ML20239A140
| ML20239A140 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 08/26/1998 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20239A142 | List: |
| References | |
| NUDOCS 9809080258 | |
| Download: ML20239A140 (30) | |
Text
_ _ _ _ _ - - - - - _ _ _ _ _.
l 6
e urug UNITED STATES p
.[C1 E
NUCLEAR REGULATORY COMMISSION l
s l
6 WASHINGTON, D.C. 2055!@ 001 SOUTHERN CAllFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA THE CITY OF ANAHEIM. CALIFORNIA DOCKET NO. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.140 License No. NPF-10 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southem Califomia Edison Company, et al.
(SCE or the licensee) dated September 16,1997, as supplemented by letter dated February 23,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissiorn'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 as.,urance (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.
I l
9809000258 990826 yDR ADOCK 05000361 PDR j
i
- r 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-10 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications co'ntained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
140, are hereby incorporated in the license. Southern Califomia Edison Company 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 is to be implemented within 30 days of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION James W. Clifford, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 26. 1998 l
i 9
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. f40 TO FACIL(TY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT 3.4-37 3.4-37 5.0-13 5.0-13 5.0-14 5.0-14 5.0-15 5.0-15 5.0-16 5.0-16 5.0-17 5.0-17 5.0-18 5.0-18 5.0-19 5.0-19 5.0-19a 5.0-19b 5.0-19c 5.0-30 5.0-30
RCS Operational LEAKAGE 3.4.13
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3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:
a.
No pressure boundary LEAKAGE; b.
I gpm unidentified LEAKAGE; c.
10 gpm identified LEAKAGE; NOTE: With no SG sleeving installed, d. and e. apply.
Following installation of any sleeving in any SG, d.
and e. do not apply and f. does apply.
d.
I gpm total primary to secondary LEAKAGE through all steam generators (SGs); and e.
720 gallons per day (1/2 gpm) primary to secondary LEAKAGE through any one SG.
f.
With steam generator. sleeving installed in any SG, 150 gallons per day primary to secondary LEAKAGE through any one SG.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ~ ACTION COMPLETION TIME A.
RCS LEAKAGE not within A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
~
limits for reasons within limits.
other than pressure boundary LEAKAGE.
B.
Required Action and B.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />
-associated Completion Time of Condition A AliQ not met.
B.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> 9.B '
h
. Pressure boundary
['
LEAKAGE exists.
l SAN ONOFRE--UNIT 2 3.4-37 Amendment No. 127,140 t
Procedures, Programs, and Manuals l.
5.5 5.5 Procedures, Programs, and Manuals 5.5.2.8 Primary Coolant Sources Outside~ Containment Program (continued) system (post-accident sampling return piping only). The program shall include the following:
a.
Preventive maintenance and periodic visual inspection requirements; and b.
Integrated. leak test requirements for each system at refueling cycle intervals or less.
5.5.2.9 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containment, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. Program itself is relocated to the LCS.
5.5.2.10 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1,. 2, and 3 components including applicable supports. Program itself is relocated to the LCS.
5.5.2.11 Steam Generator (SG) Tube Surveillance Program This program provides controls for monitoring SG tube degradation.
Each SG shall be demonstrated OPERABLE by meeting the requirements i
of Specification 5.5.2.11 and by meeting an augmented inservice inspection program based on a modification of Regulatory Guide 1.83, Revision 1, which includes at least the following:
a.
SG Sample Selection and Inspection Each SG shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of SG specified in Tables 5.5.2.11-1 and 5.5.2.11-2.
l b.
SG Tube Sample Selection and Inspection The SG tube and sleeve minimum sample size, inspection result l
classification, and the corresponding action required shall be as specified in Tables 5.5.2.11-1 and 5.5.2.11-2.
The inservice ins)ection of SG tubes and sleeves shall be performed at tie. frequencies specified in Specification 5.5.2.ll.e~ and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 5.5.2.11.f.
The tubes selected for each inservice inspection shall include at least 3% of the total
{
(continued) l SAN ONOFRE--UNIT 2 5.0-13 Amendment No. 127,140
Procedures, Programs, and Manuals 5.5 l
5.5 Procedures, Programs, and Manuals 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) number of tubes in all SGs; the tubes selected for these inspections shall be selected on a random basis except:
1.
Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from the critical areas; 2.
