ML20137L000

Addenda to Rev 3 to Inservice Insp Program for ASME Class 1,2 & 3 Components

ML20137L000
Person / Time
Site:	Cooper
Issue date:	10/31/1985
From:	GENERAL ELECTRIC CO.
To:
Shared Package
ML20137K994	List: ML20137L000 NLS8600021, Forwards Addenda to Rev 3 to Inservice Insp Program for ASME Class 1,2 & 3 Components
References
PROC-851031, TAC-54682, NUDOCS 8601240320
Download: ML20137L000 (9)

Text

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OCTOBER 1985 ADDENDA Date of Issue: October 31, 1985 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION UNIT 1 INSERVICE INSPECTION PROGRAM FOR ASME CLASS 1, 2, AND 3 COMPONENTS Revision 3 This is an Addenda to the loose-leaf version of the Inservice Inspection Program for ASME Class 1, 2, and 3 Components, Revision 3 and are issued in the form of replacement pages. Revisions, additions, or deletions are incorporated directly into the affected pages. It is advisable, however, that these title sheets and all replaced pages be retained for reference in the correspondence section.

SUMMARY

OF CHANGES This is the first addenda to be published to the Inservice Inspection Program for ASME Class 1, 2, and 3 Components, Revision 3.

r- Replace or insert the pages listed. Changes given below are identified on the

( pages by a margin note, Oct 85, placed next to the affected area.

Section Page Description Introduction 4 Line 6.3.1, Change "of" to "and" Introduction 4 Line 6.3.6, Change " poor" to

" pool" Introduction 4 Line 6.3.8, Change "contivetivity" to "conduc ti vi ty" Introduction 5 Add Type 4 AISI Introduction 6 Delete Paragraph 7.5 System / Comp Abbr. for Class 1 3 of 4 Change "budings" to " bushings" for PRD System / Comp Abbr. for Class 2 1 Change " branch" to " bleed" for BHS

' Page 1 of 2 8601240320 860117 PDR ADOCK 0 % g8 O

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October 1985 Addenda ,

. O Section Page Description

, System / Comp i

Abbr. for Class 2 1 Change " Vent" to " Vent" for PVS System / Comp Abbr. for Class 2 2 Delete " vent" in RHD -

i Hanger and Support Abbreviations 1 of 3 Change " fluid head" to " flued head" i

e 4

4

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6.0 Examination Boundaries cont'd 6.3 The following Systems or portions of Systems are included in O the isi ex iaatioa bo##a ri >:

OP&ID SYSTEM 6.3.1 2004 Condensate and Feed Water 6.3.2 2022 Primary Containment Cooling and Nitrogen Inerting

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6.3.3 2026 Reactor Vessel Instrumentation Reactor Recirculation and Suppression Oct 85 6.3.4 2027 Chamber Vent 6.3.5 2028 Reactor Building and Drywell Equipment Drain 6.3.6 2030 Fuel Pool Cooling and Cleanup

! 6.3.7 2031 Reactor Building Closed Cooling Water 6.3.8 2032 High Conductivity Floor Drains 6.3.9 2037 Stand By Gas Treatment and Off Gas Filters 6.3.10 2038 Reactor Building Floor and Roof Drains 6.3.11 2039 Control Rod Drive Hydraulic 6.3.12 2040 Residual Heat Removal 6.3.13 2041 Main Steam - Reactor Building 6.3.14 2042 Reactor Water Clean Up 6.3.15 2043 Reactor Core . Isolation 6.3.16 2044 High Pressure Coolant Injection 6.3.17 2045 Core Spray and Stand By Liquid Control 6.3.18 2049 Condensate Supply 6.3.19 2084 Atmospheric Containment Atmospheric Dilution 6.3.20 2077 Diesel Gen. Bldg. Service Water, Starting Air, Fuel Oil, Sump and Roof Drains 6.3.21 6000302 Augmented Off Gas O

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6.0 Examinaticn Boundaries cont'd OP&ID SYSTEM I

6.3.22 13095-12-FSK-1-1 Post Accident Sampling 7.0 Augmented Inservice Inspections 7.1 Augumented Inservice Inspections (AISI) are not ASME Section XI Code Requirements but are 1) additional examination areas, or 2) increased inspection frequency or combinations of both which are requested by the Nuclear Regulatory Commission.

7.2 When examination components fall into the scheduled testing of both ISI and AISI, then credit for both requirements are taken (no double testing).

7.3 There are presently 3 types of Augumented Inservice Inspections required at Cooper Nuclear Station:

TYPE DESCRIPTION 1 All ring girder bolting and ring girder anchor bolting is to be volumetrically inspected each ten year interval. The Anchor Bolting adjacent to the Inboard MSIV is to be visually inspected each ten year interval. (Reference NRC DRO Bulletin #74-3).

2 Ultrasonic examination of the feedwater nozzle safe O eads. bores. ead iaside biead r aii. iiauio penetrant examination of the feedwater nozzles, and visual inspection of the.feedwater spargers as required per Table 2 and Section 4.3.2.4 of NUREG-0619.

3 Visual inspection of the Core Spray Spargers and the Core Spray Piping inside the RPV shall be inspected each refueling outags. (Reference IE Bulletin No. 80-13).

4 Ultrasonic examinations, utilizing GE procedure TP508.0654 Rev. D or equivalent, are conducted to assessthe integrity of the jet pump hold-down beams at the mid length ligament areas bounding the beam Oct 85 bolt. These examinations shall be performed once during the 2nd Ten Year Interval.

7.4 The following ASME Catagory welds are being eliminated from the Augumented Inspection, and are listed in separate section of the ISI Program.

