ML20235C993
| ML20235C993 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/18/1987 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235C996 | List: |
| References | |
| TAC-64210, TAC-64211, NUDOCS 8709250079 | |
| Download: ML20235C993 (21) | |
Text
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- UNITED STATES l
-[
.g NUCLEAR. REGULATORY COMMISSION 5
-[
WASHINGTON D. C,20555
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ALABAMA POWER COMPANY DOCKET N0. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 72 License No NPF-2 i
I 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application-for amendment by Alabama Power Company (the licensee), dated December 19, 1986, supplemented May 4 July 10, and August 25, 1987, complies with the standards and requirements I
of the Atomic Energy Act of 1954, as amended (the Act), and j
the Comission's rules and regulations set forth in 10 CFR j
Chapter I; B.
The facility will operate in confonnity with the application, as 3
amended, the provisions of the Act, and the 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 Comission's regulations; D.
The issuance of this license 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 Comission'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-2 is hereby amended to read as follows:
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,, (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 63, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of receipt of the amendment.
FOR THE NUCLEAR REGULATORY COMMISSION ls/
Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications Date of Issuance: September 18, 1987 l
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' ATTACHMENT TO LICENSE AMENDMENT NO. 72 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 f
Replace the following pages of the Appendix "A" Technical Specifications-with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 3/4 4-9 3/4 4-9 3/4 4-10 3/4 4-10 3/4 4-12 3/4 4-12 3/4 4-13 3/4 4-13 S/4 4-15 3/4 4-15 B3/4'4-3 B3/4 4-3 B3/4 4-3a j
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R ACTOR C00' ANT SYSTEM L
3/4.4.6 ' STEAM GENERATORS a
LIMITING CONDITION FOR OPERATION
.l
---.--==.......--==......-------....=..o j
3.4.6 Each steam generator shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4 ACTION:
With one or more steam generators inoperable, restore the inoperable above 200*F.
generator (s) to OPERABLE status prior to increasing Tavg I
SURVEILLANCE REQUIREMENTS u.y.----------------------------------------
1 I
4.4.6.0 Each steam generator shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5.
j 4.4.6.1' Steam Generator Sample Selection and Inspection - Each. steam generator i
shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.
l Steam Generator Tube # ample Seler. tion and Inspection - The steam I
4.4.6.2 S
generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table 4.4-2.
The inservice inspection of steam generator tubes shall be perfonned at the frequencies specified in Specification 4.4.6.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.6.4.
The tubes selected for each inservice inspection shall include at least 3% of the total number of tubes in all steam generators. When applying the exceptions of 4.4.6.2.a through 4.4.6.2.c, previous defects or imperfections in the area repaired by sleeving are not considered an area requiring reinspection. The tubes selected for these inspections shall be selected on a random basis except:
a.
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 these critical areas.
b.
The first sample of tubes selected for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
- When referring to a steam generator tube, the sleeve shall be considered a part of the tube if 6ne tube has been repaired per Specification 4.4.6.4.a.9.
FARLEY-UNIT 1 3/4 4-9 AMENDMENT N0. U, 72
/
REACTOR C0OLANT SYSTEM-SURVEILLANCEREQUIREMENTS(Continued).
1.
All nonplugged tubes that previously had detectable wall.
~
penetrations greater than 20%.-
j 2.
Tubes' in those areas where. experience has indicated potential problems.
3.
At least 3% of the total number of sleeved tubes in all three steam generators or all of the sleeved tubes in the generator chosen for i
the inspection program, whichever is less. These inspections will include both the tube and the sleeve.-
4 A tube inspection (pursuant to Specification 4.4.6.4.a.8) shall be performed on each selected tube.
If any selected tube does not.
1 permit the passage of the eddy. current probe for a tube or sleeve inspection, this shall be recorded 'and an adjacent-tube shall be selected and subjected to a tube inspection.
c.
The tubes selected as.the second and third samples (if required by Table 4.4-2) during each inservice inspection. may be subjected to a partial tube inspection provided:
q 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, i
2.
The inspections include those portions of the tubes where imperfections were previously found.
The results of each sample inspection shall be classified into one of the following three categories:
Category Inspection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
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.
C-3 More thah 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.
Note:
In all inspections, previously degraded tubes or sleeves must-exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.
FARLEY-UNIT 1 3/4 4-10 AMEN 0 MENT NO. 3, 72
R$ACTORCOOLANTSYSTEM t
SURVEILLANCE REQUIREMENTS (Continued) 4.4.6.4 Acceptance Criteria a.
As used in this Specification:
1.