The first sample of tubes selected for each inservice I
inspection (subsequent to the preservice inspection) of each SG shall include:
a)
All non-repaired tubes that previously had l
detectable wall penetrations (greater than 20%),
b)
Tubes in those areas where experience has indicated potential problems, and c)
A tube inspection (pursuant to Specification 5.5.2.11.f) shall be performed on each selected tube.
If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection.
3.
All sleeves shall be inspected with eddy current prior to initial operatien. This includes pressure retaining portions of the parent tube in contact with the sleeve, the sleeve-to-tube weld and the pressure retaining portion of the sleeve.
4.
Following the preservice inspection, 20% of sleeves that have been in service for a full cycle of operation shall be inspected. The sleeves shall be selected on a random basis.
If indications of degradation are found in the sample the inspection sample shall be expanded. Table 5.5.2.11-2 contains the requirements for sample expansion.
(continued)
SAN ONOFRE--UNIT 2 5.0-14 Amendment No. 127,140'
Procedures, Programs, and Manuals a
5.5
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5.5 Procedures, Programs, and Manuals 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) c..
Examination Results The results of each sample inspection shall be classified into one of the following three categories:
C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
{
l C-2 One or more tubes, but not more than 1% of the total
{
tubes inspected are defective, or between 5% and 10% of l
the total tubes inspected are degraded tubes.
C-3 More than 10% of the total tubes inspected are degraded j
tubes or more than 1% of the inspected tubes are defective.
This classification shall also apply to sample inspections of sleeves.
1
.............................N0TE-------r------------------
4 In all inspections, previously degraded non-repaired tubes l
must exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.
d.
Supplemental Sampling Requirements The tubes selected as the second and third samples (if required by Table 5.5.2.11-1) may be subjected to a partial tube inspection provided:
1.
The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found, and 2.
The inspections include those portions of the tubes where imperfections were previously found.
(continued)
. SAN ONOFRE.-UNIT 2 5.0-15 Amendment No. 127,140
Procedures, Prograas, and Manuals 5.5
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5.5 Procedures, Programs, and Manuals 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) e.
Inspection Frequency The above required inservice inspections of the non-repaired l
SG tubes shall be performed at the following frequencies:
E 1.
The first inservice inspection shall be performed after 6 effective full power months but within 24 calendar l
months of initial critically. Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous inspection.
If two consecutive inspections.
not including the preservice inspection, result in all inspections results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months; 2.
If the results of the inservice inspection of a SG conducted in accordance with Table 5.5.2.11-1 at 40-J month intervals fall in Category C-3, the inspection shall be increased to at.least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 5.5.2.11.e.1, the interval may then be l
extended to a maximum of once per 40 months; and 3.
Additional, unscheduled inservice inspections shall be performed on each SG in accordance with the first sample inspection specified in Table 5.5.2.11-1 during the shutdown subsequent to any of the following conditions:
a)
Primary to-secondary tubes leak (not including leaks originating from tube-to-tube sheet welds) in excess of the limits cf Technical Specification 3.4.13, or b)
A seismic' occurrence greater than the Operating l
Basis Earthquake, or c)
A loss-of-coolant accident requiring actuation of the Engineered Safety Features, or d)
A main steam line or feedwater line break.
(continued)
SAN ONOFRE--UNIT 2 5.0-16 Amendment No. 127,140 I
f
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals l
5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) 4.
The provisions of Technical Specifications Surveillance Requirement 3.0.2 are applicable to SG Tube Surveillance inspection frequencies except those established by Category C-3 inspection results.
The above required inservice inspections of SG tubes repaired by sleeving shall be performed at the following frequencies:
1.
Steam generator tube sleeves shall be inspected prior to initial operation and in service. The initial operating period before the initial inservice sample inspection shall not be shorter than six months nor longer than 24 months. The inspections of sleeves shall be configured to ensure that each individual sleeve is inspected at least once in 60 months.
2.
If the results of the inservice inspection of SG tube sleeves conducted in accordance with Table 5.5.2.11-2 fall in category C-3, the inspection frequency shall be increased to ensure that each remaining sleeve is inspected at least once in 30 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria for Category C-1.
f.
Acceptance Criteria 1,
Terms as used in this specification will be defined as follows:
a)
Degradation - A service-induced cracking, wastage, wear, or general corrosion occurring on either inside or outside of a tube; b)
Degraded tube - A tube containing imperfections greater than or equal to 20% of the nominal wall thickness cause by degradation; c)
% Degradation - The percentage of the tube wall thickness affected or removed by degradation; d)
Defect - An imperfection of such severity that it exceeds the repair limit. A tube containing a defect is defective.
