ML20137L608

Proposed Tech Spec Pages ix,4-55,4-55a,4-57,4-57a,4-57g & 4-57h Re once-through Steam Generator Auxiliary Feedwater Header Surveillance Requirements

ML20137L608
Person / Time
Site:	Rancho Seco
Issue date:	11/25/1985
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20137L595	List: ML20137L592 ML20137L608
References
NUDOCS 8512030493
Download: ML20137L608 (7)

Text

RANCHO SECO'UNfT 1

. TECHN1 CAL S?ECIFICATIONS LIST OF TABLES Table Page 2.3-1 REACTOR PROTECTION SYSTEM TRIP SETTING LIMITS 2-9 3.5.1-1 INSTRUMENTS OPERATING CONDITIONS 3-27 3.6-1 SAFETY FEATURES CONTAINMENT ISOLATION VALVES 3-40 3.14-1 FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS 3-55 3.15-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3-61 3.16-1 RADI0 ACTIVE GASES EFFLUENT MONITORING INSTRUMENTATION 3-64 3.22-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3-83 3.22-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS 3-86 IN ENVIRONMENTAL SAMPLES w

4.1-1 INSTRUMENT SURVEILLANCE REQUIREMENTS 4-3 4.1-2 MINIMUM EQUIPMENT TEST FREQUENCY 4-8 4.1-3 MINIMUM SAMPLING FREQUENCY 4-9 4.2-1 CAPSULE ASSEMBLY WITHDRAWAL SCHEDULE AT DAVIS-BESSE 1 4-12a 4.2-2 INSERVICE INSPECTION SCHEDULE 4-13 4.10-1 ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-42

'4.10-2 OPERATIONAL ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-22a 4.14-1 SNUBBERS ACCESSIBLE DURING POWER OPERATIONS 4-47c 4.17-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE 4-51 INSPECTED DURING INSERVICE INSPECTION 4.17-2A STEAM GENERATOR TUBE INSPECTION 4-57 4.17-28 STEAM GENERATOR TUBE INSPECTION (Specific Limited Area) 4-57a 122> 4.17-3 SPECIAL PERIPHERAL GROUP TUBES 4-57b 4.17-4 SPECIAL LANE REGION GROUP TUBES 4-57f 4.17-5 OTSG AUXILIARY FEEDWATER HEADER SURVEILLANCE 4-579,

< 4-57h 4.19-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 4-64 SURVEILLANCE REQUIREMENTS 4.20-1 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION 4-66 SURVEILLANCE REQUIREMENTS Proposed Amendment 122, Revision 2 iX G512030493 DH 851125 ADOCK 05000312 PDH

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. RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards 4.17.5 Reports (Continued)

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 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.

c. Results of steam generator tube inspections which fall into 122> Category C-3 require notification of the Commission within 4 4 hours 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 Feedwater Header Surveillance On the first refueling outage following the 1983 refueling outage, and at the 10-yeer 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 Header will be inspected.

b. Selected special interest peripheral tubes, designated in Table 4.17-5, 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 4.17.5.

4.17.7 Inspection Acceptance 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 clearance (less than 1/4") or greater than 40 through wall indications, it will be plugged.

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

Proposed Amendment 122, Revision 2 4-55

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. . RANCHO SECO UNIT 1-TECHNICAL SPEC 1FICATf0NS

! Surveillance Standards Bases

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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 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 corrective measures can be taken. For example, historical data has shown that certain i~ areas of the steam generators are particularly susceptible to corrosion and degradation. Consequently, the inservice inspecton now includes provisions for a more indepth inspection of a Special Area group of tubes specified in Table 4.17-3 and Table 4.17-4.  ;

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

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

Plugging will be required for defective tubts. Steam generator tube j inspections of operating plants have demonstrated the capability to reliably detect degradation that has penetrated 20 percent of the original tube wall thickness..

Whenever the results of any steam generator tubing inservice inspection fall 122> 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 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 SpecificatioWs, if necessary.

The visual and eddy current inspections provide the capability of determining l the success of the internal aux feedwater header stabilization by monitoring

! the long term effects to tube integrity and crack propagation. The I inspections will focus on known crack growth, new crack identification (if any), and tube effects in localized areas near the internal header brackets. '

Additionally, visual inspection of the external header thermal sleeves will i provide assurance that the new design header will not introduce additional problems by demonstrating sleeve integrity.

