ML20082M318

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Forwards Inservice Insp Exam Plan for 1983-84 Refueling Outage.First Insp Period - Second 10-yr Interval Checklist & Augmented Insp to Complete First 10-yr Insp Interval Checklist Also Encl
ML20082M318
Person / Time
Site: Pilgrim
Issue date: 12/01/1983
From: Harrington W
BOSTON EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
83-290, NUDOCS 8312060103
Download: ML20082M318 (12)
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  • e BDaTON EDISON COMPANY 800 50YLETON STREET g BOETON. MA55ACHusETTs 02199 0 WILLIAM D. HARRINGTON N.dTb.A.

December 1, 1983 BECo Ltr.83-290 Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission F Washington, D.C.

1983/1984 Inservice Inspection Plan

Enclosures:

(A) First Inspection Period - Second Ten Year Interval ISI Checklist (B) Augmented Inspection to Complete First Ten Year Inspection Interval ISI Checklist

Dear Sir:

In accordance with the requirements of ASNE Section XI, 1980 Edition, Article IWA-1400(c), Boston Edison Company files for your information and use, i

a copy of the ISI Examination Plan for the 1983/1984 Refueling Outage of the Pilgrim Nuclear Power Station, Unit #1.

l The 1983/1984 ISI Examination will be divided into three specific categories; namely:

(a) mechanized volumetric examination of selected reactor vessel nozzles in the recirculation system; (b) remote visual examination of the core spray sparger and the remote visual and ultrasonic examination of the jet pump beams; (c) manual volumetric, surface, and visual examination of selected components in the Class 1, 2, and 3 systems, i

Included in the manual examination is a listing of components which are to be inspected as part of the first ten-year interval (Enclosure (B)).

The examinations which are included in the first inspection period of the second interval are listed in Enclosure (A). The examination of the Core Spray Sparger is not being considered as part of the second ten-year program.

l l Should you have any questions, please contact us.

Very truly yours, l 8312060103 831203 PDR ADOCK 05000293 PDR 0 q l \

Boct'en I13 SERVICE ItlSPEC110!1 CilECKl.IST Pilgriu !!ucicar Ed i s. .ii 1981/1984 SEFl!El.1!4C OUTAGE P wer station .

co2p.iny F !!! .i INSPECTI0ft PERIOD - SECOND TEN-YEAR INTERVAL Unit - 1 EllCLOSURE (A)

Page I of 10 Rev. 0 System: gg, g;. 3 g

! P e. ! h , Sec t ton Sect 10: tio . xw a wl '. XI XI Item of Exam ' Remarks L.loe or Ca.mponent treser Ipt jon Co -o i . T Categor Iten Description I t em!. !!etliod g4 ,

!!untier et Reactor Vessel 252 i B-A Bl.11 Circumferential Shell Weld 1 Vol. Examine length of weld that is accessible from i

nozzle opening fl2B.

252 1 B-A Bl.22 Meridional llead Welds at 3 Vol.

0 , 45 , and 90 .

252 1 B-A Bl.30 Shell-to-flange veld from 1 Vol. Examination to be con-0 through 120 . ducted from flange face.

252 i B-A Bl.40 llead-to-flange weld from 1 Vol. &

0 through 120 . ,

Surf.

252 1 B-D B3.90 flozzle-to-vessel Welds: 7 Vol. Limited access because o.f fil A, N2A, fl28, il2C, N3A, biologica'l shielding N4A, and N6A. des.ign and attachment of insulation.

252 i B-D B3.100 Nozzle inner radius sectior s'10 Vol. Feedwater nozzles are fil A, fl2A, H2B, N2C, N3A, examined in accordance i '

N4A, N4B, N4C, N40, and with NUREG 0619.

N6A ,

252 i B-F B5.10 Safe End-to-nezzle welds '9 Vol. &

  • 2-NIA-1, 2-N2A-1, 2-fl2B-1, Surf. ,

2-fl2C-1, 14-A-1, 6-N4A-1, 6-fl40-1, 6-fl4C-1, and ,

6-N4D-1. ,  ! , ,' ,

i i

4 4 0

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_ _ _ _ _ _ _~f ~ ~ ~ ~ [ ~~ ( _ __ ___ ~ $ _'_~ ~ -

Boston ~

INSERVICE INSPECTION CHECKLIST Ed ison 1983/1984 REFUELING OUTAGE Pilgrim Nuclear -

Station Company FIRST INSPECTION PERIOD - SECOND TEN YEAR INTERVAL [,]#_ ,

, ENCLOSURE (A)

System: Page 2 of 10 Ra.

