ML20086E616

Revised Pages to Cooper Nuclear Station Inservice Insp Program

ML20086E616
Person / Time
Site:	Cooper
Issue date:	11/08/1991
From:	NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20086E614	List: ML20086E616 NLS9100771, Forwards Revised Pages to Cooper Nuclear Station Inservice Insp Program Revising Augmented Insp Program for Feedwater Nozzles to Allow Use of Automated Ultrasonic Insp Method in Lieu of Penetrant Test
References
PROC-911108, NUDOCS 9112020212
Download: ML20086E616 (9)

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At t ac htwrit to lit.S91007 71 November 1991 Addenda Page 1 of 9 Date of 1ssue: November 8, 1991 NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION INSERVICE INSPECTION PROGRAM ltR ASME CIASS 1, 2, AND 3 COMPONENTS Revision 3 This is an addenda to the loose leaf version of the Inservice Inspection h sgram for ASME Class 1, 2, and 3 Components, Revision 3, and is ist,ued in the forin of replacernant or additional pages, revisions, additions, or deletions, and are incorporated directly into the affected pagem.

Summarv_of.Changitsi

'This is the tenth addenda to be published to the Inservice Inspection Program for ASME class 1, 2, and 3 components, Revision 3.

This change affects only the Augmented ISI section of the CNS ISI Pro 6 ram.

Changes given below are identified in the text by a mars n note next i

to the affected item.

SECTION PAGE(s)

DESCRIPTION Introduction Section All Remove and destroy existing pages and replace with attached pages.

Augmented Inservice Inspections Tab 2 Remove and destroy existing pages Section and replace with attached pages.

Revise CNS feedwater nozzio PT examination requirements per NPPD commitment to U.S. NRC, approved in letter, U.S. NRC to G. R. llorn (NPPD), dated 10 2 91.

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Attachment to NLS9100771 Page 2 of 9 i

Augmonted Inservico inspections 1

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Attachment to Hl.S9100771

'Page 3 of 9 AUCMENTED IL9fMICE INSPECTIONS Augtnented Inservice Inspections (AISI) are not ASME Section Xi Code requirements, but are 1) additions 1 examinations areas or 2) increased j

inspection frequency or combinations of both which are requested by l

the Nuclear Regulatory Comsnission, recommended in Cencral Electric j

Cotopany Service Information Letters or added for other reasons.

When examination components fall into the scheduled testing of ISI and are also AISI reg.irements, then credit for both requirements may he j

naken (no doubic testin6).

The following are types of Augmented Inservice Inspections required at July 89 Cooper Nucicar Station. The TAB ntunber corresponds to tabbed pages that follow which contain information on the specific type of AISI.

TAB TYPE DESCRIPTION REVISION DATE i

1 1

All ring girder bolting and ring girder anchor Original bolting is to be voltunetrically inspected each ten Release - 3/85 year interval.

The anchor bolting adjacent to the inboard HSIV is to be visually inspected each ten year interval.

(

Reference:

URC DRO Bulletin #74-3.)

2 2

Ultrasonic examination of the feedwater nozzio safe Nov. 91 ends, bores, and inside blend radii, and visual L

inspection of the feedvater sparrers per Tabic 2 and Section 4.3.2.4 of NUREC 0619.

In lieu of dyo penetrant exam of feedwater nozzles por NUREG 0619, perform automated UT of nozzles per U.S. NRC letter dated October 2, 1991, 3

3-Visual inspection of the Core Spray spargers and Original the Core Spray piping inside the RpV shall bo Releaso 3/85 contucted each refueling outage.

(

Reference:

IE Bulletin No. 80 13.)

4 4

Ultrasonic examinat;ons, utilizing'G.E. proceduro Original Tp508.0654 Revision D, or equivalent, are Release - 3/85 conducted to assess the integrity. of the jet pturp hold down beans'at the mid length ligament areas i

bounding the beam bolt.

These examinations shall be performed once during the second ten year interval.

These examinations may be deferred to the end of the interval.

s Page 1-of 3

Attachment to N1.S9100771 Page 4 of 9 TAB TYPE DESCRIPTION REVISION DATE 5

5 Ultrasonic examinations per veneric Letter (G.L.)

Sept. 91 88 01.

G.L. 88 01 applies to all EVR piping made of austenitic stainless steel that is four inches or larger in nominal diametar, and contains reactor coolant at above 200'F during power operation regardless of code classification.

All accessible welds will be examined in accordance with CNS G.L.

88 01 commitments.

Add requirements for weld crown conditioning for UT (future welds) per Generic Electric SIL No. 117R3.

6 6

Visual inspection of steam dryer channel welds Feb. 89 during refueling outages (Reference General Electric SIL No. 474.)

7 7

Visual inspection of jet pump nozzles and mixer July 89 inlets in conjunction with jet pump inspection.

(

Reference:

General Electric SIL No. 465.)

8 8

Ultrasonic examination of the shroud support access Aug. 91 hole covers once every three years beginning with the Spring 1993 Refueling Outage.

Visual examination VT 1 of the shroud support access hole covers during the 1991 Refueling Octage.

(

Reference:

General Electric SIL No. 462, S2, R1, and G.E. memo RC119143, dated April 4, 1991.)

9 9

Visual inspection of the Core Spray T junction box July 89 velds inside the reactor vessel.

(

Reference:

General Electric SIL No. 289. R1, S1.)

