ML20217N250

Proposed Improved Tech Specs 5.6.2.10 Re Tube Surveillance

ML20217N250
Person / Time
Site:	Crystal River
Issue date:	08/20/1997
From:	FLORIDA POWER CORP.
To:
Shared Package
ML20217N242	List: 3F0897-10, Forwards Description of Changes,Reason for Request & Evaluation of Request Re TS Change Request Notice 211,Rev 1, in Response to NRC ML20217N250
References
NUDOCS 9708260083
Download: ML20217N250 (6)

Text

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ATTACHMENT B TECHNICAL SPECIFICATION CHANGE REQUEST NOTICE No. 211, REVISION 1 STRIKEOUT / HIGHLIGHTED PAGES Deletions are indicated by strikeout Addition of text is indicated by highlighting 6

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DOCK O N M 2 P

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Reporting Requirements 5.7

' eporting Requirements

' 5.7 R

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 LCO 3.3.17. " Post Accident Monitoring (PAM) d within the Instrumentation," a report shall be submitte following 14 days.

The report shall outline the preplanned the cause of the alternate method of monitoring,d schedule for restoring the inoperability, and the plans an instrumentation channels of the function to OPERABLE status.

b.

Any abnormal degradation of the containn nt 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 secially at tendon anchorages), the inspection procedures, t1e tolerances on cracking, and the corrective action taken.

c.

Following each inservice ins)ection of steam generator (OTSG tubes, the NRC shall se 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 following the completion of.the inspection.

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:!GALindication,,and 4.

Identification of tubes plugged and tubes sleeved.

-(continued)

Crystal River Unit 3-5.0-29.

Amendment No M4 hlY Until hf=1 !! Only

ATTACHMENT C TECHNICAL SPECIFICATION CHANGE REQUEST NOTICE No. 211, REVISION 1 REVISION BAR P, AGES b

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Reporting Requirements 5.7

'5.7 Reporting Requirerrents 5.7.2 Special Reports (continued)

The following Sper.ial Reports shall be submitted:

When a Special Report is required by Condition B or F of a.

LC0 3.3.17, " Post Accident Monitoring (PAM) d within the Instrumentation," a report shall be submitte following 14 days. The report shall outline the preplanned the cause of the alternate method of monitoring,d schedule for restoring the inoperability, and the plans an instrumentation channels of the Function to OPERABLE status, b.

Any abnormal degradation of the containment structure detected during the %sts 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 (especially at tendon anchorages), the inspectioa procedures, the 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 following the completion of the inspection.

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 spanIGAindication,and 4.

Identification of tubes plugged and tubes sleeved.

(continued)

Crystal River Unit 3 5.0-29 Amendment No.

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Reporting Requirements 5.7 1

5.7 Reporting Requirements 5.7.2 Special Reports (continued)

Results of OTSG 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,-464 "clid Until Refucl 11 Only

Reporting Requirements 5.7 t

5.7 Reporting Requirements-5.7.2 Special Reports (continued)

Results of 0TSG tube inspections.that fall into. Category C-3 1shall be reported to the NRC prior to resumption of plant

. operation.

This report shall: provide a description of a

investigations conducted to determine cause of the-tube degradation and corrective measures taken to prevent recurrence.

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Crystal River Unit.3L 5.0-23A Amendment-No.

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