ML20081K178
| ML20081K178 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/17/1991 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20081K180 | List: |
| References | |
| GL-90-09, GL-90-9, NUDOCS 9106250238 | |
| Download: ML20081K178 (16) | |
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UNITED STATES e
E*,ecfi NUCLEAR REGULATORY COMMISSION s/
..j WASHINGTON, D C. 20555 o -
a SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CAllFORNIA THE CITY OF ANAHEIM, CAllFORNIA DOCKET N0. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 95 License No. NPF-10 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern California Edison Company, San Diego Gas and Electric Company, the City of Riverside, California, and the City of Anaheim, California (licensees) (the licensee) dated May 2, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's 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 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.
9106250238 910617 PDR ADDCK 05000361 p
. 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of facility Operating License No. NPF-10 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
95, are hereby incorporated in the license.
Southern California Edison Coinpany shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and must be fully implemented no later than 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION e
. E?./'. b d!I/6'l'
/
James E. Dyer, Director Project Directorate V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 17,1991 2
ATTACHMENT TO LICENSE AMENDMENT NO. 95 FACILITY OPERATING LICENSE NO. NPF-10 DOCKET N0. 50-361 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 7-16 3/4 7-16 3/4 7-16a 3/4 7-16b 3/4 7-17 3/4 7-17 B 3/4 7-5 B 3/4 7-5
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PLANT SYSTEMS 3/4.7.6 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.6 All snubbers shall be OPERABLE.
The only snubbers excluded from this requirement 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.
APPLICABILITY:
MODES 1, 2, 3 and 4.
(MODES S and 6 for snubbers located on systems required OPERABLE in those MODES).
ACTION:
With one or more snubbers inoperable, 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 OPERA 3LE status and perform an engineering evaluation per Specification 4.7.6.g on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.6 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program, 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 catego'42ed 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 4.7-2.
The visual inspection interval for each category of snubber shall be determined based upon the criteria provided in Table 4.7-2 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 95,
i l
SAN ONOFRE-UNIT 2 3/4 7-16 AMENDMENT N0. 95 l
1 a
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
TABLE 4.7-2 SNUBBER V!3UAL INSPECTION INTERVAL NUMBER OF INOPERABLE SNUBBERS Position Column A Column B Column C or Category Extend 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 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 shall be determined based upon the previous inspec-tion interval and the number of INOPERABLE snubbers found during that interval.
Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible.
These categories may be examined separately or jointly.
- However, the licensee must make and document that decision before any inspec-tion 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 INOPERABLE 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 IN0PERABLE snubbers as determined by interpolation.
Note 3:
If the number of INOPERABLE 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 INOPERABLE 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.
SAN ON0FRE-UNIT 2 3/4 7-16a AMENDMENT NO. 95
i PLANT SYSTEMS l
SURVEILLANCE REQUIREMENTS (Continued)
Note 5:
If the number of INOPERABLE 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 ;NOPERABLE snub-bers 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 l
factor that is one-third of the ratio of the difference between the number of INOPERABLE snubbers found during the previous interval and the number in Column B to the difference in the numbers in Columns B 3
and C.
Note 6:
The provisiors of Specification 4.0.2 are applicable for all inspection intervals up to and including 48 months.
i SAN ONOFRE-UNIT 2 3/4 7-16b AMENDMENT NO. 95
PLANT SYSTEMS SURVEILLANCE REQO.REMENTS (Continued) c.
Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indi-cations of damage or impaired OPERABILITY, and (2) attachments to the foundation or supporting structure are secure, anci (3) fasteners for attachment of the snubber to (a) the component or pipe and (b) the snubber anchorage are secure.
Snubbers which appear INOPERABLE as a result of visual inspections shall be classified as INOPERABLE and may be reclassified OPERABLE for the purpose of establishing the I
next visual inspection interval, provided that (1) the caust of the rejection is clearly established and remedied for that par +icular snubber and far other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7.6.e or 4.7.6.f, as applicable.
However, when a fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined INOPERABLE and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.
All snubbers found connected to an INOPERABLE common hydraulic fluid reservoir shall be counted as INOPERABLE sn bbers for determining the next inspection interval, A review and evaluation shall be performed and documented to justify continued operation with an IN0 PERT,DLE snubber.
