ML20210T923
| ML20210T923 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/02/1997 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20210T920 | List: |
| References | |
| NUDOCS 9709160173 | |
| Download: ML20210T923 (9) | |
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ATTACHMENT 2 LIMERICK GENERATING STATION UNITS 1 AND 2 Docket Nos. 50 352 50 353 License Nos. NPF 39 NPF 85 TECHNICAL SPECIFICATIONS CHANGE REQUEST
. No. 96-20 0
- LIST OF AFFECTED PAGES (MARKED-UP PAGES) .
Unit 1 .Ulilt2 3/4 0-2 3/4 0 2
-3/4 0-3 3/4 0-3 B 3/4 0-5 B 3/4 0 5 B 3/4 4-6 B 3/4 4-6 s
9709160173 970902 PDR ADOCK 05000352 p PDR
irtICAsItm 3901038720 SURVEILLANCE REQUIREMENTS
- 4. 0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions spedlied for individual Limiting Conditions for operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Each surveillance Requirement shall be performed within the specified surveillance time interval with a maximum allowable extension not to exceed 25%
of the surveillance interval.
4.0.3 Failura to perform a Surveillance Requirement within the allowed surveillance interval defined by Specification 4.0.2, shall constitute 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 ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perett the comp 1stima.:sf. the survaillance 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 CONDITION.or 'other specified applicable condi-l tion shal'i not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been perfomed within the applicable surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Clast 1, 2, & 3 components shall be applicable as follows:
- a. Inservice inspection of ASME Code Class 1, 2, and 3 components and inservica 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 applicable Addenda as required by 10 CFR Part 50, Section 50.55a(f}.
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- b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical specifications:
LIMERICK - UNIT 1 3/4 0-2 Amendment No. J11.38 i MRf 11 It'1, i
APPLICABILITY
- SURVEILLMCE REQUIREMENTS (Continued)
ASME loiler and Pressure Vessel- Requir'edfhquencias Code and applicable Addenda for performing inservice terminology for inservice inspection and testing insoection and testina activities activities i Weekly At least once per 7 days 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 Every 9 months At least once per 276 days Yearly or annually At least once per 366 days l
Siensally or overj 2. years At loot <no2 pv 741 dy5
- c. The provisions of Specification 4.0.2 are applicable to the above required activities, frequencies for performing inservice inspection and testing
- d. performance of the' above inservice inspection and testing act1vities shall be in addition to other specified Surveillance Requirements.
- e. Nothing in the ASME Boiler and Pressure Vessel Codes ' hall be construed to supersede the requirements of any Technical Specification.
f.
The Inservice Inspection (ISI) Program for piping identified in NRC Generic Letter 88-01 shall be performed in accordance with the staff positions on schedule, methods and personnel, and sample expansion included in the Generic Letter. Details for implementation of these requirements are included as augmented inspection requirements in the ISI Program.
LIMERICK - UNIT 1 .
3/4 0-3 Amer.dment No. II, 49 APR 0419ml
1/4.0' APPLICABILITY BASES If 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 /> 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 Surveillance Requirements that have not been performed. The purpose of this allowance is to permit the completion of a surveillance before a shutdown would be required to comply with ACTION requirements or before other remedial measures would be required that may preclude the completion of a surveillance.
The basis for this allowance. includes consideration 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 surveillance. This provision also provides a time limit for the completion of Surveillance Requ.irements that become applicable as a consequence of CONDITION 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 is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time. When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.
l Surveillance Requirements do not have to be performed on inoperable equipment l because the ACTION requirements define the remedial measures that apply. However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPEPABLE status.
Soecification 4.0.4 establishes the recuirement that all applicable surveillances must be met before entry into an OPERAYIONAL CONDITION or other condition of operation specified in the Applicability statement. The purpose of this specification is to ensure that systam and component OPERABILITY requirements or parameter limits are met before ent"y into an OPERATIONAL CONDITION or other specified condition for which these systems and components ensure safe operation of the facility. This provision applies to changes in OPERATIONAL CONDITIONS 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 th'at the Limiting Conditions for Operation are met during initial plant startup dir following a plant outage.
When a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the f acility in a lower CONDITION of operation.
