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l PROPOSED TECHNICAL SPECIFICATION CIIANGES 9107030162 910627 PDR ADOCK 03000313 P
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l PROPOSED TECHNICAL SPECIFICATION CIIANGES l
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l 9107030162 910627                                                                                                                     l PDR       ADOCK 03000313                                                                                                             '
LIMITING CONDITIONS FOR OPERATION 3.0 LlHITING CONDITION FOR OPERATION (GENERAL) 3.0.1 The Limiting Conditions for Operation requirements shall be applicable during the REACTOR OPERATING CONDITIONS or other conditions speciflod for each specification.
P                            PDR
3.0.2 Adherenco to the requirements of the Limiting Condition for Operation within the speciflod time interval shall constituto compliance with the specification.
                                                            , . , . , . . . .- ~ _ _ - ,  -    - . , . . - - , _ _ - _ - - _ _ - . _ . , . _ - - - - _
In the event the Limiting Condition for Operation is restored prior to expiration of the specified time interval, no further actions need be taken.
: 3.     LIMITING CONDITIONS FOR OPERATION 3.0     LlHITING CONDITION FOR OPERATION (GENERAL) 3.0.1 The Limiting Conditions for Operation requirements shall be applicable during the REACTOR OPERATING CONDITIONS or other conditions speciflod for each specification.
3.0.2 Adherenco to the requirements of the Limiting       Condition for Operation within the speciflod time interval shall constituto       compliance with the specification.       In the event the Limiting Condition   for Operation is restored prior to expiration of the specified time interval,       no further actions need be taken.
3.0.3 When a Limiting Condition for Operation is not mot, except as provided in the associated Action requirements, within one hour action shall be initiated to place the unit in an OPERATING CONDITION in which the Specification does not apply by placing it, as applicable, in:
3.0.3 When a Limiting Condition for Operation is not mot, except as provided in the associated Action requirements, within one hour action shall be initiated to place the unit in an OPERATING CONDITION in which the Specification does not apply by placing it, as applicable, in:
: 1.     At least 110T STANDBY within the next 6 hours,
1.
: 2.     At 1 cast il0T SiluTDOWN within the following 6 hours, and
At least 110T STANDBY within the next 6 hours, 2.
: 3.     At least COLD SilUTDOWN within the subsequent 24 hours.
At 1 cast il0T SiluTDOWN within the following 6 hours, and 3.
Whero correctivo measures are completed that permit operation under the Action requirements, the Action may be taken in accordance with the specified time limits as measured from the time of failuro to meet the Limiting Condition for Operation. Exceptions to those requirnments are stated in the individual Specifications.
At least COLD SilUTDOWN within the subsequent 24 hours.
3.0.4 Entry into a REACTOR OPERATING CONDITION or other specified condition shall not be made when the conditions of the Limiting Conditions for Operation are not met and the associated action requires a shutdown if they are not met within a specified time interval.     Entry into a REACTOR OPERATING CONDITION or other specified condition may be modo in accordance with Action requirements when conformance to them permits continued operation of the facility for an unlimited period of timo. This provision shall not prevent passage through or to REACTOR OPERATING CONDITIONS as required to comply with Action requirements. Exceptions to these requirements are stated in the individuni specification.
Whero correctivo measures are completed that permit operation under the Action requirements, the Action may be taken in accordance with the specified time limits as measured from the time of failuro to meet the Limiting Condition for Operation.
Amendment 57                       15a
Exceptions to those requirnments are stated in the individual Specifications.
3.0.4 Entry into a REACTOR OPERATING CONDITION or other specified condition shall not be made when the conditions of the Limiting Conditions for Operation are not met and the associated action requires a shutdown if they are not met within a specified time interval.
Entry into a REACTOR OPERATING CONDITION or other specified condition may be modo in accordance with Action requirements when conformance to them permits continued operation of the facility for an unlimited period of timo. This provision shall not prevent passage through or to REACTOR OPERATING CONDITIONS as required to comply with Action requirements.
Exceptions to these requirements are stated in the individuni specification.
Amendment 57 15a


LIMITING CQ!iDITION FOR_OfEEATION reontinued) 3.0.5 When a system, subsystem, train, component or device is determined to be inoperablo solely because its emergency power source is inoperable, or solely because its normal power source is luoperable, it. may be considored OPERABLE for the purpose of satisfying the requirements of its applicablo Limiting Condition for Operation, provided: (1) its corresponding normal or omorgency power source is OPERABLE and (2) all of its redundant systems (s),
LIMITING CQ!iDITION FOR_OfEEATION reontinued) 3.0.5 When a system, subsystem, train, component or device is determined to be inoperablo solely because its emergency power source is inoperable, or solely because its normal power source is luoperable, it. may be considored OPERABLE for the purpose of satisfying the requirements of its applicablo Limiting Condition for Operation, provided:
subnystem(s), train (s), component (s) and device (s) are OPERABLE; or likewise                                                     i satisfy the requirements of this specification. Unless both conditions (1)                                                         '
(1) its corresponding normal or omorgency power source is OPERABLE and (2) all of its redundant systems (s),
and (2) are satisfied, within 2 hours action shall bo initiated to place the unit in an OPERATING CONDITION in which the applicable Limiting Condition for Operation does not apply by placing it, as applicable, in :
subnystem(s), train (s), component (s) and device (s) are OPERABLE; or likewise i
: 1.       At 1 cast il0T STANDBY within the next 6 hours.
satisfy the requirements of this specification. Unless both conditions (1) and (2) are satisfied, within 2 hours action shall bo initiated to place the unit in an OPERATING CONDITION in which the applicable Limiting Condition for Operation does not apply by placing it, as applicable, in :
: 2.       At least il0T SilUTDOWN within the following 6 hours, and
1.
: 3.       At least C01.D SilVTDOWN within the subsequent 24 hours.
At 1 cast il0T STANDBY within the next 6 hours.
2.
At least il0T SilUTDOWN within the following 6 hours, and 3.
At least C01.D SilVTDOWN within the subsequent 24 hours.
This Specification is not applicabic in Cold Shutdown or Refueling Shutdown.
This Specification is not applicabic in Cold Shutdown or Refueling Shutdown.
BASES 3.0.1 through 3.0.4         Establish the general requirements applicable to Limiting Conditions for Operation. These requirements are based on the requirements for Limiting Conditions for Operation stated in the Code of Federal Regulations, 10 CFR 50.36(c)(2):
BASES 3.0.1 through 3.0.4 Establish the general requirements applicable to Limiting Conditions for Operation. These requirements are based on the requirements for Limiting Conditions for Operation stated in the Code of Federal Regulations, 10 CFR 50.36(c)(2):
                        " Limiting conditions for operation are the lowest functional capability or performance invols of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensoo shall shutdown the reactor or follow any remedial Action permitted by the Technical Specification until the condition can be met."
" Limiting conditions for operation are the lowest functional capability or performance invols of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensoo shall shutdown the reactor or follow any remedial Action permitted by the Technical Specification until the condition can be met."
3.0.1 Establishes the Applicability statement within each individual Specification as the requirement for when (i.e. , in which operational modos or other specified conditions) conformance to the Limiting Conditions for Operation is required for safe operation of the facility.                                           The Action requirements establish those remedial measures that must be taken within specified time If mits when the requirenents of a Limiting Condition for Operation are not mo'..
3.0.1 Establishes the Applicability statement within each individual Specification as the requirement for when (i.e., in which operational modos or other specified conditions) conformance to the Limiting Conditions for Operation is required for safe operation of the facility.
There are two basic types of Action requirements. The first specifies the remedial measures that permit continued operation of the facility which is not further restricted by the time limits of the Action requirements.                                           In this case, conformance to the Action requirements provides an acceptablo level of safety for unlimited continued operation as long as the Action requirements continue to be met. The second type of Action requirement specifies a time limit in which conformance to the conditions of the Limiting Condition'for Operation must be met. This time limit is the allowable outage time to Amendment No. 57,                               15b
The Action requirements establish those remedial measures that must be taken within specified time If mits when the requirenents of a Limiting Condition for Operation are not mo'..
There are two basic types of Action requirements. The first specifies the remedial measures that permit continued operation of the facility which is not further restricted by the time limits of the Action requirements.
In this case, conformance to the Action requirements provides an acceptablo level of safety for unlimited continued operation as long as the Action requirements continue to be met. The second type of Action requirement specifies a time limit in which conformance to the conditions of the Limiting Condition'for Operation must be met.
This time limit is the allowable outage time to Amendment No. 57, 15b


a a BASES (continundl restore nn inoperable system or component to OPERABLE status or for restoring paramotors within specified limits. If these Actions are not completed within the allowabic outago time limits, a shutdown is required to place the facility in a modo or condition in which the Specification no longer applies.       It is not intended that the shutdown Action requirements be used as an operational convenienco which permits (routino) voluntary removal of a system (s) or         ;
a a
component (s) from service in lieu of other alternativos that would not result in redundant systems or components being inoporabin.
BASES (continundl restore nn inoperable system or component to OPERABLE status or for restoring paramotors within specified limits.
The specified time limits of the Action requirements are applicable from the point in time it la identiflod that a Limiting condition for Operation is not met. The Limo limits of the Action requirements are also applicabin when a system or t.omponent is removed from service for surveillanco testing or investigation of operational problems. Individual Specifications may includo a specified time limit for the completion of a Survoillance Requirement when equipment is removed from servico, in this caso, tho allowable outage timo limits of the Action requirements are applicable when this limit expires if the surveillance has not been completed. When a shutdown is required to comply with Action requirements, the plant may have entered a mode in which a new specification becomes applicabin. In this case, the time limits of the Action requirements would apply from the point in time that the now specification becomes applicablo if the requirements of the Limiting Condition for Operation are not met.
If these Actions are not completed within the allowabic outago time limits, a shutdown is required to place the facility in a modo or condition in which the Specification no longer applies.
3.0.2 Establishes that noncompliance with a Specification exists when the requirements of the Limiting Condition for Operation are not mot and the         i associated Action requirements have not been implemented within the specified time Interval. The purposo of this specification is to clarify that (1) implementation of the Action requirements within the specified time interval constitutes compliance with a Specification and (2) completion'of the remedial measures of the Action requirements is not required when compliance with a Limiting Condition for Operation is restored within the-time interval specified in the associated Action requirements.
It is not intended that the shutdown Action requirements be used as an operational convenienco which permits (routino) voluntary removal of a system (s) or component (s) from service in lieu of other alternativos that would not result in redundant systems or components being inoporabin.
3.0.3 Establishes the shutdown Action requirements that must be implemented when a Limiting Condition for Operation is not met and the condition is not specifically addressed by the associated Action requirements. The purpose of this specification is to delineate the time limits for placing the unit in a safe shutdown mode when plant operation cannot be maintained within the limits for safe operation defined by the Limiting Conditions for Operation and its Action requirements. It is not inte.eded to be used as an operational convenience which permits (routine) voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable. Ono hour is allowed to         i prepare for an orderly shutdown before initiating a chango in plant operation.   .I This time permits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of thn electrical grid. The time limits speciflod to reach lower modes of operation permit the shutdown to proceed in a controlled and orderly l
The specified time limits of the Action requirements are applicable from the point in time it la identiflod that a Limiting condition for Operation is not met.
Amendment No. 57,                     15c t
The Limo limits of the Action requirements are also applicabin when a system or t.omponent is removed from service for surveillanco testing or investigation of operational problems.
Individual Specifications may includo a specified time limit for the completion of a Survoillance Requirement when equipment is removed from servico, in this caso, tho allowable outage timo limits of the Action requirements are applicable when this limit expires if the surveillance has not been completed.
When a shutdown is required to comply with Action requirements, the plant may have entered a mode in which a new specification becomes applicabin. In this case, the time limits of the Action requirements would apply from the point in time that the now specification becomes applicablo if the requirements of the Limiting Condition for Operation are not met.
3.0.2 Establishes that noncompliance with a Specification exists when the requirements of the Limiting Condition for Operation are not mot and the i
associated Action requirements have not been implemented within the specified time Interval. The purposo of this specification is to clarify that (1) implementation of the Action requirements within the specified time interval constitutes compliance with a Specification and (2) completion'of the remedial measures of the Action requirements is not required when compliance with a Limiting Condition for Operation is restored within the-time interval specified in the associated Action requirements.
3.0.3 Establishes the shutdown Action requirements that must be implemented when a Limiting Condition for Operation is not met and the condition is not specifically addressed by the associated Action requirements.
The purpose of this specification is to delineate the time limits for placing the unit in a safe shutdown mode when plant operation cannot be maintained within the limits for safe operation defined by the Limiting Conditions for Operation and its Action requirements.
It is not inte.eded to be used as an operational convenience which permits (routine) voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.
Ono hour is allowed to i
prepare for an orderly shutdown before initiating a chango in plant operation.
This time permits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of thn electrical grid. The time limits speciflod to reach lower modes of operation permit the shutdown to proceed in a controlled and orderly l
Amendment No. 57, 15c t


4 l
4 l
BASIS LconLDwed) manner that in well within the specified maximum cooldown rato and within tho                                                               :
BASIS LconLDwed) manner that in well within the specified maximum cooldown rato and within tho cooldown capabilition
cooldown capabilition <>f the facility assuming only the minimum required                                                                   i equipment is Op!'RAltl E. This reduces thermal sticases on components of tho                                                                 ;
<>f the facility assuming only the minimum required i
primary coolant system and the poter.tial for a plant upset that could                                                                       {
equipment is Op!'RAltl E.
challenge safety systems under conditions for which this specification                                                                       t applies.
This reduces thermal sticases on components of tho primary coolant system and the poter.tial for a plant upset that could
q If remedial measures permitting limited continued operation of the facility                                                                 l under the prov!sions of the Action requirements are completed, the shutdown                                                                 l l         may be t erminat ed. The Limo limitt. of the Action requirements are apolicabic                                                             ,
{
)'          from the point in timo thorn was a failuro to meet a Limiting Condition for Operation. Therefore, the shutdown may he terminated if the Action                                                                         ,
challenge safety systems under conditions for which this specification t
requirements have been mot or the timo limits of the Action requirements have 1          not expired, thus providing an allowanen for the completion of the require:1 Actions.
applies.
The timo limit s of Specificat ion 3.0.3 allow 37 hours for the plant to bn in thn C0hD SilUTDOWN condit ton when a shutdown is required during the POWER mode of operatien.     If the plant is in a lower modo of operation when a shutdown is required, the timo limit for reaching the next lower modo of operation                                                                     t applies. However, if a lower modo of operation in reached in less tien than                                                                 ,
q If remedial measures permitting limited continued operation of the facility l
allownd, the total allowable timo to reach COLD 8110TDOWN or other applicabic modo, is not reduced.           For examplo, if Il0T STANI)!!Y la reached in 2 hours, tho                                                 l timo allowo:1 to reach il0T SilVTODWN is the next 11 hours becauso the total timo to reach Il0T S110Tr)0VN is not reduced from tho allowahic limit of 13 hours.
under the prov!sions of the Action requirements are completed, the shutdown l
Thereforo, if remedial measures are completed that would permit a return to
l may be t erminat ed.
* p0WER operation, a penalty is not incurred by having to reach a lower mode of operation h less than the total time allowed.                                                                                               ,
The Limo limitt. of the Action requirements are apolicabic
The sano principle applion with regard to the allowable outogo time limits of the Action requirements, if compliance with the Action requirements for one specification results in entry into a modo or condition of operation for another specification in which the requirements of the Limiting Condition for Operation cro not mot. If tha new specificatico hocomes applicable in loss time than specified, the dif ference may be added to th3 allowable outage timo                                                             '
)
limits of the second specificatian. However, the allowable outage timo limits of Action requirements for 4 higher mode of operation may not be used to extcad the allowablo outage time that is applicable when a himiting Condition for Operation in not met in a lower mode of operation.
from the point in timo thorn was a failuro to meet a Limiting Condition for Operation. Therefore, the shutdown may he terminated if the Action requirements have been mot or the timo limits of the Action requirements have not expired, thus providing an allowanen for the completion of the require:1 1
Actions.
The timo limit s of Specificat ion 3.0.3 allow 37 hours for the plant to bn in thn C0hD SilUTDOWN condit ton when a shutdown is required during the POWER mode of operatien.
If the plant is in a lower modo of operation when a shutdown is required, the timo limit for reaching the next lower modo of operation t
applies.
However, if a lower modo of operation in reached in less tien than allownd, the total allowable timo to reach COLD 8110TDOWN or other applicabic l
modo, is not reduced.
For examplo, if Il0T STANI)!!Y la reached in 2 hours, tho timo allowo:1 to reach il0T SilVTODWN is the next 11 hours becauso the total timo to reach Il0T S110Tr)0VN is not reduced from tho allowahic limit of 13 hours.
Thereforo, if remedial measures are completed that would permit a return to p0WER operation, a penalty is not incurred by having to reach a lower mode of operation h less than the total time allowed.
The sano principle applion with regard to the allowable outogo time limits of the Action requirements, if compliance with the Action requirements for one specification results in entry into a modo or condition of operation for another specification in which the requirements of the Limiting Condition for Operation cro not mot. If tha new specificatico hocomes applicable in loss time than specified, the dif ference may be added to th3 allowable outage timo limits of the second specificatian. However, the allowable outage timo limits of Action requirements for 4 higher mode of operation may not be used to extcad the allowablo outage time that is applicable when a himiting Condition for Operation in not met in a lower mode of operation.
The shutdown requirements of Specification 3.0.3 do not apply in COLD SliUTDOWN and REl'UELING SHUTDOWN, becauno the Action requirements of individual specifications dnfine the remedial measurns to be taken.
The shutdown requirements of Specification 3.0.3 do not apply in COLD SliUTDOWN and REl'UELING SHUTDOWN, becauno the Action requirements of individual specifications dnfine the remedial measurns to be taken.
3.0.4 Establis.hos limitations on modo changes when a Limiting Condition for Operation is not met. It precludes placing the facility in a higher modo of operation when the requirements for a Limiting Condition for Operation are not mot and continued noncomplianco to theno conditions would result in a shutdown to comply with the Action requirements ;f a changn in modon worn permitted.
3.0.4 Establis.hos limitations on modo changes when a Limiting Condition for Operation is not met.
It precludes placing the facility in a higher modo of operation when the requirements for a Limiting Condition for Operation are not mot and continued noncomplianco to theno conditions would result in a shutdown to comply with the Action requirements ;f a changn in modon worn permitted.
The purpoio of this specification is to ensure that facility operation is not.
The purpoio of this specification is to ensure that facility operation is not.
A acndment No.                                   15d i
A acndment No.
                                  - - - , ~   --,--.-nnn-     ,,n-,-..-.n,.-n ~ . - - - . , - - . . , , . . - , - .- r--, _ , ,,,. .e n p m, vn,, n
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e
e RASES (continued) initiated or that. higher modes of operation are not entered when corrective act ion is being taken to obtalu compliance with a Specification by rostoring equipment to OPERABLE status or parameters to specified limits.
* RASES (continued) initiated or that. higher modes of operation are not entered when corrective act ion is being taken to obtalu compliance with a Specification by rostoring equipment to OPERABLE status or parameters to specified limits. Compliance with Action requirements that permit continued operation of the facility for an unilmited period of timo provides an acceptable level of safety for continued operation without rmnrd to the status of the plant before or af ter a modo change. Tho ro foro , in this caso, if the requirements for continued operation have bocn met in accordance with the requirements of the specification, then entry into that modo of operation in permissible. The provisions of this specificat lon should not, however, be interpreted an endorsing the failure to exercise good practico in restoring systems or components to OPERABLE status before plant startup.
Compliance with Action requirements that permit continued operation of the facility for an unilmited period of timo provides an acceptable level of safety for continued operation without rmnrd to the status of the plant before or af ter a modo change.
When a shutdown is required to comply with /ction requirements, the provisions of Specification 3.0 4 do i.ot apply because they would delay placing the f acility in a lower modo of operation.       For the purpose of compliance with this specification the term ' shutdown' is defined as a required reduction in the REACTOR OPERATING CONDITION.
Tho ro foro, in this caso, if the requirements for continued operation have bocn met in accordance with the requirements of the specification, then entry into that modo of operation in permissible.
The provisions of this specificat lon should not, however, be interpreted an endorsing the failure to exercise good practico in restoring systems or components to OPERABLE status before plant startup.
When a shutdown is required to comply with /ction requirements, the provisions of Specification 3.0 4 do i.ot apply because they would delay placing the f acility in a lower modo of operation.
For the purpose of compliance with this specification the term ' shutdown' is defined as a required reduction in the REACTOR OPERATING CONDITION.
3.0.5 Dolineaton what additional conditiona must bo satisfied to permit operation to continue when a normal or emergency power source is not OPERABLE.
3.0.5 Dolineaton what additional conditiona must bo satisfied to permit operation to continue when a normal or emergency power source is not OPERABLE.
It specifically prohibits operation when one division is inoperable because its normal or emergency power source is inoperable and a system, subsystem, train, component or device in another division is inoperable for another reason.
It specifically prohibits operation when one division is inoperable because its normal or emergency power source is inoperable and a system, subsystem, train, component or device in another division is inoperable for another reason.
The provisions of this specification permit the Limiting Condition for Operation statements associated witn individual systems, subsystems, trains, components or devices to be conristent with the Limiting Condition for l     Operation statements of the associated electrical power sourco,           it allows operation to be governed by the time limits of the bimiting Condition for l     Operation for the normal or emergency power sourec, not the individual l     Limiting Condition for Operation statements for each system, subsystem, train, component or device that in determined to be inoperable solely because of tho i     inoperability of its normal or emergency power sourco.
The provisions of this specification permit the Limiting Condition for Operation statements associated witn individual systems, subsystems, trains, components or devices to be conristent with the Limiting Condition for l
For examplo, Specification 3.7.2.C provides for a 2 day out-of-service time when one emergency diesel generator is not OPERABLE.         If the definition of OPERADLE were applied without consideration of Specification 3.0.5. , all systems, subsystems, trains, components and devices supplied by the inoperable emergency power source would also be inoperable. This would dictato invoking the applicablo Action statements for each of the applicablo Limiting Conditions for Operation.           However, the provisions of Specification 3.05 permit the timo limits for continued operation to Amendment No.                           15e
Operation statements of the associated electrical power sourco, it allows operation to be governed by the time limits of the bimiting Condition for l
Operation for the normal or emergency power sourec, not the individual l
Limiting Condition for Operation statements for each system, subsystem, train, component or device that in determined to be inoperable solely because of tho i
inoperability of its normal or emergency power sourco.
For examplo, Specification 3.7.2.C provides for a 2 day out-of-service time when one emergency diesel generator is not OPERABLE.
If the definition of OPERADLE were applied without consideration of Specification 3.0.5., all systems, subsystems, trains, components and devices supplied by the inoperable emergency power source would also be inoperable.
This would dictato invoking the applicablo Action statements for each of the applicablo Limiting Conditions for Operation.
However, the provisions of Specification 3.05 permit the timo limits for continued operation to Amendment No.
15e


  ~ _ _ _ - . - - - - _ . - - _ _ -                          _ - - _ - - - - - - - . - - _ . _ - . __ -                                                    --
~ _ _ _ -. - - - - _. - - _ _ -
e                       e 3.1.2     hniud1AUDat_)ls AinpuAnd_C901d2xn_ Limit & dona EPRCLiLCAUDD 3.1.2.1   Ilydro Test s J
e e
i                                              For thermal stendy state system hydro tests, the system may be prossiirized to the limits set forth in Specification 2.2 when there arn funt assemblics in the coro, under tho provisions of 3.1.2.3, nnd to ASHE Cmlo limits when no fuel nssemblics are present provided thn reactor coolant systen. limits nro to the right of and bolow thn limit linn in Figure 3.1.2- 1. The provisions of Specification 3.0.3 nro not applienble.
3.1.2 hniud1AUDat_)ls AinpuAnd_C901d2xn_ Limit & dona EPRCLiLCAUDD 3.1.2.1 Ilydro Test s J
3.1.2.2   I,enk Tests I,enk tests requir ed by Specificat ion 4.3 shall bn conducted under the provision of 3.1.2.3.                             'the provlsions of Specification 3.0.3 nro not applienbin.
For thermal stendy state system hydro tests, the system may be i
3.1.2.3   The reactor coolant pressuro and the system hentup and cooldown rates (with the except ion of the pressurizer) shall be                                                 ,
prossiirized to the limits set forth in Specification 2.2 when there arn funt assemblics in the coro, under tho provisions of 3.1.2.3, nnd to ASHE Cmlo limits when no fuel nssemblics are present provided thn reactor coolant systen. limits nro to the right of and bolow thn limit linn in Figure 3.1.2-1.
limited in accordance with Figurn 3.1.2-2 nnd Figure 3.1.2-3, and                                               :
The provisions of Specification 3.0.3 nro not applienble.
are as follows:
3.1.2.2 I,enk Tests I,enk tests requir ed by Specificat ion 4.3 shall bn conducted under the provision of 3.1.2.3.
'the provlsions of Specification 3.0.3 nro not applienbin.
3.1.2.3 The reactor coolant pressuro and the system hentup and cooldown rates (with the except ion of the pressurizer) shall be limited in accordance with Figurn 3.1.2-2 nnd Figure 3.1.2-3, and are as follows:
llentup:
llentup:
Allowable combinntions of pressure and temperaturn shall be to the right of and below the limit line in Figuro 3.1.2-2. The hentup rates shall not exceed those shown in Figure 3.1.2-2.
Allowable combinntions of pressure and temperaturn shall be to the right of and below the limit line in Figuro 3.1.2-2.
The hentup rates shall not exceed those shown in Figure 3.1.2-2.
Cooldown:
Cooldown:
Allownble combinations of pressurn and temperature for a specific cooldown shn11 be to the right of and bolow the limit linn in Figurn 3.1.2-3. Cooldown rates shall not excend thoso shown in Figuro 3.1.2-3.
Allownble combinations of pressurn and temperature for a specific cooldown shn11 be to the right of and bolow the limit linn in Figurn 3.1.2-3.
3.1.2.4   Thn secondary side of the stnnm generator shall not be pressurized abovn 200 psig if thn temperature of the steam generntor shell is bolow 100F.
Cooldown rates shall not excend thoso shown in Figuro 3.1.2-3.
3.1.2.5   The pressurizer hentup and cooldown ratos shall r.ot exceed 100F/br. The spray shall not be used if the temperaturn dif ference between the pressurizer and the spray fluid is grentor than 430F.
3.1.2.4 Thn secondary side of the stnnm generator shall not be pressurized abovn 200 psig if thn temperature of the steam generntor shell is bolow 100F.
3.1.2.6   With the limits of Specifications 3.1.2.3 or 3.1.2.4 or 3.1.2.5 exceeded, rostoro the temperaturo and/or pressure to within the limit within 30 minutes; perform an engineering ovaluation to determino the of fects of the out-of-limit condition on the frncturn toughness propertins of the Ronctor Coolant Systchi; determino that the Reactor Coolant System remains neceptable for continued opnrations or be in at lennt.Il0T STANDBY within the next 6 hours and reduce the RCS Tnvg and pressurn to less than 200F and 500 psia, respectively, within the following 30 hours.
3.1.2.5 The pressurizer hentup and cooldown ratos shall r.ot exceed 100F/br. The spray shall not be used if the temperaturn dif ference between the pressurizer and the spray fluid is grentor than 430F.
I Amendment No. 12,1f,, U ,                             18
3.1.2.6 With the limits of Specifications 3.1.2.3 or 3.1.2.4 or 3.1.2.5 exceeded, rostoro the temperaturo and/or pressure to within the limit within 30 minutes; perform an engineering ovaluation to determino the of fects of the out-of-limit condition on the frncturn toughness propertins of the Ronctor Coolant Systchi; determino that the Reactor Coolant System remains neceptable for continued opnrations or be in at lennt.Il0T STANDBY within the next 6 hours and reduce the RCS Tnvg and pressurn to less than 200F and 500 psia, respectively, within the following 30 hours.
I Amendment No. 12,1f,, U,
18


