Text

Inservice Insp Program,Interval 2,821222-921222.
	ML18130A376
Person / Time
Site:	Surry
Issue date:	09/21/1982
From:	; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML18130A377	List: ML18130A376; ML18139C062;
References
	PROC-820921, NUDOCS 8210130431
	Download: ML18130A376 (432)
	v • d • e

'--

Virginia Electric & Power Company Surry Power Station Unit 1

Inservice Inspection Program Interval 2 Dec. 22, 1982 -_Dec. 22, 1992

- NOTICE -

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RECORDS FACILITY BRANCH

Title ABSTRACT TABLE OF CONTENTS Page i

LIST OF DRAWINGS ii INTRODUCTION 1-1 INSERVICE INSPECTION PROGRAM FOR COMPONENTS 2-1 INSERVICE TESTING*PROGRAM FOR SUPPORTS 3-1 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES 4-1 INSERVICE SYSTEM PRESSURE TESTS 5-1

VIRGINIA ELECTRIC AND POWER COMPANY ABSTRACT SURRY POWER STATIONS INTERVAL 2 DECEMBER 22, 1982 to DECEMBER 22, 1992 UNIT 1 In accordance with 10CFR50.55a Surry Unit 1 is being updated to ASME Section XI, 1980 Edition with Addenda through Winter 1980. Steam generator inspections will continue to be inspected under Plant Technical Specifications. Specific reliefs are requested in accordance with 10CFR50.55a (g) (5) (iii).

The interval for which this program is applicable will commence on December 22, 1982, and end on December 22, 1992. Class 1, 2, and 3 inspections required to be completed during the first interval will be completed at the next refueling outage currently scheduled for the spring of 1983.

The ISI Program was developed employing 10 CFR 50 and Reg. Guide 1026.

Quality Groups A, B, and C are the same as ASME Classes 1, 2, and 3 respectively.

The list of drawings identifies the drawings used in developing the program.

Section 2 describes the Class 1, 2, and 3 component inspection program developed in accordance with Subsections IWB, IWC, and IWD of ASME Section XI.

Section 3 describes the testing program for components.

Section 4 describes the Class 1, 2, and 3 pump and valve inspection program developed in accordance with Subsection IWP and IWV of ASME Section XI.

Section 5 describes the system pressure test program *

i

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Unit 1 LIST OF DRAWINGS ISI BOUNDARIES 11448 FM-64A FB-4B 66A 6A 68A 68B 71A 71B 71D 72A 72B 72C 72D 72E 72F 72G 75C 75E 75G 75J

82B 83A 83B 84A 85A 86A 86B 87A 88A 88B 88C 89A 89B 90A 106C 118A 123A 123B 124A 130A 138A

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1.0 INTRODUCTION

1.1 GENERAL INFORMATION The Inservice Inspection (ISI) and Inservice Testing (IST) Programs for Surry Nuclear Power Station Unit 1 are developed in compliance with the rules and regulations of 10CFR50.55a and Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition including the Addenda through Winter 1980. Where these rules are determined to be impractical, specific relief is requested in writing.

The Inservice Inspection and Testing Programs for Class 1, 2 and 3 Components, Component Supports, Pumps, & Valves are applicable for the ten year interval beginning December 22, 1982 and ending December 22, 1992. The upcoming ten year interval is the second inspection interval for Surry Unit 1.

1.2 SYSTEM CLASSIFICATION The construction permits for Surry Units 1 and 2 were issued on June 25, 1968. At that time the ASME Boiler and Pressure Vessel Code covered only nuclear vessels. Piping, pumps, and valves were built primarily to the rules of USAS B31.1.0, therefore, the station has essentially no ASME Code Class 1, 2 or 3 designed systems. The system classifications used as a basis for the Inservice Inspection and Testing Programs are based on the requirements set forth in 10CFR50 and Regulatory Guide 1.26. Pursuant to 10CFR50 paragraph (g)

(1), inservice inspection requirements of Section XI of the ASME Code are then assigned to these components, within the constraints of existing plant design.

Flow Diagrams (FM' s) documenting the system classifications were developed to aid in the review and implementation of the subject programs .

1-1

2.0 2.1 2.1.1 INSERVICE INSPECTION PROGRAM FOR COMPONENTS PROGRAM DESCRIPTION The Inservice Inspection Program for ISI Class 1, 2 and 3. components meets the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addenda. Where these requirements are determined to be impractical, specific requests for relief have been written and included in this Section.

2.1.2 The ISI Component Program is presented in Section 2.2 in a tabular format. The components and associated requirements are listed according to ascending Code Category and Item Numbers. 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, and IWD-2500-1, for Class i, 2 and 3 components.

B. Item Number and Item Description - The Item Number and its description as listed in Tables IWB, !WC, and IWD-2500-1. All Item Numbers and only applicable item descriptions are listed for each Code Category.

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

VOL - Volumetric per IWA-2230 SUR - Surface per IWA-2220 VIS - Visual per IWA-2211, 12, 13 and 14 D. Relief Requests references either a specific relief request contained in this Section or references one of the Code allowed exemptions listed. below. If . the latter is referenced, the particular line or component has been exempted from volumetric and/or surface examination by the applicable Code paragraph.

Components exempted from examination by Code allowed exemptions will not appear in the component tables of this program in most cases.

EX IWB-1220(b), lines 1-inch nominal pipe size (n.p.s) and less EX IWB-1220(a), liquid carrying lines 2-inch n.p.s and less EX IWB-1220(a), steam carrying lines 4-inch n.p.s. and less EX IWB-1220(c), head connections, 2-inches n.p.s and less, made inaccessible by CRD penetrations 2-1

EX IWC-1220(b), components not required to operate above a temperature of 200°F or above a pressure of 275 psig.

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

n.p.s.

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

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

EX IWD-1220.2(a), integral attachments of supports and restraints in systems whose function is not required in support of reactor residual heat removal and emergency core cooling.

EX IWD-1220.2(b), integral attachments of supports and restraints where operating pressure is 275 psig or less and operating temperature is 200°F or less.

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

E. Alternate Exam lists the examination method or methods that will be performed in lieu of the required Section XI methods when relief has been requested.

F. Remarks - lists general clarification remarks.

2.1.3 The attached Inservice Inspection Plan Summary lists the applicable Class 1, 2 & 3 systems which are covered in the Inservie Inspection Program.

2-2

12122182 NUTECH/PRISIH PAGE l *

INSERVICE INSPECTION PLAN

SUMMARY

. REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :e~weo *

CATEGORY B-A ' PRESSURE RETAINING WELDS IN REACTOR VESSEL ITEM NUMBER :Bl.11 ITEM DESCRIPTION : REACTOR VESSEL CIRCUMFERENTIAL SHELL WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ------- ------- -------

RC FM-86A F-5 RPRV VOL

12/22/82 NUTECH/PRISIM PAGE 2

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :aowao *

CATEGORY B-A PRESSURE RETAINING WELDS IN REACTOR VESSEL ITEM NUMBER :Bl.12 ITEM DESCRIPTION : REACTOR VESSEL LONGITUDINAL SHELL WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES RC FM-86A F-5 RPRV VOL

12122/82 NUTE CH/PR IS IM PAGE 3

l

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :sowao *

CATEGORY B-A PRESSURE RETAINING WELDS IN REACTOR VESSEL ITEM NUMBER :Bi.21 ITEM DESCRIPTIPN : REACTOR VESSEL CIRCUMFERENTIAL HEAD WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll715l CO ORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ------- -------

RC FM-86A F-5 RPRV VOL

12122182 NUTECH/PRISIN INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 4

REVISION : 0001

CODE EDITION :aowao *

CATEGORY B-A PRESSURE RETAINING WELDS IN REACTOR VESSEL

ITEM NUMBER =Bl.30 ITEM DESCRIPTION : REACTOR VESSEL SHELL-TO-FLANGE WELD FLOI~ FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES RC FM-86A F-5 RPRV VOL

12122182 NUTECH/PRISIM PAGE 5 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001

SURRY POWER STATION UNIT l CODE EDITION :aowao *

CATEGORY B-A PRESSURE RETAINING WELDS IN REACTOR VESSEL ITEM NUMBER :Bl.40 ITEM DESCRIPTION : REACTOR VESSEL HEAD-TO-FLANGE WELD FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ------- ------ ======= -------

RC FM-86A F-5 RPRV SUR VOL

12/22182 HUTECH/PRISIM IHSERVICE IHSPECTIOH PLAH

SUMMARY

SURRY POWER STATION UHIT 1 PAGE 6

REVISION : 0001

CODE EDITION :aoweo *

CATEGORY B-B PRESS. RETAIHIHG WELDS IH VESSELS OTHER THAH RPV ITEM HUMBER :s2.11 ITEM DESCRIPTION : PRESSURIZER CIRCUMFERENTIAL SHELL-TO-HEAD WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LIHE EXAM RELIEF PROGRAM COMPOHEHT Cll715l COORD HUMBER METHOD REQUEST NOTES

-------- ------- ------- ======= -------

RC FM-86B G-6 PRZR VOL

12/22/82 NUTECH/PRISIM PAGE 7 *

*I

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION !80W80 *

CATEGORY B-B PRESS. RETAINING WELDS IN VESSELS OTHER THAN RPV ITEM NUMBER :B2.12 ITEM DESCRIPTION : PRESSURIZER LONGITUDINAL SHELL-TO-HEAD WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ======= ------ ------- =======

RC FM-86B G-6 PRZR VOL

12122182 NUTECH/PRISIM PAGE 8 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :aowao *

CATEGORY B-B PRESS. RETAINING WELDS IN VESSELS OTHER THAN RPV ITEM NUMBER :B2.40 ITEM DESCRIPTION : STEAM GENERATORSCPRIMARY SIDEJ TUBESHEET-TO-HEAD FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES RC FM-86A C-1 RCElA VOL RC FM-86A C-6 RCElB VOL RC FM-86A J-1 RCElC VOL

12/22182 NUTECH/PRISIM PAGE 9 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :sowao *

CATEGORY B-D PENET. WELDS OF NOZZLE IN VESSELS- INSPEC. PRGM. B

ITEM NUMBER :83.100 ITEM DESCRIPTION : REACTOR VESSEL NOZZLE INSIDE RADIUS SECTION FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES RC FM-86A F-5 RPRV VOL

12/22/82 NUTECH/PRISIM PAGE 10 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :aowao *

CATEGORY B-D PENET. WELDS OF NOZZLE IN VESSELS- INSPEC. PRGM. B

ITEM NUMBER :B3.90 ITEM DESCRIPTION : REACTOR VESSEL NOZZLE-TO-VESSEL WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT 111715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ------- ------ ------- -------

RC FM-86A F-5 RPRV VOL

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 11

REVISION : 0001

CODE EDITION :eoweo *

CATEGORY B-E PRESS. RETAINING PARTIAL PENET. WELDS IN VESSELS

ITEM NUMBER =64.12 ITEM DESCRIPTION : ALL VESSELS, CRD NOZZLES PARTIAL PENET. WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ------- -------

RC FM-86A F-5 RPRV VIS

12/22/82 NUTECH/PRISIM PAGE 12 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001

SURRY POWER STATION UNIT l CODE EDITION :aowao *

CATEGORY B-E PRESS. RETAINING PARTIAL PENET. WELDS IN VESSELS

ITEM NUMBER :B4.13 ITEM DESCRIPTION : ALL VESSELS, INSTR. NOZZLES PART. PENET. WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COO RD NUMBER METHOD REQUEST NOTES RC FM-86A F-5 RPRV VIS

12/22/82 NUTECH/PRISIM PAGE 13 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :80W80 *

CATEGORY B-E PRESS. RETAINING PARTIAL PENET. WELDS IN VESSELS *

- - - - ~****************

ITEM NUMBER :B4.20 ITEM DESCRIPTION : PRESSURIZER HEATER PENETRATION WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ------- ------ ------- -------

RC FM-86B G-6 PRZR VIS

12/22/82 NUTECH/PRISIM PAGE 14 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :aowao *

CATEGORY B-F PRESSURE RETAINING DISSIMILAR METAL WELDS

ITEM NUMBER =B5.lo ITEM DESCRIPTION : REACTOR VESSEL, NPS > 4" NOZZLE-SAFE END BUTT WE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ------- ------ -------

RC FM-86A E-2 RC1-2501R SUR VOL RC FM-86A C-4 RC3-2501R SUR VOL RC FM-86A F-5 RC4-2501R SUR VOL RC FM-86A C-8 RC6-2501R SUR VOL RC FM-86A H-2 RC7-2501R SUR VOL RC FM-86A K-4 RC9-2501R SUR VOL

12/22182 NUTECH/PRISIM PAGE 15 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :80W80 *

CATEGORY B-F PRESSURE RETAINING DISSIMILAR METAL WELDS

ITEM NUMBER :s5.20 ITEM DESCRIPTION : PRESSURIZER, NPS > 4" NOZZLE-SAFE END sun WE LOS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES RC FM-86B G-8 RC10-2501R SUR VOL RC FM-86B F-5 RC15-1502 SUR VOL RC FM-86B H-5 RC34-1502 SUR VOL RC FM-86B H-5 RC37-1502 SUR VOL RC FM-86B G-5 RC38-1502 SUR VOL RC FM-86B G-5 RC39-1502 SUR VOL

12/22/82 NUTECH/PRISIM PAGE 16 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :aowao *

CATEGORY B-F PRESSURE RETAINING DISSIMILAR METAL WELDS ITEM NUMBER :BS.30 ITEM DESCRIPTION : STEAM GEN., NPS > 4" NOZZLE-SAFE END BUTT WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ------- -------

RC FM-86A E-2 RC1-2501R SUR VOL RC FM-86A B-2 RC2-2501R SUR VOL RC FM-86A F-5 RC4-2501R SUR VOL RC FM-86A B-6 RC5-2501R SUR VOL RC FM-86A H-2 RC7-2501R SUR VOL RC FM-86A K-2 RC8-2501R SUR VOL

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 17

REVISION : 0001

CODE EDITION :eoweo *

CATEGORY B-G-1 PRESSURE RETAINING BOLTING > 2" IN DIAMETER

ITEM NUMBER :B6.10 ITEM DESCRIPTION : REACTOR VESSEL CLOSURE HEAD NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll715) CO ORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ------- -------

RC FM-86A F-5 RPRV SUR

12122/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 18

REVISION : 0001 *

cooE EDITION :8oW80 *

CATEGORY B-G-1 PRESSURE RETAINING BOLTING > 2" IN DIAMETER

ITEM NUMBER :B6.180 ITEM DESCRIPTIOH : PUMPS BOLTS AHO STUDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) CO ORD HUMBER METHOD REQUEST HOT ES

-------- ======= ======= ------ ------- =======

RC FM-86A A-1 RCPlA VOL RC FM-86A A-6 RCPlB VOL RC FM-86A L-1 RCPlC VOL

12122/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 19

REVISION : 0001

CODE EDITION :80W80 *

CATEGORY B-G-1 PRESSURE RETAINING BOLTING > 2" IN DIAMETER

ITEM NUMBER :B6.190 ITEM DESCRIPTION : PUMPS FLANGE SURFACE,WHEN CONNECTION DISASSEMBLE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM. RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES RC FM-86A A-1 RCPlA VIS RC FM-86A A-6 RCPlB VIS RC FM-86A L-1 RCPlC VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 20

REVISION : 0001 CODE EDITION :aowao

CATEGORY B-G-1 PRESSURE RETAINING BOLTING > 2" IN DIAMETER

ITEM NUMBER =B6.20 ITEM DESCRIPTION : REACTOR VESSEL CLOSURE STUDS,IN PLACE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ------- ------ -------

RC FM-86A F-5 RPRV VOL

12122/82 NUTECH/PRISIM PAGE 21 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :aowao *

CATEGORY B-G-1 PRESSURE RETAINING BOLTING > 2" IN DIAMETER ITEM NUMBER :B6.200 ITEM DESCRIPTION : PUMPS NUTS,BUSHINGS,AND WASHERS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ------- ------ ======= -------

RC FM-86A A-1 RCPlA VIS RC FM-86A A-6 RCPlB VIS RC FM-86A L-1 RCPlC VIS

12/22/82 NUTECH/PRISil1 PAGE 22 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY B-G-1 PRESSURE RETAINING BOLTING > 2" IN DIAMETER

ITEM NUMBER :B6.210 ITEM DESCRIPTION : VALVES BOLTS AND STUDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES RC FM-86A E-2 RC1-2501R VOL RC FM-86A C-4 RC3-2501R VOL RC FM-86A F-5 RC4-2501R VOL RC FM-86A C-8 RC6-2501R VOL RC FM-86A H-2 RC7-2501R VOL

RC FM-86A K-4 RC9-2501R VOL

12/22/82 NUTECH/PRISIM PAGE 23 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :aowso *

CATEGORY B-G-1 PRESSURE RETAINING BOLTING > 2" IN DIAMETER ITEM NUMBER :B6.220 ITEM DESCRIPTION : VALVES FLANGE SURFACE,WHEN CONNECTION DISASSEMBL FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) CO ORD NUMBER METHOD REQUEST NOTES RC FM-86A E-2 RC1-2501R VIS RC FM-86A C-4 RC3-2501R VIS RC FM-86A F-5 RC4-2501R VIS RC FM-86A C-8 RC6-2501R VIS RC FM-86A H-2 RC7-2501R VIS

RC FM-86A K-4 RC9-2501R VIS

12122182 NUTECH/PRISIM PAGE 24 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :sowao *

CATEGORY B-G-1 PRESSURE RETAINING BOLTING > 2" IN DIAMETER ITEM NUMBER :B6.230 ITEM DESCRIPTION : VALVES NUTS,BUSHINGS,AND WASHERS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ------- -------

RC FM-86A E-2 RC1-2501R VIS RC FM-86A C-4 RC3-2501R VIS RC FM-86A F-5 RC4-2501R VIS RC FM-86A C-8 RC6-2501R VIS RC FM-86A H-2 RC7-2501R VIS

RC FM-86A K-4 RC9-2501R VIS

12122182 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 25

REVISION : 0001

CODE EDITION :aowao *

CATEGORY B-G-1 PRESSURE RETAINING BOLTING > 2" IN DIAMETER

ITEM NUMBER :B6.30 ITEM DESCRIPTION : REACTOR VESSEL CLOSURE STUDS,WHEN REMOVED FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES RC FM-86A F-5 RPRV SUR VOL

12122/82 NUTECH/PRISIH PAGE 26 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :aowao *

CATEGORY B-G-1 PRESSURE RETAINING BOLTING > 2" IN DIAMETER ITEM NUMBER :B6.40 ITEM DESCRIPTION : REACTOR VESSEL THREADS IN FLANGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES RC FM-86A F-5 RPRV VOL

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 27

REVISION : 0001

CODE EDITION :aowao *

CATEGORY B-G-1 PRESSURE RETAINING BOLTING > 2" IN DIAMETER ITEM NUMBER :B6.50 ITEM DESCRIPTION : REACTOR VESSEL CLOSURE WASHERS,BUSHINGS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll715l COORD NUMBER METHOD REQUEST NOTES

========= --------

======= ======= ======= -------

RC FM-86A F-5 RPRV VIS

12/22/82 NUTECH/PRISIM PAGE 28 *

*t

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :80W80 *

CATEGORY B-G-2 PRESSURE RETAINING BOLTING <= 2" IN DIAMETER

ITEM NUMBER :B7.10 ITEM DESCRIPTION : REACTOR VESSEL BOLTS,STUDS, AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ------- ------ ------- =======

RC FM-86A F-5 RPRV VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 29

REVISION : 0001

CODE EDITION :aowao *

CATEGORY B-G-2 PRESSURE RETAINING BOLTING <= 2" IN DIAMETER

ITEM NUMBER :s1.20 ITEM DESCRIPTION : PRESSURIZER BOLTS,STUDS, AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (117151 COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ======= -------

RC FM-86B G-6 PRZR VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 30

REVISION : 0001

CODE EDITION :SOWSO *

CATEGORY B-G-2 PRESSURE RETAINING BOLTING <= 2" IN DIAMETER

ITEM NUMBER :B7.30 ITEM DESCRIPTION : STEAM GENERATORS BOLTS,STUDS,AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES RC FM-86A C-1 RCElA VIS RC FM-86A C-6 RCElB VIS RC FM-86A J-1 RCElC VIS

12/22/82 INSERVICE SURRY NUTECH/PRISIM INSPECTION POWER PLAN STATION

SUMMARY

UNIT l CODE PAGE REVISION EDITION 31

0001

80W80

CATEGORY B-G-2 PRESSURE RETAINING BOLTING <= 2" IN DIAMETER

ITEM NUMBER =B7.50 ITEM DESCRIPTION : PIPING BOLTS,STUDS,AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ------- ------ ======= -------

CH FM-88C G-6 CH93-1502 VIS CH FM-88C D-6 CH95-1502 VIS CH FM-88C A-6 CH97-1502 VIS RC FM-86A I-5 RClOS-1502 VIS RC FM-86A B-8 RCllS-1502 VIS

RC RC RC FM-86A FM-86A FM-86A B-7 C-8 B-3 RC116-1502 RC117-1502 RC129-1502 VIS VIS VIS

.RC FM-86A B-2 RC131-1502 VIS

12/22182 NUTECH/PRISIM PAGE 32 *

INSERVICE INSPECTION PLAN SUtlMARY REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :aowao *

CATEGORY B-G-2 PRESSURE RETAINING BOLTING <= 2" IN DIAMETER

ITEM NUMBER :B7.50 ITEM DESCRIPTION : PIPING BOLTS,STUDS,AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (117151 COORD NUMBER METHOD REQUEST NOTES

========= ======== ------- ------- ------ ------- -------

RC FM-86A C-3 RC132-1502 VIS RC FM-86A K-3 RC146-1502 VIS RC FM-86A K-2 RC147-1502 VIS RC FM-86A J-3 RC148-1502 VIS RC FM-86A I-3 RC44-1502 VIS

RC RC RC FM-86A FM-86A FM-86B E-3 E-8 H-5 RC45-1502 RC46-1502 RC37-1502 VIS VIS VIS RC FM-86B G-5 RC38-1502 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 33

REVISION : 0001

CODE EDITION :eowao *

CATEGORY B-G-2 PRESSURE RETAINING BOLTING <= 2" IH DIAMETER

ITEM NUMBER :B7.50 ITEM DESCRIPTION : PIPING BOLTS,STUOS,AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll715l COORD NUMBER METHOD REQUEST NOTES

=======

RC FM-86B G-5 RC39-1502 VIS

12/22/82 NUTECH/PRISIM PAGE 34 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :aowso *

CATEGORY B-G-2 PRESSURE RETAINING BOLTING <= 2" IN DIAMETER ITEM NUMBER :B7.70 ITEM DESCRIPTION : VALVES BOLTS,STUDS,AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES CH FM-88C E-2 CHl-1502 VIS CH FM-88C H-4 CHl0-1503 VIS CH FM-88C E-2 CH5-1502 VIS CH FM-88C E-2 CH68-1502 VIS CH FM-88C J-3 CH8-1502 VIS

CH CH CH FM-88C FM-88C FM-88C J-3 G-6 D-6 CH8-1503 CH93-1502 CH95-1502 VIS VIS VIS CH FM-88C A-6 CH97-1502 VIS

12/22/82 NUTECH/PRISIM PAGE 35 *

*I

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :aoweo *

CATEGORY B-G-2 PRESSURE RETAINING BOLTING <= 2" IN DIAMETER ITEM HUMBER :s1.10 ITEM DESCRIPTION : VALVES BOLTS,STUDS,AHD HUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD HUMBER METHOD REQUEST NOTES

========= --------

RC FM-86A I-5 RC105-1502 VIS RC FM-86A D-2 RC11-2501R VIS RC FM-86A A-8 RC112-1502 VIS RC FM-86A B-7 RC116-1502 VIS RC FM-86A C-8 RC117-1502 VIS

RC RC RC FM-86A FM-86A FM-86A D-7 A-2 B-3 RC12-2501R*

RC125-1502 RC129-1502 VIS VIS VIS RC FM-86A I-4 RC13-2501R VIS

12/22/82 NUTECH/PRISIM PAGE 36 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :eoweo *

CATEGORY B-G-2 PRESSURE RETAINING BOLTING <= 2" IN DIAMETER

ITEM NUMBER :B1.10 ITEM DESCRIPTION : VALVES BOLTS,STUDS,AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES RC FM-86A B-2 RC131-1502 VIS RC FM-86A C-3 RC132-1502 VIS RC FM-86A C-2 RC139-1502 VIS RC FM-86A L-2 RC141-1502 VIS RC FM-86A K-3 RC146-1502 VIS

RC RC RC FM-86A FM-86A FM-86A K-2 J-3 J-2 RC147-1502 RC148-1502 RC153-1502 VIS VIS VIS RC FM-86A A-2 RC198-1502 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 37

REVISION : 0001

CODE EDITION :aowao *

CATEGORY B-G-2 PRESSURE RETAINING BOLTING <= 2" IN DIAMETER ITEM NUMBER :B7.7o ITEM DESCRIPTION : VALVES BOLTS,STUDS,AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cl:):.715) CO ORD NUMBER METHOD REQUEST NOTES RC FM-86A A-6 RC199-1502 VIS RC FM-86A L-2 RC200-1502 VIS RC FM-86A I-3 RC44-1502 VIS RC FM-86A E-3 RC45-1502 VIS RC FM-86A E-8 RC46-1502 VIS

RC RC RC FM-86A FM-86A FM-86A C-2 B-2 B-6 RC53-1502 RC55-1502 RC56-1502 VIS VIS VIS RC FM-86A C-5 RC57-1502 VIS

12/22/82 NUTECH/PRISIM PAGE 38 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :80W80 *

CATEGORY B-G-2 PRESSURE RETAINING BOLTING <= 2" IN DIAMETER

ITEM NUMBER :B7.70 ITEM DESCRIPTION : VALVES BOLTS,STUDS,AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COO RD NUMBER METHOD REQUEST NOTES

-------- ======= ------- ------ -------

RC FM-86A I-1 RC58-1502 VIS RC FM-86A K-4 RC59-1502 VIS RC FM-86A A-7 RC60-1502 VIS RC FM-866 F-7 RC14-1502 VIS RC FM-86B F-5 RC15-1502 VIS

RC RC RC FM-866 FM-86B FM-866 I-5 H-5 G-5 RC35-1502 RC37-1502 RC38-1502 VIS VIS VIS RC FM-866 G-5 RC39-1502 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 39

REVISION : 0001

CODE EDITION :80W80 *

CATEGORY B-G-2 PRESSURE RETAINING BOLTING <= 2" IN DIAMETER ITEM NUMBER :B7.70 ITEM DESCRIPTION : VALVES BOLTS,STUDS,AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== -------

======= ------ ------- -------

RC FM-86B H-5 RC61-1502 VIS RC FM-88C E-2 CH5-1502 VIS RHR FM-87A L-5 RH16-1502 VIS RHR FM-87A D-7 RH18-1502 VIS RHR FM-87A J-5 RH23-1502 VIS

- SI SI SI FM-89B FM-89B FM-89B B-1 B-1 B-2 SI144-1502 SI145-1502 SI153-1502 VIS VIS VIS SI FM-89B B-1 SI45-1502 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 40

REVISION : 0001

CODE EDITION :80W80 *

CATEGORY B-G-2 PRESSURE RETAINING BOLTING <= 2" IN DIAMETER ITEM NUMBER :B7.70 ITEM DESCRIPTION : VALVES BOLTS,STUDS,AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES SI FM-89B C-7 SI46-1502 VIS SI FM-89B B-8 SI47-1502 VIS SI FM-898 B-2 SI48-1502 VIS SI FM-89B B-2 SI49-1502 VIS SI FM-898 I-3 SI50-1502 VIS

SI SI SI FM-89B FM-898 FM-898 C-1 D-2 D-1 SI74-1502 SI75-1502 SI85-1502 VIS VIS VIS

12122/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 41

REVISION : 0001

CODE EDITION :aowao *

CATEGORY B-H INTEGRAL ATTACHMENTS FOR VESSELS ITEM NUMBER :ss.20 ITEM DESCRIPTION : PRESSURIZER INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES RC FM-86A F-5 RPRV VOL RC FM-86B G-6 PRZR VOL

12/22/82 NUTECH/PRISIM PAGE 42 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :aowao

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER =B9.ll ITEM DESCRIPTION : PIPING CIRC. WELDS, NPS >= 4 IN.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

=== ======== ======= ======= ======= =

RC FM-86A E-2 RC1-2501R SUR VOL RC FM-86A D-2 RCll-2501R SUR VOL RC FM-86A D-7 RC12-2501R SUR VOL RC FM-86A I-4 RC13-2501R SUR VOL RC FM-86A E-2 RC16-1502 SUR VOL RC FM-86A B-1 RC17-1502 SUR VOL

