ML20212A153

Rev 3 to Inservice Insp Program Second 10-Year Interval, ASME XI 1980 Edition W80 Addenda, Re Recirculation Pipe Replacement Project Implemented During 1983-1984 Refueling Outage

ML20212A153
Person / Time
Site:	Pilgrim
Issue date:	09/02/1986
From:	Desmond N, Matthew Green BOSTON EDISON CO.
To:
Shared Package
ML20212A090	List: BECO-86-188, Forwards Rev 3 to Second 10-yr Inservice Insp Program.Rev Necessary Due to Recirculation Pipe Replacement Project Implemented During 1983-1984 Refueling Outage.Program Updated to Reflect Current Plant Configuration ML20212A153
References
NUDOCS 8612220292
Download: ML20212A153 (110)

Text

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l 1, ,I INSERVICE INSPECTION PROGRAM Second Ten-Year Interval AShE XI 1980 Edition W80 Addenda Revision # 3 Prepared By b Reviewed By d k /2SJ / ,d y}X h ..

Approved // w, OQC Group Leader Approved 7

'QAD Manager Date ~Z. l ( b e61 - 292 e6121=

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ADOCK 05000293 PDR DISON .__ _ _ _ _ _ _

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TABLE OF CONTENTS 1.0 GENERAL INFOR;4ATION . . . . . . . . . . . 1-1

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2.0 PROGRAM DESCRIPTION . . . . . . . . . . 2-1 3.0 COMPONENT TABLES . . . . . . . . . . . . 3-1 4.0 RELIEF REQUESTS . . . . . . . . . . . . 4-1 9

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l'.0 GENERAL INFORMATION

1.1 INTRODUCTION

The Inservice Inspection Program for Pilgrim Nuclear Power Station, Unit 1, has been developed in compliance with the rules and-regulations of 10CFR50.55a and Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through add including the Winter 1980 Addenda. Where these rules have been determined to be' impractical, specific requests for relief have been written.

This Inservice Inspection Program for Class 1, 2, and 3 components and component supports is appilcable for the 120 month interval beginning December, 1982. This is the second inspection interval for Pilgrim Nuclear Power Station.

1.2 APPLICABLE CODES The Inservice Inspection Program meets the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, 1980 Edition through and including the Hinter 1980 Addenda.

1.3 INSERVICE INSPECTION BOUNDARIES The Inservice Inspection boundarles identify those systems or portions of systems to which the examination requirements of ASME Section XI apply. These Class 1, 2 and.3 boundarles are documented on Piping and Instrumentation Diagrams (P&ID's), which form part of the Inservice Inspection Program. The system classifications are based on the requirements of 10CFR50.2 (v) for Class I systems and Regulatory Guide 1.26 for Class 2 and 3 systems. The ISI classifications are limited to those systems important to safety that contain water, steam or radioactive materials.

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c 2.0 PROGRAM DESCRIPTION 2.1 The ISI Component Tables are presented in Section 3.0. The components and associated requirements are listed by system. The following information is included in the tables: .

A. Code Category - The Section XI Examination Categories as defined in Table IWB-2500-1, IWC-2500-1, IND-2500-1, and IWF-2500-1 for Class 1, 2, and 3 components.

B. Item Number and Item Description - The Item Number and its description as listed in Tables IWB, IWC, IWO-2500-1, and IWF-2500-2. All Item Numbers and appilcable item descriptions are listed for each Code Category.

C.Section XI Exam Reautred lists the examination method or methods. This reflects the Section XI requirements. The abbreviations used are as follows:

SURF - Surface per IWA-2220 VOL - Volumetric per IWA-2230 VT-1 - Visual per IWA-2211 VT-2 - Visual per IWA-2212 VT-3 - Visual per IWA-2213 VT-4 - Visual per IWA-2214 D. Relief Requests reference a specific relief request contained in Section 4.0. It should be noted that Section 4.0 contains some generic relief requests that are not

. specifically referenced in the tables but apply to the ISI Program in general. Components exempted from examination by Code allowed exemptions are listed below and will not appear in the component tables of this program.

EX-1 -

IWB-1220(a), liquid carrying lines 1.10-inch ID and less (see 2.2). .

EX-2 - IWB-1220(a), steam carrying lines 2.20-inch ID and less (see 2.2).

EX-3 - IWB-1220(c), head connections, 2-inches nominal pipe size (n.p.s.) and less, made inaccessible by CRD penetrations.

EX-4 - IWB-1220(b), lines 1-inch nominal pipe size (n.p.s.) and less.

2-1

EX-5 - IWC-1220(b), components not required to operate above a temperature of 200*F or above a pressure of 275 psig in non-ECCS or RHR systems.

EX-6 - IWC-1220(c), component connections, piping and associated valves, and vessels and their attachments that are 4 in, n.p.s. and smaller.

EX-7 - IWC-1220(a), lines not required during normal operating conditions but remain flooded under static conditions at a minimum of 80% of the pressure they would be subjected to when required to operate.

EX-8 - IWC-1230, piping support members and piping support components encased in concrete.

EX-9 - IWD-1220.1, integral attachments of supports and restraints to components that are 4 in. n.p.s.

and smaller.

EX-10 - IWD-1220.2(a)(b), integral attachments of supports and restraints in systems whose function is not required in support of reactor residual heat removal and emergency core cooling and where operating pressure is 275 psig or less and operating temperatue is 200'F or less.

EX-11 - IWO-5223(e), open ended vent and drain lines from components extending beyond the last shut-off valve and open ended safety or relief valve discharge lines.

2.2 Pursuant to paragraph IWB-1220(a) of ASME Section XI, the maximum size line break that can be made up by the reactor coolant makeup system has been calculated to be 1.1 inches inside diameter for liquid carrying lines and 2.2 inches for steam carrying lines.

2.3 Table 2.1 lists the applicable Class 1, 2 and 3 systems which are covered in the Inservice Inspection Program.

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, , TABLE 2.1 SYSTEMS INCLUDED IN THE ISI PROGRAM System P&ID Number Clags Service Water ISI-M-212 2 &.3 Reactor Building Cooling Water ISI-M-215 3 Containment Atmosphere Control ISI-M-227 2 Residual Heat Removal ISI-M-241 1&2 High Pressure Coolant Injection ISI-M-243, 244 1&2 Core Spray ISI-M-242 1&2 Reactor Core Isolation Cooling ISI-M-245, 246 1&2 Reactor Water Cleanup ISI-M-247 1 Standby Liquid Control ISI-M-249 1&2 Control Rod Drive Hydraulic ISI-M-250 2 Reator Vessel ISI-M-252, 253 1 Main Steam ISI-M-252, 253 1 Recirc ISI-M-252, 253 1 Feedwater ISI-M-252, 253 1 s

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. . r SECTION 3.0 INSERVICE INSPECTION COMPONENT TABLES FOR PILGRIM NUCLEAR POWER STATION O

e 3-1

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nutlear Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION M80 ADDENDA Unit - 1

- ~

System: ' REACTOR PRE 550RE VESSEL Page 1 of 4 Rev. 3 Section P&ID Section XI No.

line or Component and XI Item Item of Exam Relief

. Description Co-ord. Class Category Number Description Items Method Request Remarks Psessure retalning welds 1 B-A Bl.11 Circumferential Welds in i Vol. PRR 51 accessible in the reactor vessel belt ilne region 4 1 B-A Bl.12 Longitudinal Welds in 6 Vol. PRR 101 accessible ,

belt line region 4 i B-A Bl.21 Circumferential Head Welds (a.) top head i Vol.

(b.) bottom head 2 Vol. PRR (1) weld '

5 inaccessible I b-A Bl.22 Meridonial Head Welds Vol.

(a.) top head 8 Vol. .

(b.) bottom head 14 Vol. PRR (6) Inaccessible 5 bottom head welds 1 B-A Bl.30 Shell-to-flange 1 Vol.

I B-A Bl.40 Head-to-flange i Vol.

I B-A Bl.50 Repair Weld 1 None Repair area not located in belt line region (GG) tull Penetr& tion We4ds 1 B-D B3.90 Primary Nozzle to Vessel 28 Vol. PRR . .

of Nozzles in Vessels Welds 9 1 B-D B3.100 Nozzle Inside Radius 28 Vol.

Section

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) tuss ton INSERVICE INSPECTION PROGRAM Pilgrim Nuclear-4 Edison SECOND TEN-YEAR INTERVAL Power Station 3

Ccepany ASME XI 1980 EDITION W80 ADDENDA Unit - 1 1

i

~ ~ ~ ~ ~ ~ ~ -

System: REACTOR PkESSUifE VE'SSEL Pige 2 o'f 4 Rev. 3

Section j P&ID Section XI No.

l tine or Component and XI Item Item of Esem Relief Description Co-ord. Class Categog Number Description Items,_ Method _ Request Remarks a Partial Penetration 1 B-E B4.11 Nozzles 6 V T --2 Nil, N14, N15A,N158 l Helds in Vessels N16A, N168

1 B-E B4.12 Control Drive Nozzles 145 VI-2 Note

Inspection conducted in accordance with INA-5000 1 B-E B4.13 Instrumentation Nozzles 42 VT-2 30 LPRMs 8 IRMs

! P essure Retaining 4 SRMs l Dissimilar Metal Welds ,

I l (a) Recirculation 252 1 B-F B5.10 Nozzle-to-Safe-End-Welds 12 Vol. 2R-NIA-1, 2R-N18-1 i & 2R-N2A-1 thru ,

i Surf. 2R-N2K-1 j eb) Core Spray 242 1 .B-F B5.10 Nozzle-to-Safe-End-Welds 2 14-A-1, 14-B-1

tr> CRD Return 252 1 B-F B5.10 Nozzle-to-Safe-End-Welds 1 3-I-I (d) JET Pump Instrument. 252 1 B-F B5.10 Nozzle-to-Safe-End-Welds 2 N9A-1, N98-1 (e) Main Steam (1) 252 1 B-F B5.10 Nozzle-to-Safe-End-Welds 4 1-A-1 thru l-D-1

(f) Feedwater (1) 252 I B-F B5.10 Nozzle-to-Safe-End-Welds 4 6-N4A-1 thru 6-N4D-1 (g) Vessel Head Vent 252 I B-F B5.10 Nozzle-to-Safe-End-Welds 1 N8-1 (h) Vessel Head Spray 252 i B-F B5.10 Nozzle-to-Safe-End-Welds 1 N7A-1 (i) Vessel Head Instr. 252 1 B-F B5.10 Nozzle-to-Safe-End-Welds 1 N78-1 Q) Rs Water Level Instr 253 I B-F B5.11 Nozzle-to-Safe-End-Welds 2 Surf. N16A-1 N168-1 O ) SBtC & Core dP. -

253 i B-F B5.11 Nozzle-to-Safe-End-Welds 1 N14 t1) These are not dissiellar metal welds, but for identification and inspection requirements will be classified as safe end welds. .

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Boston INSERVICE INSPECTION PROGRAM Pligria Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980_ EDITION M80 ADDENDA Unit - 1 System- REACTOR PRESSURE VESSEL Page 3 of 4 Rev. 3 Section '

P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description _

C_o_-o A Class Category Number Description Items Method Request Remarks P' essure retalning 253 1 8-J 89.21 Circ Helds NPS < 4" 1 Surf N168-2 welds in piping 253 1 B-J 89.40 Socket Nelds 2 Surf N16A-2 N168-3 P essure Retalning 252 1 B-G-1 B6.10 Closure Head Nuts 56 Surf.

Bolting Larger Than 2" Dicmeter 1 B-G-1 B6.20 Closure Studs In Place 52 Vol.

1 B-G-1 B6.30 Closure Studs, When 4 Vol. 41, 42, 43 & 44 '

Removed & Surf.

1 B-G-1 B6.40 Threads in Flange 56 Vol.

1 B-G-1 86.50 Closure Washers, 56ea. Visual VT-1 P essure Retalning 1 B-G-2 B7.50 Bolting of Piping 3 Visual Flanged head Bolting 2" dias. VT-1 piping dnd smaller Integral Attachments 252 1 B-H B8.10 Vessel Skirt Neld 1 Vol. -

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1 B-H 88.10 Head Lifting Lugs 4 Surface Not a code required exam.

I B-H B8.10 Stabilizer Support 4 Surface Verify access Lugs for examination

hoston INSERVICE-INSPECTION PROGRAM Pilgria Nuclear-Edtson SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION M80 ADDENDA Unit - 1

?.

-- System: REACTOR PRESSURE VESSEL Page 4 of 4 Rev. 3 .*,

Secti:w ' ..

P&ID Seetion X!a t No. 7 "

tiae or Component and XI Item Item of ExacM Relief - ^

Description Cg-ord., Class Category NuM,er ' Description Items Mett.ad' Request'% --

Remarks

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Interior of Reactor 1 B-N-1 B.13.10 Interior of Reactor i Visual , Accessible' area.

Ve:tel Vessel -

VT-3 'f 4

Reactor Vessel 1 B-N-2 B13.20 Integrally welded Visual , , , , .

Interior Attachmests VI- I

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interior attachments to . ' -

2 1 Reactor Wessel Integrally welded Reactor Vessel 1 B-N-2 B13.21 Visual

( Core Support Core Su, port Structures VT-1 s to Reactor Vessel

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P essure Retalning Welds 1 B-O B14.10 107. Peripheral CRD 36 -_s Vol.

sp Contrdi Rod Housings Housings '

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Boston INSERVICE INSPECTION PROGRAM '

Pilgrim Nuclear

, Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 Sys[emj[fRjyjU5f'TisilNG Page 1 of 1 Rev. 3 ,

Section P&ID Section XI -

No.

t.ine or Component and XI Item Item of Exam Relief Description _ _

Co-ord. Class Category Number Description Items Method Request Remarks

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All Pressure Retaining 1 B-P B15.10 Reactor Vessel System Visual System Leakage.

Components - Class I Leakage Test VT-2 Test Each Refueling Outage.

RHR CS 1 B-P B15.11 Reactor Vessel Hydrosta- Visual One per Interval ,. '

FW tic Test VT-2 MS RECIRC 1 B-P B15.50 Piping - Leakage Test Visual System Leakage RNCU VT-2 Test Each SBLC Refueling Out-RCIC age.

HPCI RPV 1 B-P B15.51 Piping - Hydrostatic Visual Once per Interval CRD Iest VT-2 1 B-P B15.60 Pumps - Leakage Test Visual System Leakage VT-2 Test-Each Refueling Out-age.

1 B-P B15.61 Pumps - Hydrostatic Visual Once per Interval Test VT-2 1 B-P B15.70 Valves - Leakage Test Visual -

System Leakage VT-2 Test Each Refueling Out-age 1 B-P B15.71 Valves - Hydrostatic Test Visual Once per Interval VT-2 l

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 Syi~t'em: MAIN STEAM Page 1 of 6 Rev. 3 Section P&ID Section XI- No.

Line or Component and XI Item Item of Exam Relief Descrigtion Co-ord. Class Category Number Description Items Method Request Remarks Line "A" 252 1 B-G-2 B7.70 Valves-Bolts studs, nuts 4 Visual (2) MSIV's 2" diameter and less VT-1 (1) Relief Valve (1) Safety Valve 1 B-J 89.11 Piping n.p.s. 1 4" 19 Surf. PRR Inaccessible weld Circumferential welds & Vol. 1 penetration X-7A a

1 B-J 89.31 Piping n.p.s. 1 4" 2 Surf. (2) Weldolet branch connection weld & Vol.

I B-K-1 B10.10 Piping - Integrally 4 Surf. PRR (8) Inaccessible welded attachments 1 Lugs in Penetration X-7A.

