ML20086Q178

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Preliminary Results of Inservice Insp Program,Refueling Outage 1. No Significant Deficiencies Identified
ML20086Q178
Person / Time
Site: Surry Dominion icon.png
Issue date: 06/15/1975
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20086Q161 List:
References
ISI-75-5, NUDOCS 8402270461
Download: ML20086Q178 (3)


Text

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O PRELIM 1!:ARY RESULTS OF Ti!E INSERVICE INSPECT 10'; PROGRAM KLFUELING UUTAGE NO. _1 SURRY POWEit STATION UNIT FO. 2 JUNE 15, 1975 l

REPORT No. ISI 75-5 l

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I. INTRODUCTION In accordance with the requirements of Technical Specification 6.6.C, this report contains a st.mmary of the preliminary results of re-the inservice inspection activities performed during the first fueling outage of Unit No. 2 at the Surry Power Station. The document entitled, Inservice Inspection _ Program, Refueling Outage No. 1, Surry Power Station, Unit _ M . 2, Report No. IS1 75-2 dated March 10, 1975 provides the specific details concerning the inspections performed.

This report is intended to be a preliminary report of the results "of the inservice inspections following the first refueling outage, A more detailed report will pursuant to Technical Specification 6.6.C.

be submitted within 90 days.

11.

SUMMARY

OF INSPECTION RESULTS The inservice inspections performed during the period covered by this report includec all those listed in Report No. ISI 75-2. All in-spections were conducted as specified in ISI 75-2 except Technical Spec-to shell ification reference 4.2, regenerative heat exchanger nozzle welds. This was changed from a volumetric examination to a surface ex-amination (liquid penetrant) because the regeneratiive heat exchanger is a Class III vessel.

All inspections were satisfactory; however, the following indications were identified: .

b O o Method Disposition of Examination Indication Area Examined Visual 18 punch marks Cleared Steam Cen. A item 3.3  !

. (29" RC-301-2501R) .

Nicks in threads C1 cared Reactor Vessel Visual Item 1.8 Closure Studs Visual Arc Strikes Not significant-will be Miscellaneous groundout when time permits Item 7.2 Low IIcad SIS Piping  !

Arc Strikes, Groundout and repaired, all Hisec11ancous Visual & indications were cleared MT & PT Cracked lashing Item 7.3 lugs LP Turbine blades Visual Arc Strikes at Not significant-will be Misec11aneous floor supports groundout when time permits Item 8.1.2 Sensitized SS III. CONCLUSIONS The results of the inservice inspections performed verified the integrity of the systems and components examined. The discrepancies noted were corrected or will be corrected as indicated in Part II.

Based on the results of the inservice inspection program, as summarized herein, the safety systems and components inspected have not-experienced degradation and there is reasonable assurance that they will continue to perform their design function.

i As required by Technical Specification 6.6.C, a detailed report of the inspections performed will be submitted within 90 days O

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