REACTOR PRESSURE VESSEL AND RECIRCULATION PUMPS O j P&ID n Section S ec t ior No. xW Line or Component and $' XI XI Item of Exam .$ b ' Remarks

]

Descr iption Co-ort $ Categor . Item Number Description I t ems 'fethod h{

n i

Closure Heads Nuts 252 1 B-G-1 B6.10 RPV Nuts (1-18) 18 Surf.

Closure Studs in Place 252 1 B-G-1 B6.20 RPV Studs (1-18) 18 Vol.

Threads in Flange 252 1 B-G-1 B6.40 Threaded Bushings of RPV 18 Vol.

Studs (1-18) f Closure Washers 252 1 B-G-1 B6.50 Closure Washers of RPV 18 Visual Studs (1-18) VT-1 Bushinge 252 1 B-G-1 B6.50 Bushings of RPV Studs that 4 Visual are removed for fuel , VT-1 [

transfer (41-44)

~

Recirculation Pumps 252 1 B-G-1 B6.180 Pump A - Bolts 1-9 18 Vol.

Pump B - Bolts 1-9 252 1 B-G-1 B6.200 Pump A - Nuts, Bushings & All Visual Washers VT-1 Pump B - Nuts, Bushings & All Visual Washers VT-1' Reactor Vessel Skirt Weld 252 1 B-H B8.10 Vessel Skirt Weld from 0 1 Vol.

to 60 (approx.100" of

~

weld). ,

Boston ~

INSERVICE INSPECTION CliECKLIST Ed ison 1983/1984 REFUELING OUTAGE Pilgrim Nuclear .

Company FIRST INSPECTION PERIOD - SECOND TEN YEAR INTERVAL Power Station Unit - 1 -

ENCLOSURE (A)

System: Page 3 of 10 Rev.0 R OUS P&ID n Section Sectior No. xw .

Line or Component and C' XI XI Item of Exam .$ $ ' Remarks Co-o rt E Categorr Item ItemsKethod Description Number Description hk n

Pressure Retaining Bolting 252 1 B-G-2 B7.50 Head Spray Flange All VT-1 Heat Vent Head Instrumentaf. ion 252 1 B-G-2 B7.70 Main Steam Safety & VT-1 Visually examine bolting Relief Valves of valves removed for testing.

252 1 B-G-2 B7.70 Main' Steam Isolation All VT-1 Visual exmaination may be Valves conducted while bolting is in place, valves need not be disassembled.

252 1 B-G-2 B7.70 Recirculation System All VT-1 Valves (202-6A & B) 252 1 B-G-2 B7.70 Feedwater Valves (6-57A & All VT-1 . .

B) 241 1 B-G-2 B7.70 RHR (1001-100) All VT-1 -

(1001-101)

(1001-29A & B) 247 1 B-G-2 B7.70 RWCU (1201-81) All VT-1, (

(1201-5) 245 1 B-G-2 B7.70 RCIC (1301-49) All VT-1 (1301-50) 242 1 B-G-2 B7.70 Core Spray (1400-25A & B) All VT-1 ,

243 1 B-G-2 B7.70 HPCI (2301-4) All VT-1 Valve Body exceeding 4" 243 1 B-M-2 B12.40 HPCI (2301-7) 1 VT-3 , .

n.p.s.

252 1 B-M-2 B12.40 Main Steam Safety & Relief VT-3 Visually examine internal Valves surfaces of valves removed for testing.

- ~ ._ -a

. l Boston . IWSERVIC'E INSPECTION CHECKLIST '

Ed ison 1983/1984 REFUELING OUTAGE Pilgrim Nuclear

  • Company FIRST INSPECTION PERIOD - SECOND TEN YEAR INTERVAL Power Station ,

Unit - 1 i ENCLOSURE (A)

System: VARIOUS Page 4 of 10 Rey, o P&ID n Section Sectior No. WW Line or Component and [" XI XI Item of Exam $ 0- 'R emarks Description Co-ort $ Categor: Item Number Description I tems Flethod h{

n Main Steam Welds 252 1 B-J B9.11 Circumferential Pipe Welds 3 Vol. High stress welds re-1-A-7 inspect each ten year 1-A-8 interval.