I B-M-2 B12.40 Valve body > 4" n.p.s. 4 Visual PRR (2) MSIV's VT-3 3 (1) Relief Valve (1) Safety Valve 1 Group Circumferential pipe 3 Vol. 1-A-7 I welds inspected in each 1-A-8 Welds ten year interval 1-A-9 1 B-F B5.10 Piping n.p.s. > 4" 1 .See System RPV

. Nozzle to safe end weld Held 1-A-1 i

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Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit -1 fystem: MAIN STEAM Page 2 of 6 Rev. 3 Section P&ID Section XI No.

line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Naiber Description Items Method Request Remarks Iine "B" 252 1 B-G-2 B7.70 Valves-Bolts 3 Visual (2) MSIV's studs, nuts VT-1 (1) Relief Valve 2" diam. and less 1 B-J 89.11 Piping n.p.s. 1 4" 17 Surf. PRR Inaccessible weld Circumferential welds & Vol. I penetration X-78 1 B-J B9.31 Piping n.p.s. 1 4" 1 Surf. Relief Line branch connection welds & Vol.

I B-K-1 B10.10 Piping - integrally welded 5 Surf, PRR (8) Inaccessible attachments I lugs in penetra-tion X-78 1 B-M-2 12.40 Valve body > 4" n.p.s. 3 VT-3 PRR (2) MSIV's 3 (1) Relief Valve 1 Group Circumferential pipe welds 2 Vol. 1-B-8 i I inspected in each ten year 1-B-9 Welds interval 1 B-F B5.10 Piping n.p.s. > 4" See System RPV

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nozzle to safe-end weld -

Held 1-B-1 l

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7 Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 System: MAIN STEAM Page 3 of 6 Rev. 3 Section P&ID Section XI No.

1.ine or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks Line "L- 252 I B-G-2 B7.70 Valves-Bolts, 3 Visual (2) MSIV's studs, nuts < VT-1 (1) Safety Valve 2" diameter 1 B-J 89.11 Piping n.p.s. 1 4" 17 Surf. PRR Inaccessible weld Circumferential welds & Vol. 1 in penetration X-7C 1 B-J 89.31 Piping n.p.s. 1 4" 1 Surf. Relief branch connection welds & Vol. Line 1 B-J 89.32 Piping n.p.s. < 4" 1 Surf. RCIC Out branch connection welds I half coupling 1 B-K-1 B10.10 Piping - integrally welded 4 Surf. PRR (8) Inaccessible attachments I lugs in penetra-tion X-7C 1 B-M-2 B12.40 Valve body n.p.s. > 4" 3 Visual PRR (2) MSIV's VT-3 3 (1) Safety Valve i B-F B5.10 Piping n.p.s. > 4" 1 See system RPV

, nozzle to safe-end weld . weld 1-C-1

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station

Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 Sys' tem: MAIN STEAM Page 4 of 6 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks 3 Line "C" 1 Group Circumferential welds 2 Vol. 1-C-8 I Welds inspected in each ten 1-C-9 year interval Iine "D" 252 1 B-G-2 B7.70 Valves-Bolts, 4 Visual (2) MSIV's studs, nuts < VT-1 (2) Relief Valves.

2" diameter 1 B-J B9.11 Piping n.p.s. > 4" 19 Surf. PRR Inaccessible weld Circumferential welds & Vol. I penetration X-7D 1 B-J 89.31 Piping n.p.s. > 4" 3 Surf. Relief Valve (s)

Branch connection welds & Vol. HPCI Line 1 B-K-1 B10.10 Piping - Integrally 4 Surf. PRR (8) Inaccessible welded attachments 1 in penetration X-70 1 B-F B5.10 Piping n.p.s. > 4" 1 See System RPV Nozzle to safe-end weld Held 1-D-1 t

INSERVICE INSPECTION PROGRAM Pilgrim Nuclear SECOND TEN-YEAR INTERVAL Power Station ASME XI 1980 EDITION H80 ADDENDA Unit - 1

~

System: MAIN STEAM Page 5 of 6 Rev. 3 Section P&ID Section XI No.

Iine or Component and XI Item Item of Exam Relief

_ Description Co-ord. Class Category Number Description Items Method Request Remarks Line "D" (Cont.) 1 B-M-2 812.40 Valve body > 4" n.p.s. 4 Visual PRR (2) MSIV's VT-3 3 (2) Relief Valves 1 Group Circumferential welds 3 Vol. 1-D-7 I inspected in each ten 1-0-8 Helds year interval 1-D-9 3" Drain Manifold 252 i B-F B5.51 Piping n.p.s < 4" 1 Surf. 1-SD-10 Dissimilar metal butt welds 1 B-J B9.21 Piping n.p.s. < 4" 5 Surf. PRR (1) Inaccessible Circumferential welds I weld in X-8 1 B-K-1 B10.10 Piping - integrally 1 Surf. PRR (8) Inaccessible welded attachments I lugs in penetra-tion X-8 Main Steam Line A 1 F-C F(1-4) Spring Hangers 4 VT-3 &4 1 F-C F(1-4) Snubbers 3 VT-3 &4 1 F-C F(1-3) Rigid Support 1 VT-3 1 F-B F(1-3) Anchor 1 VT-3 X-7A Moin Steam Line B 1 F-C F(1 ~4) Spring Hangers 3 VT-3&4 1 F-C F(1-4) Snubbers 3 VT-3&4 1 F-C F(1-3) Rigid Support i VT-3 1 F-B F(1-3) Anchor ,

i VT-3 X-78

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclea~r Edison SECOND TEN-YEAR INTERVAL Pcwer Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 1

System: MAIN STEAM Page 6 of 6 Rev. 3 Section ,

P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief

_ Description Co-ord. Class Category Number Description Items Method Request Remarks Main Steam Line C 1 F-C F(1-4) Spring Hangers 3 VT-3&4 I F-C F(1-4) Snubbers 3 VT-3&4 1 F-C F(1-3) Rigid Support i VT-3 1 F-B F(1-3) Anchor 1 VT-3 X-7C i

Main Steam Line D 1 F-C F(1-4) Spring Hangers 4 VT-3&4 1 F-C F(I-4) Snubbers 3 VT-3&4 1 F-C F(1-3) Rigid Suport i VT-3 1 F-B f(1-3) Anchor 1 VT-3 X-7D i

Steam Drain Line 1 F-B F(1-3) Anchor 1 VT-3 X-8

@ 9 9 9

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear .

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 System: RECIRC Page 1 of 5 Rev. 3 Section ,

P&ID Section XI No.

tine or Component and XI Item Item of Exam Relief Description Co-ord. Class Ca tego_ry. Number Description Items Method Request Remarks Recirc Loop "A" 252 I B-G-1 B6.180 Pumps-Bolts and studs 1 Vol. 16 Cap Screws 2", 12", 22", and >2" Dia 28" Pipe 252 1 B-G-1 B6.190 Pumps-Flange Surface 2 Visual When connection VT-1 is disassembled 252 1 B-G-1 B6.200 Pumps-Nuts, Bushings, 1 Visual Disassembly not and Hashers >2" Dia. VT-1 required. Acces-sible areas only 252 1 B-G-2 87.50 Piping-Bolts, Studs, 2 Visual Decontamination and Nuts 12" Dia. VT-1 Connections 252 1 B-G-2 Bl.70 Valves-Bolts, Studs, 2 VI.ual MO-4A and Nuts 1 2" Dia VI-1 MO-5A 252 1 B-J 89.11 Circumferential Helds 28 Surf. All nozzle-to-NPS > 4" & Vol. safe-end welds are listed in RPV system.

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Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear .

! Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME_XI 1980_ EDITION H80 ADDENDA Unit - 1 System: RECIRC __

Page 2 of 5 Rev. 3

_ _ _ _ _ _ _ . _ _Section PLID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method . Request Remarks Recirc Loop "A" 252 1 B-J 89.31 Branch Pipe Connections 2 Surf. 2R-N18-9BC-1 (Continued) NPS > 4" & Vol. -

2R-BPA-1 252 I B-J B9.32 Branch Pipe Connections 1 Surf. 2R-N18-9BC-2 NPS < 4" 2" Drain to C.R.H.

252 1 B-J 89.40 Socket Helds 2 Surf. 2" Drain to C.R.H.

252 1 B-K-1 B10.10 Piping-Integrally 2 Surf. 14HL2(4)

Helded attachments SHLl(4) 252 1 B-K-1 B10.20 Pumps-Integrally 3 Surf.

Helded attachments 252 1 B-L-2 B12.20 Pump Casing 1 Visual PRR VT-3 2 252 1 B-H-2 B12.40 Valves - NPS > 4" 2 -Visual PRR MO-4A VT 3 MO-5A I

s 1 Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear .

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H2O ADDENDA Unit - 1 System: RECIRC Page 3 of 5 Rev. 3

___Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Nu_mber Description Items Method Request Remarks Recirc Loop "A" 252 1 F-C F(1-4) Spring Hangers

~

9 Visual (Continued) VT-3&4 252 1 F-C F(1-4) Snubbers 12 Visual VT 3&4 252 1 F-C F(1-3) Guide 1 Visual on 2" drain VT-3 to C.R.H.

RECIRC Loop "B" 252 i B-G-1 B6.180 Pumps-Bolts and 1 Vol. 16 Cap Screws 2", 12", 22" & 28" Pipe Studs > 2" Dia 252 I B-G-1 B6.190 Pumps-Flange Surface 2 Visual When connection VT-1 is disassembled 252 1 B-G-1 B6.200 Pumps-Bolts, Studs, 2 Visual Disassembly not and washers > 2" dia. VT-1 required, Acces-sible areas only.

252 1 B-G-2 B7.50 Piping-Bolts, Studs, 2 Visual Decontamination and Nuts <2" Dia. VT-1 Connections 252 1 B-G-2 B7.70 Valves-Bolts, Studs 2 Visual MO-48

- - and Nuts < 2" Dia. VT-1 . M0-58

l Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear .

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 System: RECIRC Page 4 of 5 Rev. 3 Section PLID Section XI No.

Line or Component and XI ~

Item Item of Exam Relief

_ Description Co-ord. Class Category Number Description Items Method Request Remarks Recirc Loop "B" 252 1 B-J B9.11 Circumferential Welds 28 Surf. All nozzle-to-N.P.S. > 4" & Vol. safe end welds are listed in RPV System 252 I B-J B9.31 Branch Pipe Connections 2 Surf. 2R-NIA-7BC-1 NPS > 4" & Vol. 2R-BP-1A 252 1 B-J B9.32 Branch Pipe Connection 1 Surf 2R-NIA-7BC-2 NPS 1 4" l 252 1 B-J B9.40 Socket Welds 2 Surf 2" drain to C.R.W.

252 1 B-K-1 B10.10 Piping-Integrally 2 Surf 12HL2(4)

Welded Attachments 4HLl(4) 252 1 B-K-1 B10.20 Pumps-Integrally 3 Surf Welded Attachments 252 1 B-L-2 B12.20 Pump Casing 1 Visual PRR VT-3 2 252 I B-M-2 B12.40 Valves - NPS > 4" 2 Visual PRR M0-48 VT-3 3 MO-5B i

o .

Boston INSERVICE INSPECTION ?ROGRAM Pilgrim Nuclear -

Edison SECOND TEN-YEAR I*fiERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System: RECIRC _

Page 5 of 5 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief

, Description Co-ord. Class Category Number Description Items Method Request Remarks Recirc Loop B 252 1 F-C F(1-4) Spring Hangers 9 Visual VT-3&4 252 1 F-C F(1-4) Snubbers 12 Visual VT-3&4 252 1 F-C F(1-3) Guide 1 Visual on 2" Drain

! VT-3 to CRW

@ . O g

o .

O Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System: CONTROL ROD DRIVE Page 1 of 2 Rev. 3 Section P&ID Section XI No.

, Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks flydraulic Return 250 1 B-J B9.21 Piping r.p.s. < 4" 1 Surf. Nozzle N10 to (Cut & Capped in 1980) Circumferential Helds Cap Held in RPV System 6" Scram Discharge 250 2 C-F C5.11 Circumferential Butt 21 Surf.

Ileader - West Held.N.H.T.< .5" 250 2 F-C F(1-3) Restraints 2 Visual VT-3 250 2 F-B F(1-3) Guides 4 Visual VT-3 250 2 F-C F(1-3) Rigid Support 10 Visual VT-3 250 2 F-B F(1-3) Anchors 2 Visual VT-3 J

j 250 2 F-C F(1-4) Spring Hanger 1 Visual VT-3 & 4 i

i 12" Scram Discharge- 250 2 C-F C5.21 Circumferential Helds 2 Surf.& . .

Volume - West '

NHT > .5" Vol.

7 Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station.

Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System: CONTROL ROD DRIVE Page 2 of 2 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief

_ Description Co-ord. Class Category Number Description Items Method Request Remarks 6" Scram Discharge 250 2 C-F C5.11 Circumferential Butt 25 Surf Header-East Welds N.H.T.< .5" 250 2 F-C F(1-3) Restraint I Visual VT-3 250 2 F-8 F(1-3) Guides 5 Visual VT-3 250 2 F-C F(1-3) Rigid Support 7 Visual VT-3 250 2 F-B F(1-3) Anchor 2 Visual VT-3 12" Scram Discharge 250 2 C-F C5.21 Circumferential Butt 2 Surf Volume East Helds > .5" Piessure Retaining 250 2 C-H C7.20 System Leakage Test Visual Components-Piping VT-2 250 2 C-H - C7.21 System Hydro Test Visual VT-2 Piessure Retalning 250 2 C-H C7.3d System Leakage Test Visual Components-Valves VT-2 250 2 C-H C7.31 System Hydro Test Visual VT-2

o .

Boston INSERVICE INSPECTION PROGRAM Pilgrim NucFear.

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System: FEEDWATER Page 1 of 3 Rev. 3 Section PLID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks Loop "A" 12" Diameter 252 1 B-J B9.11 Piping n.p.s. 2 4" 21 Vol.& 6-N4(A-D)-1 Welds Piping Circumferential Welds Surf. in System RPV B-K-1 B10.10 Piping - Integrally 3 Surf. 6-N4A-5HLl(4) .

welded attachments 6-N4A-9HLl(8) j 6-N4B-5HLl(4)

Loop "A" 18" Diameter 252 i B-G-2 B7.70 Valves - Bolts, studs, 3 Visual 6-57A, 6-58A, Piping nuts 1 2" diameter VT-1 6-62A 1 B-J B9.11 Piping n.p.s. 1 4" 15 Vol.& PRR Inaccessible weld Circumferential Welds Surf. 1 in penetration X-9A 1 B-J 89.31 Piping n.p.s. 1 4" Branch 1 Vol.& RWCU Inlet connection welds Surf.

1 1 B-K-1 B10.10 Piping - Integrally 3 Surf. PRR (8) Inaccessible welded attachments I lugs in penetra-tion X-9A.

