ML20217G012

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Proposed Improved Tech Specs Section 5.7.2, Special Repts, Clarifying That Complete Results of OTSG Tube Inservice Insp Shall Be Submitted to NRC 90 Days After Startup (Breaker Closure)
ML20217G012
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 04/23/1998
From:
FLORIDA POWER CORP.
To:
Shared Package
ML20217G010 List:
References
NUDOCS 9804290010
Download: ML20217G012 (8)
v • d • e


Text

1 1

l FLORIDA POWER CORPORATION l

CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302/ LICENSE NO. DPR-72 i

ATTACHMENT B LICENSE AMENDMENT REQUEST #221, REVISION 1 "B" ONCE TIIROUGH STEAM GENERATOR TUBE SURVEILLANCE PROGRAM AND SPECIAL REPORTS Set of Changed Pages With New or Revised Information Shown in Strikeout / Shadowed Font 1

1 9804290010 980423 2 DR ADOCK 0500

i l- ,

Procedures, Programs and Manuals

, 5.6 5.6 Procedures, Programs and Manuals 5.6.2.10 OTSG Tube Surveillance Program (continued)

8. Plugging / Sleeving Limit means the extent of degradation beyond which the tube shall be restored to serviceability by the installation of a sleeve or removed from service because it may become unserviceable prior to the next inspection and is equal to 40% of the nominal tube or sleeve wall thickness. No more than five thousand sleeves may be installed in each 0TSG.
9. Unserviceable describes the condition of a tube if it 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,oramainsteamlineorfeedwaterline break, as specified in 5.6.2.10.3.c, above.
10. Tube Inspection means an inspection of the entire OTSG tube as far as possible.
b. The OTSG shall be determined OPERABLE after completing the corresponding actions (plug or sleeve all tubes exceeding the plugging /sleevin limit and all tubes containing through-wall cracks required by Table 5.6.2-2 (and Table 5.6.2-3 if he provisions of  ;

Specification 5.6.2.10.2.d are utilized). Defective tubes may be repaired in accordance with the B&W process (or method) equivalent to the method described in report BAW-2120P.

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(continued)

Crystal River Unit 3 5.0-17 Amendment No. 448 l

" Reporting Requirements 5.7 5.7 Reporting Requirements 5.7.2 Special Reports (continued)

The following Special Reports shall be submitted:

a. When a Special Report is required by Condition B or F of LC0 3.3.17, " Post Accident Monitoring (PAM)

Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status,

b. Any abnormal degradation of the containment structure detected during the tests required by the Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (es3ecially at tendon anchorages), the inspection procedures, tie tolerances on cracking, and the corrective action taken,
c. Following each inservice ins)ection of steam generator (OTSG)' tubes, the NRC shall 3e notified of the following prior to ascension into MODE 4:
1. Number of tubes plugged and sleeved
2. Crack-like indications in the first span
3. An assessment of growth in the first span indications, and
4. Results of in-situ pressure testing, if performed.

The complete results of the OTSG tube inservice insp'ection shall be submitted to the NRC within 90 days ifisEsthFOji l i

nl _os. g@ s.).Ye p sh11 W e-following the completion

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1. 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 first span IGA indication, and
4. Identification of tubes plugged and tubes sleeved.

(continued)

Crystal River Unit 3 5.0-29 Amendment No. M8 l

i

Reporting Requirements 5.7 o 1 5.7 Reporting Requirements

)

5.7.2 Special Reports (continued)

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eg?,.4w Results of 0TSG tube inspections that fall into Category C-3 shall be reported to the NRC prior to resumption of plant operation. This report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

i Crystal River Unit 3 5.0-29A Amendment No. MB l

,o 1

1 FLORIDA POWER CORPORATION I CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302/ LICENSE NO. DPR-72 1

ATTACHMENT C LICENSE AMENDMENT REQUEST #221, REVISION 1 "B" ONCE THROUGH STEAM GENERATOR TUBE SURVEILLANCE PROGRAM AND SPECIAL REPORTS Set of Changed Pages with Revision Bars l

l

I Procedures, Programs and Manuals 5.6 O

(

l 5.6 Procedures, Programs and Manuals l

5.6.2.10 OTSG Tube Surveillance Program (continued) l 8. Plugging / Sleeving Limit means the extent of degradation beyond which the tube shall be i

restored to serviceability by the installation of a sleeve or removed from service because it may become unserviceable prior to the next r,1spection and is equal to 40% of the nominal tube or sleeve wall thickness. No more than five thousand sleeves may be installed in each OTSG.