Imperfection means an exception to the dimensions, finish or contour of a tube or sleeve from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal wall thickness,-if detectable, may be considered as imperfections.
l 2.
Degradation means a service-induced cracking, wastage, wear or i
general corrosion occurring on either inside or outside of a tube or sleeve.
3.
Degraded Tube means a tube, including the sleeve if the tube has been repaired, that contains imperfections greater than or equal to 20% of the nominal wall thickness caused by degradation.
4.
% Degradation means the percentage of the tube or sleeve wall 1
tnickness affected or removed by degradation, j
5.
Defect means an imperfection of such severity that it exceeds the j
plugging or repair limit. A tube or sleeve containing a defect is defective.
I 6.
plugging or Repair Limit means the imperfection depth at or beyond which the tube shall be repaired (i.e., sleeved) or removed from
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service by plugging and is greater than or equal to 40% of the nominal tube wall thickness. For a tube that has been sleeved, through wall penetration of greater than or equal to 31% of sleeve nominal wall thickness in the sleeve requires the tube to be removed from service by plugging.
7.
Unserviceable describes the condition of a tube or sleeve if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.6.3.c, above.
8.
Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg. For a tube that has been repaired by sleeving, the tube inspection should include the sleeved portion of the tube.
9.
Tube Repair refers to mechanical sleeving, as described by Westinghouse report WCAP-11178 Rev.1, which is used to maintain a tube in service or return a tube to service. This includes the removal of plugs that were installed as a corrective or preventive measure.
FARLEY-UNIT 1 3/4 4-12 AMENDMENT N0. U, 72
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
- 10. Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to service to establish a baseline condition of the tubing. This inspection shall be' performed af ter the field hydrostatic test and prior ~ to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
b.
The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or repair of all tubes exceeding the plugging or repair limit) required by Table 4.4-2.
4.4.6.5 Reports l
l a.
Following each inservice inspection of -steam ' generator. tubes, the number of tubes plugged or repaired in each steam generator shall be' reported to the Commission within 15 days of the completion of the plugging or repair effort.
b.
The complete results of the steam. generator tube and sleeve inservice inspection shall be submitted to the Commission in a Special Report pursuant to Specification 6.9.2 within 12 months following the completion of the inspection. This Special Report shall include:
1.
Number and extent of tubes and sleeves inspected.
2.
Location and percent of wall-thickness penetration for each indication of an imperfection.
l 3.
Identification of tubes plugged or repaired.
c.
Results of steam generator tube. inspections which f all into Category C-3 shall be considered a REPORTABLE EVENT and shall be reported pursuant to 10CFR50.73 prior to resumption of plant operation. The written report sh'all provide a description of investigations conducted to determine the cause of the tube degradation and corrective measures taken to prevent recurrence.
I i
FARLEY-UNIT 1 3/4 4-13 AMENDMENT NO. Es, 72
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3/4.4.6 STEAM GENERATORS i
I The Surveillance Requirements for inspection of the steam generator tubes j
ensure that the structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.
Inservice inspection of steam generator tubing is essential in order to maintain surveillance c' the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice conditions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature I
and cause of any tube degradation so that corrective measures can be taken.
I The plant is expected to be operated in a manner such that the secondary l
coolant will be maintained within those chemistry limits found to result in
)
l negligible corrosion of the steam generator tubes.
If the secondary coolant l
chemistry is not maintained within these limits, localized corrosion may likely l
ru ult to stress corrosion cracking. The extent of cracking during plant i
operation would be limited by the limitation of steam generator tube leakage between the primary coolant system and the secondary coolant system I
(primary-to-secondary leakage = 500 gallons per day per steam generator).
l Cracks having a primary-to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents. Operating plants have demonstrated that primary-to-secondary leakage of 500 gallons per day per steam generator can readily be detected by radiation monitors of steam generator l
blowdown. Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged or repaired.
l Wastage-type defects are unlikely with proper chemistry treatment ~ of the secondary coolant. However, even if a defect should develop in service, it l
will be found during scheduled inservice steam generator tube examinations.
Plugging or repair will be required for all tubes with imperfections exceeding 40% of the tube nominal wall thickness.
If a sleeved tube is found to have through wall penetration of greater than or equal to 31% of sleeve nominal wall thickness in the sleeve, it must be plugged. The 31% limit is derived from R.G.1.121 calculations with 20% added for conservatism. The portion of the tube and the sleeve for which indications of wall degradation must be evaluated can be summarized as follows:
- 1. Indications of degradation in the entire length of the sleeve must be evaluated against the sleeve plugging limit.
