD SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as low as practical by use of alternate heat removal methods.                              -

AUG 0 8 199% LIMERICK - UNIT 1 3/4 4-25 Amendment No. 97

REACTOR COOLANT SYSTEM 3/4.4.9 RESIDUAL HEAT REMOVAL H0T SHUTDOWN LIMITING CONDITION FOR OPERATION 3.4.9.1 Two (2) independent RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one (1) RHR shutdown cooling subsystem shall be in operation. * ** *** Each independent RHR shutdown cooling subsystem shall consist of at least:

a. One OPERABLE RHR pump, and
b. One OPERABLE RHR heat exchanger, not common to the two (2) independent subsystems. '

APPLICABILITY: OPERATIONAL CONDITION 3, with reactor vessel pressure less than the RHR cut-in permissive setpoint. ACTION:

a. With less than the above required independent RHR shutdown cooling subsystems OPERABLE, immediately initiate corrective action to return the required independent subsystems to OPERABLE status as soon as possible.

Within 1 hour and at least once per 24 hours thereafter, verify the availability of at least one alternate method capable of decay heat removal for each inoperable independent RHR shutdown cooling subsystem. Be in at l least COLD SHUTDOWN within 24 hours.****

b. With no independent RHR shutdown cooling subsystem in operation, l immediately initiate corrective action to return at least one (1) independent subsystem to operation as soon as possible. Within I hour l establish reactor coolant circulation by an alternate method and monitor reactor coolant temperature and pressure at least once per hour.

SVRVEILLANCE RE0VIREMENTS 4.4.9.1 At least one independent RHR shutdown cooling subsystem or alternate method l shall be determined to be in operation and circulating reactor coolant at least once per 12 hours. One independent RHR shutdown cooling subsystem may be inoperable for up to 2 hours for surveillance testing provided the other independent subsystem is OPERABLE and in operation.

    • The shutdown cooling pump may be removed from operation for up to 2 hours per 8-hour period provided the other independent subsystem is OPERABLE. l
      • The independent RHR shutdown cooling subsystem may be removed from operation I during hydrostatic testing.
        • Whenever two or more RHR subsystems are inoperable, if unable to attain COLD SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as low as practical by use of alternate heat removal methods.

LIMERICK - UNIT 1 3/4 4-25 l

REACTOR COOLANT SYSTEM t COLD SHUTDOWN - - i I LIMITING CONDITION FOR OPERATION 3.4.9.2 Two* shutdown cooling mode loops of the residual heat removal (RHR) system shall be OPERABLE and, unless at least one recirculation pump is in operation, at least one shutdown cooling mode loop shall be in operation ** *** l th each loop consisting of at least:

a. One OPERABLE RHR pump, and One OPERABLE RHR heat exchanger.

Nb APPLICABILI Y: OPERATIONAL CONDITION 4. 1 ACTION:

a. With le than the above required RHR shutdown ooling mode loops OPERABLE, within 1 hour and at least once pe 24 hours thereafter, verify the vailability of at least one al rnate method capable of decay hea removal for each inoperabl R shutdown cooling mode loop.
b. With no RHR'shutdo cooling mode 1 .p in operation, within I hour i

' establish reactor co lant circula on by an alternate method and 1 monitor reactor coolan tempera re and pressure at least once per ' hour. INSERT 2 SURVEILLANCE RE0VIREMENTS i 4.4.9.2 At least one shutdow cooling mo\ loop of the residual heat removal system or alternate method sha be determined o be in operation and I circulating reactor coolant least once per 12%ours. 

      *0ne RHR shutdo      cooling mode loop may be inoperable for     to 2 hours for surveillance esting provided the other loop is OPERABLE an in operation.
     **The shut n cooling pump may be removed from operation for up o 2 hours per 8- r period provided the other loop is OPERABLE.
   ***The     hutdown cooling mode loop may be removed from operation during              !

h rostatic testing. l l l ? i AUG 0 81995 ! LIMERICK - UNIT I 3/4 4-26 Amendment .No. 97 . 