                                                                                  . ~ . _ - _ _                       . _ _      - - - . _ . -
. ~. _ - _ _
e
e 1
* 1 3.1.2.7     Prior to reaching fifteen effective full power years of operation, Tigures 3.1.2-1, 3.1.2-2 and 3.1.2-3 shall be updated for the next service period in accordance with 10CFR50, Appendix G, Sect. lon V. fl.       The service period shall be of sufficient duration to permit thn scheduled evaluation of a portion of the surveillance data scheduled in accordance with Speciffiation 4.2.7. The highest predicted adjusted reference temperaturn of all the boltlino region materials shall be used to determinn the adjusted reference temperaturn at the end of thn service pnriod. The basis for this prediction shnl1 be submitted for NRC staf f review in accordance with Specification 3.1.2.8. The provisions of Specification 3.0.3 arn not applicablo.
3.1.2.7 Prior to reaching fifteen effective full power years of operation, Tigures 3.1.2-1, 3.1.2-2 and 3.1.2-3 shall be updated for the next service period in accordance with 10CFR50, Appendix G, Sect. lon V. fl.
3.1.2.8     The ugxlated proposed technical specifications referred to in 3.1.2.7 shall be submitted for NRC review at least 90 days prior to thn end of the servien period. Approprinto additional NRC review time shall be allowed for proposed t echnical specifications submitted in accordanen with 10 CFR Part 50 Appendix G.
The service period shall be of sufficient duration to permit thn scheduled evaluation of a portion of the surveillance data scheduled in accordance with Speciffiation 4.2.7.
The highest predicted adjusted reference temperaturn of all the boltlino region materials shall be used to determinn the adjusted reference temperaturn at the end of thn service pnriod.
The basis for this prediction shnl1 be submitted for NRC staf f review in accordance with Specification 3.1.2.8.
The provisions of Specification 3.0.3 arn not applicablo.
3.1.2.8 The ugxlated proposed technical specifications referred to in 3.1.2.7 shall be submitted for NRC review at least 90 days prior to thn end of the servien period. Approprinto additional NRC review time shall be allowed for proposed t echnical specifications submitted in accordanen with 10 CFR Part 50 Appendix G.
Section V.C.
Section V.C.
3.1.2.9     With thn exception of ASME Section XI testing and when the coro florxl tank in depressurized, during a plant cooldown the core flood tank discharge valves shall be closed and the circuit breakers for the motor operators opened beforo depressurizing the ret.ctor coolant system below 600 psig.
3.1.2.9 With thn exception of ASME Section XI testing and when the coro florxl tank in depressurized, during a plant cooldown the core flood tank discharge valves shall be closed and the circuit breakers for the motor operators opened beforo depressurizing the ret.ctor coolant system below 600 psig.
3.1.2.10   With the exception of ASME Section XI testing, fill and vent of the reactor coolant system, emergency RCS makeup and to allow maintenance of the valves, when the reactor coolant temperature in less than 280'P, the liigh pressure injection motor operated valves                                       !
3.1.2.10 With the exception of ASME Section XI testing, fill and vent of the reactor coolant system, emergency RCS makeup and to allow maintenance of the valves, when the reactor coolant temperature in less than 280'P, the liigh pressure injection motor operated valves shall be closed with their opening control circuits for the motor operators disabled.
shall be closed with their opening control circuits for the motor operators disabled.                                                                                       ,
3.1.2.11 The plant shall not be oporated in a water solid condition when the RCS pressure boundary in intact except as allowed by Emergency Operating procndures and during System flydrotest.
3.1.2.11   The plant shall not be oporated in a water solid condition when the                                       -
h Amendment No. 5/, f,/. 75, 1/f, 18a ARKANSAS - UNIT 1 IM,
RCS pressure boundary in intact except as allowed by Emergency Operating procndures and during System flydrotest.
h Amendment No. 5/, f,/. 75, 1/f,                     18a                           ARKANSAS - UNIT 1 IM,


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. e 3.5.4     inC91c_InaLInttent atien hvnLichkk1Lt1 Applies to tho operability of the incore instrun,cntation system.
e 3.5.4 inC91c_InaLInttent atien hvnLichkk1Lt1 Applies to tho operability of the incore instrun,cntation system.
Dhlest1Yn To specify the functional and operational requirements of the incore instrumentation nystom.
Dhlest1Yn To specify the functional and operational requirements of the incore instrumentation nystom.
Spasification Abovo 80 percent of operating power dotormined by the reactor coolant pump combination (Tablo 2.3-1) at least 23 individual incoro detectors shall be operable to check gross core power distribution and to assist in the periodic calibration of the out-of-coro detectors in regard to the core inhalance trip limits. The detectors shall be arrnnged as follows and may be a part of both basic arrangements.
Spasification Abovo 80 percent of operating power dotormined by the reactor coolant pump combination (Tablo 2.3-1) at least 23 individual incoro detectors shall be operable to check gross core power distribution and to assist in the periodic calibration of the out-of-coro detectors in regard to the core inhalance trip limits. The detectors shall be arrnnged as follows and may be a part of both basic arrangements.
3.5.4.1   Axial Imbalanco A. Three detectors, one in each of throc strings shall lie in the same axial pleno with one plano in each aalal corn half.
3.5.4.1 Axial Imbalanco A.
B. The axial planes in cach core half shall be symmetrical about the coro mid-plano.
Three detectors, one in each of throc strings shall lie in the same axial pleno with one plano in each aalal corn half.
C. The detector shall not have radial symmetry.
B.
3.5.4.2     Radial Tilt A. Two sota of four detectors shall lie in each corn half. Each set of four shall lie in the same axial plano. The two   nota in the same coro half may lie in the same axial plano.
The axial planes in cach core half shall be symmetrical about the coro mid-plano.
B. Detectors in the same plano shall havo quarter cora radial symmetry.
C.
With the incoro detector system inoperablo, do not uno the system for the above applicable monitoring function. The provisions of Specification 3.0.3 are not applicablo.
The detector shall not have radial symmetry.
DannA A system of 52 incore flux detector assemblics with 7 detectors por assembly has been provided primarily for (uel management-purposes. The system includes data display and record functions and is also used for out-of-core nuclear instrumentation calibration and for coro power distribution verification.
3.5.4.2 Radial Tilt A.
A. The out-of-core nuclear instrumentatica calibration includes:
Two sota of four detectors shall lie in each corn half.
: 1. Calibration of the split detectors at initial reactor startup, during the power escalation program, and periodically thorca f t er.
Each set of four shall lie in the same axial plano.
Amendment No. 51,                       51
The two nota in the same coro half may lie in the same axial plano.
B.
Detectors in the same plano shall havo quarter cora radial symmetry.
With the incoro detector system inoperablo, do not uno the system for the above applicable monitoring function.
The provisions of Specification 3.0.3 are not applicablo.
DannA A system of 52 incore flux detector assemblics with 7 detectors por assembly has been provided primarily for (uel management-purposes.
The system includes data display and record functions and is also used for out-of-core nuclear instrumentation calibration and for coro power distribution verification.
A.
The out-of-core nuclear instrumentatica calibration includes:
1.
Calibration of the split detectors at initial reactor startup, during the power escalation program, and periodically thorca f t er.
Amendment No. 51, 51


  --.              - - - -              - .                . - ~ . - - .                           - - .. - - - . - - -                      -_
. - ~. - -.
1 3.5.5       Elte. DelcAtlan_InsitumentAtion App.11cah11113 This specification applies to fire detection instrumentation                                     111xed within           I firn arens containing safety related equipment or circuitry . er the purposon of protecting that safety related equipment or circuitry.
1 3.5.5 Elte. DelcAtlan_InsitumentAtion App.11cah11113 This specification applies to fire detection instrumentation 111xed within I
firn arens containing safety related equipment or circuitry. er the purposon of protecting that safety related equipment or circuitry.
QMentirn To provido immediato notification of fires in areas t.hnro there exists a potential for a fire to disable safety rnlated systems.
QMentirn To provido immediato notification of fires in areas t.hnro there exists a potential for a fire to disable safety rnlated systems.
Eltecifinallon j                         3.5.5.1     A minimum of 50% of the heat /smoko detectors in the locations
Eltecifinallon j
,                                        specified in Tabic 3.5-5 shall be operable.                                                                .
3.5.5.1 A minimum of 50% of the heat /smoko detectors in the locations specified in Tabic 3.5-5 shall be operable.
3.5.5.2     If less than 50% of the fire detectors in any of the locations designated in Table 3.5-5 are operable, within onn heur esta-blish a fire wat ch patrol to inspect the rrone(s) with the in-                                             ;
3.5.5.2 If less than 50% of the fire detectors in any of the locations designated in Table 3.5-5 are operable, within onn heur esta-blish a fire wat ch patrol to inspect the rrone(s) with the in-operable instrument (s) at. least onen per hour and restore the equipment. to operable status within 14 days, or prepare and submit i
operable instrument (s) at. least onen per hour and restore the equipment. to operable status within 14 days, or prepare and submit i                                       a Special Report to the Commission pursuant to Specification 6.12.5 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring thn instrument (s) to operablo status. Thn provisions of Specification                                     l 3.0.3 are not applicable.
a Special Report to the Commission pursuant to Specification 6.12.5 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring thn instrument (s) to operablo status. Thn provisions of Specification l
IlluLcA Tha various datoctors provide alarms that notify the operators of the existenen of a fire in its early stages thus providing early initiation of firn protection. The detectors in tho main and auxiliary control rooms also provido automatic fire protection initiation.
3.0.3 are not applicable.
IlluLcA Tha various datoctors provide alarms that notify the operators of the existenen of a fire in its early stages thus providing early initiation of firn protection.
The detectors in tho main and auxiliary control rooms also provido automatic fire protection initiation.
The detectors required to be operable in the various areas represent one half of those installed.
The detectors required to be operable in the various areas represent one half of those installed.
Operability of the fire detection instrumentation ensures that operable warning capability is available for the prompt detection of fires. This capability is required in order to detect and locato fires in their early stages,   prompt detection of fires will reduce the potential for damagn to safety related equipment.
Operability of the fire detection instrumentation ensures that operable warning capability is available for the prompt detection of fires.
In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire pattols in the affected                                                 !
This capability is required in order to detect and locato fires in their early
areas (s) is required to provido detection capability until the inoperable                                               '
: stages, prompt detection of fires will reduce the potential for damagn to safety related equipment.
instrumentr.tfon is restored to operability.
In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire pattols in the affected areas (s) is required to provido detection capability until the inoperable instrumentr.tfon is restored to operability.
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4 Amendment No. JP , 43. U , / / fi                                       53d l
4 Amendment No. JP, 43. U, / / fi 53d l
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j       o           o 3.5.6         RadipocL1Yu LigulLEfihtenLinstLunentat.lun britlicahility: During relcanen via this pathway.
j o
OhicsLivni             To provide instrumontation for radioactivo liquid releason.
o 3.5.6 RadipocL1Yu LigulLEfihtenLinstLunentat.lun britlicahility: During relcanen via this pathway.
Sitell1.1.c.aLioni 3.5.6.1               Thn radioactivo 11guld of fluent monitoring inst rumentation shown in Tablo 3.5.6-1 shall be operable with their alarm / trip actrointa set to onnurn that thn limits of specification 3.25.1.1 are not exccoded.
OhicsLivni To provide instrumontation for radioactivo liquid releason.
3.5.6.2               With a ntm/ trip netpoints lens conservative than required by             >
Sitell1.1.c.aLioni 3.5.6.1 Thn radioactivo 11guld of fluent monitoring inst rumentation shown in Tablo 3.5.6-1 shall be operable with their alarm / trip actrointa set to onnurn that thn limits of specification 3.25.1.1 are not exccoded.
thn abovn speciffeatlon, immediately suspend the release of radioact ive liquid of fluents monitored by thn af fected channni, until the netpoint in changed to an acceptably conservat.tvo value.
3.5.6.2 With a ntm/ trip netpoints lens conservative than required by thn abovn speciffeatlon, immediately suspend the release of radioact ive liquid of fluents monitored by thn af fected channni, until the netpoint in changed to an acceptably conservat.tvo value.
3.5.6.3               With less than the minimum number of channels operable, take the action shown in Table 3.5.6-1. Return tho instruments to operablo statun within 30 days or, in lieu of eny othnr report, explain .in thn next Somiannual Radioactivo Effluent Releann Report why the inopernbility was not corrected.
3.5.6.3 With less than the minimum number of channels operable, take the action shown in Table 3.5.6-1.
3.5.6.4               The provinfonn of Specification 3.0.3 are not applicabin.
Return tho instruments to operablo statun within 30 days or, in lieu of eny othnr report, explain.in thn next Somiannual Radioactivo Effluent Releann Report why the inopernbility was not corrected.
l llaarni Thn radioactiv, Ifquid effluent inst rumentation in provided t o n.Onitor and 4
3.5.6.4 The provinfonn of Specification 3.0.3 are not applicabin.
control, an applicab'., the releasen of radioactivo matertain in liquid offluents during actual or potential releancs. Tho alarm / trip notpoints for these instrument s shall be cal:ulated in accordance with the methods in t he ODCH to ensure that thn nlarm/ trip will occur prior to exceeding the limits of 10 CFR Part 20.
l llaarni Thn radioactiv, Ifquid effluent inst rumentation in provided t o n.Onitor and control, an applicab'., the releasen of radioactivo matertain in liquid 4
i Amendment No. ff, JJf,                                             '53f
offluents during actual or potential releancs.
                                .      ,                    _    _                                ~~ ._. _ __._ _
Tho alarm / trip notpoints for these instrument s shall be cal:ulated in accordance with the methods in t he ODCH to ensure that thn nlarm/ trip will occur prior to exceeding the limits of 10 CFR Part 20.
i Amendment No. ff, JJf,
'53f
~~._. _ __._


e                 o 3.5.7                     H ad ina c th c_CdutemuLtillut at_1 nitn acat ALloa Arn11cohilitsi An shown in Tabin 3.5.7-1.
e o
Ohjestlyni                               To provide itoiitromontntion for rndtonctivo gaseous releases.
3.5.7 H ad ina c th c_CdutemuLtillut at_1 nitn acat ALloa Arn11cohilitsi An shown in Tabin 3.5.7-1.
EPcski.LCALloni                                                                                                                                                 >
Ohjestlyni To provide itoiitromontntion for rndtonctivo gaseous releases.
3.5.7.1                                 The rndionctivo gasecun of fluent monit oring inst rumentnt ion shown lei Table 3.5.7-1 shall be operabin with their ntnrm/ trip notpoints set to ensurn that the limits of Specification 3.25.2.I atc not exceeded.
EPcski.LCALloni 3.5.7.1 The rndionctivo gasecun of fluent monit oring inst rumentnt ion shown lei Table 3.5.7-1 shall be operabin with their ntnrm/ trip notpoints set to ensurn that the limits of Specification 3.25.2.I atc not exceeded.
3.5.7.2                                 With a channel nintm/ trip sotpoint lens conservative than I
3.5.7.2 With a channel nintm/ trip sotpoint lens conservative than required, declaro the channel inopoinble.
required, declaro the channel inopoinble.
I 3.5.7.3 With loss than the minimum number of chant als operable, take the action shown in Tablo 3.5.7-1.
3.5.7.3                                 With loss than the minimum number of chant als operable, take the action shown in Tablo 3.5.7-1. Return t he instruments to operablo status within 30 days or, in lieu of any other report, explain in the next Seminnnunt Radioactivo Effluent Ec1caso Report why tho inopornbility was not corrected.
Return t he instruments to operablo status within 30 days or, in lieu of any other report, explain in the next Seminnnunt Radioactivo Effluent Ec1caso Report why tho inopornbility was not corrected.
3.5.7.4                                 The provisions of Specificat ton 3.0.3 nrn not applicable.                                                           l Litcal The radioactive gaseous of fit ent instrumentation in provided to monitor and control, as applicable, the relenses of radioactivo materials in gescous affluents during actual or poto.itial releases. The alarm / trip sotpoints for these instruments shall be calculated in accordance with methods in the ODCH to ensure that the alarm /t rip will occur prior to exceeding the limits of 10 CTR Part 20.105.
3.5.7.4 The provisions of Specificat ton 3.0.3 nrn not applicable.
l Litcal The radioactive gaseous of fit ent instrumentation in provided to monitor and control, as applicable, the relenses of radioactivo materials in gescous affluents during actual or poto.itial releases. The alarm / trip sotpoints for these instruments shall be calculated in accordance with methods in the ODCH to ensure that the alarm /t rip will occur prior to exceeding the limits of 10 CTR Part 20.105.
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l                                         Amendment No. ff>, JJE,                                                                     531 1
l Amendment No. ff>, JJE, 531 1
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  .                    e 3.7.2           A. Thn specifications in 3.7.1 may be modified to allow one of the following conditions to exist af ter the reactor has been heated above 200F, Except as indicated in the following conditions, if any of thesn conditions are not mot, a hot shutdown shall be initiated within 12 houis. If the condition is not clenrod within 24 hours, the reactor shall be brought to cold shutdown within an additional 24 hours.
e 3.7.2 A.
B. In the event that one of the offsite pownr sources specified in 3.7.1. A (1 or 2) is inoperablo, reactor operation may continue for up to 24 hours if the availability of the dicsol generators is immediately verified.
Thn specifications in 3.7.1 may be modified to allow one of the following conditions to exist af ter the reactor has been heated above 200F, Except as indicated in the following conditions, if any of thesn conditions are not mot, a hot shutdown shall be initiated within 12 houis.
C. Either one of the two dicsol generators may be inoperable for up to 7 days in any month provided that durlag such 7 days the operability of t he remaining diesel gennrator is demonstrated immediately and daily thereafter, thorn are no inoperable ESP                                 .
If the condition is not clenrod within 24 hours, the reactor shall be brought to cold shutdown within an additional 24 hours.
c.omponnnts associat ed with the operablo dicsol generator, and                               l provided that the two sources of of f-site power specified in                               )
B.
In the event that one of the offsite pownr sources specified in 3.7.1. A (1 or 2) is inoperablo, reactor operation may continue for up to 24 hours if the availability of the dicsol generators is immediately verified.
C.
Either one of the two dicsol generators may be inoperable for up to 7 days in any month provided that durlag such 7 days the operability of t he remaining diesel gennrator is demonstrated immediately and daily thereafter, thorn are no inoperable ESP c.omponnnts associat ed with the operablo dicsol generator, and provided that the two sources of of f-site power specified in
)
3.7.1.A(1) or 3.7.1.A(2) are available.
3.7.1.A(1) or 3.7.1.A(2) are available.
D. Any 4160V, 480Y, or 120V switchgear, load center, motor cont rol center, or distribution panel in one of the two ESP distribution systems may bo inoporable for up to 8 hours, provided that the operability of the diesel geacrator associated with the operablo ESF distribution system is                                       i demonstrated immediately and all of the components of the operable distt ibution system are operable.                                       If the ESP d btribution system is not returned to service at the end of the 8 hour period, Specification 3.7.2.A shall apply,                                         l E. Two station battery chargers may bo inoperahlo for 8 hours, after which Specification 3.7.2.A shall apply.
D.
F. One of the two station hatteries and the associated distribution system may be inoporabin for 8 hours provided that thorn are no inoperable safety rnlated components associated with the remaining station battery which are redundant to the inoperable stat.Jon battery and the operability of the diesel generator is verified immediately.
Any 4160V, 480Y, or 120V switchgear, load center, motor cont rol center, or distribution panel in one of the two ESP distribution systems may bo inoporable for up to 8 hours, provided that the operability of the diesel geacrator associated with the operablo ESF distribution system is i
demonstrated immediately and all of the components of the operable distt ibution system are operable.
If the ESP d btribution system is not returned to service at the end of the 8 hour period, Specification 3.7.2.A shall apply, l
E.
Two station battery chargers may bo inoperahlo for 8 hours, after which Specification 3.7.2.A shall apply.
F.
One of the two station hatteries and the associated distribution system may be inoporabin for 8 hours provided that thorn are no inoperable safety rnlated components associated with the remaining station battery which are redundant to the inoperable stat.Jon battery and the operability of the diesel generator is verified immediately.
If the battery is not returned to service at the end of the 8 hour period, Specification 3.7.2.A shall apply.
If the battery is not returned to service at the end of the 8 hour period, Specification 3.7.2.A shall apply.
G. Two control power sources from the plant to the switchyard and the attendant distribution system may be inoperable for 8 hours, after which Spncification 3.7.2.A shall apply, 11 . If the requiremnnts of Specification 3.7.1.0 cannot be met, nither:
G.
(1)    lace all Startup Transformer No. 2 feeder bronkers in p' pull-to-lock" within I hour, restore the inoperable interlocks to operablo status within 30 days, or submit within 30 days a Special Report. pursuant to Specification 6.12.5 outlining the cause of the failure, proposed correctivo Action and schedule for impicmentation; or (2) apply thn action requirements of Table 3.5.1-1, Note 14.
Two control power sources from the plant to the switchyard and the attendant distribution system may be inoperable for 8 hours, after which Spncification 3.7.2.A shall apply, 11.
P Amendment No. ff, JJE,                           57
If the requiremnnts of Specification 3.7.1.0 cannot be met, nither:
lace all Startup Transformer No. 2 feeder bronkers in (1) p' pull-to-lock" within I hour, restore the inoperable interlocks to operablo status within 30 days, or submit within 30 days a Special Report. pursuant to Specification 6.12.5 outlining the cause of the failure, proposed correctivo Action and schedule for impicmentation; or (2) apply thn action requirements of Table 3.5.1-1, Note 14.
P Amendment No. ff, JJE, 57


          .      $                                                                                                                                          l 3.8.6           During the handling of irradiated fuel in the reas. tor building, at least one door on t he personnel and emnrgency hntches shall be closed. The equipment hatch cover shall be in place with a minimum of four bolts securing the cover to the sealing sutfaces.
3.8.6 During the handling of irradiated fuel in the reas. tor building, at least one door on t he personnel and emnrgency hntches shall be closed.
3.8.7           Isolation valves in lines containing automatic containment isointion valves shall be operable, or at least one shall be closed.
The equipment hatch cover shall be in place with a minimum of four bolts securing the cover to the sealing sutfaces.
3.8.8           When two irradiated fuel assemblics are being moved simultaneously                                         1 by the bridgns within the fuol transfor canal, a minimum of 10 font separation shn11 he raintained between the assemblics at all times.
3.8.7 Isolation valves in lines containing automatic containment isointion valves shall be operable, or at least one shall be closed.
3.8.9           If any of the abovo speciflod limiting conditions for fuel loading and "nf ueling are not met , r..ovement of funi into thn reactor core shall ceaset Action shall bo initiated to correct the conditions so that the specified limits aro mot, and no operations which may increase thn reactivity of the core shall bo mado. The provisions of Specification 3.0.3 are not. applicabin.                                                             l <
1 3.8.8 When two irradiated fuel assemblics are being moved simultaneously by the bridgns within the fuol transfor canal, a minimum of 10 font separation shn11 he raintained between the assemblics at all times.
3.8.10         Tho reactor building purge isolation system, including the radiation monitors shall bo tested and verified to be operable within 7 days prior to refueling operations. The provisions of Specification 3.0.3 aro not applicablo.                                                                   l 3.8.11         Irradiated fuel shnll not be removed from the reactor until the unit has been subcritical for at least 72 hours. In the event of a completo core offlond, a full core to be discharged shall be subtritical a minimum of 175 hours prior to dischargo of more than 70 assemblics to the spent fuel pool. The provisions of Specification 3.0.3 at o not npplicabic.                                                                 l 3.8.12         All fuel handling in the Auxiliary Building shall coaso upon notification of the issuance of a tornado watch for Pope, Yell,                                           ,
3.8.9 If any of the abovo speciflod limiting conditions for fuel loading and "nf ueling are not met, r..ovement of funi into thn reactor core shall ceaset Action shall bo initiated to correct the conditions so that the specified limits aro mot, and no operations which may increase thn reactivity of the core shall bo mado. The provisions of Specification 3.0.3 are not. applicabin.
Johnson, or Logan countles in Arkansas.                         Fuel handling operations in progress will be completed to the extent necessary to placo the fuel handling bridge and crane in their normal parked and locked                                           '
l 3.8.10 Tho reactor building purge isolation system, including the radiation monitors shall bo tested and verified to be operable within 7 days prior to refueling operations.
position. Thn provisions of Specification 3.0.3 are not                                               l applicabin.
The provisions of Specification 3.0.3 aro not applicablo.
3.8.13         No loaded spent fuel shipping cask shall be carried above or into the Auxiliary Building equipment shaft unless atmosphoric disporsion conditions are equal to or bottor than those produced by Pasquill Type D stability accompanied by a wind velocity of 2 m/sec. In addition, the railroad spur door of the Turbinn Building shall be closed and the fuel handling aron ventilation system shall bo in operation. The provisions of Specification 3.0.3 are not                                         l applicable.
l 3.8.11 Irradiated fuel shnll not be removed from the reactor until the unit has been subcritical for at least 72 hours.
3.8.14         Loads in excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the storage pool. The provisions of Specification 3.0.3 are not.nppl.icabin.                                                               l l
In the event of a completo core offlond, a full core to be discharged shall be subtritical a minimum of 175 hours prior to dischargo of more than 70 assemblics to the spent fuel pool. The provisions of Specification 3.0.3 at o not npplicabic.
l 3.8.12 All fuel handling in the Auxiliary Building shall coaso upon notification of the issuance of a tornado watch for Pope, Yell, Johnson, or Logan countles in Arkansas.
Fuel handling operations in progress will be completed to the extent necessary to placo the fuel handling bridge and crane in their normal parked and locked position.
Thn provisions of Specification 3.0.3 are not l
applicabin.
3.8.13 No loaded spent fuel shipping cask shall be carried above or into the Auxiliary Building equipment shaft unless atmosphoric disporsion conditions are equal to or bottor than those produced by Pasquill Type D stability accompanied by a wind velocity of 2 m/sec.
In addition, the railroad spur door of the Turbinn Building shall be closed and the fuel handling aron ventilation system shall bo in operation. The provisions of Specification 3.0.3 are not l
applicable.
3.8.14 Loads in excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the storage pool. The provisions of Specification 3.0.3 are not.nppl.icabin.
l l
l l
Amendment No. 10,J/,/6,5/,/6,                 59                                                                           i l
l l
i Amendment No. 10,J/,/6,5/,/6, 59