6-A-4HLI(8) 6-A-6HLl(4)

I B-M-2 B12.40 Valve Body n.p.s > 4" 3 VT-3 PRR . 6-57A, 6-58A, 3 6-62A 4

1

O Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear -

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 Sy'~

s fem: FEEDWATER Page 2 of 3 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief l Description Co-ord. Class Category Number Description Items Method Request Remarks Loop "A" 12 & 18" 252 1 Group Circumferential welds 9 Vol. 6-N4A-7 6-N4A-12 l Diameter Piping I inspected in each ten 6-N4A-9 6-N4A-13 Helds year interval 6-N4A-10 6-N4B-8 6-N4A-11 6-N48-7 6-N4A-8 loop "B" 12" Diameter 252 1 B-J 89.11 Piping n.p.s. 1 4" 25 Vol.L Piping Circumferential Welds Surf.

1 B-K-1 810.10 Piping integrally 4 Surf. 6-N4D-5HLl(4) welded attachments 6-N4C-7HLl(4) 6-N4D-13HLl(8) 6-N4D-9HLl(8)

Loop "B" 18" Diameter 252 1 B-G-2 B7.70 Valves - Bolts, studs, 3 Visual 6-57B, 6-588, Piping nuts 1 2" diameter VT-1 6-62B 1 B-J B9.11 Piping n.p.s. 2 4" 16 Vol.& PRR Inaccessible weld Circumferential Welds Surf. 1 in penetration X-9B 1 B-K-1 B10.10 Piping - integrally welded 2 Surf. PRR 6-B-3HLl(4) attachments 1 (8) Inaccessible

. lugs in penetration X-9B 1 B-M-2 B12.40 Valve Body n.p.s. > 4" 3 Visual PRR 6-578, 6-588, VT-3 3 6-628

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear ~

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 System: FEEDHATER Page 3 of 3 Rev. 3 Section P&ID Section XI No.

1' Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks Loop "B" 18" Diameter 252 1 Group Circumferential welds 9 Vol. 6-N4C-8 6-N4D-12

Piping (Cont.) I Helds inspected in each ten 6-N4C-9 6-N4D-13 I year interval 6-N4D-8 6-N4D-14 i 6-N40-10 6-N4D-9 6-N4D-11 Loop "A" 252 1 F-C F(1-4) Spring Hangers 7 VT-3 VT-4

F-C F(1-4) Snubbers 5 VT-3 VT-4 F-C F(1-3) Rigid Hanger 2 VT-3 F-B F(1-3) Anchor i VT-3 X-9A toop "B" 252 1 F-C F(1-4) Spring Hangers 7 VT-3 VT-4 F-C F(1-4) Snubbers 5 VT-3 VT-4 F-C f(1-3) Rigid Hanger 2 VT-3 F-B F(1-3) Anchor i VT-3 X-98

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear -

Edison SECOND TEN-YEAR INTERVAL Power Station '

Company ASME XI 1980 EDITION W80 ADDENDA Unit - l'

' System: RESIDUAL HEAT REMOVAL (RHR) Page 1 of 24 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks RHR (in) - LPCI - Loop 241 1 B-G-2 B7.70 Valves-bolts, studs, 3 Visual 1001-33A "A" from MO 1001-29A to nuts < 2" VT-1 1001-68A 28" Recirc. Disch. Loop 1001-29A "A"

1 B-J 89.11 Piping n.p.s > 4" 16 Surf.& PRR Inaccessible weld Circumferential welds Vol. I in penetration X-51A 1 B-K-1 B10.10 Piping - Integrally 3 Surf. PRR 10R-IA-8HLl(4) welded attachments 1 10R-IA-8HL2(4)

(8) Inaccessible lugs in X-51A 1 Group Circumferential Welds 1 Vol. 10R-IA-5 I Inspected in each 10 Yr Welds Interval

• 1 B-H-2 812.40 Valve Body n.p.s. > 4" 3 Visual PRR 1001-33A VT-3 3 1001-68A 1001-29A 1 F-C F(1-4) Spring Hangers 3 Visual -

VT-3&4 1 F-C F(1-4) Snubbers 2 Visual

. VT-3&4 1 F-B F(1-3) Anchor 1 Visual X-51A VT-3

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear -

~

Edison SECOND TEN-YEAR INTERVAL Power Station Co:pany ASME XI 1980 EDITION W80 ADDENDA Unit - 1

System

RESIDUAL HEAT REMOVAL (RHR) Page 2 of 24 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category _flumber Description Itgms _Mgthod_ Request Remarks RHR (in) - LPCI - Loop 241 1 8-G-2 B7.70 Valve-bolts, studs, nuts Visual 1001-338 "B" from MO 1001-29B to ~< 2" diameter Vl-1 1001-68B 28" Main Recirc. Disch 1001-29B Loop "B" 241 1 B-J 89.11 Piping n.p.s.) 4" 16 Vol.& PRR Inaccessible weld Circumferential welds Surf. I in penetration X-51B 1 B-K-1 B10.10 Piping-Integrally 3 Surf PRR 10R-IB-8HLl(4) welded attachments 1 10R-IB-8HL2(4)

(8) Inaccessbible lugs in X-518 1 Group Circumferential welds 1 Vol 10R-IB-5 I Inspected in each 10 year Welds Interval 1 B-M-2 B12.40 Valve body n.p.s. > 4" 3 Visual PRR 1001-338 VT-3 3 1001-68B 1001-29B 1 F-C F(1-4) Spring Hangers 3 Visual VT-3&4 1 F-C F(1-4) Snubbers 2 Visual VT-3&4 1 F-B F(1-3) Anchor 1 Visual X-518 VT-3 4" Head Spray from 241 1 B-F B5.50 Piping n.p.s. > 4" l Vol.& 10-HS-23 Nozzle Flange to Dissimilar rnetal butt Surf MO-1001-60 welds

c' Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear .

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 i Syste_m: RESIDUAL HEAT REMOVAL (RHR) Page 3 of 24 Rev. 3

___Section P&ID Section XI No.

j Line or Component and XI Item Item of Exam Relief j . Description Co-ord. Class Category Number Description Items Method Request Remarks i

i 4" head spray from 241 1 B-G-2 B7.50 Piping-bolts, studs, 2 Visual nozzle flange to nuts i 2" diameter VT-1 4 M01001-60 (Continued) j

~

ISI-I-10-5A 241 1 B-G-2 B7.70 Valves-bolts, studs, 3 Visual 1001-60 nuts 1 2" diameter VT-1 1001-63 1001-64 241 1 B-J 89.11 Piping n.p.s. > 4" 32 Vol.& PRR Inaccessible weld Circumferential welds Surf. 1 in penetration X-17 1

241 1 B-K-1 B10.10 Piping-Integrally welded 1 Surf. PRR (8) Inaccessible attachments I lugs in X-17 241 1 F-C F(1-3) Restraint i Visual VT-3 241 1 F-C F(1-3) Rigid Support 1 Visual VT-3 241 1 F-C F(1-4) Spring Hanger 3 Visual VT-3&4 241 1 F-C F(1-4) Snubbers 2 Visual . .

VT-3&4 241 1 F-B F(1-3) Guide 1 Visual VT-3 241 1 F-C F(I-3) Anchor 1 Visual X-17 VT-3

. o .

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear -

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 Sy[lem: RESIDUAL HEAT REMOVAL (RHR) Page 4 of 24 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Methgd. Request Remarks RilR "OUT" from 28" 241 1 B-F B5.50 Piping n.p.s. > 4" 1 Vol.& 10R-0-14 Recirc. Piping Dissimilar metal butt Surf to M0-1001-47 welds ISI-I-10-IA 241 1 B-G-2 B7.70 Valve bolts, studs, nuts 3 Visual 1001-51

< 2" diameter VT-1 1001-50 1001-47 241 1 B-J 89.11 Piping n.p.s. > 4" 24 Vol.& PRR Inaccessible weld Circumferential welds Surf. 1 in penetration X-12 241 1 B-J 89.31 Piping n.p.s. > 4" 1 Vol.& RWCU Tie-In Branch Connection Helds Surf. 12R-0-1 241 1 Group Circumferential Helds 4 Vol. 10R-0-6, 10R-0-7

, I Inspected in each 10 Year 10R-0-8, 10R-0-9 l Helds Interval j 241 1 B-K-1 B10.10 Piping - Integrally welded 4 Surf. PRR 5HLl(2) attachments 25HLl(4) 1

. . . 10HLl(8)

(8) Inaccessible Lugs in X-12 l 241 1 B-M-2 B12.40 Valve body n.p.s. > 4" 3 Visual PRR 1001-47

VT-3 3 1001-50 1001-51 241 1 F-C F(1-4) Spring Hangers 3 Visual VT-3&4

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear -

Edison SECOND TEN-YEAR INTERVAL  : Power Station Company ASME XI 1980 EDITION H80 ADDENDA Unit 1

~ System: RESIDUAL HEAT REMOVAL (RHR) Page 5 of 24 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Descrigtion Co-ord. Class Category Number Description Items Method Request Remarks RHR "OUT" from 28" 1 F-C F(1-4) Snubbers 4 Visual Main Recirc. Suction VT-3&4 Loop "A" to M0-1001-47 (cont'd). 1 F-B F(1-3) Rigid Support i Visual VT-3 I F-B F(1-3) Anchor i Visual X-12 VT-3 18 Suction Piping from 241 2 C-F C5.11 Circumferential .

24 Surf.

lorus nozzle X-222A Helds N.H.T. 1 5" to pump 203A casing (Includes piping dwnstrm 241 2 F-C f(1-3) Restraint 3 Visual of MO-43A) VT-3 241 2 F-B F(1-3) Rigid Support 5 Visual VT-3 241 2 F-B F(1-4) Spring Support 1 Visual VT3&4 18 Suction Piping from 241 2 C-F C5.11 Circumferential 19 Surf torus nozzle +X-222D to Helds N.W.T. 1 5" . .

Pump 203B Casing (includes piping dwnstrm 241 2 F-C F(1-3) Restraint 3 Visual of MO-43B) VT-3 241 2 F-B F(1-3) Rigid Support 3 Visual VT-3

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear -

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1

~ ~

Syslem[" RESIDUAL HEXT REMOVAL (RHR) Page 6 of 24 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Categor'y Number Description Items Method Request Remarks 18 Suction Piping from 241 2 F-8 F(1-4) Spring Support i Visual torus nozzle X-222D to VT-3&4 Pump 2038 Casing (includes piping dwnstrm 241 2 C-C C3.40 Integral Attachments 1 Surf 140 HLl(4) of M0-438)(Cont.)

18" Suction Piping from 241 2 C-F C5.ll Circumferential 19 Surf torus nozzle X-2228 to Welds NWT <.5" Pump 203C casing

, (includes piping dwnstrm 241 2 F-C F(1-3) Restraint 3 Visual of MO-43C) VT-3 241 2 F-8 F(1-3) Rigid Support 3 Visual VT-3 241 2 F-8 (1-4) Spring Support i Visual Vl-3&4 241 2 C-C C3.40 Integral 1 Surf 188HLl(8)

Attachments

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear .

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI_1980_ EDITION H80 ADDENDA Unit - 1 Syi{em: RESIDUAL HEAT REMOVAL (RHR) Page 7 of 24 Rev. 3 Section P&ID Section XI No.

line or Component and XI Item Item of Exam Relief

.._ Description Co-ord. Class Category Number Description Items Method Request Remarks 18" Suction Piping from 241 2 C-F C5.11 Circumferential 24 Surf Torus nozzle X-222C to Helds NHT 1 5" pump 203D casing (includes piping dwnstrm 241 2 F-C F(1-3) Restraint 3 Visual of MO-43D) 241 2 F-C F(1-3) Rigid Support 5 Visual VT-3 241 2 F-B F(1-3) Spring Support 1 Visual VT-3&4 12" Piping on discharge 241 2 C-F C5.11 Circumferential 12 Surf of Pump 203A welds NHT 1 5" 241 2 F-C F(1-3) Restraint i Visual VT-3 241 2 F-B F(1-4) Spring Support 1 Visual VT-3&4 12" Piping on discharge 241 2 C-F C5.11 Circumferential 12 Surf of Pump P2030 .

Helds NHT 1 5" .. .

241 2 C-C C3.40 Integral 1 Surf GB10-229HLI(8)

Attachments ,

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear .

~

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 System: RESIDUAL HEAT REMOVAL (RHR) Page 8 of 24 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Catego_ry Number Description Items Method Request Remarks 12" Piping on discharge 241 2 F-B F(I-4) Spring Support i Visual of Pump P203C (Cont) VT-3&4 241 2 F-B F(I-3) Restraint 1 Visual 16" Piping on inlet 241 2 C-F C5.II Circumferential 11 Surf to H.X."A" (E- 207A) Welds N.W.T.1 5" 241 2 F-C F(1-4) Spring Hangers 2 Visual VT-3&4 241 2 F-C F(I-4) Hydraulic Snubber i V) ual VT-3&4 18" Piping on Inlet 241 2 C-F C5.ll Circumferential 2 Surf to HX "A" (E-207A) Welds 1 5" 2 C-F C5.31 Branch Connection i Surf 2 F-C F(1-3) Rigid Support i Visual VT-3 16" Discharge Piping 241 2 C-f C5. II' Circumferential 5 Surf from H.X. "A" (E-207A) Welds N.W.T. 1 5"

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear -

~

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 Syi}em: RESIDUAL HEAT REMOVAL (RHR) Page 9 of 24 Rev. 3 Section P&ID Section XI No, line or Component and XI Item Item of Exam Relief

_ Description Co-ord. Class Category Number Description Items Method Request Remarks 18" discharge piping 241 2 C-F C5.11 Circumferential 43 Surf from 12"X18" reducer Welds N.W.T. 1 5" to MO-28A and to M0-19 (on Disch. X-connect). 241 2 C-F C5.31 Branch Pipe Connec. 2 Surf Circumferential Welds 241 2 C-C C3.40 Integral 1 Surface ll7HLl(4)

Attachment 241 2 F-C F(1-3) Restraint 4 Visual VT-3 241 2 F-B f(1-3) Guide 1 Visual VT-3 241 2 F-C F(1-3) Rigid Support 7 Visual VT-3 241 2 F-C F(1-4) Spring Hanger 3 Visual VT-3&4 241 2 F-B F(1-4) Spring Support i Visual VT-3&4 241 2 F-B F(T-3) Anchor i Visual VT-3

7 Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear -

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 yytem: RESIDUAL HEAT REMOVAL (RHR) Page 10 of 24 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief

_ Description Co-ord. Class Category Number Description Items Method Request Remarks 18" Piping between 241 2 C-F C5.20 Circumferential 4 Vol.& DB/DC-10-3002-MO-29A and M0-28A Welds N.W.T.>.5" Surf 3-3 is a dis-similar metal weld .

241 2 F-B F(1-3) Rigid Support i Visual VT-3 12" Piping from 12"X18" 241 2 C-F C5.Il Circumferential 19 Surf teldolet, bounded by Welds N.W.T i .5" 12"X10" reducer, M036A, and the 12"X6" reducer 241 2 F-8 F(1-3) Rigid Support i Visual VT-3 241 2 F-C F(1-4) Spring Hanger 3 Visual VT-3 241 2 F-C F(1-4) Anchor 1 Visual VT-3 ti" Piping from 12"X6" 241 2 C-F C5.11 Circumferential 17 Surf reducer (upstrm of Welds N.W.T. 1 5" M037A) to torus . . .