 ,                                  -                                                a 7-

i REACTOR C00LAh*T SYSTEM BASES 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES Double isolation valves are provided on each of the main steam lines to j minimize the potential leakage paths from the containment in case of a line break. Only one valve in each line is required to maintain the integrity of the containment, however, single failure consinerations require that two valves be OPERABLE. The surveillance requirements are based on the operating history of

this type valve. The maximum closure time has been selected to contain fission products and to ensure the core is not uncovered following line breaks. The minimum ' closure time is consistent with the assumptions in the safety analyses to
;    prevent pressure surges.

3/4.4.8 STRUCTURAL INTEGRITY The inspection programs for ASME Code Class 1, 2, and 3 components ensure that ' the structural integrity of these components will be maintained at an acceptable level throughout the life of the plant.

Components of the reactor coolant system were designed to provide access to 3 permit inservice inspections in accordance with Section XI of the ASME Boiler and j Pressure Vessel Code 1971 Edition and Addenda through Winter 1972.

1 The inservice inspection program for ASME Code Class 1, 2, and 3 components J will be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a(g) except where specific written relief has been granted by the NRC pursuant to 10 CFR 50.55a(g)(6)(1). Additionally, the Inservice Inspection Program confoms to the NRC staff positions identified in NRC Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping," as approved in NRC Safety Evaluations dated March 6, 1990 and October 22, 1990. 3/4.4.9 RESIDUAL HEAT REMOVAL single shutdown cooling mode loop provides sufficient heat removal capabili removing core decay heat and mixing to assure accurate .rature indication, howev , n le failure considerations require t oops be 1 OPERABLE or that alterna ods capable of decay h val be verified i available by either calculation includ eview of component and system j availability to verify that an altern eat removal method is available) or j by demonstration, and that an ate method a t mixing be operational. l INSERT 5 i j ' 1 3 AUG 0 81995 l LIMERICK - UNIT 1 B 3/4 4-6 Amendment No. 49, 97  ; l

REFUELING OPERATIONS 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL i LIMITING CONDITION FOR OPERATION l 3.9.11.1 At least one shutdown cooling mode loop of the residual heat remova l' RHR) system shall be OPERABLE and in operation

  • with at least:
a. One OPERABLE RHR pump, and l
b. One OPERABLE RHR heat exchanger.

APPLICABIL TY: OPERATIONAL CONDITION 5, when irradiated fuel i vessel and t in the reactor water level is greater than or equal to 22 feet ove the top . of the reactor ressure vessel flange. . ACTION:

a. With no shutdown cooling mode loop OP BLE, within 1 hour and at least one per 24 hours thereafter, v ify the availabilty of at least on alternate method capab of decay heat removal.

Otherwise, suspe all operations in lying an increase in the reactor decay heat oad and establ h SECONDARY CONTAINMENT INTEGRITY within 4 hours.

b. With no RHR shutdown coo ng ode loop in operation, within 1 hour establish reactor coolant rculation by an alternate method and monitor reactor coolant mp ature at least once per hour.

INSERT 3 SURVEILLANCE REOUIREMENTS 4.9.11.1 At least one hutdown cooling mode loop the residual heat removal system or alternate me od shall be verified to be in eration and circulating reactor coolant at 1 st once per 12 hours. 

    *The s tdown cooling pump may be removed from operation for up to 2 h rs per     hour period.

4 AUG 0 81995 LIMERICK - UNIT 1 3/4 9-17 Amendment No. 97 

      .- __     ..      =   -. .       . - -   ..          .. .-        - ._

EffE LING OPERATIONS LOW WATER LEVEL , . LIMITING CONDITION FOR OPERATION 3.9.11.2 Two shutdown cooling mode loop of the residual heat removal (RHR) system shall be OPERABLE and at least one loop shall be in operation,* with ch loop consisting of at least:

a. One OPERABLE RHR pump, and
b. One OPERABLE RHR heat exchanger.