1 (continued)
SAN ONOFRE--UNIT 2 5.0-17 Amendment No. 127,140
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Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) e)
Imperfection - An exception to the dimensions, finish, or contour of a tube from that required by fabrication drawings or specifications.
Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections;
(
f)
Repair Limit - The imperfection depth'at or beyond l
which the tube shall be removed from service or j
repaired and is equal to 44% of the nominal tube l
wall thickness; Sleeves shall be removed from service upon detection of service-induced degradation of the sleeve material or any portion of the sleeve-to-tube weld.
g)
Preservice Inspection - An inspection of the full length of each tube in each SG performed by eddy-current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be performed prior to initial MODE 1 operating using the equipment and techniques expected to be used during subsequent inservice i
inspections. These examinations may be performed l
prior to steam generator installation. Similarly, for tube repair by sleeving, an inspection of the full length of the pressure boundary portion of the sleeved area shall be performed by eddy l
current techniques prior to service. This includes pressure retaining portions of the parent tube in contact with the sleeve, the' sleeve-to-tube weld, and the pressure retaining portion of the sleeve.
i h)
Tube Inspection - An inspection of the SG tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold i
leg; and 1)
Unserviceable - The condition of a. tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an i
i Operational Basis Earthquake, a loss-of-coolant j
accident, or a steam line of feedwater line break l
accident as specified in Specification 5.5.2.11.e.
(continued)
SAN ON0FRE--UNIT 2 5.0-18 Amendment No. 127,140 i
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) j)
Tube Repair - refers to a process that reestablishes tube serviceability. Acceptable tube repairs will be performed by the following process:
TIG welded sleeving as described in ABB/CE Topical Report, CEN-630-P, Rev. 2, is currently approved by the NRC.
Tube repair includes the installation by welding of the sleeves, heat treatment in accordance with CEN-630-P, Rev. 2, to remove the stresses that are introduced by the sleeve installation, acceptance testing of the sleeve, and nondestructive examination for future comparison. Tube repair can be performed on certain tubes that have been previously plugged as a corrective or preventive measure. A tube inspection of the full length of the tube shall be performed on a previously plugged tube prior to returning the tube to service.
2.
The SG shall be determined OPERABLE after completing the corresponding actions (plug or repair all tubes exceeding the repair limit and all tubes containing through-wall cracks, and plug all sleeved tubes that exceed the repair criteria) required by Tables 5.5.2.11-I and 5.5.2.11-2.
g.
Reports The content and frequency of written reports shall be in accordance with Technical Specification 5.7.2, "Special Reports."
(continued) l SAN ON0FRE--UNIT 2 5.0-19 Amendment No. 127,140
~
Procedures, Programs, and Manuals 5.5 4
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5.5 Procedures, Programs, and Manuals 5.5.2.11 Steam Generator Tube Surveillance Program TABLE 5.5.2.11-1.(page1of1) l STEAM GENERATOR TUBE INSPECTION SUPPLEMENTAL SAMPLING REQUIREMENTS ist Sample Inspection 2nd sagte Inspection 3rd sa gte Inspection Action Action Action Sagle Size Result Required Reoult Required Result Required A minimum of C1 None N/A N/A N/A N/A J
$ tubes per
$G C2 Plus or repair C1 None N/A N/A by sleeving defective tubes Plug or repair by N/A N/A and inspect an sl m ing additional 25 defective tubes C1 N/A s in this s t an C2 Plug or repair tubes in this $G.
by s y ng tubes.
C3 Perform action for C 3 result of first samle.
C-3 Perform action N/A N/A for C-3 result of first sagte.
C3 Inspect att All other None N/A N/A tubes in this SGs C 1 SG plus or repair by sleeving Some SGs C-2 Perform action N/A N/A defective tubes but no other for C 2 result of and inspect 2$
is C 3 second sagte, tthes in each other SG.
Additional Inspect all tubes N/A N/A Notification to SG is C 3 in each SG and NRC pursuant to plug or repair by 10CFR50.72 ste:ving l
defective tubes.
Notification to NRC pursuant to 10CFR50.72.
S = 3 N/n % Where N is the number of SGs in the unit and n is the number of SGs inspected during inspection period.
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(continued)
SAN ON0FRE--UNIT 2 5.0-19a Amendment No. 140
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals Table 5.5.2.11-2 (page 1 of 1)
Steam Generator Sleeved Tube Inspection 1st Sample Inspection 2nd Sample Inspection Sample Size Result Action Required Result Action Required C-1 None N.A.
