ML14175A615
| ML14175A615 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 11/17/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14175A616 | List: |
| References | |
| DPR-23-A-044 NUDOCS 7912130071 | |
| Download: ML14175A615 (11) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CAROLINA POWER AND LIGHT COMPANY DOCKET NO.
50-261 H. B. ROBINSON STEAM ELECTRIC PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
44 License No.
DPR-23 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Carolina Power and Light Company (the licensee) dated November 4, 1976, as supplemented June 30 and July 29, 1977, June 9 and August 9, 1978, and April 9, 1979, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and 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 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.
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- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No.
DPR-23 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 44
,- 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 17, 1979
ATTACHMENT TO LICENSE AMENDMENT NO. 44 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Insert 4.2-2 4.2-2 4.2-2a 4.2-2b 4.2-2c 4.2-2d 4.2-3 4.2-3 4.2-16 4.2-16 4.2-25
4.2.2 The inspection interval shall be 10 years 4.2.3 The following definitions shall apply to the inspection methods employed in Table 4.2-1.
- a. UT - Volumetric examination using ultrasonic techniques
- c. MT - Examination of the component surface using magnetic particle.
- d. PT - Examination of the component surface using dye penetrant.
- e. V - Visual examination directly by the eye or assisted by remote viewing devices equal to or better than direct observation.
4.2.4 Examinations which reveal unacceptable structural defects in a category shall be extended to include an additional number (or areas) of system.components or piping in the same category approximately equal to that initially examined. In the event further unacceptable structural defects are revealed, all remaining system components or piping in the category shall be examined to the extent specified in that examination category.
4.2.5 Inservice Inspection of Steam Generator Tubes 4.2.5.1.1 Tube Inspection Entry from the hot-leg side with examination from the point of entry completely around the U-bend to the top support of the cold-leg is considered a tube inspection.
4.2.5.1.2 Sample Selection and Testing Selection and testing of steam generator tubes shall be made on the following basis:
(a) One steam generator shall be inspected during inservice inspection in accordance with the following require ments:
- 1.
The inservice inspection may be limited to one steam generator on a rotating sequence basis.
This exami nation shall include at least 9% of the tubes if the results of the first or a prior inspection indicate that all three generators are performing in a com parable manner.
4.2-2 Amendment No. 44
- 2.
When other steam generators are required to be examined by Table 4.2-2 and if the condition of the tubes in one or more generators is found to be more severe than in the other steam generators, the steam generator sampling sequence at the subsequent inservice inspection shall be modified to examine the steam generator or genera tors with the more severe condition.
(b) The minimum sample size, inspection result classification and the associated required action shall be in conformance with the requirements specified in Table 4.2-2. The results of each sampling examination of a steam generator shall be classified into the following three categories:
Category C-1:
less than 5% of the total number of tubes examined are degraded but none are defective.
Category C-2:
Between 5% and 10% of the total number of tubes examined are degraded, but none are defective or one tube to not more than 1% of the sample is defective.
Category C-3:
More than 10% of the total number of tubes examined are degraded, but none are defective or more than 1% of the sample is defective.
In the first sample of a given steam generator during any inser vice inspection, degraded tubes not beyond the plugging limit detected by the prior examinations in that steam generator shall be included in the above percentage calculations, only if these tubes are demonstrated to have a further wall penetration of greater than 10% of the nominal tube wall thickness.
(c) Tubes shall be selected for examination primarily from those areas of the tube bundle where service experience has shown the most severe tube degradation.
4.2-2a Amendment No. 44
(d) The tubes examined in a given steam generator during the first examination of any inservice inspection shall include all non-plugged tubes in that steam generator that from prior examination were degraded, plus additional tubes as required to satisfy the minimum sample size specified in Table 4.2-2. If any selected tube does not permit 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.
This information shall be included in the report required by Specification 4.2.5.3.2.