Penetration X-211A 241 2 C-F F(1-3) Rigid Support 4 Visual VT-3 241 2 F-B F(1-3) Anchor i Visual VT-3 241 2 F-B F(1-3) Guide 1 Visual VT-3

~Baston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear c .

Edison . _ .

SECOND TEN-YEAR INTERVAL ,  ? Power Station Company '

ASME XI 1980 EDITION M30 ADD {NDA \ Unit - 1 y.

System: RESIDUAL HEAT REMOVAL (RHR) Page 11 of 24s -

.. Rev. 3~Y s Section '- -

_ q Section 'XI wx P&ID s - No. _

Line or Component and XI Item '

Item of Exam Relief- '

Description Co-ord. Class Category Number Description Items Method Regie A r f Remarks i,_

~

x. 12" Piping from M0-36A- 241 2 C-F C5.11 Circumferential 14 Surf '

\

to 16"X12" Reducer Welds NHT..$.5" "

x' ' -

w (upstrm of X-210A)2 x - t i s , ei "

5drf

~241 2 C-F C5.21 Eranch Pipe Conn.  ;: , ,

s

' Circum.-Helds 1

241 2 C-C C3.40 Integral Attachments 1 Suitace ,900HLl(4) 241 2 F-B F(1-3) Rigid Supporf, 1 V1.ual V

, . , VT-3

' ~

~241 2 F-C F(i-4) Spring Hanger 4 Visull' s.

_, VT-3E4  ; , - .

s _

241 2 F-8 F(1-3) Anchor -

'1 Visual VT-3 '

s ,

x lb" Piping from 16"X12" 241 2 C-F C5.11 Circumferential 2 Surf ieducer to torus nozzle Helds NHT 1 5" X-210A

! b" Piping from 1401-35A 241 2 C-F C5.11 Circumferential 1 Surf C.S. Test Line 1

1401-35A to 6 "X 12t' Helds NHT 5 5 - .

trel dol e t .

(dwnstm of M036A)

l =

~

a .- .

J /  :. ' ,

. L .

Boston INSERVICE INSPECTION PROGRAM ' Pilgrim Nuclear  :

~ # ~29 Edison SECOND TEN-YEAR INTERVAL Power Station iY Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1

=

~

Syjfem_;RESIDUALHIATREMOVAL(RHR)

Page 12 of 24 Rev. 3 Section -

P&ID Section XI No. .

~. s Line or Component and XI Item Item of Eiam Relief -

Description Co-ord. Class Category' Number Description Items Method Request Remarks ,

10" Piping from 12"X10" 241 2 C-F C5.11 Circumfbrential 25 Surf seducer to X-39A Helds NHT 1 5" 241 2 F-C F(1-4) Spring Hanger 5 Visual _'

VT3&4 i

! 241 2 l-B F(1-3) Guide 1 VI,ual i V1-3:

?

241 2 F-B F(1-4) Spring Support 1 Visual VI-3&4 16" Discharge Piping 241 2 C-F C5.11 Circumferential 5 Suit from E-207B Welds NHT <.5" 241 2 F-C F(1-3) Restraint ^ 1 Visual ~

VT-3 th" Piping on Inlet 241 2 C-F C5.11 Circumferential 11 Surf - '

to H.X."B" (E-2078) Helds N.H.T. 1 5" 241 2 F-C F(1-4) Spring Hanger 2 Visua'l VT-3&4.

-6 y

d

.S- f p

7- .

Boston INSERVICE INSPECTION. PROGRAM Pilgrim Nuclear -

Edison SECOND TEN-YEAR INTERVAL Power Station

-Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 Sj~s tem

RESIDUAL HEAT REMOVAL (RHR) .

Page 13 of 24 Rev. 3 Section P&lD Section XI No.

Line or Component and XI Item Item of Exam- Relief.

Description Co-ord. Class Category Number Description Items Method Request Remarks 16" Piping on inlet to 241 2 F-B F(1-3) Restraint 1 Visual H.X. "B" (E-207B)(Cont.) VT-3 12" Piping on Discharge 241 2 C-F C5.11 Circumferential 12 Surf Helds N.H.T. 1 5" of Pump 203D 241 2 F-C F(1-4) Spring Support i Visual-VT-3&4 241 2 F-C F(1-3) Restraint i Visual 1

VT-3 12" Piping on discharge 241 2 C-F CS.11 Circumferential 12 Suif l of Pump 203B Helds, N.H.T. 1 5" 4 241 2 C-C F(1-4) Spring Support 1 Visual -

j VT-3&4 241 2 F-C F(1-3) Restraint 1 Visual VT-3 l

241 2 C-C C3.40 Integral Attachments 1 Surface 224 HLl(8) q

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear -

~

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 System: RESI' DUAL HEAT REMOVAL (RHR) Page 14 of 24 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Catego_ry Number Description Items Method Request Remarks 18" discharge Piping 241 2 C-f C5.11 Circumferential 44 Surf from the 12"X18" & Helds N.H.T. < .5" 16"X18" reducers to MO-288 including piping up to 1001-53 241 2 C-F C5.31 Branch pipe Conn. 2 Surf (on disch. X-connect) Circum. Held 241 2 f-C f(1-3) Rigid Support 7 Vi.ual VI-3 241 2 F-C F(1-3) Restraint 5 Visual VI- 3 150-10-3B and 10-4B 241 2 F-B F(1-3) Guide 1 Visual VT-3 241 2 F-C F(1-4) Snubber 2 Visual VT-3&4 241 2 F-C f(1-4) Spring Hanger 5 Visual VT-3&4 241 2 C-C C3.40 Integral 3 Surf 174HLl(2)

Attachments -

. 19HLl(4) 12HLl(4) 18" Piping between 24I 2 C-f C5.20 Circumferential 3 Vol.& DB/DC MO-28B and M0-29B Helds N.H.T. >.5" Surf 3001-2-1 is a dissimilar metal weld

7 o

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear -

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Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 System: RESIDUAL HEAT REMOVAL (RHR)

~

Page 15 of 24 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks 18" RHR discharge 241 2 C-F C5.11 Circumferential 4 Surf X-Connect Piping Helds N.H.T 15 between MD-19, 1001-53, and 18"X12" Reducer. 241 2 C-F C5.31 Branch Pipe Conn. 1 Surf (On Service Water line) Circum. Held 241 2 F-B F(1-3) Anchor 1 Visual VT-3 6" piping to fuel pool 241 2 C-F C5.11 Circumferential 2 Surf from discharge X-Conn. Helds NHT i .5" piping i

12" piping from service 241 2 C-F C5.11 Circumferential 37 Surf Wdter system to 18"X12" Helds NHT 1 5" reducer on the discharge X-connect line 241 2 F-C F(1-3) Restraint 2 Visual VT-3 1

241 2 F-C F(1-3) Anchor 3 Visual VT-3 l 241 2 F-C F(1-3) Rigid Support 9 Visual VT-3 241 2 F-C F(1-4) Spring Hanger i Visual VT-3&4 1

1

Boston INSERVICE INSPECTION PROGRAM- Pilgrim Nuclear: -

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System: RESIDUAL HEAT REMOVAL (RHR) Page 16 of 24 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief

. Description _____Co-ord. Class Category Number _ Description Items Method Request Remarks 12" Piping to containment 241 2 C-F C5.11 Circumferential 16 Surf Includes F28 spray header, bounded Helds N.H.T. $ .5" by 12"X18" weldolet, 12"X10" reducing elbow 241 2 C-F C5.31 Branch Connection 1 Surf dnd M036B 241 2 F-B F(1-3) Restraint i Vi.ual H-10-1-40SA V1.3 241 2 F-8 F(1-3) Rigid Support 2 Visual VT-3 t, " Piping from 12"X16" 241 2 C-F C5.ll Circumferential 13 Surf weldolet (upstrm of Welds N.H.T. 1 5" M0378) to torus penetration X-2118 241 2 F-C F(1-3) Guide 1 Visual VT-3 -

241 2 F-C F(1-3) Rigid support 2 Visual VT-3 6" Piping from -

241 2 C-F C5.11 Circumferential Helds 2 Surface -

C.S. Test Line 1401-35B to 6" X 12" '

N.H.T. <.5" Weldolet (dunst of M0368) -

o -

-O Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear -

Edison SECOND TEN-YEAR INTERVAL Power Station Company AS,M,E XI 1980 EDITION W80 ADDENDA Unit - 1 System:iRESIDUALHEATREMOVAL(RHR)

Page 17 of 24 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief

. Description ___Co-ord. Class Category Number Description Items Method Request Remarks 12" Piping from M0-36B 241 2 C-F C5.11 Circumferential 14 Surf to 16" X 12" Reducer Welds N.W.T < .5"

~

(upstream of X-2108) 241 2 C-F C5.31 Branch Pipe Conn. 2 Surf Circum Welds 241 2 C-C C3.40 Integral Attachments 2 Surf 152HL1(2) 79PS 241 2 F-8 F(1-3) Guide 1 Visual ,

VT-3 241 2 F-8 F(1-3) Rigid Support i Visual VT-3 241 2 F-B F(1-3) Anchor 1 . Visual VT-3 241 2 F-C F(1-3) Rigid Support 3 Visual VT-3 16" Piping from 16"X12" 241 2 C-F C5.11 Circumferential 2 Surf reducer to torus Welds N.W.T. <.5 Penetration K-210B - -

4

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear -

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 Systemj RESIDUAL HEAT REMOVAL (RHR) Page 18 of 24 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief

_ Description Co-ord. Class Catego_ry Number Description Items Method Request Remarks 10" piping from 12"X10" 241 2 C-F C5.11 Circumferential 27 Surf reducing elbow to X-39B Helds N.H.T. 1 5" 241 2 F-C F(1-3) Restraint 3 Visual VT-3 241 2 F-B F(1-3) Guide 1 Visual VT-3 241 2 F-C F(1-3) Rigid Support 6 Visual VT-3 t

241 2 F-C F(1-4) Spring Hanger 7 Visual Includes VT-3&4 supports on 1001-23B&26B t; " Piping from check 241 2 C-F C5.ll Circumferential 2 Surf

, Volve (from conden. Held N.W.T. 1 5"

storage tank) to 12"X6" weldolet 241 2 F-C F(1-3) Rigid Support 1 Visual VT-3 20" Suction Piping from 241 2 L-F C5.Il Circumferential 21 Surface - .

! 1001-47 to RHR Pumps Welds N.H.T. 1 5" A&C

m .

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear -

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 Sys_ tem: RESIDUAL HEAT REMOVAL (RHR) Page 19 of 24 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Enm Relief Description _

Co-ord. Class Category Number Description Items Method Request _ Remarks 20" Suction Piping from 241 2 C-C C3.40 Integral Attachments 3 Surface 28HLi(2) 1001-47 to RHR Pumps 83PS A & C (Continued) 83HLI(4) 241 2 F-B F(1-3) Guide 2 Visual VT-3 241 2 F-C F(1-3) Rigid Support 2 Visual VT-3 F-8 F(1-3) Rigid Support i Visual VT-3 241 2 F-B F(1-3) Anchor 1 Visual VT-3 241 2 F-C F(1-4) Spring Hanger 4 Visual VT-3&4 e

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear -

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System: RESIDUAL HEAT REMOVAL (RHR) Page 20 of 24 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks 20" Suction Piping from 241 2 C-F C5.11 Circumferential 17 Surf tee dwnstrm of 1001-47 Welds N.W.T. < .5" to RHR Pumps B&D 241 2 C-C C3.40 Integral Welds 2 Sui t 91PS 92HLl(4) 24l 2 F-C F(1-3) Restraints 3 Visual VI-3 241 2 F-B F(1-3) Guides 2 Visual VT-3 241 2 F-8 F(1-3) Rigid Support 4 Visual VT-3 241 2 F-B F(1-3) Anchor i Visual VT-3 241 2 F-C F(1-4) Spring Hanger 4 Visual VT-3&4

, Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear '-

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADOENDA Unit - 1 System: RESIDUAL HEAT REMOVAL (RHR) Page 21 of 24 Rev. 3 Section P&ID Section XI No.

line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks 3

18" Suction Piping 241 2 C-F C5.11 Circumferential 3 Surf upstrm of 1001-43A Welds N.W.T. 1 5" 241 2 C-C C3.40 Integral Attachment 1 Surf 294HLI(8) i 241 2 F-B F(1-3) Restraint 1 Visual VT-3 1

241 2 F-C F(1-4) Spring 1 Visual Hanger VT-3&4 i

18" Suction Piping 241 2 C-F C5.11 Circumferential 2 Surface tipstream of 1001-43B Welds NWT 1 5" 241 2 F-C F(1-4) Spring Hanger i Visual VT-3&4 18" Suction Piping 241 2 C-F C5.11 Circumferential 2 Surface Upstream of 1001-43C Welds NWT 1 5" 241 2 F-C F(1-4) Spring Hanger 1 Visual

+ - . VT-3&4 . .

18" Suction Piping 241 2 C-F C5.11 Circumferential 3 Surface Upstream of 1001-43D Welds NWT 5 5" 241 2 F-B F(1-3) Restraint 1 Visual V1-3

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear. -

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Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System: RESIDUAL HEAT REMOVAL (RHR) Page 22 of 24 Rev. 3 Section P&ID Section XI No.

IIne or Component and XI Item Item of Eum Relief Description Co-ord. Class Category Number Description Items Method Request Remarks 18" Suction Piping 241 2 F-C F(1-4) Spring 1 Visual upstream of 1001-43D Hanger VT-3&4 (continued) 6" Line from fuel pool 241 2 C-F C5.11 Circumferential 19 Surface cooling to suction Welds NWT <.5" X-Connect.

241 2 F-B F(1-3) Restraint i Visual VT-3 241 2 F-B F(1-3) Guide 1 Visual VT-3 241 2 F-B f(1-3) Anchor 1 Visual VT-3 241 2 F-C F(1-4) Spring Hanger 3 Visual VT-3&4 241 2 F-C F(1-4) Spring Support 3 Visual VT-3&4 241 2 F-C F(1-3) Rigid Support i Visual . .

VT-3

S s

Boston INSERVICE' INSPECTION PROGRAM Pilgrim Nuclear '-

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION M80 ADDENDA Unit - 1 System: RESIDUAL HEAT REMOVAL (RHR) Page_23 of 24 Rev. 3 Section P&ID Section XI No.

t.ine or Component and XI Item Item of Exam Relief Description __Co-ord. Class Category Number Description Items Method Request Remarks HilR Heat Exchanger "A" 241 2 C-A Cl.10 Shell Circum. 2 Vol. E207A-1 Held E207A-2(Exempt)

E207A-3 241 2 C-A C1.20 Head Circumfer 2 Vol. E207A-4 Held E207A-5 241 2 C-B C2.21 Nozzle to Shell 2 Vol.& PRR E207A-N4A-1 Surf. 8 E207A-N3A-1 241 2 C-C C3.10 Integral 4 Surf.

Attachment RilR lleat Exchanger "B" 241 2 C-A Cl.10 Shell Circumfer. 2 Vol. E207B-1 Helds E2078-2(Exempt)

E2078-3 241 2 C-A C1.20 Head Circumfer. Held 2 Vol. E2078-4 E2078-5 241 2 C-B C2.21 Nozzle to Shell 2 Vol.& PRR E207B-N48-1 Surf. 8 E2078-N38-1 241 2 C-8 C3'.10 Integral 4 Surf.