If continued operation cannot be justified, the snubber shall be declared INOPERABLE and the ACTION requirements shall be met.
SAN ONOFRE-UNIT 2 3/4 7-17 AMENDMENT NO 95
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PLANT SYSTEMS BASES 3/4.7.6 SNUBBERS All snubbers are required OPERABLE 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 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 e*fect on any safety related system.
For visual inspection snubbers may be categorized into two (2) greups, those accessible and those inaccessible during reactor operation.
For func-tional testing, snubbers are categorized into types by design and manufacturer, irrespective of capacity.
For example, Pacific Scientific snubbers are divided into four types corresponding to different design features:
PSA 1/4 and 1/2 are one type; PSA 1, 3, and 10 are another; PSA 6 is another; and PSA 35 and 100 are a fourth type.
The visual inspection frequency is based upon maintaining a conrtant level of snubber protection to systems.
Therefore, the required inspection interval varies based upon the number of INOPERABLE snubbers found during the previous inspection in proportion to the sizes of the various snubber populations or categories and the previous inspection interval as specified in NRC Generic Letter 90-09, " Alternative Requirements For Snubber Visual Inspection Inter-vals and Corrective Actions."
Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection.
However, the retults of such early inspections performed before the original required time.nterval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval.
Any inspection whose results require a shorter inspection interval will override the previous schedule.
To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shut-downs at refueling intervals.
If a review and evaluation of an INOPERABLE snubber is performed and documented to justify continued operation and provided that all design criteria are met with the INOPERABLE snubber, then the IN0PERABLE snubber would not need to be restored or replaced as stated in TS 3/4.7.6 " ACTION."
Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.
SAN ON0FRE-UNIT 2 B 3/4 7-5 AMENDMENT NO. 45
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SOUTHERN CAllFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE, CAllFORNIA THE CITY OF ANAHEIM, CALIFORNIA DOCKET NO. 50-362 SAN ON0FRE NUCLEAR GENERATING STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Auendment No. 85 License No. NPF-15 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern California Edison Company, San Diego Gas and Electric Cs npany, the City of Riverside, California, and the City of Anaheim, California (licensees) (the licensee) dated May 2, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's regulations set forth in 10 CFR Chapter 1; 1
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 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 iiave been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Speci.
fications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of facility Operating License No. NPF-15 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
85, are hereby incorporated in the license.
Southern California Edison Company shall operate the facility in accordance with the Technical Spe<.ifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and must be fully implemented no later +han 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION r.
l)h)//1 $ lNf'ik' James E. Dyer, Director Project Directorate V Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Speciiications t
Date of 1ssuance:
June 17,1991 l
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ATTACHMENT TO LICENSE AMENDMENT NO.
>5 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 7-17 3/4 7-17 3/4 7-17a 3/4 7-17b 3/4 7-18 3/4 7-18 B 3/4 7-5 B 3/4 7-6 l
I PLANT SYSTEMS 3/4.7.6 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.6 All r.nubbers shall be OPERABLE.
The only snubbers excluded from this requirement 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.
APPLICABILITY:
HOPES 1, 2, 3 and 4.
(HODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).
ACTION:
With one or more snubbers inoperable, within *,2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> replace or restore the inoperable snubber (s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.6.g on the attached component or declare the attached system incperable and follow the appropriate ACTION statement for that system.
SURVEILLANCE REQUIREMENTS 4.7.6 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program, 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. 7-2.
The visual inspection interval for each category of snubber shall be determined based upon the criteria provided in Table 4.7-2 and the first inspection interval determined using this cri-teria shall be based upon the previous inspection interval as estab-t g
lished by the requirements in effect before amendment 85 I
L 1
l SAN ON0FRE-UNIT 3 3/4 7-17 AMENDMENT N0.
85
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
TABLE 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL NUMBER OF INOPERABLE SNUBBERS Position Column A Column B Columa C or Category Extend 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 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 shall be determined based upon the previous inspec-tion interval and the number of IN0FERABLE snubbers found during that interval.
Snubbers may be categorized, based upon their accessibility during power operation, as accessible or inaccessible.
These categories may be examined separately or jointly.
