ML20058C140
| ML20058C140 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/22/1990 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058C145 | List: |
| References | |
| NUDOCS 9011010010 | |
| Download: ML20058C140 (12) | |
Text
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a UNITE D STATES y-g NUCLE AR REGULATORY COMMISSION 1
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ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NVCLEAR PLANT. UNIT 1 l
AMENDMENT TO FACILITY OPERATING LICENSE l
Amendnent No. 85 License No. NPF-2 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Alabama Power Company (the licensee), dated August 16, 1990, 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 i
Chapter I; B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance cf this license amendnent 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-2 is hereby amended to read as follows:
t 9021010010 901022 PDR ADOCK 05000348 P
2 (2) Technical Specifications f
The Technical Specifications contained in Appendices A and B as revised through Amendment No. 85. 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 Original Signed By:
l Elinor G. Adensam. Director Project Directorate 11 1 Division of Reactor Projects. 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 22, 1990 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 85 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Pages Insert Pages 3/4 4-12 3/4 4-12 B 3/4 4-3 B 3/4 4-3 B 3/4 4-3a B 3/4 4-3a i
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REACTOR COOLANT SYSTEM EVHElhEMES.BS92H MSEE.1S m ! m9.........................................
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 vall thickness, if detectable, may be considered as imperfections.
2.
Degradation means a service-induced cracking, vastage, vear 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 been repaire3, that contains imperfections greater than or equal to 20% of the nominal vall thickness caused by degradation.
4.
% Degradation means the percentage of the tube or sleeve vall 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 tle tube shall be repaired (i.e., sleeved) or removed from service by plugging and is greater than or equal to 40% of the nominal tube vall thickness.
For a tube that has been sleeved with a mechanical joint sleeve, through vall penetration of greater than or equal to 31% of sleeve nominal vall thickness in the sleeve requires the tube to be removed from service by plugging.
For a tube that has been sleeved with a velded joint sleeve, through vall penetration greater than or equal to 37% of' sleeve nominal vall thickness in the sleeve between the veld joints 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 1
integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedvater line break as i
specified in 4.4.6.3.c, above.
B.
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 j
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 i
Vesting 1ouse report VCAP-11178 Rev. 1, or laser velded sleeving, as described by Vestinghouse report WCAP-12672, which is used to main-tain a tube in service or return a tube to service.
This includes the removal of plugs that vere installed as a corrective or preventive measure.
j FARLEY-UNIT 1 3/4 4-12 AMENDMENT NO.
26, 72, 85
!e55.....................................................................
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 vill 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 conditions 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.
i The plant is expected to be operated in a manner such that the secondary 1
coolant vill 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 vould 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).
Cracke having a primary-to-secondary leakage less than this limit during operation vill have an adequate margin of safety to withstand the loads imposed during normal operation and by postulated i
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 blovdown.
Leakage in excess of this limit vill require plant shutdown and an unscheduled inspection, during which the leaking tubes vill be located and plugged or repaired.
Vastage-type defects are unlikely with proper chemistry treatment of the secondary coolant.
However, even if a defect should develop in service, it i
vill be found during scheduled inservice steam generator tube examinations.
Plugging or repair vill be required for all tubes with imperfections exceeding 40% of the tube nominal vall thickness.
If a sleeved tube is found to have through vall penetration of greater than or equal to 31%
for the mechanical sleeve and 37% for the laser velded sleeve of sleeve nominal vall thickness in the sleeve, it must be plugged. The 31% and 37%
litits are derived from R.G. 1.121 calculations with 20% added for conserva-tism. The portion of the tube and the sleeve for which indications of vall degradation must be evaluated can be summarized as follows:
a.
Mechanical l
i
- 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 lover roll expansion does not require that the tube be removed from service.
FARLEY-UNIT 1 B3/4 4-3 AMENDMENT NO.
57, 72, 85
RfACTOR COOLANT SYSTEM BA..SES.....................................................................
- 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 ex-pansion. 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.
b.
Laser Velded
- 1. Indications of degradation in the length of the sleeve between the veld joints must be evaluated against the sleeve plugging limit.
- 2. Indication of tube degradation of any type including a complete break in the tube between the upper veld joint and the lover veld joint does not require that the tube be removed from service.
- 3. At the veld joint, degradation must be evaluated in both the sleeve and tube.
- 4. In a joint with more than one veld, the veld closest to the end of the sleeve represents the joint to be inspected and the limit of the sleeve inspection.
i
- 5. The tube plugging limit continues to apply to the portion of the i
tube above the upper veld joint and below the lover veld joint.
l Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the 1
original tube vall thickness, i
Vhenever 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 vill be considered by the Comraission on a case-by-case basis and may result in a j
requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical "necifications, if I
necessary.
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FARLEY-UNIT 1 B3/4 4-3a AMENDMENT NO.