Attachment

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear -

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System: RESIDUAL HEAT REMOVAL (RHR) Page 24 of 24 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief

. De s c_ri p t ion _

Co-ord. Class Category' Number Description Items Method Request Remarks RHR Pumps 203A, 241 2 C-C C3.70 Integral Attach 4 Surf B,C&D (Pump Support Pedestal)

Residual Heat 241 2 C-H C7.10 System Leak Test VI-2 Removal System Of Pressure Vessels 241 2 C-H C7.11 System Hydro Test VT-2 Of Pressure Vessels 2 11 2 C-H C7.20 System Leak Test of VT-2 Piping 241 2 C-H C7.21 System Hydro Test of VT-2 Piping 241 2 C-H C7.30 System Leak Test VT-2 of Pumps 241 2 C-H C7.31 System Hydro Test VT-2 of Pumps 241 2 C-H C7.40 System Leak Test VT-2 of Valves . .

241 2 C-H C7.41 System Hydro Test VT-2 of Valves

. 9 Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear Edison SECOND TEN-YEAR INTERVAL Power Statioh Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 ,

System: STANDBY LIQUID CONTROL Page 1 of 2 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief

__. Description Co-ord. Class Category Number Description Items Method Request Remarks I 1/2 line from 1101-16 249 1 B-G-2 B7.70 Valves-Bolts, studs, 3 Visual 1101-16 to RPV Nozzle N-14 and nuts 1 2" Dia. VT-1 1101-15 1101-1 249 1 B-J 89.40 Socket Welds 69 Surf 249 1 FB/FC F(1-3) Guides 21 Visual VT-3 249 1 F-B F(1-3) Anchor 1 Visual X-42 VT-3 249 1 F-C F(1-3) Rigid Support i Visual VT-3 249 1 F-C F(1-4) Soring Hanger i Visual VT-3&4 249 2 C-H C7.20 System Leak Test of Visual Piping VT-2 249 2 C-H C7.21 System Hydro Test of Visual Piping VT-2 249 2 C-H C7.'30 System Leak Test Visual of Pumps VT-2

9 o Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION M80 ADDENDA Unit - 1 System: STANDBY LIQUID CONTROL Page 2 of 2 Rev. 3 Section P&ID Section XI No.

, tino or Component and XI Item Item of Exam Relief l ._ Description Co-ord. Class Category Number Description Items Method Request Remarks 249 2 C-H C7.31 System Hydro Test Visual of Pumps VT-2 249 2 C-H C7.40 System Leak Test Visual of Valves VT-2 249 2 C-H C7.41 System Hydro Test Visual of Valves VT-2 l

l l

1 l . . .. .

I l

l l

l

_ __ ~ _-. . . - - _ . . . ..

I .

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear -

Edison SECOND TEN-YEAR INTERVAL Power Station -

Company AME XI 1980 EDITION W80 ADDENDA Unit - 1 System: REACTOR PRESSURE VESSEL DRAIN Page 1 of 1 Rev. 3'

___Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief

_ Description _

Co-ord. Class Category,_ Number Description Items Method Request Remarks 2" RPV Drain Line 252 1 B-F B5.52 Piping-Dissimilar 1 Surf 12R-BC-14 from Nozzle N-11 Metal socket welds dnd 2" branch connection piping from RWCU system 252 1 B-G-1 B7.70 Valves - Bolts, studs 3 Visual 1201-65 and Nuts 1 2" dia. VT-1 1201-39 1201-40 252 1 B-J 89.40 Piping-NPS 4" 33 Surf 12R-BC-1 is Socket Welds Branch conn.

weld see RWCU system 4-N11-1 is in RPV system 252 1 f-B F(1-3) Guides 7 Vi,ual VI-3 4

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear * -

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 4 .,

System: REACTOR NATER CLEAN-UP (RWCU) Page 1 of 2 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks 4" and 6" piping from 247 1 B-F B5.50 Piping n.p.s. 2 4" 1 Vol. 12-I-16 MO 1201-80 to 18" Dissimilar metal butt & Surf.

Feedwater Piping welds 247 1 B-G-2 B7.70 Valves Bolts, studs, 3 Visual 1201-80 and nuts < 2" diameter VT-1 1201-81 1201-82 247 1 B-J 89.11 Piping n.p.s. 1 4" 37 Vol.&

Circumferential welds Surf 247 1 B-M-2 B12.40 Valve body n.p.s. > 4" 2 Visual PRR 1201-81 VT-3 3 1201-82 247 1 F-C F(1-3) Rigid Support 1 Visual VT-3 247 1 F-C F(1-4) Spring Hanger 5 Visual VT-3&4 247 1 F-C F(1-3) Restraints 3 Visual VT-3 247 1 F-B F(1-3) Guides 3 Visual -

VT-3 247 1 F-B F(1-3) Anchor 1 Visual VT-3

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear ~

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System: REACTOR WATER CLEAN-UP (RWCU) Page 2 of 2 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks 6" Supply piping from 247 1 B-G-2 B7.70 Valves-Bolts, studs, Visual 1201-85 20" RHR piping to and nuts 1 2" diameter VT- 1 1201-2 H01201-5 1201-5 247 1 B-J 89.11 Piping n.p.s. > 4" 35 Vol. & PRR (1) 252 Circumferential welds surf 1 Inaccessible weld in X-14, 12R-0-1 is a branch conn.

see RHR system 247 1 B-J 89.32 Piping n.p.s. < 4" 1 Surf 12R-BC-1 252 Branch connection weld 247 1 B-K-1 B10.10 Integrally welded 1 Surf PRR (8) 252 Attachments 1 Inaccessible Lugs in X-14 247 1 B-M-2 B12.40 Valve body n.p.s. > 4" 3 Visual PRR 1201-85 252 VT-3 3 1201-2 1201-5

+ -

247 I F-C F(1-4)

Spring Hangers 5 Visual . .

252 VT-3&4 247 1 F-B F(1-3) Anchor 3 Visual X-14 252 VT-3

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear ^

~

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System: REACTOR CORE ISOLATION COOLING (RCIC) Page 1 of 6 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Doscription Co-ord. Class Category' Number Description Items Method Request Remarks 3" Steam Supply from 245 1 B-G-2 B7.70 Valves-Bolts, Studs 2 Visual 1301-16 Main Steam Line and nuts < 2" dia. VT-1 1301-17 "C" to M01301-17 245 1 B-J B9.21 Piping n.p.s. < 4" 20 Surf PRR (1)

Circumferential welds 1 Inaccessible weld in X-53 245 'l B-K-1 B10.10 Piping - Integral 2 Surf (8) attachments Inaccessible lugs in X-53, 11HLl(8) 245 1 F-C F(1-4) Spring Hangers 2 Visual VT3&4 245 1 F-C F(1-4) Snubbers 2 Visual VT3&4 245 i F-C F(1-3) Anchor 1 visual VT-3 O

9

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear ~

• Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 System: REACTOR CORE ISOLATION COOLING (RCIC) Page 2 of 6 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks 4" discharge Piping 245 1 B-G-2 B7.70 Valves-Bolts, Studs 2 Visual 1301-49 from M01301-49 and Nuts < 2" Dia VT-1 1301-50 to 6" RWCU Piping 245 1 B-J 89.11 Piping - NPS > 4" 17 Vol.&

Circumferential Held Surf 245 1 F-C F(1-3) Rigid Supports 3 Visual VT-3 245 1 F-C F(1-4) Spring Hangers 2 Visual VT3&4 245 1 F-C F(1-3) Restraint i Visual VT-3 245 1 F-C F(1-3) Anchor i Visual VT-3

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear

• Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H80 ADDENDA Unit - I fyst:m: REACTOR CORE ISOLATION COOLING (RCIC) Page 3 of 6 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief

_ Description Co-ord. Class Category Number Description Items Method Request Remarks 6" Suction Piping from 245 2 C-F C5.11 Circumferential welds 14 Surface M026 and from check NHT 1 5" valve 1301-23 to Pump P-206 Suction Nozzle 2 F-C F(1-3) Restraint i Visual VT-3 2 F-C F(1-4) Spring Hanger i Visual VT-3&4 2 F-A F(1-3) Rigid Support 1 Visual VT-3 6" Suction Piping from 245 2 C-F C5.11 Circumferential Welds 9 Surface Torus Nozzle X-220 to NHT 1 5" MO-25 2 F-A F(1-3) Rigid Support 2 Visual VT-3

• .g

• O O

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear ~

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System: REACTOR CORE ISOLATION COOLING (RCIC) Page 4 of 6 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks 6" Suction Piping from 245 2 C-F C5.11 Circumferential Welds 4 Surface M025 to H026 NHT 1 5" 2 F-A F(1-3) Guide 1 Visual VT-3 2 F-A F(1-3) Rigid Support 2 Visual VT-3 8" Exhaust Piping from 245 2 C-C C3.40 Integrally Welded 1 Surface F-HLl(2)

Turbine Exhaust Nozzle Attachments to Piping up to PSD 1301-9 and .

check valve 1301-41 2 C-F C5.11 Circumferential Welds 25 Surface NNT 1 5" 2 F-A F(1-3) Anchor i Visual VT-3 2 F-C F(1-4) Spring Hanger 3 Visual VT-3&4 2 FA/FC F(1-3) Rigid Support 2 Visual VT-3

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System: REACTOR CORE ISOLATION COOLING (RCIC) Page 5 of 6 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief' Description Co-ord. Class Category Number Description Items Method Request Remarks 8" Exhaust Piping 245 2 C-F C5.11 Circumferential Welds 8 Surface from Check Valve NHT < .5" 1301-41 to Torus 2 F-C F(1-4) Snubber i Visual VT-3&4 2 F-A F(1-3) Guide 1 Visual VT- 3 8" Exhaust Piping 245 2 C-F C5.11 Circumferential Welds 5 Surf from PSD 1301-9 to NWT < .5" PSD 1301-10 2 F-A F(1-3) Anchor i Vhual VT-3 2 F-C F(1-3) Rigid Support i Visual VT-3 e

d

o .

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear '

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System: REACTOR CORE ISOLATION COOLING (RCIC) Page 6 of 6 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief

.._ Description Co-ord. Class Category Number Description Items Method Request Remarks RCIC System - 245 2 C-H C7.20 System Leak Test of VT-2 Pressure Retaining Piping Components 2 C-H C7.21 System Hydro Test of VT-2 Piping 2 C-H C7.30 System Leak Test of VT-2 Pumps 2 C-H C7.31 System Hydro Test VT-2 of Pumps 2 C-H C7.40 System Leak Test VT-2 of Valves 2 C-H C7.41 System Hydro Test VT-2 of Valves 4

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear

• Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System: CORE SPRAY Page 1 of 9 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks Loop "A" Discharge 242 1 B-F B5.50 Piping - N.P.S. 1 4" 2 Vol. 14-A-3 Piping from Dissimilar metal welds & Surf 14-A-10A H0 1400-25A to RPV Nozzle N6A .

242 1 B-F B5.10 Piping - N.P.S. > 4" See RPV sys-Nozzle to safe end tem for weld dissimilar metal weld 14-A-1 242 1 B-G-2 B7.70 Valves-Bolts 3 Visual 1400-6A studs and nuts, < 2" dia. VT-1 1400-9A 1400-25A 242 1 B-J 89.11 Piping - N.P.S. 1 4" 19 Surf PRR Inaccessible Circumferential welds & Vol. I weld in X-16A 242 1 B-K-1 B10.10 Piping - Integrally 1 PRR (8) welded attachments 1 Inaccessible lugs'in X-16A 242 1 B-M-2 B12.40 Valve body N.P.S. > 4" 3 Visual PRR 1400-6A VT-3 3 1400-9A

. . 1400-25A i

o Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear

• Edison SECOND TEN-YEAR INTERVAL ' Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System: CORE SPRAY Page_2 of 9 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks Loop "A" discharge 242 1 F-C F(1-4) Spring Hangers 2 Visual piping from H01400-25A VT-3&4 to RPV nozzle N6A (Cont.) 242 1 F-C F(1-4) Snubbers 2 Visual VT-3&4 241 1 F-B F(1-3) Anchor 1 Visual X-16A VT-3 Loop "B" discharge 242 i B-F B5.50 Piping - N.P.S. > 4" 2 Vol.& 14-B-3 piping from H01400-25B Dissimilar metal welds Surf 14-B-10A to RPV Nozzle N6B 242 1 B-F B5.10 Piping - N.P.S. 1 4" see RPV sys-Nozzle to safe end tem or weld dissimilar metal weld 14-B-1 242 1 B-G-2 B7.70 Valves-bolts, studs 3 Visual 1400-6B and nuts 1 2" dia. VT-1 1400-96 1400-25B 242 1 B-J 89.11 Piping - N.P.S. 1 4" 21 Vol.& PRR Inaccesible Circumferential Welds Surf 1

. Weld In X-16B 252 1 B-K-1 810.10 Piping - Integrally 1 PRR (8) Inaccess-Welded attachments 1 lble lugs in X-16B

i Boston INSERVICE INSPECTION PROGRAM Pilgria Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station -

Company ASME XI 1980 EDITION M80 ADDENDA Unit - 1 1

Iystem: CORE SPRAY Page 3 of 9 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Cateoory Number Description Items Method Request Remarks Loop "B" discharge from 252 i B-H-2 B12.40 Valve Body - N.P.S. > 4" 3 Visual 1400-6B

MO-25B to RPV Nozzle N6B VI-3 1400-98 '

3 (Cont.) 1400-258

]

242 1 F-C F(1-4) Spring Hanger 2 Visual VT-3&4 1

l 242 1 F-C F(1-4) Snubbers 2 Visual i VT-3&4 242 1 F-B F(1-3) Anchors 1 Visual X-168 VT-3 Loop "A" - 18" Pump 242 2 C-F C5.11 Circumferential Welds 20 Surf.

I Suction Piping from N.W.T < .5"

]

Torus Nozzle X-229A i to 12"X18" reducer *

242 2 C-F C5.31 Pipe branch Connection 1 Surf From conden-sate storage tank 242 2 F-C F(1-3) Restraints 3 Visual VT-3

! 242 2 F-B F(f 3) Rigid Support 6 Visual VT-3 i

f I

l a

- y Boston INSERVICE INSPECTION PROGRAM ~

Pilgria Nucidar

• Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA 'l'~ Unit - 1

~

. > n v-  % A 3 .

' ^

System: CORE SPRAY - - Page 4 of 9 Rev. 3 Section " -.

P&ID Section XI -

No. - NN Line or Component and XI Item's ' Item of Exam Relief Description .. Co-ord. Class CateJory Number Description s Items Method Request Re s tlef '

~l b Piping from valve 242 2 _ C- F- C5.11 Circumferential Helds 2 Suif

' ~

~\ ,

1400-2A (Suction Piping - -

N.W.T. 1 5" n, ' '

from cond. storage tanki to branch connection an 242 Q F-8 Fil-3). Rigid Support s'1 ~ 9 Visual -

located -

18" section piping from

~~

vi -3

~

" upstream

[ _

of 1400-2A torus >>

242 2 F-C F(1-3) Restraint ~1 Visual located VT-3 upstream

~

_ .of1400-2A

- c-12" suction ;.ipir:q from 242 2. C-F C5.11 Circumferenital Pelds 2 Surf 18"X12" reduce, to P-215A NWT. 1 5 ,

. U" Discharge piping C5.li' Circudferential welds --E

~

242 e C-F_- '

38 surf .,

trom P215A to M025A li .W. T . 1 5" -

- -N 92 - 2 C-F C5.21 ~ CircumfereAtlal welds ' I4 ' Vo .&'

DC/DB-14-3002-5-1 N.W.T.> .5" . Surf. is a dissiellar i .

metal weld 242 2 C-F C5.31 Branch Pipe Connections i Surf Test line conn.

