ML20248B953

Amend 109 to License DPR-54,revising Tech Spec 4.17 Steam Generators & Associated Bases & Tables 4.17-2A & 4.17-2B to Permit Repairs of Steam Generator Tubes by Means of Tube Sleeves

ML20248B953
Person / Time
Site:	Rancho Seco
Issue date:	06/05/1989
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20248B950	List: ML20248B945 ML20248B953 ML20248B962
References
NUDOCS 8906090218
Download: ML20248B953 (10)

Text

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SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.109 License No. DPR-54

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Sacramento Municipal Utility District (the licensee) dated September 24, 1986, as supplemented April 27, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 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 2.C.(?) of Facility Operating License:No. DPR-54 is hereby amended to read as follows: ,

(2)TechnicalSpecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.109, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. ,

3. This license amendment shall become effective within 30 days of the. issuance

-date.. The implementation delay is provided to allow time for modification of .

affected procedures and promulgation of the changes to personnel.

FOR T NUCLEAR REGULATORY COMMISSION W -

h George W. Knighton, Director Project Directorate V Division of Reactor Projects III, IV, V and Special Projects

Attachment:

Changes to the Technical Specifications

'Date of Issuance: June 5, 1989

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ATTACHMENT TO LICENSE AMENDMENT NO.109 FACILITY OPERATING LICENSE NO. DPR-54 DOCKET NO. 50-312 1

Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. -The revised pages are identified by Amendment number 3' and contain vertical lines indicating the area of change.

i l: Remove Insert p 4-51 4-51 52 4-52 4-54 4-54 4-55 4-55 4-55a 4-55a 4-57 4-57 4-57a 4-57a i

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.17 STEAM GENERATORS Arolicability Applies to inservice inspection of the steam generator tubes.

Obiettive To verify the the reactor operability coolant boundary. and structural integrity of the tubing as part of Specification following1.3.

Specification augmented inservice inspection program an 4.17.1 Steam Generator Samole Selection and Inseettien and inspecting steam generators as specified in Ta 4.17.2 Steam Generator Tube samele Selection and Inseettien The steam generator tube minimum sample $12e, inspection result classification, specified in Table and4.17-2A. the corresponding action required'shall be as The inspection result classification and the corresponding action required for inspection of " specific limited4.17-28.

Table areas" (see paragraph 4.17.2e) shall be as specified in shall be performed at the frequencies specified in Specifi 4.17-3 and the inspected tubes shall be verified acceptable per the acceptance criteria of Specification 4.17.4 [

The tubes selected for 1 these inspections shall include at least 3% of the total number of except:in both steam generators and be selected on a random basis tubes a.

If 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 inspection during inservice inspection (subsequent generator shallto include:

the first inservice inspection) of each steam 1.

) All tubes that previously had detectable wall penetrations D 20%), that have not been plugged or sleeve repaired in the affected area.

2.

All sleeves that previously had detectable wall penetrations D20%) that have not been plugged, and Amendment No. 73 / 5,795,109 4-51 1 .

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- RANCHO.SECO UNIT 1 TECHNICAL SPECIFICATIONS I

Surveillance Standards 4.17.2 -(continued) I

3. . Tubes in those areas where experience has indicated l potential problems. l c.

The second and third sample inspections during each inservice inspection may be less than a full tube inspection by concentrating (selecting at least 50% of the tubes to be inspected) the inspection on those areas of the tube sheet i

~ array and on those portions of the tubes where tubes with imperfections were previously.found. i d.

A tube inspection (pursuant to Specification 4.17.4.5) shall be performed on each selected tube. If any selected tube does not permit.the passage of the eddy current probe for a tube inspection, this shall be recorded and an adjacent tube tha11 be selected and subjected to a tube inspection. (" Adjacent"is interpreted to mean the nearest tube capable of being inspected.)

Tubes which do not permit passage of the eddy current probe will be considered as degraded tubes.when classifying inspection results.

e.

Tubes in specific limited areas which are distinguished.by unique operating conditions and/or physical Construction (for example, tubes adjacent to the open inspection lane or tubes whose 15th tube support plate hole is not broached but drilled) may be' excluded from random samples if all such tubes in the specific area of a steam generator are inspected. No credit i will be taken for these tubes in meeting minimum sample size requirements.

The results of each sample inspection shall be classified into one of the following three categories:

Cateeorv Inseettien 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 l

L tubes inspected are defective, or between Si and 10% of the total tubes inspected are degraded tubes.

C-3 Nore 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 must exhibit significant 010%) further wall penetrations to be included in the above percentage calculations.

Amendment No. 73, 75, Jpp, 109 4-52

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• RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.17.4 Definitions

a. As used in this Specification:

1. Irrerfection means an exception to tht dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy current testing indications of less than 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections. ,

2. Degradation means a service-induced cracking, wastage, wea.r or general corrosion occurring on either inside or outside of a tube.

3.

Deoraded Tube means a tube in the pressure boundary l containing imperfections 220% of the nominal wall thickness caused by degradation.