10 10 Visual examination of the Reactor Recirculation July 89 (RR) pumps' shafts, pump covers, impeller / shaft attachment region (including bolts), and hydrostatic bearings (including baffle plate).

Frequency of examination shall coincide with the regularly scheduled RR pumps inspection.

(

Reference:

General Electric SIL No. 459 and RICSIL No. 038.)

11 11 Visual examination of all accessible areas of the Aug. 91 Intermediate Range Monitor (IPA) and Source Range Monitor (SRM) dry tubes each refueling outage.

(

Reference:

General Electric SIL No. 409 RI.)

12 12 Ultrasonic (UT) examination cf all remaining old Aug. 91 design creviced Inconel 6001hroud llend Bolts (SHBs) each refueling outage.

(Referenco:

General Elcetric SIL No. 433.)

13 13 Rationale for updating of G :neral Electric reactor Aug. 91 pressure vessel ultrasonic inspection procedures to incorporate U.S. NRC Regulatory Guide 1.150 requirements.

(Reference General Electric SIL No. 515.)

Pare 2 of 3

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Attathment to 14LS91007 71 l'a r e 5 o f 9

__m TAB TYPE DESCRil'TIO!1 REVIS1011 DATE 14 14 Au6mented Inservice Inspection (AISI) Program for Aug. 91 Service k'ater (SW) and Reactor Equipment Cooling (REC) pipe supports outside the scope of the CllS ASME Section XI ISI Program. This AISI Program requires only VT 3 and/or VT 4 examinations of selected supports.

15 15 Ultrasonic examination of C!15 RP" llend Studs in Sept. 91 accordance with General Electric RICSIL llo. 055.

RPV studs 1-21 and 26 scheduled for examination based on raw material heat treated hardness values (ASME Section XI Category B C 1 Code credit will be taken for RPV studs 18 21 and 26).

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Page 3 of 3

- At tachtnent to NLS9100771 l' age 6 of 9 Augmented Inservico Inspections Tab No. 2 l

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Attachment to NLS9100771 J

COOPER NUCLEAR STATION Page 7 of 9 AUCMENTED INSERVICE INSPECTION PROGRAM IN ACCORDANCE WITH U.S. NRC NUREG 0619

.REFERENCESt 1.

U.S.

NRC NUREG 0619,. BWR Feedwater Nozzle and. Control Rod N o v. '. i Drive Return Line Nozzle Cracking, published Novembet, 1980.

c 2.

Letter, G. R. llorn (NPPD) to U.S. NRC, dated January 22, 1991, subject:

BWR Feedwater Nozzle Inspections. Cooper Nuclear Station.

3.

Letter, G. R. llorn (NPPD) to U.S. NRC, dated August 14, 1991, subject:

BWR Feedwater Nozzle Inspections, Cooper Nuclear l

Station.

4.

Letter, P. W. O'Connor (U.S. NRC) to G. R. llorn (NPPD), dated October 2, 1991, subject:

Cocper Nuclear Station Review of gi NPPD Request Regarding Feedwater Nozzle Examination Methods.

1980, as a result of previous commitment to Reference 1 CNS removed the

.l-existing stainless steel cladding from the reactor pressure vessel (RPV) feedwater nozzles and installed new triple sleeve / double piston ring seal 1

feedwater spargers.

Also at that time, CNS implemented the non destructive i

examination requirements of NUREG 0619.

The table below lists the NUREG 0619 required NDE exams performed at CNS since 1980.

1 NDE EXAMINATION PERFORMED ON FW REFUELING O m.F.S N4A; N4 B. N4C. N@

OUTAGE PT UT VT 1980 Yr.S YES YES f

1982 NO YES YES-SPARGERS ONLY 1983 NO NO YES-SPARCERS ONLY-1984 NO NO YES-SPARGERS ONLY 1986 NO YES YES-SPARGERS ONLY 1988 NO NO YES-SPARGERS ONLY 1989 NO YES YES-SPARGERS ONLY Page 1 of 2 i

I Attachment to NLS9100771 Page 8 of 9 l

NUREC 0619. Table 2 requires a dye penetrant (PT) exam of the inner surfaces on one feedwater nozzle every nine refueling cycles. This would require during the

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1991 Refueling Outage, as a minimum, removal of one feedwater sparge

• and a penetrant exam of that nozzle, as well as accessible portions of the wm ining nozzles. Due to ALARA concerns and operational consider: cions, CNS p or;ve3 in Reference 2, to pe'rform an automated ultrasonic ei tmination of the f m.Nate r nozzles in lieu of the specified dye penetrant examination. NPPD also cer.mitted to implement automated feedwater sparger seal leakage and fatigue usage / crack growth monitoring at CNS. Furthermore, CNS committed in Reference 3-to qualify the automated UT examination techniques to be employed on a full-size BWR nozzle mockup with several narrow notches and at least one actual fatigue crack.

The NRC in Reference 4 approved NPPD's proposal to perform automated UT examina-tion in lieu of PT examination of feedwater nozzles at CNS. CNS will conduct an automated UT exam at the feedwater nozzles during the 1991 Refueling Outage using the General Electric Reactor Inspection System (GERIS) and the following General Electric procedures:

• GF UT-309, Rev. O Planar Flav Sizing for Nozzle Inner Radius and dore Regions

+ GE UT-402, Rev. 0 UT Alternative to NUREG 0619 Nozzle Radius and Lot 3 PT Requirements Copies of these procedures are on file at CNS, A copy of the Reference 4 letter is included in this section for further information.

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