72, 85 1
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UNITED STATES
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l ALABAMA POWER COMPANY l
DOCKET N0. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 78 License No. NPF-8 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Alabama Power Company (the licensee),datedAugust 16, 1990, 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 rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and l
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 i
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;.
andparagraph2.C.(2)ofFacilityOperatingLicenseNo.NPF-8ishereby amended to read as follows:
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-2 (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 78, are hereby incorporated in the license. Alabama Power Company 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 Original Signed By:
Elinor G. Adensam. Director Project Directorate 11 1 Division of Reactor Projects. I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 22, 1990
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ATTACHMENT TO LICENSE AMENDMENT NO. 78 TO FACILITY OPERAT1HG LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Pages insert Pages 3/4 4-12 3/4 4-12 B 3/4 4-3 B 3/4 4-3 B 3/4 4-3a B 3/4 4-3a 1
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REACT 0h COOLANT SYSTEM E!!E! W S!SE.!!921R{Mgg S,[g n g y g,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,
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 belov 20% of the nominal vall thickness, if detectable, may be considered as imperfections.
2.
Degradation means a service-induced cracking, vastage, vear 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 been repaired, that contains imperfections greater than or equal to 20% of the nominal vall thickness caused by degradation.
4.
% Degradation means the percentage of the tube or sleeve vall 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 i
beyond which the tube shall be repaired (i.e., sleeved) or removed from service by plugging and is greater than or equal to 40% of the nominal tube vall thickness. This definition does l
i not apply to the area of the tubesheet region below the F*
distance in F* tubes.
For a tube that hss been sleeved with a mechanical joint sleeve, through vall penetration of greater than or equal to 31% of sleeve nominal vall thicknes= in the sleeve requires the tube to be removed from service by plugging.
For a i
tube that has been sleeved with a velded joint. sleeve, through wall penetration greater than or equal to 37% of sleeve nominal vall i
thickness in the sleeve between the veld joints 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 feedvater 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 Vesting 1ouse report VCAP-lll78 Rev. 1, or laser velded sleeving, as described by Vestinghouse report VCAP-12672, which is used to maintain a tube in service or return a tube to service. This includes the removal of plugs that vere installed as a corrective or. preventive measure.
FARLEY-UNIT 2 3/4 4-12' AMENDMENT NO.
63, 6#, 78 i
REACTOR COOLANT S m Ey
%E52.....................................................................
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 vill 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 conditions 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 vill be maintained within those chemistry limits found to result in i
negligible corrosion of the steam generator tubes..If the secondary j
coolant chemistry is not maintained within these limits, localized corrosion may likely result in stress corrosion cracking. The extent of cracking during plant operation vould 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 vill 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 blovdown.
Leakage in excess of this limit vill require plant shutdovn and an unscheduled inspection, during which the leaking tubes vill be located and plugged or repaired.
Vastage-type defects are unlikely with proper chemistry treatment of the secondary coolant.
However, even if a defect should develop in service, it i
vill be found during scheduled inservice steam generator tube examinations.
Plugging or repair vill be required for all tubes with imperfections exceeding 40% of the tube nominal vall thickness.
If a sleeved tube is 4
found to have through vall penetration of greater than or equal to 11%
for the mechanical sleeve and 37% for the laser velded sleeve of sleeve I
nominal vall thickness in the sleeve, it must be plugged. The 31% and 37%
i limits are derived from R.G. 1.121 calculations with 20% added for conserva-I tism. The portion of the tube end-the sleeve for which indications of vall degradation must be evaluated can be summarized as follovst a.
Mechanical l
- 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 lover roll expansion does not require that the tube be removed from service.
FARLEY-UNIT 2 B3/4 4-3 AMENDMENT NO.
H, 63, 78-
i
!a5E!.....................................................................
- 3. The tube plugging limit continues to apply to the portion'of the tube in the entire upper joint region and in the lover roll ex-pansion.
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.
b.
Laser Velded
- 1. Indications of degradation in the length of the sleeve between the veld joints must be evaluated against the sleeve plugging ifmit.
- 2. Indication of tube degradation of any type including a complete break in the tube between the upper veld joint and the lover veld joint does not require that the tube be removed from service.
- 3. At the veld joint, degradation must be evaluated in both the sleeve and tube.
- 4. In a joint with more than one veld, the veld closest to the end of the sleeve represents the joint to be inspected and the limit of the sleeve inspection.
- 5. The tube plugging limit continues to apply to the portion of the tube above the upper veld joint and below the lover veld joint.
F* tubes do not have to be plugged or repaired provided the remainder of the tube within the tubesheet that is above the F* distance is not degraded. The F* distance is equal to 1.79 inches and is measured down from the top of the tubesheet or the bottom of the roll transition, whichever is lover in elevation.
Included in this distance is an allovance of 0.25 inch for eddy current elevation measurement uncertainty.
Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect vastage type degradation that has penetrated 20% of the original tube vall thickness.
Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, these results vill be reported to the Commission pursuant to 10CFR50.73 prior to resumption of plant-operation.
Such. cases vill be censidered by the Commission on a case-by-case basis and may result in a r:quirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.
)
FARLEY-UNIT 2 B3/4 4-3a AMENDMENT NO.
63, 64,t78
-