Proposed Amendment 122, Revision 2 4-55a

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Stand 1rds -

TABLE 4.17-2A STEAM GENERATOR TUBE INSPECTION IST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION Sample Size Result Action Required Result Action Required Result Action Required A minimum of C-1 None N/A N/A .

N/A N/A S of the Tubes per C-2 Plug defective C-1 None N/A N/A 122>< S.G. tubes and inspect additional 2S of c-z Plug detective tubes and c-1 None the tubes in this inspect additional 4S of S.G. the tubes in this S.G. C-2 Plug defective tubes 122> C-3 Plug defective tubes an -

perform action for C-3 j result of first sample C-3 Plug defective tubes and 4 perform action for C-3 N/A N/A result of first sample 122> C-3 Inspect 65 tubes The other None N/A N/A in this S.G., plug S.G. is defective tubes C-1 and inspect 2S tubes in the other S.G. The other Perform action for C-2 N/A N/A Perform follow-on S.G. is result of second sample inspections in the C-2 other S.G. in accordance with results of the above The other (a) If defects can be N/A N/A inspection as applied to S.G. is localized to an affected Table 4.17-2A. C-3 area, inspect all tubes in affected area and Notification to NRC plug defected tubes.

within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and shall (b) If defects cannot be be reported pursuant to localized to an affected Specification 6.9.5P area, inspect all tubes in this S.G. and plug defective tubes 4

b S=3% Where n is the number of steam generators inspected during an inspection Proposed Amendment 122, Revision 2 4-57

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS .

Surveillance Standards TABLE 4.17-2B STEAM GENERATOR TUBE INSPECTION IST SAMPLE INSPECTION OF A " SPECIFIC LIMITED AREA" 2ND SAMPLE INSPECTION OF A " SPECIFIC LIMITED AREA" Sample Size Result Action Required Result Action Required 100% of Area C-1 None .N/A N/A in both OTSGs C-2 Plug defective tubes N/A N/A C-3 Plug defective tubes. N/A N/A Notification to NRC within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and a report shall be filed pursuant to Specification 6.9.5P 100% of Area C-1 None N/A N/A in one OTSG C-2 Plug defective tubes and inspect C-1 None 100% of corresponding area in other OTSG.

C-2 Plug defective tubes C-3 Plug defective tubes and notify NRC within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and a report shall be filed pursuant to Specification 6.9.5F 4

C-3 Plug defective tubes and inspect C-1 None 100% of corresponding area in other OTSG. Notification to NRC within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and a report C-2 Plug defective tubes shall be filed pursuant to Specification 6.9. 5P C-3 Plug defective tubes Proposed Amendment 122, Revision 2 4-57a

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RANCH 0:SECO UNIT 1*

TECHNICAL' SPECIFICATIONS Surveillance Standards TABLE 4.17-5 OTSG Auxiliary Feedwater Header Surveillance OTSG A Special Interest Tubes Row Tube No

-5 1, 46 6 2, 3, 4), 50, S1 7 1, 2, 53, 54 8 1, 2, 56, 57 44 1, 129 45 1, 120 46 1, 121 47 1, 122 48 1, 123 49 1, 124 103 1, 124 105 1 106 1, 119 107 1, 120 108~ 1, 119 144 1, 2, 56, 57 145 1, 2, 53, 54 146 2, 3, 49, 50, 51 147 1, 46

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s Proposed Amendment 122, Revision 2 4-579 e

RANCHO SECO UNIT 1  ;

TECHNICAL SPECIFICATIONS i l

Surveillance Standards TABLE 4.17-5 (Continued)

OTSG Auxiliary Feedwater Header Surveillance OTSG B Special Interest Tubes Row Tube No .

5 1, 46 6 2, 3, 49, 50 7 1, 2, 53, 54 8 1, 2, 56, 57 44 1, 119 45 1, 120 46 1, 121 47 122 48 1, 123 49 1, 124 103 1, 124 104 123 105 122 106 1, 119 107 1, 120 108 1, 119 144 1, 2, 56, 57 145 1, 2, 53, 54 146 2, 3, 49, 50, 51 147 1, 46 Proposed Amendment 122, Revision 2 4-57h

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