i O           o 3.8.15* The spent fuel shipping cask shall not bn carried by the Auxiliary Building crano pending thn ovaluation of the spent fuel cask drop                                   l accident and the cranc design by AP&h and NRC review and approval.                   The           l provisions of Specification 3.0.3 are not applicabin.                                     l 3.8.16 Storngo in the spent fuel pool shall bn restricted to fuel assembifes                                 ,
i O
having inittal enrichment less thnn or equal to 4.1 w/o 11-235.         The provisions of Specification 3.0.3 nro not applicable.                                     l 3.8.17     Storago in Region 2 (as shown on rigurn 3.8.1) of the spent feel pool shall be further restricted by burnup and enrichment limits specified in Figuro 3.8.2.         In the event a checkerboard storage configuration in deemed necessary for a portion 01 Region 2. vacant spaces adjacent to t he f aces of any fuel assembly which does not meet the Region 2 burnup                         i criteria (non-restricted) shall bn physically blocked before any such fuel assembly may be placed in Region 2. This will prevent inadvertent fuel assembly insertion into two adjacent storage locations. Tbo provisions of Specification 3.0.3 are not applicabin.
o 3.8.15* The spent fuel shipping cask shall not bn carried by the Auxiliary Building crano pending thn ovaluation of the spent fuel cask drop accident and the cranc design by AP&h and NRC review and approval.
3.8.18     The boron concentration in the spent fuel pool shall be maintained (at all times) at greater then 1600 parts por million.
The l
provisions of Specification 3.0.3 are not applicabin.
l 3.8.16 Storngo in the spent fuel pool shall bn restricted to fuel assembifes having inittal enrichment less thnn or equal to 4.1 w/o 11-235.
The provisions of Specification 3.0.3 nro not applicable.
l 3.8.17 Storago in Region 2 (as shown on rigurn 3.8.1) of the spent feel pool shall be further restricted by burnup and enrichment limits specified in Figuro 3.8.2.
In the event a checkerboard storage configuration in deemed necessary for a portion 01 Region 2. vacant spaces adjacent to t he f aces of any fuel assembly which does not meet the Region 2 burnup i
criteria (non-restricted) shall bn physically blocked before any such fuel assembly may be placed in Region 2.
This will prevent inadvertent fuel assembly insertion into two adjacent storage locations. Tbo provisions of Specification 3.0.3 are not applicabin.
3.8.18 The boron concentration in the spent fuel pool shall be maintained (at all times) at greater then 1600 parts por million.
Easta Detailed written procedures will bn available for use by refueling personnel.
Easta Detailed written procedures will bn available for use by refueling personnel.
These procedures, thn above specifications, and thn design of the fuel handling equipment as described in Section 9.6 of the PSAR incorporating built-in interlocks and safety features, providn assurance that no incident could occur during the refueling operations that would result fu a hazard to public health and safety, if no change is being made in coro geometry, one flux monitor is sufficient.       This permits maintenanco on the instrumentation. Continuous monitoring of radiation invols and neutron flux provides immediato indication of an unsafo condition.
These procedures, thn above specifications, and thn design of the fuel handling equipment as described in Section 9.6 of the PSAR incorporating built-in interlocks and safety features, providn assurance that no incident could occur during the refueling operations that would result fu a hazard to public health and safety, if no change is being made in coro geometry, one flux monitor is sufficient.
The requirement that at least one decay heat removal loop bn in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in thn reactor pressure vossol at the refueling temperature (normally 140*F), and (2) sufficient coolant circulation is maintained through the reactor core to mingzo the of fects of a boron dilution incident and prevent boron stratification The requirement to have two decay heat removal loops operable when thoro is less than 23 feet of water above the core, ensures that a single failure of the operating decay heat removal loop will not result in a complete loss of decay heat removal capability. With the reactor vessel head removed and 23 foot of water above the core, a large heat sink is availabin for coro cooling, thus in the event of a failure of the operating decay heat removal loop, adequato timo is provided to initiato emergency procedures to cool the corn.
This permits maintenanco on the instrumentation. Continuous monitoring of radiation invols and neutron flux provides immediato indication of an unsafo condition.
The shutdown margin indicated in Specification 3.8.4 will keep                 coro                             j subcritical, even with all control rods withdrawn from the coro                 Although the refueling boron concentration is sufficient to maintain the c. ore k                 5 0.99 if all the control rods woro removed from the core, only a few controli>ds will be removed at nny one timo during fuel shuffling and Note:     *A one timo exception to 3.8.15 is granted for the period of July 13, 1987 through August 12, 1987.
The requirement that at least one decay heat removal loop bn in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in thn reactor pressure vossol at the refueling temperature (normally 140*F), and (2) sufficient coolant circulation is maintained through the reactor core to mingzo the of fects of a boron dilution incident and prevent boron stratification The requirement to have two decay heat removal loops operable when thoro is less than 23 feet of water above the core, ensures that a single failure of the operating decay heat removal loop will not result in a complete loss of decay heat removal capability.
Amendment No. J/,75,J/,/f>,JP/,                 59a                                                           J j
With the reactor vessel head removed and 23 foot of water above the core, a large heat sink is availabin for coro cooling, thus in the event of a failure of the operating decay heat removal loop, adequato timo is provided to initiato emergency procedures to cool the corn.
The shutdown margin indicated in Specification 3.8.4 will keep coro j
subcritical, even with all control rods withdrawn from the coro Although the refueling boron concentration is sufficient to maintain the c. ore k 5 0.99 if all the control rods woro removed from the core, only a few controli>ds will be removed at nny one timo during fuel shuffling and Note:
*A one timo exception to 3.8.15 is granted for the period of July 13, 1987 through August 12, 1987.
Amendment No. J/,75,J/,/f>,JP/,
59a J
j


e       s 3.12 HISCEl.l.ANEOUS RAD 10 ACTIVE MATF.RI A!.S SOURCES                                                                                                                                         ,
e s
App 11cabtL113 Applien to byproduct, sourco, and special nuclear radioactivo material Rources.
3.12 HISCEl.l.ANEOUS RAD 10 ACTIVE MATF.RI A!.S SOURCES App 11cabtL113 Applien to byproduct, sourco, and special nuclear radioactivo material Rources.
t Qbjesthi To assure that 1cakagn f rom byprcxtuct , source and Ppocini nuclent radionetivo material sources does not exceed allowablo limitn.                                                                                                                                             ,
t Qbjesthi To assure that 1cakagn f rom byprcxtuct, source and Ppocini nuclent radionetivo material sources does not exceed allowablo limitn.
Snecification 3.12.1             The source lenkage test performed pursuant to Specification 4,14 shall be capable of detect ing the pror.ence of 0.005 901 of rndioactiva materint on the tent anmple.                                                     If the test reveals the presenen of 0.005 pCi or mero of removnbic contamination, it shall immediately be withdrawn from uno, decontaminated and repaired, or bo disposed of in accordnnce with Comminnion regulations. Senled sources are nxempt from such leak tents when the sourco contains                                                                                                         i 100 pCi or less of beta and/or ramma emitting materint or 5 pCi or loan of alpha emitting materin1.                                                       The provisions of Speciffention                                                   '
Snecification 3.12.1 The source lenkage test performed pursuant to Specification 4,14 shall be capable of detect ing the pror.ence of 0.005 901 of rndioactiva materint on the tent anmple.
3.0.3 are not applicable.
If the test reveals the presenen of 0.005 pCi or mero of removnbic contamination, it shall immediately be withdrawn from uno, decontaminated and repaired, or bo disposed of in accordnnce with Comminnion regulations.
l 3.12.2               A Specini Report shall be prepared and submitted to the Commission pursuant to Specification 6.12.5 within 90 days if sourco leakago tents reveal the prenonce of ;0.005 microcurlen of removabin                                                                                                             i contaminntlon.
Senled sources are nxempt from such leak tents when the sourco contains i
3.12.3             A complete 2nventory of licensed radioactive materials in possession shall be maintained current at all times.                                                                                                                     !
100 pCi or less of beta and/or ramma emitting materint or 5 pCi or loan of alpha emitting materin1.
I i
The provisions of Speciffention 3.0.3 are not applicable.
l i
l 3.12.2 A Specini Report shall be prepared and submitted to the Commission pursuant to Specification 6.12.5 within 90 days if sourco leakago tents reveal the prenonce of ;0.005 microcurlen of removabin i
l Amendment No. J)l,55,5/,JJE,                                               66b
contaminntlon.
                                                                                                                                                                                                                        ]
3.12.3 A complete 2nventory of licensed radioactive materials in possession shall be maintained current at all times.
i i
l Amendment No. J)l,55,5/,JJE, 66b
]
1
1
  . - - - . .              _ . _ . = . , . , , _          _ . _ . _ . _ . . _ . , _ . _ . , _                      . _ _ . _ , .        . _ . _ _ _ _ . . _ . . _ . _ . . . . . _ . _ _ . _ _ , _ . . _ . _ _ _ ~
_. _. =
.. _. _ _. _ _, _.. _. _ _ _ ~


o           o I
o o
i 3.15           10Eh IIANDI. LNG AREA VENT 1 HAT 10N SYSTEM                                                                                           i bpplicabnity Applies to the operability of thn fuel handling aren ventflation system.                                                                             i
I i
;                                                                                                                                                                                i Oldtclite To ensure that the fuel handling arna ventilation system will perform within acceptable levnis of officiency and reliability.                                                                                                     ;
3.15 10Eh IIANDI. LNG AREA VENT 1 HAT 10N SYSTEM i
bpplicabnity Applies to the operability of thn fuel handling aren ventflation system.
i i
Oldtclite To ensure that the fuel handling arna ventilation system will perform within acceptable levnis of officiency and reliability.
StecLLication i
StecLLication i
3.15.1         The fuel handling area ventilation system shn11 be in operation whenever irrndfated fuel handling operations are in progress in the fuel handling area of the auxiliary building and shall have the following performanco capabilities:
3.15.1 The fuel handling area ventilation system shn11 be in operation whenever irrndfated fuel handling operations are in progress in the fuel handling area of the auxiliary building and shall have the following performanco capabilities:
: a.        The results of the in-place cold DC? and halogenated hydrocarbon                                                           ;
The results of the in-place cold DC? and halogenated hydrocarbon a.
tests at design flows (110%) on llEPA i11 tors and charcon1 adsorber                                                       j bnnks shall show 2 99% DOP removal and b 99% halogenated hydrocarbon removal.                                                                                                       ,
tests at design flows (110%) on llEPA i11 tors and charcon1 adsorber j
: b.       The results of laboratory entbon samplo analysis shall show 2 90%
bnnks shall show 2 99% DOP removal and b 99% halogenated hydrocarbon removal.
b.
The results of laboratory entbon samplo analysis shall show 2 90%
radionctive mothyl fodido removal at a velocity within 120% of system denign, 0.05 to 0.15 mg/m' inlet methyl lodido concentration, 2 70% R.il and 2 125F.
radionctive mothyl fodido removal at a velocity within 120% of system denign, 0.05 to 0.15 mg/m' inlet methyl lodido concentration, 2 70% R.il and 2 125F.
,                                          c.      Fans shall be shown to operate within 110% design flow.                                                                     [
Fans shall be shown to operate within 110% design flow.
: d.       The pressure drop across the combined llEPA filters and charcoal adsorber banks shall be less than 6 inches of water at system design flow rate (110%).
[
: e.       Air distribution shall be uniform within 120% across llEPA filters and charcoal adsorbors when tested initially and after any unintenanen or testing that could affect the air distribution within the funi handling arna ventilation system.
c.
3.15.2           If thn rnquirements of Specification 3.15.1 cannot be met, irradiated                                                               '
d.
fuel movement shall not be started (any irradiated fuel assembly movement in progress may be cornpinted). The provisions of Specification 3.0.3 are not applicabin.                                                                                           l BASIA The fuel handling aren ventilat.fon system is designed to filter the auxiliary building atmosphero during fuel handling operations to limit the relenso of activity should a fuel handling accident occur. The system consists of ono                                                                             )
The pressure drop across the combined llEPA filters and charcoal adsorber banks shall be less than 6 inches of water at system design flow rate (110%).
circuit containing two exhaust fans and a flitor train.                                           The fans are redundant and only ono is required to be operating. The filter train consists of 1 profilter, a llEpA filter and a charcoal adsonber in series.
e.
i                                                                                                                                                                                 !
Air distribution shall be uniform within 120% across llEPA filters and charcoal adsorbors when tested initially and after any unintenanen or testing that could affect the air distribution within the funi handling arna ventilation system.
l                                                                                                                                                                                  I Amendment No. JP,/f,51,                                   66g l
3.15.2 If thn rnquirements of Specification 3.15.1 cannot be met, irradiated fuel movement shall not be started (any irradiated fuel assembly movement in progress may be cornpinted). The provisions of Specification 3.0.3 are not applicabin.
      ,  . - . - . - - -                  . . ,      . -        .  - . - . -                    .. . ~ - - , - - . - . .                     -
l BASIA The fuel handling aren ventilat.fon system is designed to filter the auxiliary building atmosphero during fuel handling operations to limit the relenso of activity should a fuel handling accident occur. The system consists of ono
I
)
circuit containing two exhaust fans and a flitor train.
The fans are redundant and only ono is required to be operating. The filter train consists of 1 profilter, a llEpA filter and a charcoal adsonber in series.
i l
Amendment No. JP,/f,51, 66g
~ - -, - -. -..


          .                        +
+
b 3.18 TIRE SUPPRESSION SI'RINEl,ER SYSTEM i
b 3.18 TIRE SUPPRESSION SI'RINEl,ER SYSTEM i
Arrlhak11h3 i                                               This specification applies to thn following firn suppression sprinkler systems protect ing safety related arcan:
Arrlhak11h3 i
.                                              n.               Each of the four tonctor building cablo penetration arens.
This specification applies to thn following firn suppression sprinkler systems protect ing safety related arcan:
: b.               Each of the four cablo penotration rooms.
n.
: c.               Each of the two escrgency dicsol gennrator rooms,
Each of the four tonctor building cablo penetration arens.
: d.               Cable spreading room.
b.
: c.               Each of thn two diesel generntor fuel vaults.
Each of the four cablo penotration rooms.
4
c.
: f.               lin11way El 372 (Zonn 98-J).
Each of the two escrgency dicsol gennrator rooms, d.
: g.               Condensate demineralir.cr aren.*                                                                                                                 i Oldesihti To assure that (fro suppression is avn11able to safety related equipment.
Cable spreading room.
c.
Each of thn two diesel generntor fuel vaults.
4 f.
lin11way El 372 (Zonn 98-J).
g.
Condensate demineralir.cr aren.*
i Oldesihti To assure that (fro suppression is avn11able to safety related equipment.
located in the above-listed areas.
located in the above-listed areas.
Encs.if.ic.011nti 3.18.1               The above-listed sprinkler systems shall be operable at all times.
Encs.if.ic.011nti 3.18.1 The above-listed sprinkler systems shall be operable at all times.
3.18.2               With one or more of the above-list ed sprinklor systems inopernble, establish a cont inuotas fire watch (or operable smoke and/or heat detection equipment with control room alarm) with backup firo suppression equipmont for thn applicable arca(s) within one hour.
3.18.2 With one or more of the above-list ed sprinklor systems inopernble, establish a cont inuotas fire watch (or operable smoke and/or heat detection equipment with control room alarm) with backup firo suppression equipmont for thn applicable arca(s) within one hour.
Restore the system (s) to operable status within 14 days, or preparo and submit a Special Report to the Commission pursuant. to Specification 6.12.5 within the next 30 days outlining the act.fon taken, the cauno of the inoperability and the plans and schedule for restoring the system (s) to operable status. The provisions of Spect ficst ion 3.0.3 are not appl (cabin.                                                                                               l EaaftE Safety related equipment. located in various areas is protected by sprinkler systems. The operability of thesn systems ensures that adequate fire supprossion capability is available to confino and extinguish a fire occurring in thn applicable areas.                               In the event a system is inoperable, alternato backup firn fighting equipment or operable detection equipment is required to be modo availablo until the inoperable equ;pment is restornd to servico.
Restore the system (s) to operable status within 14 days, or preparo and submit a Special Report to the Commission pursuant. to Specification 6.12.5 within the next 30 days outlining the act.fon taken, the cauno of the inoperability and the plans and schedule for restoring the system (s) to operable status.
j                                               *To be implemented no later than July 30, 1979.
The provisions of Spect ficst ion 3.0.3 are not appl (cabin.
Amendment No. /$,4,J/,JJf,                                                             66n l
l EaaftE Safety related equipment. located in various areas is protected by sprinkler systems. The operability of thesn systems ensures that adequate fire supprossion capability is available to confino and extinguish a fire occurring in thn applicable areas.
1 l~             __ - , _ _ . - _ . . . _ . _ _ _ , _ . . . . _ , .              _ . , _ _ . _ . . . . , - . , _ , , _ _ , . . , . . . .    . - . . . _ . . _ - . . , . _ _ . _ , . _ , _ , , . , . . _ . _ _ , .
In the event a system is inoperable, alternato backup firn fighting equipment or operable detection equipment is required to be modo availablo until the inoperable equ;pment is restornd to servico.
j
*To be implemented no later than July 30, 1979.
Amendment No. /$,4,J/,JJf, 66n l
1 l~


e                     e                                                                                                                                                                             I 3.19 CONTROL ROOM AND AtlX1hiARY CONTROL ROOM llA!,0N SYSTEMS l
e e
Apnlicahillis                                                                                                                                                 l I
3.19 CONTROL ROOM AND AtlX1hiARY CONTROL ROOM llA!,0N SYSTEMS Apnlicahillis Thin specification applies to the llalon systems utilfr.ed as the firo I
.                                                Thin specification applies to the llalon systems utilfr.ed as the firo                                                                                       1 I                                                 suppression system for the cont rol room and auxiliary control room.
suppression system for the cont rol room and auxiliary control room.
Oldesthe To assurn that fire suppression is available to the snfoty related equipment in the control room and auxiliary control room.
Oldesthe To assurn that fire suppression is available to the snfoty related equipment in the control room and auxiliary control room.
Spnc.lL! cat.Lon 3.19.1       The three control room and auxiliary coatrol room llalon systems shall ho operablo at all timon with the storage tanks having at least 957. of full charge weight and 907. of full chargo pressuto.
Spnc.lL! cat.Lon 3.19.1 The three control room and auxiliary coatrol room llalon systems shall ho operablo at all timon with the storage tanks having at least 957. of full charge weight and 907. of full chargo pressuto.
3.19.2       With any of the control room and auxiliary control room llalon systems inopornble, establish backup fire suppression equipment                                                                             !
3.19.2 With any of the control room and auxiliary control room llalon systems inopornble, establish backup fire suppression equipment for the affected area within ono hour.
for the affected area within ono hour. Restore the system (s) to operable status within 14 days, or preparo and submit a Special Report to the Commission pursunnt to Specif f ention 6.12.5 within                                                                           ;
Restore the system (s) to operable status within 14 days, or preparo and submit a Special Report to the Commission pursunnt to Specif f ention 6.12.5 within i
30 days outlining the actions taken, the cause of the                                                                                       i inopernbility, and the plans and schedule for restoring the system                                                                           ,
30 days outlining the actions taken, the cause of the inopernbility, and the plans and schedule for restoring the system to operablo status.
to operablo status.                             The provisions of Specification 3.0.3 are not applicablo.                                                                                                                             l l
The provisions of Specification 3.0.3 are not applicablo.
Baans                                                                                                                                                     ,
l l
Safety related circuitry located in portions of the control room and auxiliary control room is protected by the llalon systems. The operability of those systems ensures that adequnto firo suppression capability is availablo to confine and extinguish n fire occurring in the control room or the auxiliary control room.                                                                                                                                             I In the event that the system (s) is inoperahic, alternate backup fire fighting                                                                             !
Baans Safety related circuitry located in portions of the control room and auxiliary control room is protected by the llalon systems. The operability of those systems ensures that adequnto firo suppression capability is availablo to confine and extinguish n fire occurring in the control room or the auxiliary control room.
equipment is required to be made available in the affected aren until the                                                                                 i inoperable equipment is restored to servico.                                                                                                               !
I In the event that the system (s) is inoperahic, alternate backup fire fighting equipment is required to be made available in the affected aren until the i
inoperable equipment is restored to servico.
i 1
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h i
.r Amendment No. /A, 51, JJ6                                                   66o                                                                             :
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.r Amendment No. /A, 51, JJ6 66o i
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3.20     plRE 11081: STATIONS hvplicahtilts This specification applies to firo hose stations protecting arens containing safety related equipmnnt.
3.20 plRE 11081: STATIONS hvplicahtilts This specification applies to firo hose stations protecting arens containing safety related equipmnnt.
UkkC&LhD
UkkC&LhD To assure that manual itre suppression enpability is available to all safety l
-                            To assure that manual itre suppression enpability is available to all safety l                             related equipment.                                                                                             '
related equipment.
Specificath n                                                                                                 j f                             3.20.1   All fire hoso stations protecting areas containing safety related j                                     equipment shall bo operablo whenover the equipment in these areas in required to be operable.
Specificath n j
1 I
f 3.20.1 All fire hoso stations protecting areas containing safety related j
equipment shall bo operablo whenover the equipment in these areas in required to be operable.
I 1
]
]
3.20.2 k'ith one or more of the fire hoso stations of 3.20.1 inoperable, routo nn additional equivalent capacity fire hose to the unprotected arca(s)
3.20.2 k'ith one or more of the fire hoso stations of 3.20.1 inoperable, routo
{
{
4 irom an operabic hose station within one hour. The provisions of                                       l Speciffention 3.0.3 are not applicable,                                                             g   l 1                                                                                                                                             i
nn additional equivalent capacity fire hose to the unprotected arca(s) irom an operabic hose station within one hour. The provisions of 4
:                            Ratta                                                                                                         ;
Speciffention 3.0.3 are not applicable, g
i j                             The operability of the firo hose stations adds addit ional assurance that j                             adequat e fire supprossion capability is available to confino and extinguish                                   ;
1 i
fires occurring in nny portion of the facility where safety related equipment                                 ;
Ratta i
'                            is located.                                                                                                   !
j The operability of the firo hose stations adds addit ional assurance that j
In the event that portions of this system are inoperable, backup fire hose oquipment is required to be made available in the affected trea(s) until the inoperablo equipment is restored to service.                                                                   l l
adequat e fire supprossion capability is available to confino and extinguish fires occurring in nny portion of the facility where safety related equipment is located.
I i                                                                                                                                           ,
In the event that portions of this system are inoperable, backup fire hose oquipment is required to be made available in the affected trea(s) until the inoperablo equipment is restored to service.
I                                                                                                                                           '
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i                           Amendment No. f$,f/,                       66p i
i Amendment No. f$,f/,
66p i
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l 3.21     FIRE BARRIERS                                                                                                                     i Apn1hnh11Ry i
l 3.21 FIRE BARRIERS i
This specification applies to fire barriors separating safety related firo areas or redundant snfo shutdown systems required in the event of a fire.                                                                 7 DbhtthD To assure that fire bnrriers separating safety related firo areas or redundant safe shutdown systems perform their separation funct.fon.                                                                       !
Apn1hnh11Ry i
Specificatinti 3.21.1       All fire barriors separating safety related firo areas or redundnnt safe shutdown systems shall be operable at all timos.
This specification applies to fire barriors separating safety related firo areas or redundant snfo shutdown systems required in the event of a fire.
3.21.2       With one or more of the required fire barriors inoperable,                                                                   i within 1 hour, either
7 DbhtthD To assure that fire bnrriers separating safety related firo areas or redundant safe shutdown systems perform their separation funct.fon.
: a. Establish a continuous fire watch on at least one sido of                                                             '
Specificatinti 3.21.1 All fire barriors separating safety related firo areas or redundnnt safe shutdown systems shall be operable at all timos.
the a f fect ed firo barrior or,
3.21.2 With one or more of the required fire barriors inoperable, i
: b. Verify the operability of smoke and/or heat detection equipment with control room alarm on at least ot'o sido of the affected barrior and establish an hourly fire watch                                                               '
within 1 hour, either a.
patrol.
Establish a continuous fire watch on at least one sido of the a f fect ed firo barrior or, b.
3.21.3       The provisions of Specification 3.0.3 are not applicable.
Verify the operability of smoke and/or heat detection equipment with control room alarm on at least ot'o sido of the affected barrior and establish an hourly fire watch patrol.
BA1cA The operability of the firo barriors, including firo-rated walls; floors / ceilings; fire doors; firo dampers and ponotration seals, ensures that firon will be confined or adequatoly rotarded from spreading to adjacent. fire areas or to portions of redundant safe shutdown systems required in the event of a fire within the fire area.                                 This design feature minimir.os the possibility of a single fire rapidly involving several areas of the f acility prior to detection and extinguishment. The firo barriors are a passivo olement in the facility fire protection program and are subject to periodic inspections. Safety related fire areas are the Control Room, the Switchgear Roors, the Battery Pooms, and the Diesel Generator Rooms. Fire barriers also separato lubricating oil storago                                                                       i areas from other areas of the plant. Fire barriers separating rodundant safe shutdown systems have bocn defined by analysis.                                                                                       "
3.21.3 The provisions of Specification 3.0.3 are not applicable.
BA1cA The operability of the firo barriors, including firo-rated walls; floors / ceilings; fire doors; firo dampers and ponotration seals, ensures that firon will be confined or adequatoly rotarded from spreading to adjacent. fire areas or to portions of redundant safe shutdown systems required in the event of a fire within the fire area.
This design feature minimir.os the possibility of a single fire rapidly involving several areas of the f acility prior to detection and extinguishment.
The firo barriors are a passivo olement in the facility fire protection program and are subject to periodic inspections. Safety related fire areas are the Control Room, the Switchgear Roors, the Battery Pooms, and the Diesel Generator Rooms.
Fire barriers also separato lubricating oil storago i
areas from other areas of the plant.
Fire barriers separating rodundant safe shutdown systems have bocn defined by analysis.
During periods of time when the barriors are inoperable, a continuous fire watch or operablo detection equipment with an hoJrly fire watch patrol is required to be maintained in the vicinity of the af fected barrior until the barrior is restored to operable status, s
During periods of time when the barriors are inoperable, a continuous fire watch or operablo detection equipment with an hoJrly fire watch patrol is required to be maintained in the vicinity of the af fected barrior until the barrior is restored to operable status, s
Amendment No. Ap,57,Jff,                           669 i
Amendment No. Ap,57,Jff, 669 i
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        - ~ - - - -                                                             - _ . - -                  -.                          _ . - ~ . - . - - -              - . -
- ~ - - - -
e                   e 3.22                         REACTOR llUll. DING PURGE FibTRATION SYSTEM ApplicahillLY This specification applies to the operability of the reactor building l
_. - ~. -. - - -
e e
3.22 REACTOR llUll. DING PURGE FibTRATION SYSTEM ApplicahillLY This specification applies to the operability of the reactor building l
purge filtrntion system.
purge filtrntion system.
OhjeA11Ya To assure that. the reactor building purge filtration system will perform within acceptable levels of efficiency and reliability.
OhjeA11Ya To assure that. the reactor building purge filtration system will perform within acceptable levels of efficiency and reliability.
Sps%LLLLSLL011 3.22.1                       The reactor building purge filtration system shall be operable whenever irradiated fuel handling operations are in progress in the reactor building and shall have the following performance capnbi1itles:
Sps%LLLLSLL011 3.22.1 The reactor building purge filtration system shall be operable whenever irradiated fuel handling operations are in progress in the reactor building and shall have the following performance capnbi1itles:
: a. The results of t he in-place cold DOP and halogenated hydrocarbon tests at design flows (110%) on llEPA filters and charcon) adsorber bnnks shall show 299% DOP removal and 299%                                     i hologenated hydrocarbon removal,
a.
: b. The resulte of laboratory carbon sample analysis shall show 290% radioactive methyl iodido removal at a velocity within 120% of system design, 0.05 to 0.15 mg/m' inlet methyl lodido concentrat f on, 2707 R. II, and 2125F.
The results of t he in-place cold DOP and halogenated hydrocarbon tests at design flows (110%) on llEPA filters and charcon) adsorber bnnks shall show 299% DOP removal and 299%
: c. Fans shall be shown to operate wit.hin 110% design flow,
i hologenated hydrocarbon removal, b.
: d. The pressure drop across the combined ilEPA filters and charcoal adsorber banks shall be less the.n 6 inches of water at system design flow rate (110%).
The resulte of laboratory carbon sample analysis shall show 290% radioactive methyl iodido removal at a velocity within 120% of system design, 0.05 to 0.15 mg/m' inlet methyl lodido concentrat f on, 2707 R. II, and 2125F.
: c. Air distribution shall be uniform within 120% across llEPA filters and charcoal adsorbers when tested initially and after any maintennnce or testing that could affect the air distribution within the reactor building purgo filtration system.
c.
3.22.2                       If the requirements of Specification 3.22.1 cannot be met, either:
Fans shall be shown to operate wit.hin 110% design flow, d.
: a. Irradiated fuel movement shall not be started (any irradiated fuel assembly movement in progress may be completed); or,
The pressure drop across the combined ilEPA filters and charcoal adsorber banks shall be less the.n 6 inches of water at system design flow rate (110%).
: b. Isolate the reactor building purge system.
c.
Air distribution shall be uniform within 120% across llEPA filters and charcoal adsorbers when tested initially and after any maintennnce or testing that could affect the air distribution within the reactor building purgo filtration system.
3.22.2 If the requirements of Specification 3.22.1 cannot be met, either:
a.
Irradiated fuel movement shall not be started (any irradiated fuel assembly movement in progress may be completed); or, b.
Isolate the reactor building purge system.
3.22.3 The provisions of Specification 3.0.3 are not applicable.
3.22.3 The provisions of Specification 3.0.3 are not applicable.
l Bains The reactor building purge filtration system is designed to filter the reactor building atmosphere during normal operations for case of personnel entry into the reactor building.                           This specification is intended to require the system operabic during fuel hnndling operations, if the system Amendment. No. H ,U ,                                         66r
l Bains The reactor building purge filtration system is designed to filter the reactor building atmosphere during normal operations for case of personnel entry into the reactor building.
This specification is intended to require the system operabic during fuel hnndling operations, if the system Amendment. No. H,U,
66r


