ML20079D303
| ML20079D303 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/25/1991 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079D304 | List: |
| References | |
| GL-90-09, GL-90-9, NUDOCS 9107050155 | |
| Download: ML20079D303 (17) | |
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UNITED STATES
!7i 2'
NUCLEAR REGULATORY COMMISSION
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PHILADELPHI A ELECTRIC C0t'PANY, DOCKET NO. 50-352 LIMERICK GEtlERATING STATION, l' NIT 1 AMEt!Dt'EtlT TO FAC!LITY OPERAT!NG LICENSE Amendrmnt No. 51 License No. NPF-39 f
1.
The tluclear Regulatory Comission (the Commission) has found that A.
The application for amendment by Philadelphia Electric Company (the licensee) dated April 30, 1991, complies with the standards and requirements of the Atomic Ercrgy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issurnee of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. IlPF.39 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment flo.
51, are hereby incorporated into this license. Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, 9107050155 910625 PDR ADOCK 05000352 P
PDR e
.e 3.
This license amendment is effective as of its date of issuance.
FOR THE tittrLEAR REGULATORY C0l'Ji!5510tl kb L-
/
w Walter R. Putler. Director froject Directorate 1-2 Division of Reactor Projects - 1/11 Att,achment:
Changes to the Technical Specifications Date of Issuance:
June 25,1991
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ATT AC HME tit..T.O..L_I.C E.t15.E..A.P.E.ld.D.f 4.E.l4.T..li.0. 51 _
FACILITY OPERAT1tJG LICEtis,E,110. f4PF-39 l
00CLET E0. EO-352 Replace the following pages of the Appendix A Technical Specifications with the attackd pa es.
The revised pages are identified by Arnendment nurr.ber and contain vertica lines indicating the area of change.
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3/4 7-11 3/4 7-11 t
3/4 7-12 3/4 7-11a 3/4 7-11b 3/4 7-1?
B 3/4 7-2 B 3/4 7-2 l
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1/4.7.4 SNUBBERS LlHITING CONDITION FOR OPERATION 3.7.4 All snubbers shall be OPERABLE.
APPLiCABIL1TY: OPERA 110NAL CONDIT10NS 1. 2. and 3.
OPERAT10NAL COND11 IONS 4 and 5 for snubbers located on systems required OPERABLE in those OPERATIONAL CON 01iIONS.
ACTION:
With one or more snubbers inoperable on any system, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.4g on the attached component or declare the attached system inoperable and fo11cw the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.4 Each snubber shall be demonstrated OPERABLE by perfors.
e of the following augmented inservice inspection program and the requi.... ants of Specification 4.0.5.
a.
inspection Types As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity, b.
Visual Inspections Snubbers are categorized as inaccessible or accessible during reactor operation.
Each of these categcries (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.7.4-1.
The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4.7.4-1 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by the requirements in effect before amendment (NRC will include the number of the license amendment that implements this change).
LlHERICK - UNIT 1 3/4 7 11 Amendment No. 51
TABLE 4.7.4 1
$NUBBER VISUAL INSPECTTUN INTERVAL NUMBER Of UNACCEPTABLE SNUBBERS Population Column A Column B Column C or Category txtend Interval Repeat interval Reduce interval (Notes 1 and 2)
(Notes 3 and 6)
(Notes 4 and 6)
(Notes 5 and 6) 1 0
0 1
80 0
0 2
100 0
1 4
150 0
3 8
200 2
5 13 300 S
12 25 400 8
18 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 109 Note 1:
The next visual inspection interval for a snubber in?ulation or category size shall be determined based upon the pr stous inspection interval and the number of unacceptable snubbers fosnd during that interval. Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible.
These catergories may be examined separately or jointly.
- However, the licensee must make and document that decision before any inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.
Note 2:
Interpolation between population or category sizes and the number of unacceptable snubbers is permissible.
Use next lower integer for the value of the limit for Columns A, B, or C if that integer includes a fractional value of unacceptable snubbers as determined by interpolation.
Note 3:
If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval but not greater than 48 months.
Note 4:
If the number of unacceptable snubbers is equal to or less than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.