1-A-9 Feedwater Welds 252 1 B-J B9.ll Circumferential Pipe Welds 6 Vol. High stress welds re-6-N4A-7 inspect each ten year ',

6-N4A-8 interval. '

6-N4B-7 6-N4B-8 6-N4C-8 6-N4C-9 Residual Heat Removal 241 1 B-J B9.ll Circumferential Pipe. Weld's 2 Vol. liigh stress welds re- 7 10-1A-5 inspect each ten year 10-1B-5 interval. -

High Pressure Coolant 244 1 B-J B9.ll . Circumferential Pipe Welds 2 Vol. High stress welds re- i Injection 23-0-9 ins'pect each ten year 23-0-10 interval.

)

Main Steam Welds 252 1 8-J B9.ll Circumferential Pipe Welds 6 Vol.

1-C-11 1-C-12 1-B-10 1-A-10 .

1-SD-1 1-AS-2 '

Feedwater Welds 252 1 B-J B9.ll Circumferential Pipe Welds 5 Vol.

6-N4A-6 6-N4B-6 6-N4C-7 l 6-B-5 6-A-7

Boston .

INSERVICE INSPECTION CHECKLIST '

Ed ison 1983/1984 REFUELING OUTAGE Pilgrim Nuclear Company FIRST INSPECTION PERIOD - SECOND TEN YEAR INTERVAL Power Station ,

Unit - 1 ENCLOSURE (A)

System: VARIOUS Page 5 of 10 Rev. O P&ID n Section Sectior No. mW ,

Line or Component and [ XI XI Item of Exam .$ b ' Remarks Description Co-ort $ Categor7 Item Number Description Items 3ethod h{

re h

High Pressure Coolant 243 1 B-J B9.11 Circumferential Pipe Welds 3 Vol. l Injection Welds

[

23-0-7 {

23-0-8 {

23-I-17 l t

Residual Heat Removal Welds 241 1 B-J B9.11 Circumferential Pipe Welds 3 Vol.  !

10-HS-8 b 10-HS-9 l 10-HS-10 l

Reactor Water Cleanup Weld 247 1 B-J B9.11 Circumferential Pipe Welds 1 Vol. l 12-I-6 {

. o Reactor Core Insolation 245 1 B-J 89.11 Circumferential Pipe Welds 3 Vol. 1 Cooling Welds .

13-I-7  !

13-0-3 13-0-4 Core Spray Welds 242 1 B-J B9.ll Circumferential Pipe Welds 4 Vol.

14-A-8 14-A-9 1 14-B-19 j 14-B-20 t

, I

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, c l

l 6

8

Boston INSERVIC"E INSPECTION CHECKLIST Ed ison 1983/1984 REFUELING OUTAGE Pilgrim Nuclear Company FIRST INSPECTION PERIOD - SECOND TEN YEAR INTERVAL [,{*"_ Station ENCLOSURE (A) -

System: VARIOUS Page 6 of 10 Rev. O P&ID o Section S ectior No. WW Line or Component and $' XI XI Item of Eram $ Oa 'R emarks Descr iption Co-orc $ Categor r Item Number Description Items Fiethod h{

n Reactor Recirculation 252 1 B-J B9.40 Socket Weld 2 Surf. Specific welds selected for examination will be identified by BECo

. later. ,

RPV Drain 252 1 B-J B9.40 Socket Weld 2 Surf.

Standby Liquid Control 252 1 B-J B9.40 Sock'et Weld 2 Surf.

  • o 0

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Boston ~ INSERVICE INSPECTION C11ECKLIST

  • Ed icon 1983/1984 REFUELING OUTAGE Pilgrlin Nuclear

! Company FIRST INSPECTION PERIOD - SECOND TEN YEAR INTERVAL Po r Station ENCLOSURE (A)

System: VARIOUS Page 7 of 10 gey, o P&ID n Section S ec tior No. WW Line or Component and $' XI XI Item of Exam .$ b ' Remarks Description Co-orc $ Categor r Item Description ItemsFfethod Number

((

n Reactor Recircula' tion 252 1 B-K-1 B10.10 Piping - Integra,lly Weldec 2 Surf. Specific welds selected Attachment for examination will be

, identified by BECo later.

Main Steam 252 1 B-K-1 B10.10 Pipi.ng - Integrally Weldec 2 Surf.

Attachment Feedwater 252 1 B-K-1 B10.10 Piping - Integrally Weldec 5 Surf.