APPLICABILI - OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel nd the water level is less than 22 feet above t top of the reactor pressure essc. flange. ACTION:

a. With less th the above required shutdow ooling mode loops of the RHR system OP BLE, within I hour and least once per 24 hours thereafter, veri the availability of t least one alternate method capable of cay heat removal or eacii inoperable RHR shut-down cooling mode lo .
b. With no RHR shutdown coo ng m e loop in operation, within I hour establish reactor coolant ulation by an alternate method and monitor reactor coolant te ature at least once per hour.

INSERT 4 5URVEILLANCE REOUIREMENTS 4.9.11.2 At least one s tdown cooling mode loop the residual heat removal system or alternate meth shall be verified to be in eration and circulating reactor coolant at lea once per 12 hours.

  • The shu own cooling pump may be removed from operation for up to 2 h rs per 8- ur period.

AUG 0 819H LIMERICK - UNIT 1 3/4 9-18 Amendment No. 97

l REFUELING OPERATIONS f BASES l 3/4.9.6 REFUELING PLATFORM 4 } The OPERABILITY requirements ensure that 1) the refueling platform will ! be used for handling control rods and fuel assem(blies within the reactor pressure  ; ! vessel, (2) each hoist has sufficient load capacity for handling fuel assemblies ' ! and control rods, (3) the core internals and pressure vessel are protected from

excessive lifting force in the event they are inadvertently engaged during

! lifting being loaded operations, into aand (4)d cell. inadvertent criticality will not occur due to fuel unrodde 3 /4. 9. 7 CRANE TRAVEL - SPENT FUEL STORAGE POOL The restriction on movement of loads in excess of the nominal weight of a fuel assembly and associated lifting device ovar other fuel assemblies in the l 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 safety analyses. 3/4.9.3 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL STORAG E POOL i The restrictions on minimum water level ensure that sufficient water depth i is available to remove 99% of the assumed 10% iodine gap activity released ! from the rupture of an irradiated fuel assernbly. This minimum water depth is consistent with the assumptions of the accident analysis. 3/4.9.10 CONTROL R0D REMOVAL These specifications ensure that maintenance or repair of control rods or control rod drives will be performed under conditions that limit the probability of inadvertent criticality. The requirements for simultaneous removal of more than one control rod are more stringent since the SHUTDOWN MARGIN specification provides for the core to remain subcritical with only one control rod fully withdrawn. - 3/4.9.11 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION INSERT 6 The requirements that at least one residual heat removal loo) be OPERABLE i that an alternate method capable of decay heat removal be ver fied ava e by ett alculation (which include:, a review of component and system av ability to verify t an alternate decay heat removal method is available) or demonstration, and that an ate method of coolant mixing be operational ures that 1)  ; sufficient coolin acity is available to remove decay and maintain the  ; water in the reactor p ure vessel below 140*F, and 2 ficient coolant circulation would be available throug reactor core to as accurate temperature indication and to distribute and prevent itification he poison in the event it becomes i necessary to' actuate the standby d rol system. l The requirement to have t utdown ling mode loops OPERABLE when there l is less than 22 feet of wat ove the reactor usel flange ensures that a single failuro of the o ting loop will not resu M1 a complete loss of resid-ual heat removal c ity. With the reactor vessel 1 removed and 22. feet of water above reactor vessel flange, a large heat sin available for core cooli . Thus, in the event a failure of the operating op, adequate l time ovided to initiate alternate methods capable of decay hea moval 1 o rgency procedures to cool the core. 

          -                                                                                                      AUG 0 81995 LIMERICK - UNIT 1                                  B 3/4 9-2                               Amendment No.83, 97

I. b l

INSERT 1 l

] 3.4.9.1 Two (2) independent RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one (1) RHR shutdown cooling subsystem shall be in operation. * ** *** i Each independent RHR shutdown cooling subsystem shall consist of at least: ! a. One OPERABLE RHR pump, and 3 

,        b. One OPERABLE RHR heat exchanger, not co.unon to the two (2) independent j                subsystems.