N.A.
Plug defective C-1 None repaired tubes and inspect Plug defective, 100% of the C-2 repaired tubes.
Perform action f ;r C-3 result C-3 of first Inspect all d
bes
['p k Other SG is C-1 None n
A minimum of plug defective 20% of the repaired tubes, sleeves.
and inspect 20%
Perform acti.on of the sleeves for C-2 result Other SG is C-2 of first in the other SG.
sample.
C-3 Notification to Inspect all NRC pursuant to repaired tubes in both SG's 50.72 (b)(2) of 10CFR Part 50 and plug defective
{
Other SG is C-3 repaired tubes.
i Notification to NRC pursuant to 50.72 (b)(2) of l
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(contint.ed) i f
. SAN ONOFRE--UNIT 2 5.0-19b Amendment No. 140
)
._ O
Procedures, Programs, and Manuals 5.5
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5.5 Procedures, Programs, and Manuals 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) 5.5.2.11.1 The inservice inspection may be limited to one SG on a rotating schedule encompassing 6% of the tubes if the results of the first or previous inspections indicate that all SGs are performing in a like manner. Note that under some circumstances, the operating conditions in one SG may be found to be more severe than those in the other SG. Under such circumstances the sample sequence shall be modified to inspect the most severe conditions.
5.5.2.11.2 The other SG not inspected during the first inservice inspection shall be inspected. The third and subsequent inspections should follow the instructions described in Specification 5.5.2.11.1 above.
5.5.2.12 Ventilation Filter Testing Program (VFTP)
This Program establishes the required testing of the Engineered Safety Feature filter ventilation systems, " Control Room Emergency Air Cleanup System" and " Fuel Handling Building Post-accident Cleanup Filter System," in accordance with Regulatory Guide 1.52, Revision 2, and ASME N510-1989. The frequency of testing shall be in accordance with Regulatory Guide 1.52, Revision 2.
As a minimum the VFTP program shall include the following:
a.
Inplace testing of the high efficiency particulate air (HEPA) filters to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ASME N510-1989; and b.
Inplace testing of the charcoal adsorber to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ASME N510-1989; and c.
Laboratory testing of charcoal adsorber samples obtained in accordance with Regulatory Guide 1.52, Revision 2 and tested at the appropriate temperature and relative humidity in accordance with ASTM D3803-1989 to show acceptable methyl iodide penetration; and d.
Testing to demonstrate the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers, when tested at the appropriate system flowrate, is acceptable in accordance with Regulatory Guide 1.52, Revision 2, and ASME N510-1989.
S l
(continued)
SAN ON0fRE--UNIT 2 5.0-19c Amendment No. 140
Reporting Requirements 5.7 5.7 Reporting Requirements (continued)
)
5.7.2 Special Reoorts Special Reports may be required covering inspection, test, and j
maintenance activities. These special reports are determined on an I
I individual basis for each unit and their preparation and submittal are designated in the Technical Specifications.
Special Reports shall be submitted to the U. S. Nuclear Regulatory Commission, Attention: Document Control Desk, Washington, D. C.
20555, with a copy to the Regional Administrator of the Regional Office of the NRC, in accordance with 10 CFR 50.4 within the time period specified for each report.
The following Special Reports shall be submitted:
)
a.
When a pre-planned alternate method of monitoring post-I accident instrumentation functions is required by Condition B
)
or Condition H of LC0 3.3.11, a report shall be submitted q
within 30 days from the time the action is required. The report shall outline the action taken, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the function to OPERABLE status.
I b.
Any abnormal degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken, c.,
Following each inservice inspection of steam generator (SG) tubes, in accordance with the SG Tube Surveillance Program, the number of tubes plugged and tubes sleeved in each SG shall be r2 ported to the NRC within 15 days. The complete results of the SG tube inservice inspection shall be submitted to the NRC within 12 months following the completion of the inspection. The report shall include:
1.
Number and extent of tubes and sleeves inspected, and 2.
Location and percent of wall-thickness penetration for each indication of an imperfection, and 3.
Identification of tubes plugged and tubes sleeved.
(continued) l SAN ONOFRE--UNIT 2 5.0-30 Amendment No. 127,140
p reg O
t UNITED STATES 3
]
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. was m1
$9*****
SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA THE CIW OF ANAHEIM. CALIFORNIA DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STAT!ON. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.132 License No. NPF-15 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southem California Edison Company, et al.