12/22/82 NUTECH/PRISIM PAGE 43 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :aowso *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER :B9.ll ITEM DESCRIPTION : PIPING CIRC. WELDS, NPS >= 4 IN.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES RC FM-86A E-6 RC18-1502 SUR VOL RC FM-86A E-7 RC19-1502 SUR VOL RC FM-86A B-2 RC2-2501R SUR VOL RC FM-86A H-4 RC20-1502 SUR VOL RC FM-86A H-2 RC21-1502 SUR VOL RC FM-86A E-5 RC22-1502 SUR VOL

12122/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 44

REVISION : 0001

CODE EDITION :aowao *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING

ITEM NUMBER !B9.ll ITEM DESCRIPTION : PIPING CIRC. WELDS, NPS >= 4 IN.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ======= ------ -------

=======

RC FM-86A E-8 RC23-l502 SUR VOL RC FM-86A H-4 RC24-1502 SUR VOL RC FM-86A C-4 RC3-2501R SUR VOL RC FM-86A F-5 RC4-2501R SUR VOL RC FM-86A B-6 RC5-2501R SUR VOL RC FM-86A C-8 RC6-2501R SUR VOL

12/22/82 NUTECH/PRISIM PAGE 45 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :80W80 *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING

ITEM NUMBER :B9.ll ITEM DESCRIPTION : PIPING CIRC. WELDS, NPS >= 4 IN.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT !11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ------- ------ ------- -------

RC FM-86A H-2 RC7-2501R SUR VOL RC FM-86A K-2 RC8-2501R SUR VOL RC FM-86A K-4 RC9-2501R SUR VOL RC FM-86B G-8 RC10-2501R SUR VOL RC FM-868 F-5 RC15-1502 SUR VOL RC FM-868 H-5 RC34-1502 SUR VOL

12/22/82 NUTECH/PRISIM PAGE 46 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :80W80 *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER :B9.ll ITEM DESCRIPTION : PIPING CIRC. WELDS, NPS >= 4 IN.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (117151 COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ------- -------

RC FH-866 H-5 RC37-1502 SUR VOL RC FM-868 G-5 RC38-1502 SUR VOL RC FM-868 G-5 RC39-1502 SUR VOL RHR FM-87A I-7 RHl-1502 SUR VOL RHR FH-87A L-5 RH16-1502 SUR VOL RHR FM-87A J-5 RH23-602 SUR VOL

12122/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 47

REVISION : 0001

CODE EDITION :sOW80 *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING

ITEM NUMBER :s9.11 ITEM DESCRIPTION : PIPING CIRC. WELDS, NPS >= 4 IN.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

------ ======= -------

SI FM-86A E-6 SI48-1502 SUR VOL SI FH-89B B-1 SI144-1502 SUR VOL SI FH-89B B-1 SI145-1502 SUR VOL SI FH-89B B-2 SI153-1502 SUR VOL SI FH-89B B-1 SI45-1502 SUR VOL SI FM-89B C-7 SI46-1502 SUR VOL

12122182 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 48

REVISION : 0001

CODE EDITION :80W80 *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER =B9.ll ITEM DESCRIPTION : PIPING CIRC. WELDS, NPS >= 4 IN.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ------- -------

SI FM-89B B-8 SI47-l502 SUR VOL SI FM-89B B-2 SI49-1502 SUR VOL SI FM-89B I-3 SI50-1502 SUR VOL SI FM-89B C-1 SI74-1502 SUR VOL SI FM-89B D-1 SI85-1502 SUR VOL

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 49

REVISION : 0001

CODE EDITION :sowao *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER :s9.12 ITEM DESCRIPTION : PIPING LONG. WELDS, NPS >= 4 IN.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

=== ======== ------- ------- ------ ======= =

RC FH-86A B-2 RC2-2501R SUR VOL RC FM-86A B-6 RC5-2501R SUR VOL RC FH-86A K-2 RC8-2501R SUR VOL

12/22/82 NUTECH/PRISIM PAGE 50 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER =B9.21 ITEM DESCRIPTION : PIPING CIRC. WELDS, NPS < 4 IN.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT !11715) COORD NUMBER METHOD .REQUEST NOTES CH FM-88C E-2 CHl-1502 . SUR RC FM-86A B-7 RC116-1502 SUR RC FM-86A B-2 RC131-1502 SUR RC FM-86A C-3 RC132-1502* SUR RC FM-86A K-2 RC147-1502 SUR

RC RC RC FM-86A FM-86B FM-86B J-3 F-7 F-5 RC148-1502 RC14-1502 RClS-1502 SUR SUR SUR RC FM-86B I-5 RC35-1502 SUR

12122182 NUTECH/PRISIM PAGE 51 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :eowso *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER :B9.21 ITEM DESCRIPTION : PIPING CIRC. WELDS, NPS < 4 IN.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

========= --------

------- ------ ------- =======

RC FM-86B H-5 RC61-1502 SUR SI FM-89B C-1 SI74-1502 SUR SI FM-89B D-2 SI75-1502 SUR

12/22/82 NUTECH/PRISIM PAGE 52 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY .POWER STATION UNIT l CODE EDITION :aowao *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING

ITEM NUMBER :B9,31 ITEM DESCRIPTION : PIPING, NPS >= 4 IN. ,BRANCH PIPE CONNECTION WELD FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== -------

CH FM-88C E-2 CHl-1502 SUR VOL RC FM-86A B-7 RC116-1502 SUR SR-3 VOL RC FM-86A B-2 RC131-1502 SUR SR-3 VOL RC FM-86A K-2 RC147-1502 SUR SR-3 VOL.

RC FM-86A E-2 RC16-1502 SUR SR-3 VOL RC FM-86A B-1 RC17":"1502 SUR SR-3 VOL

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 53

REVISION : 0001

CODE EDITION :aowso *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING

ITEM NUMBER :B9.31 ITEM DESCRIPTION : PIPING, NPS >= 4 IN. ,BRANCH PIPE CONNECTION WELD FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES RC FM-86A E-6 RC18-1502 SUR SR-3 VOL RC FM-86A E-7 RC19-1502 SUR SR-3 VOL RC FM-86A H-4 RC20-1502 SUR SR-3

.)

VOL RC FM-86A H-2 RC21-1502 SUR SR-3 VOL RC FM-86A E-5 RC22-1502 SUR SR-3 VOL RC FM-86A E-8 RC23-1502 SUR SR-3 VOL

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 54

REVISION : 0001

CODE EDITION :aowao *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER :89.31 ITEM DESCRIPTION : PIPING, NPS >= 4 IN.,BRANCH PIPE CONNECTION WELD FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES RC24-1502 SUR SR-3 VOL RC10-2501R SUR SR-3 VOL RC14-1502 SUR SR-3 VOL RC15-1502 SUR SR-3 VOL RC35-1502 SUR SR-3 VOL RHl-1502 SUR SR-3 VOL

12122/82 NUTECH/PRISIM PAGE 55 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 SURRY POWER STATION UNIT l CODE EDITION :eoweo *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER :B9.32 ITEM DESCRIPTION : PIPING, NPS < 4 IN., BRANCH PIPE CONNECTION WELD FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES CH FM-88C E-2 CHS-1502 SUR CH FM-88C E-2 CH68-1502 SUR RC FM-86A I-5 RC105-1502 SUR RC FM-86A B-8 RC115-1502 SUR RC FM-86A C-8 RC121-1502 SUR

RC RC RC FM-86A FM-86A FM-86A B-3 B-3 L-2 RC125-1502 RC129-1502 RC141-1502 SUR SUR SUR RC FM-86A K-'3 RC146-1502 SUR

12122182 NUTECH/PRISIM PAGE 56 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :aowao *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER :B9.32 ITEM DESCRIPTION : PIPING, NPS < 4 IN., BRANCH PIPE CONNECTION WELD FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ------- ------ ======= -------

RC FM-86A A-2 RC198-1502 SUR RC FM-86A A-6 RC199-1502 SUR RC FM-86A L-2 RC200-1502 SUR RC FM-86A I-3 RC44-1502 SUR RC FM-86A E-3 RC45-1502 SUR

RC RC RC FM-86A FM-86A FM-86A E-8 C-2 B-2 RC46-l502 RC53-1502 RC55-1502

' SUR SUR SUR RC FM-86A B-6 RC56-1502 SUR

12122/82 NUTECH/PRISIM PAGE 57 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :aowao *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING

ITEM NUMBER :B9.32 ITEM DESCRIPTION : PIPING, NPS < 4 IN., BRANCH PIPE CONNECTION WELD FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES

========= -------- ======= ------- ------ ------- -------

RC FH-86A C-5 RC57-1502 SUR RC FH-86A I-1 RC58-1502 SUR RC FH-86A K-4 RC59-l502 SUR RC FH-86A A-7 RC60-1502 SUR

12/22182 NUTECH/PRISIM PAGE 58 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER :B9.40 ITEM DESCRIPTION : PIPING SOCKET WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COO RD NUMBER METHOD REQUEST NOTES

-------- ======= ======= ------ -------

CH FM-88C H-4 CHl0-1503 SUR CH FM-88C E-2 CH5-1502 SUR CH FM-88C E-2 CH68-1502 SUR CH FM-88C J-3 CH8-1503 SUR CH FM-88C G-4 CH9-1503 SUR

CH CH CH FM-88C FM-88C FM-88C G-6 D-6 A-6 CH93-1502 CH95-1502 CH97-1502 SUR SUR SUR RC FM-86A I-5 RC105-1502 SU~

12/22/82 NUTECH/PRISIN PAGE 59 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER :B9.40 ITEM DESCRIPTION : PIPING SOCKET WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES RC FM-86A A-8 RC112-1502 SUR RC FM-86A B-8 RC115-1502 SUR RC FM-86A C-8 RC121-1502 SUR RC FM-86A B-3 RC125-1502 SUR RC FM-86A B-3 RC129-1502 SUR

RC RC RC FM-86A FM-86A FM-86A C-3 C-2 L-2 RC132-1502 RC139-1502 RC141-1502 SUR SUR SUR RC FM-86A K-3 RC146-1502 SUR

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 60

REVISION : 0001

CODE EDITION :aowao *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER !B9.40 ITEM DESCRIPTION : PIPING SOCKET WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ------- ------ ------- -------

RC FM-86A J-3 RC148-1502 SUR RC FM-86A J-2 RC153-1502 SUR RC FM-86A A-2 RC198-1502 SUR RC FM-86A A-6 RC199-1502 SUR RC FM-86A L-2 RC200-1502 SUR

RC RC RC FM-86A FM-86A FM-86A I-3 E-3 E-8 RC44-1502 RC45-1502 RC46-1502 SUR SUR SUR RC FM-86A C-2 RC53-1502 SUR

12122182 NUTECH/PRISIM PAGE 61 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :aowao *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER :B9.4o ITEM DESCRIPTION : PIPING SOCKET WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES RC FM-86A B-2 RC55-1502 SUR RC FM-86A B-6 RC56-1502 SUR RC FM-86A C-5 RC57-1502 SUR RC FM-86A I-1 RC58-1502 SUR RC FM-86A K-4 RC59-1502 SUR

RC RC RC FM-86A FM-86B FM-86B A-7 I-5 H-5 RC60-l502 RC35-1502 RC61-1502 SUR SUR SUR SI FM-89B C-1 SI74-1502 SUR

1U2U82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

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SURRY POWER STATION UNIT 1 PAGE 62

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CODE EDITION :aowao *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING

ITEM NUMBER :e9.40 ITEM DESCRIPTION : PIPING SOCKET WELDS

FLOl4 FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM*

COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES SI FM-89B D-1 SI85-1502 SUR

12122182 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 63

REVISION : 0001

CODE EDITION :aowao *

CATEGORY B-K-1 INTEGRAL ATTACHMENTS FOR PIPING, PUMPS, AND VALVES

ITEM NUMBER :Bl0.10 ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) CO ORD NUMBER METHOD REQUEST NOTES

========= ======== ======= ======= ------ ------- -------

CH FM-88C H-4 CHl0-1503 SUR CH FM-88C E-2 CH5-1502 SUR CH FM-88C E-2 CH68-1502 SUR CH FM-88C J-3 CHS-1503 SUR CH FM-88C G-4 CH9-1503 SUR

RC RC RC FM-86A FM-86A FM-86A B-7 B-2 C-3 RC116-1502' RC131-1502 RC132-1502 SUR SUR SUR RC FM-86A K-2 RC147-1502 SUR

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :eowao *

CATEGORY B-K-1 INTEGRAL ATTACHMENTS FOR PIPING, PUMPS, AND VALVES ITEM NUMBER :Bl0.10 ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ------- ------ -------

RC FM-86A H-4 RC24-1502 SUR RC FM-86A C-2 RC53-1502 SUR RC FM-86A I-1 RC58-1502 SUR RC FM-86A K-4 RC59-1502 SUR RC FM-868 G-8 RC10-2501R SUR

RC RC RC FM-86B FM-86B FM-868 F-7 F-5 H-5 RC14-1502 RC15-1502 RC34-1502 SUR SUR SUR RC FM-86B I-5 RC35-1502 SUR

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :aowao *

CATEGORY B-K-1 INTEGRAL ATTACHMENTS FOR PIPING, PUMPS, AND VALVES ITEM NUMBER :010.10 ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES RC FH-86B H-5 RC61-1502 SUR RHR FM-87A I-7 RHl-1502 SUR RHR FH-87A L-5 RH16-1502 SUR RHR FM-87A J-5 RH23-602 SUR

., SI SI SI FH-89B FM-89B FM-89B B-2 B-1 C-7 SI153-1502 SI45-1502 SI46-l502 SUR SUR SUR SI FH-898 B-8 SI47-1502 SUR

12122/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 66

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CODE EDITION :eoweo *

CATEGORY B-K-1 INTEGRAL ATTACHMENTS FOR PIPING, PUMPS, AND VALVES

ITEM NUMBER :Bl0.20 ITEM DESCRIPTION : PUMPS INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COO RD NUMBER METHOD REQUEST NOTES RC FM-86A A-1 RCPlA SUR RC FM-86A A-6 RCPlB SUR RC FM-86A L-1 RCPlC SUR

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 67

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CODE EDITION :aowao *

CATEGORY B-L-2 PUMP CASINGS ITEM NUMBER :s12.10 ITEM DESCRIPTION : PUMP CASING WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ------- ------ ======= -------

RC FM-86A A-1 RCPlA VOL RC FM-86A A-6 RCPlB VOL RC FM-86A L-1 RCPlC VOL

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY B-L-2 PUMP CASINGS

ITEM NUMBER :B12.20 ITEM DESCRIPTION : PUMP CASING FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES

=== -------- ------- ------- ------ ------- =

RC FH-86A A-1 RCPlA VIS RC FM-86A A-6 RCPlB VIS RC FM-86A L-1 RCPlC VIS

69 *

12/22/82 NUTECH/PRISIM PAGE

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :eoweo *

CATEGORY B-M-2 VALVE BODIES

ITEM NUMBER :Bl2.40 ITEM DESCRIPTION : VALVES, VALVE BODY EXCEEDING 4 IN. NOMINAL PIPE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= --------

RC FM-86A E-2 RC1-2501R VIS SR-1 RC FM-86A D-2 RC11-2501R VIS SR-1 RC FM-86A D-7 RC12-2501R VIS SR-1 RC FM-86A I-4 RC13-2501R VIS SR-1 RC FM-86A C-4 RC3-2501R VIS SR-1

RC RC RC FM-86A FM-86A FM-86A F-5 H-2 K-4 RC4-2501R RC7-2501R RC9-2501R VIS VIS VIS SR-1 SR-1 SR-1 RC FM-86B H-5 RC37-1502 VIS SR-1

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REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY B-M-2 VALVE BODIES ITEM HUMBER :s12.4o ITEM DESCRIPTION : VALVES, VALVE BODY EXCEEDING 4 IN. NOMINAL PIPE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll7l5) COORD HUMBER METHOD REQUEST NOTES

-------- ------- ------- ------ ------- =======

RC FM-86B 6-5 RC38-l502 VIS SR-1 RC FM-86B G-5 RC39-l502 VIS SR-1 RC FM-86B H-5 RC6-2501R VIS SR-1 RHR FM-87A I-7 RHl-1502 VIS SR-1 RHR FH-87A L-5 RH16-l502 VIS SR-1

RHR SI SI FM-87A FM-86A FM-86A J-5 E-7 H-4 RH23-602 RC19-l502 RC20-l502 VIS VIS VIS SR-1 SR-1 SR-1 SI FM-86A H-2 RC2l-l502 VIS SR-1

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SUMMARY

REVISION : 0001 *

SURRY POl~ER STATION UNIT 1 CODE EDITION :80W80 *

CATEGORY B-M-2 VALVE BODIES

ITEM NUMBER :Bl2.40 ITEM DESCRIPTION : VALVES, VALVE BODY EXCEEDING 4 IN. NOMINAL PIPE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ -------

=======

SI FM-86A E-5 RC22-1502 VIS SR-1 SI FM-86A E-8 RC23-l502 VIS SR-1 SI FM-86A H-4 RC24-1502 VIS SR-1 SI FM-898 B-1 SI144-1502 VIS SR-1 SI FM-89B B-1 SI145-1502 VIS SR-1

SI SI SI FM-89B FM-89B FM-898 B-2 B-1 C-7 5!153-1502 SI45-1502 SI46-1502 VIS VIS VIS SR-1 SR-1 SR-1 SI FM-898 B-8 SI47-1502 VIS SR-1

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SURRY POWER STATION UNIT 1 PAGE 72

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CODE EDITION :80W80 *

CATEGORY B-M-2 VALVE BODIES

ITEM HUMBER :Bl2.40 ITEM DESCRIPTION : VALVES, VALVE BODY EXCEEDING 4 IN. NOMINAL PIPE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT !11715) COORD NUMBER METHOD REQUEST NOTES

-------- ======= ------- ------ ======= -------

SI FM-89B B-2 SI48-1502 VIS SR-1 SI FM-89B B-2 SI49-1502 VIS SR-1 SI FM-89B I-3 SI50-1502 VIS SR-1

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SUMMARY

POWER STATION UNIT 1 PAGE REVISION :

73 0001 CODE EDITION :sowao *

CATEGORY B-N-1 INTERIOR OF REACTOR VESSEL

ITEM NUMBER :Bl3.10 ITEM DESCRIPTION : REACTOR VESSEL, VESSEL INTERIOR FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ------- -------

RPV FM-86A F-5 RPRV VIS

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :eoweo *

CATEGORY B-N-3 REMOVABLE CORE SUPPORT STRUCTURES

ITEM NUMBER :Bl3.30 ITEM DESCRIPTION : REACTOR VESSELCPWR) CORE SUPPORT STRUCTURE FLml FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

-------- ======= ------- ------- -------

RPV FM-86A F-5 RPRV VIS

12/22/82 HUTECH/PRISIM IHSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 75

REVISION : 0001

CODE EDITION !80W80 *

CATEGORY B-0 PRESSURE RETAINING WELDS IH CONTROL ROD HOUSINGS

ITEM HUMBER :Bl4.10 ITEM DESCRIPTION : REACTOR VESSEL WELDS IH CRD HOUSING FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT !11715) COORD HUMBER METHOD REQUEST NOTES

======== ------- ------- ------ ======= =======

RC FM-86A F-5 RPRV VOL

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SUMMARY

UNIT 1 CODE PAGE REVISION EDITION 76 0001

aowso

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :Bl5.10 ITEM DESCRIPTION : REACTOR VESSEL PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ======= ------ ------- -------

RC FM-86A F-5 RPRV VIS

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :aowao *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :Bl5.ll ITEM DESCRIPTION : REACTOR VESSEL PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUM.BER METHOD REQUEST NOTES

------ ------- =======

RC FM-86A F-5 RPRV VIS

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :Bl5.20 ITEM DESCRIPTION : PRESSURIZER PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES RC FM-86B G-6 PRZR VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 79

REVISION : 0001

CODE EDITION !80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :BlS.21 ITEM DESCRIPTION : PRESSURIZER PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES RC FM-86B G-6 PRZR VIS

_'./

12122/82 NUTECH/PRISIM PAGE 80 *

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :ao~l80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :sis.so ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll71Sl CO ORD NUMBER METHOD REQUEST NOTES CH FM-88C E-2 CH1-1S02 VIS CH FM-88C H-4 CH10-lS03 VIS CH FM-88C D-S CH103-1S02 VIS CH FM-88C C-6 CH10S-1S02 VIS CH FM-88C F-6 CH106-1S02 VIS

CH CH CH FM-88C FM-88C FM-88C F-6 I-6 I-6 CH108-1S02

CH109-1S02 CHlll-lS02 VIS VIS VIS CH FM-88C D-S CH1S-1S02 VIS

12122/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

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SURRY POl4ER STATION UNIT l PAGE 81

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CODE EDITION :80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :Bl5.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COM PONE HT !117151 COORD HUMBER METHOD REQUEST HOT ES

======== ------- ------- ------ ------- -------

CH FM-88C B-7 CH261-1502 VIS CH FM-88C B-7 CH262-1502 VIS CH FM-88C E-7 CH263-1502 VIS CH FM-88C E-7 CH264-1502 VIS CH FM-88C H-7 CH265-1502 VIS

CH CH CH FM-88C FM-88C FM-88C H-7 E-2 J-3 CH266-1502 CH5-1502 CH8-1503 VIS VIS VIS CH FM-88C F-4 CH9-1503 VIS

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INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :sis.so ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll71Sl COORD NUMBER METHOD REQUEST NOTES CH FH-88C G-6 CH93-1S03 VIS CH FH-88C D-6 CH9S-1S03 VIS CH FH-88C A-6 CH97-1S03 VIS RC FH-86A E-2 RC1-2S01R VIS RC FM-86A K-1 RC100-1S02 VIS

RC RC RC FH-86A FM-86A FH-86A K-1 K-1 J-2 RC101-1S02 RC102-1S02 RC103-1S02 VIS VIS VIS RC FH-86A I-S RC10S-1S02 VIS

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SUMMARY

UNIT 1 CODE PAGE REVISION EDITION 83

0001

80W80

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :Bl5.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll 715) COO RD NUMBER METHOD REQUEST NOTES RC FM-86A I-5 RC106-1502 VIS RC FM-86A D-2 RC11-2501R VIS RC FM-86A A-8 RC112-1502 VIS RC FM-86A A-8 RC113-2501R VIS RC FM-86A A-8 RC114-1502 VIS

RC RC RC FM-86A FM-86A FM-86A B-8 B-7 C-8 RC115-1502 RC116-1502 RC117-1502 VIS VIS VIS RC FM-86A c.:.7 RC118-1502 VIS I

le I

12/22/82 NUTECH/PRISIM PAGE 84 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER !615.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COO RD NUMBER METHOD REQUEST NOTES RC FM-86A C-"8 RC119-2501R VIS RC FM-86A* D-7 RC12-2501R VIS RC FM-86A D'-8 RC120-l502 VIS RC FM-86A C-7 RC121-1502 VIS RC FM-86A C-7 RC122-1502 VIS

RC RC RC FM-86A FM-86A FM-86A C-7 C-6 A-2 RC123-1502 RC124-1502 RC125-1502 VIS VIS VIS RC FM-86A B-4 RC126-1502 VIS

12122182 NUTECH/PRISIM INSERVICE INSPECTION PLAN SUMMARr SURRY POWER STATION UNIT 1 PAGE 85

REVISION : 0001

CODE EDITION :80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :Bl5.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ======= ------- ------ ------- -------

RC FM-86A A-3 RC127-1502 VIS RC FM-86A B-3 RC128-2501R VIS RC FM-86A B-3 RC129-1502 VIS RC FM-86A I-4 RC13-2501R VIS RC FM-86A A-4 RC130-1502 VIS

RC RC RC FM-86A FM-86A FM-86A B-2 C-3 C-4 RC131-1502 RC132-1502 RC133-2501R VIS VIS VIS RC FM-86A C-3 RC134-1502 VIS

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :Bl5.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) CO ORD NUMBER METHOD REQUEST NOTES

-------- ------- ------- ------ ======= -------

RC FM-86A D-3 RC135-1502 VIS RC FM-86A C-2 RC136-1502 VIS RC FM-86A C-2 RC137-1502 VIS RC FM-86A C-2 RC138-1502 VIS RC FM-86A C-2 RC139-1502 VIS

RC RC RC FM-86A FM-86A FM-86A A-8 L-2 K-3 RC140-1502 RC141-1502 RC142-1502 VIS VIS VIS RC FM-86A L-3 RC143-1502 VIS

12/22/82 NUTECH/PRISIM PAGE 87 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :sis.so ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( ll71S) COORD NUMBER METHOD REQUEST NOTES

======== ------- ======= ------ ------- -------

RC FM-86A K-3 RC144-2501R VIS RC FM-86A K-3 RC145-1502 VIS RC FM-86A K-3 RC146-1502 VIS RC FM-86A K-2 RC147-1502 VIS RC FM-86A J-3 RC148-1502 VIS

RC RC RC FM-86A FM-86A FM-86A J-3 J-3 J-4 RC149-1502 RC151-2501R RClS2-lS02 VIS VIS VIS RC FM-86A J-2 RC1S3-l502 VIS

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :sis.so ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (1171Sl COORD NUMBER METHOD REQUEST NOTES

-------- ======= ------- ------ ======= =======

RC FM-86A J-2 RC1S4-1502 VIS RC FM-86A J-2 RC155-1S02 VIS RC FM-86A J-2 RC1S6-1502 VIS RC FM-86A E-2 RC16-1502 VIS RC FM-86A J-4 RC161-1S02 VIS

RC RC RC FM-86A FM-86A FM-86A H-3 I-2 D-2 RC162-1S02 RC163-1S02 RC165-1S02 VIS VIS VIS RC FM-86A E-7 RC166-1502 VIS

I e

I

12/22/82 NUTECH/PRISIM PAGE 89

I I * *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER !Bl5.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES RC FM-86A B-1 RC17-1502 VIS RC FM-86A D-6 RC172-1502 VIS RC FM-86A G-5 RC173-1502 VIS RC FM-86A E-6 RC18-1502 VIS RC FM-86A E-7 RC19-1502 VIS

RC RC RC FM-86A FM-86A FM-86A A-2 A-6 B-2 RC198-1502 RC199-1502 RC2-2501R VIS VIS VIS RC FM-86A H-4 RC20-1502 VIS

12122182 NUTECH/PRISIM PAGE 90 *

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :sis.so ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( ll 71S) COORD NUMBER METHOD REQUEST NOTES

------ ======= -------

RC FM-86A L-2 RC200-lS02 VIS RC FM-86A H-2 RC21-1S02 VIS RC FM-86A E-S RC22-1S02 VIS RC FM-86A E-8 RC23-1S02 VIS RC FM-86A H-4 RC24-1S02 VIS

RC RC RC FM-86A FM-86A FM-86A C-4 F-5 I-3 RC3-2S01R RC4-2S01R RC44-1S02 VIS VIS VIS RC FM-86A E-3 RC4S-1S02 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 91

REVISION : 0001

CODE EDITION :eoW80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :sis.so ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll71S) COORD NUMBER METHOD REQUEST NOTES RC FM-86A E-8 RC46-1S02 VIS RC FM-86A E-2 RC47-1S02 VIS RC FM-86A E-7 RC48-1S02 VIS RC FM-86A H-2 RC49-1S02 VIS RC FM-86A B-6 RCS-2S01R VIS

RC RC RC FM-86A FM-86A FM-86A C-2 B-2 B-6 RCS3-1S02 RCSS-1S02 RCS6-1S02 VIS VIS VIS RC FM-86A C-S RCS7-1S02 VIS

12122182 NUTECH/PRISIM PAGE 92 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :80W80 *

- - - - ~*******************************************

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :Bl5.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ======= ------ ------- -------

RC FM-86A I-1 RC58-1502 VIS RC FM-86A K-4 RC59-1502 VIS RC FM-86A C-8 RC6-2501R VIS RC FM-86A A-7 RC60-1502 VIS RC FM-86A D-3 RC63-1502 VIS

RC RC RC FM-86A FM-86A FM-86A D-8 I-3 H-2 RC64-1502 RC65-1502 RC7-2501R VIS VIS VIS RC FM-86A K-2 RC8-2501R VIS I*

12122/82 NUTECH/PRISil1 PAGE 93 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :aowao *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :sis.so ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 1171S) COO RD NUMBER METHOD REQUEST NOTES

======== ======= ------- ------ ------- =======

RC FM-86A K-4 RC9-2S01R VIS RC FM-86A B-1 RC92-1S02 VIS RC FM-86A B-1 RC93-1S02 VIS RC FM-86A B-1 RC94-1S02 VIS RC FM-86A C-2 RC9S-1S02 VIS

RC RC RC FM-86A FM-86A FM-86A B-6 B-6 B-6 RC96-1S02 RC97-1S02 RC98-1S02 VIS VIS VIS RC FM-86A C-6 RC99-1S02 VIS

12/22182 NUTECH/PRISIM PAGE 94 *

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS *

- - - - ~*************************

ITEM NUMBER :Bl5.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

=======

RC FM-86B G-8 RC10-2501R VIS RC FM-868 F-7 RC14-1502 VIS RC FM-868 F-5 RC15-1502 VIS

. RC FM-86B F-5 RC225-1502 VIS RC FM-86B F-7 RC226-1502 VIS

RC RC RC FM-868 FM-86B FM-86B 6-6 6-6 H-6 RC227-1502 RC228-1502 RC229-1502 VIS VIS VIS RC FM-86B H-6 RC230-1502 VIS

12122/82 NUTECH/PRISIM PAGE 9S *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY 8-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :sis.so ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (1171Sl COO RD NUMBER METHOD REQUEST NOTES RC FM-868 F-4 RC2S-1S02 VIS RC FM-868 G-4 RC26-1S02 VIS RC FM-868 G-4 RC27-1S02 VIS RC FM-868 H-S RC34-1S02 VIS RC FM-868 H-S RC37-1S02 VIS

RC RC RC FM-868 FM-868 FM-868 G-S G-S H-6 RC38-1S02 RC39-1S02 RCS0-1S02 VIS VIS VIS RC FM-868 I-S RCS1-1S02 VIS

12122/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 96

REVISION : 0001

CODE EDITION :80W80 *

- - - - ~*************************************

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :sis.so ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 1171Sl COORD NUMBER METHOD REQUEST NOTES

========= ======== ======= -------

RC FM-868 H-S RC61-1S02 VIS RC FM-868 D-S RC66-1S02 VIS RC FM-868 F-S RC67-1S02 VIS RHR FM-87A I-7 RH1-1S02 VIS RHR FM-87A L-S RH16-1S02 VIS

RHR SI SI FM-87A FM-898 FM-89B L-S B-6 B-8 RH17-1S02 SI39-1S02 SI4-1S02 VIS VIS VIS SI FM-898 E-7 SI40-1S02 VIS

12/22/82 NUTECH/PRISIM IHSERVICE INSPECTION PLAN

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SURRY POWER STATION UNIT 1 PAGE 97

REVISION : 0001

CODE EDITION :80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

- - - - ><;..:.

