ML20128E735
| ML20128E735 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/26/1993 |
| From: | Hubbard G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128E740 | List: |
| References | |
| NPF-06-A-142 NUDOCS 9302110052 | |
| Download: ML20128E735 (9) | |
Text
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/ g2Oto UNITED STATES --
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- NUCLEAR REGULATORY COMMISSION-
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ENTERGY OPERATIONS. INC.
DOCKET N0t 50-368.
ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 142 License No. NFF-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated July 22, 1992, as supplemented by-letter dated -
September 11, 1992, complies with the standards and-requirements of.
the Atomic Energy Act-of 1954, as amended-(the Act), Land the.
Commission's-rules-and regulations set-forth in 10 CFR Chapter;I;'
B.
The facility will operate in conformity with the application,:the -
provisions of.the Act, and the rules and regulations of the-Commission; C.
There.is reasonable assurance:
(i) that the activities authorized-by this amendment can be conducted without endangering'the health and safety of the public,-- and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this-license amendment will-nec be inimical-to the-common defense and security or to the health and safety of the public; and E.
The issuance of-thi:, ameidmentcis 'in accordance with 10 CFR Part-51 of-the Commission's regulitions and.all-applicable requirements have been satisfied.
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Accordingly, the license is amended by changes to the Techn'ical Specifientions as indicated in-the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-6 is hereby amended to read as follows:
2.
Jaghnical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.142, are hereby_ incorporated 'n the license.-
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION dd
@ George T. Hubbard, Acting Director Project Directorate'IV-1 Division of Reactor Projects - III/IV/v Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
1/26/93
ATTACHMENT TO LICENSE AMENDMENT NO.142 facillTY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Revise the following pages of the Appendix "A" Technical Specifications with -
the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE PAGE1 JNSERT PAGES 3/4 4-9 3/4 4-9 3/4 4-10 3/4 4-10 8 3/4 4-3 8 3/4 4-3 a..a
-. e
,a v
t REACTOR COOLANT SYSTEM SURVEI1 LANCE REOUIREMENJS (Continued) i 10.
Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to servic> 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 liapections.
- b. The steam generator shall be determineo OPERABLE after completing the corresponding actions (plug or repair all tubes exceeding the plugging or repair limit and all tubes containing through-wall cracks) required by Table 4.4-2.
Defective tubes may be repaired in accordance withs i
- 1) B&W Topical Report BAW-2045PA-00 as supplemented by the infor. nation provided in B&W Report 51-1212L39-00, "BVNS Kinetic Sleeve Design-Application to ANO Unit 2".
- 2) CENS Report CEN-601 4, "ANO-2 Steam Generator Tube Repair Using Leak Tight Sleeves", Revision 01-P, dated July, 1992 4.4.5.5 Reports
.. Following each inservice inspection of steam generator tubes the number of tubes plugged or sleeved in each steam generator shall be reported to the Commission within 15 days,
- b. The complete results of the steam generator tube inservice inspection shall be reported on an annual basis for the period in which the inspectior was completed.
This report shall include:
- 1. Number and extent of tubes inspected.
- 2. Location and percent of wall-thickness penetration for each indication of an imperfection,
- 3. Identification of tubes plugged or sleeved.
- c. Results of steam generator tube inspections 'which fall into Category C-3 shall be reported in a Special Report pursuant to Specification 6.9.2 as denoted by Table 4.4-2.
Notificatic-f the Commission will be made prior to resumption of plant operation.
The written Special Report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken.to prevent recurrence.
ARKANSAS - UNIT 2 3/4 4-10 Amendment No. 91, 133.'142
REACTOR COOLANT SYSTEM BASES Vastage-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 tubes examinations.
Plugging or sleeving will be required for ell tubes with imperfections exceeding the plugging or repair limit as defined in Surveillance Requirement 4.4.5.4.a.
Defective tubes may be repaired by sleeving in accordance with the B&W Topical Report BAW-2045PA-00 as supplemented by the infonnation n
provided in B&W Report 51-1212539-00, "BWNS Kinetic Sleeve Design-Application to ANO Unit 2" or CENS Report CEN-601-P, ANO-2 Steam Generator Tube Repair Using Leak Tight Sleeves", Revision 01-P dated July, 1992.
Steam generator tube inspections of operating plants have demonstrated the capability-to reliably detect degradation that has penetrated 20% of the tube wall thickness.
For sleeved tubes, the adequacy of the system that is used for periodic inservice inspection will be validated.
Additionally, upgraded testing methods will be e.aluated and appropriately implemented as better methods are developed :.nd validated for commercial use.
Whenever the results of any steam generator tubing inservice inspection fall into Category C-3 certain results will be reported in a Special Report to the Commission pursur.nt to Specification 6.9.2 as denoted by Table 4.2-2.
Notification of the Commissien will be made 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 requi ra. 2ent for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.
3/4.4.6 REACTOR COOLANT SYSTEM LEAKAC" 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure Boundary.
These detection systems are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems" May 1973.
3/4.4.6.2 REACTOR COOLANT SYSTEM LEAKAGE Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portion of this leakage can be reduced to a threshold value of less than 1 GPM.
This threshold value is sufficiently low to ensure early detection of additional leakage.
The 10 GPM TDENTIFIED LEAKAGE limitation provides allowances for a limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAG' by the leakage detection systenu.
The Surveillance Requirements for RCS Pressure Iso 1Ltion Valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA.
Leakage from the RCS Prescura Isolation Valves is IDENTIFIED LEAKAGE (nd will be considered as a portion of the allowed limit.