(SCE or the licensee) dated September 16,1997, as supplemented by letter dated February 23,1998, 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 smendment 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.
l w____-___________=___:______.
.=
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-15 is hereby amended to read as follows:
(2)
Technical sinacifications The Technical Specifications contained in Appendix A and the Environrrantal Protection Plan contained h Appendix B, as revised through Amendment No.
132, are hereby incorporated in the license. Southem Califomia Edison Company 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 is to be implemented within 30 days of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION J
s W. Clifford, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
August 26, 1998 l
L_-__-__-_-________-________.
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 132 TO FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Revise Appendix A Technical Specificat. As by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by Amendment number and contain marginal lines indicating the arens of change.
REMOVE INSERT 3.4-37 3.4-37 5.0-13 5.0-13 5.0-14 5.0-14 5.0-15 5.0-15 5.0-16 5.0-16 5.0-17 5.0-17 5.0-18 5.0-18 5.0-19 5.0-19 5.0-19a 5.0-19b 5.0-19c 5.0-30 5.0-30 i
I l
3.4.13 3.4 REACTORCOOLANTSYSTEM(RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:
a.
No pressure boundary LEAKAGE; b.
I gpm unidentified LEAKAGE; c.
10 gpm identified LEAKAGE; NOTE:
With no SG sleeving installed, d. and e. apply.
Following installation of any sleeving in any SG, d.
and e. do not apply and f. does apply.
l d.
I gpm total primary to secondary LEAKAGE through all steam generators (SGs); and e.
720 gallons per day (1/2 gpm) primary to secondary LEAKAGE through any one SG.
f.
With steam generator sleeving installed ir any SG, 150 gallons per day primary to secondary LEAKAGE through any one SG.
APPLICABILITY:
MODES 1, 2, 3, end 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I
A.
RCS LEAKAGE not within A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> limits for reasons within limits.
other than pressure boundary LEAKAGE.
B.
Required Action and B.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A AND not met.
B.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> l
Pressure boundary LEAKAGE exists.
SAN ONOFRE--UNIT 3 3.4 37 Amendment No. 116,132 I
L I
Procedures, Programs, and Manuals 5.5 w
i 5.5~ Procedures, Programs, and Manuals
]
5.5.2.8 Primary Coolant Sources Outside Containment Program (continued) system (post-accident sampling return piping only). The program shall include the following:
a.
Preventive maintenance and periodic visual inspection requirements; and I
b.
Integrated leak test requirements for each system at refueling cycle intervals or less.
l 5.5.2.9 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containment, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. Program itself is relocated to the LCS.
5.5.2.10 Inservice Testing Program
)
This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components including applicable supports. Program itself is relocated to the LCS.
5.5.2.11 Steam Generator (SG) Tube Surveillance Program i
This program provides controls for monitoring SG tube degradation.
Each SG shall be demonstrated OPERABLE by meeting the requirements.
of Specification 5.5.2.11 and by meeting an augmented inservice inspection program based on a modification of Regulatory Guide 1.83, Revision 1, which includes at least the following:
a.
SG Sample Selection and Inspection Each SG shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of SG specified in Tables 5.5.2.11-1 and 5.5.2.11-2.
l b.
SG Tube Sample Selection and Inspection The SG tube and sleeve minimum sample size, inspection result l
classification, and the corresponding action required shall be as specified in Tables 5.5.2.11-1 and 5.5.2.11-2.
The inservice ins >ection of SG tubes and sleeves shall be performed at tie frequencies specified in Specification 5.5.2.11.e and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 5.5.2.11.f.
The tubes selected.for each inservice inspection shall include at least 3% of the total t
(continued)
SAN ONOFRE--UNIT 3 5.0-13 Amendment No. 116,132 L-
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) number of tubes in all SGs; the tubes selected for these inspections shall be selected on a random basis.except:
1.
Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 50% of the tubes inspected shall be from the critical areas; 2.
The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each SG shall include:
a)
All non-repaired tubes that previously had l
detectable wall penetrations (greater than 20%),
b)
Tubes in those areas where experience has indicated potential problems, and 1
c)
A tube inspection (pursuant to Specification 5.5.2.11.f) shall be performed on each selected tube.
If any selected tube does not permit the I
passage of the eddy current probe for a tube 1
inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube 1
inspection.
3.