Circuitferential

~ ~

Weld

. . s . .

i.3.<0

^

242 2 C-C' Integral Attachments 2 Surf 28HL2(4) 8HLl(4)

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear

• Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H80-ADDENDA Unit - 1 Sis [em: CORE SPRAY Page 5 of 9 Rev. 3 Section- -

P&ID Section XI No. <

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks 10" discharge piping 242 2 F-C F(1-3) Restraints 2 Visual Continued -

VT-3 242 2 F-B F(1-3) Guides 2 Visual ^

VT-3 242 2 F-B F(1-3) Rigid Supports 2 Visual VT-3 ,_

242 2 F-C F(1-3) Rigid Supports 6 Visual VT-3 242 2 F-B F(1-3) Anchor 1 Visual VT-3 242 2 F-C F(1-4) Spring Hangers 2 -Visual VT3&4 6" test line piping 242 2 C-F C5.11 Circumferential Helds 13 Surf (A-Loop) from 10"X6" 241 NHT < .5" Heldolet (on P215A discharge piping)to 242 2 F-C F(1-4) Spring Support 1 Visual y ,

1401-35A 9

O Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station -

Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 System: CORE SPRAY Page 6 of 9 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks Loop "B"-18" pump 242 2 C-F C5.11 Circumferential Helds 19 Surf suction piping from NWT 1.S" torus nozzle X-229B to 12"X18" Reducer 242 2 C-F C5.31 Pipe Branch Connection 1 Suit from condensate Circumferential Weld storage tank 242 2 F-C F(1-3) Restraint 3 Visual

VT-3 242 2 F-B F(1-3) Rigid Support 6 Visual VT-3 12" Piping from valve 242 2 C-F C5.11 Circumferential Helds 2 Surf

. 1400-2B (Suction piping NHT 1.S" from conden storage tank) to branch 242 2 F-C F(1-3) Restraint i Visual located upstream connection on 18" VT-3 of 1400-2B suction piping from torus 242 2 F-B F(1-3) Rigid Support 1 Visual located upstream VT-3 of 1400-2B s v j .

• O Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear '

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 System: CORE SPRAY Page 7 of 9 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks 12" Suction piping from 242 2 C-F C5.ll Circumferential Helds 2 Surf 18"X12" reducer to P215B NHT 1 5" 10" discharge piping 242 2 C-F C5.ll Circumferential Helds 29 Surf .

from P215B to MO-25B NHT 1 5" 242 2 C-F C5.21 Circumferential Helds 3 Vol& DC/DB-14-3001-4-1 NHT >.5" Surf. is a dissimilar metal weld 242 2 C-F C5.31 Branch pipe connection 1 Surf Test line conn.

circumferential weld 242 2 C-C C3.40 Integral attachments 3 Surf 2HLl(4) lHLl(4) 22HLl(4)

%.g

O Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station -

• Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System: CORE SPRAY Page 8 of 9 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class CateJory Number Description items Method Request Remarks 10" discharge piping 242 2 F-B F(1-3) Restraint i Visual from P215B to M0-25B VI- 3 (continued) 242 2 F-8 F(1-3) Guide 1 Visual VT-3 242 2 F-B 'F( 1 -3 ) Rigid Support 1 Visual VT-3 242 2 F-C F(1-3) Rigid Support 3 Visual VT-3 242 2 F-B F(1-3) Anchor 2 Visual VT-3 242 2 F-C F(1-4) Spring Hanger 3 Visual VT-3&4 6" test line piping 242 2 C-F C5.11 Circumferential Welds  ? Surf (B-Loop) from 10"X6" 241 NHT <.5" weldolet (on P-215B discharge piping) to 242 2 F-B F(1-3) Guide 1 Visual 1401-35B

• .g h

o .

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear ~

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 system: CORE SPRAY Page 9 of 9 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Categori Number Description Items Method Request Remarks Pressure Retaining 242 2 C-H C7.20 System leak test Visual components-piping VT-2 242 2 C-H C7.21 System Hydro Test Visual VT- 2 Pressure Retaining 242 2 C-H C7.30 System Leak Test Visual components-pumps VT-2 242 2 C-H C7.31 System Hydro Test Visual i

VT-2 Pressure Retaining 242 2 C-H C7.40 System Leak Test Visdal Components-Valves VT-2 242 2 C-H C7.41 System Hydro Test Visual VT-2 i

} -

4 i

i

o .

O Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear ~

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 System: HIGH PRESSURE COOLANT INJECTION Page 1 of 8 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks 10" Steam Supply from 243 1 B-J B9.11 Circumferential 23 Surf & PRR Inaccessibe weld Main Steam Line "D" to 244 Helds N.P.S. 2 4" Volume 1 in X-52 2301-5 243 1 B-K-1 B10.10 Integral Attach. 2 Surface 8HLl(8) 8 inaccessible lugs in X-52 243 1 B-M-2 B12.40 Valve Body 2 Visual PRR 2301-4 N.P.S 1 4" VT-3 3 2301-5 243 1 B-G-2 B7.70 Valve-Bolts, Studs 2 Visual 2301-4 and Nuts 1 2" Dia. VT-1 2301-5 243 1 F-C F(1-4) Snubber 2 Visual VT-3&4 243 1 F-C F(1-4) Spring 3 Visual Supports VT-3&4 243 1 F-8 F(1-3) Anchor 1 Anchor X-52

2 Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear

• Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System: HIGH PRESSURE COOLANT INJECTION Page 2 of 8 Rev. 3 Section j P&ID Section XI No.

! Line or Component and XI Item Item of Exam Relief.

Description Co-ord. Class Category Number Description Items Method Request Remarks 14" Discharge Piping 243 I B-J 89.11 Circumferential 18 Surf.&

from MO-8 to feedwater 244 Helds N.P.S. > 4" Volume Line "B" 243 1 B-H-2 B12.40 Valve Body 2 Visual PRR-3 2301-7 N.P.S. > 4" VT-3 2301-8 I

243 1 B-G-2 B7.70 Valves-Bolts, Studs 2 Visual 2301-7 i & Nuts 1 2" Dia. VT-1 2301-8 243 1 B-K-1 B10.10 Integral 2 Surf 12HLl(6)

Attachments 12PS(2)

243 1 F-C F(1-3) Restraint i Visual VT-3 1

243 1 F-B F(1-3) Guide 1 Visual j VT-3 l

243 1 F-C F(1-3) Rigid Support 3 Visual i

V1 3 1 243 1 F-8 F(1-3) Anchor I Visual i , -

VT-3 . .

s. .

243 1 F-C F(1-4) Spring Hanger 2 Visual

! VT-3&4 j Group Circumferential welds 3- Vol. 23-0-9 j I Helds inspected in ten year 23-0-10

! interval 23-0-14 l

1 i

I

o .

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear

• Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System; HIGH PRESSURE COOLANT INJECTION Page 3 of 8 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number .

Description Items _ M_ethod Request Remarks 16" Pump Suction Piping 243 2 C-F C5.11 Circumferential 43 Surf from Torus and Condensate Welds. N.W.T. 1 5" Storage Line (MO-6) to 16" X 14" Reducer 243 2 C-C C3.40 Integral Attach. 1 Surf 175HLl(1) 243 2 F-B F(1-3) Restraint i Visual VT-3 243 2 F-C F(1-3) Restraint 2 Visual VT-3 243 2 F-B F(1-3) Anchor i Visual VT-3 243 2 F-B F(1-3) Rigid 4 Visual Support VT-3 243 2 F-C F(1-3) Rigid 2 Visual Support VT-3 243 2 F-C F(1-4) Spring 3 Visual Hanger VT-3&4 . .

o . .

O Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station -

Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 System: HIGH PRESSURE COOLANT INJECTION Page 4 of 8 Rev. 3 Section i P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks 14 Inch Pump Suction 243 2 C-F C5.11 Circumferential 1 Surface Piping from 16" X 14" Held N.H.T. < .5" Reducer to Pump Inlet 14" Discharge Piping 243 2 C-F C5.21 Circumferential 34 Surface from P205 to MO-8 Helds, N.H.T > .5" and Volume 243 2 C-C C3.40 Integral 4 Surface 37HL1(4), SlHLl(4)

Attachments 53HLi(4), 53PS(2) 243 2 F-C F(1-4) Spring Hangers 6 Visual VT-3 243 2 F-B F(1-3) Rigid Support 2 Visual VT-3 243 2 F-B F(1-3) Anchor 3 Visual VT-3 10" HPCI Discharge 243 2 C-F C5.21 Circumferential Helds 12 Volume.

Piping to M0-10 NHT >.5" and Surf 243 2 F-B F(1-3) Rigid Support 3 Visual H-23-1-27S VT-3 Included s .. ,

i

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear ~

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 System: HIGH PRESSURE COOLANT INJECTION Page 5 of 8 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks 10" HPCI Discharge 243 2 F-B F(1-3) Guide 1 Visual Piping to MO-10 VT-3 (Cont.)

10" Turbine Steam supply 243 2 C-F C5.21 Circumferential 28 Vol. &

from MO-5 to turbine Helds. N.W.T. ).5" Surface .

Inlet 243 2 C-C C3.40 Integral 3 Surface 59HLI(4)

Attachments 62HLI(4) 13HLl(4) 243 2 F-C F(1-3) Restraint 2 Visual VT-3 243 2 F-C F(1-3) Rigid Supports 2 Visual VT-3 243 2 F-C F(1-4) Snubber 3 Visual VT-3&4 243 2 F-C F(1-4) Spring 6 Visual Hangers VT-3&4

, W Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station

~

Ccapany ASME XI 1980 EDITION H80 ADDENDA Unit - 1 System: HIGH PRESSURE COOLANT INJECTION

- Page 6 of 8 Rev. 3 Section s P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks 18" Turbine Exhaust Line 243 2 C-F C5.Il Circumferential 2 Surface 244 Held N.H.T. S .5" 20" Turbine Exhaust Line 243 2 C-F C5.11 Circumferential 21 Surface 244 Welds N.W.T. 1 5" 243 2 C-C C3.40 Integral Attachments 1 Surface 75HLl(8) 243 2 F-C F(1-3) Rigid Support 2 Visual VT-3 243 2 F-C F(1-4) Snubbers 4 Visual VT-3&4 243 2 F-C F(1-4) Spring 2 Visual Hangers VT-3&4 24" Turbine Exhaust 243 2 C-F C5.ll Circumferential 6 Surface from 24" X 20" reducer Helds. N.H.T. 1 5" to torus penetration X-223 243 2 C-C C3.40 Integral Attach. I Surface 69HLl(24) og

o , .

o Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear -

Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 System: HIGH PRESSURE COOLANT INJECTION Page 7 of 8 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief

_ Description Co-ord. Class Category Number Description Items Method Request Remarks 24" Turbine Exhaust from 243 2 F-C F(1-3) Rigid Support 1 Visual 24" X 20" reducer to VT-3 Torus Penetration X-223 (Cont.)

243 2 F-C F(1-4) Snubber 1 Visual VT-3&4 243 2 F-B F(1-3) Stiffener Collars 3 Visual C-8603 VT-3 16" Turbine Exhaust 244 2 C-F C5.ll Circumferential 8 Surf Piping To PSD-69 Helds N.H.T. <.5 243 2 F-C F(1-4) Spring Hanger 2 Visual VT-3&4 243 2 F-C F(1-4) Snubber 1 Visual VT-3&4 Pressure retaining 243 2 C-H C7.20 System Leakage Test VT-2 components (piping) 243 2 C-H C7.21 System Hydro Test VT-2 Pressure retaining -

243 2 C-H C7.30 System Leakage Test VT-2 -

components (pumps) 243 2 C-H C7.31 System Hydro Test VT-2

o o

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station -

Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1

-~ ~~

Systeni: HIGH PRESSURE COLLANT INJECTION Page 8 of 8 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks l

Pressure retalning 243 2 C-H C7.40 System Leakage Test VT-2 components (valves) 243 2 C-H C7.41 System Hydro Test VT-2 4

1 1

4 j

?

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station

~

Company ASME XI 1980 EDITION W80 ADDENDA Unit - 1 System: SERVICE HATER SYSTEM Page 1 of I Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item' of Exam Relief Description Co-ord. Class Category Number Description Items Method Request Remarks P-203A and B Discharge 212 3 FB/FC F(1-3) Restraints, Guides, 9 Visualy Includes Piping up to MO-3808, Rigid Supports and VT-3 H-29-1-1321SA A0-3915 and up to anchors i the buried portion of discharge piping P-203D and E discharge 212 3 FB/FC F(1-3) Restraints, Guides, 9 Visual Includes Piping up to MO 3813, Rigid Supports, and VT-3 H-29-1-1333SA A0-3925 and up to anchors the buried portion of discharge piping '

E-209A&E-122A(A-Loop) 212 3 FB/FC F(1-3) Restraints, Guides 12 Visual inlet and outlet piping '

rigid supports, and VT-3 (piping in aux-bay) anchors E-2098&E-122B (B-Loop) 212 3 FB/FC f(1-3) Restraints, guides 12 Visual inlet and outlet piping rigid supports and VT-3 (piping in aux bay) anchors 1

]

P-208 A, B, C, D, & E 212 3 FA F(1-3) Pump support 5 Visual VT-3 212 3 FB/FC F(1-3) Lower pump casing 15 Visual . .

restraint VT-3 i

Pressure Retaining 212 3 D-B D2.10 System hydro / leakage . Visual components test VT-2

Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear

• Edison SECOND TEN-YEAR INTERVAL Power Station Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 System: REACTOR BUILDING CLOSED COOLING HATER SYSTEM Page 1 of 3 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief

__ Description Co-ord. Class Category Number Description Items Method Request Remarks RBCCW "A" Loop Suction 215 3 D-B D2.20 Integral Attachments 6 Visual H-30-1-61 piping bounded by D-C D3.20 VT-3 H-30-1-65SH P202A, B & C, 401-12, H-30-1-66 E-207A, E-206A, and H-30-1-67 .