1 ) INSERT 2 l i 3.4.9.2 Two (2) RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one (1) RHR shutdown cooling i subsystem shall be in operation. * ** *** 1 APPLICABILITY: OPERATIONAL CONDITION 4. 1 ACTION: # l

a. With one (1) or two (2) RHR shutdown cooling subsystems inoperable:

l , i t l 1. Within one (1) hour, and once per 24 hours thereafter, verify an i alternate method of decay heat removal is available for each  ; inoperable RHR shutdown cooling subsystem. ) i ' ! b. With no RHR shutdown cooling subsystems in operation and no recirculation , ! pump in operation: l i  ! ! 1. Within one (1) hour from discovery of no reactor coolant 4 circulation, and once per 12 hours thereafter, verify reactor , i coolant circulating by an alternate method; and i t i 2. Once per hour monitor reactor coolant temperature and pressure. l l SURVEILLANCE REQUIREMENTS l

i. t
4.4.9.2 At least (1) RHR shutdown cooling subsystem or recirculation pump is i

! operating or an alternate method shall be determined to be in operation

and circulating reactor coolant at least once per 12 hours.

t i. O Both RHR shutdown cooling subsystems and recirculation pumps may be removed from  ;

operation for up two (2) hours per eight (8) period.

o* One (1) RHR shutdown cooling subsystem may be inoperable for up to two (2) hours i i for the performance of Surveillances. o** The shutdown cooling subsystem may be removed from operation during hydrostatic j testing. 1 l l # Separate Action entry is allowed for each shutdown cooling subsystem.

INSERT 3 3.9.11.1 One (1) RHR shutdown cooling subsystem shall be OPERABLE and in operation.

  • APPLICABILITY: OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor vessel and the water level is greater than or equal to 22 feet above the top of the reactor pressure vessel flange.

ACTION:

a. With the required RHR shutdown cooling subsystem inoperable:

J 1. Within one (1) hour, and once per 24 hours thereafter, verify an j alternate method of decay heat removal is available.

b. With the required action and associated completion time of Action "a"

, above not met.

1. Immediately suspend loading of irradiated fuel assemblies into the reactor pressure vessel; and
2. Immediately initiate action to restore REFUELING FLOOR SECONDARY CONTAINMENT INTEGRITY to OPERABLE status; and
3. Immediately initiate action to restore one (1) Standby Gas Treatment subsystem to OPERABLE status; and
4. Immediately initiate action to restore isolation capability in each required Refueling Floor secondary containment penetration flow path !

not isolated.

c. With no RHR shutdown cooling subsystem in operation:
1. Within one (1) hour from discovery of no reactor coolant circulation, and once per 12 hours thereafter, verify reactor coolant circulation by an alternate method; and
2. Once per hour monitor reactor coolant temperature.

SURVEILLANCE RE0VIREMENTS 4.9.11.1 At least one (1) RHR shutdown cooling subsystem, or an alternate method, shall be verified to be in operation and circulating reactor coolant at least once per 12 hours.

  • The required RHR shutdown cooling subsystem may be removed from operation for up to two (2) hours per eight (8) hour period.

INSERT 4 ,

3. l 1

j 3.9.11.2 Two (2) RHR shutdown cooling subsystems shall be OPERABLE, and one (1)

RHR shutdown cooling subsystem shall be in operation.
  • i i  !
APPLICABILIT11 OPERATIONAL CONDITION 5, when irradiated fuel is in the reactor  !