Attachment Residual lieat Removal 252 1 B-K-1 B10.10 Piping - Integrally tieldec 2 Surf.

Attachment E

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Boston INSERVIC"E INSPECTION CHECKLIST #

Ed ison 1983/1984 REFUELING OUTAGE Pilgrim Nuclear Company FIRST INSPECTION PERIOD - SECOND TEN YEAR INTERVAL Power Station ,

ENCLOSUREUn At )- 1 System: VARIOUS Page 8 or 10 Rev. O P&ID o Section S ec tior No. Mr mi Line or Component and $f XI XI Item of Exam $b ' Remarks Description Co-o rc $ Ca tegor r Item Number Description ItemsHethod h{

n High Pressure Coolant 243 2 C-F C5.ll Circumferential Pipe Weld 2 Vol. Specific welds selected Injection for examination will be identified by BECo later.

High Pressure Coolant 243 2 C-F C5.21 Circumferential Pipe Weld 2 Vol. PRR 6 Injection Residual He'at Removal 241 2 C-F C5.21 Circumferential Pipe Weld 7 Vol. PRR 6 Control Rod Drive 250 2 C-F C5.21 Circumferential Pipe Weld 1 Vol.

O 8

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= . .

Boston INSERVICE INSPECTION CHECKLIST Ed ison 1983/1984 REFUELING OUTAGE Pilgrim Nuclear Company FIRST INSPECTION PERIOD - SECOND TEN YEAR INTERVAL Power Station .

Unit - 1 ENCLOSURE (A)

System: Page 9 10 VARIOUS of Rev. O P&ID o Section S ec tior No. mW Line or Component and 7 XI XI Item of Exam .$ $ Temarks Description Co-orc $ Ca tegor r Item Number Description ItemsFiethod h{

n

_a .

Residual Heat Rem' oval 241 2 C-C C3.40 Piping - Integrally Welde< 6 Surf. Specific welds selected Attachments fo. examination will be ,

, identified by BECo later.

High Pressure Coolant 243 2 C-C C3.40 Piping - Integrally Welde< 2 Surf.

Injection Attachments e

  1. 4 y

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r

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Boston -

INSERVICE INSPECTION CHECKLIST .

Ed ison 1983/1984 REFUELING OUTAGE Pilgrim Nuclear Company FIRST INSPECTION PERIOD - SECOND TEN YEAR INTERVAL P{erStation ENCLOSURE (A)

System: VARIOUS Page 10 of 10 Rev. O P&ID n Section S ectior No. ms us Line or Component and $' XI XI Item of Exam $b 'R emarks Description Co-orc $ Categor r Item Number Description Itema dethod h{

n Component Supports 1 F-A, F(1-3) Component Supports VT 3 Specific supports to be 2 F-B, examined will be 3 F-C Main Steam 1 identified by BECo later. Total number

, Reactor Recirculation 4 requiring examination =

56.

Feedwater 2 Residual Heat Removal 15 Core Spray 4 High Pressure Injection 9

~

Reactor Water Cleanup 1 Service Water 5 Reactor Bldg. Cooling Wate -

9 Containment Atmosphere 1 Control Reactor Core Isolation 2 Cooling

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Boston INSERVICE INSPECTION CHECKLIST Ed ison 1983/1984 REFUELING OUTAGE ilgrim Nuclear .'

Company "

Augmented Inspection to Complete First TEN-Year Unt-Inspection Interval '

Enclosure (B)

System: VARIOUS Page 1 of 1 Rev. O P&ID n S ec t ion S ec tior No. xW Line or Component and 7 XI XI Item of Exam $b Remarks Desc r iption Co-o rc $ Categor. Item Number Description I t ems 'fethod h{

n i

Reactor Vessel 1 B-C Bl.3 Reactor Vessel shell to Vol. Examinations to be con-flange weld from'll6 - ducted in accordance with 120 . the 1974 Edition of Section XI through the Pressure retaining bolting 1 B-G-1 Bl.7 Reactor pressure vessel 2 Vol. Summer '75 Addenda.

closure studs - #46 & #47.

Reactor Pressure vessel 11 Vol.

closure Nuts - #46, 47 48, 49, 50, 51, 52, 53, 54, 55, 56 Valve Body exceeding 1 B-M-2 B12.4 HPCI (2301-4) 1 VT-3 l 4" n.p.s. .

t i  !

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