408-58. H-30-1-68 H-30-1-26SR 215 3 FB/FC F(1-4) Pipe Supports 40 Visual VT-3 RBCCW "B" Loop Suction 215 3 D-B D2.20 Integral Attachments 8 Visual H-30-1-27SA piping bounded by D-C D3.30 VT-3 H-30-1-52 P-202 0, E, & F, E-2078, H-30-1-53 401-12 and 400-9B H-30-1-54 I, H-30-1-30SA H-30-1-1SA l

H-30-1-31SA H-30-1-99 215 3 FB/FC F(1-4) Pipe Supports 22 Visual VT-3

-4 4

I

o Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station -

Company ASME XI 1980 EDITION H80 ADDENDA ' Unit - 1 l System: REACTOR BUILDING CLOSED COOLING HATER SYSTEM Page 2 of 3 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief

_ Description Co-ord. Class Category Number Description Items Method Request Remarks RBCCH "A" Loop Discharge 215 3 D-B D2.20 Integral Attachments 11 Visual H-30-1-130 Piping bounded by P202A, D-C D3.20 VT-3 H-30-1-131 B and C, 408-5A, E-207A, H-30-1-85A E-206A and 401-197. H-30-1-437 H-30-1-438 H-30-1-439 H-30-1-121 H-30-1-10SS H-30-1-11SA H-30-1-62SA H-30-1-294 215 3 FB/FC F(1-4) Pipe Supports 39 Visual VT-3 RBCCH "B" Loop Discharge 215 3 D-B D2.20 Integral Attachments 11 Visual H-30-1-44SG Piping Bounded by P-202D, D-C D3.20 VT-3 H-30-1-43SH E and F. H-30-1-42SR H-30-1-41SG H-30-1-46 H-30-1-37SR H-30-1-12SA H-30-1-104

. . .. . H-30-1-440 H-30-1-441 H-30-1-442 215 3 FB/FC F(1-4) Pipe Supports 22 Visual VT-3

O e Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station

~

Company .ASME XI 1980 EDITION H80 ADDENDA Unit - 1

- ~

SystemiREACTORBUILDINGCLOSEDCOOLINGHATERSYSTEM Page 3 of 3 Rev. 3

, Section P&ID Section XI No.

Line or Component and XI Item Item of Exam Relief

_ A scription Co-ord. Class Category Number Description Items Method Request Remarks Pressure Retaining 215 3 D-A 01.10 System Leakage and Visual i Components Hydro Test VT-2 P202-A,B,C,D,E,&F 215 3 F-A F(1-3) Pump Supports 6 Visual VT-3 i

i E209-A&B 215 3 F-A F(1-3) Heat Exchanger 4 Visual j Support VT-3

]

4 l

e

• O Boston INSERVICE INSPECTION PROGRAM Pilgrim Nuclear Edison SECOND TEN-YEAR INTERVAL Power Station -

Company ASME XI 1980 EDITION H80 ADDENDA Unit - 1 Sy'steinT CONTAINMENT ATMOSPHERE CONTROL Page 1 of 1 Rev. 3 Section P&ID Section XI No.

Line or Component and XI Item Item of. Exam Relief

_Descrip_ tion Co-ord. Class Categog_ Number _

Description Items Method Request Remarks Purge Line to Drywell 227 2 F-C F(1-3) Pipe Supports 2 Visual from A0-5035A VT-3 Purge Line to Torus 227 2 F-C F(1-3) Pipe Supports 2 Visual From A0-5036A VT-3 Vent Line from Torus 227 2 F-C F(1-3) Pipe Supports 2 Visual Bounded by A0-5040 A&B VT-3 and A0-5042B 227 2 F-C F(1-4) Spring Supports 3 Visual VT3&4 O

• 4 s

t W

O SECTION 4.0 INSERVICE INSPECTION PROGRAM RELIEF REQl]ESTS I

l 1

4-1

Request No. DESCRIPTION Page PRR-1 Rev. 3 Drywell Penetrations 4-3 PRR-2 Rev. O Recirc Pumps 4-6 PRR-3 Rev. 1 Class 1 valves 4-8 PRR-4 Rev. 1 Reactor Vessel Helds 4-12 PRR-5 Rev. 1 Reactor Vessel neids 4-13 PRR-6 Withdrawn PRR-7 Rev. 1 Containment Atmosphere Control Helds :4-14 PRR-8 Rev. 1 RHR Heat Exchanger Nozzles ~4-15 PRR-9 Rev. 1 Reactor Vessel Nozzles .4-17 PRR-10 Rev. O RBCCH Pump Seal Coolers and 10-liter Shielded 4-18 Sample Chambers PRR-11 Rev. O Salt Service Water Pumps 4-19 PRR-12 Rev. O CRD Piping 4-20 PRR-13 Rev. O Containment Atmosphere Control Piping 4-21 PRR-14 Rev. O Relief Valves and Gages 4-22 PRR-15 Rev. 0 HPCI Turbine Exhaust Drain Line 4-23 PRR-16 Rev. O HPCI Pump Suction Piping 4-25

~

O i

PRR Index 4-2 Revision 0 l

s

RELIEF REQUEST NO. PRR-1 Rev. 3 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS Each of the Class I lines listed in Table PRR-1.1 penetrates the primary containment by means of a penetration assembly similar in design to that shown in Figure PRR-1.1.

The ASME Boller and Pressure Vessel Code,Section XI, 1980 Edition through Winter 1980 Addenda requires a surface and volumetric e.xamination of pressure retaining welds in piping > 4" and either a volumetric or surface examination for integral attachments to piping.

Relief is requested from the above mentioned code requirements on the basis of inaccessibility.

II. BASIS FOR RELIEF For plants who construction permits were issued prior to January 1, 1971, components shall meet Section XI requirements to the extent practical (see 10CFR50.55a(g)(1)). Since examination requirements for these welds did not exist at the time Pilgrim Nuclear Power Station was designed, examination accessibility was not a prime consideration. Figure PRR-1.1 clearly illustrates the design constraints which make it extremely impractical to examine the subject welds by volumetric or surface techniques. Boston Edison feels that this constitutes a basis for relief from the volumetric and surface examination requirements of Section XI.

III. ALTERNATE PROVISIONS The first accessible pipe weld outside the penetrations, listed in Table PRR-1.1, will be volumetrically examined each interval. Weld B-11-178 will be examined by a surface examination method as this is a socket weld which can not be volumetrically examined. The examinations required by IWB-5000 will be conducted on the alternate weld in accordance with the code. ~

, A VT-3 examination of the penetrations listed in table PRR-1.1 will be conducted each interval, to the extent practical.

PRR-1 Revision 3 Page 1 of 3 4-3

TABLE PRR-1.1 Line Alternate System Penetration Size Weld RHR (Shutdown X-12 20" 10-0-17 Cooling Suction) -

RHR (LPCI & Shutdown X-51A 18" 10-IA Cooling Return) '

RHR (LPCI & Shutdown X-518 18" 10-IB-14~ '

Cooling Return)

RHR (Head Spray) X-17 4" 10-HS-25 Core Spray X-16A 10" 14-A-17 X-16B 10" 14-B-17 RCIC X-53 3" 13-0-18 RWCU X-14 6" 12-0-24 SBLC X-42 1.5" B-11-178 Feedwater X-9A 18 6-A-10 X-9B 18" 6-B-8 Main Steam X-7A 20" 1-A-15 X-78 20" 1-B-15 X-7C 20" 1-C-15 X-7D 20" 1-D-15 X-8 3" 1-SD-9 HPCI X-52 10" 23-0-17 O

l PRR-1 Revision 3 -

Page 2 of 3 4-4 l

~~

kOutsid2. .

j Ccntoinmen.,

o := o Expansion Triple y .

Bellows . Flued wy" o=

Head w \, . e ,'#

w , ,

l -

Centering l Luga l -

,, _ , , ,,.rgU\ - .

g N N Nh x x x N -

i.s x x n .j p _ y\ \ \ u 1.2 to 4.2 I

{ Insula y 3

l Inacceaeible l Weld 4

1 I $xi xx x

...:.......g..

x , x,N

'. .' Y '/ y,.7""

/

N N. N \ .N N7 l N N N YA ~

. /A

} Process Pipe N ', - ..

i 1

l Guard /~

Pipe l

i

/

l Penetration Sleeve Tynical Design of Primary Containment Penetration i

i FIGURE PRR-1.1 ,

)

RELIEF REQUEST NO. PRR-2 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS Pilgrim Station has an ISI Class-1 recirculation pump in each of the two 28-inch diameter recirculation loops. These pumps function during normal reactor operation to provide forced recirculation through the core.

The ASME Boiler and Pressure Vessel Code,Section XI,1980 Edition through the Winter 1980 Addenda requires that one of these recirculation pumps be examined visually during each inspection interval. .

Specifically, the area of examination includes all pump internal pressure boundary surfaces.

As discussed in detail below, Boston Edison requests relief from the Section XI examination requirement to visually examine the recirculation pump internal surfaces on the basis of impracticality.

II. BASIS FOR RELIEF The basis for this relief request is predicated on the following two points:

1. to complete the subject examination, large expenditures of manhours and man-rem are required with essentially no compensating increase in plant safety, and

2. the structural integrity afforded by the pump casing material utilized will not significantly degrade over the lifetime of the pump.

Based on data compiled from an actual recirculation pump disassembly, it is expected that approximately 1000 man-hours and 50 man-rem exposure would be required to disassemble, inspect, and reassemble one pump.

Performing this visual examination under adverse conditions such as high dose rate (30-40 R/hr) and poor as-cast surface condition, realistically, provides little additional information as to the pump casing integrity.

PRR-2 Revision 0 Page 1 of 2 4-6

. , The recirculation pump casing material, cast stainless steel (ASTM A351-CF-8), i s widely used in the nuclear industry and has performed extremely well. The presence of some delta ferrite (typically 5% or more) imparts substantially increased resistance to intergranular stress corrosion cracking. The delta ferrite also results in improved pitting corrosion resistance in chloride containing environments.

Boston Edison feels that adequate safety margins are inherent in the basic pump design and that the health and safety of the public will not <

be adversely effected by performing the visual examination of the pump internal pressure boundary surfaces only when the pumps are required to be disassembled for maintenance.

III. ALTERNATE PROVISIONS As stated above, it is not felt that the visual examination required by Code each ten year interval is warranted. However, as standard maintenance practice dictates, when a pump of this type is disassembled for maintenance, examination of the pump internals and internal pressure boundary surfaces will be performed, to the extent practical.

i

, PRR-2 '

Revision 0 Page 2 of 2 4-7 I

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RELIEF REQUEST NO. PRR-3 Rev. 1 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS In the Class-1 system, there are 48 valves which are greater than four inches nominal pipe size. These valves vary in size, design, and manufacturer but are all manufactured from either cast stainles.s steel or carbon steel. None of the valve body casings are welded. The valves have been grouped in seven categories as shown in Table PRR 3.1.

Section XI of the ASME Code, 1980 Edition through the Hinter 1980 Addenda requires a visual examination of the internal pressure boundary surfaces of one valve in each group of valves of the same constructional design

~

and manufacturing method that perform similar functions in the system.

These examinations are required to be completed each inspection interval. (Code Category B-M-2)

Since these examinations must be met whether or not the valves have to be disassembled for maintenance, this requirement is considered impractical.

II. BASIS FOR RELIEF The requirement to disassemble primary system valves for the sole purpose of performing a visual examination of the internal pressure boundary surfaces has only a very small potential of increasing plant safety margins and a very disproportionate impact on expenditures of plant manpower and radiation exposure.

Performing these visual examinations, under such adverse conditions as high dose rates (10 R/hr) and poor as-cast surface condition, realistically, provides little additional information as to the valve casing integrity.

, For approximately 20 percent of these valves, the reactor vessel _ core

! must be completely unloaded and the vessel drained to permit disassembly i for examination.

The performance of both carbon and stainless cast valve bodies has been excellent in all BNR applications. Based on this experience and both industry and regulatory acceptance of these alloys, continued excellent service performance is anticipated.

PRR-3 Revision 1 Page 1 of 4 4-8 ,

1 l

. , A more practical approach that would essentially provide an equivalent sampling program and significantly reduced radiation exposure to plant personnel is to inspect :ne internal pressure boundary of only those valves that require disassembly of maintenance purposes. This would still provide a reasonable sampling of primary system valves and give adequate assurance that the integrity of these components is being maintained.

III. ALTERNATE PROVISIONS An examination of the 'nternal pressure boundary surfaces willibe ,

performed, to the extent practical, each time a valve is disassembled for maintenance purposes.

O PRR-3 Revision I

• Page 2 of 4 4-9

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Table PRR-3.1

. ., ,t >  :

.d .i Class'1 Valve Groups per ASME XI Category B-M-2

(

Group 1 Gate valves which are primary co'ntainment isolation valves and subject to Appendix J 1eak iate testing.!

rt

\

Valve Numoer Size Valve Numbir'

,0 Size -

!: t 2301-4 + ,

10" 1001-29E, ,

18" '

2301-5 10" 1001-47 i t 20" 2301-8 14" 1001-50 ' d 20" 1201-2 .

6" 1400-25A ,

$, 10" 1201-5 f ', 6" ' 1400-25B c 10" 1b01-29A'., ', 18" ,

. i'

e 4

Group 2 Globevalv[eswhichareprimaryconhinmenEisolationvalvesand subject td Appendix J leak rate testing. '

3 i '

Valve Number Size Valve Number S)2a 203-1A - , 20" 203-2A 20" 1 203-1B ". > ^ ' 20" 203-2B 20" 203-lC f 20" 203-2C 20" 203-10 '

20" 203-2D 20"

~

Group 3 Check valves which are primary-containment isolation valves and subject to Appendix J 1eak rate testing.

Valve Numb'ert ^

Size Valve Nor.ber '

Size 6-58A;. .,., 18" 6-62A i s 18" 6-588- c >

1, 8 " 6-62B 18" i.

I Group 4 Relief valves - at;least one is disusembled for inspection and testing during each rifueling outage.

! Valve Number ISize Valva Number Size [

203-3A 6" 203-3C 6" o 203-3B 6" 203-3D 6" i Group 5 Safety valves - at least one 1s disassembled for inspection and testing during each refuel outage.

Valve Number Size Valve Number Size 203-4A 6" 203-4B 6" PRR-3 Revision 1 Page 3 of 4 4-10

, -, -- - n _ . . _ . -- -. -_. _ _ . - - . - - -

Table PRR-3.1 continued

.O q Group 6 Check valves whicn perform as system isolation valves.

Valve Number Size. Valve Number Size 1001-68A 18" 1400-9A 10" 1001-688 18" 1400-98 10" 1201-81 6" 2301-7 14" -

Group 7 Gate valves which perform as system isolation valves. l Valve Number Size Valve Number Size 202-4A 28" 202-4B 28" 202-5A 28" 202-58 28" 6-57A 18" 6-57B 18" 1001-33A 18" 1001-33B 18" 1001-51 20" 1201-82 6" 1201-85 6" 1400-6A 10" 1400-68 10" I

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l PRR-3 Fevision 1 l Page 3 of.4 4-11 I

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. , RELIEF REQUEST NO. PRR-4 Rev. 1 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The reactor vessel is designed with one circumferential and six longitudinal welds in the core beltline region.

The ASME Boller and Pressure Vessel Coae.Section XI, 1980 Edition through Winter 1970 Addenda requires a volumetric examination of 100 percent of the length of one beltline longitudinal weld and onel beltline circumferential weld each ten year interval (Code Category B-A).

Relief is requested from the above untioned Code requirements on the basis of inaccessibility.

II. BASIS FOR RELIEF Accessibility for the examination of the entire weld lengths was not provided for in the original plant desigrt which occurred prior to the issuance of Section XI Inservice Inspection requirements. Access is sufficient to meet all Code requirements of Section XI up to and including the Summer 1975 Addenda. This requires examination of 10% of the length of each beltline longitud-inal weld and 5% of the length of .

each beltline circumferential weld.

Further examination of the beltline region welds is precluded by the close proximity of the biological shield wall and obstruction by the vessel insulation. The insulation consists of interlocking panels which were not designed to be easily removable. Furthermore, the annular dimensions between the shield wall and the insulation is not sufficient to allow direct access to personnel.

Examination of the beltline region welds from inside the vessel is

! 1mpeded by vessel internal design features. The core shroud, jet pumps, and various brackets welded to the vessel wall are not designed to be removable.

