ML20080B884
| ML20080B884 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 11/02/1994 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co |
| Shared Package | |
| ML20080B888 | List: |
| References | |
| NPF-39-A-081, NPF-85-A-042 NUDOCS 9412060340 | |
| Download: ML20080B884 (10) | |
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NUCLEAR REGULATORY COMMISSION t,;
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PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 81 License No. NPF-39 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated September 16, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; t
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 2
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 issuance 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.
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. 2.
Accnrdingly, 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-39 is hereby amended to read as folluss:
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
81, are hereby incorporated into this license.
Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
e-FOR THE NUCLEAR REGULATORY COMMISSION
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lbf John F. Stolz, Directod Project Directorate I-2 Division of Reactor Projects - I/,Il Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 2, 1994
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ATTACHMENT TO LICENSE AMENDMENT NO. 81 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and coatain vertical lines indicating the area of change.
Remove Insert 3/4 7-13 3/4 7-13 B 3/4 7-3 8 3/4 7-3 i
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PLANT SYSTEMS SVRVEILLANCERE0VIREMENTS(Continued) e.
Functional Tests At least once per 24 months a representative sample of each type ofsnubber l
shall be tested using the following sample plans.
The sample plan (s) shall be selected for each type prior to the test period and cannot be changed during the test period. The NRC Regional Administrator shall be notified in writing of the sample plan (s) selected for each type prior to the test period or the sample plan (s) used in the prior test period shall be implemented:
1)
At least 13.3% of the total population of a snubber type shall be l
functionally tested.
For each snubber of that type that does not meet the functional test acceptance criteria of Specification 4.7.4f., an additional sample of at least 1/2 the size of the initial sample shall be tested until the total number tested is equal to the initial sample multiplied by the factor,1+C/2, where C is the total number of unacceptable snubbers or until all the snubbers of that type have been tested; or 2)
A representative sample of 37 snubbers of a snubber type shall be functionally tested in accordance with Figure 4.7.4-1.
"C" is the total number of snubbers of that type found not meeting the acceptance requirements of Specification 4.7.4f.
The cumulative number of snubbers of the type tested is denoted by "N".
If at any time the point plotted falls in the " Accept" region, testing of snubbers of that type may be terminated.
When the point plotted lies in the " Continue Testing" region, additional snubbers of that type shall be tested until the point falls in the " Accept" region, or all the snubbers of that type have been tested.
i l
LIMERICK - UNIT 1 3/4 7-13 Amendment No. 2S, )#,81 i
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PLANT SYSTEMS BASES SNUBBERS (Continued)
To provide assurance of snubber functional reliability one of two functional testing methods is used with the stated acceptance criteria:
1.
Functionally test 13.3% sample of a type of snubber with an additional 1/2 l
sample tested for each functional testing failure, or 2.
Functionally test 37 snubbers and determine sample acceptance using Figure 4.7.4-1.
Functional Testing sample plans are based on ASME/ ANSI OMc-1990 Addenda to ASME/ ANSI OH-1987, Part 4.
Figure 4.7.4-1 was developed using "Wald's Sequential Probability Ratio Plan" as described in Quality Control and Industrial Statistics" by Acheson J. Duncan.
1 Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubbers for the applicable design conditions at either the completion of their fabrication or at a subsequent date.
Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.
The service life of a snubber is evaluated via manuf acturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (i.e., newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.).
The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.
These records will provide statistical bases for future consideration of snubber 2ervice life.
3/4.7.5 SEALED SOURCE CONTAMINATIQH The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.
This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.
Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group.
Those sources which are frequently handled are required to be tested more often than those which are not.
Sealed sources which are continuously enclosed within a shielded mechanism, i.e,, sealed sources within radiation monitoring devices, are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
LIMERICK - UNIT 1 B 3/4 7-3 Amendment No. 74, 81
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/j NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D.C. 20555-4001
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PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-353 LIMERICK GENERATING STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
42 License No. NPF-85 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company (the licensee) dated September 16, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission'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 Commission; 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 issuance of this amendment will not be inimical t9 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. NPF-85 is hereby amended to read as follows:
Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
42, are hereby incorporated into this license.
Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This licer.se amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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, John F. Stolz, DireEtor
' Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 2, 1994
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4 ATTACHMENT TO LICENSE AMENDMENT NO. 42 FACILITY OPERATING LICENSE N0, NPF-85 DOCKET NO. 50-353 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are :dentified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 3/4 7-13 3/4 7-13 1
8 3/4 7-3 8 3/4 7-3 f
- -l
PLANT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) e.
Functional Tests At least once per 24 months a representative sample of each type ofsnubber l
shall be tested using the following sample plans.
The sample plan (s) shall be selected for each type prior to the test period and cannot be changed during the test period. The NRC Regional Administrator shall be notified in writing of the sample plan (s) selected for each type prior to the test period or the sample plan (s) used in the prior test period shall be implemented:
1)
At least 11 3% of the total population of a snubber type shall be l
functionally tested.
For each snubber of that type that does not meet the functional test acceptance :riteria of Specification 4.7.4f., an additional sample of at least 1/2 the size of the initial sample shall be tested until the total number tested is equal to the initial sample multiplied by the factor, 1+C/2, where C is the total number of unacceptable snubbers or until all the snubbers of that type have been tested; or 2)
A representative sample of 37 snubbers of a snubber type shall be functionally tested in accordance with Figure 4.7.4-1.
"C" is the total number of snubbers of that type found not meeting the acceptance requirements of Specification 4.7.4f.
The cumulative number of snubbers of the type tested is denoted by "N".
If at any time the point plotted falls in the " Accept" region, testing of snubbers of that type may be terminated.
When the point plotted lies in the " Continue Testing" region, additional snubbers of that type shall be tested until the point falls in the " Accept" region, or all the snubbers of that type have been tested.
LIMERICK - UNIT 2 3/4 7-13 knendment No.19, 42
1 PLANT SYSTEMS BASES SNUBBERS (Continued)
To provide assurance of snubber functional reliability one of two functional testing methods is used with the stated acceptance criteria:
1.
Functionally test 13.3% sample of a type of snubber with an additional 1/2 sample tested for each functional testing failure, or 2.
Functionally test 37 snubbers and determine sample acceptance using figure 4.7.4-1.
Functional Testing sample plans are based on ASME/ ANSI OMc-1990 Addenda to ASME/ ANSI OH-1987, Part 4.
Figure 4.7.4-1 was developed using "Wald's Sequential Probabil ty Ratio Plan" as described in Quality Control and Industrial Statistics" by Aches (n J. Duncan.
Permanent. or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for e.temption is presented and, if applicable, snubber life destructive testing was pertarmed to qualify the snubbers for the applicable design conditions at either the completion of their fabrication or at a subsequent date.
Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.
The service life of a snubber is evaluated via manufacturer input and information through consideration of the snubber service conditions and associated installation and maintenance records (i.e., newly installed snubber, seal replaced, spring replaced, in high radiation area, in high temperature area, etc.). The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions. These records will provide statistical bases for future consideration of snubber service life.
3/4.7.5 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium.
This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.
Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group.
Those sources which are frequently handled are required to be tested more often than those which are not.
Sealed sources which are continuously enclosed within a shielded mechanism, i.e., sealed sources within radiation monitoring devices, are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
LIMERICK - UNIT 2 B 3/4 7-3 Amendment No. 79,42