- 2. Indication of tube degradation of any type including a complete guillotine break in the tube between the bottom of the upper joint and the top of the lower roll expansion does not require that the tube be removed from service.
FARLEY-UNIT 1 B3/4 4-3 AMEN 0 MENT N0. E/, 72
I J
REACTOR COOLANT SYSTEM BASES
=======,,
............... -............................,,,,,,, m,,,
i
- 3. The tube plugging limit continues to apply to the portion of the tube in the entire upper joint region and in_ the lower roll expansion. As noted above the sleeve plugging limit applies to these areas also.
- 4. The tube plugging limit continues to apply to that portion of the tube above the top of the upper joint.
Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the original tube wall thickness.
Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results will be reported to the Commission pursuant to 10CFR50.73 prior to resumption of plant operation. _ Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessa ry.
k FARLEY-UNIT 1 B3/4 4-3a AMENDMENT NO. 72.
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. UNITED STATES g
NUCLEAR REGULATORY COMMISSION 5
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ALABAMA POWER COMPANY DOCKET NO. 50-364
-JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE
)
Amendment No. 63 l
1.icense No. NPF-8 i
1.
The Nuclear Regulatory Comission'(the Comission) has found that:
A.
.The application for amendment by Alabama Power Company (the licensee), dated December 19, 1986,. supplemented May 4 July 10,.
i and August 25, 1987, 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; B.
The facility will operate in conformity with the application the provisions of the Act, and the 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 Comission's regulations; D.
The issuance of this license amendment will not be inimical to the comon 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 Comission'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-8 is hereby amended to read as follows:
u_________.________________________
a, C
ATTACHMENT T0. LICENSE AMENDMENT N0.' 63~
1 TO FACILITY OPERATING LICENSE NO. NPF-8 l
DOCKET NO. 50-364 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages'as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages
' 3/4 4-9 3/4 4-9.
3/4 4-10 3/4 4-10 3/4 4-12 3/4-4-12 l
3/4 4-13 3/4 4-13 l
3/4 4-15 3/4 4-15 B3/4 4-3 B3/4 4-3 B3/4 4-3a 1
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e g REACTOR COOLANT SYSTEM j
l 3/4.4.6' STEAM GENERATORS-LIMITING CONDITION FOR OPERATION 3.4.6 Each steam generator shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one or more steam. generators inoperabl.e, restore the inoperable.
1 generator (s) to OPERABLE status prior to increasing Tavg.above 200*F.
SURVEILLANCE REQUIREMENTS
.soms 4.4.6.0. Each steam generator shall be demonstrated OPERABLE by performance of.
I the following augmented inservice inspection program and the requirements of Specification 4.0.5.
l 4.4.6.1 Steam Generator Sample Selection and Inspection - Each steam generator shall be determined OPERABLE during shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 4.4-1.
4.4.6.2 Steam Generator Tube # Sample Selection and Inspection
.The steam l
generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as specified in Table.4.4-2..The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.4.6.3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.4.6.4.
The-l tubes selected for each inservice inspection shall include at least 3% of the' l
total number of tubes in all steam generators. When applying the exceptions of 4.4.6.2.a through 4.4.6.2.c, previous defects or imperfections in the area repaired by sleeving are not considered an area requiring reinspection. The tubes selected for these inspections shall be selected on a random basis except:
a.
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 these critical areas.
b.
The first sample of tubes select $d for each inservice inspection (subsequent to the preservice inspection) of each steam generator shall include:
- When referring to a steam generator tube, the sleeve shall be considered a part of the tube if the tube has been repaired per Specification 4.4.6.4.a.9.
FARLEY-UNIT 2 3/4 4-9 AMENDMENT NO. 63 f
~ 4
- ,iEACTORCOOLANTSYSTEM SURVEILLANCEREQUIREMENTS(Continued) 1.
All nonplugged tubes that previously had detectable wall penetrations greater than 20%.
2.
Tubes in those areas where experience has indicated potential probl ems.
3.
At least 3% of the total number of sleeved tubes in all three steam generators or all of the sleeved tubes in the generator chosen for the inspection program.whichever is less. These inspections will include both the tube and the sleeve.
4.
A tube inspection (pursuant to Specification 4.4.6.4.a.8) shall be performed on each selected tube.
If any selected tube does not permit the passage of the eddy current probe for a tube or sleeve inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a tube inspection, l
c.
The tubes selected as the second and third samples (if required by
~
l Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:
l l
2.
The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.
2.
The inspections ine.lude those portions of the tubes where imperfections were previously found.