Soecification 4.0.5 establishes the requirement 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 Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a. Pere r-tr: nt: :;;b : = ;t t:r : lief hn b:= '
- --ided " ~iti9 by tM "" *- Additionally, the Inservice Inspection Program conforms tc the NRC staff positions identified in NRC Generic Letter 88-01, "HRL Position on IGSCC in BWR Austinetic StafnTiss Steel Piping," as approved in HRC Safety Evaluations dated March 6,1990 and October 22, 1990.
LIMERICK - UNIT 1 B 3/4 0-5 Amendment No. 49 APR 0 41891 n-
' REACTOR COOLANT SYSTEM RASES .
- 3/4.41 MAIN STEAM LINE ISOLATION VALVES
- Double isolation valves are provided on each of the main steam lines to minimize the potential leakage paths from the containment in case of a line break.
Only one valve in each line is required to maintain the integrity of the containment, however, single failure considerations require that two valves be OPERABLE.- The surveillance requirements are based on the operating history of this type. valve. The maximum closure time has been selected to contain fission products and to ensure the core is not uncovered following line breaks. The minimum closure time is consistent with the assumptions in the safety analyses to prevent pressure ' surges.
3/4.4.8 STRUCTURAL INTEGRITY The inspection programs for ASME Code Class 1, 2, and 3 components ensure that the structural integrity of these components will be maintained at an acceptable level throughout the life of the plant.
Components of the reactor coolant system were designed to provide access to permit inservice inspections in accordance with Section XI of the ASME Botier and Pressure Vessel Code 1971 Edition and Addenda through Winter 1972.
-The inservice inspection program for ASME Code Class 1, 2, and 3 components will be performed-in accordance with-Section-XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55:(;) ::::;t t::: t
.___.....=CA 50_ S;;;;!);'.)? Additionally, the Inservice Inspec iont Program conforms to the
' NRC staff positions identified in NRC Generic Letter 88-01, "NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping," as approved in NRC Safety Evaluations dated March 6,1990 and October 22, 1990.
3/4.4.9 RESIDUAL HEAT REMOVAL The RHR system is required to remove decay _ heat and sensible heat in order to maintain the temperature of the reactor coolant. RHR shutdown cooling is-comprised of four (4) subsystems which make'two (2 -loops. Each loop consists of two (2) motor driven pumps, a heat exchanger, s and a)sociated piping and . valves. -Both loops have connon suction from the same recirculation loop. Two (2) redundant, manually controlled shutdown cooling subsystems of the RHR System can provide the required decay heat removal capability. Each pump discharges the reactor coolant, after it- has been cooled by circulation through the respective heat exchangers, to the reactor via the associated recirculation loop or to the reactor'via the low pressure coolant injection pathway. The RHR heat exchangers transfer heat to the RHR Service Water System. The RHR shutdown cooling mode is manually controlled.
An 0PERABLE RHR shutdown cooling subsystem consists of an RHR pump, a heat exchanger, valves, piping, instruments,- and controls to ensure an OPERABLE flow path.
In H0T SHUTDOWN condition, the requirement to maintain OPERABLE two (2) independent RHR' shutdown cooling subsystems means that.each subsystem considered OPERABLE must be associated with a different heat exhanger loop, i.e., the "A" RHR heat exchanger with the "A" RHR pump or the "C" RHR pump, And the "B" RHR heat exchanger with the "B" RHR pump or the "D" RHR pump are two (2) independent RHR shutdown cooling subsystems. Only one (1)'.of the the two (2) RHR pumps associated with each RHR heat exchanger loop is LIMERICK - UNIT 1 B 3/4 4-6 Amendment No. 497 -97 7 119 FEB 31997 m .
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sPuCAs!tm 3905081240 SURVEILLANCE P.EQUIREMENTS
- 4.0.1 Surveillance Requirements shall be met during the 6PERATIONAL -
CONDITIONS or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall be perf' ormed within the specified surveillance the surveilla'interval with a maximum allowable extension not to exceed 255 of n ce it;terval.
l , a 4.0.3 Failure to perform a surveillance itoquirement within the allowed surveillance interval defined by Specification 4.0.2, shall constitute .