e                 a 3.24 EXphOSlVE GAS MIXTURE Alm 11sah11113 Applies to the Wasto Gas System hydrogen / oxygen analyr.ers.
e a
3.24 EXphOSlVE GAS MIXTURE Alm 11sah11113 Applies to the Wasto Gas System hydrogen / oxygen analyr.ers.
Oldenthe To prevent accumulation of cyplosivo mixture in the wastn gas system.
Oldenthe To prevent accumulation of cyplosivo mixture in the wastn gas system.
Spn Li h ALLou 3.24.1     The concentration of hydrogen / oxygen shall be limited in the waste gas decay tanks to Region "A" of Figurn 3.24-1.
Spn Li h ALLou 3.24.1 The concentration of hydrogen / oxygen shall be limited in the waste gas decay tanks to Region "A" of Figurn 3.24-1.
3.24.2     When the hydrogen /exygnn concentration in any of the decay tenks enters Region "it" of Figure 3.24-1, correctivn action shall be taken to return the concentration values to Region     "A" within 24 hours, 3.24.3     Thn provisions of Specification 3.0.3 arn not applicabin.
3.24.2 When the hydrogen /exygnn concentration in any of the decay tenks enters Region "it" of Figure 3.24-1, correctivn action shall be taken to return the concentration values to Region "A" within 24
l Daics Those hydrogen / oxygen limit s provide reasonable assurance that r,o hydrogen / oxygen explosion conld occur to allow rupture of the waste gas decay tanks. The hydrogen and oxygen limits are based on information .in NUREG/CR-2726 " Light Water Reactor ilydrogen Manual".
: hours, 3.24.3 Thn provisions of Specification 3.0.3 arn not applicabin.
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l Daics Those hydrogen / oxygen limit s provide reasonable assurance that r,o hydrogen / oxygen explosion conld occur to allow rupture of the waste gas decay tanks.
Amendment No. ff,7),                                       66u
The hydrogen and oxygen limits are based on information.in NUREG/CR-2726 " Light Water Reactor ilydrogen Manual".
i Amendment No. ff,7),
66u


I e                   e 3.25                       RADIDACTIVE EFFl.UENTS 3.25.1                     Eftdinactive Liquidlf1LuenLa 3.25.1.1                   Concentratinn Applisab111111 At a11 tiaes Oldect.ly.ti                     To ensure that the limits of 10 CFR 20 arn mot.
I e
Synrd Lit.!tLka w 3 25.1.1                   A. The concentration of radioactivo material rnleased to                                                                           ,
e 3.25 RADIDACTIVE EFFl.UENTS 3.25.1 Eftdinactive Liquidlf1LuenLa 3.25.1.1 Concentratinn Applisab111111 At a11 tiaes Oldect.ly.ti To ensure that the limits of 10 CFR 20 arn mot.
the dischargo canal shall be limited to the concentration specifind in 10 CFR Part 20 Appendix D, Tablo II, Column 2 for rndionuclides othnr than dissolved or oatrained noble gases. For dissolved or entrainnd noble gases, the total concentration released shall be limited to 2 x 10J pCf/ml.
Synrd Lit.!tLka w 3 25.1.1 A.
B. Yith the conenntrction of radioactivo material relonsod                                                                         '
The concentration of radioactivo material rnleased to the dischargo canal shall be limited to the concentration specifind in 10 CFR Part 20 Appendix D, Tablo II, Column 2 for rndionuclides othnr than dissolved or oatrained noble gases.
exceeding the abovo limits, immediately initiato action to rostoro concentration to within limits and provido notification to the Commission within 24 hours.                                                           In lieu on any other report, preparc and submit a Special Report                                                                           '
For dissolved or entrainnd noble gases, the total concentration released shall be limited to 2 x 10J pCf/ml.
within 30 days pursuant to Specificat.lon 6.12.5 C. The provisions of Specification 3.0.3 are not applicable.
B.
Balcal This specification is provided to ensure that the concentration of radioactivo materials roloased in liquid wasto offluents from the sito to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B. Tablo II.                                       This limitation provi'os additional assurance that the levnis of radioactivo materials in bodies of water outside the rite will not result in exposures greater than the Sects- ,I A design ohjeictives of Appendix 1,10 CFR Part 50, to a member of the
Yith the conenntrction of radioactivo material relonsod exceeding the abovo limits, immediately initiato action to rostoro concentration to within limits and provido notification to the Commission within 24 hours.
,                                      public. The concentration limit for noble gases is based upon the I
In lieu on any other report, preparc and submit a Special Report within 30 days pursuant to Specificat.lon 6.12.5 C.
The provisions of Specification 3.0.3 are not applicable.
Balcal This specification is provided to ensure that the concentration of radioactivo materials roloased in liquid wasto offluents from the sito to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B. Tablo II.
This limitation provi'os additional assurance that the levnis of radioactivo materials in bodies of water outside the rite will not result in exposures greater than the Sects-
,I A design ohjeictives of Appendix 1,10 CFR Part 50, to a member of the public. The concentration limit for noble gases is based upon the I
assumption that Xo-133 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
assumption that Xo-133 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
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l Amendment No. f$,JJE,                                                                 66v                                                                         1
Amendment No. f$,JJE, 66v


          ,      e                                                                                                                                                                       ;
e
{
{
Radioactivo Liquid Effluents 3.25.1.2                 Donn Arrlicability: At all t.imes
Radioactivo Liquid Effluents 3.25.1.2 Donn Arrlicability: At all t.imes
;                                @jestiro:                 To ensure that the dose limits of 10 CFR 50, Appe , dix I, Section IV A, are met..
@jestiro:
SPEllis.0110D11 3.25.1.2       A       Tho dosn commitment to a member of thn public from radioactivo material in liquid offluents released from ANO-1 to the dischargo canal shall be:
To ensure that the dose limits of 10 CFR 50, Appe, dix I, Section IV A, are met..
: 1)   During any enlendar quarter less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrom to any organ, and
SPEllis.0110D11 3.25.1.2 A
: 2)   During any cal.ndar year less than or equal to 3 mrem                                                                   l to the total oody and less than or equal to 10 mrem to any organ.
Tho dosn commitment to a member of thn public from radioactivo material in liquid offluents released from ANO-1 to the dischargo canal shall be:
B.       With the calculated doso from the rolense of radioactivo materials in liquid effluents exceeding any of the above limits, in lieu of any other report, prepare and submit a Special Report. to t.hn Commission within 30 days, pursuant to Speci fication 6.12.5.
1)
C.       The provisions of Specification 3.0.3 are not applicable.                                                                 l Ilanx.s:
During any enlendar quarter less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrom to any organ, and 2)
During any cal.ndar year less than or equal to 3 mrem l
to the total oody and less than or equal to 10 mrem to any organ.
B.
With the calculated doso from the rolense of radioactivo materials in liquid effluents exceeding any of the above limits, in lieu of any other report, prepare and submit a Special Report. to t.hn Commission within 30 days, pursuant to Speci fication 6.12.5.
C.
The provisions of Specification 3.0.3 are not applicable.
l Ilanx.s:
Specification 3.25.1.2 provides assuranco that releases of liquid offluents will result in concentrations far below the limits of 10CFR20.
Specification 3.25.1.2 provides assuranco that releases of liquid offluents will result in concentrations far below the limits of 10CFR20.
The specification provides the required operating flexibility and at the same timo assures that the release of radioactivo material in liquid offluents will be kept "as low as reasonably achievablo".
The specification provides the required operating flexibility and at the same timo assures that the release of radioactivo material in liquid offluents will be kept "as low as reasonably achievablo".
Amendment. No. $f,JJE,                                                                       66w
Amendment. No. $f,JJE, 66w
                                                                  . _ .                      _ , _ . - - _ . _ _ - _ . , _ . . -          _ . . ~ . _ . - , - . - ,       _ . . _ . . . _
_.. ~. _. -, -. -,


v
v
(   n Radioactive !.1 quid 1:ffluents 3.25.1.3         Waste Trentment Arnlicahilliyi At all times Qbjec11tni       To assure that thn amount of radioactive materint in liquid effluents will be "ns low ns rensonnbly achievabin."
(
SDecLLLCaLivD31 3.25.1.3   A. The 9pptoprinto parts of the liquid radwnste t reatment system shn11 be used to reduce the radioactive materials in liquid waste prior to thnir discharge when it is projected that the cumulative donn during a calendar quarter dun to liquid effluent releases would exceed 0.18 mrom to the total body oi 0.6?.5 mrem to any organ.
n Radioactive !.1 quid 1:ffluents 3.25.1.3 Waste Trentment Arnlicahilliyi At all times Qbjec11tni To assure that thn amount of radioactive materint in liquid effluents will be "ns low ns rensonnbly achievabin."
B. The provisions of this specification do not npply to the laundry tanks due to their incompatibility with the radwnste system.
SDecLLLCaLivD31 3.25.1.3 A.
C. With radionctive liquid waste being dischntged without treatment nnd in excess of the abovn limits, in lieu of any other report, preparn and submit n Special Report to thn Commission within 30 days per Specification 6.12.5.
The 9pptoprinto parts of the liquid radwnste t reatment system shn11 be used to reduce the radioactive materials in liquid waste prior to thnir discharge when it is projected that the cumulative donn during a calendar quarter dun to liquid effluent releases would exceed 0.18 mrom to the total body oi 0.6?.5 mrem to any organ.
D. The provisions of Specification 3.0.3 are not applicable.
B.
The provisions of this specification do not npply to the laundry tanks due to their incompatibility with the radwnste system.
C.
With radionctive liquid waste being dischntged without treatment nnd in excess of the abovn limits, in lieu of any other report, preparn and submit n Special Report to thn Commission within 30 days per Specification 6.12.5.
D.
The provisions of Specification 3.0.3 are not applicable.
EAscal The requirements that the approprinte port ions of this system be used when specified provides assurance that the relenses of radionctive materinis in liquid offluents will be kept "as low nn is reasonably achievable." The specified limit s governing the use of approprinto portions of thn liquid radwnsto treatment system were specified as a suitable fraction of the guido set f orth in Section li A of Appendix 1, 10 CFR Part 50, for liquid effluents. The values of 0.18 mrem and 0.625 mrem are approximately 25*.
EAscal The requirements that the approprinte port ions of this system be used when specified provides assurance that the relenses of radionctive materinis in liquid offluents will be kept "as low nn is reasonably achievable." The specified limit s governing the use of approprinto portions of thn liquid radwnsto treatment system were specified as a suitable fraction of the guido set f orth in Section li A of Appendix 1, 10 CFR Part 50, for liquid effluents. The values of 0.18 mrem and 0.625 mrem are approximately 25*.
of the yearly design objectives on a quarterly basis. Tho       yearly design objectives are given in 10 CFR 50, Appendix I, Section 11.
of the yearly design objectives on a quarterly basis.
1 I
Tho yearly design objectives are given in 10 CFR 50, Appendix I, Section 11.
l l      Amendment No. ff,JJf.                           66x l
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l Amendment No. ff,JJf.
66x l
1
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v 4   s Radioactive biquid Effluents 3.25.1.4       Liquid fluldup Tanks Applicability: /.t all times.
v 4
Objen11y.c:     To ensure that thn limits of 10 CFR 20 are not exceeded.
s Radioactive biquid Effluents 3.25.1.4 Liquid fluldup Tanks Applicability: /.t all times.
500Gliitaliana1 3.25.1.4   A. Thn quantity of radioactivo materini contained in nach unprotected
Objen11y.c:
To ensure that thn limits of 10 CFR 20 are not exceeded.
500Gliitaliana1 3.25.1.4 A.
Thn quantity of radioactivo materini contained in nach unprotected
* outside temporary radionctivo liquid storagn tank shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.
* outside temporary radionctivo liquid storagn tank shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.
D. With thn quantity of radioactivo materini exceeding the above limit, immodlately suspnnd all additions of radioactive material to the af fected tank and within 48 boot s reduce tho tank content s to within tho limit.
D.
C. The provisions c,f Specification 3.0.3 are not applicable.                                 l Esses:
With thn quantity of radioactivo materini exceeding the above limit, immodlately suspnnd all additions of radioactive material to the af fected tank and within 48 boot s reduce tho tank content s to within tho limit.
C.
The provisions c,f Specification 3.0.3 are not applicable.
l Esses:
This specification is provided to ensurn t hat in the event of an uncontrolled release of the contents of tho tank
This specification is provided to ensurn t hat in the event of an uncontrolled release of the contents of tho tank
* the resulting concentrations would be less than the limits of 10 CFR Part 20. Appendix D. Table !!. Column 2, at the nearest potable water supply and the nearest surface water supply in the unrnstricted area.
* the resulting concentrations would be less than the limits of 10 CFR Part 20. Appendix D. Table !!. Column 2, at the nearest potable water supply and the nearest surface water supply in the unrnstricted area.
* Tanks included in this specification are thosn outdoor temporary tanks i       that 1) are not surrounded by liners, dikes, or walls capable of holding the tank contents, and 2) do not havo overflown and surrounding area drains connected to the 11guld radwasta treatment system.
* Tanks included in this specification are thosn outdoor temporary tanks i
that 1) are not surrounded by liners, dikes, or walls capable of holding the tank contents, and 2) do not havo overflown and surrounding area drains connected to the 11guld radwasta treatment system.
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Amendment No. $$,
Amendment No. $$,                               66y                                                         l l
66y l
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,\ .
,\\
3.2%.2           KndioCCLLY23RheaubblL195mLE 3.25.2.1         Dose Rate 01'idic0kilityl At all times hjtcLivel       To ?nsurn thnt the dose rate in unrestricted arens from gaseous effluents will bn within the limits of 10 CPR 20.
3.2%.2 KndioCCLLY23RheaubblL195mLE 3.25.2.1 Dose Rate 01'idic0kilityl At all times hjtcLivel To ?nsurn thnt the dose rate in unrestricted arens from gaseous effluents will bn within the limits of 10 CPR 20.
SEtGiliGAll0HR1 3.25.2.1   A. The dono rate in unr est ricted nrens (see rigure 5.1-1) due to radioactive materinis relensed in gosnous effluents from the site shall be:
SEtGiliGAll0HR1 3.25.2.1 A.
: 1)   For nobir gnses:     I.e s s t hnu or equal to 500 mrem /yr to the total body nnd less than or equoi to 3000 mrem /yr to the skin.
The dono rate in unr est ricted nrens (see rigure 5.1-1) due to radioactive materinis relensed in gosnous effluents from the site shall be:
: 2)   For iodine-131, for t rit ium nnd for all radionuclides in particulnto form with half lives grnater than 8 days:   I.e s s than or equnt to 1500 rnrern/yr to any organ.
1)
For nobir gnses:
I.e s s t hnu or equal to 500 mrem /yr to the total body nnd less than or equoi to 3000 mrem /yr to the skin.
2)
For iodine-131, for t rit ium nnd for all radionuclides in particulnto form with half lives grnater than 8 days:
I.e s s than or equnt to 1500 rnrern/yr to any organ.
During periods of reactor building purging the dose rate may bn av'.,i 9;,ed over a one hour interval.
During periods of reactor building purging the dose rate may bn av'.,i 9;,ed over a one hour interval.
11 . With the doro rate (s) exceeding the abovo limit s, without dr.iny rest r re the release rato to within thn above limit (s)
11.
C. The .. visions of Specificntion 3.0.3 nrn not applienbin.           l Eainst This specification is provided to ensure that, at any time, the dosn rato due to ganoo'.s effluents from nll units on the site till be within the limits of IC CPR 20 for unrestricteel arens.
With the doro rate (s) exceeding the abovo limit s, without dr.iny rest r re the release rato to within thn above limit (s)
C.
The.. visions of Specificntion 3.0.3 nrn not applienbin.
l Eainst This specification is provided to ensure that, at any time, the dosn rato due to ganoo'.s effluents from nll units on the site till be within the limits of IC CPR 20 for unrestricteel arens.
This npocification applien to the rolensn of gnsnous effluents from all reactors at the site.
This npocification applien to the rolensn of gnsnous effluents from all reactors at the site.
Amendment No. ff,JJf,                               66z
Amendment No. ff,JJf, 66z


e e           .
e e
Radioactive Gaseous Fffluents 3.25.2.2           Dono - Nobin Gases Arn1Jsab111ty.1 At a11 Limes OhjerAiyni         To ensure that the design objective doses of 10 CFR 50,                                         ,
Radioactive Gaseous Fffluents 3.25.2.2 Dono - Nobin Gases Arn1Jsab111ty.1 At a11 Limes OhjerAiyni To ensure that the design objective doses of 10 CFR 50, Appendix 1. Section IV A, are not exceeded.
Appendix 1. Section IV A, are not exceeded.                                                     l 621c.LLLc.o Linns.L 3.23.2.2. A.       The dose due to noble gases released in gaseous effluents from ANO-1 to unrestricted areas (see Figure 5.1-1) shall be:
l 621c.LLLc.o Linns.L 3.23.2.2. A.
: 1)       During any calendar quarter, less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiat lon, and i       During any calendar year, less then or equal to 10                                     ;
The dose due to noble gases released in gaseous effluents from ANO-1 to unrestricted areas (see Figure 5.1-1) shall be:
mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
1)
B. With the cniculated dosa from radioactive nobin gases in                                       ,
During any calendar quarter, less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiat lon, and i
gaseous effluents exceeding any of the above limits, in lieu of any other report, preparo and submit a Special Report to the Commission within 30 days, pursuant to Specification 6.12.5.
During any calendar year, less then or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
C. The provisions of Specification 3.0.3 are not applicable.                                     l Enges:
B.
With the cniculated dosa from radioactive nobin gases in gaseous effluents exceeding any of the above limits, in lieu of any other report, preparo and submit a Special Report to the Commission within 30 days, pursuant to Specification 6.12.5.
C.
The provisions of Specification 3.0.3 are not applicable.
l Enges:
Specification 3.25.2.2 implements the design guides speciflod in 10 CFR So, Appendix I, Section II, and the limiting condition for operation as set forth in Section IV A of Appendix 1.
Specification 3.25.2.2 implements the design guides speciflod in 10 CFR So, Appendix I, Section II, and the limiting condition for operation as set forth in Section IV A of Appendix 1.
The specifications provide the required operating flexibility and at the same time implement the guides set forth in Section IV A Appendix 1, to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievabic."
The specifications provide the required operating flexibility and at the same time implement the guides set forth in Section IV A Appendix 1, to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievabic."
These limits provide reasonable assuranco that radioactive material discharged in gaseous ef fluents will not result in the exposure of an individual in an unrestricted area, to annual average concentrations exceeding the limits specified in Appendix B. Table 11 of 10 CFR Part 20
These limits provide reasonable assuranco that radioactive material discharged in gaseous ef fluents will not result in the exposure of an individual in an unrestricted area, to annual average concentrations exceeding the limits specified in Appendix B. Table 11 of 10 CFR Part 20
[10 CFR Part 20.106(b)]. For individuals who may at times be within the exclusion area boundary, the occupancy of the individual will bn sufficiently low to compensate for any increaso in the atmospheric dif fusion f actor above that for the exclusion area boundary.
[10 CFR Part 20.106(b)].
l               Amendment No. $$,/J$,                                 66aa l
For individuals who may at times be within the exclusion area boundary, the occupancy of the individual will bn sufficiently low to compensate for any increaso in the atmospheric dif fusion f actor above that for the exclusion area boundary.
l Amendment No. $$,/J$,
66aa l
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e     .
e Radtonetive Gaseous F.f fluents 3.25.2.3 Dose - lodine-131, Trit ium, and Radionuclides in Particulate Form hyplicabilltv: At all times Qbjcnirai To ensuro that thn dosn limits of 10 CrR So, Appendix 1, Section IV A, are met.
Radtonetive Gaseous F.f fluents 3.25.2.3         Dose - lodine-131, Trit ium, and Radionuclides in Particulate Form hyplicabilltv: At all times Qbjcnirai       To ensuro that thn dosn limits of 10 CrR So, Appendix 1, Section IV A, are met.
SncEllital_iRD11 3.25.2.3 A.
SncEllital_iRD11 3.25.2.3   A. The doso to a member of the public f rom lodinn-131, f rom tritium, and from all radionucliden in ,articulato form with half-lives greater than 8 days in gaseous ef fluents released from ANO-1 to unrestrict ed areas (sen Figuro 5.1-1) shall bn;
The doso to a member of the public f rom lodinn-131, f rom tritium, and from all radionucliden in,articulato form with half-lives greater than 8 days in gaseous ef fluents released from ANO-1 to unrestrict ed areas (sen Figuro 5.1-1) shall bn; 1)
: 1)   During any calendar quarter, less tnan or equal to 7.5 mrems to any organ, and
During any calendar quarter, less tnan or equal to 7.5 mrems to any organ, and 2)
: 2)   During any calendar year, less than or equal to 15 mrems to any organ.
During any calendar year, less than or equal to 15 mrems to any organ.
11 With the calculated doso from the release of fodino-131, tritium and radionuclides in particulato form with half-lives greater than 8 days, in gaseous offluents exceeding any of the above limits, in lieu of any other report, prepnro and submit a Special Report to the Commission within 30 days, pursuant to Specification 6.12.5.
11 With the calculated doso from the release of fodino-131, tritium and radionuclides in particulato form with half-lives greater than 8 days, in gaseous offluents exceeding any of the above limits, in lieu of any other report, prepnro and submit a Special Report to the Commission within 30 days, pursuant to Specification 6.12.5.
C. The provisions of Specification 3.0.3 arn not applicable,         j Enns:
C.
The provisions of Specification 3.0.3 arn not applicable, j
Enns:
Specification 3.25.2.3 implements the design guides not forth in 10 CFR 50, Appendix 1, Section 11 C, and the limiting conditions for operation as set forth in Appendix 1, Section IV A.
Specification 3.25.2.3 implements the design guides not forth in 10 CFR 50, Appendix 1, Section 11 C, and the limiting conditions for operation as set forth in Appendix 1, Section IV A.
The specifications provide the requirnd operatir.g flexibility and at the same time implement the guidos snt forth in Section IV A of Appendix 1 to assure that the releases of radioactivo materials in gaseous effluents will be kept "as low as reasonably achievablo".
The specifications provide the requirnd operatir.g flexibility and at the same time implement the guidos snt forth in Section IV A of Appendix 1 to assure that the releases of radioactivo materials in gaseous effluents will be kept "as low as reasonably achievablo".
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l Amendment No f5.J/S, 66bb
l Amendment No f5.J/S,                             66bb I
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1 e     e Radioactivo Goncous Effluents 3.25.2.4               Ganeous Radwnsto Treatment Arpikabilily: At a11 timos i
e e
Ohju.tlyo:             To assure that the amount of radioactivo material in gescous effluents in "as Icw na rnasonnbly nchievablo."
Radioactivo Goncous Effluents 3.25.2.4 Ganeous Radwnsto Treatment Arpikabilily: At a11 timos Ohju.tlyo:
To assure that the amount of radioactivo material in gescous effluents in "as Icw na rnasonnbly nchievablo."
SAcnillrAlf ona':
SAcnillrAlf ona':
3.25.2.4     A.       i'entilation exhnunt. treatment systems shall be used to reduce radioactivo materials in gascaun wasto prior to dischargo when thn projoct ed doses duo to gaseous ef fluent rnlenses from ANO-1 to unrestricted arens (sco rigure 5.1-1) would exceed 0.625 mrad for gamma radiation and 1.25 mrnd for beta radiation ovnr a enlendar quart er; or when the projected doses due to lodine-131, tritium, and radionuclidon in particulato form with half-lives greater than 8 days would exceed 1.0 stem to any organ over n calendar qunrter.
3.25.2.4 A.
B.       When degnsi fying the reactor coolant system, the gaseous radwnste treatment system shall be utillr.ed to procosa the degesning ef fluent to reduce the concentration of radioactive materinta prior to discharge when the projected doses dun to goneous of fluent rolenson from ANO-1 to unrentricted arens (sco Figurn 5.1-1) would exceed 0.625 mrad for gamma radiation and 1.25 mrad for botn radiation over a calendar quarter.
i'entilation exhnunt. treatment systems shall be used to reduce radioactivo materials in gascaun wasto prior to dischargo when thn projoct ed doses duo to gaseous ef fluent rnlenses from ANO-1 to unrestricted arens (sco rigure 5.1-1) would exceed 0.625 mrad for gamma radiation and 1.25 mrnd for beta radiation ovnr a enlendar quart er; or when the projected doses due to lodine-131, tritium, and radionuclidon in particulato form with half-lives greater than 8 days would exceed 1.0 stem to any organ over n calendar qunrter.
C.       With gaseous wastn being discharged without treatment and in excess of the above limits, in llou of any other report, preparo and submit to the Commission within 30 days a Special Report, por Specification 6.12.5.
B.
D.       The provisions of Specification 3.0.3 are not applicable, bses:
When degnsi fying the reactor coolant system, the gaseous radwnste treatment system shall be utillr.ed to procosa the degesning ef fluent to reduce the concentration of radioactive materinta prior to discharge when the projected doses dun to goneous of fluent rolenson from ANO-1 to unrentricted arens (sco Figurn 5.1-1) would exceed 0.625 mrad for gamma radiation and 1.25 mrad for botn radiation over a calendar quarter.
The requirement that tbn approprinto portions of thnne systems bo used when specified providen reasonnble nasurance that thn relonnes of radioactive materials in gaseous offluents will be kept "na low na reasonably achievable." Tho specified limits governing the uso of approprinto portions of the systems worn specified as a suitablo fraction of the guide set forth in Sections 11 B and II C of Appendix 1,10 CFR Part 50, for gaseous of fluents.                                             The values 0.625 mrad,1.25 mrad, and 1.0                                           ,
C.
mrom are approximately 25% of the yently design objectives on a quarterly                                                                                       I basis. The yearly desigt. objectiven are given in Specifications 3.25.2.2 and 3.25.2.3.
With gaseous wastn being discharged without treatment and in excess of the above limits, in llou of any other report, preparo and submit to the Commission within 30 days a Special Report, por Specification 6.12.5.
l l                                                                                                                                                                                    !
D.
I l
The provisions of Specification 3.0.3 are not applicable, bses:
Amendment No. 75,1J5,                                                                             66cc                                                           l
The requirement that tbn approprinto portions of thnne systems bo used when specified providen reasonnble nasurance that thn relonnes of radioactive materials in gaseous offluents will be kept "na low na reasonably achievable." Tho specified limits governing the uso of approprinto portions of the systems worn specified as a suitablo fraction of the guide set forth in Sections 11 B and II C of Appendix 1,10 CFR Part 50, for gaseous of fluents.
_ _ . _ . _ . _ . _ _ . _ _      _ , . _ _ _ . _ _ _ . _ . _ . . ~ . . . _ _ _ . - _ .
The values 0.625 mrad,1.25 mrad, and 1.0 mrom are approximately 25% of the yently design objectives on a quarterly I
basis. The yearly desigt. objectiven are given in Specifications 3.25.2.2 and 3.25.2.3.
l l
Amendment No. 75,1J5, 66cc
.. ~...