ARKANSAS - UNIT 2 B 3/4 4-3 Amendment No. 91, 133, 142
@fddf diidd 4 29 81 I
4 4
ATTACHMENT TO LICENSE AMENDMENT NO.142 FACIllTY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Revise the following pages of the Appendix "A" Technical Specifications with the attached pages. 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 B 3 '4 4-3 B 3/4 4-3
REACTOR COOLANT SYSTEM BASES 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 tubes examinations.
Plugging or sleeving will be required for all tubes with imperfections exceeding the plugging or -repair limit as defined in Surveillance Requirement 4.4.5.4.a.
Defective tubes may be repaired by sleeving in accordance with the B&W Topical Report BAW-2045PA-00 as supplemented by the information provided in B&W Report 51-1212539-00, "BWNS Kinetic Sleeve Design-Application to ANO Unit 2" or CENS Report CEN-601-P, "ANO-2 Steam Generator Tube Repair Using Leak Tight Sleeves", Revision 01-P, dated July, 1992.
Steam generator tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the tube wall thickness.
For sleeved tubes, the adequacy of the system that is used for periodic inservice inspection will be validated.
Additionally, upgraded testing methods will be evaluated and appropriately implemented as better methods are developed and validated for commercial use.
Whenever the results of any steam generator tubing inservice inspection fall into Category C-3 certain results will be reported in a Special Report to the Commission pursuant to-Specification 6.9.2 as denoted by Table 4.2-2.
Notification of the Commission will be made prior to resumption of plat t 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 necessary.
3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTInN SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure-Boundary.
These detection systems are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems" May 1973.
3/4.4.6.2 REACTOR COOLANT SYSTEM LEAKAGE Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portiet of this leakage can be reduced to a threshold value of less than 1 GPM.
This threshold value is sufficiently low to ensure early detection of additior.41 leakage.
The 10 GPM IDENTIFIED LEAKAGE limitation provides allowances for a limited l
amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.
The Surveillance Requirements for RCS Pressure Isolation Valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA.
Leakage from the RCS Pressurs 1so1Ltion Valves is IDENTIFIED LEAKAGE and will be considered as a portion of l
the allowed limit.
l l
ARKANSAS - UNIT 2 B 3/4 4-3
' Amendment No. 91, 133, 142 l
9tddt ditdd d' 29 81
REACTOR COOLANT SYSTEM SURVEILLANCE REOUIREMENTS (Continued) 4.4.5.4 Acceptance Criteria l
a.
As used in Cais Specification 1.
Tubing or Tube means that portion of the tube or sleeve which forms the primary system to secondary system pressure boundary.
2.
Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or stucifications.
Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
3.
Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.
4.
Degraded Tube means a tube containing imperfections 220% of the nominal wall thickness caused by degradation.
5.
_% Degradation means the percentage of the tube wall thickness affected or removed by degradation.
6.
Defect means an imperfection of such severity that it exceeds the plugging or repair limit.
A tube containing a defect is defective.
7.
Plugging or Repair Limit means the imperfection depth at or beyond which-the tube shall be removed.from service by plugging or repaired by sleeving because it may become unserviceable prior to the next inspection.
The plugging or repair limit is equal to 4C% of the nominal parent tube and sleeve wall thickness for sleeves installed in 'accordance with B&W Topical Report BAW-2045-PA-00 as supplemented _by the information provided in B&W Report 51-1212539-00, "BWNS Kinetic Sleeve Design -
Application to ANO Unit 2".
The plugging limit is equal to.34%
of the nominal sleeve wall thickness for sleeves installed in-'
accordance with CENS Report CEN-601-P, "ANO-2 Steam Generator Tube Repair Using Leak-Tight Sleeves", Revision 01-P, dated July, 1992.
8.
Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its-structural integrity in the event of an Operating Basis Earthquake, a loru-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.
9.
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.
ARKANSAS -' UNIT 2
'3/4 4-9 Amendment No. 133, 142
j:'..
REACTOR COOLANT SYSTEM SURVEIttANCE REOUIREMENTS (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.
- b. The steam generator shall be determined OPERABLE after completing the corresponding actions (plug or repair all tubes exceeding the plugging or repair limit and all tubes containing through-wall cracks) required by Table 4.4-2.
Defective tubes may be repaired in accordance with:
- 1) B&W Tepical Report BAW-2045PA-00 as supplemented by the information provided in B&W Report 51-1212539-00, "BWNS Kinetic Sleeve Design-Application to ANO Unit 2".
- 2) CENS Report CEN-601-P, "ANO-2 Steam Generator Tube Repair Using Leak Tight Sleeves", Revision 01-P dated July, 1992 4.4.5.5 Reports
- a. Following each inservice inspection of steam generator tubes the number of tubes plugged or sleeved in each steam generator shall be reported to the Commission within 15 days.
- b. The complete results of the steam generator tube inservice inspection shall be reported on an annual basis for the period in which the inspection was completed.
This report shall include:
- 1. Number and extent of tubes inspected.
- 2. Location and percent'of wall-thickness penetration for each indication of an imperfection.
- 3. Identification of tubes plugged or sleeved.
- c. Results of steam generator tube inspections which fall into Category C-3 shall be reported in a Special Report pursuant to Specification 6.9.2 as denoted by Thble 4.4-2.
Notification of the Commission will be made prior to resumption of plant' operation.
The written Special Report shall provide a description
-of investigations conducted to determine cause of the tube
.i degradation and corrective measures taken to prevent recurrence.
(
ARKANSAS - UNIT 2 3/4 4-10 Amendment No. 91, 133, 142
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