9. Unserviceable describes the condition of a tube if it 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,oramainsteamlineorfeedwaterline break, as specified in 5.6.2.10.3.c, above.
10. Tube Inspection means an inspection of the entire OTSG tube as far as possible.
b. The OTSG shall be determined OPERABLE after completing the corresponding actions (plug or sleeve all tubes exceeding the plugging /sleevin limit and all tubes containing through-wall cracks required by Table 5.6.2-2 and Table 5.6.2-3 if he provisions of Specifica(tion 5.6.2.10.2.d are utilized). Defective tubes may be re) aired in accordance with the B&W process (or metiod) equivalent to the method described ,

in report BAW-2120P.

c. In service tubes with pit-like IGA indications in the first span of the "B" 0TSG shall be monitored for growth of these indications in the following fashion:
1. Tubes that were inspected with the high frequency bobbin probe in 1997 shall have the indicated %

throughwall value from the current inspection compared to the 1997 indicated % throughwall value. A high frequency bobbin > robe comparable to the high frequency bobbin pro 3e used in the 1997 inspections shall be used for this comparison.

2. Tubes shall have the indicated voltage on the 400 kHz channel from the current inspection compared to the 1997 indicated voltage on the 400 kHz channel. A mid-range frequency bobbin probe comparable to the mid-range frequency bobbin probe used in the 1997 inspections shall be used for this comparison.

(continued) l Crystal River Unit 3 5.0-17 Amendment No.

l

. Reporting Requirements 5.7 O

5.7 Reporting Requirements 5.7.2 Special Reports (continued)

The following Special Reports shall be submitted:

a. When a Special Report is required by Condition B or F of LC0 3.3.17, " Post Accident Monitoring (PAM)

Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

b. Any abnormal degradation of the containment structure detected during the tests required by the Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (es aecially at tendon anchorages), the inspection procedures, tie tolerances on cracking, and the corrective action taken.
c. Following each inservice ins)ection of steam generator (OTSG) tubes, the NRC shall ae notified of the following prior to ascension into MODE 4:
1. Number of tubes plugged and sleeved
2. Crack-like indications in the first span
3. An assessment of growth in the first span indications, and
4. Results of in-situ pressure testing, if performed.

The complete results of the OTSG tube inservice inspection shall be submitted to the NRC within 90 days after startup (breakerclosure). The 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. Location, bobbin coil amplitude, and axial and circumferential extent (if determined) for each first span IGA indication, and
4. Identification of tubes plugged and tubes sleeved.

(continued)

Crystal River Unit 3 5.0-29 Amendment No.

' Reporting Requirements 5.7 i

5.7. Reporting Requirements 5.7.2 Special Reports (continued) i

5. For first span "B" 0TSG pit-like IGA, a summary of  ;

l analyses performed to determine if estimated leakage i based on the projected end-of-cycle percent throughwall i distribution exceeds the leak limit (determined from l the licensing basis dose calculation for the main i steamline break) for the next operating cycle.  !

6. For first span "B" 0TSG pit-like IGA, a summary of analyses performed to determine if the calculated i conditional burst probability based on the projected  !

end-of-cycle (or if not practical, using the actual l measured end-of-cycle) percent throughwall distribution exceeds 1x10-2, and an assessment of the safety significance of the occurrence if exceeded.

Results of OTSG tube inspections that fall into Category C-3 l shall be reported to the NRC prior to resumption of plant operation. This report shall provide a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

I l

I l Crystal River Unit 3 5.0-29A Amendment No.

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