All sleeves shall be inspected with eddy current prior to initial operation. This includes pressure retaining portions of the parent tube in contact with the sleeve, the sleeve-to-tube weld and the pressure retaining portion of the sleeve.
4.
Following the preservice inspection, 20% of sleeves that have been in service for a full cycle of operation shall be inspected. The sleeves shall be selected on a random basis.
If indications of degradation are found in the sample the inspection sample shall be expanded. Table 5.5.2.11-2 contains the requirements for sample expansion.
1 l
l l
l (continued)
SAN ONOFRE--UNIT 3 5.0-14 Amendment No. 116,132 l
l L__----__--------
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) c.
Examination Results The results of each sample inspection shall be classified into l
one of the following three categories:
i C-1 Less than 5% of the total tubes inspected are degraded tubes-and none of the inspected tubes are defective.
j C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.
i C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.
This classification shall also apply to sample inspections of sleeves.
.........................---N0TE--------------------------
In all inspections, previously degraded non-repaired tubes l
must exhibit significant (greater than 10%) further wall l
penetrations to be included in the above percentage calculations.
d.
Supplemental Sampling Requirements l
The tubes selected as the second and third samples (if required by Table 5.5.2.11-1) may be subjected to a partial tube inspection provided:
1.
The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found, and 2.
Tne inspections include those portions of the tubes where imperfections were previously found.
(continued)
SAN ON0FRE--UNIT 3 5.0-15 Amendment No. 116.132
Procedures, Programs, and Manuals 5.5 5.5, Procedures, Programs, and Manuals 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) e.
Inspection Frequency The above required inservice inspections of the non-repaired SG tubes shall be performed at the following frequencies:
1.
The first inservice inspection shall be performed after 6 effective full power months but within 24 calendar months of initial critically. Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the-previous inspection.
If two' consecutive inspections, not including the preservice inspection, result in all inspections results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months; 2.
If the results of the inservice inspection of a SG conducted in accordance with Table 5.5.2.11-1 at 40-month intervals fall in Category C-3, the inspection shall be increased to at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 5.5.2.11.e.1, the interval may then be l
extended to a maximum of once per 40 months; and 3.
Additional, unscheduled inservice inspections shall be performed on each SG in accordance with the first sample inspection specified in Table 5.5.2.11-1 during the shutdown subsequent to any of the following conditions:
a)
Primary-to-secondary tubes leak (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Technical Specification 3.4.13, or b)
A seismic occurrence greater than the Operating Basis Earthquake, or c)
A loss-of-coolant accident requiring..:tuation of the Engineered Safety Features, or d)
A main steam line or feedwater line break.
(continued)
SAN ONOFRE--UNIT 3 5.0-16 Amendment No. 116,132
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) 4.
The provisions of Technical Specifications Surveillance Requirement 3.0.2 are applicable to SG Tube Surveillance inspection frequencies except those established by Category C-3 inspection results.
The above required inservice inspections of SG tubes repaired by sleeving shall be performed at the following frequencies:
1.
Steam generator tube sleeves shall be inspected prior to initial operation and in service. The initial operating period before the initial inservice sample inspection shall not be shorter than six months nor longer than 24 months. The inspections of sleeves shall be configured to ensure that each individual sleeve is inspected at least once in 60 months.
2.
If the results of the inservice inspection of SG tube sleeves conducted in accordance with Table 5.5.2.11-2 l
fall in category C-3, the inspection frequency shall be increased to ensure that each remaining sleeve is inspected at least once in 30 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria for Category C-1.
f.
Acceptance Criteria 1.
Terms as used in this specification will be defined as follows:
a)
Degradation - A service-induced cracking, wastage, wear, or general corrosion occurring on either inside or outside of a tube; b)
Degraded tube - A tube containing imperfections greater than or equal to 20% of the nominal wall thickness cause by degradation; c)
% Degradation - The percentage of the tube wall thickness affected or removed by degradation; d)
Defect - An imperfection of such severity that it exceeds the repair limit. A tube containing a defect is defective.