] vessel and the water level is less than 22 feet above the top of l the reactor pressure vessel flange.  ; l ACTION:

a. With one (1) or two (2) required RHR shutdown cooling subsystems

! inoperable: l l 1. Witnin one (1) hour, and once per 24 hours thereafter, verify an ]

alternate method of decay heat removal is .available for each

! inoperable required RHR shutdown cooling subsystem. l

b. With the required action and associated completion time of Action "a" 1 above not met: l

! 1. Immediately initiate action to restore REFUELING FLOOR SECONDARY 1 CONTAINMENT INTEGRITY to OPERABLE status; and l l l 2. Immediately initiate action to restore one (1) Standby Gas i Treatment subsystem to OPERABLE status; and i 3. Immediately initiate action to restore isolation capability in each

required Refueling Floor secondary containment penetration flow path not isolated.

j c. With no RHR shutdown cooling subsystem in operation:

1. Within one (1) hour from discovery of no reactor coolant i circulation, and once per 12 hours thereafter, verify reactor
coolant circulation by an alternate method; and i

! 2. Once per hour monitor reactor coolant temperature. i SURVEILLANCE REQUIREMENTS I i 4.9.11.2 At least one (1) RHR shutdown cooling subsystem, or an alternate method, , shall be verified to be in operation and circulating reactor coolant at least once per 12 hours. 1 l S

  • The required operating shutdown cooling subsystem may be removed from operation for up to two (2) hours per eight (8) hour period.

j i

l INSERT 5 i l i The RHR system is required to remove decay heat and sensible heat in order to maintain the temperature of the reactor coolant. RHR shutdown cooling is comprised of i four (4) subsystems which make two (2) loops. Each loop consists of two (2) motor  ! , driven pumps, a heat exchanger, and associated piping and valves. Both loops have a l common suction from the same recirculation loop. Two (2) redundant, manually i controlled shutdown cooling subsystems of the RHR System can provide the required decay heat removal capability. Each pump discharges the reactor coolant, after it has been cooled by circulation through the respective heat exchangers, to the reactor via the ' i associated recirculation loop or to the reactor via the low pressure coolant injection ( pathway. The RHR heat exchangers transfer heat to the RHR Service Water System. The l RHR shutdown cooling mode is manually controlled.  ; An OPERABLE RHR shutdown cooling subsystem consists of an RHR pump, a beat . exchanger, valves, piping, instruments, and controls to ensure an OPERABLE flow path. { In HOT SHUTDOWN condition, the requirement to maintain OPERABLE two (2) independent RHR ! shutdown cooling subsystems means that each subsystem considered OPER4BLE must be associated with a different heat exchanger loop, i.e., the "A" RHR heat e:: changer with

the "A" RHR pump or the "C" RHR pump, ytd the "B" RHR heat exchanger with the "B" RHR

! pump or the "D" RHR pump are two (2) independent RHR shutdown cooling subsystems. Only ! one (1) of the two (2) RHR pumps associated with each RHR heat exchanger loop is i required to be OPERABLE for that independent subsystem to be OPERABLE. During COLD SHUTDOWN and REFUELING conditions, . however, the subystems not only have a common suction source, but are allowed to have a common heat exchanger and common discharge piping. To meet the LC0 of two (2) OPERABLE subsystems, both pumps in one (1) loop or one (1) pump in each of the two (2) loops must be OPERABLE. Since the piping and heat exchangers are passive components, that are assumed not to fail, they are allowed to

be common to both subsystems. Additionally, each RHR shutdown cooling subsystem is

!- considered OPERABLE if it can be manually aligned (remote or local) in the shutdown l cooling mode for removal of decay heat. Operation (either continuous or intermittent) { of one (1) subsystem can maintain and reduce the reactor coolant temperature as j required. However, to ensure adequate core flow to allow for accurate average reactor coolant temperature monitoring, nearly continuous operation is required. I i ! Alternate decay heat removal methods are available to operators. These alternate l j methods of decay heat removal can be verified available either by calculation ( which ! includes a review of component and system availability to verify that an alternate , J decay heat removal method is available) or by demonstration, and that a method of ' } coolant mixing be operational. Decay heat removal capability by ambient losses can be l considered in evaluating alternate decay heat removal capability. 1 i i i i i 1 i i

1 INSERT 6 l Irradiated fuel in the shutdown reactor core generates heat during the decay of

fission products and increases the temperature of the reactor coolant. This decay heat
must be removed by the RHR system to maintain adequate reactor coolant temperature.