III. ALTERNATE PROVISIONS Boston Edison proposes to examine the weld lengths as specified in Category B-A of the 1974 Edition of Section XI, through and including the Summery 1975 Addenda.

In addition, a visual examination for evidence of leakage of the vessel and shield annulus area will be performed during system pressure tests, to the extent practical, in accordance with subsection INB-5000 requirements.

l PRR-4 Revision 1 Page 1 of 1 4-12 l

, RELIEF REQUEST NO. PRR-5 Rev. 1

-I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS.

The reactor pressure vessel bottom head contains seventeen circumferential and meridional welds.

Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addenda requires a volumetric examination of 100 percent of the length of one merldlonal head weld and one circu'mferential head weld each inspection interval (Code Category B-A).

Relief is requested from the above mentioncd Code requirements on the basis of inaccessibility.

II. BASIS FOR RELIEF As discussed in Relief Request PRR-4, accessibility for examination of these welds was not considered in the plant design. The configuration of the vessel support skirt attachment weld and the reactor vessel skirt insulation limits the examination of the outer circumferential weld to a one side only examination.

III. ALTERNATE PROVISIONS Boston Edison will perform a volumetric examination of the reactor vessel outer circumferential weld from one side only.

PRR-5 Revision 1 Page 1 of 1 4-13

• ' ~

RELIEF REQUEST NO. PRR-7 Rev. I I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The ASME Boiler and Pressure Vessel Code,Section XI, 1980 Edition through and including the Winter 1980 Addenda requires a surface examination on Class 2 piping welds (Category C-F) less than one half inch in nominal wall thickness.

Relief is requested from performing the surface examinations on the Containment Atmospheric Control System required by Section XI.

II. BASIS FOR RELIEF This system normally operates at a temperature of 50*F and a pressure of 1 psig. As this system is normally dry and not subjected to high temperatures and pressures, the probability for failure is remote. The Appendix J Type A integrated leak rate test required by Relief Request No. PRR-13 and the isolation valve test required by Article IWV provide sufficient assurance of system integrity.

III. ALTERNATE PROVISIONS No alternate examinations are necessary in this case.

o.

PRR-7 Revision 1 Page 1 of 1 4_14 .

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• I RELIEF REQUEST NO. PRR-8 Rev. 1 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS There are two 16" diameter nozzles in the Class-2 portion of each of the two RHR System heat exchangers that are fabricated with reinforcement saddles. These saddles are fillet welded over the actual pressure retaining nozzle to shell weld. The configuration is shown on Figure 1.

Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through Hinter 1980 Addenda requires a surface and volumetric examination of two of these four nozzle to shell welds in the inspection interval (Code Category C-B). This requirement is impractical due to inaccessibility.

II. BASIS FOR RELIEF The fabrication of these nozzle-to-shell welds precludes any type of volumetric or surface examination. The design does, however, provide additional strength at the joint and results in lower stresses at the internal weld. Integrity of these joints will be monitored by surface exams of the reinforcing plate welds.

III. ALTERNATE PROVISIONS A surface exam of the reinforcing plate welds to the nozzles and vessel will be conducted in lieu of the volumetric exams of the nozzle to vessel welds required by IWC-2500-1.

D PRR-8 Revision 1 Page 1 of 2 4-15 -

< r RHR HFAT DDIANGER N0ZZE CONFIGURATION -

Nozzle OD >

1 Reinforcing Pad Weld 7 . ,.

Gannel fil/16" Nozzle to Vessel Weld Figure 1 Relief Request PRR-8 PRR-8 Rev. 1 Page 2 of 2 4-16

T

< r RELIEF REQUEST NO. PRR-9 Rev. 1 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The reactor vessel is designed with 21 nozzle-to-vessel welds located within the biological shield wall.

The ASME Boller & Pressure Vessel Code.Section XI, 1980 Edition, Winter 1980 Addenda, Table IHB-2500-1, Category B-D, Item Number B3.90 requires that a volumetric examination of each nozzle-to-vessel weld be .

conducted. Item B3.100 requires that a volumetric examination of each nozzle inner radius section be conducted. These examinations are required to be completed each inspection interval.

II. BASIS FOR RELIEF Relief is requested from the above mentioned code requirements (Item 83.90) on the basis that 100% accessibility is not permitted due to the reactor vessel insulation / biological shield configuration. Accessibility for the examination of all nozzle-to-vessel welds was not provided for in the original plant design which occurred prior to the issuance of ASME B&PV Code,Section XI requirements.

Relief is requested from the above mentioned code requirements (Item B3.100) for nozzle NIB due to a thermocouple pad which is installed on the nozzle in the area of the required examination. The pad interferes with examination of a portion of the nozzle inner radius section.

III. ALTERNATE PROVISIONS The reactor nozzle-to-vessel welds and the nozzle inner radius on Nozzle N1B will be volumemetrically examined to the maximum extent practible.

PRR-9

• Revision 1 Page 1 of 1 4-17

r RELIEF REQUEST NO. PRR-10 I. IDENTIFICATION OF COMPONENT AND IMPRACTICAL CODE REQUIREMENT The Reactor Building Closed Cooling Water (RBCCH) system has been designated Class 3 and is designed to provide cooling for various reactor building components. A part of this system includes 4 Residual, Heat Removal (RHR) pump seal coolers and two-10 liter shielded sample chamcers.

The ASME Boiler and Pressure Vessel (B&PV) Code,Section XI, 1980 Editicn thru the Winter 1980 Addenda requires a hydrostatic test of all Class 3 pressure retaining components each ten year interval (Code Category D-C)

Relief is requested from the above mentioned code requirement for the 4-RHR pump seal coolers and the two-10 liter shielded sample chambers on the basis of exceeding a design safety allowance.

II. BASIS FOR RELIEF Thy hydrostatic test pressure of the RBCCW system is 165 PSIG which exceeds the design safety allowance of the 4-RHR pump seal coolers and the two-10 liter shielded sample chambers. ,

III. ALTERNATE PROVISIONS Boston Edision proposes that within each inspection period, a VT-2 exam be performed on the 4-RHR pump seal coolers and the two-10 liter shielded sample chambers. This VT-2 exam will be conducted during an Inservice Leakage Test as defined by the ASME B&PV Code Section XI, 1980 Edition thru the Hinter 1980 Addenda.

PRR-10 .

Revision 0 Page 1 of 1 4-18

, , RELIEF REQUEST NO. PRR-11 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The Salt Service Water (SSW) System has been designated Class 3 and provides cooling to the Reactor Building and Turbine Building Closed Cooling Water Systems. The system includes 5 pumps whose pump casings are located under water. .

The ASME Boiler and Pressure Vessel (B&PV) Code,Section XI 1980 Edition thru the Hinter 1980 Addenda requires a hydrostatic test of all Class 3 pressure retaining components each ten year interval (Code Category 0-B).

Relief is requested from the requirements to hydrostatically test the SSW pumps up to the expansion joints in the pump discharge lines on the basis of impracticality.

II. BASIS FOR RELIEF Hydrostatic test of the SSW pumps and the discharge line would require disassembly and removal of the pumps. The requirements to remove the pumps for the sole purpose of performing a test of the pressure boundary has only a very small potential of increasing plant safety margins and a disproportionate impact on expenditures of plant manpower.

III. ALTERNATE PROVISIONS VT-2 examinations of the pump discharge piping up to the expansion joints will be conducted during system inservice leakage tests once each period as defined by the ASME B&PV Code,Section XI, 1980 Edition thru the Winter 1980 Addenda.

o.

PRR-11 Revision 0 -

Page 1 of 1 4-19

F

, , RELIEF REQUEST NO. PRR-12 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The Control Rod Drive hydraulic system has been designated Class 2 and provides insert and withdraw control for 145 control rod blades.

The ASME Boller and Pressure Vessel (B&PV) Code,Section XI 1980 Edition thru the Winter 1980 Addenda requires a hydrostatic test of all Class 2 pressure retaining components each 10 year interval (Code Category C-H).

Relief is requested from the above requirement for CR0 piping from the HCU's to the reactor pressure vessel due to design configuration and impracticality.

II. BASIS FOR RELIEF Portions of the lines cannot be isolated for Class 2 hydrostatic testing due to design configuration. Isolation of the remaining piping at the hydraulic control units (HCU's) is impractical due to the large number of valves to be realigned.

III. ALTERNATE PROVISIONS The CRD hydraulic system from the reactor pressure vessel to each HCU will be tested during the Class I hydrostatic test at a pressure of 1135 psig once per interval in accordance with the ASME B&PV Code,Section XI, 1980 edition thru the Winter 1980 addenda.

7 J

B PRR-12 Revision 0 -

Page 1 of 1 4-20

RELIEF REQUEST NO. PRR-13 I. IDENTIFICATION OF COMPONENT AND IMPRACTICAL CODE REQUIREMENTS The Class 2 portions of Containment Atmospheric Control System provide a flow path for inerting, purging, and sampling of the primary containment atmosphere. -

The ASME Boiler and Pressure Vessel (B&PV) Code,Section XI, 1980 Edition thru Winter 1980 Addenda requires a hydrostatic test of all Cliss 2 pressure retaining components each ten year interval (Code Category C-H). Relief is requested from the required hydrostatic test because the Containment Atmospheric Control System (CACS) is designed for operation with air.

II. BASIS FOR RELIEF The purge and vent lines are open to the primary containment atmosphere and are unable to be isolated for hydrostatic or pneumatic testing. The sample lines can be isolated outside of containment but would require that extensive supports be added for hydrostatic testing.

III. ALTERNATE PROVISIONS The ncn-isolable portions of the CACS will be tested for integrity during the Appendix J Type A integrated leak rate test once each period. The

~ - ~

~~ -

isolable portions of the sample lines will be tested during the performance of Appendix J Type C local leak rate tests once each period.

O PRR-13 Revision 0 Page 1 of 1 4-21

' s RELIEF REQUEST NO. PRR-14 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS Most of the safety class 2 and 3 systems utilize instrumentation for monitoring of system performance. Several systems contain relief valves for over pressure protection. .

The ASME Boiler and Pressure Vessel (B&PV) Code,Section XI, 1980 Edition thru Winter 1980 Addenda requires a hydrostatic test of all Clas~s 2 and 3 pressure retaining components each 10 year interval (Code Categories C-H, D-A, D-B and D-C), Relief is requested from the above requirements on the basis of impracticality for installed instrumentation which could be over pressurized and relief valves which are removed in order to perform hydrostatic tests.

II. BASIS FOR RELIEF Some installed instruments could be damaged due to exposure to the hydrostatic test pressure. Susceptible instruments must be isolated or removed to prevent unneccesary replacement costs. Relief valves must also be removed or isolated to allow pressurization to test pressure.

III. ALTERNATE PROVISIONS A VT-2 examination will be performed on the instruments and relief valves during system inservice or functional tests once per period in accordance with the ASME B&PV Code,Section XI, 1980 Edition thru the Winter 1980 Addenda.

PRR-14 ,

Revision 0 Page 1 of 1 4-22

t. , RELIEF REQUEST NO. PRR-15

!. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The Class 2 High Pressure Coolant Injection (HPCI) Turbine Exhaust Drain System collects condensate from the turbine exhaust line, turbine casing, turbine steam rings, body drains on the stop valve and the steam chest drain. -

The turbine exhaust drain line runs from a drain pot off the.tpenty inch turbine exhaust line to the suppression pool. A one inch line runs from a tee connection on the drain line to the gland seal condenser. See Attachment I for piping configuration and-identification.

The ASME Boller and Pressure Vessel (B&PV) Code,Section XI, 1980 Edition thru Hinter 1980 Addenda requires a hydrostatic test of all Class 2 pressure retaining components each ten year interval (Code Category C-H).

Relief is requested from the above requirements for all components bounded by MO-3, CV-52, 2301-112, 2301-33, 2301-33A, and the second flange on the turbine exhaust line based on impracticality.

II. BASIS FOR RELIEF

-The 1" (reduced to 3/4") turbine casing. drain line is non isolable between the HPCI turbine and the turbine exhaust drain pot. This line prevents isolation of the following piping off the exhaust drain pot; (1) the piping from the turbine exhaust nozzle flange to the first down-stream flange, (2) the steam ring drain lines, (3) the drain lines from HO-2 and the steam chest drain line downstream of HO-1, (4) The 3/4" drain line from the exhaust drain pot to 2301-112, (5) The 1" line from the exhaust drain pot to 2301-131B, and (6) The 2" and 1" lines from the exhaust drain pot bounded by 2301-131A, 2301-33, 2301-33A and CV-32.

III. ALTERNATE PROVISIONS -

Boston Edison proposes that within each inspection period, a VT-2 exam be 6

performed on the components bounded by MO-3, CV-52, 2301-112, 2301-33, 2301-33A and the second flange on the turbine exhaust line. This VT-2 exam will be conducted during a system functional test as defined by ASME B&PV Code,Section XI, 1980 Edition thru Winter 1980 Addenda.

PRR-15 ,

Revision 0 Page 1 of 2 4-23

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10"-EB-23 Stean m upply turbine turbine trip-throttle stop-valw valve 10-2 10-1 10-3 f""

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main steam p -t ,e 2e Line "D"

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~3 seat

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• 20"-1B-23 p drains 3/4',-HB-23 turbine exhaust p ,

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() g 3 steam chest suppressidn'- lT . ll 0 HPCI drain Pool 45 turbine .

drain pot -

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3/4"-HB-23 ~ _qd N 1"-HB-23 % U7 steam drainsring V

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131B ' g casing drain 1"-HB-23 2"-HB-23 131A '

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47A ys 33A M e-34 8049 W  ; to gland seal e n h ser

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Turbine Exhaust Drain Line "F -(

v to suppression pool

• RELIEF REQUEST NO. PRR-16 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENT The High Pressure Coolant Injection (HPCI) Turbine is designed with a sixteen inch pump suction line which can take suction from either the Condensate Storage Tank (CST) or the Suppression Pool. The piping from the CST located immediately upstream of the suction 1ozzle is e~ quipped with a motor operated isolation valve (MO-6) and a check valve.(2301-20).

The ASME Boller and Pressure Vessel (B&PV) Code, Secticn XI, 1980 Edition thru Winter 1980 Addenda requires a hydrostatic test of all Class 2 pressure retaining components each ten year interval (Code Category C-H).

Relief is requested from the above mentioned code requirement for the portion of piping located between MO-6 and 2301-20 on the basis of impracticality.

II. BASIS FOR RELIEF The portion of piping between MO-6 and 2301-20 has no drain or vent valves to allow installation of a test pump and disassembly of check valve 2301-20 internals would be required to pressurize this portion of piping Design requirements for the purpose of performing Class 2 Hydrostatic test were not provided for in the original plant design which occurred prior to the issuance of Section XI inservice inspection requirements.

The requirements to disassemble a primary system valve for the sole purpose of performing a visual examination of an external pressure boundary has only a very small potential of increasing plant safety margins and a very disproportionate impact on expenditures of plant manpower and radiation exposure. ,

III. ALTERNATE PROVISIONS

\ .%

Boston Edison proposes that within each inspection period..a VT-2 exam be i

performed on the piping located between MO-6 and 2301-20. This VT-2 exam l

will be conducted during a system functional test as defined by ASME B&PV Code,Section XI, 1980 Edition thru the Winter 1980 Addenda.

l PRR-16 -

Revision 0 1 Page 1 of 1 4-25 l

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