(continued)
SAN ONOFRE--UNIT 3 5.0-17 Amendment No. 116,132 l
A
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) e)
Imperfection - An exception to the dimensions, finish, or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections; f)
Repair Limit - The imperfection depth at or beyond l
which the tube shall be removed from service or repaired and is equal to 44% of the nominal tube wall thickness; Sleeves shall be removed from service upon detection of service-induced degradation of the sleeve material or any portion of the sleeve-to-tube weld.
g)
Preservice Inspection - An inspection of the full length of each tube in each SG performed by eddy-current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be performed prior to initial MODE 1 operating using the equipment and techniques expected to be used during subsequent inservice inspections. These examinations may be performed prior to steam generator installation. Similarly, for tube repair by sleeving, an inspection of the full length of the pressure boundary portion of i
the sleeved area shall be performed by eddy l
current techniques prior to service. This includes pressure retaining portions of the parent tube in contact with the sleeve, the sleeve-to-tube weld, and the pressure retaining portion of the sleeve.
h)
Tube Inspection - An inspection of the SG tube 1
from the point of entry (hot leg side) completely i
around the U-bend to the top support of the cold j
leg; and i)
Unserviceable - The condition of a tube if it leaks or contains a defect.large enough to affect its structural integrity in the event of an Operational Basis Earthquake, a loss-of-coolant accident, or a steam line of feedwater line break i
accident as specified in Specification 5.5.2.11.e.
l (continued) 1 SAN ONOFRE--UNIT 3 5.0-18 Amendment No. 116,132 i
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals l
5.5.2.11 Steam Generator (SG) Tube Surveillance Program (continued) j)
Tube Repair - refers to a process that reestablishes tube serviceability. Acceptable tube repairs will be performed by the following process:
l l
TIG welded sleeving as described in ABB/CE Topical Report, CEN-630-P, Rev. 2, is currently approved by the NRC.
l Tube repair includes the installation by welding of the sleeves, heat treatment in accordance with l
CEN-630-P, Rev. 2, to remove the stresses that are introduced by the sleeve installation, acceptance l
testing of the sleeve, and nondestructive examination for future comparison. Tube repair can be performed on certain tubes that have been F
previously plugged as a corrective or preventive measure. A tube inspection of the full length of the tube shall be performed on a previously plugged tube prior to returning the tube to service.
l 2.
The SG shall be determined OPERABLE after completing the corresponding actions (plug or repair all tubes exceeding the repair limit and all tubes containing through-wall cracks, and plug all sleeved tubes that I
exceed the repair criteria) required by Tables 5.5.2.11-l 1 and 5.5.2.11-2.
I g.
Reports The content and frequency of written reports shall be in accordance with Technical Specification 5.7.2, "Special l
Reports."
l (continued)
SAN ONOFRE--UNIT 3 5.0-19 Amendment No. 116.132 1
___________________j
Procedures, Programs, and Manuals 5.5-e 5.5 : Procedures, Programs, and Manuals 5.5.2.11 Steam Generator Tube Surveillance Program TABLE 5.5.2.11-1 (page 1 of 1)
STEAM GENERATOR TUBE INSPECTION SUPPLEMENTAL SAMPLING REQUIREMENTS
'I ist semple Inspection 2nd semple Inspection 3rd semple Inspection Action Action Action Senple Site Result Required Result Required Result Required A mininun of C1 None N/A N/A N/A N/A S tutms per SG C2 Plug or repelr C1 None N/A N/A by sleeving defective t e es Plug or repair by N/A N/A and inspect en eteeving additionet 23 defective tubes C-1 N/A s in this pect M en C2 Plug or repair s
ng tubes in this SG.
9p tubes.
C-3 Perform action for C 3 result of first senpt e.
C3 Perform action N/A N/A for C 3 result of first senple.
C-3 Inspect ett Att other None N/A N/A tubes in this SGs C 1 SG plug or repelr by ecf[veths some SGs C-2 Perform action N/A N/A but no other for C 2 result of and inspect 28 isC3 second souple, tees in each.
other SG.
Additional Inspect att tubes N/A N/A j
Notification to SG is C-3 in each SG and y
NRC pursuant to P, lug or repair by 10CFR50.72 tseving defective tubes.
]
Notification to NRC pursuert to 10CFR50.72.
S = 3 N/n % Where N is the number of SGs in the unit and n is the number of SGs inspected during inspection period.
(continued)
SAN ON0FRE--UNIT 3 5.0-19a Amendment No. 132 l
l I
l
Procedures, Programs, and Manuals 5.5 i
e 5.5 Procedures, Programs, and Manuals
~
Table 5.5.2.11-2(page1of1) l Steam Generator Sleeved Tube Inspection 1st Sample Inspection 2nd Sample Inspection Sample Size Result Action Required Result Action Required l
C-1 None N.A.
N.A.
I Plug defective C-1 None repaired tubes j
and inspect Plug defective,
{
100% of the C-2 repaired tubes.