(e) During the second and third sample examinations of any inservice inspection, the tube inspection may be limited to those sections of the tube lengths where imperfections were detected during the prior examination.
(f) During subsequent inservice inspections, the tube inspection may be limited to certain areas of the tube sheet array and those sections of the tube lengths where imperfections were detected during previous inservice inspections.
4.2.5.1.3 Examination Method and Requirements Steam generator tubes shall be examined in accordance with the method prescribed in Appendix IV, "Eddy Current Examination of Non-Ferromagnetic Steam Generator Heat Exchanger Tubes," as contained in ASME Boiler and Pressure Vessel Code - Section IX "Inservice Inspection of Nuclear Power Plant Components."
4.2.5.1.4 Inspection Intervals (a) Inservice inspections shall not be more than 24 calendar months apart, except that reduced or tightened inspection intervals shall be governed as specified in 4.2.5.4(c) and (d).
(b) The inservice inspections may be scheduled to be coincident with refueling outages or any plant shutdown, provided the inspection intervals of 4.2.5.1.4(a), (c) or (d), as applicable, are not exceeded.
(c) If two consecutive inservice inspections covering a time span of at least 12 months yield results that fall in C-1 category, the inspection frequency may be extended to 40 month intervals between inspections.
(d) If the results of the inservice inspection of steam generator tubing conducted in accordance with Table 4.2-2 at 40 month intervals fall in category C-3, the inspection frequency shall be reduced to at least once per 20 months.
The increase in inspection frequency shall apply until a subsequent inspection meets the conditions specified in 4.2.5.1.4(c) and the interval can be extended to a 40 month period.
4.2-2b Amendment No. 44
(e) Unscheduled inspections shall be conducted in accordance with Specification 4.2.5.1.2 on any steam generator with primary-to-secondary tube leakage (not including leaks originating from tube-to-tube sheet welds) exceeding Specification 3.1.5.3.
All steam generators shall be inspected before returning to power in the event of a seismic occurrence greater than an operating basis earthquake, a LOCA requiring actuation of engineered safeguards, or a main steam line or feedwater line break.
4.2.5.1.5 Acceptance Limits Definitions:
Imperfection is an exception to the dimension, finish, or contour of a tube from that required by fabrication drawings or specifi cations.
Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
Degradation means a service induced cracking, wastage, wear, or general corrosion occurring on either inside or outside of a tube.
Degraded Tube is a tube that contains imperfections caused by degradation equal to or greater than 20% of the nominal tube wall thickness.
Defect is an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective.
Plugging Limit is the imperfection depth beyond which a degraded tube must be removed from service by plugging, because the tube may become defective prior to the next scheduled inspection of that tube.
The plugging limit is 47% of the nominal tube wall thickness if the next inspection interval of that tube is 12 months, and a 2%
reduction in the plugging limit for each 12 month period until the next inspection of the inspected steam generator.
4.2.5.2 Corrective Measures All tubes that leak or are determined to have degradation exceeding the plugging limit shall be plugged prior to return to power.
4.2.5.3 Reports
- 1. After each inservice examination, the number of tubes plugged in each steam generator shall be reported to the Commission in accordance with Specification 6.9.2.a(3).
4.2-2c Amendment No. 44
- 2. The complete results of the steam generator tube inservice inspection shall be included in the uperating Report for the.period in which the inspection was completed.
Reports shall include:
(a) Number and extent of tubes inspected (b) Location and percent of wall thickness penetration for each eddy current indication and any leaks.
(c) Identification of tubes plugged.
- 3. All results in Category C-3 of Table 4.2.2 shall be reported to the Commission as a prompt notification of Specification 6.9.2.a prior to resumption of plant operation.
The written follow-up shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.
Basis:
The inspection program, where practical, is in compliance with Section XI of the ASME Code for In-service Inspection of Nuclear Reactor Coolant Systems dated January, 1970. Though examinations in certain areas are desirable, it should be recognized that equipment and techniques to perform the inspection are still in development. In all areas scheduled for volumetric examination, a detailed pre-service mapping will be conducted using techniques anticipated to be used for post-operation examinations.