- However, the licensee must make and document that decision before any inspec-tion 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 INOPERABLE 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 IN0PERABLE snubbers as determined by interpolation.
Note 3:
'If the number of INOPERABLE 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 INOPERABLE 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.
SAN ONOFRE-UNIT 3 3/4 7-17a AMENDMENT NO. 85 i
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
Note 5:
If the number of INOPERABLE snubbers is equal to or greater than the number in Column C, the next inspection interval shall be two-thirds of the previous itsterval.
However, if the number of INOPERABLE snub-bers 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 difference between the number of INOPERABLE snubbers found during the previous interval and the number in Coluirin 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.
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SAN ON0FRE-UNIT 3 3/4 7-17b AMENDMENT NO. 85 l
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.
Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indica-tions of damage or impaired OPERABILITY, and (2) attachments to the foundation or supporting structure are secure, and (3) fasteners for attachment of_the snubber to (a) the component or pipe and (b) the snubber anchorage are secure.
Snubbers which appear INOPERABLE as a result of visual inspections shall be classified as INOPERABLE and may be reclassified OPERABLE for the purpose of establishing the next visual inspection interval, provided that (1) the cause of the rejec-tion is clearly established cnd remedied for that particular snubber and for other snubbers that may be generically eusceptible; and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7.6 e or 4.7.6.f, as applicable.
However, when a fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined INOPERABLE and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.
All snubbers found connected to an IN0PERABLE common hydraulic fluid reservoir shall be counted as inoperable snubbers for determining the next inspection interval.
A review and evaluation shall be performed and documented to justify continued operation with an INOPERABLE snobber.
If continued operation cannot be justified, the snubber shall be declared INOPERABLE and the ACTION requirements shall be met.
d.
Functional Tests
- At least once per refueling interval during shutdown, a representative sample of at least 15% of the total of each type of snubber in use in the plant shall be functionally tested either in place or in a bench test.
For each snubber of a type of that-does not meet the functional test acceptance criteria of Specification 4.7.6.e or 4.7.6.f, an additional 151 of that tvpe of snubber shall be functionally tested until no more failures are found or until all snubbers of that type have been functionally tested.
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of :,nubbers.
At least 25% of the snubbers i
in the representative sample shall include snubbers from the following three categories:
1.
The first snubber away from each reactor vessel nozzle 2.
Snubbers within 5 feet of heavy equipment (valve, pump, turbine motor, etc. )
3.
Snubbers within 10 feet of the discharge from safety relief valve.
- Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
SAN ON0FRE-UNIT 3 3/4 7-18 AMENDMENT NO. 85
PLANT SYSTEMS BASES 3/4.7.6 $NUBBERS All snubbers are required OPERABLE tu 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 inspection program are those installed on nonsafety related systems and then only if their f ailure or f ailure of the system on which they are installed, would have no adverse effect on any safety related system.
For visual inspection snubbers may be categorized into two (2) groups, l
those accessible and those inaccessible during reactor operation.
For func-tional testing, snubbers are categorized into types by design and manufacturer, irrespective of capacity.
For example, Pacific Scientific snubbers are divided into four types corresponding to different design features:
PSA 1/4 and 1/2 are one type; PSA 1, 3, and 10 are another; PSA 6 is another; and PSA 35 and 100 are a fourth type.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.
Therefore, the required inspection interval varies based upon the number of INOPERABLE snubbers found during the previous inspection in proportion to the sizes of the various snubber populations or categories and the previous inspection interval as specified in NRC Generic Letter 90-09, " Alternative Requirements For Snubber Visual Inspection Intervals and Corrective Actions."
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 lengthen the required inspection interval.
Any inspection whose results require a shorter inspection interval will override the previous schedule, g
To provide assurance of snubber functional reliab:lity, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at refueling intervals.
If a review and evaluation of an INOPERABLE snubber is performed and documented to justify continued operation and proviued that all design criteria are met with the INOPERABLE snubber, then the INOPERABLE snubber would not need to be restored or replaced as stated in TS 3/4.7.6 " ACTION."
Hydre.ulic snubbers and mechanical snubbers may each be treated as a dif-ferent entity for the above surveillance programs.
SAN ONOFRE-UNIT 3 8 3/4 7-5 AMENDMENT NO. 85
_