ITEM NUMBER :Bl5.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (117151 COORD HUMBER METHOD REQUEST NOTES

======== ------- ------- ------ ------- -------

SS FM-82B C-1 SS1-ICH9 VIS SS FM-82B C-2 SS100-ICN9 VIS SS FM-82B C-2 SS101-ICN9 VIS SS FM-82B C-2 SS102-ICN9 VIS SS FM-82B C-2 SS103-ICH9 VIS

SS SS SS FM-82B FM-82B FM-82B C-1 C-2 C-2 SS2-ICH9 SS3-ICN9 SS4-ICN9 VIS VIS VIS SS FM-82B C-2 SS5-ICN9 VIS I

~

*----~------ - -- -

121221S2 NUTECH/PRISIM. PAGE 9S *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :SOWSO *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :Bl5.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ======= ------ ======= =======

CH FM-SSC E-2 CHl-1502 VIS CH FM-SSC H-4 CHl0-1503 VIS CH FM-SSC D-5 CH103-l502 VIS CH FM-SSC C-6 CH105-1502 VIS CH FM-SSC F-6 CH106-l502 VIS

CH CH CH FM-SSC FM-S8C FM-88C F-6 I-6 I-6 CH108-l502 CH109-1502 CHlll-1502 VIS VIS VIS CH FM-88C 0-5 CH15-1502 VIS

12/22182 NUTECH/PRISIM PAGE 99 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 cooE EDITION :eoweo *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :Bl5.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ======= ------ -------

CH FM-88C B-7 CH261-1502 VIS CH FM-88C B-7 CH262-1502 VIS CH FM-88C E-7 CH263-1502 VIS CH FM-88C E-7 CH264-1502 VIS CH FM-88C H-7 CH265-1502 VIS

CH CH CH FM-88C FM-88C FM-88C H-7 E-2 J-3 CH266-1502 CH5-1502 CHS-1503 VIS VIS VIS CH FM-88C F-4 CH9-1503 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 100

REVISION : 0001.

CODE EDITION :eoweo *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :B15.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ------- ------ ------- -------

CH FM-88C 6-6 CH93-1503 VIS CH FM-88C D-6 CH95-1503 VIS CH FM-88C A-6 CH97-1503 VIS RC FM-86A E-2 RC1-2501R VIS RC FM-86A K-1 RCl00-1502 VIS

RC RC RC FM-86A FM-86A FM-86A K-1 K-1 J-2 RClOl-1502 RC102-1502 RC103-1502 VIS VIS VIS RC FM-86A I-5 RC105-1502 VIS

12/22/82 NUTECH/PRISIM PAGE 101 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :B15.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES RC FM-86A I-5 RC106-1502 VIS RC FM-86A D-2 RC11-2501R VIS RC FM-86A A-8 RC112-1502 VIS RC FM-86A A-8 RC113-2501R VIS RC FM-86A A-8 RC114-1502 VIS

RC RC RC FM-86A FM-86A FM-86A B-8 B-7 C-8 RC115-1502 RC116-1502 RC117-1502 VIS VIS VIS RC FM-86A C-7 RC118-1502 VIS

12122/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 102

REVISION : 0001

CODE EDITION !80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :B1s.s1 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

-------- ======= ------- ------ ======= -------

RC FM-86A C-8 RC119-2501R VIS RC FM-86A D-7 RC12-2501R VIS RC FM-86A D-8 RC120-1502 VIS RC FM-86A C-7 RC121-1502 VIS RC FM-86A C-7 RC122-1502 VIS

RC RC RC FM-86A FM-86A FM-86A C-7 C-6 A-2 RC123-1502 RC124-1502 RC125-1502 VIS VIS VIS RC FM-86A B-4 RC126-1502 VIS

j

12122/82 NUTECH/PRISIM PAGE 103 * ~

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :aowao *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER =Bl5.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT !11715) CO ORD NUMBER METHOD REQUEST NOTES

.-<i RC FM-86A A-3 RC127-1502 VIS .,

~

RC FM-86A B-3 RC128-2501R VIS *1 RC FM-86A B-3 RC129-1502 VIS RC FM-86A I-4 RC13-2501R VIS RC FM-86A A-4 RC130-1502 VIS

RC RC RC FM-86A FM-86A FM-86A B-2 C-3 C-4 RC131-1502 RC132-1502 RC133-2501R VIS VIS VIS RC FM-86A C-3 RC134-1502 VIS

12/22/82 NUTECH/PRISIM PAGE 104 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :aowao *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :B1s.s1 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ------- ------ ------- =======

RC FM-86A D-3 RC135-1502 VIS RC FM-86A C-2 RC136-1502 VIS RC FM-86A C-2 RC137-1502 VIS RC FM-86A C-2 RC138-1502 VIS RC FM-86A C-2 RC139-1502 VIS

RC RC RC FM-86A FM-86A FM-86A A-8 L-2 K-3 RC140-1502 RC141-1502 RC142-1502 VIS VIS VIS RC FM-86A L-3 RC143-1502 VIS

12/22/82 HUTECH/PRISIM PAGE 105 *

IHSERVICE IHSPECTIOH PLAH

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UHIT l CODE EDITION :aowao *

CATEGORY B-P ALL PRESSURE RETAIHIHG COMPOHEHTS

ITEM HUMBER !815.51 ITEM DESCRIPTION : PIPING PRESSURE RETAIHIHG BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LIHE EXAM RELIEF PROGRAM COMPOHEHT (11715) COORD HUMBER METHOD REQUEST HOT ES

========= -------- -------

------ ======= -------

RC FH-86A K-3 RC144-2501R VIS RC FH-86A K-3 RC145-1502 VIS RC FM-86A K-3 RC146-1502 VIS RC FH-86A K-2 RC147-1502 VIS RC FM-86A J-3 RC148-1502 VIS

RC RC RC FM-86A FM-86A FM-86A J-3 J-3 J-4 RC149-l502 RC151-2501R RC152-1502 VIS VIS VIS RC FM-86A J-2 RC153-1502 VIS

12122182 NUTECH/PRISIN INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 106

REVISION : 0001

cooE EDITION :aowso *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :Bl5.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES RC FM-86A J-2 RC154-1502 VIS RC FM-86A J-2 RC155-1502 VIS RC FM-86A J-2 RC156-1502 VIS RC FM-86A E-2 RC16-1502 VIS I ., RC RC RC FH-86A FM-86A FM-86A J-4 H-3 I-2 RC161-1502 RC162-1502 RC163-1502 VIS VIS VIS RC FM-86A D-2 RC165-1502 VIS RC FM-86A E-7 RC166-1502 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 107

REVISION : 0001

CODE EDITION :aowao *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :Bl5.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) CO ORD NUMBER METHOD REQUEST NOTES

------- ======= ------ ======= -------

RC FM-86A B-1 RC17-1502 VIS RC FM-86A D-6 RC172-1502 VIS RC FM-86A G-5 RC173-1502 VIS RC FM-86A E-6 RC18-l502 VIS RC FM-86A E-7 RC19-l502 VIS

RC RC RC FM-86A FM-86A FM-86A A-2 A-6 B-2 RC198-l502 RC199-l502 RC2-2501R VIS VIS VIS RC FM-86A H-4 RC20-1502 VIS

12/22/82 NUTECH/PRISIM PAGE 108 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :s15.51

!TEN DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOl4 SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ------- -------

RC FM-86A L-2 RC200-1502 VIS RC FM-86A H-2 RC21-1502 VIS RC FM-86A E-5 RC22-1502 VIS RC FM-86A E-8 RC23-1502 VIS RC FM-86A H-4 RC24-1502 VIS

RC RC RC FM-86A FM-86A FM-86A C-4 F-5 I-3 RC3-2501R RC4-2501R RC44-1502 VIS VIS VIS RC FM-86A E-3 RC45-1502 VIS

12122/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 109 REVISION : 0001

CODE EDITION :aowao *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER !Bl5.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COO RD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ------- -------

RC FM-86A E-8 RC46-1502 VIS RC FM-86A E-2 RC47-1502 VIS RC FM-86A E-7 RC48-1502 VIS RC FM-86A H-2 RC49-1502 VIS RC FM-86A B-6 RC5-2501R VIS

RC RC RC FM-86A FM-86A FM-86A C-2 B-2 B-6 RC53-1502 RC55-1502 RC56-1502 VIS VIS VIS RC FM-86A C-5 RC57-1502 VIS

12122/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POl~ER STATION UNIT l PAGE 110

REVISION : 0001

CODE EDITION :80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :Bl5.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll715J COORD NUMBER METHOD REQUEST NOTES RC FM-86A I-1 RC58-1502 VIS RC FH-86A K-4 RC59-l502 VIS RC FM-86A C-8 RC6-2501R VIS RC FM-86A A-7 RC60-1502 VIS RC FM-86A D-3 RC63-1502 VIS

RC RC RC FM-86A FM-86A FM-86A D-8 I-3 H-2 RC64-1502 RC65-1502 RC7-2501R VIS VIS VIS RC FM-86A K-2 RC8-2501R VIS

12122/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 111

REVISION : 0001

CODE EDITION :aowao *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :Bl5.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COO RD NUMBER METHOD REQUEST NOTES

=== -------- ------- ======= ------ ------- =

RC FM-86A K-4 RC9-2501R VIS RC FM-86A B-1 RC92-1502 VIS RC FM-86A B-1 RC93-l502 VIS RC FM-86A B-1 RC94-1502 VIS RC FM-86A C-2 RC95-1502 VIS

RC RC RC FM-86A FM-86A FM-86A B-6 B-6 B-6 RC96-1502 RC97-1502 RC98-1502 VIS VIS VIS RC FM-86A C-6 RC99-1502 VIS

12122/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l CODE PAGE 112

REVISION : 0001

EDITION :80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :B15.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= ======== ------- ------- ------ ------- -------

RC FM-866 G-8 RC10-2501R VIS RC FM-866 F-7 RC14-1502 VIS RC FM-866 F-5 RC15-1502 VIS RC FM-866 F-5 RC225-1502 VIS RC FM-866 F-7 RC226-1502 VIS

RC RC RC FM-866 FM-866 FM-86B G-6 G-6 H-6 RC227-1502 RC228-1502 RC229-1502 VIS VIS VIS RC FM-86B H-6 RC230-1502 VIS

12/22/82 NUTECH/PRISIM PAGE 113 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :aowao *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

12/22/82 NUTECH/PRISIN PAGE 114 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :Bl5.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== ======= ------- ------ -------

=======

RC FM-866 H-5 RC61-1502 VIS RC FM-86B D-5 RC66-1502 VIS RC FM-86B F-5 RC67-1502 VIS RHR Ft1-87A I-7 RHl-1502 VIS RHR FM-87A L-5 RH16-1502 VIS

RHR SI SI FM-87A FM-89B FM-89B L-5 B-6 B-8 RH17-1502 SI39-1502 SI4-1502 VIS VIS VIS SI FM-896 E-7 SI40-1502 VIS le

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 115

REVISION : 0001

CODE EDITION :aoweo *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :Bl5.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES SS FM-82B C-1 SS1-ICN9 VIS SS FM-82B C-2 SS100-ICN9 VIS SS FM-82B C-2 SS101-ICN9 VIS SS FM-82B C-2 SS102-ICN9 VIS SS FM-82B C-2 . SS103-ICN9 VIS

SS SS SS FM-82B FM-82B FM-826 C-1 C-2 C-2 SS2-ICN9 SS3-ICN9 SS4-ICN9 VIS VIS VIS SS FM-826 C-2 SS5-ICN9 VIS

12/22/82 NUTECH/PRISIM PAGE 116 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :aowao *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER !Bl5.60 ITEM DESCRIPTION : PUMPS PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COO RD NUMBER METHOD REQUEST NOTES

=== -------- ======= ======= ------ ------- =

RC FM-86A A-6 RC-P-lA VIS RC FM-86A A-6 RC-P-lB VIS RC FM-86A A-6 RC-P-lC VIS

12/22/82 NUTECH/PRISIM PAGE 117

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001

SURRY POWER STATION UNIT 1 CODE EDITION :aowao *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :Bl5.61 ITEM DESCRIPTION : PUMPS PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

========= ======== ------- ------- ------ ======= -------

RC FM-86A A-6 RC-P-lA VIS RC FM-86A A-6 RC-P-lB VIS RC FM-86A A-6 RC-P-lC VIS

12122/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 118

REVISION : 0001

CODE EDITION :80W80 *

CATEGORY C-A PRESSURE RETAINING WELDS IN PRESSURE VESSELS

ITEM NUMBER :ci.10 ITEM DESCRIPTION : PRESSURE VESSELS SHELL CIRCUMFERENTIAL WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES CH FM-72A F-4 CHE4 VOL CH FM-88B G-3 CH El VOL CH FM-886 C-2 CHE2 VOL CH FM-886 J-1 CHFL2 VOL SR-4 CH FM-886 E-3 CHFL3 SUR

CH CH CH FM-886 FM-886 FM-886 E-3 E-3 H-2 CHFL4A CHFL4B CHTK2 VOL VOL VOL CH FM-88C F-2 CHE3 VOL

12/22/82 NUTECH/PRISIM PAGE 119 *1

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :aowao *

CATEGORY C-A PRESSURE RETAINING WELDS IN PRESSURE VESSELS ITEM NUMBER :cl.10 ITEM DESCRIPTION : PRESSURE VESSELS SHELL CIRCUMFERENTIAL WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== ======= ======= ------ ------- -------

MS FM-64A. A-2 RCElA VOL MS FM-64A A-4 RCElB VOL MS FM-64A A-6 RCElC VOL RHR FM-87A K-2 RHElA VOL RHR FM-87A K-3 RHElB VOL

12/22/82 NUTECH/PRISIM PAGE 120 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :80W80 *

CATEGORY C-A PRESSURE RETAINING WELDS IN PRESSURE VESSELS ITEM NUMBER :ci.20 ITEM DESCRIPTION : PRESSURE VESSELS HEAD CIRCUMFERENTIAL WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cl1715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ======= ======= ------ ======= -------

CH FM-72A F-4 CHE4 VOL CH FM-88B G-3 CH El VOL CH FM-88B C-2 CHE2 VOL CH FM-88B J-1 CHFL2 VOL SR-4 CH FM-88B E-3 CHFL3 VOL

CH CH MS FM-88B FM-888 FM-64A E-3 E-3 A-6 CHFL4A CHFL4B RCElC VOL VOL VOL RHR FM-87A K-2 RHElA VOL

12/22/82 NUTECH/PRISIM PAGE 121 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :eoweo *

CATEGORY C-A PRESSURE RETAINING WELDS IN PRESSURE VESSELS

ITEM NUMBER :ci.20 ITEM DESCRIPTION : PRESSURE VESSELS HEAD CIRCUMFERENTIAL WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= ======== ------- ------- ------ ------- -------

RHR FM-87A K-3 RHElB VOL

12122182 NUTECH/PRISIM PAGE 122

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001

SURRY POWER STATION UNIT 1 CODE EDITION :eowao *

CATEGORY C-A PRESSURE RETAINING WELDS IN PRESSURE VESSELS

ITEM NUMBER :ci.30 ITEM DESCRIPTION : PRESSURE VESSELS TUBESHEET-TO-SHELL WELD FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ======= -------

CH FM-88C F-2 CHE3 VOL MS FM-64A A-2 RCElA VOL MS FM-64A A-4 RCElB VOL MS FM-64A A-6 RCEIC VOL

12122/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 CODE PAGE 123

REVISION : 0001

EDITION :sowao *

CATEGORY C-B PRESSURE RETAINING WELDS IN NOZZLE VESSELS

ITEM NUMBER :c2.10 ITEM DESCRIPTION : PRESS. VESSELS,NOZ. IN VESSELS <= 1/2" NOM. THIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= ======== ======= ------- ------ ------- -------

CH FM-72A F-4 CHE4 SUR CH FM-88B G-3 CHEl SUR CH FM-88B C-2 CHE2 SUR CH FM-88B J-1 CHFL2 SUR

,. CH RHR RHR FM-88B FM-87A FM-87A E-3 K-2 K-3 CHFL3 RHElA RHElB SUR SUR SUR SR-2 SR-2

12122/82 NUTECH/PRISIM PAGE 124 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :aowao *

CATEGORY C-B PRESSURE RETAINING WELDS IN NOZZLE VESSELS ITEM NUMBER :c2.20 ITEM DESCRIPTION : PRESS. VESSELS,NOZ. IN VESSELS > 1/2" NON. THICK FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll715) COORD NUMBER METHOD REQUEST NOTES FW FM-64A A-2 RCElA VOL FW FN-64A A-4 RCElB VOL FW FN-64A A-6 RCElC VOL NS FM-64A A-2 RCElA VOL NS FN-64A A-4 RCElB VOL

NS FN-64A A-6 RCElC VOL

12/22/82 NUTECH/PRISIM PAGE 125 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY *POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY C-C INTEGRAL ATTACH. - VESSELS,PIPING,PUMPS, & VALVES

ITEM NUMBER :c3.10 ITEM DESCRIPTION : PRESSURE VESSELS INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES CH FM-886 G-3 CH El SUR CH FM-886 C-2 CHE2 . SUR Cl:f .FM-888 J-1 CHFL2 SUR CH FM-886 E-3 CHFL3 SUR CH FM-886 E-3 CHFL4A SUR

CH CH RHR FM-886 FM-886 FM-87A E-3 H-2 K-2 CHFL4B CHTK2 RHElA SUR SUR SUR RHR FM-87A K-3 RHElB SUR

12/22/82 NUTECH/PRISIM PAGE 126 *1

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITiON :eowao *

CATEGORY C-C INTEGRAL ATTACH. - VESSELS,PIPING,PUMPS, & VALVES ITEM NUMBER :c3.40 ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

=== -------- ------- ======= ------ ======= =

FW FM-68A B-3 WFPD13-60l SUR FW FM-68A D-2 WFPD17-601 SUR MS FM-64A A-2 SHPl-601 SUR MS FM-64A A-5 SHP2-601 SUR MS FM-64A B-3 SHP22-601 SUR

MS MS MS FM-64A FM-64A Fl1-64A C-5 B-7 A-6 SHP23-60l SHP24-60l SHP3-60l SUR SUR SUR MS FM-64A D-2 SHP45-601 SUR

12/22/82 NUTECH/PRISIH PAGE 127 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :soweo *

CATEGORY C-C INTEGRAL ATTACH. - VESSELS,PIPING,PUNPS, & VALVES

ITEM NUMBER :c3.40 ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT 111715) COORD NUMBER METHOD REQUEST NOTES MS FM-64A D-4 SHP46-601 SUR NS FM-64A D-6 SHP47-601 SUR RHR FH-87A E-4 RH19-602 SUR SI FM-89A A-4 SI152-l502 SUR SI FM-89B B-1 SI144-1502 SUR

SI SI SI FN-89B FM-89B FM-89B B-1 B-2 B-2 SI145-1502 SI153-1502 SI48-1502 SUR SUR SUR SI FM-89B B-2 SI49-1502 SUR

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 128

REVISION : 0001 CODE EDITION :eowso *

CATEGORY C-C INTEGRAL ATTACH. - VESSELS,PIPING,PUMPS, & VALVES ITEM NUMBER :c3.40 ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ======= ------ -------

=======

SI FM-89B I-3 SIS0-1502 SUR

12/22/82 NUTECH/PRISIM PAGE 129

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY C-D PRESSURE RETAINING BOLTING > 2" IN DIAMETER ITEM NUMBER :c4.30 ITEM DESCRIPTION : PUMPS BOLTS AND STUDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ------- ------ -------

CH FM-888 D-7 CHPlA VOL CH FM-88B E-7 CHPlB VOL CH FM-888 G-7 CHPlC VOL

12122/82 NUTECH/PRISIM PAGE 130 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY PO~IER STATION UNIT l CODE EDITION :aowao *

CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER :cs.11 ITEM DESCRIPTION : PIPING CIRC. WELDS <= 1/2 IN. NOM. WALL THICKNES FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll715l COORD NUMBER METHOD REQUEST NOTES MS FM-64A C-4 SDHV4-601 SUR MS FM-64A B-3 SHP22-601 SUR MS FM-64A C-5 SHP23-601 SUR MS FM-64A B-7 SHP24-601 SUR MS FM-64A C-3 SHP37-601 SUR

MS MS MS FM-64A FM-64A FM-64A B-4 C-6 D-2 SHP38-601 SHP39-601 SHP45-601 SUR SUR SUR MS FM-64A D-4 SHP46-601 SUR

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 131

REVISION : 0001 CODE EDITION :aowao *

CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING

ITEM NUMBER :c5.ll ITEM DESCRIPTION : PIPING CIRC. WELDS <= 1/2 IN. NOM. WALL THICKNES FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (117151 COORD NUMBER METHOD REQUEST NOTES

========= ======== ------- ------- ------ ------- -------

MS FM-64A D-6 SHP47-60l SUR RHR FM-87A D-3 RHl0-602 SUR RHR FM-87A E-5 RH12-602 SUR RHR FM-87A E-5 RH12-604 SUR

,. RHR RHR RHR FM-87A FM-87A FM-87A I-5 D-7 E-4 RH14-602 RH18-602 RH19-602 SUR SUR SUR RHR FM-87A E-7 RH2-602 SUR RHR FM-87A J-5 RH23-602 SUR

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 132

REVISION : 0001

CODE EDITION :aowao

CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING

ITEM NUMBER :c5.ll ITEM DESCRIPTION : PIPING CIRC. WELDS <= 1/2 IN. NOM. WALL THICKNES FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ------- -------

RHR FM-87A B-6 RH4-602 SUR RHR FM-87A D-6 RH5-602 SUR RHR FM-87A A-5 RH6-602 SUR RHR FH-87A C-4 RH7-602 SUR RHR FM-87A A-3 RH8-602 SUR

RHR RS RS FM-87A FM-84A FM-84A B-3 B-7 F-6 RH9-602 RSl-153 RSl0-153 SUR SUR SUR RS FM-84A D-7 RS2-153 SUR

*--------~--------------------------------------- -- - -.- - - -

12122/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 133 **

REVISION : 0001

CODE EDITION :80W80 *

CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING

ITEM NUMBER :c5.11 ITEM DESCRIPTION : PIPING CIRC. WELDS <= 1/2 IN. NOH. WALL THICKNES FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll 715) CO ORD NUMBER METHOD REQUEST NOTES

========= --------

------- ------ ------- =======

RS FM-84A F-6 RS9-153 SUR SI FM-896 B-2 SI48-l502 SUR SI FM-896 B-2 SI49-1502 SUR

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 134

REVISION : 0001 CODE EDITION :aowao

CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING

ITEM NUMBER :c5.21 ITEM DESCRIPTION : PIPING CIRC. ~IELDS > 1/2" NOM. WALL THICKNESS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

------- ------- ------ ------- =======

FW FM-68A B-3 WFPD13-601 SUR VOL FW FM-68A D-2 WFPD17-601 SUR VOL FW FM-68A D-5 WFPD9-601 SUR VOL MS FM-64A A-2 SHPl-601 SUR VOL MS FM-64A A-5 SHP2-601 SUR VOL MS FM-64A B-3 SHP22-601 SUR VOL

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 135

REVISION : 0001 CODE EDITION :80W80

CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING

ITEM NUMBER :c5.21 ITEM DESCRIPTION : PIPING CIRC. WELDS > 1/2" NOM. WALL THICKNESS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== ======= ------- ------ ------- -------

MS FM-64A C-5 SHP23-601 SUR VOL MS FM-64A B-7 SHP24-601 SUR VOL MS FM-64A A-6 SHP3-601 SUR VOL SI FM-89A A-4 SI152-1502 SUR VOL SI FM-89B B-1 SI144-1502 SUR VOL SI FM-896 B-1 SI145-1502 SUR VOL

12/22/82 HUTECH/PRISIM IHSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 136

REVISIOH : 0001

CODE EDITION :aowao *

CATEGORY C-F PRESSURE RETAINING WELDS IH PIPING

ITEM HUMBER :c5.21 ITEM DESCRIPTION : PIPING CIRC. WELDS > 1/2" HOM. WALL THICKNESS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD HUMBER METHOD REQUEST HOT ES

========= -------- ------- ======= ------ ------- -------

SI FM-89B B-2 SI153-1502 SUR VOL SI FM-89B B-2 SI48-1502 SUR VOL SI FM-896 6-2 SI49-1502 SUR VOL SI FM-896 I-3 SI50-1502 SUR VOL

12/22/82 NUTECH/PRISIH PAGE 137 *

!NSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001

SURRY POWER STATION UNIT 1 CODE EDITION :eoweo *

CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER :c5.22 ITEM DESCRIPTION : PIPING LONG. WELDS > 1/2" NOM. WALL THICKNESS FL0!4 FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ======= ------ ======= -------

MS FM-64A A-2 SHPl-601 SUR VOL MS FM-64A A-5 SHP2-601 SUR VOL MS FM-64A B-3 SHP22-601 SUR VOL MS FM-64A C-5 SHP23-601 SUR VOL MS FH-64A B-7 SHP24-601 SUR VOL HS FM-64A A-6 SHP3-601 SUR VOL

12/22/82 NUTECH/PRISIM INSERV!CE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 138

REVISION : 0001

CODE EDITION :80W80 *

CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING

ITEM NUMBER :c5.31 ITEM DESCRIPTION : PIPING CIRCUMFERENTIAL WELD,PIPE BRANCH CONNECT!