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 ACTION requirements may be delayed for up to 24 houn 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 en OPERATIONAL CONDITION or other specified applicable condi-tion shall not be made unless the Surveillance Requirement (s) associated with the L1aiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified. This provision shall not prevent with passage ACTION through or to OPERATIONAL CONDITIONS as required to comply requirements.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, & 3 components shall be applicable as follows:
- a. Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASNE 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 ap Part 50, section 50.55at;;;- - > __:plicable , f. : ; _Addenda as required
" ' 4 by 10 CFR
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- b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and
-Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical specifications:
LIMERICK - UNIT 2 3/4 0-2 -
Amendment No. 5 l
IW 1111H
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APPLICMILITY
- SURVEILLANCE REgl!REMENTS (Continued) .
ASE Boiler and Pressure Vessel Required frequencies - -
Code and applicable Addenda for performing inservice terminology for inservice inspection and testing -
inspection and testino activities actnities Weekly- At least once per 7 days Monthly At least once per 31 days At least once per 92 days Quarterly or every 3 months . -
Samiannually or every 6 months At least once per 184 days -
Every 9 months - At least once per 276 days
- Yearly or annually ,
At least once per 366 days L6'anr6911 y or omr/ 2.prves At Imf+ once pu-. 73l Q
- c. The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing activities. ,
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- d. Performance of the above inservice inspection and testing activities
. shall be in addition to other specified Surveillance Requirements.
- a. Nothing in the ASME Boiler- and Pressure vessel Code .shall be, construed to supersede the requirements of any Technical Specification..
- f. The Inservice Inspection (ISI) Program for piping identified in NRC Generic' Letter 88-01 shall be performed in accordance with the staff positions on schedule, methods and personnel, and sample expansion ,
included in the Generic Letter. Details for implementation of these requirements are included as augmented inspection requirements in the ISI Program. (
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LIMERICK - UNIT 2 3/40-3 Amendment No.12 APR 84 55 J
APPLICABILITY l
! ' the allowable outage time limits of the ACTION requirements are less than 24 L hours or a shutdown is required to comply with ACTION requirements, e.g.,
L Specification 3.0.3, a 24-hour allowance is provided to permit a delay in
! 1mplementing the ACTION requirements. This provides an adequate time limit <to
[ complete Surveillance Requirements that have not been performed. The purpose of !
- this allowance is to permit the completion of a surveillance before a shutdown j~ would be required to comply with ACTION requirements or before other remedial measures would be required that may preclude the completion of a surveillance. 1 The basis for this allowance includes consideration for plant conditions, adequate i'
- planning, availability of personnel, the time required to perfom the surveillance,'and the safety significance of the delay in completing the required ,
, . surveillance. This provision also provides a time limit for the completion of -
- Surveillance-Requirements that become applicable as a consequence of CONDITION
- l' changes imposed by ACTION requirements and for completing Surveillance- 4 l ' Requirements that are applicable when an exception to the requirements of -
Specification 4.0.4 is allowed. If a surveillance is not completed within 24-hour i
- -allowance, the time limits of the ACTION requirements are applicable at that time.
e When a surveillance is performed within the 24-hour allowance and the Surveillance
! Requirements are not met, the time limits of the ACTION requirements are ' -
applicable at the. time that the surveillance is teminated.
l . Surveillance Requirements do not have to be. performed on inoperable equipment i because tha-ACTION requirements-define the remedial measures that apply. However, l
the Surveillance Requirements have to be met to demonstrate that
j equipment has been restored to OPERABLE status.
Soecification 4.0.4 establishes the requirement that all applicable surveillances -
- must be met before entry into an OPERATIONAL CONDITION or other condition of operation
- specified in the Applicability statement. The purpose of this .
j specification is to ensure that system and component OPERASILITY requirements or parameter limits are met before entry into an OPERATIONAL CONDITION or other-specified condition for which these systems and components ensure safe operation ef the facility. This provision applies to changes in OPERATIONAL CONDITIONS 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 Limiting Conditions for Operation are met during initial plant
~startup or following a plant outage.
When a shutdown is required to comply with ACTION requiremerits, the provisions of Specification 4.0.4 do.not apply because this would delay' placing the facility in a lower-CONDITION of operation.