Radioactivo Gancous Effluents 3.25 2.5             Gas Storage Tanks Applicabilfly t At. ell times Ohjgsihe:           To rostrict the amount of activity in a radioactive gas holdup tank.
Radioactivo Gancous Effluents 3.25 2.5 Gas Storage Tanks Applicabilfly t At. ell times Ohjgsihe:
Eggstficationgs 3.25.2.5   A.       The quantity of radioactivity contained in each gas stu_ago tank shall bo limited to 300,000 curies noble gases (Xc-133 equivalent).
To rostrict the amount of activity in a radioactive gas holdup tank.
B.       With thn quantity of radioactivo material in any gas storago tank exceeding the abovn limit, immediately suspend all additions of radtonctive material to the tank and within 48 hours reduce the tank contents to within the limit.
Eggstficationgs 3.25.2.5 A.
C.       The provisions of Specification 3.0.3 are not applicable.
The quantity of radioactivity contained in each gas stu_ago tank shall bo limited to 300,000 curies noble gases (Xc-133 equivalent).
B.
With thn quantity of radioactivo material in any gas storago tank exceeding the abovn limit, immediately suspend all additions of radtonctive material to the tank and within 48 hours reduce the tank contents to within the limit.
C.
The provisions of Specification 3.0.3 are not applicable.
Rases:
Rases:
The value of 300,000 curies is a suitable fraction of the quantity of radioactive material which if released over a 2-hour period, would result in a total body exposure to a member of the public at the exclusion area boundary of 500 mrom. This is consistent with Branch Technical Position ETSB 11-5 in NUREG-0800, July 1981.
The value of 300,000 curies is a suitable fraction of the quantity of radioactive material which if released over a 2-hour period, would result in a total body exposure to a member of the public at the exclusion area boundary of 500 mrom.
This is consistent with Branch Technical Position ETSB 11-5 in NUREG-0800, July 1981.
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l Amendment No ff, 66dd i
!                Amendment No ff,                                             66dd i
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l-              .                          - .    - . . -.  .    . -- - . - _.                  -      .                  _ _ . - _ - -


3.25.3     Iolal_ Doms ApplLcJth111ty.1 At all times l
3.25.3 Iolal_ Doms ApplLcJth111ty.1 At all times l
i                         Qbjnily.gl               To ensure that the limita of 40 CFR 190 are not exceeded.
i Qbjnily.gl To ensure that the limita of 40 CFR 190 are not exceeded.
Spnifica t ioni l                         3.25.3.1   The calculated doses from the release of radioactivo materials in liquid or gaseous offluents shall not exceed twice the limits of Specification 3.25.1.2, 3.25.2.2, or 3.25.2.3.
Spnifica t ioni l
3.25.3.2   With the calculated doses exceeding the above limits, preparo and submit a Special Report pursuant to 10CFR part 20.4050.
3.25.3.1 The calculated doses from the release of radioactivo materials in liquid or gaseous offluents shall not exceed twice the limits of Specification 3.25.1.2, 3.25.2.2, or 3.25.2.3.
3.25.3.3   If thn limits of 40CFR190 havn been exceeded, obtain a variance i
3.25.3.2 With the calculated doses exceeding the above limits, preparo and submit a Special Report pursuant to 10CFR part 20.4050.
3.25.3.3 If thn limits of 40CFR190 havn been exceeded, obtain a variance i
f rom the Commission t o permit further rolcasos in excess of 40CFR190 limits. A variance is granted until staf f action on the request is completed.
f rom the Commission t o permit further rolcasos in excess of 40CFR190 limits. A variance is granted until staf f action on the request is completed.
3.25.3.4   The provisions of Specification 3.0.3 are not applicable.
3.25.3.4 The provisions of Specification 3.0.3 are not applicable.
l Hanni This specification is provided to mont the dose limitations of 40 CFR 190 that have now been incorporated into 10 CFR part 20.               The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactivo offluents exceed twice the design objective doses of Appendix I.             For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the doso limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Specini Report will ds6cribe a course of action that should result in the limitation of the annual dose to a member of the public to within the 40 CFR 190 limits.                     For the purposes of the Special Report, it may bn assumed that the dose commitment to the member of the public from other uranium tual cycin sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities within a radius of 8 km must bn considered.                       If the dose to any member of the public is estimated to excnod the requirements of 40 CFR 190, the Special Report with a requnst for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not
l Hanni This specification is provided to mont the dose limitations of 40 CFR 190 that have now been incorporated into 10 CFR part 20.
!                        already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staf f action is completed. The variance only relates to the limits of 40 CFR 190, and does not apply la any way to the other rnquirements for dose limitation of l                         10 CFR 20, as addressed in Specifications 3.25.1 and 3.25.2.                       An I                         individual is not considered to be a member of the public during any l                         period in which he/she is engaged in carrying out any operation that is part of the nuclect funt cycle.
The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactivo offluents exceed twice the design objective doses of Appendix I.
For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the doso limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level.
The Specini Report will ds6cribe a course of action that should result in the limitation of the annual dose to a member of the public to within the 40 CFR 190 limits.
For the purposes of the Special Report, it may bn assumed that the dose commitment to the member of the public from other uranium tual cycin sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities within a radius of 8 km must bn considered.
If the dose to any member of the public is estimated to excnod the requirements of 40 CFR 190, the Special Report with a requnst for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staf f action is completed.
The variance only relates to the limits of 40 CFR 190, and does not apply la any way to the other rnquirements for dose limitation of l
10 CFR 20, as addressed in Specifications 3.25.1 and 3.25.2.
An I
individual is not considered to be a member of the public during any l
period in which he/she is engaged in carrying out any operation that is part of the nuclect funt cycle.
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l Amendment No. 58,                                       66ce
l Amendment No. 58, 66ce
_. _        __ . -- _      ~~,
~~,


3.23.4                 Holid_.RadiontinLWaste App _licability : At all timns Objective;             To ensurn solid radwasto is processed in accordance with the Process Cont rol Program to meet shipping and burial ground rnquirements.
3.23.4 Holid_.RadiontinLWaste App _licability : At all timns Objective; To ensurn solid radwasto is processed in accordance with the Process Cont rol Program to meet shipping and burial ground rnquirements.
Specifinational 3.25.4.1         With the provisions of the Process Control Program not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastn from the sito.
Specifinational 3.25.4.1 With the provisions of the Process Control Program not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastn from the sito.
3.25 4.2         The provisions of Specification 3.0.3 nro not applicable.
3.25 4.2 The provisions of Specification 3.0.3 nro not applicable.
l Eases:           This specification impicments the requirements of 10CFR50.36a and General Design Criterion 60 of Appendix A to 10CFR50.
l Eases:
l l
This specification impicments the requirements of 10CFR50.36a and General Design Criterion 60 of Appendix A to 10CFR50.
!            Amendment No fE,J/5,                                             66ff                                                                       I I
Amendment No fE,J/5, 66ff


  -.--      - =                           _ _ - -
- =
l     ,
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* i l
l SURVEILLANCE REQUIREMENTS 4.0.1 Survnillanco Requirements shall bo met during the operational modos or other conditions specified for individual Limiting Conditions for Operation unless otherwiso stated in an individual Surveillance Requirement.
SURVEILLANCE REQUIREMENTS 4.0.1   Survnillanco Requirements shall bo met during the operational modos or other conditions specified for individual Limiting Conditions for Operation unless otherwiso stated in an individual Surveillance Requirement.                                                                                                       ,
4.0.2 Each Surveillanco Requirement shall be performed within the i
I 4.0.2 Each Surveillanco Requirement shall be performed within the                                                 i specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.
specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.
I 4.0.3   Failure to perform a Surveillanco Requirement within the allowed                                         ,
4.0.3 Failure to perform a Surveillanco Requirement within the allowed surveillance interval defined by Specification 4.0.2, shall constituto noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation.
surveillance interval defined by Specification 4.0.2, shall constituto                                             )
The time limits of the Action requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The timo at which the Action is taken may be delayed for up to 2' hours to permit the completion of the surveillance when the allowable outage time limits of the Action requirements are less than 24 hours.
noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation. The time limits of the Action requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The timo at which the Action is taken may be delayed for up to 2' hours to permit the completion of the surveillance when the allowable outage time limits of the Action requirements are less than 24 hours.
Surveillance Requirements do not have to be performed on inoperable equipment.
Surveillance Requirements do not have to be performed on inoperable equipment.                                                                                                       !
4.0.4 Entry into an operational mode or other specified condition shall not be made unless the Surveillanco Requirement (s) associated with the Limiting Condition for Operation has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to operational modes as ' required to comply with Action requirements.
4.0.4 Entry into an operational mode or other specified condition shall not be made unless the Surveillanco Requirement (s) associated with the Limiting Condition for Operation has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to operational modes as ' required to comply with Action requirements.
4.0.5   Surveillance Requirements for inservice inspection and testing of-ASME Code Class 1,2, and 3 components shall be applicable as follows:
4.0.5 Surveillance Requirements for inservice inspection and testing of-ASME Code Class 1,2, and 3 components shall be applicable as follows:
5
5 a.
: a. Inservice inspection of ASME Code Class 1,2, and 3 components and inservice testing of ASME Code Class 1,2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and pressure Vessel Code and nop11 cable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(1),
Inservice inspection of ASME Code Class 1,2, and 3 components and inservice testing of ASME Code Class 1,2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and pressure Vessel Code and nop11 cable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(1),
Amendment No. 25,/J,//,JZ9,                             67
Amendment No. 25,/J,//,JZ9, 67
                              . - _ . - _        _ ,    ._. _ __ _ .. _ . . . . _ _ _ . _ _ _ . . _ . ~ . _ , _ _ . ~
_.... _ _ _. _ _ _.. _. ~. _, _ _. ~


O             O SURVEILLANCE REQUIREMENTS _(Continued) 4.0.5 (Continued) l                                       b.           Surveillance intervals specified in Section XI of the ASME Boiler I                                                     and Pressure Vessel Code and applicable Addenda for the inservice I                                                     inspection and testing activities required by the ASME Boiler and i                                                    Pressure Vessel Code and applicable Addenda shall be applicable as follown in these Technical Specifications:
O O
l ASME Boiler and Pressure Vessel                                                   Required frequencies for Code and applicable Addenda                                                             performing incervice terminology for inservice                                                         inspection and testing inspection and testing activities                                                            activities
SURVEILLANCE REQUIREMENTS _(Continued) 4.0.5 (Continued) l b.
Surveillance intervals specified in Section XI of the ASME Boiler I
and Pressure Vessel Code and applicable Addenda for the inservice I
inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as i
follown in these Technical Specifications:
l ASME Boiler and Pressure Vessel Required frequencies for Code and applicable Addenda performing incervice terminology for inservice inspection and testing
(
(
l                                                                     Weekly                                                                 At least once por 7 days l                                                                     Monthly                                                                 At least once per 31 days Quarterly or every 3 months                                                             At least once per 92 days
inspection and testing activities activities l
!                                                    Semiannually or every 6 months                                                         At least once per 184 days Yearly or annually                                                                     At least once per 366 days
Weekly At least once por 7 days l
: c.          The provisions of Specification 4.0.2 are applicable to the above                                                                                       ,
Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Yearly or annually At least once per 366 days The provisions of Specification 4.0.2 are applicable to the above c.
required frequencies for performing inservice inspection and testing activities.
required frequencies for performing inservice inspection and testing activities.
: d.           Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
d.
: n.           Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.
Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
4.1                   OPERATIONAL SAFETY ITEMS Applicability Applies to items directly related to safety limits and limiting conditions for operation.
n.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.
4.1 OPERATIONAL SAFETY ITEMS Applicability Applies to items directly related to safety limits and limiting conditions for operation.
Objective To specify the minimum frequency and type of surveillance to be applied to unit equipment and conditions.
Objective To specify the minimum frequency and type of surveillance to be applied to unit equipment and conditions.
Specification
Specification a.
: a.         The minimum frequency and type of surveillance required for reactor protective system and engineered safeguards system instrumentation when the reactor is critical shall be as stated in ' fable 4.1-1.
The minimum frequency and type of surveillance required for reactor protective system and engineered safeguards system instrumentation when the reactor is critical shall be as stated in ' fable 4.1-1.
Amendment No.                                                                     67a i
Amendment No.
67a i


1 OPERATIONAL SAFETY ITEMS _(cont.in,ued)_
1 OPERATIONAL SAFETY ITEMS _(cont.in,ued)_
4.1 (Continued)
4.1 (Continued) b.
: b. Equipment and sampling test shall be performed as detailed in Table 4.1-2 and 4.1-3.
Equipment and sampling test shall be performed as detailed in Table 4.1-2 and 4.1-3.
: c. Discrepancies noted during surveillance testing will be corrected and recorded,
c.
: d. A power distribution map shall be made to verify tho expected power distribution at periodic intervals at a 'at every 10 effective full power days using the incorn instrumentation detector system.
Discrepancies noted during surveillance testing will be corrected and recorded, d.
A power distribution map shall be made to verify tho expected power distribution at periodic intervals at a 'at every 10 effective full power days using the incorn instrumentation detector system.
BASES 4.0.1 through 4.0.5_ Establish the general requirements applicable to Surveillance Requirements. These requirements arn based on thn Surveillance Requirements stated in the Code of Federal Regulations, 10CFR 50.36(c)(3):
BASES 4.0.1 through 4.0.5_ Establish the general requirements applicable to Surveillance Requirements. These requirements arn based on thn Surveillance Requirements stated in the Code of Federal Regulations, 10CFR 50.36(c)(3):
                    " Surveillance Requirements are requiremet '.s relating to test, calibration, or inspection to ensurn that the riecessary quality of systems and components is maintained, that facility operation will be tithin safety limits, and that the limiting conditions of operation will be met."
" Surveillance Requirements are requiremet '.s relating to test, calibration, or inspection to ensurn that the riecessary quality of systems and components is maintained, that facility operation will be tithin safety limits, and that the limiting conditions of operation will be met."
4.0.1 Establishes the requirement that surveillances must be performed     ,
4.0.1 Establishes the requirement that surveillances must be performed during the operational modos or other conditions for which the requirements of the Limiting Conditions for Operation apply.unless otherwise stcted in an individual Surveillance Requirement.
during the operational modos or other conditions for which the requirements of the Limiting Conditions for Operation apply.unless otherwise stcted in an individual Surveillance Requirement. The purpose of this specification is to ensurn that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a mode or other specified condition for which the associated Limiting Conditions for 0poration arn applicabin.
The purpose of this specification is to ensurn that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a mode or other specified condition for which the associated Limiting Conditions for 0poration arn applicabin.
Surveillance Requirements do not have to be performed when thn facility is -
Surveillance Requirements do not have to be performed when thn facility is in an operational mode for which the requirements of the associated Limiting Condition for Operat. ion do not apply unless otherwise specified.
in an operational mode for which the requirements of the associated Limiting Condition for Operat. ion do not apply unless otherwise specified.
Amendment No. 75 67b
Amendment No. 75                               67b


o     -
o e
e BASES (continued) 4.0.2 Establishes the limit for which the specified time interval for Surveillance Requirements may be extended. It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may ut be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities. It also provides flexibility to accommodate the length of a fuel cycle for surveillances t.ha t are performed at each refueling outage and are specified with an 18-month surveillance Interval.                         It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages. The limitation of Specification 4.0.2 is based on engineering judgement and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance intervals.
BASES (continued) 4.0.2 Establishes the limit for which the specified time interval for Surveillance Requirements may be extended.
4.0.3 Establishes the failure to perform a Surycillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation. Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval,                                   flowever, nothing in this provision is to be construed as implying that syatems or components are OPERABLE when they are found or known to be Inoperable although still meeting the Surveillance Requirements. This specification also clarifles that the Action requirements are applicable'when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the Action requirements apply from the point-in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded. Completion of the Surveillance Requirement within the allowable outage time limits of the Action -requirements restores compliance with thr- requirements of l                   Specification 4.0.3.                         Ilowever, this does not negate the fact that the failure to have performed the surveillanco within the allowed surveillance interval, defined by the provisions of Specification 4.0.2 was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action. Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10CFR 50.73(a)(2)(1)(B) because it is a condition prohibited by the plant's Technical Specifications.
It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may ut be suitable for conducting the surveillance; e.g.,
If the allowabic outage time limits of the Action requirements are less than 24 hours or a shutdown is required to comply with Action requirements,           e.g., Specification 3.0.3, a 24-hour allowance is provided to permit a delay in implementing the Action requirements. This provides an adequate time limit to complete Surveillan;.e Requirements that have not been performed. The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with Action requirements or before other remedial measures would be required that may preclude completion of a surveillance. The basis for this allowance l
transient conditions or other ongoing surveillance or maintenance activities.
l l                   Amendment No.                                                 67c
It also provides flexibility to accommodate the length of a fuel cycle for surveillances t.ha t are performed at each refueling outage and are specified with an 18-month surveillance Interval.
It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages. The limitation of Specification 4.0.2 is based on engineering judgement and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements.
This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance intervals.
4.0.3 Establishes the failure to perform a Surycillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation. Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval, flowever, nothing in this provision is to be construed as implying that syatems or components are OPERABLE when they are found or known to be Inoperable although still meeting the Surveillance Requirements.
This specification also clarifles that the Action requirements are applicable'when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the Action requirements apply from the point-in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded. Completion of the Surveillance Requirement within the allowable outage time limits of the Action -requirements restores compliance with thr-requirements of l
Specification 4.0.3.
Ilowever, this does not negate the fact that the failure to have performed the surveillanco within the allowed surveillance interval, defined by the provisions of Specification 4.0.2 was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action.
Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10CFR 50.73(a)(2)(1)(B) because it is a condition prohibited by the plant's Technical Specifications.
If the allowabic outage time limits of the Action requirements are less than 24 hours or a shutdown is required to comply with Action requirements, e.g., Specification 3.0.3, a 24-hour allowance is provided to permit a delay in implementing the Action requirements. This provides an adequate time limit to complete Surveillan;.e Requirements that have not been performed. The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with Action requirements or before other remedial measures would be required that may preclude completion of a surveillance. The basis for this allowance l
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Amendment No.
67c


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MSES (cat iny.edl t
MSES (cat iny.edl includes cons ideration for plant conditions , adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required survoillanco.       This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of mode changes imposed by Action requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed, if a surveillance la not completed within the 24-hour allowance, the timo limits of the Action requirements are applicable at that time. When a surveillanen is performed within the 24-hour allowance and thn Surveillance Requirement.s are not met, the time limits of t he Action requirements arn applicable at the time that the surveillance is terminated.         if the Action requirements are greater than 24 hours, suf ficient t ime exists to complete the survn111ance.
includes cons ideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required survoillanco.
Surveillance Requirements do not. have to be performed on inoperable equipment because the Action requirements define the remedial measures that apply,       llowevn r , the Surveillanco Requirements have to be met to demonstratn that. inoperable equipment has been restored to OPERABl.E status.
This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of mode changes imposed by Action requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed, if a surveillance la not completed within the 24-hour allowance, the timo limits of the Action requirements are applicable at that time. When a surveillanen is performed within the 24-hour allowance and thn Surveillance Requirement.s are not met, the time limits of t he Action requirements arn applicable at the time that the surveillance is terminated.
4.0.4 Establishes the requirement that all applicable surveillances must be met before entry into an operational mode or other condit.fon of operation specified in the Specification. The purpose of this Specification is to ensure that system and component OPERABil.lTY requirements or parameter limits are met before entry into a mode or condition for which these systems and components ensure safe operation of the facility.       This provision applies to changes in operational modes or other specified conditions associated with plant shutdown as well as startup Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to ensure that the Limit!ng Conditions for Operation are met during initial plant startup or following a plant outage.
if the Action requirements are greater than 24 hours, suf ficient t ime exists to complete the survn111ance.
Surveillance Requirements do not. have to be performed on inoperable equipment because the Action requirements define the remedial measures that apply, llowevn r, the Surveillanco Requirements have to be met to demonstratn that. inoperable equipment has been restored to OPERABl.E status.
4.0.4 Establishes the requirement that all applicable surveillances must be met before entry into an operational mode or other condit.fon of operation specified in the Specification. The purpose of this Specification is to ensure that system and component OPERABil.lTY requirements or parameter limits are met before entry into a mode or condition for which these systems and components ensure safe operation of the facility.
This provision applies to changes in operational modes or other specified conditions associated with plant shutdown as well as startup Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to ensure that the Limit!ng Conditions for Operation are met during initial plant startup or following a plant outage.
When a shutdown is required to comply with Action requirements, the provision of Specification 4.0.4 do not apply because this would delay placing the facility in a lower mode of operation.
When a shutdown is required to comply with Action requirements, the provision of Specification 4.0.4 do not apply because this would delay placing the facility in a lower mode of operation.
4.0.5 Establishes the requiremont that inservice inspection of ASME Code Class 1,2, and 3 components and inservice testing of ASME Code Class 1,2, and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section XI of the ASME Boller and Pressurn Vessel Code and Addenda as requ'.e4 by 10 CFR 50.55a.             These requirements apply except. when rnlief has been provided in writing by the Commission.
4.0.5 Establishes the requiremont that inservice inspection of ASME Code Class 1,2, and 3 components and inservice testing of ASME Code Class 1,2, and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section XI of the ASME Boller and Pressurn Vessel Code and Addenda as requ'.e4 by 10 CFR 50.55a.
This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boller and Pressure Vessel Code and applicable Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout Technical Specifications and to remove any ambiguities relativo to the frequencies for performing the required                   ,
These requirements apply except. when rnlief has been provided in writing by the Commission.
inservico inspec, tion and testing activities.
This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boller and Pressure Vessel Code and applicable Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout Technical Specifications and to remove any ambiguities relativo to the frequencies for performing the required inservico inspec, tion and testing activities.
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Amendment No.                                 67d                                           l l
67d 9
9


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J EASES fcontinurdl Under the terms of this specification, the more restrictive requirements of the Technical Specificat ions take precedence over the ASME Boiler and Pressuro Vessel Codo and applicablo Addenda. The requirements of Specification 4.0.4 to perform surynlliance activities beforo entry into an eperational mode or other spncified condition takes precedence over the ASME Boiler and Pressuro Vessel Ccxin provision which allows pumps and valves to be tested up to one week af ter return to normal operation. The Technical Specificatien dnfinition of OPERABLE does not allow a graco period before a component, that is not. capable of performing its specified function, is declared inoperable and takes procedence over the ASME Boiler and Pressuro Vessel Code provision which allows a valve to be incapable of performing its specJ fied function for up to 24 hours before being declared inoperabin, Check Failures such as blown instrument fuses, defective indicators, faulted ampitfiers which result in " upscale" or "downscale" indication can be easily recognized by simple observation of the functioning of an instrument or system. Furthermoro, such failures are, in many cases, revealed by alarm or annunciator Action. Comparison of output and/or state of indepnndent channels measuring the same variable supplements this type of built-in surveillance. Based on experienco in operation of both conventional and nuclear plant systems, when the plant is in operation, the mlnimum checking frequency stated is doomed adequate for reactor sysua instrumentation.
* EASES fcontinurdl Under the terms of this specification, the more restrictive requirements of the Technical Specificat ions take precedence over the ASME Boiler and Pressuro Vessel Codo and applicablo Addenda. The requirements of Specification 4.0.4 to perform surynlliance activities beforo entry into an eperational mode or other spncified condition takes precedence over the ASME Boiler and Pressuro Vessel Ccxin provision which allows pumps and valves to be tested up to one week af ter return to normal operation. The Technical Specificatien dnfinition of OPERABLE does not allow a graco period before a component, that is not. capable of performing its specified function, is declared inoperable and takes procedence over the ASME Boiler and Pressuro Vessel Code provision which allows a valve to be incapable of performing its specJ fied function for up to 24 hours before being declared inoperabin, Check Failures such as blown instrument fuses, defective indicators, faulted ampitfiers which result in " upscale" or "downscale" indication can be easily recognized by simple observation of the functioning of an instrument or system. Furthermoro, such failures are, in many cases, revealed by alarm or annunciator Action. Comparison of output and/or state of indepnndent channels measuring the same variable supplements this type of built-in surveillance. Based on experienco in operation of both conventional and nuclear plant systems, when the plant is in operation, the mlnimum checking frequency stated is doomed adequate for reactor sysua instrumentation.
Calibration Calibration shall he performed to assure the presentation and acquisition of accurate information.
Calibration Calibration shall he performed to assure the presentation and acquisition of accurate information. The nuclear flux (power rango) channels shall be calibrated at least twice wenkly (during steady state operating conditions) against a heat balance standard to compensate for instrumentation drift. During non-steady stato operation, the nuclear flux channels shall be calibrated daily to componsato for instrumentation drift and changing rod patterns and corn physics parameters.
The nuclear flux (power rango) channels shall be calibrated at least twice wenkly (during steady state operating conditions) against a heat balance standard to compensate for instrumentation drift.
Amendment No.                     670
During non-steady stato operation, the nuclear flux channels shall be calibrated daily to componsato for instrumentation drift and changing rod patterns and corn physics parameters.
Amendment No.
670