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ======= ======= ------ ======= -------

MS FM-64A B-3 SHP22-601 SUR MS FM-64A C-5 SHP23-601 SUR MS FM-64A B-7 SHP24-601 SUR MS FM-64A C-3 SHP37-601 SUR MS FM-64A B-4 SHP38-601 SUR

MS MS MS FM-64A FM-64A FM-64A C-6 D-2 D-4 SHP39-601 SHP45-601 SHP46-601 SUR SUR SUR MS FM-64A D-6 SHP47-601 SUR

12122182 INSERVICE SURRY NUTECH/PRISIM INSPECTION PLAN

SUMMARY

POWER STATION UNIT l PAGE 139

REVISION : 0001 CODE EDITION :80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.10 ITEM DESCRIPTION : PRESSURE VESSELS,PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll715J COORD NUMBER METHOD REQUEST NOTES

-------- ------- ------- ------ ======= -------

CH FM-72A F-4 CHE4 VIS CH FM-888 G-3 CHE! VIS Cl:I FM-888 C-2 CHE2 VIS CH FM-888 J-1 CHFL2 VIS CH FM-888 E-3 CHFL3 VIS

CH CH CH FM-888 FM-888 FM-888 E-3 E-3 H-2 CHFL4A CHFL4B CHTK2 VIS VIS VIS MS FM-64A A-2 RCElA VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 140 **

REVISION : 0001

CODE EDITION :aowao *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.10 ITEM DESCRIPTION : PRESSURE VESSELS,PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

=== ======== ------- ------- ------ ------- =

MS FM-64A A-4 RCElB VIS MS FM-64A A-6 RCElC VIS RHR FM-87A K-2 RHElA VIS RHR FM-87A K-3 RHElB VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 141

REVISION : 0001

CODE EDITION :80W80 *

CATEGORY C-H . ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.11 ITEM DESCRIPTION : PRESSURE VESSELS,PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

=== ======== ======= ------- ------ ------- =

CH FM-72A F-4 CHE4 VIS CH FM-88B G-3 CH El VIS CH FM-886 C-2 CHE2 VIS CH FM-886 J-1 CHFL2 VIS CH FM-88B E-3 CHFL3 VIS

CH CH CH FM-886 FM-886 FM-886 E-3 E-3 H-2 CHFL4A CHFL46 CHTK2 VIS VIS VIS HS FM-64A A-2 RCElA VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 142

REVISION : 0001

CODE EDITION :eoweo *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.11 ITEM DESCRIPTION : PRESSURE VESSELS,PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- -------

=======

MS FM-64A A-4 RCElB VIS MS FM-64A A-6 RCElC VIS RHR FM-87A K-2 RHElA VIS RHR FM-87A K-3 RHElB VIS

12/22/82 NUTECH/PRISIM PAGE 143 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001

SURRY . POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES BO FM124A B-5 WGCB-601 VIS BO FM124A A-2 WGCBl-601 VIS BO FM124A A-4 WGCB2-601 VIS BO FM124A A-5 WGCB3-601 VIS CH FM-88A C-1 CH25-152 VIS

CH CH CH FM-88A FM-88A FM-888 E-2 B-2 F-3 CH29-152 CH32-152 CHl00-152 VIS VIS VIS CH FM-88B A-6 CHll-1503 VIS

12/22/82 NUTECH/PRISIM PAGE 144

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- -------

CH FM-88B H-3 CH112-152 VIS CH FM-88B E-5 CH113-l503 VIS CH FM-88B F-3 CH117-l52 VIS CH FM-88B F-3 CH118-l52 VIS CH FM-88B I-2 CH119-l52 VIS

CH CH CH FM-88B FM-88B FM-88B A-6 H-2 I-1 CH12-l503 CH120-152 CH121-152 VIS VIS VIS CH FM-88B C-1 CH125-152 VIS

12122182 NUTECH/PRISIM PAGE 145 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY C-'H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll715) COORD NUMBER METHOD REQUEST NOTES

=======

CH FM-88B A-7 CH13-1503 VIS CH FM-88B H-2 CH163-152 VIS CH FM-886 I-3 CH164-152 VIS CH FM-88B G-3 CH165-152 VIS CH FM-88B B-7 CH167-1503 VIS

CH CH CH FM-888 FM-888 FM-888 B-8 F-7 D-7 CH17-152 CH18-152 CH187-1503 VIS VIS VIS CH FM-888 F-7 CH188-1503 VIS

12/22182 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 146

REVISION : 0001 CODE EDITION :80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll715) COORD NUMBER METHOD REQUEST NOTES

========= --------

CH FM-88B G-7 CH189-1503 VIS CH FM-88B H-7 CH19-152 VIS CH .fM-88B H-2 CH190-152 VIS CH FM-886 F-4 CH191-152 VIS CH FM-888 D-3 CH192-152 VIS

CH CH CH FM-88B FM-888 FM-886 K-1 H-6 F-2 CH193-152 CH196-152 CH199-152 VIS VIS VIS CH FM-88B F-6 CH2-1503 VIS

12/22/82 NUTECH/PRISIN PAGE 147 **

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :eoW80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll715J COORD NUMBER METHOD REQUEST NOTES

========= -------- -------

======= ------ ------- -------

CH FM-888 D-6 CH20-1503 VIS CH FM-88B H-7 CH201-152 VIS CH FM-88B F-7 CH202-152 VIS CH FM-88B E-7 CH203-152 VIS CH FM-886 6-8 CH204-152 VIS

CH CH CH FM-888 FM-888 FM-886 C-8 C-8 D-8 CH205-152 CH206-152 CH207-1503 VIS VIS VIS CH FM-888 F-8 CH208-1503 VIS

12122/82 NUTECH/PRISIM PAGE 14a *

INSERVICE INSPECTION PLAN

SUMMARY

. REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY C-H . ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES

========= ======== ------- ------- ------ -------

=======

CH FM-886 H-8 CH209-1503 VIS CH FM-888 J-4 CH211-152 VIS CH FM-888 J-4 CH212-152 VIS CH FM-886 H-6 CH22-1503 VIS CH FM-888 D-8 CH224-1503 VIS I

I

CH CH CH FM-886 FM-888 FM-888 E-8 G-8 F-2 CH225-1503 CH226-1503 CH23-152 VIS VIS VIS CH FM-886 B-4 CH231-1503 VIS

12/22/82 NUTECH/PRISIM PAGE 149 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES

-------- ------- ------- ------ ------- =======

CH FM-88B F-1 CH234-152 VIS CH FM-88B F-2 CH236-152 VIS CH FM-88B H-2 CH237-152 VIS CH FM-88B G-3 CH238-152 VIS CH FM-88B E-2 CH239-152 VIS

CH CH CH FM-88B FM-888 FM-888 H-2 A-6 H-6 CH24-152 CH276-1503 CH3-l503 VIS VIS VIS CH FM-888 I-3 CH58-152 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 150

REVISION : 0001

CODE EDITION :80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES

========= ======== ------- ======= ------ -------

CH FM-88B I-3 CH59-152 VIS CH FM-88B H-2 CH67-152 VIS CH FM-88B D-5 CH69-1503 VIS CH FM-88B C-2 CH7-602 . VIS CH FM-88B E-6 CH70-1503 VIS

CH CH CH FM-88B FM-88B FM-88B G-6 E-7 H-3 CH71-1503 CH72-152 CH73-152 VIS VIS VIS CH FM-88B B-6 CH74-1503 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PlAH

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 151

REVISION : 0001

CODE EDITION :eoweo *

CATEGORY C-H All PRESSURE RETAINING COMPONENTS

ITEM NUMBER !C7.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ------- ------ ======= -------

CH FM-88B B-6 CH76-1503 VIS CH FM-88B B-7 CH77-1503 VIS CH FN-88B F-2 CH78-152 VIS CH FM-88B D-6 CH80-1503 VIS CH FN-88B D-6 CH81-1503 VIS

CH CH CH FN-88B FN-88B FN-88B E-1 E-5 B-6 CH87-152 CH89-1503 CH90-1503 VIS VIS VIS CH FM-88B A-6 CH91-1503 VIS

12/22/82 NUTECH/PRISIN INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 152

REVISION : 0001

CODE EDITION :aoweo *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPIHG, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COO RD NUMBER METHOD REQUEST NOTES

========= -------- ------- -------

CH FM-88B B-3 CH99-l52 VIS CH FM-88C E-2 CHl-1502 VIS CH FM-88C E-5 CHlOl-1502 VIS CH FM-88C H-5 CH102-l502 VIS CH FM-88C D-5 CH103-l502 VIS

CH CH CH FM-88C FM-88C FM-88C H-7 I-6 H-4 CH106-l502 CHl09-l502 CH122-l52 VIS VIS VIS CH FM-88C B-3 CH123-l502 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 153

REVISION : 0001

COD.E EDITION :aowao *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c?.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (117151 CO ORD NUMBER METHOD REQUEST NOTES

========= ======== ======= ======= ------ ------- -------

CH FM-88C E-4 CH124-152 VIS CH FM-88C A-5 CH14-1502 VIS CH FM-88C F-2 CH1502 VIS CH FM-88C C-5 CH16-1502 VIS CH FM-88C B-4 CH214-152 VIS

CH CH CH FM-88C FM-88C FM-88C D-4 G-4 C-5 CH215-152 CH216-152 CH217-152 VIS VIS VIS CH FM-88C F-5 CH218-152 VIS

12/22/82 NUTECH/PRISIM PAGE 154 *'

!NSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :aowao *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c7.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ======= ------- =======

CH FM-88C I-4 CH219-152 VIS CH FM-88C B-3 CH223-1502 VIS CH FM-88C H-2 CH232-602 VIS CH FM-88C I-3 CH233-602 VIS CH FM-88C E-3 CH240-1502 VIS

CH CH CH FM-88C FM-88C FM-88C E-2 I-2 E-2 CH5-1502 CH6-602 CH68-1502 VIS VIS VIS CH FM-88C G-3 CH79-1503 VIS

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CATEGORY C-H , ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= --------

======= ------- ------ ------- -------

CH FM-88C I-3 CH8-1503 VIS CH FM-88C F-2 CH82-1502 VIS CH FM-88C G-3 CH83-1502 VIS CH FM-88C H-2 CH85-602 VIS CH FM-88C H-2 CH86-602 VIS

CH CH CH FM-88C FM-88C FM-88C H-7 E-7 B-7 CH92-1503 CH94-1503 CH96-1503 VIS VIS VIS CH FM-88C B-5 CH98-1502 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES cs FM-84A I-3 CSl-153 VIS cs FM-84A K-1 CS14-153 VIS cs FM-84A L-1 CS19-152 VIS cs FM-84A .I-3 CS2-153 VIS cs FM-84A C-2 CS22-153 VIS cs FM-84A C-1 CS23-153 VIS cs FM-84A K-2 CS26-153 VIS cs FM-84A J-3 CS28-153 VIS cs FM-84A J-3 CS29-153 VIS

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SURRY POWER STATION UNIT l CODE EDITION :eoweo *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COO RD NUMBER METHOD REQUEST NOTES

========= ======== ------- ------- ------ ------- -------

cs FM-84A C-2 CS3-153 VIS cs FM-84A E-2 CS33-153 VIS cs FM.,-84A H-4 CS34-153 VIS cs FM-84A G-3 CS35-153 VIS cs FM-84A H-3 CS36-152 VIS

cs cs cs FM-84A FM-84A FM-84A E-2 H-2 H-3 CS4-153 CSS-152 CS6-152 VIS VIS VIS cs FM-84A 6-2 CS74-152 VIS

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SURRY POWER STATION UNIT l CODE EDITION !80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES cs FM-84A F-2 CS75-152 VIS cs FM-84A H-2 CS76-152 VIS cs FM-84A G-2 CS77-152 VIS cs FM-84A G-3 CS8-152 VIS FW FM-68A D-3 WFPD13-601 VIS

FW FW MS FM-68A FM-68A FM-64A D-2 D-5 C-4 WFPD17-601 WFPD9-601 SDHVl-601 VIS VIS VIS MS FM-64A C-5 SDHV2-601 VIS

/.

- - - - "¥'~***********************

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SURRY POWER STATION UNIT l CODE EDITION :sowao *

CATEGORY C-H ALL PRESSURE RETAINING* COMPONENTS

ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES MS FM-64A C-6 SDHV3-601 VIS MS FH-64A C-4 SDHV4-601 VIS MS FM-64A D-4 SHPD6-601 VIS HS FM-64A E-7 SHPD7-601 VIS MS FM-64A D-5 SHPD8-601 VIS

MS MS MS FM-64A FM-64A FM-64A A-2 A-5 C-2 SHPl-601 SHP2-601 SHP22-601 VIS VIS VIS MS FM-64A C-5 SHP23-601 VIS

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REVISION : 0001

SURRY POWER STATION UNIT 1 CODE EDITION :eoweo *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES MS FM-64A C-6 SHP24-601 VIS MS FM-64A A-6 SHP3-601 VIS MS FM-64A C-3 SHP37-601 VIS MS FM-64A B-4 SHP38-60l VIS MS FM-64A C-6 SHP39-60l VIS

MS MS MS FM-64A FM-64A FM-64A D-2 D-4 D-6 SHP45-601 SHP46-601 SHP47-601 VIS VIS VIS MS FM-64A B-2 SSVl-601 VIS

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SURRY PmlER STATION UNIT 1 CODE EDITION :aowao *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

-------- ======= ------ ------- -------

MS FM-64A B-6 SSVll-601 VIS MS FM-64A B-6 SSV12-601 VIS MS FM-64A C-6 SSV13-601 VIS MS FM-64A C-6 SSV14-601 VIS MS FM-64A C-6 SSV15-601 VIS

MS MS MS FM-64A FM-64A FM-64A B-2 C-2 C-2 SSV2-601 SSV3-601 SSV4-601 VIS VIS VIS MS FM-64A C-2 SSV5-601 VIS

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SURRY POWER STATION UNIT l CODE EDITION :eo~l80 *

CATEGORY C-H , ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 117151 COORD NUMBER METHOD REQUEST NOTES

======== ======= ======= ------ ------- -------

MS FM-64A B-4 SSV6-601 VIS MS FM-64A B-4 SSV7-601 VIS MS FM-64A C-4 SSV8-601 VIS MS FM-64A C-4 SSV9-601 VIS MS FM64AC -4 SSVl0-601 VIS

RHR RHR RHR FM-87A FM-87A FM-87A C-6 D-6 D-3 RHPlA RHPlB RHl0-602 VIS VIS VIS RHR FM-87A G-6 RHll-602 VIS

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SURRY POWER STATION UNIT l CODE EDITION :soWSO *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ======= -------

------ ------- =======

RHR FM-87A E-5 RH12-602 VIS RHR FM-87A I-4 RH13-602 VIS RHR FM-87A I-5 RH14-602 VIS RHR FM-87A D-7 RH18-602 VIS RHR FM-87A E-4 RH19-602 VIS

RHR RHR RHR FM-87A FM-87A FM-87A E-7 C-5 I-5 RH2-602 RH21-602 RH22-602 VIS VIS VIS RHR FM-87A J-5 RH23-602 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COO RD NUMBER METHOD REQUEST NOTES

========= ======== ------- ======= ------ ------- -------

RHR FM-87A C-7 RH24-602 VIS RHR FM-87A C-7 RH25-602 VIS RHR FM-87A G-3 RH3-602 VIS RHR FM-87A B-6 RH4-602 VIS RHR FM-87A D-6 RH5-602 VIS

RHR RHR RHR FM-87A FM-87A FM-87A B-7 D-7 A-5 RH51-602 RH52-602 RH6-602 VIS VIS VIS RHR FM-87A C-4 RH7-602 VIS

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- - - - ~~************************************************************

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cl1715l CO ORD NUMBER METHOD REQUEST NOTES

========= ======== ======= ======= ------ ======= -------

RHR FM-87A A-3 RH8-602 VIS RHR FM-87A B-3 RH9-602 VIS RS FM-84A B-7 RSl-153 VIS RS FM-84A F-6 RSl0-153 VIS RS FM-84A D-4 RSU-153 VIS

RS RS RS FM-84A FM-84A FM-84A E-4 H-6 G-8 RS12-153 RS13-153 RS14-153 VIS VIS VIS RS FM-84A I-8 RS15-153 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORO NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ------- -------

RS FM-84A 0-7 RS2-153 VIS RS FM-84A A-2 RS20-153 VIS RS FM-84A B-2 RS21-153 VIS RS FM-84A 0-2 RS22-153 VIS RS FM-84A E-2 RS23-153 VIS

RS RS RS FM-84A FM-84A FM-84A A-4 B-4 E-8 RS3-153 RS4-153 RS7-153 VIS VIS VIS RS FM-84A E-8 RS8-153 VIS

- - - - ~****************************************************************************************

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SURRY POWER STATION UNIT 1 PAGE 167 REVISION : 0001

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) CO ORD NUMBER METHOD REQUEST NOTES

=== -------- ------- ------- ------ ------- =

RS FM-84A F-6 RS9-153 VIS SI FM-89A E-8 CL153 *VIS SI FM-89A F-4 Sl102-152 VIS SI FM-89A G-8 Sl106-153 VIS SI FM-89A F-8 Sl107-153 VIS

SI SI SI FM-89A FM-89A FM-89A G-8 G-5 I-6 Sl108-153 SI13-153 SI130-152 VIS VIS VIS SI FM-89A J-4 SI131-152 VIS

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SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

------- ======= ------ ------- -------

SI FM-89A B-7 SI132-153 VIS SI FM-89A C-8 SI133-ICN9 VIS SI FM-89A E-7 SI134-ICN9 VIS SI FM-89A D-8 SI135-ICN9 VIS SI FM-89A E-7 SI136-ICN9 VIS

SI SI SI FM-89A FM-89A FM-89A F-7 E-8 H-7 SI137-153 SI138-ICN9 SI139-ICN9 VIS VIS VIS SI FM-89A G-8 SI140-ICN9 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

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SURRY POWER STATION UNIT l PAGE 169 *

. REVISION : 0001

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CATEGORY C-H , ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) 'COORD NUMBER METHOD REQUEST NOTES

======== -------

======= ------ ------- -------

SI FM-89A H-7 SI141-ICN9 VIS SI FM-89A F-5 SI148-153 VIS SI FM-89A F-5 SI149-153 VIS SI FM-89A D-5 Sil50-153 VIS SI FM-89A D-6 SI151-153 VIS

SI SI SI FM-89A FM-89A FM-89A A-4 C-6 E-6 SI152-1502 SI16-153 SI160-153 VIS VIS VIS SI FM-89A D-6 SI17-152 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ======= ------ ------- -------

SI FM-89A E-6 SI18-152 VIS SI FM-89A E-6 SI19-152 VIS SI FM-89A G-1 SI20-l503 VIS SI FM-89A G-7 SI23-152 VIS SI FM-89A G-6 SI24-153 VIS

SI SI SI FM-89A FH-89A FM-89A E-7 F-5 I-3 SI25-152 SI30-152 SI5-153 VIS VIS VIS SI FM-89A E-6 SI55-153 VIS

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REVISION : 0001 *

SURRY

POWER STATION UNIT 1 CODE EDITION =80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ======= -------

SI FM-89A F-7 SI56-153 VIS SI FM-89A H-2 SI57-1503 VIS SI FM-89A H-1 SI59-1503 VIS SI FM-89A I-4 SI6-153 VIS SI FM-89A 6-2 SI60-1503 VIS

SI SI SI FM-89A FM-89A FM-89A F-1 E-6 G-7 SI68-1503 SI78-153 SI83-152 VIS VIS VIS SI FM-89A D-7 SI84-152 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

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CODE EDITION :80W80 *

CATEGORY.C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

========= ======== ------- ======= ------ ------- -------

SI FM-89A I-1 SI87-1503 VIS SI FM-89A B-2 SI90-1503 VIS SI FM-89A C-6 SI92-153 VIS SI FM-89A F-1 SI93-1503 VIS SI FM-89B H-8 S:i:l-153 VIS

SI SI SI FM-89B FM-89B FM-89B C-4 E-4 H-6 Sil00-602 Sill-602 SI12-602 VIS VIS VIS SI FM-89B I-3 SI143-1502 VIS

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SURRY POWER STATION UNIT 1 CODE EDITION :sowao *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cl1715l COORD NUMBER METHOD REQUEST NOTES

======== ------- ======= ------ -------

SI FM-89B B-1 SI144-1502 VIS SI FM-89B B-1 SI145-1502 VIS SI FH-89B I-1 SI146-1503 VIS SI FH-89B I-2 SI147-1503 VIS SI FH-89B B-2 SI153-1502 VIS

SI SI SI FH-89B FH-89B FM-89B B-5 B-3 F-6 SI154-1502 SI155-1502 SI156-1502 VIS VIS VIS SI FH-89B B-2 SI157-1502 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES SI FM-89B D-8 SI158-1502 VIS SI FM-89B B-3 SI159-1502. VIS SI 'FM-89B H-7 SI2-153 VIS SI FM-89B H-8 SI3-153 VIS SI FM-89B C-6 SI33-l502 VIS

SI SI SI FM-89B FM-89B FM-89B G-7 C-8 D-5 SI34-l502 SI35-1502 SI36-602 VIS VIS VIS SI FM-89B G-6 SI37-602 VIS

12/22/82 SURRY NUTECH/PRISIM INSERVICE INSPECTION PLAN

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POWER STATION UNIT l CODE PAGE 175 *'

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EDITION :80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll715J COORD NUMBER METHOD REQUEST NOTES

========= ======== ------- ------- ------ ------- -------

SI FM-898 D-8 SI38-602 VIS SI FM-89B 8-5 SI45-1502 VIS SI FM-898 F-6 SI46-1502 VIS SI FM-89B 8-8 SI47-1502 VIS SI FM-89B 8-2 SI48-1502 VIS

SI SI SI FM-898 FM-896 FM-898 8-2 I-3 D-7 SI49-1502 SI50-l502 SI61-602 VIS VIS VIS SI FM-898 D-5 SI62-152 VIS

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. REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY C-H . ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 117151 COORD NUMBER METHOD REQUEST NOTES

========= ======== ------- ------- ------ ------- -------

SI FM-89B C-5 SI63-602 VIS SI FM-89B G-6 SI64-152 VIS SI FM-89B G-6 SI65-602 VIS SI FM-89B. D-8 SI66-152 VIS SI FM-89B C-8 SI67-602 VIS

SI SI SI FM-89B FM-89B FM-89B I-1 F-1 I-3 SI70-1503 SI71-l503 SI72-1503 VIS VIS VIS SI FM-89B F-2 SI73-1503 VIS

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SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

=== -------- ======= ------- ------ ======= =

SI FM-89B C-1 SI74-1502 VIS SI FM-896 D-2 SI75-l502 VIS SI FM-896 F-2 SI76-l503 VIS SI FM-896 F-2 SI77-1503 VIS SI FM-896 D-3 SI79-1502 VIS

SI SI SI FM-896 FM-896 FM-896 D-2 D-2 D-1 SIB0-1502 SI81-1502 SI85-1502 VIS VIS VIS SI FM-896 G-5 SI97-602 VIS

12/22/82 INSERVICE NUTECH/PRISIM INSPECTION PLAN

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SURRY

POWER STATION UNIT l PAGE 178

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c7.20 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ------- ------ ------- -------

SI FM-89B D-7 SI99-602 VIS SI FM106C C-3 SI170-153 VIS SI FM106C C-3 SI171-153 VIS SI FM106C A-3 SI5-153 VIS SI FM106C D-3 Sll7Z-153 VIS

- SS SS FM-82B FM-8ZB C-1 C-1 SS6-ICN9 SS7-ICN9 VIS VIS

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SURRY POWER STATION UNIT 1 PAGE 179

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES

========= -------- -------

BO FM124A B-5 WGCB-601 VIS BO FM124A A-2 WGCBl-601 VIS BO FM124A A-4 WGCB2-601 VIS BO FM124A A-5 WGCB3-601 VIS CH FM-88A C-1 CH25-l52 VIS

CH CH CH FM-88A FM-88A FM-888 E-2 B-2 F-3 CH29-152 CH32-152 CHl00-152 VIS VIS VIS CH FM-888 A-6 CHll-1503 VIS

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SURRY POWER STATION UNIT l PAGE 180

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CODE EDITION !80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOH FLOH SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

=== ======== ======= ------- ------ ======= =

CH FM-88B H-3 CH112-152 VIS CH FM-88B E-5 CH113-1503 VIS CH FM-88B F-3 CHll 7-152 VIS CH FM-88B F-3 CH118-152 VIS CH FM-88B I-2 CH119-152 VIS

CH CH CH FM-88B FM-888 FM-88B A-6 H-2 I-1 CH12-1503 CH120-152 CH121-152 VIS VIS VIS CH FM-88B C-1 CH125-152 VIS

12122182 NUTECH/PRISIM INSERVICE INSPECTION PLAN

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SURRY POWER STATION UNIT l PAGE 181

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CODE EDITION :80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES

========= ======== ------- ------- ------ ------- -------

CH FM-888 A-7 CH13-l503 VIS CH FM-888 H-2 CH163-152 *VIS CH *FM-888 I-3 CH164-152 VIS CH FM-888 G-3 CH165-152 VIS CH FM-888 8-7 CH167-1503 VIS

CH CH CH FM-888 FM-888 FM-888 B-8 F-7 D-7 CH17-152 CH18-152 CH187-1503 VIS VIS VIS CH FM-888 F-7 CH188-l503 VIS

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SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (117151 COORD NUMBER METHOD REQUEST NOTES

-------- ======= ------- ------ ======= =======

CH FM-888 G-7 CH189-1503 VIS CH FM-888 H-7 CH19-152 VIS CH FM-88B H-2 CH190-152 VIS CH FM-88B F-4 CH191-152 VIS CH FM-888 D-3 CH192-152 VIS

CH CH CH FM-888 FM-88B FM-888 K-1 H-6 F-2 CH193-152 CH196-152 CH199-152 VIS VIS VIS CH FM-888 F-6 CH2-l503 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

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SURRY POWER STATION UNIT l PAGE 183 *

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CATEGORY C-H , ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES CH FM-88B D-6 CH20-l503 VIS CH FM-88B H-7 CH201-152 VIS CH FM-88B F-7 CH202-152 VIS CH FM-88B E-7 CH203-152 VIS CH FM-88B B-8 CH204-152 VIS

CH CH CH FM-88B FM-88B FM-88B C-8 C-8 D-8 CH205-152 CH206-152 CH207-1503 VIS VIS VIS CH FM-88B F-8 CH208-1503 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT tll715) CO ORD NUMBER METHOD REQUEST NOTES CH FM-886 H-8 CH209-l503 VIS CH FM-886 J-4 CH211-152 VIS CH FM-886 J-4 CH212-152 VIS CH FM-886 H-6 CH22-l503 VIS CH FH-886 D-8 CH224-1503 VIS

CH CH CH FM-886 FH-886 FH-886 E-8 G-8 F-2 CH225-1503 CH226-l503 CH23-l52 VIS VIS VIS CH FM-886 6-4 CH231-1503 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

=== ======== ------- ------- ------ ------- =

CH FM-88B F-1 CH234-152 VIS CH FM-88B F-2 CH236-152 VIS CH FM-88B H-2 CH237-152 VIS CH FM-88B G-3 CH238-152 VIS CH FM-88B E-2 CH239-152 VIS

CH CH CH FM-88B FM-88B FM-88B H-2 A-6 H-6 CH24-152 CH276-1503 CH3-l503 VIS VIS VIS CH FH-88B I-3 CH58-152 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- -------

======= ------ -------

=======

CH FM-888 I-3 CH59-152 VIS CH FM-888 H-2 CH67-152 VIS CH FM-888 D-5 CH69-1503 VIS CH FM-888 C-2 CH7-602 VIS CH FM-88B E-6 CH70-1503 VIS

CH CH CH FM-88B FM-888 FM-888 G-6 E-7 H-3 CH71-1503 CH72-152 CH73-152 VIS VIS VIS CH FM-888 8-6 CH74-1503 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES CH FM-888 B-6 CH76-1503 VIS CH FM-888 B-7 CH77-1503 VIS CH FM-888 F-2 CH78-152 VIS CH FM-888 D-6 CH80-1503 VIS CH FM-88B D-6 CH81-1503 VIS

CH CH CH FM-88B FM-88B FM-88B E-1 E-5 B-6 CH87-152 CH89-1503 CH90-1503 VIS VIS VIS CH FM-888 A-6 CH91-l503 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

=======

-------- ------- ------ ======= =======

CH FM-88B B-3 CH99-152 VIS CH FM-88C E-2 CHl-1502 . VIS CH FM-88C E-5 CHlOl-1502 VIS CH FM-88C H-5 CH102-1502 VIS CH FM-88C D-5 CH103-1502 VIS

CH CH CH FM-88C FM-88C FM-88C H-7 I-6 H-4 CH106-1502 CH109-1502 CH122-152 VIS VIS VIS CH FM-88C B-3 CH123-1502 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll 715) COORD NUMBER METHOD REQUEST NOTES

------ ======= -------

CH FM-88C E-4 CH124-152 VIS CH FM-88C A-5 CH14-1502 VIS CH FM-88C F-2 CH1502 VIS CH FM-88C C-5 CH16-1502 VIS CH FM-88C B-4 CH214-152 VIS

CH CH CH FM-88C FM-88C FM-88C 0-4 G-4 C-5 CH215-152 CH216-152 CH217-152 VIS VIS VIS CH FM-88C F-5 CH218-152 VIS

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CATEGORY C-H , ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES

-------- ------- ------- ------ ======= -------

CH FM-88C I-4 CH219-152 VIS CH FM-88C B-3 CH223-l502 VIS CH FM-88C H-2 CH232-602 VIS CH FM-88C I-3 CH233-602 VIS CH FM-88C E-3 CH240-l502 VIS