{
C-2 sleeves in this SG Perform action for C-3 result' C-3 of first sample.
Inspect all repaired tubes Other SG is C-1 None in this SG, A minimum of plug defective 20% of repaired tubes, sleeves.
and inspect 20%
Perform action of the sleeves for C-2 result Other SG is C-2 in the other of first SG.
sample.
C-3 Notification to Inspect all NRC pursuant to repaired tubes 50.72 (b)(2) of in both SG's 10CFR Part 50 and plug defective Other SG is C-3 repaired tubes.
Notification to NRC pursuant to 50.72 (b)(2) of 10CFR Part 50 (continued)
SAN ONOFRE--UNIT 3 5.0-19b Amendment No. 132
Procedures, Programs, and Manuals.
5.5 h.
l 5.5 Procedures, Programs, and Manuals i
5.5.2;11-Steam Generator (SG) Tube Surveillance Program (continued) 5.5.2.11.1 The inservice inspection may be limited to one SG on a rotating schedule encompassing 6% of the tubes if the results of the first or previous inspections indicate that all SGs are performing in a like manner. Note that under some. circumstances, the operating g
conditions in one SG may be found to be more severe than those in t
the other SG. Under such circumstances the sample sequence shall be i
modified to inspect the most severe conditions.
5.5 2.11.2 The other SG not inspected during the first inservice inspection shall be inspected. The third and subsequent inspections should l
. follow the instructions described in Specification 5.5.2.11.1 above.
5.5.2.12 Ventilation Filter Testing Program (VFTP)
.This Program establishes the required testing of the Engineered l
Safety Feature filter ventilation systems, " Control Room Emergency l
Air. Cleanup System" and " Fuel Handling Building Post-accident i
Cleanup Filter System," in accordance with Regulatory Guide 1.52, Revision 2, and ASME N510-1989. The frequency of testing shall be in accordance with Regulatory Guide 1.52 Revision 2.
As a minimum the VFTP program shall include the following:
a.
Inplace testing of the high efficiency particulate air (HEPA) j filters to demonstrate acceptable penetration and system l
bypass when tested at the appropriate system flowrate in l
accordance with Regulatory Guide 1.52, Revision 2, and ASME l
N510-1989; and i
b.
Inplace testing of the charcoal adsorber to demonstrate acceptable penetration and system bypass when tested at the appropriate system flowrate in accordance with Regulatory Guide 1.52, Revision 2, and ASME N510-1989; and c.
Laboratory testing of charcoal adsorber samples obtained in accordance with kegulatory Guide 1.52, Revision 2 and tested at the appropriate temperature and relative humidity in accordance with ASTM D3803-1989 to show acceptable methyl I
iodide penetration; and d.
Testing to demonstrate the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers, when tested at the appropriate system flowrate, is acceptable in accordance with Regulatory Guide 1.52, Revision 2, and ASME N510-1989.
l (continued)
SAN ONOFRE--UNIT 3 5.0-19c Amendment No. 132
i Reporting Requirements 5.7
~
5.7 Reporting Requirements (continued) 5.7.2 Special Reports Special Reports may be required ccvering inspection, test, and maintenance activities. These special reports are determined on an l
individual basis for each unit and their preparation and submittal are designated in the Technical Specifications.
Special Reports shall be sbbmitted to the U. S. Nuclear Regulatory i
Commission, Attention: Document Control Desk, Washington, D. C.
I 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, in accordance with 10 CFR 50.4 within the time l
period specified for each report.
The following Special Reports shall be submitted:
a.
When a pre-planned alternate method of monitoring post-accident instrumentation functions is required by Condition B l
or Condition H of LC0 3.3.11, a report shall be submitted within 30 days from the time the action is required. The report shall outline the action taken, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the function to OPERABLE status.
l b.
Any abnormal degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on racking, and the corrective action taken.
c.
Following each inservice inspection of steam generator (SG) tubes, in accordance with the SG Tube Surveillance Program, the number of tubes plugged and tubes sleeved in each SG shall be reported to the NRC within 15 days. The complete results of the SG tube inservice inspection shall be submitted to the NRC within 12 months following the completion of the inspection. The report shall include:
1.
Number and extent of tubes and sleeves inspected, and 2.
Location and percent of wall-thickness penetration for each indication of an imperfection, and 3.
Identification of tubes plugged and tubes sleeved.
(continued)
SAN ON0FRE--UNIT 3-5.0-30 Amendment No. 116,132