ML20198K218
| ML20198K218 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/16/1997 |
| From: | Eaton R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20198K220 | List: |
| References | |
| NUDOCS 9710230197 | |
| Download: ML20198K218 (8) | |
Text
I 90 Cthy y+
UNITED SYATES s
- NUCLEAR REGULATORY COMMIS810N W'.SMIN070N. D,Q. 306K4001
- ...+
lifJBOPOLITANEDISONCOMPANY df,RSEY CENTRAL POWER & LIGHT COMPAtil PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO. 50-289 THREE MILE 15tAND NUCLEAR STATION. UNIT N(LJ AMENDMENT TO FACILITY _ OPERATING LICENSE Amendment No. 206 License No. DPR 50 1.
The Nuclear Regulatory Cremission (the Commission or NRC) has found that:
A.
The application for an,endment by GPU Nuclear Corporation, et al.
(the licensee) dated August 12. 1997, as supplemented August 28.
September 15. October 3. 9. and 10, 1997, 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.n 10 CFR Chapter I:
B.
The facility will operate in conformity with the application, the 3rovisions 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 t.onducted in compliance with the Commission's regulations:
The issuanc' of this amendment will not be inimical to the common D.
e defense and security or to the health and safety of the public:
4' 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.
EA"R8bilPd8&se, P
2-2.
Accordingly, the license is amendef oy changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of facility Operating License No. DPR 50 is hereby amended to read as follows:
(2)
Technical Soecj.11 cations The Technical Specifications contained in Appendix A. as revised through Amendment No. 206. are hereby incorporated in the license.
GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Rn B. Eaton. Acting Director Project Directorate 1-3 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 16, 1997
4
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ATTACHMENT TO LICENSE AMENDMENT NO. 206 FACILITY OPERATING LICENSE NO. DPR 50 DOCKET R U,^ E Replace the followin the attached pages. g ) ages of the Appendix A Technical Specifications, with 11e revised pages are identified b contain vertical lines indicating the areas of change. :' Amendment number and 8202Xe Insert 4 79 4 79 4 80 4 80 4-81 4-81 4 82 4 82 4 83 4 83 l
4.19.2 Specification (Continued)
C2 One or more tubes, but not more than 1% of the total tubes inspected in a steam generator are defective, or between 5% and 10% of the total tubes inspected are degraded tubes.
i C-3 More thsn 10% of the total tubes inspected in a steam generator are degraded tubes or more than 1% of the inspected tubes are defective.
NOTES: (1) In all inspections, previously degraded tubes whose degradation has not been spanned by a sleeve must exhibit significant inercase in the applicable degradation size measurement (> 0.6 volt bobbin coil amplitude increase for In Ide diameter IGA Indications or > 10%
further wall penetration for all other degradation) to be included in the above percentage calculations.
(2) Where special inspections are performed pursuant to 4.19.2.a.4, defective or degraded tubes found as a result of the inspection shall be included in determining the Inspection Results Category for that special inspection but need not be included in det rmining the Inspection Results Category for the general steam generator inspection.
4.19.3 Impection Frequencies The required inservice inspections of steam generator tubes shall be performed at the following frequencies:
- a. The first (baseline) inspection was performed after 6 effective full power months but within 24 calendar months ofinitial criticality. The subsequent inservice inspections shall be performed not more than 24 calendar months atler the previous inspection. If the results of two consecutive inspections for a given group of tubes encompassing not less than 18 calendar months all fall into the C-1 category or demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval for that group may be extended tu a maximum of once per 40 months.
- b. If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.19 2 at 40 month intervals for a given group of tubes
- fall into Category C-3 the inspection frequency for that group 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 4.19.3.a; the interval may then be extended to a maximum of once per 40 months.