IahJe 4.1-1 (Cont.)
IahJe 4.1-1 (Cont.)
Channel Descriotion         Check       Igs1   Calibrate         Remarks 1
Channel Descriotion Check Igs1 Calibrate Remarks 1
: 30. Decay heat removal                     S(1)(2)   M(i)(3) R       (1) Includes RCS Pressure Analog Channel system isolation valve                                     (2) Includes CFT Isolation Valve Position automatic closure and                                     (3) Shall also be tested during refueling interlock system                                                 shutdown prior to repressurization at a pressure greater than 300 but less than 420 psig.
: 30. Decay heat removal S(1)(2)
: 31. Turbine overspeed trip                 NA         E       NA     (1) The provisions of Specification 4.0.4 mechanism                                                       are not applicable.
M(i)(3) R (1) Includes RCS Pressure Analog Channel system isolation valve (2) Includes CFT Isolation Valve Position automatic closure and (3) Shall also be tested during refueling interlock system shutdown prior to repressurization at a pressure greater than 300 but less than 420 psig.
: 32. Diesel generator                       M         Q       NA protective relaying starting interlocks and circuitry
: 31. Turbine overspeed trip NA E
: 33. Of f-site power undervoltage           W         R(1)     R(1)   (1) Shall be tested during refueling and protective relaying                                         shutdown to demonstrate selective interlocks and circuitry                                         load shedding interlocks function during manual or automatic trans-fer of Unit I auxiliary load to Startup Transformer No. 2.
NA (1) The provisions of Specification 4.0.4 mechanism are not applicable.
: 34. Borated water storage                 W         NA       R tank level indicator
: 32. Diesel generator M
: 35. Reactor trip upon loss                 M         PC       R of main feedwater circuitry 1
Q NA protective relaying starting interlocks and circuitry
Amendment No. 4,19,59,69,67,91,                               72
: 33. Of f-site power undervoltage W
R(1)
R(1)
(1) Shall be tested during refueling and protective relaying shutdown to demonstrate selective interlocks and circuitry load shedding interlocks function during manual or automatic trans-fer of Unit I auxiliary load to Startup Transformer No. 2.
: 34. Borated water storage W
NA R
tank level indicator
: 35. Reactor trip upon loss M
PC R
of main feedwater circuitry 1
Amendment No. 4,19,59,69,67,91, 72


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year limits of Specifications 3.25.1.2 and 3.25.2.2.             This Special Report is not required if the measured level of radioactivity was not the result of plant effluents, however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental                               ,
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Report,
1 year limits of Specifications 3.25.1.2 and 3.25.2.2.
: c.           With milk or fresh leafy vogotable samples unavailable from                           ;
This Special Report is not required if the measured level of radioactivity was not the result of plant effluents, however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental
any of the sample locations required by Table 4.29-1,                                 '
: Report, c.
identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.         The specific locations from which samples were unavailable may then be deleted from the monitoring program. Identify the causes of the unavailability of samples and identify the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also Jnclude in the report a revised table for the ODCM reflecting the new location (s),
With milk or fresh leafy vogotable samples unavailable from any of the sample locations required by Table 4.29-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.
: d.           The provisions of Specification 3.0.3 are not applicable.
The specific locations from which samples were unavailable may then be deleted from the monitoring program.
Identify the causes of the unavailability of samples and identify the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also Jnclude in the report a revised table for the ODCM reflecting the new location (s),
d.
The provisions of Specification 3.0.3 are not applicable.
4.30.1.3 The results of analyses performed on the radiological environmental monitoring samples shall be summarized in the Annual Radiological Environmental Report.
4.30.1.3 The results of analyses performed on the radiological environmental monitoring samples shall be summarized in the Annual Radiological Environmental Report.
Bases:
Bases:
The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation.
The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation.
This monitoring program thereby supplements the radiological effluents monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program will be ef fective for at least the first three years of commercial operation.
This monitoring program thereby supplements the radiological effluents monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.
Following this period, program changes may be initiated based on operational experience,                                                                                     j l
The initially specified monitoring program will be ef fective for at least the first three years of commercial operation.
The detection capabilities required by Table 4.30-2 are state-of-the-art                                     f for routine environmental measurements in industrial laboratories.                     The                 l LLD's for drinking water meet the requirements of 40 CFR 141.                                               j l
Following this period, program changes may be initiated based on operational experience, j
                                                                                                                  )
l The detection capabilities required by Table 4.30-2 are state-of-the-art f
for routine environmental measurements in industrial laboratories.
The l
LLD's for drinking water meet the requirements of 40 CFR 141.
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1 Amend:nent No. $1L , J / 5,                           110tt                                                 j t
1 Amend:nent No. $1L, J / 5, 110tt j
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4r   r Radiological Environmnntal Honitoring 4.30.2         Land.Use C_eJuina Apolicabilltv: Applies at all timon Objectivea:     This specification will identify changes in use of the unrestricted areas.
4r r
SPE llinalisual                                                 %
Radiological Environmnntal Honitoring 4.30.2 Land.Use C_eJuina Apolicabilltv: Applies at all timon Objectivea:
4.30.2.1   A land use census shall be conducted and shall identify the location of the nearnst milk animal, the nearest residence, and the nearest garden
This specification will identify changes in use of the unrestricted areas.
SPE llinalisual 4.30.2.1 A land use census shall be conducted and shall identify the location of the nearnst milk animal, the nearest residence, and the nearest garden
* of greator ttan 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles from thn ANO-1 reactor building.
* of greator ttan 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles from thn ANO-1 reactor building.
4.30.2.2 The land use census shall be conducted at Itast once por 12 months between the dates of Junn 1 and October 1, oy door-to-door survey, aerial survey, or by consulting local agricultural authorities.
4.30.2.2 The land use census shall be conducted at Itast once por 12 months between the dates of Junn 1 and October 1, oy door-to-door survey, aerial survey, or by consulting local agricultural authorities.
4.30.2.3   n. With a land uso census identifying a location (s) which yinids a calculated dose commitment due to I-131, tritium, and radionuclidos in particulate form greater than the values currently being calculated in Unit 1 Specification 4.29.3 and Unit 2 Specification 4.11.2.3 submit location description in the Semiannual Radioactive Effluent Release Report por Specification 6.12.2.6.
4.30.2.3 n.
: b. With a land uso census identifying a location (s) which yields a calculated dose commitment (via the same exposure pathway) greater than at a location from which samples are currently being obtained in accordance with Specification 4.30.1.1, identify the new location in the Semiannual Radioactivo Effluent Release Report per Specification 6.12.2.6. The new location shall be added to the radiological environmental monitoring program within 30 days, if possib1n. The sampling location having the lowest calculated dose commitment (via the samn exposure pathway) may be doloted from this monitoring program af ter October 31 of the year in which this land use census was conducted.                           ,
With a land uso census identifying a location (s) which yinids a calculated dose commitment due to I-131, tritium, and radionuclidos in particulate form greater than the values currently being calculated in Unit 1 Specification 4.29.3 and Unit 2 Specification 4.11.2.3 submit location description in the Semiannual Radioactive Effluent Release Report por Specification 6.12.2.6.
l 4.30.2.4 The results of the land uso consus shall be included in the Annual Radiological Environmental Report.
b.
s 4.30.2.5 The provisions of Specification 3.0.3 are not applicable.
With a land uso census identifying a location (s) which yields a calculated dose commitment (via the same exposure pathway) greater than at a location from which samples are currently being obtained in accordance with Specification 4.30.1.1, identify the new location in the Semiannual Radioactivo Effluent Release Report per Specification 6.12.2.6.
The new location shall be added to the radiological environmental monitoring program within 30 days, if possib1n. The sampling location having the lowest calculated dose commitment (via the samn exposure pathway) may be doloted from this monitoring program af ter October 31 of the year in which this land use census was conducted.
l 4.30.2.4 The results of the land uso consus shall be included in the Annual Radiological Environmental Report.
s 4.30.2.5 The provisions of Specification 3.0.3 are not applicable.
* Broad Icaf vegetation sampling may be performed at the sito boundary in the direction sector with the highnst D/Q in lieu of the garden census.
* Broad Icaf vegetation sampling may be performed at the sito boundary in the direction sector with the highnst D/Q in lieu of the garden census.
4 J
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Amendment No. $$,JJE,                     110zz
Amendment No. $$,JJE, 110zz


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Radiological Environmental Monitoring 4.30.3           J.nirdabparators ComparlantLProgIAm Aimlitability : Applies to thn of f-site rnalochemistry laboratory.
=
QbJr.cilyni       To provide independent checks on the accuracy of the measurements of radioact.ivo matnrlal n environmental samples.
Radiological Environmental Monitoring 4.30.3 J.nirdabparators ComparlantLProgIAm Aimlitability : Applies to thn of f-site rnalochemistry laboratory.
Specificatiangi 4.30.3.1   Analyses shall be performed on rcdlonctivo materials supplied as part of Interlaboratory Comparison Program which has been approved by NRC.
QbJr.cilyni To provide independent checks on the accuracy of the measurements of radioact.ivo matnrlal n environmental samples.
4.30.3.2   With analyses not being performed as required above, report the corrective actions taken to prevent a re:urrence to the Commissica in thn Annual Radiological Environmental Report.
Specificatiangi 4.30.3.1 Analyses shall be performed on rcdlonctivo materials supplied as part of Interlaboratory Comparison Program which has been approved by NRC.
4.30.3.3   The results of analysos performed as part of the above required Interlaboratory Comparison Program shall bo included in tini Annual Radiological Environmental Report. pursuant to Specification 6.12.2.5.
4.30.3.2 With analyses not being performed as required above, report the corrective actions taken to prevent a re:urrence to the Commissica in thn Annual Radiological Environmental Report.
4.30.3.4   The provisions of Specification 3.0.3 are not applicabin.
4.30.3.3 The results of analysos performed as part of the above required Interlaboratory Comparison Program shall bo included in tini Annual Radiological Environmental Report. pursuant to Specification 6.12.2.5.
4.30.3.4 The provisions of Specification 3.0.3 are not applicabin.
l aim The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that Independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrato that the results are reasonably valid.
l aim The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that Independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrato that the results are reasonably valid.
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Amendment No. $$,JJE,                   110bbb}}
Amendment No. $$,JJE, 110bbb}}

Latest revision as of 01:32, 15 December 2024

Proposed Tech Specs Re Limiting Condition for Operation 3.0.4 & Surveillance Requirement 4.0
ML20077G917
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 06/27/1991
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20077G913 List:
References
NUDOCS 9107030162
Download: ML20077G917 (44)
v • d • e


Text

. - -.. _ _

i e

l PROPOSED TECHNICAL SPECIFICATION CIIANGES 9107030162 910627 PDR ADOCK 03000313 P

PDR

~

3.

LIMITING CONDITIONS FOR OPERATION 3.0 LlHITING CONDITION FOR OPERATION (GENERAL) 3.0.1 The Limiting Conditions for Operation requirements shall be applicable during the REACTOR OPERATING CONDITIONS or other conditions speciflod for each specification.

3.0.2 Adherenco to the requirements of the Limiting Condition for Operation within the speciflod time interval shall constituto compliance with the specification.

In the event the Limiting Condition for Operation is restored prior to expiration of the specified time interval, no further actions need be taken.

3.0.3 When a Limiting Condition for Operation is not mot, except as provided in the associated Action requirements, within one hour action shall be initiated to place the unit in an OPERATING CONDITION in which the Specification does not apply by placing it, as applicable, in:

1.

At least 110T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 2.

At 1 cast il0T SiluTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 3.

At least COLD SilUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Whero correctivo measures are completed that permit operation under the Action requirements, the Action may be taken in accordance with the specified time limits as measured from the time of failuro to meet the Limiting Condition for Operation.

Exceptions to those requirnments are stated in the individual Specifications.

3.0.4 Entry into a REACTOR OPERATING CONDITION or other specified condition shall not be made when the conditions of the Limiting Conditions for Operation are not met and the associated action requires a shutdown if they are not met within a specified time interval.

Entry into a REACTOR OPERATING CONDITION or other specified condition may be modo in accordance with Action requirements when conformance to them permits continued operation of the facility for an unlimited period of timo. This provision shall not prevent passage through or to REACTOR OPERATING CONDITIONS as required to comply with Action requirements.

Exceptions to these requirements are stated in the individuni specification.

Amendment 57 15a

LIMITING CQ!iDITION FOR_OfEEATION reontinued) 3.0.5 When a system, subsystem, train, component or device is determined to be inoperablo solely because its emergency power source is inoperable, or solely because its normal power source is luoperable, it. may be considored OPERABLE for the purpose of satisfying the requirements of its applicablo Limiting Condition for Operation, provided:

(1) its corresponding normal or omorgency power source is OPERABLE and (2) all of its redundant systems (s),

subnystem(s), train (s), component (s) and device (s) are OPERABLE; or likewise i

satisfy the requirements of this specification. Unless both conditions (1) and (2) are satisfied, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> action shall bo initiated to place the unit in an OPERATING CONDITION in which the applicable Limiting Condition for Operation does not apply by placing it, as applicable, in :

1.

At 1 cast il0T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

2.

At least il0T SilUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 3.

At least C01.D SilVTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

This Specification is not applicabic in Cold Shutdown or Refueling Shutdown.

BASES 3.0.1 through 3.0.4 Establish the general requirements applicable to Limiting Conditions for Operation. These requirements are based on the requirements for Limiting Conditions for Operation stated in the Code of Federal Regulations, 10 CFR 50.36(c)(2):

" Limiting conditions for operation are the lowest functional capability or performance invols of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensoo shall shutdown the reactor or follow any remedial Action permitted by the Technical Specification until the condition can be met."

3.0.1 Establishes the Applicability statement within each individual Specification as the requirement for when (i.e., in which operational modos or other specified conditions) conformance to the Limiting Conditions for Operation is required for safe operation of the facility.

The Action requirements establish those remedial measures that must be taken within specified time If mits when the requirenents of a Limiting Condition for Operation are not mo'..

There are two basic types of Action requirements. The first specifies the remedial measures that permit continued operation of the facility which is not further restricted by the time limits of the Action requirements.

In this case, conformance to the Action requirements provides an acceptablo level of safety for unlimited continued operation as long as the Action requirements continue to be met. The second type of Action requirement specifies a time limit in which conformance to the conditions of the Limiting Condition'for Operation must be met.

This time limit is the allowable outage time to Amendment No. 57, 15b

a a

BASES (continundl restore nn inoperable system or component to OPERABLE status or for restoring paramotors within specified limits.

If these Actions are not completed within the allowabic outago time limits, a shutdown is required to place the facility in a modo or condition in which the Specification no longer applies.

It is not intended that the shutdown Action requirements be used as an operational convenienco which permits (routino) voluntary removal of a system (s) or component (s) from service in lieu of other alternativos that would not result in redundant systems or components being inoporabin.

The specified time limits of the Action requirements are applicable from the point in time it la identiflod that a Limiting condition for Operation is not met.

The Limo limits of the Action requirements are also applicabin when a system or t.omponent is removed from service for surveillanco testing or investigation of operational problems.

Individual Specifications may includo a specified time limit for the completion of a Survoillance Requirement when equipment is removed from servico, in this caso, tho allowable outage timo limits of the Action requirements are applicable when this limit expires if the surveillance has not been completed.

When a shutdown is required to comply with Action requirements, the plant may have entered a mode in which a new specification becomes applicabin. In this case, the time limits of the Action requirements would apply from the point in time that the now specification becomes applicablo if the requirements of the Limiting Condition for Operation are not met.

3.0.2 Establishes that noncompliance with a Specification exists when the requirements of the Limiting Condition for Operation are not mot and the i

associated Action requirements have not been implemented within the specified time Interval. The purposo of this specification is to clarify that (1) implementation of the Action requirements within the specified time interval constitutes compliance with a Specification and (2) completion'of the remedial measures of the Action requirements is not required when compliance with a Limiting Condition for Operation is restored within the-time interval specified in the associated Action requirements.

3.0.3 Establishes the shutdown Action requirements that must be implemented when a Limiting Condition for Operation is not met and the condition is not specifically addressed by the associated Action requirements.

The purpose of this specification is to delineate the time limits for placing the unit in a safe shutdown mode when plant operation cannot be maintained within the limits for safe operation defined by the Limiting Conditions for Operation and its Action requirements.

It is not inte.eded to be used as an operational convenience which permits (routine) voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

Ono hour is allowed to i

prepare for an orderly shutdown before initiating a chango in plant operation.

This time permits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of thn electrical grid. The time limits speciflod to reach lower modes of operation permit the shutdown to proceed in a controlled and orderly l

Amendment No. 57, 15c t

4 l

BASIS LconLDwed) manner that in well within the specified maximum cooldown rato and within tho cooldown capabilition

<>f the facility assuming only the minimum required i

equipment is Op!'RAltl E.

This reduces thermal sticases on components of tho primary coolant system and the poter.tial for a plant upset that could

{

challenge safety systems under conditions for which this specification t

applies.

q If remedial measures permitting limited continued operation of the facility l

under the prov!sions of the Action requirements are completed, the shutdown l

l may be t erminat ed.

The Limo limitt. of the Action requirements are apolicabic

)

from the point in timo thorn was a failuro to meet a Limiting Condition for Operation. Therefore, the shutdown may he terminated if the Action requirements have been mot or the timo limits of the Action requirements have not expired, thus providing an allowanen for the completion of the require:1 1

Actions.

The timo limit s of Specificat ion 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the plant to bn in thn C0hD SilUTDOWN condit ton when a shutdown is required during the POWER mode of operatien.

If the plant is in a lower modo of operation when a shutdown is required, the timo limit for reaching the next lower modo of operation t

applies.

However, if a lower modo of operation in reached in less tien than allownd, the total allowable timo to reach COLD 8110TDOWN or other applicabic l

modo, is not reduced.

For examplo, if Il0T STANI)!!Y la reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, tho timo allowo:1 to reach il0T SilVTODWN is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> becauso the total timo to reach Il0T S110Tr)0VN is not reduced from tho allowahic limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

Thereforo, if remedial measures are completed that would permit a return to p0WER operation, a penalty is not incurred by having to reach a lower mode of operation h less than the total time allowed.

The sano principle applion with regard to the allowable outogo time limits of the Action requirements, if compliance with the Action requirements for one specification results in entry into a modo or condition of operation for another specification in which the requirements of the Limiting Condition for Operation cro not mot. If tha new specificatico hocomes applicable in loss time than specified, the dif ference may be added to th3 allowable outage timo limits of the second specificatian. However, the allowable outage timo limits of Action requirements for 4 higher mode of operation may not be used to extcad the allowablo outage time that is applicable when a himiting Condition for Operation in not met in a lower mode of operation.

The shutdown requirements of Specification 3.0.3 do not apply in COLD SliUTDOWN and REl'UELING SHUTDOWN, becauno the Action requirements of individual specifications dnfine the remedial measurns to be taken.

3.0.4 Establis.hos limitations on modo changes when a Limiting Condition for Operation is not met.

It precludes placing the facility in a higher modo of operation when the requirements for a Limiting Condition for Operation are not mot and continued noncomplianco to theno conditions would result in a shutdown to comply with the Action requirements ;f a changn in modon worn permitted.

The purpoio of this specification is to ensure that facility operation is not.

A acndment No.

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e RASES (continued) initiated or that. higher modes of operation are not entered when corrective act ion is being taken to obtalu compliance with a Specification by rostoring equipment to OPERABLE status or parameters to specified limits.

Compliance with Action requirements that permit continued operation of the facility for an unilmited period of timo provides an acceptable level of safety for continued operation without rmnrd to the status of the plant before or af ter a modo change.

Tho ro foro, in this caso, if the requirements for continued operation have bocn met in accordance with the requirements of the specification, then entry into that modo of operation in permissible.

The provisions of this specificat lon should not, however, be interpreted an endorsing the failure to exercise good practico in restoring systems or components to OPERABLE status before plant startup.

When a shutdown is required to comply with /ction requirements, the provisions of Specification 3.0 4 do i.ot apply because they would delay placing the f acility in a lower modo of operation.

For the purpose of compliance with this specification the term ' shutdown' is defined as a required reduction in the REACTOR OPERATING CONDITION.

3.0.5 Dolineaton what additional conditiona must bo satisfied to permit operation to continue when a normal or emergency power source is not OPERABLE.

It specifically prohibits operation when one division is inoperable because its normal or emergency power source is inoperable and a system, subsystem, train, component or device in another division is inoperable for another reason.

The provisions of this specification permit the Limiting Condition for Operation statements associated witn individual systems, subsystems, trains, components or devices to be conristent with the Limiting Condition for l

Operation statements of the associated electrical power sourco, it allows operation to be governed by the time limits of the bimiting Condition for l

Operation for the normal or emergency power sourec, not the individual l

Limiting Condition for Operation statements for each system, subsystem, train, component or device that in determined to be inoperable solely because of tho i

inoperability of its normal or emergency power sourco.

For examplo, Specification 3.7.2.C provides for a 2 day out-of-service time when one emergency diesel generator is not OPERABLE.

If the definition of OPERADLE were applied without consideration of Specification 3.0.5., all systems, subsystems, trains, components and devices supplied by the inoperable emergency power source would also be inoperable.

This would dictato invoking the applicablo Action statements for each of the applicablo Limiting Conditions for Operation.

However, the provisions of Specification 3.05 permit the timo limits for continued operation to Amendment No.

15e

~ _ _ _ -. - - - - _. - - _ _ -

e e

3.1.2 hniud1AUDat_)ls AinpuAnd_C901d2xn_ Limit & dona EPRCLiLCAUDD 3.1.2.1 Ilydro Test s J

For thermal stendy state system hydro tests, the system may be i

prossiirized to the limits set forth in Specification 2.2 when there arn funt assemblics in the coro, under tho provisions of 3.1.2.3, nnd to ASHE Cmlo limits when no fuel nssemblics are present provided thn reactor coolant systen. limits nro to the right of and bolow thn limit linn in Figure 3.1.2-1.

The provisions of Specification 3.0.3 nro not applienble.

3.1.2.2 I,enk Tests I,enk tests requir ed by Specificat ion 4.3 shall bn conducted under the provision of 3.1.2.3.

'the provlsions of Specification 3.0.3 nro not applienbin.

3.1.2.3 The reactor coolant pressuro and the system hentup and cooldown rates (with the except ion of the pressurizer) shall be limited in accordance with Figurn 3.1.2-2 nnd Figure 3.1.2-3, and are as follows:

llentup:

Allowable combinntions of pressure and temperaturn shall be to the right of and below the limit line in Figuro 3.1.2-2.

The hentup rates shall not exceed those shown in Figure 3.1.2-2.

Cooldown:

Allownble combinations of pressurn and temperature for a specific cooldown shn11 be to the right of and bolow the limit linn in Figurn 3.1.2-3.

Cooldown rates shall not excend thoso shown in Figuro 3.1.2-3.

3.1.2.4 Thn secondary side of the stnnm generator shall not be pressurized abovn 200 psig if thn temperature of the steam generntor shell is bolow 100F.

3.1.2.5 The pressurizer hentup and cooldown ratos shall r.ot exceed 100F/br. The spray shall not be used if the temperaturn dif ference between the pressurizer and the spray fluid is grentor than 430F.

3.1.2.6 With the limits of Specifications 3.1.2.3 or 3.1.2.4 or 3.1.2.5 exceeded, rostoro the temperaturo and/or pressure to within the limit within 30 minutes; perform an engineering ovaluation to determino the of fects of the out-of-limit condition on the frncturn toughness propertins of the Ronctor Coolant Systchi; determino that the Reactor Coolant System remains neceptable for continued opnrations or be in at lennt.Il0T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce the RCS Tnvg and pressurn to less than 200F and 500 psia, respectively, within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

I Amendment No. 12,1f,, U,

18

. ~. _ - _ _

e 1

3.1.2.7 Prior to reaching fifteen effective full power years of operation, Tigures 3.1.2-1, 3.1.2-2 and 3.1.2-3 shall be updated for the next service period in accordance with 10CFR50, Appendix G, Sect. lon V. fl.

The service period shall be of sufficient duration to permit thn scheduled evaluation of a portion of the surveillance data scheduled in accordance with Speciffiation 4.2.7.

The highest predicted adjusted reference temperaturn of all the boltlino region materials shall be used to determinn the adjusted reference temperaturn at the end of thn service pnriod.

The basis for this prediction shnl1 be submitted for NRC staf f review in accordance with Specification 3.1.2.8.

The provisions of Specification 3.0.3 arn not applicablo.

3.1.2.8 The ugxlated proposed technical specifications referred to in 3.1.2.7 shall be submitted for NRC review at least 90 days prior to thn end of the servien period. Approprinto additional NRC review time shall be allowed for proposed t echnical specifications submitted in accordanen with 10 CFR Part 50 Appendix G.

Section V.C.

3.1.2.9 With thn exception of ASME Section XI testing and when the coro florxl tank in depressurized, during a plant cooldown the core flood tank discharge valves shall be closed and the circuit breakers for the motor operators opened beforo depressurizing the ret.ctor coolant system below 600 psig.

3.1.2.10 With the exception of ASME Section XI testing, fill and vent of the reactor coolant system, emergency RCS makeup and to allow maintenance of the valves, when the reactor coolant temperature in less than 280'P, the liigh pressure injection motor operated valves shall be closed with their opening control circuits for the motor operators disabled.

3.1.2.11 The plant shall not be oporated in a water solid condition when the RCS pressure boundary in intact except as allowed by Emergency Operating procndures and during System flydrotest.

h Amendment No. 5/, f,/. 75, 1/f, 18a ARKANSAS - UNIT 1 IM,

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e 3.5.4 inC91c_InaLInttent atien hvnLichkk1Lt1 Applies to tho operability of the incore instrun,cntation system.

Dhlest1Yn To specify the functional and operational requirements of the incore instrumentation nystom.

Spasification Abovo 80 percent of operating power dotormined by the reactor coolant pump combination (Tablo 2.3-1) at least 23 individual incoro detectors shall be operable to check gross core power distribution and to assist in the periodic calibration of the out-of-coro detectors in regard to the core inhalance trip limits. The detectors shall be arrnnged as follows and may be a part of both basic arrangements.

3.5.4.1 Axial Imbalanco A.

Three detectors, one in each of throc strings shall lie in the same axial pleno with one plano in each aalal corn half.

B.

The axial planes in cach core half shall be symmetrical about the coro mid-plano.

C.

The detector shall not have radial symmetry.

3.5.4.2 Radial Tilt A.

Two sota of four detectors shall lie in each corn half.

Each set of four shall lie in the same axial plano.

The two nota in the same coro half may lie in the same axial plano.

B.

Detectors in the same plano shall havo quarter cora radial symmetry.