4 Soecification 4.0.5 establishes the requirement that inservice inspect. ion 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 accordancrs with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel
- ',
- r
- 3 Code and Y r":' Addenda
'r i::- 4 as required g-._by 10,CFR g 50.55a. - 'trn:;M-d:
. . ' - #- Additionally, the Inservice Inspection
- Program conforms to the NRC staff positions identified in NRC Generic Letter 88-
- 01. "NRC Position on IGSCC in 8WR Austinatic Stainless Steel Piping," as approved in NRC Safety-Evaluations dated March 6,1990 and October 22, 1990.
LIMERICK - UNIT 2- 8 3/4 0-5 Amendment No.12 APR 0 4 M
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REACTOR COOLANT SYSTEN w v -
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, 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES 1 -
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. Double isolation valves 'are provided on each of the main steam lines to' '
ainimize the potential leakage paths from the containment in case of a line break.
Only one valve in each line is required to maintain the integrity of thee containment, however, single failure considerations require that two valves be OPERABLE. The surveillance requirements are based on the operating history of this type valve. The maximum closure time has been selected to contain fission products and to ensure the core is not uncovered following line breaks. The cinimum closure time is consistent with the assumptions in the safety analyses to prevent pressure surges.
3/4.4.8 STRUCTURAL INTEGRITY '
P" * ,
,-v 1 _a. .. - 4 ,y The inspection programs for ASME Code Class 1, 2, and 3 components ensure that the' structural integrity of these components will be maintained at an acceptable level throughout the life of the plant, 4 .
.?9 . .-
t u Components of the reactor coolant system were designed to provide access to permit inservice inspections in accordance with Section XI of the ASME Boller and Pressure Vessel Code 1971 Edition and Addenda throtgh Winter 1972.
The inservice inspection program for ASME Code Class 1, 2, and 3 components will be performed in accordance with Section XI of the ASME Boiler and Pressure Vesse,l,
. 1. Code
..u.and applica,ble u. '___ . addenda
... 2 u asit.required
- by 10 CFR c 50.55a'.;.;
t t9 7 3 5" " 'C!'/; L Additionally, the Inservice inspection Program conforms to the NRC sta0f positions identified in NRC Generic Letter 88-01, "NRC Position on IGSCC' in BWR Austenitic Stainless Steel Pipi " as appro d_in NRC Safety Evaluations dated March 6,1990 and October 22,19 '
3/4.4.9 RESIOUAL HEAT REMO M
'Q 'E NW Thh RHR sydtemis required to remove bec hat arid serisilbbMih order to -
maintain the temperature of the reactor coolant. RHR' shutdown cooling is comprised of four (4) subsystems;which make two driven pumps, a heat exchanger, and(2) _ associated loops., Each piping loopvalves.
~ and consists Both ofloops two (2) motor =
have'a' #
common suction from the same recirculation loop. Two (2) redundant, manually ,
controlled shutdown cooling subsystems of the RHR System can provide,the requiresdecay heat removal capability. Each pump discharges;the reactor coolant, after it has been cooled by circulation through the respective heat exchangers; to the reactor via the
- associated recirculatior: loop or to the reactor via the low pressur9' coolant injection
'o' pathway. The RHR heat exchangers transfer heat to the RHR Service Water System. The -
RHR shutdown cooling mode is manually controlled.c . ;
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An OPERABLE RHR shu1 Sown cooling subsystem consists of an RHRhund, a heatl."
exchanger, valves, piping, instruments, and controls to ensure an OfERABLE flow path.
in HOT SHUTDOWN . condition, the requirement to maintain.0PERABLE two (2) independent RHR shutdown cooling subsystems means that each subsystem considered OPERABLE must be associated with a different heat exhanger loop, i.e., the "A" RHR heat exchanger with the "A" RHR pump or the "C" RHR pump, and the "B" RHR heat exchanger with the "B" RHR pump or the "D" RHR pump are two (2) independent RHR shutdown cooling subsystems. Only one-(1) of the two (2) RHR pumps associated with each RHR heat exchanger loop is'"
LIMERICK - UNIT 2 B 3/4 4-6 Amendment No. 42r-64, 82 n
y-me
- a. g FEB ._31997
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