CH CH CH FM-88C FM-88C FM-88C E-2 I-2 E-2 CH5-1502 CH6-602 CH68-1502 VIS VIS VIS CH FM-88C G-3 CH79-1503 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COO RD NUMBER METHOD REQUEST NOTES CH FM-88C I-3 CHB-1503 VIS CH FM-88C F-2 CH82-1502 VIS CH FM-88C G-3 CH83-l502 VIS CH FM-88C H-2 CH85-602 VIS CH FM-88C H-2 CH86-602 VIS

CH CH CH FM-88C FM-88C FM-88C H-7 E-7 B-7 CH92-1503 CH94-1503 CH96-1503 VIS VIS VIS CH FM-88C B-5 CH98-1502 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ======= -------

------ ------- =======

cs FM-84A I-3 CSl-153 VIS cs FM-84A K-1 CS14-153 VIS cs FM-84A L-1 CS19-152 VIS cs FM-84A I-3 CS2-153 VIS cs FM-84A C-2 CS22-153 VIS

cs cs cs FM-84A FM-84A FM-84A C-1 K-2 J-3 CS23-153 CS26-153 CS28-153 VIS VIS VIS cs FM-84A J-3 CS29-153 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ======= ------ ======= -------

cs FM-84A C-2 CS3-153 VIS cs FM-84A E-2 CS33-153 VIS cs FM-84A H-4 CS34-153 VIS cs FM-84A G-3 CS35-153 VIS cs FM-84A H-3 CS36-152 VIS

cs cs cs FM-84A FM-84A FM-84A E-2 H-2 H-3 CS4-153 CSS-152 CS6-152 VIS VIS VIS cs FM-84A G-2 CS74-152 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT 111715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ------- -------

cs FM-84A F-2 CS75-152 VIS cs FM-84A H-2 CS76-152 VIS cs FM-84A G-2 CS77-152 VIS cs FM-84A G-3 CS8-152 VIS FW FH-68A D-3 WFPD13-601 VIS

FW FW MS FM-68A FM-68A FM-64A D-2 D-5 C-4 WFPD17-601 WFPD9-601 SDHVl-601 VIS VIS VIS HS FM-64A C-5 SDHV2-601 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES

========= -------- -------

MS FM-64A C-6 SDHV3-601 VIS MS FM-64A C-4 SDHV4-601 VIS MS FM-64A D-4 SHPD6-601 VIS MS FM-64A E-7 SHPD7-601 VIS MS FM-64A D-5 SHPD8-601 VIS

MS MS MS FM-64A FM-64A FM-64A A-2 A-5 C-2 SHPl-601 SHP2-601 SHP22-601 VIS VIS VIS MS FM-64A C-5 SHP23-601 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ======= ------ ------- -------

MS FM-64A C-6 SHP24-601 VIS HS FM-64A A-6 SHP3-601 VIS MS FM-64A C-3 SHP37-601 VIS MS FM-64A B-4 SHP38-601 VIS MS FH-64A C-6 SHP39-601 VIS

MS MS HS FM-64A FH-64A FM-64A D-2 D-4 D-6 SHP45-601 SHP46-601 SHP47-60l VIS VIS VIS MS FM-64A B-2 SSVl-601 VIS

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CATEGORY C-H , ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C-11715) CO ORD NUMBER METHOD REQUEST NOTES

========= ======== ------- -------

MS FM-64A B-6 SSVll-601 VIS MS FM-64A B-6 SSV12-601 VIS MS FM-64A C-6 SSV13-601 VIS MS FM-64A C-6 SSV14-601 VIS MS FM-64A C-6 SSV15-601 VIS

MS MS MS FM-64A FM-64A FM-64A B-2 C-2 C-2 SSV2-601 SSV3-601 SSV4-601 VIS VIS VIS MS FM-64A C-2 SSVS-601 VIS

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SURRY POWER STATION UNIT l PAGE 198

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOI~ FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES

======= ------ ------- =======

MS FM-64A B-4 SSV6-601 VIS MS FM-64A B-4 SSV7-601 VIS MS FM-64A C-4 ssva-601 VIS MS FM-64A C-4 SSV9-601 VIS MS FM64AC -4 SSVl0-601 VIS

RHR RHR RHR FM-87A FM-87A FM-87A C-6 D-6 D-3 RHPlA RHPlB RHl0-602 VIS VIS VIS RHR FM-87A G-6 RHll-602 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COO RD NUMBER METHOD REQUEST NOTES RHR FM-87A E-5 RH12-602 VIS RHR FM-87A I-4 RH13-602 VIS RHR FM-87A I-5 RH14-602 VIS RHR FM-87A D-7 RH18-602 VIS RHR FM-87A E-4 RH19-602 VIS

RHR RHR RHR FM-87A FM-87A FM-87A E-7 C-5 I-5 RH2-602 RH21-602 RH22-602 VIS VIS VIS RHR FM-87A J-5 RH23-602 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES RHR FM-87A C-7 RH24-602 VIS RHR FM-87A C-7 RH25-602 VIS RHR FM-87A G-3 RH3-602 VIS RHR FM-87A B-6 RH4-602 VIS RHR FM-87A D-6 RH5-602 VIS

RHR RHR RHR FH-87A FH-87A FH-87A B-7 D-7 A-5 RHSl-602 RH52-602 RH6-602 VIS VIS VIS RHR FM-87A C-4 RH7-602 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES

=== -------- =

======= ------ ------- -------

RHR FM-87A A-3 RH8-602 VIS RHR FM-87A B-3 RH9-602 VIS RS FH-84A B-7 RSl-153 VIS RS FM-84A F-6 RSl0-153 VIS RS FM-84A D-4 RSll-153 VIS

RS RS RS FM-84A FM-84A FM-84A E-4 H-6 G-8 RS12-153 RS13-153 RS14-153 VIS VIS VIS RS FM-84A I-8 RS15-153 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ -------

=======

RS FM-84A D-7 RS2-153 VIS RS FM-84A A-2 RS20-153 . VIS RS FM-84A B-2 RS21-153 VIS RS FM-84A D-2 RS22-153 VIS RS FM-84A E-2 RS23-153 VIS

RS RS RS FM-84A FM-84A FM-84A A-4 B-4 E-8 RS3-153 RS4-153 RS7-153 VIS VIS VIS RS FM-84A E-8 RS8-153 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

========= ======== -------

------- ------ ------- =======

RS FM-84A F-6 RS9-153 VIS SI FM-89A E-8 CL153 VIS SI FM-89A F-4 SI102-l52 VIS SI FM-89A G-8 SI106-153 VIS SI FM-89A F-8 SI107-153 VIS

SI SI SI FM-89A FM-89A FM-89A G-8 G-5 I-6 SI108-153 SI13-153 SI130-152 VIS VIS VIS SI FM-89A J-4 SI131-152 VIS

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SURRY POWER STATION UNIT l CODE.EDITION :80W80 *

CATEGORY C-H ' ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ -------

SI FM-89A B-7 SI132-153 VIS SI FM-89A C-8 SI133-ICN9 VIS SI FM-89A E-7 SI134-ICN9 VIS SI FM-89A D-8 SI135-ICN9 VIS SI FM-89A E-7 SI136-ICN9 VIS

SI SI SI FM-89A FM-89A FM-89A F-7 E-8 H-7 SI137-153 SI138-ICN9 SI139-ICN9 VIS VIS VIS SI FM-89A G-8 SI140-ICN9 VIS

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SURRY POWER STATION UNIT 1 CODE EDITION :aoweo *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES SI FM-89A H-7 SI141-ICN9 VIS SI FM-89A F-5 SI148-153 VIS SI FM-89A F-5 SI149-153 VIS SI FM-89A D-5 5!150-153 VIS SI FM-89A D-6 SI151-153 VIS

SI SI SI FM-89A FM-89A FM-89A A-4 C-6 E-6 SI152-1502 SI16-153 SI160-153 VIS VIS VIS SI FM-89A D-6 5!17-152 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES SI FM-89A E-6 SI18-152 VIS SI FM-89A E-6 SI19-152 VIS SI FM-89A G-7 SI23-152 VIS SI FM-89A G-6 SI24-153 VIS SI FM-89A E-7 SI25-152 VIS

SI SI SI FM-89A FM-89A FM-89A F-5 I-3 E-6 SI30-152 SI5-153 SI55-153 VIS VIS VIS SI FM-89A F-7 SI56-153 VIS

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SURRY POWER STATION UNIT l PAGE 207

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ------- -------

SI FM-89A H-2 SI57-1503 VIS SI FM-89A H-1 SI59-1503 VIS SI FM-89A I-4 SI6-153 VIS SI FM-89A G-2 SI60-l503 VIS SI FM-89A F-1 SI68-1503 VIS

SI SI SI FM-89A FM-89A FM-89A E-6 G-7 D-7 SI78-153 SI83-152 SI84-152 VIS VIS VIS SI FM-89A B-2 SI90-1503 VIS

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SURRY POWER STATION UNIT l PAGE 208

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CODE EDITION =80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ======= ------ ------- -------

SI FM-89A C-6 SI92-153 VIS SI FM-89A F-1 SI93-1503 VIS SI FM-89B H-8 Sil-153 VIS SI FM-89B C-4 Sil00-602 VIS SI FM-89B E-4 Sill-602 VIS

SI SI SI FM-89B FM-89B FM-89B H-6 I-3 B-1 SI12-602 SI143-1502 SI144-1502 VIS VIS VIS SI FM-89B B-1 SI145-1502 VIS

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SURRY POWER STATION UNIT l PAGE 209

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CATEGORY C-H All PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ======= ------- ------ ------- -------

SI FM-89B I-1 SI146-1503 VIS SI FM-896 I-2 SI147-1503 VIS SI FM-89B 8-2 SI153-1502 VIS SI FM-89B 8-5 SI154-1502 VIS SI FM-89B 6-3 SI155-1502 VIS SI FM-896 F-6 SI156-1502 VIS SI FM-898 8-2 SI157-1502 VIS SI FM-896 D-8 SI158-1502 VIS SI FM-898 6-3 SI159-1502 VIS

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CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

=== -------- ------- ------- ------ ------- =

SI FM-89B' H-7 SI2-153 VIS SI FM-89B H-8 Sl3-153 VIS SI FM-89B C-6 Sl33-1502 VIS SI FM-89B G-7 SI34-1502 VIS SI FM-89B C-8 Sl35-1502 VIS

SI SI SI FM-89B FM-89B FM-89B D-5 G-6 D-8 SI36-602 SI37-602 Sl38-602 VIS VIS VIS SI FM-89B B-5 SI45-1502 VIS

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SURRY POWER STATION UNIT l PAGE 211 *

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CODE EDITION :80W80 *

CATEGORY C-H ' ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ------- -------

SI FH-89B F-6 SI46-1502 VIS SI FH-89B B-8 SI47-1502 VIS SI FM-89B B-2 SI48-1502 VIS SI FM-89B B-2 SI49-l502 VIS SI FM-89B I-3 SI50-1502 VIS

SI SI SI FM-89B FH-89B FM-89B D-7 D-5 C-5 SI61-602 SI62-152 SI63-602 VIS VIS VIS SI FM-89B G-6 SI64-152 VIS

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SURRY POWER STATION UNIT 1 PAGE 212

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CODE EDITION :sOW80

iE CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ======= ------ ------- -------

SI FM-89B G-6 SI65-602 VIS SI FM-89B 0-8 SI66-152 VIS SI FM-89B C-8 SI67-602 VIS SI FM-89B I-1 SI70-1503 VIS SI FM.;.898 F-1 SI71-1503 VIS

SI SI SI FM-89B FM-898 FM-898 I-3 F-2 C-1 SI72-1503 SI73-1503 SI74-1502 VIS VIS VIS SI FM-898 D-2 SI75-1502 VIS

________ I

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES SI FM-89B F-2 SI76-1503 VIS SI FM-89B F-2 SI77-1503 VIS SI FM-89B D-3 SI79-1502 VIS SI FM-89B D-2 SI80-1502 VIS SI FM-898 D-2 SI81-1502 VIS

SI SI SI FM-89B FM-898 FM-898 D-1 G-5 D-7 SI85-1502 SI97-602 SI99-602 VIS VIS VIS SI FM106C C-3 SI170-153 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

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SURRY POWER STATION UNIT l PAGE 214

REVISION : 0001

CODE EDITION !80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c7.21 ITEM DESCRIPTION : PIPING, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT 111715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ------- ------ ======= -------

SI FM106C C-3 Sil71-153 VIS SI FM106C A-3 SI5-153 VIS SI FM106C D-3 Sll72-153 VIS SS FM-828 C-1 SS6-ICN9 VIS SS FM-828 C-1 SS7-ICN9 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 215

REVISION : 0001

COOE EDITION :80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c7.30 ITEM DESCRIPTION : PUMPS, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

-------- ======= ======= ------ ------- -------

CH FM-88B D-7 CHPlA VIS CH FM-88B E-7 CHPlB VIS CH FM-88B G-7 CHPlC VIS RC FM-86A A-1 RC Pl A VIS RC FM-86A A-6 RCPlB VIS

RC FM-86A L-1 RCPlC VIS

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION !80W80 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c7.31 ITEM DESCRIPTION : PUMPS, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ======= ------ ======= -------

CH FM-88B D-7 CHPlA VIS CH FH-88B E-7 CHPlB VIS CH FH-888 G-7 CHPlC VIS RC FM-86A A-1 RCPlA VIS RC FM-86A A-6 RCPlB VIS

RC FM-86A L-1 RCPlC VIS

12122/82 INSERVICE SURRY NUTECH/PRISIM INSPECTION PLAN

SUMMARY

POWER STATION UNIT l PAGE 217

REVISION : 0001 CODE EDITION :soWSO *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1.4o ITEM DESCRIPTION : VALVES, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES

========= --------

------- ------- ------ ======= =======

FW FM-68A B-3 WFPD13-601 VIS FW FM-68A 0-2 WFPD17-601 VIS FW FM-68A 0-5 WFPD9-601 VIS MS FM-64A B-3 SHP-22-601 VIS MS FM-64A A-2 SHPl-601 VIS

MS MS MS FM-64A FM-64A FM-64A A-5 B-3 C-5 SHP2-601 SHP22-601 SHP23-601 VIS VIS VIS MS FM-64A B-7 SHP24-601 VIS I

_ _ _J

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SURRY POWER STATION UNIT l PAGE 218

REVISION : 0001

CODE .EDITION :80W80 *

CATEGORY C-H . ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.4o ITEM DESCRIPTION : VALVES, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ======= ------ ------- -------

MS FM-64A A-6 SHP3-601 VIS MS FM-64A D-2 SHP45-601 VIS MS FM-64A D-4 SHP46-601 VIS MS FM-64A D-6 SHP47-601 VIS RHR FM-87A D-3 RHl0-602 VIS

RHR RHR RHR FM-87A FM-87A FM-87A E-5 I-5 D-7 RH12-602 RH14-602 RH18-602 VIS VIS VIS RHR FM-87A E-4 RH19-602 VIS

12/22/82 NUTECH/PRISIM PAGE 219 *

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :soW80

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c?.40 ITEM DESCRIPTION : VALVES, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll715) CO ORD NUMBER METHOD REQUEST NOTES

======== ======= ------- ------ ------- =======

RHR FM-87A E-7 RH2-602 VIS RHR FM-87A B-6 RH4-602 VIS RHR FM-87A D-6 RH5-602 VIS RHR FM-87A C-4 RH7-602 VIS RHR FM-87A A-3 RH8-602 VIS

RHR SI SI FM-87A FM-87A FM-89B B-3 A-4 B-2 RH9-602 SI152-1502 SI48-1502 VIS VIS VIS SI FM-89B B-2 SI49-1502 VIS

12122/82 NUTECH/PRISIM PAGE 220 *

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SUMMARY

REVISION : 0001 *

SURRY ' POl~ER STATION UNIT 1 CODE EDITION :aowao *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c7.41 ITEM DESCRIPTION : VALVES, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======= ------- ------ ------- -------

FW FM-68A B-3 WFPD13-601 VIS FW FM-68A D-2 WFPD17-601 VIS FW FM-68A D-5 WFPD9-601 VIS MS FM-64A B-3 SHP-22-601 VIS MS FM-64A A-2 SHPl-601 VIS

MS MS MS FM-64A FM-64A FM-64A A-5 B-3 C-5 SHP2-601 SHP22-601 SHP23-601 VIS VIS VIS MS FM-64A B-7 SHP24-601 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

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SURRY POWER STATION UNIT l PAGE 221

REVISION : 0001

CODE EDITION :aowao *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER :c1.41 ITEM DESCRIPTION : VALVES, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES MS FM-64A A-6 SHP3-601 VIS MS FM-64A D-2 SHP45-601 VIS MS FM-64A D-4 SHP46-601 VIS MS FM-64A D-6 SHP47-601 VIS RHR FM-87A D-3 RHl0-602 VIS

RHR RHR RHR FM-87A FM-87A FM-87A E-5 I-5 D-7 RH12-602 RH14-602 RH18-602 VIS VIS VIS RHR FM-87A E-4 RH19-602 VIS

12/22182 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 222

REVISION : 0001

CODE EDITION :soweo *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER :c1 .41 ITEM DESCRIPTION : VALVES, PRESSURE RETAINING BOUNDARY FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT 111715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ -------

RHR FM-87A E-7 RH2-602 VIS RHR FM-87A B-6 RH4-602 VIS RHR FM-87A D-6 Rli5-602 VIS RHR FM-87A C-4 RH7-602 VIS RHR FM-87A A-3 RH8-602 VIS

RHR SI SI FM-87A FM-87A FM-89B B-3 A-4 B-2 RH9-602 SI152-l502 SI48-1502 VIS VIS VIS SI FM-89B B-2 SI49-1502 VIS

* .12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 223

REVISION : 0001

CODE EDITION :aowao *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER :Di.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES cc FM-71B D-7 CC335-151 VIS cc FM-71B F-7 CC336-151 VIS cc FM-71B F-7 CC337-151 VIS cc FM-71B E-7 CC338-151 VIS cc FM-71B G-6 CC339-151 VIS

cc cc cc FM-71B FM-71B FM-71B D-5 G-5 E-5 CC340-151 CC341-151 CC342-1Sl VIS VIS VIS cc FM-71B D-4 CC343-151 VIS

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SURRY POWER STATION UNIT l PAGE 224

REVISION : 0001

CODE EDITION :aowao *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION

ITEM NUMBER :oi.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

=== ======== ------- ------- ------ ======= =

cc FM-716 I-4 CC344-151 VIS cc FM-716 G-4 CC345-151 VIS cc FM-716 H-4 CC346-151 VIS cc FM-716 E-4 CC347-151 VIS cc FM-716 6-4 CC348-151 VIS

cc cc cc FM-716 FM-716 FM-716 G-4 H-6 E-6 CC349-151 CC350-151 CC351-151

' VIS VIS VIS cc FM-72A F-2 CCl0-121 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 225 REVISION : 0001

CODE EDITION :eowao *

- - - - ~******************************************

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION

ITEM NUMBER :Dl.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT 111715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ======= -------

cc FM-72A A-3 CCl00-151 VIS cc FM-72A E-6 CClOl-151 VIS cc FM-72A D-3 CC102-151 VIS cc FM-72A 0-3 CC103-151 VIS cc FM-72A D-4 CC104-151 VIS

cc cc cc FM-72A FM-72A FM-72A E-7 F-4 F-5 CC105-151 CC107-151 CC108-151 VIS VIS VIS cc FM-72A E-6 CC109-151 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 226

REVISION : 0001

CODE EDITION :eoweo *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION

ITEM NUMBER =Di.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

=== ======== ------- ------- ------ ------- =

cc FM-72A H-7 CCll0-151 VIS cc FM-72A H-4 CC112-151 VIS cc FM-72A H-5 CC113-151 VIS cc FM-72A H-6 CC114-151 VIS cc FM-72A L-3 CC16-181 VIS

cc cc cc FM-72A FM-72A FM-72A J-4 A-2 D-2 CC17-121 CC200-151 CC20l-151 VIS VIS VIS cc FM-72A A-4 CC202-151 VIS

12/22/82 NUTECH/PRISIM PAGE 227 *

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :aowso *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER :oi.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES cc FM-72A 0-:"4 CC203-151 VIS cc FM-72A A-6 CC204-151 VIS cc FM-72A D-6 CC205-151 VIS cc FM-72A E-2 CC206-151 VIS cc FM-72A H-5 CC207-l51 VIS

cc cc cc FM-72A FM-72A FM-72A E-2 H-8 F-6 CC246-151 CC247-151 CC305-151 VIS VIS VIS cc FM-72A H-6 CC306-151 VIS

12122182 NUTECH/PRISIM PAGE 228 *

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l . CODE EDITION :80W80 *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION

ITEM NUMBER :Dl.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES

========= ======== ------- ------- ------ -------

=======

cc FM-72A F-7 CC307-151 VIS cc FM-72A G-7 CC308-151 VIS cc FM-72A F-1 cc8-121 VIS cc FM-72A A-8 CC81-151 VIS cc FM-72A A-6 CC82-151 VIS

cc cc cc FM-72A FM-72A FM-72A A-7 A-7 D-7 CC83-151 CC84-151 CC85-151 VIS VIS VIS cc FM-72A 0.:.7 CC86-151 VIS

______ j

12/22/82 NUTECH/PRISIM PAGE 229 *

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :aowao *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER :oi.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES cc FM-72A C-7 CC87-151 VIS cc FM-72A E-7 CC88-151 VIS cc FM-72A A-6 CC89-151 VIS cc FM-72A A-4 CC90-151 VIS cc FM-72A A-5 CC91-151 VIS

cc cc cc FM-72A FM-72A FM-72A A-5 D-6 D-5 CC92-151 CC93-151 CC94-151 VIS VIS VIS cc FM-72A C-5 CC95-151 VIS

12122182 NUTECH/PRISIM PAGE 230 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :aowao *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION

ITEM NUMBER :Di.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

=== ======== ------- ------- ------ ======= =

cc FM-72A D-6 CC96-151 VIS cc FM-72A A-3 CC97-151 VIS cc FM-72A A-2 CC98-151 VIS cc FM-72A A-3 CC99-l51 VIS cc FM-72B A-1 CC115-151 VIS

cc cc cc FM-72B FM-72B FM-72B E-3 I-4 F-3 CC120-151 CC75-151 CC76-151 VIS VIS VIS cc FM-72B E-4 CC77-151 VIS

12122/82 NUTECH/PRISIM PAGE 231 *

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION

ITEM NUMBER :Di.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWt~, PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

========= -------

------- ======= ------ ======= =======

cc FM-72B E-1 CC78-l5l VIS cc FM-72B F-4 CC79-l5l VIS cc FM-72B G-2 CC80-l5l VIS cc FM-72B I-1 CC8l-l2l VIS cc FM-72B I-1 CC89-l2l VIS

cc cc cc FM-72C FM-72C FM-72C G-8 K-1 G-8 CC14-l2l CC143-12l CC15-l2l VIS VIS VIS cc FM-72C K-1 CC15l-15l VIS

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 COOE. EOITION :aowao *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER :Di.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ------- -------

cc FM-72C G-3 CC153-151 VIS cc FM-72C F-2 CC154-151 VIS cc FM-72C E-3 CC155-151 VIS cc FM-72C G-1 CC161-121 VIS cc FM-72C H-2 CC169-121 VIS

cc cc cc FM-72C FM-72C FM-72C H-2 L-4 K-4 CC177-151 CC30l-151 CC302-151 VIS VIS VIS cc FM-72C L-4 CC303-151 VIS

12122182 NUTECH/PRISIM INSERVICE INSPECTION PLAN

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SURRY POWER STATION UNIT l CODE PAGE 233

REVISION : 0001

EDITION :aowao *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION

ITEM NUMBER :Di.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

========= ======== ======= ------- ------ ======= -------

cc FM-72C L-5 CC304-151 VIS cc FM-72C J-5 CC364-l l VIS cc FM-72C J-5 CC364-151 VIS cc FM-72C K-4 CC383-121 VIS cc FM-72C K-5 CC385-151 VIS

cc cc cc FM-72C FM-72C FM-72C H-3 J-5 I-7 CC473-151 CC474-151 CC61-151 VIS VIS VIS cc FM-72C I-6 CC62-151 VIS

12/22/82 NUTECH/PRISIM PAGE 234 *

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION

ITEM NUMBER :Di.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES cc FM-72C I-3 CC65-121 VIS cc FM-72C J-6 CC66-151 VIS cc FM-72C I-3 CC67-151 VIS cc FM-72C I-3 CC69-151 VIS cc FM-72C J-7 CC70-121 VIS

cc cc cc FM-72C FM-72C FM-72C J-5 J-4 K-2 CC70-l51 CC71-151 CC72-121 VIS VIS VIS cc FM-72D C-2 CCl-121 VIS

12122/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

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SURRY POWER STATION UNIT 1 PAGE 235

REVISION : 0001

CODE EDITION :aowao *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER !Dl.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ------- ------ ------- -------

cc FM-720 B-2 CC19-121 VIS cc FM-720 C-2 CC2-121 VIS cc FM-720 A-2 CC20-151 VIS cc FM-72D A-3 CC21-151 VIS cc FM-72D A-2 CC22-151 VIS

cc cc cc FM-72D FM-72D FM-72D D-2 A-3 D-3 CC220-121 CC222-151 CC224-121 VIS VIS VIS cc Fl1-72D F-2 CC225-121 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

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SURRY PO~IER STATION UNIT l PAGE 236

REVISION : 0001

CODE EDITION :aowao *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER :Di.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ======= ------ ------- =======

cc FM-720 J-1 CC226-121 VIS cc FM-72D D-2 CC227-121 VIS cc FM-72D D-2 CC228-121 VIS cc FM-72D D-3 CC229-l21 VIS cc FM-72D D-1 CC230-121 VIS

cc cc cc FM-72D FM-72D FM-72D E-1 E-2 E-3 CC231-121 CC232-121 CC233-121 VIS VIS VIS cc FM-72D E-4 CC234-121 VIS

12122182 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT 1 PAGE 237

REVISION : 0001

CODE EDITION :80W80 *

CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER :oi.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ======= ------ ------- =======

cc FM-720 G-1 CC235-121 VIS cc FM-720 F-1 CC236-121 VIS cc FM-720 F-1 CC237-121 VIS cc FM-720 L-2 CC27-121 VIS cc FM-720 C-3 CC3-121 VIS

cc cc cc FM-720 FM-720 FM-720 F-8 D-3 C-3 CC314-151 CC319-151 CC4-121 VIS VIS VIS cc FM-720 D-2 CCS-121 VIS

12/22/S2 NUTECH/PRISIM PAGE 23S *

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :SOWSO *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER :oi.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

------ ------- =======

cc FM-72D D-3 CC6-121 VIS cc FM-720 L-1 CC7-121 VIS cc FM-720 K-1 CC9-121 VIS cc FM-720 B-1 CC320-151 VIS CH FM-SSA D-4 CH139-152 VIS

CH CH CH FM-SSA FM-SSA FM-SSA F-4 H-S F-6 CH140-152 CH141-152 CH142-152

' VIS VIS VIS CH FM-SSA G-7 CH143-152 VIS

12122182 NUTECH/PRISIM PAGE 239 *

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :eoweo *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER :oi.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES CH FM-88A F-6 CH144-152 VIS CH FM-88A D-5 CH145-152 VIS CH FM-88A D-5 CH146-152 VIS CH FM-88A F-5 CH147-152 VIS CH FM-88A C-7 CH148-152 VIS

CH CH CH FM-88A FM-88A FM-88A D-6 D-6 C-4 CH149-152 CH150-152 CH152-152 VIS VIS VIS CH FM-88A D-4 CH153-152 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 240

REVISION : 0001

CODE EDITION :eoweo *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER :Di.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

=======

CH FM-88A G-4 CH154-152 VIS CH FM-88A H-7 CH155-152 VIS CH FM-88A E-7 CH156-152 VIS CH FM-88A E-6 CH158-152 VIS CH FM-88A E-5 CH160-152 VIS

CH CH CH FM-88A FM-88A FM-88A H-5 B-5 A-6 CH179-152 CH181-152 CH229-152 VIS VIS VIS CH FM-88A J-7 CH230-152 VIS

12122182 NUTECH/PRISI!1 INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 241

REVISION : 0001

CODE EDITION :aowso *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER :Di.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN, PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll 715) COORD NUMBER METHOD REQUEST NOTES CH FM-S8A E-7 CH241-152 VIS CH FM-8SA D-5 CH243-152 VIS CH FM-S8A D-4 CH245-152 VIS CH FM-88A F-4 CH246-152 VIS CH FM-8SA C-S CH34-152 VIS

CH CH CH FM-88A FM-SSA FM-88A I-7 C-S E-8 CH342-152 CH35-152 CH36-152 VIS VIS VIS CH FM-88A F-8 CH37-152 VIS I

J

12/22/82 NUTECH/PRISIN INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 242