The areas indicated for inspection represent those of representative stress levels and therefore will serve to indicate potential problems before significant flaws develop there or at other areas.
As more experience is gained in operation of pressurized water reactors, the time schedule and location of inspection may be altered or, should new techniques be developed, consideration may be given to incorporate these new techniques into this inspective program.
The use of conventional nondestructive, direct visual and remote visual cast techniques can be applied to the inspection of most primary loop components except the reactor vessel.
The reactor vessel presents special problems because of the radiation levels and the recuirement for remote underwater accessibiity to this component.
Because of these limitations an access to the reactor vessel, several steps have been incorporated into the design and manufacturing procedures in preparation for nondestructive test techniques which may be available in the future.
4.2-2d Amendment No. 44
The techniques anticipated for in-service inspection iacitde visual inspec tions, ultrasonic, radiographic, magnetic particle and dye penetrant testing of selected parts during refueling periods.
As more experience is gained in operation of this and other pressurized water reactors, the t!me schedule and location of exnination might alter.
The primary pressure boundary covered by this inspection will include the primary reactor coolant system and branch lines 2" or greater from the reactor coolant system to the second design isolation valve.
Credit is taken in the design of this plant for check valves.
4.2-3 Amendment No. 44
In addition to the capsules discussed above, there are three spares.
Two are located at the same location as Capsule No. 5 and one is located at the same location as Capsule No. 4 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 for evidence of mechanical damage or progressive degradation. 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.
Wastage-type defects will be minimized with proper chemistry treatment of the secondary coolant. If defects or significant degradations should develop in service, this condition is expected to be detected during inservice steam generator tube examinations. Plugging will be required for all tubes with imperfections exceeding the plugging limit. Steam generator tube inspections by means of eddy current testing 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 promptly reported to the Commission pursuant to Specification 6.9.2.a 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.
References (1)
FSAR, Section 4.4 (2) FSAR, Volume 4, Tab VII, Question VI.C 4.2-16 Amendment No. 44
TABLE 4.2-2 STEAM GENERATOR TUBE INSPECTION H. B. ROBINSON UNIT NO. 2 1ST SAMPLE EXAMINATION 2ND SAMPLE EXAMINATION 3RD SAMPLE EXAMINATION Sample Size Result Action Required Result Action Required Result Action Required A minimum of C-1 Acceptable for N/A N/A N/A N/A S tubes per Continued Service Steam
.Generator C-2 Plug tubes exceeding the C-1 Acceptable for N/A N/A (G.)at plugging limit and pro-continued Service ceed with 2nd sample examination of 2S tubes C-2 Plug tubes exceeding C-1 Acceptable for S=3(N/n)%
in same steam generator the plugging limit Continued Service and proceed with 3rd Plug tubes exc. plug.
sample examination of C-2 limit. Acceptable for where:
4S tubes in same continued service steam generator Perform action required N is the C-3 under C-3 of 1st L
number of
._sample examinct.ion steam genera-Perform action required tors in the C-3 under C-3 of let sample N/A N/A plant -
3 examination c-3 Inspect all All other Acceptable for N/A N/A n is the tubes in this S.G., plug S.G.s ar Continued Service
'number of tubes exceeding the C-1 Isteam genera-plugging limit and Somo S. G.s tore inspect-proceed with 2nd sample dd iut no Perform action required N/A N/A ed during an examination of 2S tubes S.G.are under C-2 of 2nd sample examination in each other steam C-3 examination above z
generator not included in Additional the inservice inspection
.G. Is C-3 Inspect all N/A N/A program.
tubes in S.G. and plug Report results.to NRC tubes exceeding the plug within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in ging limit. Report to accordance with Technical NRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in Specification 6.9.2.a(3).
accordance with Technical Specification 6.9.2.a(3).