! 7.4.1 Weld susceptible to Intergranular stress corrosion l

cracking that are required to be inspected per NUREG-0313.

7.4.2 Welds catagory B-F and B-J that are designated as

" Pipe Whip".

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8.0 Relief Requests Oct 85 8.1 When on ASME Code Class 1, 2 or 3 component is determined to

() 6' '=aract'ca' ' '"'a c' '" accorda"c "" ^S"E S*ct' " "'

IWA-2000, IWB-2000, IWC-2000, IWD-2000 or IWF-2000, a specific written relief request from the ASME Code is submitted to the NRC in accordance with Section 3.0 (above).

Each written relief request contains the following information as a minimum:

8.1.1 Identification of conponent(s) for which relief is requested 8.1.2 ASME Section III Code Class 8.1.3 The specific ASME Code requirement that has been determined to be impractical 8.1.4 Cooper Nuclear Station relief justification (s) information for requesting relief 8.1.5 Specific alternative inspection (s) in lieu of ASME Code Section XI requirement (s) 8.2 The following is a list of Relief Requests:

Relief Request No. Description w 1 ASME Category B-J, Inaccessible welds, primary containment 2 ASME Category C-F, RHR Drywell Spray internal to Drywell 3 ASME Category B-D, RPV Top Head Nozzle inner radii 4 ASME Category C-F, Inaccessible welds in floor penetrations 5 ASME Category C-A, Inaccessible welds on the RHR Heat Exchanger ,

6 ASME Category B-A, Inaccessible RPV welds O -s-GENERAL $ ELECTRIC

SYSTEM / COMPONENT ABBREVIATIONS FOR ASME CLASS 1 SYSTEM / COMPONENT ABBREVIATIONS SYSTEM / COMPONENTS O PRC Pressure Retaining Bolting - Washers Oct 85 PRD Pressure Retaining Bolting - Bushings PRE Pressure Retaining Bolting - Ligaments PRF Ring Girder Anchor Bolts PRG RPV Skirt-to-Ring Girder Bolts PSA HPCI Steam PWA HPCI Water RCA CRD Return RCIC Reactor Core Isolation Cooling (Bolting)

RF Reactor Feedwater Bolting RFH Reactor Feedwater Hanger RFS Reactor Feedwater Seismic Restraint RHA 20" RHR Supply RHB RHR - Loop A RHC RHR - Loop B RHD 6" RHR Head Spray RHH RHR Hanger PHR Residual Heat Removal (Bolting)

RHS RHR Seismic Restraint RMA Recirculation - Loop Al RMB Recirculation - Loo'p B1 RPA Recirculation - Loop A2 RPB Recirculation - Loop B2 RR Reactor Recirculation (Bolting) 1 RRA Recirculation - Loop B1

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SYSTEM / COMPONENT ABBREVIATIONS FOR ASME CLASS 2 SYSTEM / COMPONENT ABBREVIATIONS SYSTEM / COMPONENTS O BHS Bleed Steam Hanger BSS Bleed Steam Seismic Restraint CAD Containment Atmospheric Dilution CDS Condensate Supply CS Core Spray CND Condensate HPCI HPCI Flange - to Punp Bolting MS Main Steam Oct 85 MSH MS Hanger MSS MS Seismic Restraint N ,

Nitrogen Primary Containment Bolting OG Off Gas PNC Nitrogen Primary Containment Isolation O- System PSA HPCI Steam PVH Process Vent Hanger PVS Process Vent Seismic Restraint RAS RHR Loop A Steam RAW RHR Loop A Suction Bypass, Torus Test Line and Spray RCIC Reactor Core Isolation Cooling RBS RHR Loop B, Steam RBW RHR Loop B, Water RCT RHR Cross Tie RCIC RCIC Flange - to Pung Bolting RHA RHR 20" Supply O RHB RHR tooP A. Water GENERAL $ ELECTRIC l r,

SYSTEM / COMPONENT ABBREVIATIONS FOR ASME CLASS 2 l SYSTEM / COMPONENT ABBREVIATIONS SYSTEM / COMPONENTS RHC RHR Loop B Water RHD 6" RHR Head Spray Oct 85 RHE Containment Spray Loop B RHF RHR Heat Exchanger Flange Bolting RHG Containment Spray Loop A RHH RHR Hanger RHR RHR Heat Exchangers RHS RHR Seismic Restraint RHRA RHR Pump 1A Strainer, Bolting RHRB RHR Pump 1B Strainer, Bolting RHRC RHR Pump IC Strainer, Bolting RHRD RHR Pump 1D Strainer, Bolting RWCU Reactor Water Cleanup RSA RCIC Steam RWA RCIC Water SGTS Standby Gas Treatment

. SDN Scram Discharge Volume North SDS Scram Discharge Volume South

! SW Service Water RCC Reactor Bldg. Closed Cooling Water REC RPA RHR Pump, A Loop RPB RHR Pump, B Loop RPC RHR Pump, C Loop RPD RHR Pump, D Loop O

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HANGER AND SUPPORT ABBREVIATIONS FIELD ABBREVIATION DESCRIP1 ION ABS - Attachment to building structure B Bolted W Welded APRC - Attachment to pressure retaining component.

B Bolted HG Hanger NA Not Attached PC Primary Containment Penetration PI Pipe PU Pump VA Valve VE Vessel W Welded BS - Building Structure CB Concrete Beam CC Conc.ete Ceiling CF Concrete Floor CW Concrete Wall CWC Concrete Wall and Ceiling CWF Concrete Nall and Floor DW Drywell EP Embed Plate Oct 85 FH Flued Head l

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