REVISION : 0001 *

coDE EDITION :8owao *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDmlN FUNCTION

ITEM NUMBER :Di.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT Cll715) COORD NUMBER METHOD REQUEST NOTES CH FM-88A C-5 CH38-152 VIS CH FM-88A E-6 CH39-152 VIS CH FM-88A E-7 CH40-152 VIS CH FM-88A G-5 CH41-152 VIS CH FM-88A A-8 CH42-152 VIS

CH CH CH FH-88A FM-88A FM-88A B-6 E-8 F-8 CH43-152 CH52-152 CH53-152 VIS VIS VIS CH FM-88A F-7 CH61-152 VIS

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INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :80W80 *

CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER :Di.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN, PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- -------

======= ------ ------- -------

CH FM-88A D-7 CH62-152 VIS CH FM-88A H-6 CH64-152 VIS CH FM-88B J-3 CH195-152 VIS CH FM-888 K-4 CH56-152 VIS CH FM-88B J-6 CH57-152 VIS

CH FW FW FM-88B FM-68A FM-68A J-3 F-8 E-6 CH58-152 WAPD-151 WAPDl-601 VIS VIS VIS FW FM-6BA C-6 WAPDl0-601 VIS

12122182 HUTECH/PRISIM PAGE 244 *

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT 1 CODE EDITION :eoweo *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER :Di.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW*

SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES FW FM-68A B-5 WAPDll-601 VIS FW FM-68A B-6 WAPD12-601 VIS FW FM-68A B-6 WAPD13-601 VIS FW FN-68A B-6 WAPD14-601 VIS FW FM-68A D-7 WAPD15-601 VIS

FW FW FW FM-68A FM-68A FM-68A D-6 E-7 F-6 WAPD16-151 WAPD17-601 WAPD18-151 VIS VIS VIS FW FM-68A F-6 WAPD19-151 VIS

12122/82 NUTECH/PRISIM PAGE 245 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :aowao *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER :Di.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) CO ORD NUMBER METHOD REQUEST NOTES FW FM-68A E-7 WAPD2-601 VIS FW FM-68A G-7 WAPD20-601 VIS FW FM-68A G-6 WAPD21-151 VIS FW FM-68A D-7 WAPD3-601 VIS FW FM-68A D-6 WAPD4-601 VIS

FW FW FW FM-68A FM-68A FM-68A E-6 F-6 F-6 WAPD5-601 WAPD6-601 WAPD7-601

' VIS VIS VIS FW FM-68A G-6 WAPD8-601 VIS

12122182 NUTECH/PRISIM PAGE 246 INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 SURRY POWER STATION UNIT 1 CODE EDITION :sOW80

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER :Di.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAM RELIEF PROGRAM COMPONENT (117151 COO RD NUMBER METHOD REQUEST NOTES

======== ------- ======= ------ ======= -------

FW FM-68A C-4 WAPD9-601 VIS FW FM-68A E-8 WCMUl0-151 VIS FW FM-68A D-8 WCMUll-151 VIS FW FM-68A G-8 WCMU151 VIS FW FM-68A H-8 WCMU4-151 VIS

FW FW FW FM-68A FM-68A FM-68A H-8 E-8 G-8 WCMU5-151 WCMU54-151 WCMU56-151 VIS VIS VIS FW FM-68A H-8 WCMU6-151 VIS

12/22/82 NUTECH/PRISIM PAGE 247 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :80W80 *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER :Di.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES FW FM-68A H-8 WCMU7-151 VIS FW FM-68A F-8 WCMU8-151 VIS FW FM-68A G-8 WCMU9-151 VIS FW FM-68B K-4 WAPD150-601 VIS FW FM-68B I-3 WAPD151-601 VIS

FW FW FW FM-688 FM-688 FM-688 K-2 K-6 I-7 WAPD152-601 WAPDS0-601 WAPD5l-601 VIS VIS VIS FW FM-688 K-6 WAPD52-601 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 248

REVISION : 0001

CODE EDITION :SOW80 *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER :Di.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ------- ------ ------- -------

FW FM-68B E-5 WCMUlll-151 VIS FW FM-68B E-6 WCMU153-151 VIS FW FM-68B E-7 WCMU154-151 VIS FW FM-l?8B E-6 WCMU156-151 VIS FW FM-68B E-2 WCMU53-151 VIS

MS MS MS FM-64A FM-64A FM-64A B-5 B-6 C-7 SHP25-601 SHP26-601 SHP27-601 VIS VIS VIS

.MS FM-64A C-8 SHP28-601 VIS

_____ _J

12122182 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 249

REVISION : 0001

CODE EDITION :80W80 *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION

ITEM NUMBER :Dl.10 ITEM DESCRIPTION : SUPPORT REACTOR SHUTDOWN,PRESS. RETAINING COMPS.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ======= ------ ------- -------

MS FM-64A C-7 SHP29-601 VIS MS FM-64A C-7 SHP30-60l VIS MS FM-64A F-8 SHP31-601 VIS MS FM-64A B-7 SHP32-601 VIS MS FM-64A G-8 SHP57-601 VIS

12/22/82 NUTECH/PRISIM PAGE 250 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :ao~l80 *

CATEGORY D-B SYS. SUPPORT OF ECCS,CHR,ATMCU, & REACTOR RHR

ITEM NUMBER !D2.10 ITEM DESCRIPTION : ECCS.,CHR ,ATMCU,RRHR, PRESSURE RETAINING COMPONEN FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) COO RD NUMBER METHOD REQUEST NOTES

======== ------- ------- ------ ------- -------

SW FM-71A E-6 WCl-10 VIS SW FM-71A E-6 WC2-10 VIS SW FM-71A F-6 WC3-10 VIS SW FM-71A F-6 WC4-10 VIS SW FM-71A C-7 WSl-10 VIS

SW SW SW FM-71A FM-71A FM-71A G-6 G-6 H-4 WS12-10 WS13-10 WS14-1D VIS VIS VIS SW FM-71A H-5 WS15-10 VIS

12/22/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 251

REVISION : 0001

CODE EDITION :aowao *

CATEGORY D-B SYS. SUPPORT OF ECCS,CHR,ATMCU, & REACTOR RHR

ITEM NUMBER :02.10 ITEM DESCRIPTION : ECCS,CHR,ATMCU,RRHR, PRESSURE RETAINING COMPONEN FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ======= ------ ------- -------

SW FM-71A H-5 WS16-10 VIS SW FM-71A G-3 WS17-10 VIS SW FM-71A G-4 WS18-10 VIS SW FM-71A G-5 WS19-l0 VIS SW FM-71A C-7 WS2-10 VIS

SW SW SW FM-71A FM-71A FM-71A D-5 D-7 A-6 WS21-10 WS22-10 WS23-10 VIS VIS VIS SW FM-71A B-7 WS24-10 VIS

12/22/82 NUTECH/PRISIM PAGE 252 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0001

SURRY POWER STATION UNIT l CODE EDITION :aowao *

CATEGORY D-B SYS. SUPPORT OF ECCS,CHR,ATMCU, & REACTOR RHR ITEM NUMBER :D2.10 ITEM DESCRIPTION : ECCS,CHR,ATMCU,RRHR, PRESSURE RETAINING COMPONEN FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 117151 CO ORD NUMBER METHOD REQUEST NOTES

-------- ======= ------- ------ -------

=======

SW FM-71A A-3 WS26-10 VIS SW FM-71A B-3 WS28-l0 VIS SW FM-71A C-3 WS30-10 VIS SW FM-71A C-3 WS32-10 VIS SW FM-71A A-3 WS33-10 VIS

SW SW SW FM-71A FM-71A FM-71A B-3 B-3 C-3 WS34-10 WS35-10 WS36-10 VIS VIS VIS SW FM-71A D-3 WS37-10 VIS

12122182 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 253

REVISION : 0001

CODE EDITION :eoweo *

CATEGORY D-B SYS. SUPPORT OF ECCS,CHR,ATMCU, & REACTOR RHR

ITEM NUMBER :D2.10 ITEM DESCRIPTION : ECCS,CHR,ATMCU,RRHR, PRESSURE RETAINING COMPONEN FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT 111715) COORD NUMBER METHOD REQUEST NOTES

======== ======= ======= ------ ------- -------

SW FM-7lA D-3 WS38-l0 VIS SW FM-7lA I-6 WS39-l0 VIS SW FM-7lA C-7 WS4-l0 VIS SW FM-7lA H-6 WS40-l0 VIS SW FM-7lA G-6 WS4l-l0 VIS

SW SW SW FM-7lA FM-7lA FM-7lA F-6 I-8 I-8 WS42-l36

~lS5l-lO WS52-l0 VIS VIS VIS SW FM-7lA I-8 WS53-l36 VIS

12122/82 NUTECH/PRISIM INSERVICE INSPECTION PLAN

SUMMARY

SURRY POWER STATION UNIT l PAGE 254

REVISION : 0001

CODE EDITION :aowao *

CATEGORY D-B SYS. SUPPORT OF ECCS,CHR,ATMCU, & REACTOR RHR

ITEM NUMBER :D2.10 ITEM DESCRIPTION : ECCS,CHR,ATMCU,RRHR, PRESSURE RETAINING COMPONEN FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11715) CO ORD NUMBER METHOD REQUEST NOTES

========= ======== ------- ------- ------ ------- -------

SW FM-71A J-7 WSSS-136 VIS SW FM-71A J-7 WS56-136 VIS SW Fl1-71A J-6 WS57-136 VIS SW FM-71A K-7 WS58-l36 VIS s~~ Fl1-71B B-7 WS178-136 VIS

SW SW SW FM-71B FM-718 FM-71B D-8 D-8 G-8 WS70-136 WS71-l36 WS72-136 VIS VIS VIS SW Fl1-71B G-8 WS73-136 VIS

12/22/82 INSERVICE SURRY NUTECH/PRISIN INSPECTION PLAN

SUMMARY

PO~IER STATION UNIT l PAGE 255

REVISION : 0001 CODE EDITION :80W80 *

CATEGORY D-B SYS. SUPPORT OF ECCS,CHR,ATMCU, & REACTOR RHR

ITEM NUMBER :D2.10 ITEM DESCRIPTION : ECCS,CHR,ATMCU,RRHR, PRESSURE RETAINING COMPONEN FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- ------ ======= -------

SW FM-718 D-7 WS74-218 VIS SW FN-71B G-7 WS75-218 VIS SW FM-718 F-8 WS76-218 VIS SW FM-71B C-8 WS77-21B VIS SW FM-71B B-6 WS78-l36 VIS

SW SW SW FM-718 FM-718 FM-718 C-1 H-1 D-1 WS79-218 WSB0-218 WS81-21B VIS VIS VIS SW FM-718 H-1 WS82-21B VIS

12122182 NUTECH/PRISIM PAGE 256 *

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SUMMARY

REVISION : 0001 *

SURRY POWER STATION UNIT l CODE EDITION :aowao *

CATEGORY D-B SYS. SUPPORT OF ECCS,CHR,ATMCU, & REACTOR RHR ITEM NUMBER :D2.10 ITEM DESCRIPTION : ECCS,CHR,ATMCU,RRHR, PRESSURE RETAINING COMPONEN FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) CO ORD NUMBER METHOD REQUEST NOTES

========= ======== ======= -------

------ ======= -------

SW FM-71B E-1 WS83-21B VIS SW FM-71B E-1 WS84-21B VIS SW FM-71B A-1 WS85-21B VIS SW FM-71B E-1 WS86-21B VIS SW FM-71B H-2 WS87-21B VIS

SW SW SW FM-71B FM-71B FM-71B D-2 A-6 E-7 WS88-21B WS89-136 WS90-l36 VIS VIS VIS

09/21/82 NUTE CH/PR IS IM PAGE 257 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0000 *

SURRY POWER STATION UNIT l *

CATEGORY D-B SYS. SUPPORT OF ECCS,CHR,ATMCU, ~ REACTOR RHR

ITEM NUMBER :D2.10 ITEM DESCRIPTION : ECCS,CHR,ATMCU,RRHR, PRESSURE RETAINING COMPONEN FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT {11715) CO ORD NUMBER METHOD REQUEST NOTES SW Flt-716 C-8 wsn-21B VIS SW Flt-716 B-6 WS78-136 VIS SW Flt-716 C-1 WS79-21B VIS SW Flt-71B H-1 wsao-21B VIS SW Flt-71B 0-1 wsa1-21B VIS

SW SW SW Ftt-71B Flt-718 FM-716 H-1 e-1 E-1 wsa2-21a wsa3-21a wsa4-21a VIS VIS VIS SW Flt-716 A-1 wsa5-21B VIS

09/21/82 *

NUTECH/PRISIM

PAGE 258 *

INSERVICE INSPECTION PLAN

SUMMARY

REVISION : 0000 *

SURRY POl~ER STATION UNIT 1 *

CATEGORY D-B SYS. SUPPORT OF ECCS,CHR,ATMCU, ~ REACTOR RHR

ITEM NUMBER :D2.10 ITEM DESCRIPTION : ECCS,CHR,ATMCU,RRHR, PRESSURE RETAINING COl1PONEN FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11715) COORD NUMBER METHOD REQUEST NOTES

======== ------- ------- ------ ------- -------

SW Ftt-718 E-1 lo!S86-21B VIS SW Ftt-71B H-2 WS87-218 VIS SW Ftt-718 D-2 wsa8-218 VIS SW Ftt-718 A-6 WS89-136 VIS SW Ftt-718 E-7 WS90-136 VIS

RELIEF REQUEST NO. SR-1 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS In Class 1 systems, valves which are greater than four inches nominal pipe size are subject to visual examination. These valves vary in size, design and manufacturer but are all manufactured from either cast stainless steel or carbon steel.

None of the valve bodies are welded.

Section XI of the ASME Code, 1980 Edition through the Winter 1980 Addenda requires that 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. (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 and poor as-cast surface condition, realistically, provides little additional information as to the valve casing integrity.

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

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

III. ALTERNATE PROVISIONS An examination of the internal pressure boundary surfaces will be performed, to the extent practical, each time a valve is disassembled for maintenance purposes.

I.

RELIEF REQUEST NO. SR-2 IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The design of the Residual Heat Removal Heat Exchanger nozzle to vessel welds calls for the use of a reinforcement pad. These pads are fillet welded and completely encase the nozzle to vessel weld.

(See Figure 3)

Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addenda requires a volumetric and surface examination of the nozzle inside radius section (Category C-B).

Relief from this requirement is requested due to the physical inaccessibility of the subject weld.

II. BASIS FOR RELIEF The fabrication of these welds precludes any type of surf ace or volumetric examination. Additional assurance of the continued integrity of these welds is afforded by the fact that the reinforcement pads strengthen the welds and reduce stresses on the internal welds.

III. ALTERNATE PROVISIONS A visual examination for evidence of leakage will be performed in accordance with Subsection IWC-5000 requirements.

- WESTINOHOUSE ELECTRIC CORPORAHG,~

f If1URE 3 RESIDUAL HEAT REMOVAi HEAT EX.CHANGER 2

c 0

r-.._.+"l'"T/"CHANNEL HEAD FLANGE 1* THICK.REINFORCEMENT PAD NOZZLE TO VESSEL WELD

~ (.TYPICAL OF TWO)

NQZZLE 10" SCH 405

.875~ THICK SHELL AND HEAD

RELIEF REQUEST NO. SR-3 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The configuration of the Reactor Coolant branch nozzle connection welds precluded complete examination (See Figure 2).

Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addenda requires a volumetric and surface examination of branch pipe connection welds on piping having a nominal pipe size of four inches or greater. In particular, paragraph III-4430 requires an angle beam examination of the weld root from the weld crown.

Relief is requested from the requirements of paragraph III-4430 due to physical configuration of these branch nozzle connection welds.

II. BASIS FOR RELIEF Due to the configuration* of the weld crown, transducer contact cannot be maintained on the weld. The slope of the weld crown precludes examination of the weld root when scanning from the weld crown.

III. ALTERNATE PROVISIONS The volumetric examinations on these welds will be performed to the extent practical.

- WESTINGHOUSE ELECTRIC CORPORATION FIGURE 2 BRANCH NOZZLE CONNECTION WELD CENTERLINE.

NOZZLE NOZZLE FORGING REACTOR COOLANT PIPE

RELIEF REQUEST NO. SR-4 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The Reactor Coolant Filter has three circumferential welds subject to examination. (See Figure 4)

Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addenda, requires a volumetric examination of circumferential shell welds (Category C-A).

II. BASIS FOR RELIEF The stainless steel material and thickness (0 .188") preclude any type of meaningful examination by ultrasonic examination.

III. ALTERNATE PROVISIONS A surface examination will be.performed in lieu of the volumetric examination.

- -. ,_. ~ - --- - -- -- ----* **"~**-~ -- ._,---~-- ----~- .... .,..* .,,. ~.- ., - (* . ...... ' **.,. ... . .. .

RELIEF REQUEST NO. SR-5

I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The shell to top head circumferential weld on the Surry 2 Pressurizer is not accessible for examination.

Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addenda requires a volumetric examination of the pressurizer head to shell weld (Category B-B).

Relief is requested from this requirement due to the physical unaccessibility of this weld.

II. BASIS FOR RELIEF The shell to top head circumferential weld is not accessible for volumetric or surface examination due to interference from the insulation support ring.

III. ALTERNATE PROVISIONS A visual examination for evidence of leakage will be performed during system pressure tests.

- - __- _ _ --,--...-.- .. ~-**~ -:"**'-*":"'"'..................-~.--- .... --.-*:*~~.,,--- _ _ _* *_-_-_..... -"!" , .....- . .--~ *****: _*

..~*"-*--~~--"-*,_ *-~'- - - - -

3.0 INSERVICE TESTING PROGRAM FOR SUPPORTS 3.1 GENERAL INFORMATION The 1980 Edition of the ASME Section XI with Addenda through Winter 1980 was expanded to include Subsection IWF. This subsection is still largely in course of preparation by the ASME and as written (IWF 1100 (a)) excludes supports not constructed to Subsection NF.

However, since some scope previously included in IWB 2000, IWC 2000, and IWD 2000 has been transposed into Subsection IWF, VEPCO will continue to examine, as a minimum, the support boundaries required to be examined by the 1974 Edition with Addenda through Summer 1975.

The acceptance standards of the 80W80 Code will be applied. Surry Power Station is in course of preparing an Inservice Inspection Program for Class I, II and II supports including administrative control for repairs and replacements.

Snubbers will continue to be inspected and tested in accordance with the Plant Technical Specifications.

3-1

4.0 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES 4.1 PROGRAM DESCRIPTION This Inservice Testing Program for ISI Class 1, 2, 3 and NC pumps and valves meets the requirements of Subsections IWP and IWV of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addenda. Where these requirements are determined to be impractical, specific requests for relief have been written and included in th.e program plan attached .

4-1

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 Pump and Valve Inservice Test Program P_lan September 22, 1982

TABLE OF CONTENTS

1.0 INTRODUCTION

2.0 PUMP INSERVICE TEST PROGRAM DESCRIPTION 2.1 Program Development Philosophy 2.2 Program Implementation 2.3 Program Administration 2.4 Pump Reference List 2.5 Pump Inservice Test Tables 2.6 Pump Test Program Relief Request 3.0 VALVE INSERVICE TEST PROGRAM DESCRIPTION 3.1 Program Development Philosophy 3.2 Program Implementation 3.3 Program Administration 3.4 Valve Inservice Test Table 3.5 Valve Test Program Relief Request 4.0 REPORTING OF INSERVICE TEST RESULTS 4.1 Pump Inservice Program 4.2 Valve Inservice Program 4.3 Reports to Regulatory Agencies 5.0 QUALITY ASSURANCE PROGRAM 6.0 PIPING AND DIAGRAMS

INTRODUCTION This Pump and Valve Inservice Test Program Plan is applicable to the Surry Power Station Unit 1. Surry Power Station Unit 1 is a Pressurized Water Reactor located on Gravel Neck and adjacent to the James River in Surry County, Virginia. The plant employs a Westinghouse Electric Corp. Nuclear Steam Supply System.

This program.plan has been prepared as the controlling document governing Pump and Valve Inservice Testing for Surry Power Station Unit 1. The requirements for Pump and Valve Inservice Testing are outlined in the ASME Boiler and Pressure Vessel Code,Section XI entitled "Rules for Inservice Inspection of Nuclear Power Plant Components". The scope of this plan encompasses the, testing of ASME Section III Nuclear Class 1, 2, and 3 pumps and valves as defined by Sub-Sections IWP and IWV of ASME Section XI.

Surry Power Station Unit 1 will be testing Class 1, 2 and 3 pumps and valves according to the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition with Addenda through Winter 1980. This is consistent with Federal Regulations, part 50 (10 CFR 50. 55a (g)). This program was prepared in accordance with this code edition and addenda.

This program plan is comprised of two independent sub programs - the Pump Inservice Test Program and the Valve Inservice test program. The development, implementation and administration of these two programs is detailed in subsequent sections *

~ ,.~,..._ _., ._...,,.._,_,....,-.....,.... -._,,.,..._.,.., -..-*-~..-,...,.*~~-* ~~-,.,.,. ..,_..,.. *-~-~--_. ..,..__.,... - .. * -.,,..,..._,, ..... .,...---***v*~~--- -* - *---**** ,...,., *"*'"'. ** ... _.,_ . * *-*-** ***,*

~-- -

2 2.0 PUMP INSERVICE TEST PROGRAM DESCRIPTION 2.1 Program Development Philosophy Highly reliable safety grade equipment is a vital consideration in the operation of a nuclear generating station. To help assure operability, the Surry Power Station Unit 1 Pump Inservice Test Program has been developed.

The Program is designed to detect and evaluate significant hydraulic or mechanical change in the operating parameters of vital pumps and to inititate corrective action when necessary. The Program is based on the requirements of the ASME Boiler and Pressure Vessel Code, Section XI, Subsection IWP. To the maximum extent practical, the Program complies with the specifications of ASME Boiler and Pressure Vessel Code,Section XI, Subsection IWP, 1980 Edition w~th Addenda through Winter of 1980; 10 CFR 50.55a (g); and NRC Staff guidelines for complying with certain provisions of 10 CFR 50.55a (g) "Inservice Inspection Requirements".

The Nuclear Regulatory Commission and Code Committee recognized that design differences among plants may render impractical certain Code requirements. Where such impracticalities exist, they have been substantiated as relief request which are allowed by the Code.

Alternate testing requirements have been proposed when warranted.

2.2 Program Implementation Surveillance testing is performed, to detect equipment malfunction or degradation and to initiate corrective action. Since the safeguards pumps are normally in standby mode, periodic testing of this equipment is especially important. The Surry Power Station

3 Unit 1 Inservice Test Program provides a schedule for testing safety grade, pumps and will be implemented as part of normal periodic surveillance testing.

Reference data will be gathered during initial surveillance tests. In most cases, test parameters will be measured with normal plant imstrumentation. This approach will simplify the test program and will promote timely completion of periodic surveillance testing.

When permanently installed instrumentation is not available, portable instrumentation will be used to record the required parameters.

During subsequent surveillance tests, flow rate will normally be selected as the independent test parameter and will be set up to match the reference flow rate. Other hydraulic and mechanical performance parameters will be measured and evaluated against the appropriate reference valves. The results of such evaluations will determine whether or not corrective action is warranted.

Each pump in the Pump Test Program will be tested according to a detailed test procedure. The procedure will include, as minimum:

a)

References:

This section will identify references applicable to Technical Specifications, and other necessary material as drawings.

b)

Purpose:

This section will identify test objectives.

c) Initial Conditions: Each procedure should identify those independent actions or procedures which shall be completed and station conditions which shall exist prior to use.

d) Precautions: Precautions should be established to alert the individual performing the task to those situations in which important measures should be taken early or where extreme care should be used to protect equipment and personnel. Cautionary notes applicable to specific steps in the procedure shall be included in the main body of the procedure as appropriate and shall be identified as such.

4 e) Instructions: The main body of a procedure should contain step by step instructions in the degree of detail necessary for performing a required test. Instructions shall reference or include detailed steps to remove a system from service and to return the system to operating status or standby.

f) Acceptance Criteria: The ranges within which test data will be considered acceptable will be established and included in the test procedure. In the event that data falls outside the acceptable range, operator action will be governed by approved station procedures.

Finally, it is recognized that the Pump InserYice Test Program sets forth minimum testing requirements. Additional testing will be performed, as required, after pump maintenance or as determined necessary by administrative personnel at Surry Power Station.

2.3 Program Administration The operations and engineering staff at Surry Power Station is responsible for administration and execution of the Pump Inservice Test Program. The Program will be officially implemented on December 22, 1982 and will govern pump testing for a 120 month period. Prior to the end of the 120 month period, the Program will be reviewed and upgraded to assure continued compliance with 10 CFR 50.SSa (g) (4). The Program will be updated a minimum of at least once every 40 months for new systems, relief request, etc.

+ -;-

2.4 Pump Reference List This list gives a brief description of each pump identified in the Pump Test Program. The pumps ASME Code Classifications are specified in "Pump Inservice Test Tables."

Rev. 1 12/22/82

5 1-CH-P-lA 1-CH-P-lB 1-CH-P-lC High Head Safety Injection or Charging Pumps provide high pressure flow for safety injection system and during normal operation, maintain pressurizer level, and seal water injection to the reactor coolant pumps. See drawing 11448-FM-BBB.

1-SI-P-lA 1-SI-P-lB Low Head Safety Injection pumps provides low pressure safety injection to core for long term cooling and as a backup to accumulators. See drawing 11448-FM-89A.

1-CS-P-lA 1-CS-P-lB Containment Spray Pump provides a cooled, chemically treated,

borated spray to reduce containment pressure following a loss of coolant accident.

l-RS-P-2A l-RS-P-2B See drawing 11448-FM-84A.

Outside Recirculation Spray Pumps aid the containment spray system in reducing contai~ment pressure rapidly following a loss of coolant accident. See drawing 11448-FM-84A.

1-RS-P-lA 1-RS-P-lB*

Inside Recirculation Spray Pump aid the containment spray system in reducing containment pressure rapidly following a loss of coolant accident. See drawing 11448-FM-84A.

6 l-FW-P-3A l-FW-P-3B l-FW-P-2 Auxiliary Feedwater pump supplies the steam generator with feedwater in the event of a complete loss of normal feedwater. loss See drawing 11448-FM-68A.

1-RH-P-lA 1-RH-P-lB The function of Residual Heat Removal Pumps is to remove heat energy from the core when the reactor.coolant system is below 350°F See drawing 11448-FM-87A.

1-CC-P-lA 1-CC-P-lB Component Cooling Water Pumps are used to supply water to remove heat from the Residual Heat Removal System. See drawings 11448-FM-72D.

l-CH-P-2A l-CH-P-2B Boric Acid Transfer Pumps supply boric acid to suction of charging pumps via normal coolant boron concentration and emergency makeup. See drawings 11448-FM-SSA.

l-CC-P-2A l-CC-P-2B Charging Pump Cooling Water Pump provide water to transfer heat from the charging pump mechanical seals. See drawing 11448-FM-71B.

1-SW-P-lOA 1-SW-P-lOB Charging Pump Service Water Pumps provides cooling water for charging pump cooling water systems. See drawings 11448-FM-71B.

7

1-SW-P-lA 1-SW-P-lB 1-SW-P-lC Emergency Service Water Pumps supply the required service water to the canal to provide for minimum safeguards operation in the unlikely event of a loss of site power coincident with a DBA. See drawing 11448-FM-71A.

EE-P-lA EE-P-lD EE-P-lF Fuel Oil Pumps supply fuel oil to emergency diesel generators wall mounted tank. See drawing 11448-FB-4B.

2.5 Pump Inservice Test Tables This tabulation identifies the pumps to be tested, code, class, required test quantities and frequencies. Relief from test require-ments is requested in cases where their test requirements have been determined to be impractical. Where relief is requested, technical justification is provided along with alternative test methods when applicable.