- A group of tubes means:
(a) All tubes inspected pursuant to 4.19.2.a.4, or (b) All tubes in a steam generator less those inspected pursuant to 4.19.2.a.4 4 79 Amendment No 4h44, 206
4.19.3 Inanection Freauencies (Continued)
- c. Additional, uascheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.19 2 during the shutdown subsequent to any of the fallowing conditions:
i
- 1. A seismic occurrence greater than the Operating Basis Earthquake.
- 2. A loss of coolant accident requiring actuation of engineering safeguards, or
- 3. A major main steam line or fudwater line break,
- d. After primary to-secondary tube leakage (not including leaks originating from tube to tube sheet welds) in excess of the limits of Specification 3.1.6.3, an inspection of the efrected steam gerierator will be performed in accordance with the following criteria:
- 1. If the leak is above the 14th tube support plate in a Group as defined in Section 4.19.2.a.4(1) all of the tabes in this Group in the affected steam generator will be inspected above the 14th tube support plate, if the results of this inspection fall into the C 3 category, additionalinspections will be performed in the same Group in the other steam generator.
- 2. If the leaking tube is not as defined in Section 4.19.3.d.1, then an inspection will be performed on the affected steam generator (s)in accordance with Table 4.19 2.
4.19.4 Accentance Criteria
- a. As used in this Specificationt
- 1. Imperfection means an exception to the dimensions, finish,- or contour of a tube from that required by fabrication drr. wing or specifications. Eddy current testing indications less than degraded tube criteria specified in a.3 below may be considered l
Imperfections.
- 2. Qtgradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.
- 3.
Dearaded Tube means a tube containing :
(a) an inside diameter (LD.) IGA indication with a bobbin coilindication 3 0.5 volt or 3 0.13 inches axial extent or2 0.26 inches circumferential extent (for 12R outage eaaminations and Cycle 12 operation only), or (b) imperfections t 20% of the nominal wall thickness caused by degradation.
- 4. % Degradation means the percentage of the tube wall thickness affected or removed by degradation.
4 80
- Amendment No. !!5, M9, !#, 206 4
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____._..m
4.19.4 Acceptance Criteria (Continued) i 5.
Defect means an imperfection of such severity that it exceeds the repair ~ limit. A tube containing a defect is defective.
1 6.
Repair Limit means the extent of degradation at or beyond which the tube shall be repaired or removed from service because it may become unserviceable prior to the next inspection.
This limit is equal to 40% of the nominal tube wall thickness. For Outage 12R examinations and Cycle 12 operation only,inside diameter IGA Indications shall be repaired or removed from service if they eaceed an asial extent of 0.25 laches, or a circumferential extent of 0.52 inches, or a through wall degradation dimension of 3 40% if assigned.
- 7. IJnserviceable describes the condition of a tube ifit 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 4.19.3.c.,
above.
- 8. Tube Inspection means an inspection of the steam generator tube from the bottom of the upper tubesheet completely to the top nf the lower tubesheet, except as permitted by 4.19.2.b.2, above.
- 9. Inside Diameter Inter-Granular Attack (IGA) Indication means a bobbin coil indication initiating on the inside diameter surface and confirmed by diagnostic ECT to have a volumetric morphology characteristic ofIGA.
- b. The steam generator shall be determined OPERABLE after completing the corresponding actions (removal from service by plugging, or repair by kinetic expansion, sleeving, or other methods, of all tubes exceeding the repair limit and all tubes containing throughwall cracks) required by Table 4.19 2.
4.19.5 Reports
- a. Aner the completion of each inservice inspection of steam generator tubes, prior to exceeding a reactor coolant system (RCS) temperature of 250 'F, the NRC shall be notified of the following:
- 1) The number of tubes repaired or removed from service in each steam generator,
- 2) An assessment of growth ofinside diameter IGA degradation, and
- 3) Results ofin situ pressure testing,if performed.
4 81 Amendment No. 47,*3,91,103,129,119,155,157,206
~
I 4.19.5 Reports (Continued) b'.