The results of each sample inspection shall be classified into one of the following three categories:
Category Inspection Results C-1 Less than 5% of the total tubes inspec9.ed are degraded tubes and none of the inspected tubes are defective.
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.
C-3 More than 10% of the total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.
Note:
In all inspections, previously degraded tubes or sleeves must L
exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.
FARLEY-UNIT 2 3/4 4-10 AMENDMENT NO. 63 l
l e
5 L__________._______._.___
f j
SURVEILLANCE _ REQUIREMENTS (Continued) l l
1.
All nonplugged tubes that previously had detectable wall penetrations greater than 20%,.
2.
Tubes in those areas where experience has indicated potential problems.
3.
At least 3% of the total number of sleeved tubes in all three steam generators or all of the sleeved tubes in the generator chosen for 4
the inspection program, whichever is less. These inspections will include both the tube and the sleeve.
4.
A tube inspection (pursuant to Specification 4.4.6.4.a.8) shall be performed on each selected tube.
If any. selected' tube does not permit the passage of the eddy current probe for a tube or sleeve inspection, this shall be recorded and an adjacent tube shall be selected and subjected to a. tube inspection.
c.
The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to-a partial tube inspection provided:
l 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.
2.
The inspections include those portions of the tubes where imperfections were previously found.
The results of each sample inspection shall be classified into one of the following three categories:
Category Inspection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.
I 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.
C-3 More than 10% of the total tubes inspected are I
degraded tubes or more than 1% of the inspected tubes are defective.
Note:
In all inspections, previously degraded tubes or sleeves must l
exhibit significant (greater than 10%) further wall penetrations to be included in the above percentage calculations.
l FARLEY-UNIT 2 3/4 4-10 AMENDMENT NO. 63 Y
~____________m
' REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.6.4 AccepN.nce Criteria a.
As used in this Specification:
1.
Imperfection means an exception to.the dimensions, finish <or contour of c tube.or sleeve from that required by fabrication drawings or specifications. Eddy-current testing indications below r.
20% of the nominal wall thickness, if detectable, may be considered
)
as imperfections.
2.
Degradation means' a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube or sleeve.
3.
Degraded Tube means a tube, including the sleeve if the tube has
['
H been repaired, that contains imperfections greater than.or equal to 20% of the nominal wall thickness caused.by degradation.
4.
% Degradation.means the percentage of the tube or sleeve wall thickness affected or removed by degradation.
5.
Defect means an imperfection of such severity that it exceeds the' plugging or repair limit. A tube or sleeve containing a defect is defective.
6.
Plugging or Repair Limit means the imperfection depth at.or beyond which the tube shall be repaired (i.e., sleeved) or removed from l
service by plugging and is greater than or equal to 40% of the nominal tube wall thickness. For a tube that has been sleeved, l
l through wall penetration of greater than or equal to 31% of sleeve nominal wall thickness in the sleeve requires the tube to be l
removed from service by plugging.
7.
Unserviceable describes the condition of a tube or sleeve if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a.
loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.6.3.c, above.
8.
Tube Inspection means an inspection of the steam generator tube from tne point of entry (hot' leg side) completely around the U-bend i
to the top support of the cold leg. For a tube that has been repaired by sleeving, the tube inspection should include the sleeved portion of the tube.
9.
Tube Re> air refers to mechanical sleeving, as described by l
Westing 1ouse report WCAP-11178 Rev.-1, which is used to maintain a-tube in service or return a tube to service. This includes the.
removal of plugs that were installed as a corrective or preventive
- measure, i
FARLEY-UNIT 2 3/4 4-12 AMENDMENT NO. 63 4
---_-_..__.~_=-__------L--
__________l___
~
,4 R ACTOR COOLANT SYSTEM-SURVEILLANCE REQUIREMENTS (Continued) 10.
Preservice Inspection means an inspection of the full length of each tube:in each steam generator performed by ' eddy. current techniques prior to~ service to establish a baseline condition of the tubing.. This inspection shall be performed. after the field hydrostatic test and prior to initial POWER OPERATION using.the -
equipment and techniques expected to be used during subsequent inservice inspections.
1 b.. The steam generator shall be determined OPERABLE.after completing the-corresponding actions { plug or repair of all-tubes exceeding the j
plugging or repair limit) required by Table 4.4-2.
4.4.6.5 Repo~ts 1
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a.
Following each inservice inspection of steam generator tubes, the j
number of tubes plugged or repaired in.each steam generator shall be.
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reported to the Commission within 15 days of the completion of. the l
plugging or-repair effort.
b.