4. Defect means an imperfection 2,40% of the nominal tube or sleeve wall thickness. .A tube or sleeve containing a defect in its pressure boundary is defective and shall either be plugged or repaired by sleeving. Tube sleeving must be in accordance with the methodology approved by NRC for use at Rancho Seco.

5. Tube Interetien means an inspection of the steam generator tube from the point of entry completely to the point of exit (except as noted in 4.17.2'c and 4.17.4a.6).

6.

Seetial area Tubes include those tubes which have shown a significant amount of degradation throughout their operating history. These include peripheral tubes and lane region tubes designated in Tables 4.17-4 and 4.17-5.

b. The steam generator shall be determined OPERABl.E after completing the corresponding actions required by Table 4.17-2A (and Table 4.17-2B if provisions of paragraph 4.17.2e are utilized). ,-

c.

Each steam generator shall not have more than,5.000 tubes repaired by sleeving.

4.17.5 Ef.22I11

a. Followingeachinserviceknspectionofsteamgeneratortubes, the number of tubes plugged or rephired in each steam generator l shall be reported to the Commission within 30 days.

b. The results of the steam generator tube inservice inspection shall be included in a Monthly Operating Report for the period in which this inspection was completed. This report shall inclutt:

Amendment No. 73.EE"76.JPE,109 . 4-54

RANCHO SECO UNIT 1 TEC M AL SPECIFICATIONS Surveillance Standards 4.17.5 (continued)

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 piogged.

c. Results of steam generator tube inspections which fall into Category C-3 require notification of the Commission within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and shall be reported pursuant to Specification 6.9.5P.

The written followup of this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence. .

4.17.6 OTSG auxiliary Feedvater Hender Surveillance On the first refueling outage following the 1983 refueling outage, and at the 10-year ISI. the following inspections will take place:

a. Visual inspections of the secured Internal Header, attachment welds and external headers thermal sleeves will be made

, through selected openings, and will be performed in such a manner that the known cracks in the Internal Feader will be inspected.

b. Selected special interest peripheral tubes. designated in Table 4.17-3 will be Eddy Current inspected but shall not be considered a part of the Eddy Current inspection that is conducted pursuant to Technical Specification 4.17.1 through L ,

4.17.5.

4.17.7 Inseettien Atteetante Criteria and Corrective' Actions

a. Video taped inspections of the known cracks performed during the initial discovery will be compared with the crack configuration found during this surveillance. This comparison will allow a determination to be made as to whether or not the crack has propagated.

b. If any inspected special interest peripheral tube indicates I cinrance (less than 1/4") or greater than 40% through wall indications..it will be plugged.

4.17.8 Reeerts A report of these inspections will be prepared and incorporated in the subsequent Monthly Report to the NRC.

Amendment No.72, if, 7f 706.

109 4-55

RANCC SECO UN8T 1 TECNN8 CAL SPIC 8F2 CAT 80NS Su veillance Standards LLLL1 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 surveillance requirements of steam generator tubes are based on a modification of ELW - Standard Technical Specifications dated June 1,1976. 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 eyidence of mechanical damage or progressive degradation due to. design, manufacturing errors, or inseryice conditions that lead to corrosion. Inservice inspectitrn 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. For example, historical data has shown that certain areas of the steam generators are particularly susceptible to corrosion and degradation. Consequently, the inservice inspection now includes provisions for a more in-depth inspection of a Special Area group of tubes specified in Table 4.17-4 and Table 4.17-5. The surveillance requirements for inspection of the steam generator tubes are applicable to all tubes, including those previously repaired by sleeving.

0;erational experience has shown that tube defects can be the result of unique operating conditions or physical arrangements in certain areas of the

. steam generators. A full inspection of all of the tubes in such limited areas will provide complete assurance that degraded or defective tubes in these areas are detected. Because no credit is taken for these distinctive tubes in the constitution of the first sample or its results, the requirements for the first sa ;1e are unchanged. This requirement is essentially e;uivalent to and teets the intent of the requirements set forth in NRC Fe;ulatory Guide 1.E3. Revision 1 and does not reduce the margin of safety provided by these, requirements. -

l Wastage-type defects are unlikely with AVT chemistry treatment of the l secondary coolant. However, even if a defect should develop in service, it l

will be found during scheduled inservice steam generator tube examinations.

i Repair or plugging will be required for defective tubes. Steam generator l tube inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20% of the original tube wall thickness.

Degraded steam generator tubes can be repaired by the insta.11ation of sleeves which span the area of degradation and serve as a replacement pressure boundary for the degraded portion of the tube, thus permitting the tube to remain in service. Total tube sleeving is limited to 5,000 tubes in each steam generator due to cumulative increased pressure drop through the steam generator tubes as more and more are sleeved.

Whenever the results of any steam generator tubing inservice inspection fall into Category C-3, the Commission will be notified within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the

. results shall be reported pursuant to Specification 6.9.5P. Such cases will be considered by the Ccm.ission on a case-by-case basis and may result in a requirement for analysis, lateratory examinations, tests, additional eddy current inspection and revision of the Technical Specifications, if necessary.

Amendment No. 72.f f,76,7Ef 109 4-55a

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