ML20245H578

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Proposed Tech Specs for Amend 109 to License DPR-54
ML20245H578
Person / Time
Site: Rancho Seco
Issue date: 06/22/1989
From:
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20245H544 List:
References
NUDOCS 8906300003
Download: ML20245H578 (6)
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Text

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

Obiective To verify the operability and structural integrity of the tubing as part of the reactor coolant boundary.

Specification Each steam generator shall be demonstrated OPERABLE by performar.ce of the following augmented inservice inspection program and the requirements of Specification 1.3. .

4.17.1 Steam Generator Samo*,e Selection and Insoection Steam generator tuting shall be demonstrated OPERABLE by selecting and inspecting steem generators as specified in Table 4.17-1.

4.17.2 Steam Generator Tube 3 amole Selection and Insoection The steam generator tube minimum sample size, inspection result classification, and the corresponding action required shall be as g

specified in Table 4.17-2A. The inspection result classification and the corresponding action required for inspection of " specific limited areas" (see paragraph 4.17.2e) shall be as specified in Table 4.17-28. The inservice inspection of steam generator tubes shall be performed at the frequencies specified in Specification 4.17.3 and the inspected tubes shall be verified acceptable per Specification 4.17.4. The tubes selected for these inspections '

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

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 to the first inservice inspection) of each steam k.. generator shall include:

$ 1. All tubes that previously had detectable wall 48 penetrations (>20%), that have not been plugged or sleeve repaired in the affected area, o

O 2. All sleeves that previously had detectable wall penetrations (>20%) that have not been plugged, and Amendment No. 13, 76, 706, 109 4 4-51

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS i l

Surveillance Standards

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4.17.2 (continued)

3. Tubes in those areas where experience has indicated ,

potential problems.

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 array and on those portions of the tubes where tubes with imperfections were previously found,
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 shall 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 i specific area of a steam generator are inspected. No credit 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:

CAtR90ly 1H1p3ction Re_siti 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 tubes inspected are defective, or between 5% and 10% of the total tubes inspected are degraded tubes. ,

C-3 More 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 mus exhibit significant (>10%) further wall penetrations to be included in the above percentage calculations. l Amendment No. 13, 76, 106, 109 4-52

RANCHO SECO UN8T 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.17.4 Definitions

a. As used in this Specification:

' 1. Imperfec11pn means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing l

L 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, wear or general corrosion occurring on either inside or outside of a tube.
3. Dearaded Tube means a tube in the pressure boundary l containing imperfections 120% of the nominal wall thickness caused by degradation.
4. Defect means an imperfection 140% 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 Insoection means an inspection of the steam
  • generator tube from the point of entry completely to the point of exit (except as noted in 4.17.2c and 4.17.4a.6).
6. Soecial 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 OPERABLE 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). - i

c. Each steam genernor shall not have more than 5,000 tubes repaired by sleeving.

4.17.5 Reports

a. Following each inservice inspection of s' team generator tubes, the number of tubes plugged or repaired in each steam l l generator 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 c-ompleted. This report shall include:

Amendment No. 13, 66, 76, 106, 109 4-54

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RANCHO SECO UNIT 1 TECHNICAL SPECZF! CATIONS

- Surveillance Standards Baiel 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 l

based on a modification of B&W - 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 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 I corrective measures can be taken. For example, historical data has shown that certain areas of the steam generators are particularly susceptible to

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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.

Operational. 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 sample are unchanged. This requirement is Essentially- equivalent to and meets the intent of the requirements set forth 9 in NRC Regulatory Guide 1.83, Revision 1 and does not reduce the margin of safety provided by those requirements.

Hastage-type defects are unlikely with AVT chemistry treatment of the se:ondary coolant. However, even if a defect should develop in service, it will be found during scheduled inservice steam generator tube examinations. ,

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 201. of the original tube wall thickness.

Degraded steam generator tubes can be repaired by the installation 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. I 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 I 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.

Amendment No. 13, 66. 76, 106, 109 4-55a

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