The complete results of the steam generator tube and sleeve inservice
- l inspection shall be submitted to the Commission in a Special Report-I pursuant to Specification 6.9.2 within 12 months following the completion of tne inspection. This Special Report shall include:
1.
Number and extent 'af tubes and sleeves' inspected.
2.
Location and percent of wall-thickness penetration for each indication of an imperfection.
3.
Identification of tubes plugged or repaired.
c.
Results of steam generator tube inspections which fall into Category C-3 shall be considered a REPORTABLE EVENT and shall be reported pursuant to 10CFR50.73 prior to resumption of plant operation. The written report shall provide a description of investigations conducted to determine the cause of the tube degradation and corrective measures taken to prevent recurrence.
o FARLEY-UNIT 2 3/4 4-13
. AMENDMENT NO. H, 63 L
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.J REACTOR COOLANT SYSTEM BASES
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3/4.4.6 STEAM GENERATORS The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be maintained. The program for inservice inspection of steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1.
Inservice inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or inservice corditions that lead to corrosion.
Inservice inspection of steam generator tubing also provides a means of characterizing the nature and cause of any tube degradation so that corrective measures can be taken.
The plant is expected to be operated in a manner such that the secondary coolant will be maintained within those chemistry limits found to result in negligible corrosion of the steam generator tubes.
If the secondary coolant chemistry is not maintained within these limits, localized corrosion may likely result in stress corrosion cracking. The extent of cracking during plant operation would be limited by the limitation of steam generator tube leakage between the primary coolant system and the secondary coolant system (primary-to-secondary leakage = 500 gallons per day per steam generator).
Cracks having a primary-to-secondary leakage less than this limit during operation will have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated accidents. Operating plants have demonstrated that primary-to-secondary leakage of 500 gallons per day per steam generator can readily be detected by radiation monitors of steam generator blowdown. Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and plugged or repaired.
l Wastage-type defects are unlikely with proper chemistry treatment of the secondary coolant. However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations.
l Plugging or repair will be required for all tubes with imperfections exceeding I
40% of the tube nominal wall thickness.
If a sleeved tube is found to have I
through wall penetration of greater than or equal to 31% of sleeve nominal wall l
thickness in the sleeve, it must be plugged.
The 31% limit is derived from R.G.1.121 calculations with 20% added conservatism. The portion of the tube and the sleeve for which indications of wall degradation must be evaluated can be summarized as follows:
- 1. Indications of degradation in the entire length of the sleeve must be evaluated against the sleeve plugging limit.
- 2. Indication of tube degradation of any type including a complete guillotine break in the tube between the bottom of the upper joint and the top of the lower roll expansion does not require that the tube be removed f rom service.
FARLEY-UNIT 2 B3/4 4-3 AMENDMENT NO. ff,63 l
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+
a REACTOR COOLANT SYSTEM BASES k
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- 3. The tube plugging limit continues to apply to the portion of the tube in the entire upper joint region and in the lower roll' expansion. As noted above the sleeve plugging limit. applies to these areas also.
- 4. The tube plugging limit continues to apply to that portion of the tube above the top of the upper joint.
. Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the q
original tube wall thickness.
i l
Whenever the results of any steam generator tubing inservice inspection fall
.j into Category.C-3, the'se results will be reported to the Commission pursuant to 10CFR50.73 prior to resumption of plant operation. Such cases will be.
J considered by the Cem!nission on a case-by-case basis and may result in a r
l requirement for analjsis, laboratory examinations, tests. additional
]
eddy-current inspection, and revision of the Technical Specifications, if a
necessary. '
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FARLEY-UNIT 2 B3/4 4-3a AMENDMENT NO. 63 Mu-___.m.__ _. _ _ _ _ - _ _ _ _ - _ - _ _ - - - - - - - _ - - _. - _. - -
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-AMENDMENT NO. '/2 TO FACILITY OPERATING LICENSE NO. NPR-2 FARLEY, UNIT 1
+
AMENDMENT NO. (.5 T0. FACILITY OPERATING LICENSE NO. NPF-8 '- FARLEY, UNIT. 2 -
4 DISTRIBUTION:
,j$5 M E W R $ 343, (gDr.cketENoE502364 NRC PDR Local PDR-PD21 r/f o
S. Varga G.'Lainas.
.P. Anderson E. Reeves (2)
OGC-B D. Hagan E. Jordan' J. Partlow T.Barnhart(8)
Wanda Jones r
E. Butcher H. Conrad-ACRS (10)
GPA/PA '
ARM / LIMB 1
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