The complete results of the steam generator tube inservice inspection shall be reponed to the NRC within 90 days following completion of the inspection and repairs. The report shall l
include:
- l. Number and extent of tubes inspected.
- 2. Location and percent of wall thickness penetration for each indication of an imperfection.
- 3. location, bobbin coil amplitude, and axial and circumferential extent (if determined) for each inside diameter IGA indication, and
- 4. Identification of tubes repaired or removed from service.
- c. Results of steam generator tube inspections which fall into Category C 3 require notification in accordance with _10 CFR 50.72 prior to resumption of plant operation. The written follow up of this report shall provide a description ofinvestigations conducted to determine the cause of the tube degradation and corrective measures taken to prevent recurrence in accordance with 10 CFR 50.73.
BAnfJ 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 modification of Regulatory Guide 1.83, Revision 1. In service 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 progress.<e degradation due to design, manufacturing errors, or inservice conditions. 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 Unit 's expected to be operated in a manner such that the primary and secondary coolant will be maintained within those chemistry limits found to result in negligible corrosio of the steam generator tubes. If the primary or secondary coolant chemistry is not maintained within these chemistry limits, localized corrosion may likely result.
The extent of steam generator tube leakage due to cracking would be limited by the secondary coolant activity, Specification 3.1.6.3..
The extent of cracking during plant operation would be limited by the limitation of total steam generator tube leakage between the primary coolant system and the secondary coolant system (primary-to secondary leakage = 1 gpm). Leakage in excess of this limit will require plant shutdown and an unscheduled inspection, during which the leaking tubes will be located and repaired or removed from senice.
4 82 Amendment No 17,56, ! !6, H9, !M, 206
linu (Continued)
Wastage; type defects are unlikely with proper chemistry treatment of the primary or the secondary i
coolant However, eve.,if a defect would develop in service, it will be found during scheduled in-service steam genera:or tube examint.tlons. For tobes with ID IGA Indications, additional j
conservatism is belt's applied during the 12R Outage, for Cycle 12 operation, to evaluate circumferential and asial dimensions for determining final disp isition of the tube. For ID IGA indications through wall dimension will continue to be assigned to those indications where l
amplitude response permits measuring through wall dimension. Steam generator tube inspections 1
of operating plants hsve demonstrated the capability to reliably detect degradation that has penetrated 20% of the original tube wall thickness.
Removal from service by plugging, or repair by kinetic expansion, sleeving, or other methods, will i
be required for degradation equal to or in excess of 40% of the tube nominal wall thickness. For the 12R Outage examinations and Cycle 12 operation ont, tubes with I.b. initiated
/
intergranular degradation may remain in service without % T.W. string if the degradation morphology has been tharacterized as not crack like by diagnostic eddy current inspection and the degradation is ofilmited circumferential and asialiength to ensure tube structural integrity. Additionally, serviceability for accident leakage under the limiting postulated Main Steam Line Break (MSLB) accident will be evaluated by determining that this I.D.
Initiated degradation methanism is inactive (e.g. comparison of the 12R Outage tammination results with the resuhs from past outages does not show growth greater than espected ECT repeatability variations) and by successful 12R in situ pressure testing of a sample of these degraded tubes to evaluate their accident leakage potential.
Where experience in similar phnts with similar water chemistry, as documented by USNRC Bulletins / Notices, indicate critical areas to be inspected, at least 50% of the tubes inspected should be from these critical areas. First semple inspections sample size may be modined subject to NRC review i
and approval.
Whenever the results of any steam generator tubing inservice inspection fall into Category C 3 on the first sample inspection (See Table 4.19.2), these results will oc reported to NRC pursuant to the requirements of Speci0 cation 4.19.5.c. Such cases will be considered by the NRC on a case by-case basis and may result m a requirement for analysis, laboratory examinations, tens, additional eddy current inspection, and revision of the Technical Speci0 cations, if necessary, I
4 83 Amendment No. 4h429, 206
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