LIMERICK - UNIT 1 3/4 7-Ila Amendment No. 51
I TABLE 4.7.4-1 (continued)
SNUBBER VISUAL INSPECTION INTERVAL i
Note 5:
If the number of unacceptable snubbers is equal to or greater than the number in Column C. the next inspection interval shall be two-thirds of the previous interval. However if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column G, the next interval shall be reduced proportionaliy by interpolation, that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the difference between the number of unacceptable snubbers found during the previous interval and the number in Column B to the difference in the numbers in Columns B and C.
Note 6:
The provisions of Specification 4.0.2 are applicable for all inspection intervals up to and including 48 months.
l LIMERICK - UNIT 1 3/4 7-11b
.,mendment No. 51 1
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PLANT SYSVE_.MS i
D SURVEllLANCE REQUIREMENTS (Continued)
I I
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c.
Visual Inspection Acceptance Criteria i
Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are secure.
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, providing that: (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type on that system that may be generically susceptible; and/or (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specifications 4.7.4f.
For those snubbers common to more than one system, the OPERABILITY of such snubbers shall be considered in assessing the surveillance schedule for each of the related systems. A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber, if continued operation cannot be justified, the snubber shall be declared inoperabic and the ACTIONS requirements shall be met.
d.
Transient Event Inspection An inspection shall be performed of all snubbers attached to sections of systems that have experienced unexpected, potentially damaging transients, as determined from a review of operational data or a visual inspection of the systems, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for accessible systems and 6 months for inaccessible systems following this determination.
In addition to satisfying the visual _ inspection acceptance criteria, freedom-of-motion of mechanical snubbers shall be verified using at least one of the following:.(1) manually induced snubber movement; or (2) evaluation of in-place snubber piston setting; or (3) stroking the mechanical snubber through its full range of travel.
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a LIMERICK - UNIT 2 3/4 7-12 Amendment No. 51
1 BASES 3/4.7.4 S N UBB E_R_S.
All snubbers are required OPLRABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.
Snubbers excluded from this intnection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed ould have no adverse effect on any safety related system.
Snubbers are classified and grouped by design and manufacturer but not by
- size, for example, mechanical snubbers utilizing the same design features of the 2-kip, 10-kip, and 100-kip capacity manufactured by Company "A" are of the same type.
The same design mechanical nubbers manufactured by Company "B" for the purposes of this Technical Specificat # would be of a different L.,pe, as would hydraulic snubbers from either manufacturer.
A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 Cf3 Part 50.
The access Qility of each snubber shall be determined and approved by the Plant Operation, Review Comittee.
The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g., temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guides 8.8 and 8.10.
The addition or deletion of any snubber shall be made in accordance with Section 50.59 of 10 CfR Part 50.
The visual inspection scnedule is based on the number of unacceptable snubbers found during the previous inspection in proportion to the sizes of the various snubber populations or categories.
The visual inspection interval is based on a fuel cycle of up to 24 months and may be as long as two fuel cycles or 48 months depending on the number of unacceptable snubNrs found during the previous visual inspection.
The visu].1 iMpection schedu b provides confidence that a constant level of snubber protection is being mMntained and generally allows performance of visual inspections and correJ...e actions during plant outages, inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection.
However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lenotnen the required inspection interval.
Any inspection whose results required a shorter inspection interval will override the previous schedule.
A snubber is considered inoperable if it falls the acceptance criteria of the visual inspection.
LlHERICK UNIT 1 B 3/4 7-2 Amendment No. 21. 40. 51 i
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UNITED STATES 2k.
i NUCLEAR REGULATORY COMMISSION
/
WASHINoTON. o C 2W4 t
PHILADELPHIA ELECTRIC COMPANY DOCKET IJ0. FO-353 LIMERICK GEt!ERATit!G STATION, UlllT p Al'ENOMEtlT TO FAClllTY OPERATING LICEf{SE Amendment flo.15 License 110. NPF-85 1.
The f.'uclear Repulatory Commission (the Comission) has found that A.
The application for amendrent by Philadelphia Electric Company (the licensee) dated tpril 30, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; F.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; U.
Tho issuance of this amendrent will not be inimical to the common nse and security or to the health and safety of the public; and e
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
P.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-85 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendnent No. 15
, are hereby incorporated into this license.
Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, m
\\
i
' 3.
This license amendrent is effective as of its date of issuance.