J RHR shutdown cooling is -comprised .of four (4) subsystems which make two (2) 3 loops. Each loop consists of two (2) motor driven pumps, a heat exchanger, and i associated piping and valves. Both loops have a common suction from the same

recirculation loop. Two (2) redundant, manually controlled shutdown cooling subsystems

! of the RHR system provide decay heat removal. Each pump discharcas the reactor i coolant, after circulation through the respective heat exchanger, to the reactor via i the associated recirculation loop. The RHR heat exchangers transfer heat to the RHR l Service Water System. An OPERABLE RHR shutdown cooling subsystem consists of one (1) OPERABLE RHR pump, one (1) heat exchanger, and the associated piping and valves. The requirement for having one (1) RHR shutdown cooling subsystem OPERABLE ensures that 1) sufficient i cooling capacity is available to remove decay heat and maintain the water in the i reactor pressure vessel below 140*F, and 2) sufficient coolant circulation would be

available through the reactor core to assure accurate temperature indication and to
distribute and prevent stratification of the poison in the event it becomes necessary
to actuate the standby liquid control system.

l The requirement to have two (2) RHR shutdown cooling subsystems OPERABLE when l there is less than 22 feet of water above the reactor vessel flange ensures that a single failure of the operating loop will not result in a complete loss of residual heat removal capability. With the reactor vessel head removed and 22 feet j of water above the reactor vessel flange, a large heat sink is available for  ; j core cooling. Thus, in the event of a failure of the operating RHR subsystem, adequate ' time is provided to initiate. alternate methods capable of decay heat removal or i j emergency procedures to cool the core. I To meet the LC0 of the two (2) subsystems OPERABLE when there is less than 22

feet of water above the reactor vessel flange, both pumps in one (1) loop or one (1) l pump in each of the two (2) loops must be OPERABLE. The two (2) subsystems have a common suction source and are allowed to have a common heat exchanger and common discharge piping. Additionally, each shutdown cooling subsystem can provide the
required decay heat removal capability; however, ensuring operability of the other
shutdown cooling subsystem provides redundancy.

i The required cooling capacity of an alternate method of decay heat removal should l be ensured by verifying its capability to maintain or reduce reactor coolant temperature either by calculation (which includes a review of component and system i availability to verify that an alternate decay heat removal method is available) or by demonstration. Decay heat removal capability by ambient losses can be considered in evaluating alternate decay heat removal capability. i i 1

INSERT 6 (Continued)  ; a With the required decay heat removal subsystem (s) inoperable and the required alternate method (s) of decay heat removal not available in accordance with Action "a," additional actions are required to minimize any potential fission product release to the environment. This includes ensuring Refueling Floor Secondary Containment is OPERABLE; one (1) Standby Gas Treatment subsystem is OPERABLE; and Secondary Containment isolation capability (i.e., one (1) Secondary Containment isolation valve  ; and associated instrumentation are OPERABLE or other acceptable administrative controls to assure isolation capability) in each associated penetration not isolated that is assumed to be isolated to mitigate radioactive releases. This may be performed as an administrative check, by examining logs or other information to determine whether the components are out of service for maintenance or other reasons. It is not necessary to perform the Surveillances needed to demonstrate the OPERABILITY of the components. If, however, any required component is inoperable, then it must be restored to OPERABLE status. In this case, the surveillance may need to be performed to restore the component to OPERABLE status. Actions must continue until all required components are OPERABLE. If no RHR subsystem is in operation, an alternate method of coolant circulation is required to be established within one (1) hour. The Completion Time is modified such that one (1) hour is applicable separately for each occurrence involving a loss of coolant circulation. l l _}}

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