With the incoro detector system inoperablo, do not uno the system for the above applicable monitoring function.

The provisions of Specification 3.0.3 are not applicablo.

DannA A system of 52 incore flux detector assemblics with 7 detectors por assembly has been provided primarily for (uel management-purposes.

The system includes data display and record functions and is also used for out-of-core nuclear instrumentation calibration and for coro power distribution verification.

A.

The out-of-core nuclear instrumentatica calibration includes:

1.

Calibration of the split detectors at initial reactor startup, during the power escalation program, and periodically thorca f t er.

Amendment No. 51, 51

. - ~. - -.

1 3.5.5 Elte. DelcAtlan_InsitumentAtion App.11cah11113 This specification applies to fire detection instrumentation 111xed within I

firn arens containing safety related equipment or circuitry. er the purposon of protecting that safety related equipment or circuitry.

QMentirn To provido immediato notification of fires in areas t.hnro there exists a potential for a fire to disable safety rnlated systems.

Eltecifinallon j

3.5.5.1 A minimum of 50% of the heat /smoko detectors in the locations specified in Tabic 3.5-5 shall be operable.

3.5.5.2 If less than 50% of the fire detectors in any of the locations designated in Table 3.5-5 are operable, within onn heur esta-blish a fire wat ch patrol to inspect the rrone(s) with the in-operable instrument (s) at. least onen per hour and restore the equipment. to operable status within 14 days, or prepare and submit i

a Special Report to the Commission pursuant to Specification 6.12.5 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring thn instrument (s) to operablo status. Thn provisions of Specification l

3.0.3 are not applicable.

IlluLcA Tha various datoctors provide alarms that notify the operators of the existenen of a fire in its early stages thus providing early initiation of firn protection.

The detectors in tho main and auxiliary control rooms also provido automatic fire protection initiation.

The detectors required to be operable in the various areas represent one half of those installed.

Operability of the fire detection instrumentation ensures that operable warning capability is available for the prompt detection of fires.

This capability is required in order to detect and locato fires in their early

stages, prompt detection of fires will reduce the potential for damagn to safety related equipment.

In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire pattols in the affected areas (s) is required to provido detection capability until the inoperable instrumentr.tfon is restored to operability.

l l

4 Amendment No. JP, 43. U, / / fi 53d l

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o 3.5.6 RadipocL1Yu LigulLEfihtenLinstLunentat.lun britlicahility: During relcanen via this pathway.

OhicsLivni To provide instrumontation for radioactivo liquid releason.

Sitell1.1.c.aLioni 3.5.6.1 Thn radioactivo 11guld of fluent monitoring inst rumentation shown in Tablo 3.5.6-1 shall be operable with their alarm / trip actrointa set to onnurn that thn limits of specification 3.25.1.1 are not exccoded.

3.5.6.2 With a ntm/ trip netpoints lens conservative than required by thn abovn speciffeatlon, immediately suspend the release of radioact ive liquid of fluents monitored by thn af fected channni, until the netpoint in changed to an acceptably conservat.tvo value.

3.5.6.3 With less than the minimum number of channels operable, take the action shown in Table 3.5.6-1.

Return tho instruments to operablo statun within 30 days or, in lieu of eny othnr report, explain.in thn next Somiannual Radioactivo Effluent Releann Report why the inopernbility was not corrected.

3.5.6.4 The provinfonn of Specification 3.0.3 are not applicabin.

l llaarni Thn radioactiv, Ifquid effluent inst rumentation in provided t o n.Onitor and control, an applicab'., the releasen of radioactivo matertain in liquid 4

offluents during actual or potential releancs.

Tho alarm / trip notpoints for these instrument s shall be cal:ulated in accordance with the methods in t he ODCH to ensure that thn nlarm/ trip will occur prior to exceeding the limits of 10 CFR Part 20.

i Amendment No. ff, JJf,

'53f

~~._. _ __._

e o

3.5.7 H ad ina c th c_CdutemuLtillut at_1 nitn acat ALloa Arn11cohilitsi An shown in Tabin 3.5.7-1.

Ohjestlyni To provide itoiitromontntion for rndtonctivo gaseous releases.

EPcski.LCALloni 3.5.7.1 The rndionctivo gasecun of fluent monit oring inst rumentnt ion shown lei Table 3.5.7-1 shall be operabin with their ntnrm/ trip notpoints set to ensurn that the limits of Specification 3.25.2.I atc not exceeded.

3.5.7.2 With a channel nintm/ trip sotpoint lens conservative than required, declaro the channel inopoinble.

I 3.5.7.3 With loss than the minimum number of chant als operable, take the action shown in Tablo 3.5.7-1.

Return t he instruments to operablo status within 30 days or, in lieu of any other report, explain in the next Seminnnunt Radioactivo Effluent Ec1caso Report why tho inopornbility was not corrected.

3.5.7.4 The provisions of Specificat ton 3.0.3 nrn not applicable.

l Litcal The radioactive gaseous of fit ent instrumentation in provided to monitor and control, as applicable, the relenses of radioactivo materials in gescous affluents during actual or poto.itial releases. The alarm / trip sotpoints for these instruments shall be calculated in accordance with methods in the ODCH to ensure that the alarm /t rip will occur prior to exceeding the limits of 10 CTR Part 20.105.

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l Amendment No. ff>, JJE, 531 1

1

{

_, _ _.. _ _.. _. ~ _, _ _ _ -. _

e 3.7.2 A.

Thn specifications in 3.7.1 may be modified to allow one of the following conditions to exist af ter the reactor has been heated above 200F, Except as indicated in the following conditions, if any of thesn conditions are not mot, a hot shutdown shall be initiated within 12 houis.

If the condition is not clenrod within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be brought to cold shutdown within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

B.

In the event that one of the offsite pownr sources specified in 3.7.1. A (1 or 2) is inoperablo, reactor operation may continue for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the availability of the dicsol generators is immediately verified.

C.

Either one of the two dicsol generators may be inoperable for up to 7 days in any month provided that durlag such 7 days the operability of t he remaining diesel gennrator is demonstrated immediately and daily thereafter, thorn are no inoperable ESP c.omponnnts associat ed with the operablo dicsol generator, and provided that the two sources of of f-site power specified in

)

3.7.1.A(1) or 3.7.1.A(2) are available.

D.

Any 4160V, 480Y, or 120V switchgear, load center, motor cont rol center, or distribution panel in one of the two ESP distribution systems may bo inoporable for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, provided that the operability of the diesel geacrator associated with the operablo ESF distribution system is i

demonstrated immediately and all of the components of the operable distt ibution system are operable.

If the ESP d btribution system is not returned to service at the end of the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, Specification 3.7.2.A shall apply, l

E.

Two station battery chargers may bo inoperahlo for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, after which Specification 3.7.2.A shall apply.

F.

One of the two station hatteries and the associated distribution system may be inoporabin for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> provided that thorn are no inoperable safety rnlated components associated with the remaining station battery which are redundant to the inoperable stat.Jon battery and the operability of the diesel generator is verified immediately.

If the battery is not returned to service at the end of the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period, Specification 3.7.2.A shall apply.

G.

Two control power sources from the plant to the switchyard and the attendant distribution system may be inoperable for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, after which Spncification 3.7.2.A shall apply, 11.

If the requiremnnts of Specification 3.7.1.0 cannot be met, nither:

lace all Startup Transformer No. 2 feeder bronkers in (1) p' pull-to-lock" within I hour, restore the inoperable interlocks to operablo status within 30 days, or submit within 30 days a Special Report. pursuant to Specification 6.12.5 outlining the cause of the failure, proposed correctivo Action and schedule for impicmentation; or (2) apply thn action requirements of Table 3.5.1-1, Note 14.

P Amendment No. ff, JJE, 57

3.8.6 During the handling of irradiated fuel in the reas. tor building, at least one door on t he personnel and emnrgency hntches shall be closed.

The equipment hatch cover shall be in place with a minimum of four bolts securing the cover to the sealing sutfaces.

3.8.7 Isolation valves in lines containing automatic containment isointion valves shall be operable, or at least one shall be closed.

1 3.8.8 When two irradiated fuel assemblics are being moved simultaneously by the bridgns within the fuol transfor canal, a minimum of 10 font separation shn11 he raintained between the assemblics at all times.

3.8.9 If any of the abovo speciflod limiting conditions for fuel loading and "nf ueling are not met, r..ovement of funi into thn reactor core shall ceaset Action shall bo initiated to correct the conditions so that the specified limits aro mot, and no operations which may increase thn reactivity of the core shall bo mado. The provisions of Specification 3.0.3 are not. applicabin.

l 3.8.10 Tho reactor building purge isolation system, including the radiation monitors shall bo tested and verified to be operable within 7 days prior to refueling operations.

The provisions of Specification 3.0.3 aro not applicablo.

l 3.8.11 Irradiated fuel shnll not be removed from the reactor until the unit has been subcritical for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

In the event of a completo core offlond, a full core to be discharged shall be subtritical a minimum of 175 hours0.00203 days <br />0.0486 hours <br />2.893519e-4 weeks <br />6.65875e-5 months <br /> prior to dischargo of more than 70 assemblics to the spent fuel pool. The provisions of Specification 3.0.3 at o not npplicabic.

l 3.8.12 All fuel handling in the Auxiliary Building shall coaso upon notification of the issuance of a tornado watch for Pope, Yell, Johnson, or Logan countles in Arkansas.

Fuel handling operations in progress will be completed to the extent necessary to placo the fuel handling bridge and crane in their normal parked and locked position.

Thn provisions of Specification 3.0.3 are not l

applicabin.

3.8.13 No loaded spent fuel shipping cask shall be carried above or into the Auxiliary Building equipment shaft unless atmosphoric disporsion conditions are equal to or bottor than those produced by Pasquill Type D stability accompanied by a wind velocity of 2 m/sec.

In addition, the railroad spur door of the Turbinn Building shall be closed and the fuel handling aron ventilation system shall bo in operation. The provisions of Specification 3.0.3 are not l

applicable.

3.8.14 Loads in excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the storage pool. The provisions of Specification 3.0.3 are not.nppl.icabin.

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i Amendment No. 10,J/,/6,5/,/6, 59

i O

o 3.8.15* The spent fuel shipping cask shall not bn carried by the Auxiliary Building crano pending thn ovaluation of the spent fuel cask drop accident and the cranc design by AP&h and NRC review and approval.

The l

provisions of Specification 3.0.3 are not applicabin.

l 3.8.16 Storngo in the spent fuel pool shall bn restricted to fuel assembifes having inittal enrichment less thnn or equal to 4.1 w/o 11-235.

The provisions of Specification 3.0.3 nro not applicable.

l 3.8.17 Storago in Region 2 (as shown on rigurn 3.8.1) of the spent feel pool shall be further restricted by burnup and enrichment limits specified in Figuro 3.8.2.

In the event a checkerboard storage configuration in deemed necessary for a portion 01 Region 2. vacant spaces adjacent to t he f aces of any fuel assembly which does not meet the Region 2 burnup i

criteria (non-restricted) shall bn physically blocked before any such fuel assembly may be placed in Region 2.

This will prevent inadvertent fuel assembly insertion into two adjacent storage locations. Tbo provisions of Specification 3.0.3 are not applicabin.

3.8.18 The boron concentration in the spent fuel pool shall be maintained (at all times) at greater then 1600 parts por million.

Easta Detailed written procedures will bn available for use by refueling personnel.

These procedures, thn above specifications, and thn design of the fuel handling equipment as described in Section 9.6 of the PSAR incorporating built-in interlocks and safety features, providn assurance that no incident could occur during the refueling operations that would result fu a hazard to public health and safety, if no change is being made in coro geometry, one flux monitor is sufficient.

This permits maintenanco on the instrumentation. Continuous monitoring of radiation invols and neutron flux provides immediato indication of an unsafo condition.

The requirement that at least one decay heat removal loop bn in operation ensures that (1) sufficient cooling capacity is available to remove decay heat and maintain the water in thn reactor pressure vossol at the refueling temperature (normally 140*F), and (2) sufficient coolant circulation is maintained through the reactor core to mingzo the of fects of a boron dilution incident and prevent boron stratification The requirement to have two decay heat removal loops operable when thoro is less than 23 feet of water above the core, ensures that a single failure of the operating decay heat removal loop will not result in a complete loss of decay heat removal capability.

With the reactor vessel head removed and 23 foot of water above the core, a large heat sink is availabin for coro cooling, thus in the event of a failure of the operating decay heat removal loop, adequato timo is provided to initiato emergency procedures to cool the corn.

The shutdown margin indicated in Specification 3.8.4 will keep coro j

subcritical, even with all control rods withdrawn from the coro Although the refueling boron concentration is sufficient to maintain the c. ore k 5 0.99 if all the control rods woro removed from the core, only a few controli>ds will be removed at nny one timo during fuel shuffling and Note:

  • A one timo exception to 3.8.15 is granted for the period of July 13, 1987 through August 12, 1987.

Amendment No. J/,75,J/,/f>,JP/,

59a J

j

e s

3.12 HISCEl.l.ANEOUS RAD 10 ACTIVE MATF.RI A!.S SOURCES App 11cabtL113 Applien to byproduct, sourco, and special nuclear radioactivo material Rources.

t Qbjesthi To assure that 1cakagn f rom byprcxtuct, source and Ppocini nuclent radionetivo material sources does not exceed allowablo limitn.

Snecification 3.12.1 The source lenkage test performed pursuant to Specification 4,14 shall be capable of detect ing the pror.ence of 0.005 901 of rndioactiva materint on the tent anmple.

If the test reveals the presenen of 0.005 pCi or mero of removnbic contamination, it shall immediately be withdrawn from uno, decontaminated and repaired, or bo disposed of in accordnnce with Comminnion regulations.

Senled sources are nxempt from such leak tents when the sourco contains i

100 pCi or less of beta and/or ramma emitting materint or 5 pCi or loan of alpha emitting materin1.

The provisions of Speciffention 3.0.3 are not applicable.

l 3.12.2 A Specini Report shall be prepared and submitted to the Commission pursuant to Specification 6.12.5 within 90 days if sourco leakago tents reveal the prenonce of ;0.005 microcurlen of removabin i

contaminntlon.

3.12.3 A complete 2nventory of licensed radioactive materials in possession shall be maintained current at all times.

i i

l Amendment No. J)l,55,5/,JJE, 66b

]

1

_. _. =

.. _. _ _. _ _, _.. _. _ _ _ ~

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3.15 10Eh IIANDI. LNG AREA VENT 1 HAT 10N SYSTEM i

bpplicabnity Applies to the operability of thn fuel handling aren ventflation system.

i i

Oldtclite To ensure that the fuel handling arna ventilation system will perform within acceptable levnis of officiency and reliability.

StecLLication i

3.15.1 The fuel handling area ventilation system shn11 be in operation whenever irrndfated fuel handling operations are in progress in the fuel handling area of the auxiliary building and shall have the following performanco capabilities:

The results of the in-place cold DC? and halogenated hydrocarbon a.

tests at design flows (110%) on llEPA i11 tors and charcon1 adsorber j

bnnks shall show 2 99% DOP removal and b 99% halogenated hydrocarbon removal.

b.

The results of laboratory entbon samplo analysis shall show 2 90%

radionctive mothyl fodido removal at a velocity within 120% of system denign, 0.05 to 0.15 mg/m' inlet methyl lodido concentration, 2 70% R.il and 2 125F.

Fans shall be shown to operate within 110% design flow.

[

c.

d.

The pressure drop across the combined llEPA filters and charcoal adsorber banks shall be less than 6 inches of water at system design flow rate (110%).

e.

Air distribution shall be uniform within 120% across llEPA filters and charcoal adsorbors when tested initially and after any unintenanen or testing that could affect the air distribution within the funi handling arna ventilation system.

3.15.2 If thn rnquirements of Specification 3.15.1 cannot be met, irradiated fuel movement shall not be started (any irradiated fuel assembly movement in progress may be cornpinted). The provisions of Specification 3.0.3 are not applicabin.

l BASIA The fuel handling aren ventilat.fon system is designed to filter the auxiliary building atmosphero during fuel handling operations to limit the relenso of activity should a fuel handling accident occur. The system consists of ono

)

circuit containing two exhaust fans and a flitor train.

The fans are redundant and only ono is required to be operating. The filter train consists of 1 profilter, a llEpA filter and a charcoal adsonber in series.

i l

Amendment No. JP,/f,51, 66g

~ - -, - -. -..

+

b 3.18 TIRE SUPPRESSION SI'RINEl,ER SYSTEM i

Arrlhak11h3 i

This specification applies to thn following firn suppression sprinkler systems protect ing safety related arcan:

n.

Each of the four tonctor building cablo penetration arens.

b.

Each of the four cablo penotration rooms.

c.

Each of the two escrgency dicsol gennrator rooms, d.

Cable spreading room.

c.

Each of thn two diesel generntor fuel vaults.

4 f.

lin11way El 372 (Zonn 98-J).

g.

Condensate demineralir.cr aren.*

i Oldesihti To assure that (fro suppression is avn11able to safety related equipment.

located in the above-listed areas.

Encs.if.ic.011nti 3.18.1 The above-listed sprinkler systems shall be operable at all times.

3.18.2 With one or more of the above-list ed sprinklor systems inopernble, establish a cont inuotas fire watch (or operable smoke and/or heat detection equipment with control room alarm) with backup firo suppression equipmont for thn applicable arca(s) within one hour.

Restore the system (s) to operable status within 14 days, or preparo and submit a Special Report to the Commission pursuant. to Specification 6.12.5 within the next 30 days outlining the act.fon taken, the cauno of the inoperability and the plans and schedule for restoring the system (s) to operable status.

The provisions of Spect ficst ion 3.0.3 are not appl (cabin.

l EaaftE Safety related equipment. located in various areas is protected by sprinkler systems. The operability of thesn systems ensures that adequate fire supprossion capability is available to confino and extinguish a fire occurring in thn applicable areas.

In the event a system is inoperable, alternato backup firn fighting equipment or operable detection equipment is required to be modo availablo until the inoperable equ;pment is restornd to servico.

j

  • To be implemented no later than July 30, 1979.

Amendment No. /$,4,J/,JJf, 66n l

1 l~

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3.19 CONTROL ROOM AND AtlX1hiARY CONTROL ROOM llA!,0N SYSTEMS Apnlicahillis Thin specification applies to the llalon systems utilfr.ed as the firo I

suppression system for the cont rol room and auxiliary control room.

Oldesthe To assurn that fire suppression is available to the snfoty related equipment in the control room and auxiliary control room.

Spnc.lL! cat.Lon 3.19.1 The three control room and auxiliary coatrol room llalon systems shall ho operablo at all timon with the storage tanks having at least 957. of full charge weight and 907. of full chargo pressuto.

3.19.2 With any of the control room and auxiliary control room llalon systems inopornble, establish backup fire suppression equipment for the affected area within ono hour.

Restore the system (s) to operable status within 14 days, or preparo and submit a Special Report to the Commission pursunnt to Specif f ention 6.12.5 within i

30 days outlining the actions taken, the cause of the inopernbility, and the plans and schedule for restoring the system to operablo status.

The provisions of Specification 3.0.3 are not applicablo.

l l

Baans Safety related circuitry located in portions of the control room and auxiliary control room is protected by the llalon systems. The operability of those systems ensures that adequnto firo suppression capability is availablo to confine and extinguish n fire occurring in the control room or the auxiliary control room.

I In the event that the system (s) is inoperahic, alternate backup fire fighting equipment is required to be made available in the affected aren until the i

inoperable equipment is restored to servico.

i 1

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4 i

.r Amendment No. /A, 51, JJ6 66o i

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3.20 plRE 11081: STATIONS hvplicahtilts This specification applies to firo hose stations protecting arens containing safety related equipmnnt.

UkkC&LhD To assure that manual itre suppression enpability is available to all safety l

related equipment.

Specificath n j

f 3.20.1 All fire hoso stations protecting areas containing safety related j

equipment shall bo operablo whenover the equipment in these areas in required to be operable.

I 1

]

3.20.2 k'ith one or more of the fire hoso stations of 3.20.1 inoperable, routo

{

nn additional equivalent capacity fire hose to the unprotected arca(s) irom an operabic hose station within one hour. The provisions of 4

Speciffention 3.0.3 are not applicable, g

1 i

Ratta i

j The operability of the firo hose stations adds addit ional assurance that j

adequat e fire supprossion capability is available to confino and extinguish fires occurring in nny portion of the facility where safety related equipment is located.

In the event that portions of this system are inoperable, backup fire hose oquipment is required to be made available in the affected trea(s) until the inoperablo equipment is restored to service.

l l

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i

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1 i

i t

i Amendment No. f$,f/,

66p i

. ~

l 3.21 FIRE BARRIERS i

Apn1hnh11Ry i

This specification applies to fire barriors separating safety related firo areas or redundant snfo shutdown systems required in the event of a fire.

7 DbhtthD To assure that fire bnrriers separating safety related firo areas or redundant safe shutdown systems perform their separation funct.fon.

Specificatinti 3.21.1 All fire barriors separating safety related firo areas or redundnnt safe shutdown systems shall be operable at all timos.

3.21.2 With one or more of the required fire barriors inoperable, i

within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, either a.

Establish a continuous fire watch on at least one sido of the a f fect ed firo barrior or, b.

Verify the operability of smoke and/or heat detection equipment with control room alarm on at least ot'o sido of the affected barrior and establish an hourly fire watch patrol.

3.21.3 The provisions of Specification 3.0.3 are not applicable.

BA1cA The operability of the firo barriors, including firo-rated walls; floors / ceilings; fire doors; firo dampers and ponotration seals, ensures that firon will be confined or adequatoly rotarded from spreading to adjacent. fire areas or to portions of redundant safe shutdown systems required in the event of a fire within the fire area.

This design feature minimir.os the possibility of a single fire rapidly involving several areas of the f acility prior to detection and extinguishment.

The firo barriors are a passivo olement in the facility fire protection program and are subject to periodic inspections. Safety related fire areas are the Control Room, the Switchgear Roors, the Battery Pooms, and the Diesel Generator Rooms.

Fire barriers also separato lubricating oil storago i

areas from other areas of the plant.

Fire barriers separating rodundant safe shutdown systems have bocn defined by analysis.

During periods of time when the barriors are inoperable, a continuous fire watch or operablo detection equipment with an hoJrly fire watch patrol is required to be maintained in the vicinity of the af fected barrior until the barrior is restored to operable status, s

Amendment No. Ap,57,Jff, 669 i

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e e

3.22 REACTOR llUll. DING PURGE FibTRATION SYSTEM ApplicahillLY This specification applies to the operability of the reactor building l

purge filtrntion system.

OhjeA11Ya To assure that. the reactor building purge filtration system will perform within acceptable levels of efficiency and reliability.

Sps%LLLLSLL011 3.22.1 The reactor building purge filtration system shall be operable whenever irradiated fuel handling operations are in progress in the reactor building and shall have the following performance capnbi1itles:

a.

The results of t he in-place cold DOP and halogenated hydrocarbon tests at design flows (110%) on llEPA filters and charcon) adsorber bnnks shall show 299% DOP removal and 299%

i hologenated hydrocarbon removal, b.

The resulte of laboratory carbon sample analysis shall show 290% radioactive methyl iodido removal at a velocity within 120% of system design, 0.05 to 0.15 mg/m' inlet methyl lodido concentrat f on, 2707 R. II, and 2125F.

c.

Fans shall be shown to operate wit.hin 110% design flow, d.

The pressure drop across the combined ilEPA filters and charcoal adsorber banks shall be less the.n 6 inches of water at system design flow rate (110%).

c.

Air distribution shall be uniform within 120% across llEPA filters and charcoal adsorbers when tested initially and after any maintennnce or testing that could affect the air distribution within the reactor building purgo filtration system.

3.22.2 If the requirements of Specification 3.22.1 cannot be met, either:

a.

Irradiated fuel movement shall not be started (any irradiated fuel assembly movement in progress may be completed); or, b.

Isolate the reactor building purge system.

3.22.3 The provisions of Specification 3.0.3 are not applicable.

l Bains The reactor building purge filtration system is designed to filter the reactor building atmosphere during normal operations for case of personnel entry into the reactor building.

This specification is intended to require the system operabic during fuel hnndling operations, if the system Amendment. No. H,U,

66r

e a

3.24 EXphOSlVE GAS MIXTURE Alm 11sah11113 Applies to the Wasto Gas System hydrogen / oxygen analyr.ers.

Oldenthe To prevent accumulation of cyplosivo mixture in the wastn gas system.

Spn Li h ALLou 3.24.1 The concentration of hydrogen / oxygen shall be limited in the waste gas decay tanks to Region "A" of Figurn 3.24-1.

3.24.2 When the hydrogen /exygnn concentration in any of the decay tenks enters Region "it" of Figure 3.24-1, correctivn action shall be taken to return the concentration values to Region "A" within 24

hours, 3.24.3 Thn provisions of Specification 3.0.3 arn not applicabin.

l Daics Those hydrogen / oxygen limit s provide reasonable assurance that r,o hydrogen / oxygen explosion conld occur to allow rupture of the waste gas decay tanks.

The hydrogen and oxygen limits are based on information.in NUREG/CR-2726 " Light Water Reactor ilydrogen Manual".

i Amendment No. ff,7),

66u

I e

e 3.25 RADIDACTIVE EFFl.UENTS 3.25.1 Eftdinactive Liquidlf1LuenLa 3.25.1.1 Concentratinn Applisab111111 At a11 tiaes Oldect.ly.ti To ensure that the limits of 10 CFR 20 arn mot.

Synrd Lit.!tLka w 3 25.1.1 A.

The concentration of radioactivo material rnleased to the dischargo canal shall be limited to the concentration specifind in 10 CFR Part 20 Appendix D, Tablo II, Column 2 for rndionuclides othnr than dissolved or oatrained noble gases.

For dissolved or entrainnd noble gases, the total concentration released shall be limited to 2 x 10J pCf/ml.

B.

Yith the conenntrction of radioactivo material relonsod exceeding the abovo limits, immediately initiato action to rostoro concentration to within limits and provido notification to the Commission within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

In lieu on any other report, preparc and submit a Special Report within 30 days pursuant to Specificat.lon 6.12.5 C.

The provisions of Specification 3.0.3 are not applicable.

Balcal This specification is provided to ensure that the concentration of radioactivo materials roloased in liquid wasto offluents from the sito to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B. Tablo II.

This limitation provi'os additional assurance that the levnis of radioactivo materials in bodies of water outside the rite will not result in exposures greater than the Sects-

,I A design ohjeictives of Appendix 1,10 CFR Part 50, to a member of the public. The concentration limit for noble gases is based upon the I

assumption that Xo-133 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

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Amendment No. f$,JJE, 66v

e

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Radioactivo Liquid Effluents 3.25.1.2 Donn Arrlicability: At all t.imes

@jestiro:

To ensure that the dose limits of 10 CFR 50, Appe, dix I,Section IV A, are met..

SPEllis.0110D11 3.25.1.2 A

Tho dosn commitment to a member of thn public from radioactivo material in liquid offluents released from ANO-1 to the dischargo canal shall be:

1)

During any enlendar quarter less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrom to any organ, and 2)

During any cal.ndar year less than or equal to 3 mrem l

to the total oody and less than or equal to 10 mrem to any organ.