FOR THE NUCLEAR PfGULATORY C0t'JilSS10t O
Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects - 1/11
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 25,1991 I
1 e
1
ATT ACHt4Et41 TO LICEtiSE Af tEtiDt'EtiT f;0. 15 FAClllTY OPERAllt!G LICENSE !!O. IPF-85 00Cr.CT I40. 50-353 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by Arnendn.ent nun'ber and contain vertical lines indicating the area of change. Overleaf page is provided to maintain document corpleto ess.*
Remove
_ Insert 3/4 7-11 3/4 7-11 3/4 7-12 3/4 7-11a 3/4 7-11b 3/4 7-1?
B 3/4 7-la B 3/4 7-la*
B 3/4 7-2 B 3/4 7-2 s
PLANT SYSTEMS 3/4.7.4 SNt'3BE RS LlHITING CONDITION FOR OPERA 110N 3.7.4 All snubbers shall be OPERABLE.
APPLICABitITY: OPERATIONAL CONDil!ONS 1, 2, and 3.
OPERAll0NAL COND1110NS 4 and 5 for snubbers located on systems required OPERABLE in those OPERA 110NAL CON 0!TIONS.
t ACTION:
With one or more snubbers inoperable on any system, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replate or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.4g on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.4 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
a.
inspection Types As used in this specification, type of snubber shall mean snubbers of the same design and manufacturer, irrespective of capacity.
b.
Visual Inspections Snubbers are categorized as inaccessible or accessible during reactor operation.
Each of these categories (inaccessible and accessible) may be inspected independently according to the schedule determined by Table 4.7.4-1.
The visual inspection interval for each type of snubber shall be determined based upon the criteria provided in Table 4.7.4-1 and the first inspection interval determined using this criteria shall be based upon the previous inspection interval as established by tne requirements in effect before amendment (NRC will include the number of the license amendment that implements this change).
t l
l LlHERICK - UNIT 2 3/4 7-11 Amendment No. I. 15 1
o
TABLE 4,7.4 1 SNUBBER VISOAL INSF((TIDN INTERVAL NUMBER Of UNACCEPTABLE SNUBBERS Population Column A Co'umn 8 Column C or Category Extend Interval Repeat Interval Reduce Interval (Notes 1 and 2)
(Notes 3 ar.d 6)
(Notes 4 and 6)
(Notes 5 and 6) 1 0
0 1
80 0
0 2
100 0
1 4
150 0
3 8
200 2
5 13 300 5
12 25 400 8
18 36 500 12 24 48 750 20 40 78 1000 or greater 29 56 109 Note 1:
The next visual inspection interval for a snubber population or category size s'all be determined based upon the previous inspection interval and the number of unacceptable snubbers found during that interval. Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible.
These catergories may be examined separately or jointly.
- However, the licensee must make and document that decision before any i
inspection and shall use that decision as the basis upon which to determine the next inspection interval for that category.
Note 2:
Interpolation between population or category sizes and the number of unacceptable snubbers is permissible.
Use next lower integer for the value of the limit for Columns A, B, or C if that integer includes a fractional value of unacceptable snubbers as determined by interpolation.
Note 3:
If the number of unacceptable snubbers is equal to or less than the number in Column A, the next inspection interval may be twice the previous interval but not greater than 48 months.
Note 4:
If the number of unacceptable snubbers is equal to or less than the number in Column B but greater than the number in Column A, the next inspection interval shall be the same as the previous interval.
LIMERICK - UNIT 2 3/4 7 11a Amendment No. 15 t
1 TABLE 4.7.4 1 (continued)
SNUBBfk'VIIUAL INSPEC110N INTERVAL Note 5:
If the number of unacceptable snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous interval.
However, if the number of unacceptable snubbers is less than the number in Column C but greater than the number in Column B, the next interval shall be reduced proportionally by interpolation, that is, the previous interval shall be reduced by a factor that is one-third of the ratio of the dif f erence between the number of unacceptable snubbers found during the previors interval and the number in Column B to the difference in the numbers in Columns B and C.
Note 6:
The provisions of Specification 4.0.2 are applicable for all inspection intervals up to and including 48 months.
s LlHERICK - UNIT 2 3/4 7-llb Anendment No.15 i
PLANT SYSTEMS SURVE!LLANCE REQUIREMENTS (Continued) i t
c.
Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attact.ments to the foundation or supporting structure are secure, and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are secure.
Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, providing that: (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type on that system that may be generically suscMtible; and/or (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specifications 4.7.4f.
For those snubbers common to more than one system, the OPERABILITY of such snubbers shall be considered in assessing the surveillance schedule for each of the related systems. A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber.
if continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met, d.
Transient Event inspection An inspection shall be performed of all snubbers attached to sections of systerrs that have experienced unexpected, potentially damaging transients, as determined from a review of operational data or a visual inspect'.on of the systems, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for accessible systems and 6 months for inaccessible systems following this determination.
In 3ddition to satisfying the visual inspection acceptance criteria, frecuom-of-motion of mechanical snubbers shall be verified using at least one of the following:
(1) manually induced snubber movement; or (2) evaluation of in-place snubber piston setting; or (3) stroking the mechanical snubber through its full range of travel.
LIMERICK - UNIT 1 3/4 7-12 Amendment No.15 I
i PLANT SYSTEMS BASES 1
CONTROL ROOM EMERGENCY FRESH AIR $UPPLY SYSTEM - COMMON SYSTEM times are consistent with those in the Unit 1 Technical Specifications for CREFAS and AC electrical power supply out of service condition combinations.
3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM The reactor core isolation cooling (RCIC) system is provided to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without requiring actuation of any of the emergency core cooling system equipment.
The RCIC system is conservatively required to be OPERABLE whenever reactor pressure ex-ceeds 150 psig.
This pressure is substantially below that for which low pressure core cooiing systems can provide adequate core cooling.
The RCIC system specifications are applicable during OPERATIONAL CONDITIONS 1, 2, and 3 when reactor vessel pressure exceeds 150 psig because RCIC is the i
primary non-ECCS source of emergency core cooling when the reactor is pressurized.
With the RCIC system inoperable, adequate core cooling is assured by the OPERABILITY of the HPCI system and justifies the specified 14 day out-of-service period.
The surveillance requiremen+.s provide adequate assurance that RCIC will be OPERABLE when required.
Althougn all active components are testable and full flow can be demonstrated by recirculation during reactor operation, a complete functional test requires reactor shutdown.
The pump discharge piping is maintained full to prever,t water hammer damage and to start ecoling at the earliest possible moment.
l l
LIMERICK - UNIT 2 B 3/4 7-la L
PLANT SYSTEMS BASES 3/4.7.4 SHUBBERS All snubbers are required OPERABLE to ensure that tht. structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.
Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then'only if their failure or failure of the system on which they are installed would have no adverse effect on any safety related system.
Snubbers are classified and grouped by design and manufacturer but not by size.
For example, mechanical snubbers utilizing the same design features of the 2-kip, 10-kip, and 100. kip capacity manufactured by Company "A" are of the same
)
type.
The same design mechanical snubbers maisfactured by Company "B" for the purposes of this Technical Specification would be of a different type, as would hydrauli snubbers from either manufacturer.
A l' of individual snubbers with detailed information of snubber location and size ad of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50.
The accessibility of each snubber shall be determined and approved by the Plant Operations Review Committee.
The determination shall be based upon the existing radiation levels and the expected time to perform a visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g., temperature, atmosphers, location, etc.), and the recommendations of Regulatory Guides 8.8 and 8.10.
The addition or deletion of any snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
The visual inspection schedule is based on the number of unacceptable snubbers found curing the previous inspection in proportion to the sizes of the various snubbei populations or categories.
The visual inspection interval is based on a fuel c)cle of up to 24 months and may be as long as two fuel cycles or 48 months depene'ng on the number of unaccepttble snubbers found during the previous visual inspection.
The visual inspection schedule provides confidence that a constant level of snubber protection is being maintained and generally allows performance of visual inspections and corrective actions during plant outages.
Inspections performed before that interval has elapsed may be used as a n6e reference point to determine the next inspection.
Ho.ever, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results required a shorter inspection interval will override the previous schedule.
A snubber is considered inoperable if it fails the acceptance criteria of the visual inspection.
t L.!MERICK - UNIT 2 0 3/4 7-2 Amendment No. 15 L
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