ML20107G459

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Proposed Tech Specs 4.4.5.4.a.10 Re SG Surveillance Requirements
ML20107G459
Person / Time
Site: South Texas STP Nuclear Operating Company icon.png
Issue date: 04/18/1996
From:
HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20107G452 List:
References
NUDOCS 9604230237
Download: ML20107G459 (1)


Text

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. ST-IIL-AE-5270 Attachment 3 l Page 3 of 5 REACTOR COOLANT SYSTEM STEAM GENERATORS SURVEILLANCE REQUIREMENTS (Continued) 10)'"F*"'c'r teHa^fFor Unit'1'slvT7'Tutie"degiiadati'6s be16(a"

""speci" led distance from tie hard roll contact point at or near the top of-tubesheet (the F* distance) can be excludsd from consideration,to the acceptance criteria stated in this section (i.e., plugging of such tubes is not required). The 1 methodology for determination for the F* distance as well as the list of' tubes to which the F* criteria is not applicable is described in detailin Topical _ Report 2BAW'10203Pj ~  !

Revision b l

b. The steam generator shall be determined OPERABLE after completing the corres)onding actions (plug all tubes exceeding the plugging limit and I all tu)es containing through-wall cracks) required by Table 4.4-2.

4.4.5.5 Reoorts )

l

a. Within 15 days .following the completion of each inservice inspection i of steam generator tubes. the number of tubes plugged in each steam  :

generator shall be reported to the Commission in a Special. Report  !

pursuant to Specification 6.9.2. i i

b. The complete results of the steam generator tube inservice inspection I shall be submitted to the Commission in a Special Report pursuant to l Specification 6.9.2 within 12 months following the completion of the inspection. This Special Report shall include:
1) Number and extent of tubes inspected.
2) Location and percent of wall-thickness penetration for each  ;

indication of an imperfection, and ,

3) Identification of tubes plugged.
c. Results of steam generator tube inspections which fall into l Category C-3 shall be reported in a Special Re) ort to the l Commission pursuant to Specification 6.9.2 wit 11n 30 days and prior to resumption of plant operation. This report shall provide i a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

SOUTH TEXAS - UNIT 1 & 2 3/4 4-16 TSCA NIH4 9604230237 960410 t

PDR ADOCK 05000498 P PDR

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