B.

With the calculated doso from the rolense of radioactivo materials in liquid effluents exceeding any of the above limits, in lieu of any other report, prepare and submit a Special Report. to t.hn Commission within 30 days, pursuant to Speci fication 6.12.5.

C.

The provisions of Specification 3.0.3 are not applicable.

l Ilanx.s:

Specification 3.25.1.2 provides assuranco that releases of liquid offluents will result in concentrations far below the limits of 10CFR20.

The specification provides the required operating flexibility and at the same timo assures that the release of radioactivo material in liquid offluents will be kept "as low as reasonably achievablo".

Amendment. No. $f,JJE, 66w

_.. ~. _. -, -. -,

v

(

n Radioactive !.1 quid 1:ffluents 3.25.1.3 Waste Trentment Arnlicahilliyi At all times Qbjec11tni To assure that thn amount of radioactive materint in liquid effluents will be "ns low ns rensonnbly achievabin."

SDecLLLCaLivD31 3.25.1.3 A.

The 9pptoprinto parts of the liquid radwnste t reatment system shn11 be used to reduce the radioactive materials in liquid waste prior to thnir discharge when it is projected that the cumulative donn during a calendar quarter dun to liquid effluent releases would exceed 0.18 mrom to the total body oi 0.6?.5 mrem to any organ.

B.

The provisions of this specification do not npply to the laundry tanks due to their incompatibility with the radwnste system.

C.

With radionctive liquid waste being dischntged without treatment nnd in excess of the abovn limits, in lieu of any other report, preparn and submit n Special Report to thn Commission within 30 days per Specification 6.12.5.

D.

The provisions of Specification 3.0.3 are not applicable.

EAscal The requirements that the approprinte port ions of this system be used when specified provides assurance that the relenses of radionctive materinis in liquid offluents will be kept "as low nn is reasonably achievable." The specified limit s governing the use of approprinto portions of thn liquid radwnsto treatment system were specified as a suitable fraction of the guido set f orth in Section li A of Appendix 1, 10 CFR Part 50, for liquid effluents. The values of 0.18 mrem and 0.625 mrem are approximately 25*.

of the yearly design objectives on a quarterly basis.

Tho yearly design objectives are given in 10 CFR 50, Appendix I, Section 11.

I l

l Amendment No. ff,JJf.

66x l

1

v 4

s Radioactive biquid Effluents 3.25.1.4 Liquid fluldup Tanks Applicability: /.t all times.

Objen11y.c:

To ensure that thn limits of 10 CFR 20 are not exceeded.

500Gliitaliana1 3.25.1.4 A.

Thn quantity of radioactivo materini contained in nach unprotected

  • outside temporary radionctivo liquid storagn tank shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

D.

With thn quantity of radioactivo materini exceeding the above limit, immodlately suspnnd all additions of radioactive material to the af fected tank and within 48 boot s reduce tho tank content s to within tho limit.

C.

The provisions c,f Specification 3.0.3 are not applicable.

l Esses:

This specification is provided to ensurn t hat in the event of an uncontrolled release of the contents of tho tank

  • the resulting concentrations would be less than the limits of 10 CFR Part 20. Appendix D. Table !!. Column 2, at the nearest potable water supply and the nearest surface water supply in the unrnstricted area.
  • Tanks included in this specification are thosn outdoor temporary tanks i

that 1) are not surrounded by liners, dikes, or walls capable of holding the tank contents, and 2) do not havo overflown and surrounding area drains connected to the 11guld radwasta treatment system.

I l

Amendment No. $$,

66y l

- _ ~ _ -. -

,\\

3.2%.2 KndioCCLLY23RheaubblL195mLE 3.25.2.1 Dose Rate 01'idic0kilityl At all times hjtcLivel To ?nsurn thnt the dose rate in unrestricted arens from gaseous effluents will bn within the limits of 10 CPR 20.

SEtGiliGAll0HR1 3.25.2.1 A.

The dono rate in unr est ricted nrens (see rigure 5.1-1) due to radioactive materinis relensed in gosnous effluents from the site shall be:

1)

For nobir gnses:

I.e s s t hnu or equal to 500 mrem /yr to the total body nnd less than or equoi to 3000 mrem /yr to the skin.

2)

For iodine-131, for t rit ium nnd for all radionuclides in particulnto form with half lives grnater than 8 days:

I.e s s than or equnt to 1500 rnrern/yr to any organ.

During periods of reactor building purging the dose rate may bn av'.,i 9;,ed over a one hour interval.

11.

With the doro rate (s) exceeding the abovo limit s, without dr.iny rest r re the release rato to within thn above limit (s)

C.

The.. visions of Specificntion 3.0.3 nrn not applienbin.

l Eainst This specification is provided to ensure that, at any time, the dosn rato due to ganoo'.s effluents from nll units on the site till be within the limits of IC CPR 20 for unrestricteel arens.

This npocification applien to the rolensn of gnsnous effluents from all reactors at the site.

Amendment No. ff,JJf, 66z

e e

Radioactive Gaseous Fffluents 3.25.2.2 Dono - Nobin Gases Arn1Jsab111ty.1 At a11 Limes OhjerAiyni To ensure that the design objective doses of 10 CFR 50, Appendix 1.Section IV A, are not exceeded.

l 621c.LLLc.o Linns.L 3.23.2.2. A.

The dose due to noble gases released in gaseous effluents from ANO-1 to unrestricted areas (see Figure 5.1-1) shall be:

1)

During any calendar quarter, less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiat lon, and i

During any calendar year, less then or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

B.

With the cniculated dosa from radioactive nobin gases in gaseous effluents exceeding any of the above limits, in lieu of any other report, preparo and submit a Special Report to the Commission within 30 days, pursuant to Specification 6.12.5.

C.

The provisions of Specification 3.0.3 are not applicable.

l Enges:

Specification 3.25.2.2 implements the design guides speciflod in 10 CFR So, Appendix I,Section II, and the limiting condition for operation as set forth in Section IV A of Appendix 1.

The specifications provide the required operating flexibility and at the same time implement the guides set forth in Section IV A Appendix 1, to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievabic."

These limits provide reasonable assuranco that radioactive material discharged in gaseous ef fluents will not result in the exposure of an individual in an unrestricted area, to annual average concentrations exceeding the limits specified in Appendix B. Table 11 of 10 CFR Part 20

[10 CFR Part 20.106(b)].

For individuals who may at times be within the exclusion area boundary, the occupancy of the individual will bn sufficiently low to compensate for any increaso in the atmospheric dif fusion f actor above that for the exclusion area boundary.

l Amendment No. $$,/J$,

66aa l

l

~.

e Radtonetive Gaseous F.f fluents 3.25.2.3 Dose - lodine-131, Trit ium, and Radionuclides in Particulate Form hyplicabilltv: At all times Qbjcnirai To ensuro that thn dosn limits of 10 CrR So, Appendix 1,Section IV A, are met.

SncEllital_iRD11 3.25.2.3 A.

The doso to a member of the public f rom lodinn-131, f rom tritium, and from all radionucliden in,articulato form with half-lives greater than 8 days in gaseous ef fluents released from ANO-1 to unrestrict ed areas (sen Figuro 5.1-1) shall bn; 1)

During any calendar quarter, less tnan or equal to 7.5 mrems to any organ, and 2)

During any calendar year, less than or equal to 15 mrems to any organ.

11 With the calculated doso from the release of fodino-131, tritium and radionuclides in particulato form with half-lives greater than 8 days, in gaseous offluents exceeding any of the above limits, in lieu of any other report, prepnro and submit a Special Report to the Commission within 30 days, pursuant to Specification 6.12.5.

C.

The provisions of Specification 3.0.3 arn not applicable, j

Enns:

Specification 3.25.2.3 implements the design guides not forth in 10 CFR 50, Appendix 1, Section 11 C, and the limiting conditions for operation as set forth in Appendix 1,Section IV A.

The specifications provide the requirnd operatir.g flexibility and at the same time implement the guidos snt forth in Section IV A of Appendix 1 to assure that the releases of radioactivo materials in gaseous effluents will be kept "as low as reasonably achievablo".

I i

l Amendment No f5.J/S, 66bb

... l

e e

Radioactivo Goncous Effluents 3.25.2.4 Ganeous Radwnsto Treatment Arpikabilily: At a11 timos Ohju.tlyo:

To assure that the amount of radioactivo material in gescous effluents in "as Icw na rnasonnbly nchievablo."

SAcnillrAlf ona':

3.25.2.4 A.

i'entilation exhnunt. treatment systems shall be used to reduce radioactivo materials in gascaun wasto prior to dischargo when thn projoct ed doses duo to gaseous ef fluent rnlenses from ANO-1 to unrestricted arens (sco rigure 5.1-1) would exceed 0.625 mrad for gamma radiation and 1.25 mrnd for beta radiation ovnr a enlendar quart er; or when the projected doses due to lodine-131, tritium, and radionuclidon in particulato form with half-lives greater than 8 days would exceed 1.0 stem to any organ over n calendar qunrter.

B.

When degnsi fying the reactor coolant system, the gaseous radwnste treatment system shall be utillr.ed to procosa the degesning ef fluent to reduce the concentration of radioactive materinta prior to discharge when the projected doses dun to goneous of fluent rolenson from ANO-1 to unrentricted arens (sco Figurn 5.1-1) would exceed 0.625 mrad for gamma radiation and 1.25 mrad for botn radiation over a calendar quarter.

C.

With gaseous wastn being discharged without treatment and in excess of the above limits, in llou of any other report, preparo and submit to the Commission within 30 days a Special Report, por Specification 6.12.5.

D.

The provisions of Specification 3.0.3 are not applicable, bses:

The requirement that tbn approprinto portions of thnne systems bo used when specified providen reasonnble nasurance that thn relonnes of radioactive materials in gaseous offluents will be kept "na low na reasonably achievable." Tho specified limits governing the uso of approprinto portions of the systems worn specified as a suitablo fraction of the guide set forth in Sections 11 B and II C of Appendix 1,10 CFR Part 50, for gaseous of fluents.

The values 0.625 mrad,1.25 mrad, and 1.0 mrom are approximately 25% of the yently design objectives on a quarterly I

basis. The yearly desigt. objectiven are given in Specifications 3.25.2.2 and 3.25.2.3.

l l

Amendment No. 75,1J5, 66cc

.. ~...

Radioactivo Gancous Effluents 3.25 2.5 Gas Storage Tanks Applicabilfly t At. ell times Ohjgsihe:

To rostrict the amount of activity in a radioactive gas holdup tank.

Eggstficationgs 3.25.2.5 A.

The quantity of radioactivity contained in each gas stu_ago tank shall bo limited to 300,000 curies noble gases (Xc-133 equivalent).

B.

With thn quantity of radioactivo material in any gas storago tank exceeding the abovn limit, immediately suspend all additions of radtonctive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit.

C.

The provisions of Specification 3.0.3 are not applicable.

Rases:

The value of 300,000 curies is a suitable fraction of the quantity of radioactive material which if released over a 2-hour period, would result in a total body exposure to a member of the public at the exclusion area boundary of 500 mrom.

This is consistent with Branch Technical Position ETSB 11-5 in NUREG-0800, July 1981.

l l

l Amendment No ff, 66dd i

l-

3.25.3 Iolal_ Doms ApplLcJth111ty.1 At all times l

i Qbjnily.gl To ensure that the limita of 40 CFR 190 are not exceeded.

Spnifica t ioni l

3.25.3.1 The calculated doses from the release of radioactivo materials in liquid or gaseous offluents shall not exceed twice the limits of Specification 3.25.1.2, 3.25.2.2, or 3.25.2.3.

3.25.3.2 With the calculated doses exceeding the above limits, preparo and submit a Special Report pursuant to 10CFR part 20.4050.

3.25.3.3 If thn limits of 40CFR190 havn been exceeded, obtain a variance i

f rom the Commission t o permit further rolcasos in excess of 40CFR190 limits. A variance is granted until staf f action on the request is completed.

3.25.3.4 The provisions of Specification 3.0.3 are not applicable.

l Hanni This specification is provided to mont the dose limitations of 40 CFR 190 that have now been incorporated into 10 CFR part 20.

The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactivo offluents exceed twice the design objective doses of Appendix I.

For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the doso limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level.

The Specini Report will ds6cribe a course of action that should result in the limitation of the annual dose to a member of the public to within the 40 CFR 190 limits.

For the purposes of the Special Report, it may bn assumed that the dose commitment to the member of the public from other uranium tual cycin sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities within a radius of 8 km must bn considered.

If the dose to any member of the public is estimated to excnod the requirements of 40 CFR 190, the Special Report with a requnst for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staf f action is completed.

The variance only relates to the limits of 40 CFR 190, and does not apply la any way to the other rnquirements for dose limitation of l

10 CFR 20, as addressed in Specifications 3.25.1 and 3.25.2.

An I

individual is not considered to be a member of the public during any l

period in which he/she is engaged in carrying out any operation that is part of the nuclect funt cycle.

1 l

l Amendment No. 58, 66ce

~~,

3.23.4 Holid_.RadiontinLWaste App _licability : At all timns Objective; To ensurn solid radwasto is processed in accordance with the Process Cont rol Program to meet shipping and burial ground rnquirements.

Specifinational 3.25.4.1 With the provisions of the Process Control Program not satisfied, suspend shipments of defectively processed or defectively packaged solid radioactive wastn from the sito.

3.25 4.2 The provisions of Specification 3.0.3 nro not applicable.

l Eases:

This specification impicments the requirements of 10CFR50.36a and General Design Criterion 60 of Appendix A to 10CFR50.

Amendment No fE,J/5, 66ff

- =

l i

l SURVEILLANCE REQUIREMENTS 4.0.1 Survnillanco Requirements shall bo met during the operational modos or other conditions specified for individual Limiting Conditions for Operation unless otherwiso stated in an individual Surveillance Requirement.

4.0.2 Each Surveillanco Requirement shall be performed within the i

specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

4.0.3 Failure to perform a Surveillanco Requirement within the allowed surveillance interval defined by Specification 4.0.2, shall constituto noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation.

The time limits of the Action requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The timo at which the Action is taken may be delayed for up to 2' hours to permit the completion of the surveillance when the allowable outage time limits of the Action requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an operational mode or other specified condition shall not be made unless the Surveillanco Requirement (s) associated with the Limiting Condition for Operation has been performed within the stated surveillance interval or as otherwise specified. This provision shall not prevent passage through or to operational modes as ' required to comply with Action requirements.

4.0.5 Surveillance Requirements for inservice inspection and testing of-ASME Code Class 1,2, and 3 components shall be applicable as follows:

5 a.

Inservice inspection of ASME Code Class 1,2, and 3 components and inservice testing of ASME Code Class 1,2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and pressure Vessel Code and nop11 cable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(1),

Amendment No. 25,/J,//,JZ9, 67

_.... _ _ _. _ _ _.. _. ~. _, _ _. ~

O O

SURVEILLANCE REQUIREMENTS _(Continued) 4.0.5 (Continued) l b.

Surveillance intervals specified in Section XI of the ASME Boiler I

and Pressure Vessel Code and applicable Addenda for the inservice I

inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as i

follown in these Technical Specifications:

l ASME Boiler and Pressure Vessel Required frequencies for Code and applicable Addenda performing incervice terminology for inservice inspection and testing

(

inspection and testing activities activities l

Weekly At least once por 7 days l

Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Yearly or annually At least once per 366 days The provisions of Specification 4.0.2 are applicable to the above c.

required frequencies for performing inservice inspection and testing activities.

d.

Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.

n.

Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.

4.1 OPERATIONAL SAFETY ITEMS Applicability Applies to items directly related to safety limits and limiting conditions for operation.

Objective To specify the minimum frequency and type of surveillance to be applied to unit equipment and conditions.

Specification a.

The minimum frequency and type of surveillance required for reactor protective system and engineered safeguards system instrumentation when the reactor is critical shall be as stated in ' fable 4.1-1.

Amendment No.

67a i

1 OPERATIONAL SAFETY ITEMS _(cont.in,ued)_

4.1 (Continued) b.

Equipment and sampling test shall be performed as detailed in Table 4.1-2 and 4.1-3.

c.

Discrepancies noted during surveillance testing will be corrected and recorded, d.

A power distribution map shall be made to verify tho expected power distribution at periodic intervals at a 'at every 10 effective full power days using the incorn instrumentation detector system.

BASES 4.0.1 through 4.0.5_ Establish the general requirements applicable to Surveillance Requirements. These requirements arn based on thn Surveillance Requirements stated in the Code of Federal Regulations, 10CFR 50.36(c)(3):

" Surveillance Requirements are requiremet '.s relating to test, calibration, or inspection to ensurn that the riecessary quality of systems and components is maintained, that facility operation will be tithin safety limits, and that the limiting conditions of operation will be met."

4.0.1 Establishes the requirement that surveillances must be performed during the operational modos or other conditions for which the requirements of the Limiting Conditions for Operation apply.unless otherwise stcted in an individual Surveillance Requirement.

The purpose of this specification is to ensurn that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in a mode or other specified condition for which the associated Limiting Conditions for 0poration arn applicabin.

Surveillance Requirements do not have to be performed when thn facility is in an operational mode for which the requirements of the associated Limiting Condition for Operat. ion do not apply unless otherwise specified.

Amendment No. 75 67b

o e

BASES (continued) 4.0.2 Establishes the limit for which the specified time interval for Surveillance Requirements may be extended.

It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may ut be suitable for conducting the surveillance; e.g.,

transient conditions or other ongoing surveillance or maintenance activities.

It also provides flexibility to accommodate the length of a fuel cycle for surveillances t.ha t are performed at each refueling outage and are specified with an 18-month surveillance Interval.

It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages. The limitation of Specification 4.0.2 is based on engineering judgement and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements.

This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance intervals.

4.0.3 Establishes the failure to perform a Surycillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation. Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval, flowever, nothing in this provision is to be construed as implying that syatems or components are OPERABLE when they are found or known to be Inoperable although still meeting the Surveillance Requirements.

This specification also clarifles that the Action requirements are applicable'when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the Action requirements apply from the point-in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded. Completion of the Surveillance Requirement within the allowable outage time limits of the Action -requirements restores compliance with thr-requirements of l

Specification 4.0.3.

Ilowever, this does not negate the fact that the failure to have performed the surveillanco within the allowed surveillance interval, defined by the provisions of Specification 4.0.2 was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action.

Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10CFR 50.73(a)(2)(1)(B) because it is a condition prohibited by the plant's Technical Specifications.

If the allowabic outage time limits of the Action requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to comply with Action requirements, e.g., Specification 3.0.3, a 24-hour allowance is provided to permit a delay in implementing the Action requirements. This provides an adequate time limit to complete Surveillan;.e Requirements that have not been performed. The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with Action requirements or before other remedial measures would be required that may preclude completion of a surveillance. The basis for this allowance l

l l

Amendment No.

67c

J t

MSES (cat iny.edl t

includes cons ideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required survoillanco.

This provision also provides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of mode changes imposed by Action requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed, if a surveillance la not completed within the 24-hour allowance, the timo limits of the Action requirements are applicable at that time. When a surveillanen is performed within the 24-hour allowance and thn Surveillance Requirement.s are not met, the time limits of t he Action requirements arn applicable at the time that the surveillance is terminated.

if the Action requirements are greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, suf ficient t ime exists to complete the survn111ance.

Surveillance Requirements do not. have to be performed on inoperable equipment because the Action requirements define the remedial measures that apply, llowevn r, the Surveillanco Requirements have to be met to demonstratn that. inoperable equipment has been restored to OPERABl.E status.

4.0.4 Establishes the requirement that all applicable surveillances must be met before entry into an operational mode or other condit.fon of operation specified in the Specification. The purpose of this Specification is to ensure that system and component OPERABil.lTY requirements or parameter limits are met before entry into a mode or condition for which these systems and components ensure safe operation of the facility.

This provision applies to changes in operational modes or other specified conditions associated with plant shutdown as well as startup Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to ensure that the Limit!ng Conditions for Operation are met during initial plant startup or following a plant outage.

When a shutdown is required to comply with Action requirements, the provision of Specification 4.0.4 do not apply because this would delay placing the facility in a lower mode of operation.

4.0.5 Establishes the requiremont that inservice inspection of ASME Code Class 1,2, and 3 components and inservice testing of ASME Code Class 1,2, and 3 pumps and valves shall be performed in accordance with a periodically updated version of Section XI of the ASME Boller and Pressurn Vessel Code and Addenda as requ'.e4 by 10 CFR 50.55a.

These requirements apply except. when rnlief has been provided in writing by the Commission.

This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boller and Pressure Vessel Code and applicable Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout Technical Specifications and to remove any ambiguities relativo to the frequencies for performing the required inservico inspec, tion and testing activities.

l Amendment No.

67d 9

J EASES fcontinurdl Under the terms of this specification, the more restrictive requirements of the Technical Specificat ions take precedence over the ASME Boiler and Pressuro Vessel Codo and applicablo Addenda. The requirements of Specification 4.0.4 to perform surynlliance activities beforo entry into an eperational mode or other spncified condition takes precedence over the ASME Boiler and Pressuro Vessel Ccxin provision which allows pumps and valves to be tested up to one week af ter return to normal operation. The Technical Specificatien dnfinition of OPERABLE does not allow a graco period before a component, that is not. capable of performing its specified function, is declared inoperable and takes procedence over the ASME Boiler and Pressuro Vessel Code provision which allows a valve to be incapable of performing its specJ fied function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperabin, Check Failures such as blown instrument fuses, defective indicators, faulted ampitfiers which result in " upscale" or "downscale" indication can be easily recognized by simple observation of the functioning of an instrument or system. Furthermoro, such failures are, in many cases, revealed by alarm or annunciator Action. Comparison of output and/or state of indepnndent channels measuring the same variable supplements this type of built-in surveillance. Based on experienco in operation of both conventional and nuclear plant systems, when the plant is in operation, the mlnimum checking frequency stated is doomed adequate for reactor sysua instrumentation.

Calibration Calibration shall he performed to assure the presentation and acquisition of accurate information.

The nuclear flux (power rango) channels shall be calibrated at least twice wenkly (during steady state operating conditions) against a heat balance standard to compensate for instrumentation drift.

During non-steady stato operation, the nuclear flux channels shall be calibrated daily to componsato for instrumentation drift and changing rod patterns and corn physics parameters.

Amendment No.

670

IahJe 4.1-1 (Cont.)

Channel Descriotion Check Igs1 Calibrate Remarks 1

30. Decay heat removal S(1)(2)

M(i)(3) R (1) Includes RCS Pressure Analog Channel system isolation valve (2) Includes CFT Isolation Valve Position automatic closure and (3) Shall also be tested during refueling interlock system shutdown prior to repressurization at a pressure greater than 300 but less than 420 psig.

31. Turbine overspeed trip NA E

NA (1) The provisions of Specification 4.0.4 mechanism are not applicable.

32. Diesel generator M

Q NA protective relaying starting interlocks and circuitry

33. Of f-site power undervoltage W

R(1)

R(1)

(1) Shall be tested during refueling and protective relaying shutdown to demonstrate selective interlocks and circuitry load shedding interlocks function during manual or automatic trans-fer of Unit I auxiliary load to Startup Transformer No. 2.

34. Borated water storage W

NA R

tank level indicator

35. Reactor trip upon loss M

PC R

of main feedwater circuitry 1

Amendment No. 4,19,59,69,67,91, 72

~

.___=_. ___

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1 year limits of Specifications 3.25.1.2 and 3.25.2.2.

This Special Report is not required if the measured level of radioactivity was not the result of plant effluents, however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental

Report, c.

With milk or fresh leafy vogotable samples unavailable from any of the sample locations required by Table 4.29-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.

The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Identify the causes of the unavailability of samples and identify the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also Jnclude in the report a revised table for the ODCM reflecting the new location (s),

d.

The provisions of Specification 3.0.3 are not applicable.

4.30.1.3 The results of analyses performed on the radiological environmental monitoring samples shall be summarized in the Annual Radiological Environmental Report.

Bases:

The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation.

This monitoring program thereby supplements the radiological effluents monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.

The initially specified monitoring program will be ef fective for at least the first three years of commercial operation.

Following this period, program changes may be initiated based on operational experience, j

l The detection capabilities required by Table 4.30-2 are state-of-the-art f

for routine environmental measurements in industrial laboratories.

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LLD's for drinking water meet the requirements of 40 CFR 141.

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1 Amend:nent No. $1L, J / 5, 110tt j

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Radiological Environmnntal Honitoring 4.30.2 Land.Use C_eJuina Apolicabilltv: Applies at all timon Objectivea:

This specification will identify changes in use of the unrestricted areas.

SPE llinalisual 4.30.2.1 A land use census shall be conducted and shall identify the location of the nearnst milk animal, the nearest residence, and the nearest garden

  • of greator ttan 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles from thn ANO-1 reactor building.

4.30.2.2 The land use census shall be conducted at Itast once por 12 months between the dates of Junn 1 and October 1, oy door-to-door survey, aerial survey, or by consulting local agricultural authorities.

4.30.2.3 n.

With a land uso census identifying a location (s) which yinids a calculated dose commitment due to I-131, tritium, and radionuclidos in particulate form greater than the values currently being calculated in Unit 1 Specification 4.29.3 and Unit 2 Specification 4.11.2.3 submit location description in the Semiannual Radioactive Effluent Release Report por Specification 6.12.2.6.

b.

With a land uso census identifying a location (s) which yields a calculated dose commitment (via the same exposure pathway) greater than at a location from which samples are currently being obtained in accordance with Specification 4.30.1.1, identify the new location in the Semiannual Radioactivo Effluent Release Report per Specification 6.12.2.6.

The new location shall be added to the radiological environmental monitoring program within 30 days, if possib1n. The sampling location having the lowest calculated dose commitment (via the samn exposure pathway) may be doloted from this monitoring program af ter October 31 of the year in which this land use census was conducted.

l 4.30.2.4 The results of the land uso consus shall be included in the Annual Radiological Environmental Report.

s 4.30.2.5 The provisions of Specification 3.0.3 are not applicable.

  • Broad Icaf vegetation sampling may be performed at the sito boundary in the direction sector with the highnst D/Q in lieu of the garden census.

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Amendment No. $$,JJE, 110zz

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Radiological Environmental Monitoring 4.30.3 J.nirdabparators ComparlantLProgIAm Aimlitability : Applies to thn of f-site rnalochemistry laboratory.

QbJr.cilyni To provide independent checks on the accuracy of the measurements of radioact.ivo matnrlal n environmental samples.

Specificatiangi 4.30.3.1 Analyses shall be performed on rcdlonctivo materials supplied as part of Interlaboratory Comparison Program which has been approved by NRC.

4.30.3.2 With analyses not being performed as required above, report the corrective actions taken to prevent a re:urrence to the Commissica in thn Annual Radiological Environmental Report.

4.30.3.3 The results of analysos performed as part of the above required Interlaboratory Comparison Program shall bo included in tini Annual Radiological Environmental Report. pursuant to Specification 6.12.2.5.

4.30.3.4 The provisions of Specification 3.0.3 are not applicabin.

l aim The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that Independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrato that the results are reasonably valid.

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Amendment No. $$,JJE, 110bbb

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