"'.. .. ~ . - . .. *-* .- ... _. ,.,, .. ---<:. -... ,. -~**- *' '*< --~* - .._,.__ ' .-. *: -- ,~'-. 1.1* - r ,l, PUMP INSERVICE TEST TABLE Pump ASME Inlet Discharge Diffierential Flow Bearing Pump Lubrication Relief Identification Class Pressure Pressure Pressure Rate Vibration Temperature Speed Level/Pressure Request 1-CH-P-lA 2 NA Q NA NA Q NR NA Q 0' 1, 2 1-CH-P-lB 2 NA Q NA NA Q NR NA Q 0' 1, 2 1-CH-P-lC 2 NA Q NA NA Q NR NA Q 0' 1, 2 1-SI-P-lA 2 NA Q NA Q Q NR NA Q* 0' 1, 3 1-SI-P-lB 2 NA Q NA Q Q NR NA Q* 0' 1, 3 1-CS-P-lA 2 Q Q Q Q Q NR NA Q 0, 1 1-CS-P-lB 2 Q Q Q Q Q NR NA Q 0, 1 l-RS-P-2A 2 NA Q NA NA Q NR NA Q* 0, 1, 4 l-RS-P-2B 2 NA Q NA NA Q NR NA Q* 0' 1, 4 1-RS-P-lA 2 NA NA NA NA NA NR NA NA 0, 1, 5 1-RS-P-lB 2 NA NA NA NA NA NR NA NA 0' 1, 5 l-FW-P-3A 3 Q Q Q NA Q NR NA Q 0, 1, 6 l-FW-P-3B 3 Q Q Q NA Q NR NA Q 0' 1, 6 l-FW-P-2 3 Q Q Q NA Q NR Q Q 0' 1, 6 1-RH-P-lA 2 CSD CSD CSD CSD CSD NR NA Q* 0' 1, 7 1-RH-P-lB 2 CSD CSD CSD CSD CSD NR NA Q* 0' 1, 7 1-CC-P-lA 3 Q Q Q NA Q NR NA Q 0' 1 1-cc.:..P-IB 3 Q Q Q NA Q NR NA Q O, 1

The following pumps are cooled by fluid through pump. Therefore, other pump parameters will ensure proper level of lubrication.

PUMP INSERVICE TEST TABLE Pump ASME Inlet Discharge Dif f ierential Flow Bearing Pump Lubrication Relief Identification Class Pressure Pressure Pressure Rate Vibration Temperature Speed Level/Pressure Request l-CH-P-2A 3 NA Q NA NA NA NR NA Q* 0, 1, 9 l-CH-P-2B 3 NA Q NA NA NA NR NA Q* 0, 1, 9 l-CC-P-2A 3 NA Q NA Q Q NR NA Q** 0, 1, 10 l-CC-P-2B 3 NA Q NA Q Q NR NA Q** O, 1, 10 1-SW-P-lOA 3 NA Q NA Q Q NR NA Q** 0, 1, 10 1-SW-P-lOB 3 NA Q NA Q Q NR NA g** O, 1, 10 1-SW-P-lA 3 NA g NA NA Q NR NA g 0, 1, 11 1-SW-P-lB 3 NA Q NA NA Q NR NA Q 0, l', 11 1-SW-P-lC 3 NA g NA NA g NA NA g 0, 1, 11

1-EE-P-lA 3 Q Q Q NA NA NR NA NA 0, 1, 12 1-EE-P-lD 3 Q g g NA NA NR NA NA 0, 1, 12 1-EE-P-lF 3 Q Q Q NA NA NR NA NA O, 1, 12

These pumps are cooled by fluid through pump. Therefore, other pump parameters will ensure proper level of lubrication.

- Pump bearings are carried in drive motor and are greased and lubricated, therefore, other parameters will ensure proper level of lubrication.

8 2.6 PUMP TEST PROGRAM RELIEF REQUEST Relief Request identify code requirements which are impractical for Surry Unit 1 and provide justification for the requested excep-tion. Where appropriate, we also propose alternate testing to be performed in lieu of the code requirements.

9 NOTE 0 PUMPS All IWP Program Pumps except l-FW-P-2.

SECTION XI CODE REQUIREMENTS FOR WHICH RELIEF IS REQUESTED Quarterly measurements of pump speed.

BASIS FOR REQUEST IWP-4400 does not require pump speed measurement if pump is directly coupled to a constant speed motor driver.

ALTERNATE TESTING PROPOSED None

__ -~,.,.:. ___ _

10 RELIEF REQUEST 1 PUMPS All IWP Program Pumps SECTION XI CODE REQUIREMENTS FOR WHICH RELIEF IS REQUESTED Measure pump bearing temperatures and vibration in mils.

BASIS FOR REQUEST Pump vibration and bearing temperature measurements are used to detect changes in the mechanical characteristics of a pump. Regular testing should detect developing problems, thus repairs can be initiated prior to a pump becoming inoperable. The ASME Section XI minimum standards require measurements of the vibration amplitude displacement in mils every three mbnths and bearing temperatures once per year.

Our proposed program is based on vibration readings in velocity units rather than vibration amplitude in mils displacement. This technique is an industry accepted method which is more sensitive to small changes than are indicative of developing mechanical problems and hence more meaningful. Velocity measurements detect not only high amplitude vibrations that indicate a major mechanical problem, but also I

the equally harmful low amplitude high frequency vibrations .due to misalignment in balance, or bearing wear that usually go undetected by simple displacement measurements.

In addition, these readings go far beyond the capabilities of a bearing temperature monitoring program. A bearing will be seriously

11 degraded prior to the detection of increased heat at the bearing

-housing. Quarterly vibration velocity readings should achieve a much higher probability of detecting developing problems than the once per year reading of bearing temperatures.

Bearing temperature data gathering test present problems which include the following: The enforced thirty minute run time causes problems for pumps having no recirculation test loop and the temperature of lubricating fluid will vary with ambient conditions and make meaningful data trending impractical. Therefore, the detection of possible bearing failure by a yearly temperature measurement is extremely unlikely. The small probability of detection of a bearing failure by temperature measurement does not justify the additional pump operating time required to obtain the measurements. In addition, it is impractical to measure bearing temperatures on many pumps.

ALTERNATE TESTING PROPOSED:

Pump vibration measurements will be taken in vibration velocity (in/sec). The evaluation of the readings will be per the attached table. For more information, see ASME Publication 78-WA/NE-5 and minutes of November 28, 1979 meeting of the Operating and Maintenance Working Group - Testing of Pumps and Valves in San Jose, California, dated January 9, 1980

ALLOWABLE RANGES OF TEST QUANTITIES(l)

ALERT RANGE REgUIRED ACTION RANGE LOW HIGH LOW HIGH QUANTITY ACCEPTABLE RANGE VALUES VALUES VALUES VALUES v When 0 < v < .15 in/sec 0 to .3 in/sec None .3 in/sec to None v > .45 in/sec r -

.45 in/sec v When .15 in/sec < v 0 to .45 in/sec None .45 in/sec to None v >

75 in/sec

< .3 in/sec r

.75 in/sec v When .3 in/sec < v 0 to .9 in/sec None .9 in/sec to None v > 1.5 in/sec

< .6 in/sec r

1.5 in/sec v When .6 in/sec < v 0 to 1.1 in/sec None 1.1 in/sec to None v > 1.5 in/sec

< 1.0 in/sec r

1.5 in/sec .,

'{ Where:

v = velocity measured in inches/second, peak.

vr = referenced velocity measurement (initial measurement after installation or rewor~)

(1) See ASME Technical Paper 78-WA/NE-5, Table 2

12 RELIEF REQUEST 2 PUMPS 1-CH-P-lA 1-CH-P-lB 1-CH-P-lC SECTION XI CODE REQUIREMENTS FOR WHICH RELIEF IS REQUESTED Measure Inlet Pressure, Differential Pressure and Flow BASIS FOR REQUEST Instrumentation not installed ALTERNATE TESTING PROPOSED

1) Design Change has been initiated for flow measurement instrumentation Proposed installation date is 12/1/83.

2) Suction pressure instrtimentation is not installed nor required, therefore differential pressure can not be calculated. These pumps are capable of producing greater than 2400 psig discharge pressure, while the suction pressure is normally 20 psig. Therefore, differential pressure developed by the pump is more than 100 times the suction pressure and a gage for suction pressure would not provide significant data. Therefore, we propose to observe Volume Control Tank Pressure using control room indication to assure repeated initial conditions for testing the pumps.

13

RELIEF REQUEST 3 PUMPS 1-SI-P-lA 1-SI-P-lB SECTION XI CODE REQUIREMENTS FOR WHICH RELIEF IS REQUESTED Measure Inlet Pressure and Differential Pressure BASIS FOR REQUEST

1) Inlet and differential pressure instrumentation not installed.

ALTERNATE TESTING PROPOSED These pumps take suction from the RWST for performance testing. The tank level has a minimum requirement by Technical Specification which will insure initial conditions for testing.

14 RELIEF REQUEST 4 PUMPS l-RS-P-2A l-RS-P-2B SECTION XI CODE REQUIREMENTS FOR WHICH RELIEF IS REQUESTED Measurement inlet pressure, Differential Pressure and Flow BASIS FOR REQUEST

1) Inlet Pressure, Differential Pressure and Flow instrumentation not installed.

ALTERNATE TESTING PROPOSED

1) Suction pressure instrumentation is not installed, the ref ore differential pressure cannot be calculated. Suction pressure is same for each test since suction pressure is only head of water ln filled pump casing. Design. Change has been initiated for flow measurement instrumentation. Proposed installation date is 12/1/83. Until Design Change is completed and Technical Specification Change 11113 for ASME Section XI is approved by NRG, the pumps will be flow tested at shutoff head.

15 RELIEF REQUEST 5 PUMPS 1-RS-P-lA 1-RS-P-lB SECTION XI CODE REQUIREMENTS FOR WHICH RELIEF IS REQUESTED Measurement Inlet Pressure, Discharge Pressure, Differential Pressure, Flow, Vibration, and Lubrication Level and Pressure.

BASIS FOR REQUEST Technical Specification 4.5.A.2 requires the pumps be dry tested. Testing of these pumps would require spraying water on components in containment. Also dry testing of pump will not give meaningful data.

ALTERNATE TESTING PROPOSED Motor current is measure monthly and compared with previous reading. Also it can be determined that pump shafts are turning by rotation sensors which indicate in Main Control Room.

16 RELIEF REQUEST 6 PUMPS 1-FW-P-3A 1-FW-P-3B 1-FW-P-2 SECTION XI CODE REQUIREMENTS FOR WHICH RELIEF IS REQUESTED Measure Flow.

BASIS FOR REQUEST Instrumentation not installed.

ALTERNATE TESTING PROPOSED All inservice inspection data is collected except flow, therefore, there is sufficient data collected for evaluation of pump performance. A Design Change has been initiated for flow measurement instrumentation. Proposed installation date is 12/1/83.

17 RELIEF REQUEST 7 PUMPS 1-RH-P-lA 1-RH-P-lB SECTION XI CODE REQUIREMENTS FOR WHICH RELIEF IS REQUESTED

1) Frequency of Pump Test.

BASIS FOR REQUEST

1) It is considered impractical to make a containment entry on a quarterly bases in order to test these pumps. These pumps are not engineered safety feature pumps. Operability will be determined each cold shutdown when system is placed into operation (but not more frequently than every three months).

ALTERNATE TESTING PROPOSED

1) Pump will be tested each cold shutdown (but not more frequently than every three months).

. ~. - .,.. .. .. * -,.._ * .,.,.,,._, .* , *** ._. *. *~***- _.,.r* """';.,., ** -. *" * ~* - ,._ ***-T***,** ,-* ~ .... ._,.-* -* ,,., -~*";""*' ,- *-

18 RELIEF REQUEST 9 PUMPS 1-CH-P-2A 1-CH-P-2B SECTION XI CODE REQUIREMENTS FOR WHICH RELIEF IS REQUESTED Measure inlet pressure, differential pressure, flow, and vibration.

BASIS FOR REQUEST

1) No instrumentation installed for inlet pressure, differential pressure and flow.

2) Pumps are totally incased in insulation, therefore, probes for vibration

can not get in contact with pumps for a reading.

ALTERNATE TESTING METHOD

1) These pumps take suction from Boric Acid Storage Tanks. Tank Level will be observed to establish initial condition of testing. A design change has been initiated to install inlet pressure gages so that inlet pressure can be measured and differential pressure calculated. No flow rate measurement device is currently installed. At this time, a method for collecting repeatable flow data has not been determined. The evaluation is still in progress.

2) Design Change has been initiated. Proposed completion date is 12/1/83.

19 RELIEF REQUEST 10 PUMPS 1-SW-P-lOA 1-SW-P-lOB 1-CC-P-2A 1-CC-P-2B SECTION CI CODE REQUIREMENTS FOR WHICH RELIEF IS REQUESTED Measure inlet pressure and differential pressure.

BASIS OF REQUEST

1) No installed instrumentation for inlet pressure and differential pressure.

ALTERNATE TESTING PROPOSED

1) A design change has been initiated to install inlet and discharge pressure gages. Also, design change will add accurate flow measurement devices. The design change proposed completion date is 12/1/83. Flow rate and vibration will be monitored for pump performance until

.,' completion of design change .

~*

fi

20

RELIEF REQUEST 11 PUMPS 1-SW-P-lA 1-SW-P-lB 1-SW-P-lC SECTION XI CODE REQUIREMENTS FOR WHICH RELIEF IS REQUESTED Measure inlet pressure, differential pressure, and flow rate.

BASIS FOR REQUEST No installed inlet pressure, differential pressure and flow instrumentation exists. Pumps take suction from James River through seismic structure. Also, discharge through a seismic structure. These restrictions makes it impractical to install instrumentation on these pumps.

ALTERNATE TESTING PROPOSED None, but discharge pressure, vibration, and lubricant level are monitored which should be adequate indication of pump performance

21 RELIEF REQUEST 12 PUMPS EE-P-lA EE-P-lD EE-P-lF SECTION XI CODE REQUIREMENTS FOR WHICH RELIEF IS REQUESTED Measure Inlet pressure, differential pressure, flow rate, lubrication level or pressure and vibration.

BASIS FOR RELIEF Code interpretations consider these pumps to be outside the scope of ASME Section XI. Hence all testing of these pumps is voluntary.

Attached is copy of specif~ed inquiry and reply on which relief is based.

ALTERNATE TESTING PROPOSED Monitor Pump discharge pressure *

- - ---.-* e* . *-*.,... - - ..,. .---.---*------ .**--~---- ..,..,..-~- .,..,.. ---

22

INQUIRY AND REPLY AS SENT TO INQUIRER 08/14/81 FILE NUMBER INQUIRER COMPANY REPLY SENT BC/77 /666 WPP SS 78/02/17 SUBJECT SCOPE OF SECTION XI, DIVISION 1 Question:

Is it the intent of Subarticle IWA-1100 that the rules and requirements of Section XI, Division 1 for inservice inspection of Class 1, 2 & 3 pressure retaining components (and their supports) be applied only to water and steam systems in light water cooled nuclear power plants?

Reply:

Systems containing other than steam or water were not originally considered by the committee in formulating the rules in Section XI; they may, however, be included for further consideration and for revisions to future editions of Section XI. The requirements shown in Section XI, Article IWA-1100 on Scope and Responsibility, specifically paragraph IWA-1400, requires the owner of the nuclear plant to determine the appropriate code, class or classes for each component of the nuclear power plant to be examined according to Section XI rules

23

3.0 VALVE INSERVICE TEST PROGRAM DESCRIPTION 3.1 Program Development Philosophy Surry Power Station Unit 1 is a Pressurized Water Reactor being operated in compliance with the ASME Boiler and Pressure Vessel Code. The code requires periodic testing of certain safety related valves in order to verify their operability and physical integrity.

The Surry Unit 1 Valve Inservice Test Program satisfies these requirements.

The program will detect potentially adverse changes in the mechanical condition of valves within the scope of Section XI, Subsection IWV of the Code. This includes all valves "which are required to perform a specific function in shutting down a reactor

to the cold shutdown condition or in mitigating the consequences of an accident. 11 *It is important to note that the scope of ASME Section XI, and the Surry Program for its implementation includes many values which are not required to operate to meet FSAR license condition of hot shutdown nor limiting conditions in the plant Technical Specifications. Therefore corrective action as specified in Subsection IWV will be applied as much as practical but is not interpreted to supercede or append any existing limiting condition of operation.

To *generate the Surry Unit 1 Valve Program, all ASME Class 1, 2 and 3 valves were analyzed to determine their required type, and frequency of testing. The valves to be tested under Section *xI, Subsection IWV commitments are listed, by system and drawing, in the

Valve Test Tables.

23 3.0 VALVE INSERVICE TEST PROGRAM DESCRIPTION 3.1 Program Development Philosophy Surry Power Station Unit 1 is a Pressurized Water Reactor being operated in compliance with the ASME Boiler and Pressure Vessel Code. The code requires periodic testing of certain safety related valves in order to verify their operability and physical integrity.

The Surry Unit 1 Valve Inservice Test Program satisfies these requirements.

The program will detect potentially adverse changes in the mechanical condition of valves within the scope of Section XI, Subsection IWV of the Code. This includes all valves "which are required to perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of an accident." It is important to note that the scope of ASME Section XI, and the Surry Program for its implementation includes many values which are not required to operate to meet FSAR license condition of hot shutdown nor limiting conditions in the plant Technical Specifications. Therefore corrective action as specified in Subsection IWV will be applied as much as practical but is not interpreted to supercede or append any existing limiting condition of operation.

To generate the Surry Unit 1 Valve Program, all ASME Class 1, 2 and 3 valves were analyzed to determine their required type, and frequency of testing. The valves to be tested under Section XI, Subsection IWV commitments are listed, by system and drawing, in the Valve Test Tables.

24

The Surry Unit 1 is coI!llllitted to meeting the requirements of both 10 CFR 50, Appendix J, and Seeton XI. Each of these documents addresses particular but slightly different concerns with respect to valve leakage. Each contains guidance for valve leak rate testing.

Appendix J is primarily concerned with leakage out of containment subsequent to Loss of Coolant Accident (LOCA). It requires leak rate testing of containment isolation valves at the maximum differential pressure (~P) expected during an accident.

Section XI requires leak rate testing of all valves for which seat leakage "is limited to a specific maximum amount" and that testing be performed at the valves operating ~p unless a lower ~p can be shown to give conservative results. Operating ~p may be many times the maximum post-LOCA-~P. Plant Technical Specifications address leak rate testing and imposed specific testing requirements.

The testing requirements imposed by the various sources are not identical nor are they mutually exclusive. It is anticipated that Appendix J testing will satisfy Section XI Leak Rate testing.

However, some valves require only Section XI testing. Valves are identified which are subject to leak rate testing under the scope of Section XI, Subsection IWV.

The Code recognized that certain of its requirements may be impractical for a specific plant and contains provisions for requesting relief from impractical requirements.

r:,

25 The relief requests for the Valve Inservice Test Program identify testing impracticalities, provide technical basis for the request and propose alternate testing where*warranted.

The stroke times of solenoid controlled, air operated valves is both extremely rapid and subject to considerable variation.

Exception is taken to complying with stroke time variations defined by Artical IWV-3410 (c) (3). The valve stroke timing tolerance specified is based on a reference valve. This will not exceed the maximum stroke time.

VEPCO is confident that Surry Unit 1 Valve Inservice Test Program complies with the intent of all applicable codes, regulations and guidelines 'and that it will make a positive contribution to the safe operation of the plant.

3.2 Program Implementation The Valve Test Program will be executed as part of the normal plant surveillance routine. Two types of test will be conducted as part of the Valve Test Program:

1) Valve Operability Tests

2) Valve Leakage Tests

3) Safety Valve Test The Operability Tests will verify: 1) the valve responds to control commands, 2) the valve stroke time is within specific limits and, 3) remote position indication accurately reflects the observed valve* position. Remote valve position indication will be verified every two years.

26 Fail safe valves will be tested by observing the valve operation upon loss of actuating power. In most cases, this can be accomplished using normal control circuits.

The following clarification shall apply to those valves which are scheduled to be excercised during cold shutdown:

"Valve testing shall commence not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after reaching cold shutdown and continue until complete or unit is ready to return to power.

Completion of the valve testing is not a prerequisite to return to power. Any testing not completed at one cold shutdown should be performed during the subsequent scheduled cold shutdowns to meet the code specified testing frequency."

Valve Leakage Test will verify valves are leak 'tight in accordance with Appendix J or ASME Section XI. Relief and Safety valves are not required to leak rate tested (IWV-3512) and are not included as valve to be leak tested.

Safety and Relief valves setpoints are tested in accordance with PTC-25.3-1976 as directed by IWV-3512. Main Steam Safety valves will be tested in accordance with Section 4.091(a)(2). All other safety and relief valves will be tested in accordance with Section 4.091(c)(l).

3.3 PROGRAM ADMINISTRATION The operations and engineering staff at Surry Power Station is responsible for administration and execution of the Valve Inservice Program. The Program will be officially implemented on December 22, 1982 and will govern valve testing for a 120 month period. Prior to end of 120 month period, the program will be reviewed and upgraded to assure continued compliance with 10 CFR 50.55a (g) (4). The program will be updated a minumum of at least once every 40 months or for a new system, relief request, etc.

27 To insure compliance of the Valve Program, a training program will be established for inservice test personnel.

3.4 VALVE INSERVICE TEST TABLES The Valve Test Tables are the essence of the Valve Program to meet ASME Section XI, Subsection IWV requirements. The tables reflect the positions taken in support of the relief requests to aid the reader in the interpr.etation of the Tables, brief explanations of the Table headings and abbreviatoins are provided.

1) Valve Number - Each valve in the plant has a unique "tag" number whi'ch identifies the system to which the equipment belongs and type of equipment.

2) Drawing Locaton - The specific coordinates of each valve are supplied to facilitate location of the valves on the flow diagrams provided.

3) Function - A brief description of the function of the valve.

4) Code Class - ASME Code Class of each valve as per 10 CFR 50.55a and Regulatory Guide 1.26.

NOTE: - are for non-class valves

5) Category - Categories are defined by ASME Section XI. Subsection IWV. Each valve has specific testing requirements which are determined by the category to which it belongs.

6) Size - Nominal pipe diameter to which valve connects is given in inches.

7) Valve Type - The following abbreviatons are used to describe valve type:

CK - Check GA - Gate RV - Relief BF - Butterfly SF - Safety SCK - Stop Check BA - Ball PL - Plug GL - Globe DA - Diaphram

8) Actuator Type - The following abbreviations are used to describe actuator types. Valves may be actuated in more than one way.

. i 28 SA Self Actuating (actuated by a change in system parameters such as Flow, or Pressure, e.g., check and relief valves).

MO Motor Operated PN Pneumatic (Air Operated)

MAN - Manually Operated sov - Electronic solonoid Operated Valves

9) Normal Position - The following abbreviations are used to describe valve positions:

0 - Open c - Closed OC - Open or Closed T - Throttled

10) Test Required - Testing requirements identified for the valves are identified here.

ST - Stroke Times shall be measured per Section XI subarticle IWV-3410 or as modified by specific relief request.

EV - Exercise Valve for operability at least once every 3 months per Section XI subarticle IWV-3410 or as modified by specific relief request.

LT - Leak Test shall be performed per Section XI subarticle IWV-3420 or as modified by specific relief request.

Valves marked by asterisk (*) will be tested in accordance with Appendix J.

' CV - Check Valves shall be exercised at least once every 3

~.* months per section XI subarticle IWV-3520 or as modified by specific relief request.

VP - Valve Position Indication Verification shall be verified per Section XI subarticle IWV-3300 or as modified by specific relief request.

SP - Set points of safety and relief valves shall be tested per Section IX subarticle IWV-3510 or as modified by specific relief request.

1 Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Main Steam Drawing Number: 11448-FM-64A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gor}1: Size T}1:~e Tn~e Position Reg,uired Reg,uest SV-MS-101A,B,C B-3, B-4, B-6 Main Steam Safety Valves 2 c 4 SF SA c SP 1 SV-MS-102A,B,C C-3, c-4, C-6 Main Steam Safety Valves 2 c 6 SF SA c SP 1 SV-MS-103A,B,C B-3, B-4, B-6 Main Steam Safety Valves 2 c 6 SF SA c SP 1 SV-MS-104A, B; C B-3, B-4, B-6 Main Steam Safet}1: Valves 2 c 6 SF SA c SP. 1 SV-MS-105A,B,C C-3, C-4, C-6 Main Steam Safet}1: Valves 2 c 6 SF SA c SP 1 TV-MS-lOlA,B,C D-3, D-5, D-7 Main Steam Line Trip 2 B 30 CK PN 0 EV,ST 2 Valves VP NRV-MS-101A D-3 NRV-MS-101B D-5 Main Steam Non Return NRV-MS-101C D-6 Valves 2 c 30 SCK MOV 0 CV 3 RV-MS-101A C-2 RV-MS-101B B-4 Main Steam PORV 2 c 4 RV SA c SP 1 RV-MS-101C C-6 SOV-MS-102A F".""8 Main Steam to Turbine 2 B 3 GA PN c EV,ST None SOV-MS-102B G-8 Driven Aux. FW Pum:e VP HCV-MS-104 B-4 Decay Heat Release 2 B 4 GA PN c EV,VP 32 Control Valve TV-MS-109 F-7 Main Steam Drain to 2 B 3 GA PN 0 EV,ST None Condenser VP

Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves 2

System Name: Main Steam Drawing Number: 11448-FM-64A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Reqest TV-MS-110 E-7 Main Steam Drain to Blow- 2 B 2 GA PN 0 EV,ST NO down VP 1-MS-176 F-8 Main Steam to Turbine 2 c 3 CK SA c CV NO 1-MS-178 F-8 Driven Auxiliary FW 1-MS-182 F-8 check valves

Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves 3

System Name: Aux. Steam and Air Removal Drawing No. 11448-FM-66A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request TV-SV-102A L-2 Air Removal Direct to 2 A 6 GA PN c LT*, EV, None Reactor-Containment St, VP l-VP-12 L-1 Air Removal Direct to 2 AC 6 CK SA c LT* None Reactor Containment

4 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Feedwater Drawing No. 11448 - FM - 68A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request 1-FW-27 C-2 Auxiliary Feedwater Header l-FW-58 B-4 Check Valves at Main Feed- 2 c 3 CK SA c CV 4 1-FW-89 B-5 Water Header 1-FW-131 C-6 Auxiliary Feedwater Header :I 1-FW-133 *C-6 Check Valves at Contain- 2 c 6 CK SA c CV 4 .!

l-FW-136 C-6 ment Penetration *I 1-FW-138 C-6 'I

1 1-FW-142 D-7 Auxiliary Feedwater Pump 3 c 6 CK SA c CV 4 l-FW-157 E-7 Discharge Check Valves 1-FW-172 'F-7 MOV-151A,B,C, B-6, B-6, B-6 Auxiliary Feedwater to EV, ST, D,E,F B-6, c-6, C-6 Steam Generators 2 B 3 GL MOV 0 VP None 1-FW-144 D-7 Auxiliary Feedwater Pump 1-FW-159 F-7 Recirculation Check 3 c 1 CK SA c CV None 1-FW-174 G-7 Valves 1-FW-10, 12 C-2, c-2 Main Feedwater Check Valves 2 c 14 CK SA 0 CV 5 41, 43 C-4, C-4 at Containment Pene-72, 74 C-5, C-5 trations

-* 5 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Auliliary Feed Cross Connect Drawing No. 11448 - FM - 68B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request MOV-FW-160A J-5 Cross-Connect for Unit #1 EV, ST, MOV-FW-160B J-6 -Aux. Feed. from Unit #2 3 B 6 GL MOV c VP None 1-FW-272 I-7 Cross-connect for Unit #1 1-FW-273 I-7 Aux. Feed. for Unit #2 3 c 6 CK SA c CV 4 Check Valves at Cont. Penet.

1-FW-309 H-7 Cross-connect for Unit #1 1-FW-310 H-7 Aux. Feed. for Unit #2 3 c 6 CK SA c CV 4 Check Valves at Cont. Penet.

Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves 6

System Name: Service Water Drawing No. 11448 - FM - 71A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request MOV-CW-106A E-4 MOV-CW-106B E-4 Condenser inlet 3 B 96 BF MOV 0 EV, ST None MOV-CW-106C F-4 Isolation Valves VP MOV-CW-106D F-4 MOV-SW-102A E-6 Service Water to Component EV, ST, MOV-SW-102B F-6 Cooling Water Heat Ex- 3 B 42 BF MOV 0 VP None chan ers MOV-SW-103A B-6 Service Water to Recircu- EV, ST, MOV-SW-103B B-6 lation Spray Heat Ex- 3 B 30 BF MOV c VP 6 MOV-SW-103C D-6 changers MOV-SW-103D E-6 MOV-SW-104A A-2 Recirculation Spray Heat EV, ST MOV-SW-104B B-2 Exchangers Suction Isola- 3 B 24 BF MOV 0 VP None MOV-SW-104C C-2 tion Valves MOV-SW-104D C-2 MOV-SW-105A A-2 MOV-SW-105B A-2 Recirculation Spray Heat EV,ST MOV-SW-105C B-2 Exchanger Discharge Isola- 3 B 24 BF MOV 0 VP None MOV-SW-105D C-2 tion Valves MOV-SW-106A D-4 Recirculation Spray Heat EV,ST MOV-SW-106B D-4 Exchangers Cross-Connect 3 B 36 BF MOV 0 VP None Valves

7 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Service Water Drawing No. 11448 - FM - 71A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request MOV-SW-101A B-4 Bearing Cooling Water EV, ST MOV-SW-101B C-4 Heat Exchanger Isolation 3 B 36 BF MOV 0 VP None Valves MOV-CW-lOOA E-2 MOV-CW-lOOB E-2 Condenser Discharge EV, ST MOV-CW-lOOC F-2 Isolation Valves 3 B 96 BF MOV 0 VP None MOV-CW-lOOD F-2 1-SW-206 A-1 Containment Isolation 1-SW-208 A-1 Valves for Service Water 2 A 2 GA Man c LT* - None Drains to Heat Exchan~er

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8 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Circulating and Service Water Drawing No. 11448 - FM - 71B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number L-ocation Function Class gory Size Type Type Position Required Request 1-CC-764 D-6 Charging Pump Cooling l'-CC-752 G-6 Water Pump Discharge Check 3 c 2 CK SA oc CV None Valve 1-SW-113 D-8 Charging Pump Senrice 1-SW-108 G-8 Water Pump Check Valve 3 c 2 CK SA oc CV None

9 Surry Power Station Unit 1 Inservice Testing ,,

ASME Code Class 1, 2, and 3 Valves 1!

i:

System Name: Component Cooling Drawing No. 11448 - FM - 72A

~I

/

Valve Drawing Code Cate- Valve Actuator Normal Test Relief ,,

,

Number Location Function. Class gory Size Type Type Position Required Request RV-CC-119A L-2 Component Cooling from RHR RV-CC-119B L-3 Heat Exchanger Relief 3 c 1~ RV SA c SP 1 Valve 1-CC-176 B-1 Component Cooling to RHR 'I l-CC-177 B-1 Heat Exchanger Check Valve 2 c 18 CK SA oc CV 7 l-CC-1 A-2 Component Cooling to l-CC-58 A-2 Reactor Coolant Pumps 2 c 6 CK SA 0 CV 8 1-CC-59 A...:.2 TV-CC-105A D-8 Component Cooling from 2 B 6 BA PN 0 ST 8 TV-CC-105B D-8 Reactor Coolant Pumps EV, VP TV-CC-105C E-8

'I Component Cooling from 2 B 2~ GL PN 0 ST 8 TV-CC-107 D-8 Reactor Coolant Pumps EV, VP TV-CC-109A F-8 Component Cooling from 2 B 18 BP PN 0 ST NONE TV-CC-109B F-9 RHR Heat Exchangers EV, VP RV-CC-116A B-3 Component Cooling Reactor 3 c 1 RV SA c SP 1 RV-CC-116B B-5 Coolant Pump RV-CC-116C B-8 RV-CC-124 F-1 Component Cooling 3 c 3/4 RV SA c SP 1 Piping Relief Valve RV-CC-118 G-4 Component Cooling Excess 3 c 1 RV SA c SP 1 Letdown Heat Exchanger Relief

Surry Power Station Unit 1 Inservice Testing

10 ASME Code Class 1, 2, and 3 Valves System Name: Component Cooling Water Drawing No. 11448 - FM - 72B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request 1-CC-242 C-4 Component Cooling to l-CC-233 E-4 Reactor Containment Air 2 c 6 CK SA 0 CV, LT* 7 1-CC-224 I-4 Recirculation Coolers TV-CC-llOA D-3 Component Coolirig from 2 B 6 BF PN 0 EV, ST NONE TV-CC-llOB F-3 Reactor Containment Air VP TV-CC-llOC H-3 Recirculation Coolers

11 Surry Power Station Unit 1 lnservice Testing ASME Code Class 1~ 2, and 3 Valves System Name: Component Cooling Water Drawing No. 11448 - FM - 72C Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request Component Cooling to RV-CC-lllA 1-3 Fuel Pit Coolers 3 c 3/4 RV SA c SP 1 RV-CC-lllB 1-4 Relief Valves Component Cooling to Non-RV-CC-110 1-5 Regenerative Heat 3 c 1 RV SA c SP 1 Exchanager Relief va*1ve RV-CC-109 1-7 Component Cooling to 3 c 1 RV SA c SP 1 Seal Water Heat Exchan~er Relief Valve

12 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Component Cooling Water Drawing No. 11448 - FM - 72D Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request 1-CC-557 C-2 Component Cooling Pump 1-CC-563 C-2 Discharge Check 3 c 18 CK SA oc CV None RV-CC-123 A-1 Component Cooling Surge 3 c RV SA c SP 1 Tank Relief Valve

Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves 13 System Name: CompRessed Air Drawing No. 11448 - FM - 75C Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request Back up Instrument Air 1-IA-446 A-2 to Containment 2 A 2 GA Man c LT* None Back up Instrument Air to 2-IA-446 A-2 Containment from Unit 2 2 A 2 GA Man c LT* None

Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves 14 System Name: CompRessed Air Drawing No. 11448 - FM - 75E Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request Instrument Air to Contain-1-IA-939 G-5 ment 2 AC 2 CK SA 0 CV, LT* 9 Instrument Air to Contain-1-IA-938 G-5 ment 2 AC 2 CK SA 0 CV, LT* 9

Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves 15 System Name: CompRessed Air System Drawing No. 11448 - FM - 75G Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request 1-SA-62 D-7 Service Air to Containment 2 A 2 GA Man c LT* None

.. 1-SA-60 E-7 Service Air to Containment 2 A 2 GA Man c LT* None i*.

Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves 16 System Name: Containment Instrument Air Drawing No. 11448 - FM - 75J Valve Drawing . Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request TV-IA-101A K-7 Instrument Air Suction LT*, EV TV-IA-lOlB J-7 from Containment 2 A 3 GA PN 0 ST, VP None Instrument Air Discharge LT*, EV TV-IA-100 K-1 to Containment 2 A 2 GA PN 0 ST, VP None

17 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Boron Recovery System Drawing No. 11448 - FM - 79A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request SV-BR-100 G-5 Gas Stripper Relief c 2" SF SA c SP 1 RV-BR-120 G-1 Gas Stripper Surge c 1" RV SA c SP 1 Tank Relief RV-BR-108 A-5 Primary Drain Tank c 4" RV SA c SP 1 Relief

Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves 18 System Name: Boron Recovery System Drawing No. 11448 - FM - 79B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request SV-BR-101A C-1 Boron Evaporator and c 10" SF SA c SP 1 SV-BR-101B H-1 Boron Overhead Condenser Relief RV-BR-115 K-5 Evaporator Bottoms Tank c 2" SF SA c SP 1 Relief

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19 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Sampling System Drawing No. 11448 - FM - 82B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request TV-SS-103A D-1 Residual Heat Removal LT*, EV TV-SS-103B E-1 System Sample 2 A 3/8 GA sov c ST, VP None TV-SS-lOOA D-1 Pressurizer Liquid Space LT*, EV TV-SS-lOOB E-1 SamEle 1 A 3/8 GA sov c ST, VP None TV-SS-101A D-1 Pressurizer Vapor Space LT*, EV TV-SS-101B E-1 SamEle 1 A 3/8 GA sov c ST, VP None TV-SS-106A D-2 Primary Coolant Hot Leg LT*, EV TV-SS-106B E-2 SamEles 1 A 3/8 GA sov c ST, VP None TV-SS-102A D-2 Primary Coolant Cold Leg LT*, EV TV-SS-102B E-2 Sam:ele 1 A 3/8 GA sov c ST, VP None TV-SS-104A D-2 Pressurizer Relief Tank LT*, EV TV-SS-104B E-2 Gas s;eace SamEle 2 A 3/8 GA sov c ST, VP None

20 Surry Power Station Unit l Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Vents and Drains Drawing No. 11448 - FM - 83A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Ty:ee Ty:ee Position Reg,uired Reguest Reactor Containment Sump LT*, VP TV-DA-lOOB A-8 Pump Discharge Isolation 2 A 2 GA PN c EV, ST None TV-DA-103A A-6 Post Accident Sample LT*, VP TV-DA-103B Return Line 2 A 2 GA PN c EV, ST None 1-VA-l A-3 Primary Vent Pot Vent 2 A 2 GA PN c LT* None Primary Drain Transfer LT*, VP TV-DG-108B A-3 Pum:e Discharge Isolation 2 A 2 GA PN c EV, ST None LT*, VP TV-VG-109B A-1 Gas Vent Header Isolation 2 A 2 GA PN c EV, ST None

21 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Vents and Drains Drawing No. 11448 - FM - 83B

.Valve Drawing Code Cate- Vaive Actuator Normal Test. Relief Number Location Function Class gorl'.: Size Tn~e Tn~e Position Reg,uired Reguest

' Reactor Containment Sump LT*, EV TV-DA-lOOA H-8 PumE Discharge Isolation 2 A 2 GA PN c ST, VP None 1-VA-9 J-5 Primary Vent Pot Vent 2 A 2 GN MAN c LT* None Primary Drain Transfer LT*, EV TV-DG-108A L-5 PumE Discharge Isolation 2 A 2 GA PN c ST, VP None LT*, EV TV-VG-109A L-2 Gas Vent Header Isolation 2 A 2 GN PN 0 ST, VP None

'l

' ~

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23 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Containment Vacuum and Leakage Monitoring Drawing No. 11448 - FM - 85A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request TV-LM-lOOA E-3 TV-LM-lOOB E-3 TV-LM-lOOC E-3 TV-LM-lOOD E-3 Leakage Monitoring System LT*, EV TV-LM-lOOE E-3 Isolation 2 A 3/8 GA PN c ST, VP None !

TV-LM-lOOF E-3 i TV-LM-lOOG D-3 TV-LM-lOOH E-3 Containment Air Ejector HCV-CV-100 J-5 Isolation 2 A 8 GA PN c LT*, VP None Containment Air Ejector l-CV.-2 I-5 Isolation 2 A 8 GA Man c LT* None TV-CV-150A H-7 TV-CV-lSOB H-7 Containment Vacuum Pump LT*, EV TV-CV-lSOC H-8 Suction Isolation 2 A 2 GA PN 0 VP, ST None TV-CV-lSOD H-8

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24 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Reactor Coolant System Drawing No. 11448 - FM - 86A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request HCV-1556A A-2 HCV-1556B A-7 Loop Fill Boundary 1 A 2 GA PN c LT, VP 30 HCV-1556C L-2 SOV-RC-lOOA-1 H-7 SOV-RC-lOOA-2 H-7 Reactor Vessel Head Vent 2 B 1 PN c EV, ST 31 SOV-RC-lOOB-1 H-7 SOV-RC-lOOB-2 H-7 i

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Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves

25 System Name: Reactor Coolant Drawing No. 11448 - FM - 86B Valve* Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request SV-1551-A F-4 SV-1551-B G-4 Pressurizer Safety Valves 1 AC 6 SF SA c SP, LT 1, 30 SV-1551-C H-4 Primary Grade Water to LT*, EV TV-1519A A-6 PRZ Relief Tank 2 A 3 GA PN c ST, VP None Primary Grade Water to 1-RC-160 B-7 PRZ Relief Tank 2 AC 3 CK SA c LT*, CV 9 MOV-1535 I-4 Power Operated Relief EV, ST MOV-1536 I-5 Block Valves 1 A 3 BF MOV 0 VP, LT 30 PCV-1456 J-4 Pressurizer Power Operated EV, ST PCV-1456C J-5 Relief Valve 1 A 3 GA PN c VP, LT 30 SOV-RC-lOlA-1 1-6 Pressurizer Head Vent 2 B 1 PN c EV, ST 31 SOV-Rc..:..101A-2 J-6 SOV-RC-lOlB-1 1-6 SOV-RC-lOlB-2 J-6

26 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Residual Heat Removal Drawing No. 11448 - FM - 87A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gorl'.: Size T:n~e T;y:Ee Position Reguired Reg,uest MOV-1700 H...:7 RHR Suction from Reactor ST, EV MOV-1701 H-7 Coolant System 1 A 4 GA MO c LT, VP 12, 30 MOV-1720-A K-5 RHR Discharge to Reactor ST, EV MOV-1720-B K-5 Coolant S;y:stem 1 A 10 GA MO c LT, VP 13' 30 RV-1721 I-4 RHR System Relief Valve 2 c 3 RV SA c SP 1 1-RH-5 D-6 RHR Pump Discharge Check 1-RH-11 B-6 Valve 2 c 10 CK SA c CV 11 MOV-RH-100 K-3 RHR to RWST 2 A 6 GA MO c LT*, VP None

Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves 27 System Name: Chemical and Volume Control Drawing No. 11448 - FM - 88A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request l-Ch C-7 Boric Acid Transfer Pump 1-Ch-92 D-7 Discharge Valve 3 c 2 CK SA oc CV None RV-1322 K-5 Batching Tank Heating c 2 RV SA c SP 1 Jacket Relief

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29 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves Systetn Name: Chemical and Volume Control Drawing No. 1144B - FM - BBB Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request MOV-12B9A B-5 Normal Charging Header LT*, EV Isolation 2 A 4 GA MOV 0 ST, VP 19 RCS Loop Fill Header LT*, EV FCV-1160 A-3 Isolation 1 A 2 GL PN c VP None Seal Water Return Line RV-13B2-B F-3 to VCT 2 c 2 RV SA c SP 1

. *',~' .. , '* "' *..... '**.** *: *. '. *:.* *, :.. '-'."'"" . * <' , , , , ..... : .** . * - * *. . . r.*~ ~*

30 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Chemical and Volume Control Drawing No. 11448 - FM 88C Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gorx Size Tx:Ee Tx:Ee Position Reg,uired Reguest RV-1203 H-1 Letdown Header Relief 2 c 2 RV SA c SP 1 HCV-1200A H-2 HCV-1200B H-2 LT*, EV HVC-1200C H-2 Letdown Orifice Isolation 2 A 2 GA PN oc ST, VP None Seal Water Return to RV-1382A H-4 Pressurizer Relief Tank 1 AC 2 RV SA c SP 1, 30 l-CH-309 J-3 Normal Charging 2 AC 4 CK SA 0 CV, LT* 9 Isolation Check Valve

,, "**~"** ** .* .. *., ~.; ~*;.- :*, '*:"'~ .c .-. ~ <\-, ,._. **. "'< ;:>~*\ :. r." :* *'.; ;*~*-* ....* -1.*'**'* ;-< ~** \"*" *., ** r_:. ** , (*"* :.-* * :, ,* *** .<'*;<.\ . , - .,-.. **:;*. ., *.;**:.; . **::' ~ .. ' ... ~* ; _, I ,.. *'. **.... . . " . .. : '. .

~ .* . ,_- . ;**.- .** .....*.:*:" (.*.*>,:;.

31 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Safety Injection Drawing No. 11448 - FM 89A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request Low Head Safety Injection Pump Suction from Contain- LT*, EV MOV-1860A, B B-8, E-8 ment Sump 2 A 12 GA MOV c ST, VP None Low Head Safety Injection Pump Suction from Contain-1-SI-56, 47 C-8, F-8 ment SumE Check 2 c 12 CK SA c CV 20 Low Head Safety Injection Pump Suction from RefueLing EV, ST MOV-1862A, B G-9, G-8 Water Storage Tank 2 B 12 GA MOV 0 VP None Low Head Safety Injection Pump Suction from RefueLing l-SI-46A, B G-9, G-8 Water Storage Tank Check 2 c 12 CK SA c CV 21 Low Head Safety Injection 1-SI-58, 50 D-7, G-7 PumE Discharge Check 2 c 10 CK SA c CV 21 Low Head Safety Injection Pump Discharge to High Head EV, ST MOV-1863A, B E-6, G-6 Safety Injection Pump 2 B 8 GA MOV c VP Suction None Low Head Safety Injection MOV-1885A, B C-7, G-6 Pump Recirculation to EV, ST C, D G-6, C-7 RefueLing Water Storage 2 B 2 GA MOV 0 VP None Tank Low Head Safety Injection Pump Recirculation to l-SI-61, 53 C-6, G-6 RefueLing Water storage 2 c 2 CK SA c CV None

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32 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Safety Injection Drawing No. 11448 - FM - 89A Valve Drawing Code Cate- Valve Actuator Normal Test Relief

Number Location Function Class gory Size TyEe Tl:Ee Position Reg,uired Reg,uest Low Head Safety Injection Pump Discharge to Reactor EV, LT*

MOV-1864A, B D-6, G-5 Coolant System Cold legs 2 A 10 GA MOV 0 ST, VP None RV-1845A, B C-6, D-5 Low Head Safety Injection 2 c 1 RV SA c SP 1 C, C-5 Flow Path Relief Low Head Safety Injection to Reactor Coolant System LT*, EV

-~

, MOV-1890 A, B B-6, B-5 Hot Legs 2 A 10 GA MOV c ST, VP None Low Head Safety Injection to Reactor Coolant System LT*, EV MOV-1890C B-6 Cold Legs 2 A 10 GA MOV 0 ST, VP 22 i

MOV-1869A, B A-3, I-3 High Head Safety Injection LT*, EV 1842 A-1 to Reactor Coolant System 2 A 3 GA MOV c ST, VP 23

'{

Boron Injection Tank LT*, EV MOV-1867 C, D B-1, B-2 Outlet Isolation 2. A 3 GA MOV c ST, VP 24

1 Boron Injection Tank EV, ST MOV-1867 A, B I-2, I-2 Inlet Isolation 2 B 3 GA MOV c VP 25

~ ,,. . " -.. -.. ~~

33 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Safety Injection Drawing No. 11448 - FM - 89A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request Boron Injection Tank EV, ST ::

TV-1884A H-1 Recirculation 2 B 1 GA PN 0 VP None Boron Injection Tank EV, ST TV-1884B, C H-1, G-2 Recirculation 3 B 1 GA PN 0 VP None Boron Injection Tank RV-1857 D-1 Relief 2 c 3/4 RV SA c SP 1 LT*, EV TV-SI-100 B-4 Nitrogen Accumulators 2 A 1 GA PN 0 ST, VP None 1-SI-73 A-5 Accumulators Isolation 2 A 3/4 GL Man c LT* None 1-SI-32 A-5 Accumulator Isolation 2 A 1 GL Man c LT* None 1-SI-150 E-1 Boron Injection Tank 2 A 1 GL Man 0 LT* None High Head Safety Injection 1-SI-174 C-2 to Reactor Coolant Sistem 2 A 3/4 GA Man c LT* None

34 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Safety Injection Drawing No. 11448 - FM - 89B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request RV-1858 A, B C-4, G-5 Accumulator Tank Relief c C-7 2 c 1 RV SA c SP 1 1-SI-107, 109 C-5, A-5 128, 130 G-7, A-7 145, 147 C-8, A-9 Accumulator Discharge Check 1 AC 12 CK SA c CV, LT 26 MOV-1865 A, B C-5, G-6 EV, ST c C-8 Accumulator Discharge 2 B 12 GA MOV 0 VP None 1-SI-88, 91 A-2, A-2 94, 238 A-3, B-2 Safety Injection to RCS 239, 240 B-2, A-3 Hot Le~s 1 AC 6 CK SA c CV, LT 27, 30 1-SI-235, 236 B-1, B-1 High Head Safety Injection 237 B-2 to RCS Cold Le~s 1 AC 2 CK SA c CV 27 1-SI-241, 242 B-1, B-1 Low Head Safety Injection 243 B-2 to RCS Cold legs 1 AC 6 CK SA c CV, LT 27 1-SI-224, 225 J-1, J-1 High Head Safety Injection 226, 227 J-2, J-3 Check Valves at Containment 2 c 3 CK SA c CV 27 Penetrations Low Head Safety Injection 1-SI-228, 229 J-3, J-3 Check Valves at Containment . 2 c 6 CK SA c CV 27 Penetrations

Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves 35 .1 System Name: Safety Injection Drawing No. 11448 - FM - 89B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number* Location Function Class gory Size Type Type Position Required Request 1-SI-79, 82 A-1, A-1 Safety Injection to RCS 85 A-2 Cold legs 1 AC 6 CK SA c CV, LT 27 Accumulator nitrogen LT*, EV TV-SI-101A, B J-5, J-5 Relief Line Isolation 2 A 1 GA PN 0 ST, VP None 1-SI-234 J-4 Nitrogen Accumulators 2 AC 1 CK SA c CV, LT* 9 Accumulator Return to RV-1859 I-4 RWST Relief 2 c 3/4 RV SA c SP 1

36 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Gaseous Waste Disposal Drawing No. 11448 - FM - 90A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request TV-GW-100 A-3 Suction Line to Hydrogen LT*, ST TV-GW-101 A-3 Analyzer - Unit 1 2 A 3/8 GA sov c EV, VP None TV-GW-102 A-3 Discharge Line to Hydrogen LT*, ST TV-GW-103 A-3 Analyzer - Unit 1 2 A 3/8 GA sov c EV, VP None TV-GW-104 B-1 Suction Line to Hydrogen LT*, ST TV-GW-105 B-2 Analyzer - Unit 2 2 A 3/8 GA sov c EV, VP None TV-GW-106 B-3 Discharge Line to Hydrogen LT*, ST TV-GW-107 B-3 Anal~zer - Unit 1 2 A 3/8 GA sov c EV, VP None RV-GW-lOOA C-6 Waste Gas Decay Outer c l~ RV SA c SP 1 RV-GW-lOOB H-6 Tank Relief RV-GW-102A C-6 Waste Gas Decay Inner c l~ RV SA c SP 1 RV-GW-102B G-6 Tank Relief RV-GW-103 K-1 Waste Gas Surge Drum c l~ RV SA c SP 1 Relief TV-GW-lllA A-1 LT*, ST TV-GW-lllB Containment Grab SamEle 2 A 3/8 GA sov c EV, VP None

Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves 37 ii I

System Name: Gaseous Waste Disposal Drawing No. 11448 - FM - 90B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request RV-GW-107 K-5 Relief Valve on Gases c 3/4 RV SA c SP 1 Going to Waste Gas Surge Drain for Storage

, I

Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves 38 System Name: R.W.S.T. Cross Tie Drawing No. 11448 - FM - 106C Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request TV-SI-102A D-3 Unit No. 1 RWST to Unit ST, EV TV-SI-102B D-3 No. 2 RWST Cross Tie 2 B 8 GA PN c VP None Charging Pump Suction from l-SI-25 C-3 RWST Check Valve 2 c 8 CK SA c CV 28 Charging Pump Suction from 1-SI-410 B-3 RWST Check Valve 2 c 10 CK SA c CV 28

\

39 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Reactor Cavit}'.: Purification Drawing No. 11448 - FM - 118A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request Reactor Cavity Purifica-RL-5, RL-3 C-4, D-4 tion Return Line 2 A 3 DA Man c LT* None Reactor Cavity Purifica-RL-13, RL-15 C-6, D-6 tion Return Line 2 A 3 DA Man c LT* None

Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves 40 System Name: Steam Generator Blowdown Drawing No. 11448 - FM - 124A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request TV-BD-100 A, B C-2, C-2 C, D C-4, C-4 Steam Generator Blowdown EV, ST E, F C-5, C-5 Isolation 2 B 3 GA PN 0 VP 29

41 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Radiation Monitor - Containment Particulate Drawing No. 11448 - SPS - 14A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request Isolation on Monitor 1-RM-03 D-8 Return Line 2 AC 3/4 CK SA 0 LT*, CV 9 Isolation on Monitor LT*, EV TV-RM-lOOA F-8 Return Line 2 A 3/4 GA PN 0 ST, VP None TV-RM-lOOB F-4 Isolation on Monitor LT*, EV TV-RM-lOOC E-4 Return Line 2 A 3/4 GA PN 0 ST, VP None

Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves 42 System Name: Fuel Oil Lines Drawing No. 11448 - FB - 4B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request SOV-EE-100 J-3 SOV-EE-101 J-3 Disel Fuel Oil Pump SOV-EE-103 J-5 Discharge Valves 3 B 1 GA PN c EV, VP None

43 Surry Power Station Unit 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Conta.inment Purge Drawing No. 11448 - FB - 6A i'

Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request MOV-VS-lOOA D-5 Containment Purge Supply MOV-VS-lOOB D-5 MOV's 2 A 36" BF MOV c LT*, VP None MOV-VS-102 D-5 Containment Vacuum Breaker 2 A 8" BF MOV c LT*, VP None MOV-VS-lOOC D-5 Containment Purge Exhaust MOV-VS-lOOD D-5 MOV's 2 A 36" BF MOV c LT*, VP None Containment Purge Exhaust MOV-VS-101 D-5 B~pass 2 A 4" GA Man c LT* None

System Name: Containment Fire Protection Valve Drawing Number Location Function 1-FP-151 Containment Stand Pipe 1-FP-152 Supply

29 3.5 Valve Test Program Relief Request Relief Request identify code requirements which are impractical for Surry Unit 1 and provide justification for the requested exception.

Where appropriate, we also propose alternate testing to be performed in lieu of code requirements

30 NOTE 1 Safety and Relief Valves setpoints are tested in accordance with PTC-25.3-1976 as directed by IWV-3512. Main Steam safety valves will be tested in accordance with Section 4. 091 (a) (2). All other Safety and Relief Valves will be tested in accordance with Section 4.091 (c) (1).

TABLE A Valve Categor~ Class Function SV-MS-lOlA, B, c c 2 Main Steam Safety Valves SV-MS-102A, B, c SV-MS-103A, B, c SV-MS-104A, B, c SV-MS-105A, B, c RV-MS-101A c 2 Main Steam PORV RV-MS-lOlB RV-MS-101C RV-CC-119A c 3 Component Cooling from RHR RV-CC-119B Heat Exchanger Relief Valve RV-CC-116A c 3* Component Cooling Reactor RV-CC-116B Coolant Pump RV-CC-116C RV-CC-124 c 3 Component Cooling Piping Relief Valve RV-CC-118 c 3 Component cooling from excess letdown heat exchanger relief .*

RV-1721 c 2 *RHR System Relief Valve RV-CC-lllA c 3 Component Cooling to Fuel Pit RV-CC-lllB Coolers Relief Valves RV-CC-110 c 3 Component Cooling to Non Regenerative Heat Exchanger Relief Valve RV-CC-109 c 3 Component Cooling to Seal Water Tank Relief Valve

31 TABLE A Valve Category Class Function RV-CC-123 c 3 Component Cooling to Surge Tank Relief Valve SV-1551A AC 1 Pressurizer Safety Valves SV-1551B SV-1551C RV-1209 c 2 Reactor Coolant System Letdown relief valve RV-1257 c 2 Volume Control Tank Relief Valve RV-1203 c 2 Letdown Header Relief RV-1845A, B, C c 2 Low Head Safety Injection Flow Path Relief RV-1857 c 2 Boron Injection Tank Relief Valve RV-1858A, B, C c 2 Accumulator Relief Valve SV-BR-100 c Gas Stripper Relief RV-BR-120 c Gas Stripper Surge Tank Relief RV-BR-108 c Primary Drain Tank Relief SV-BR-101A&B c Boron Evaporator and Boron Overhead Condenser Relief RV-BR-115 c Evaporator Bottoms Tank Relief RV-1322 c Batching Tank Heating Jacket Relief RV-1382B c 2 Seal Water Return Line to VCT RV-1382A c 1 Seal Water Return to Pressurizer Relief Tank RV-1859 c 2 Accumulator Return to RWST Relief RV-1893 c Positive Displacement Pump Discharge Relief

32 TABLE A Valve Category Class Function RV-GW-lOOA, B c Waste Gas Decay Outer Tank Relief RV-GW-102A, B c Waste Gas Decay Outer Tank Relief RV-GW-103 c Waste Gas Decay Inner Tank Relief RV-GW-107 c Relief Valve on Gases going to Waste Gas Surge Drum for Storage

33 RELIEF REQUEST 2 System: Main Steam Valve(s): TV-MS-lOlA TV-MS-101B TV-MS-101C Category: B Class: 2 Function: Main Steam Line Trip Valves Sectiorl XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Ba~is for Request Full Stroke or partial stroke exercise of these valves during power operation could result in a turbine and reactor trip.

Alternate Testing Proposed Full stroke exercise during each cold shutdown or startup in accordance with Technical Specification.

\

34 RELIEF REQUEST 3 System: Main Steam Valve(s): NRV-MS-101A NRV-MS-101B NRV-MS-101C Category: C Code: 2 Function: Main Steam Non-Return ValvesSection XI Code Requirements For Which Relief is Requested Exercise valves every three months.

Basis for Request Full stroke or partial stroke exercise of these valves during power operation could result in a turbine and reactor trip.

Alternate Testing Proposed Full stroke exercise during each cold shutdown (but not more frequently than every three months)

35

~ RELIEF REQUEST 4 System: Auxiliary Feedwater Valve(s):

Category: See valves affected by this relief are identified by Table C.

Class:

Function:

Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request Opening these valves during power operation would introduce cold auxiliary feedwater to the steam generators resulting in thermal stress and possible degradation.

Alternate Testing Proposed Exercise these valves for operability every cold shutdown (but not more frequently than every three months).

36 TABLE C Valve Category Class Function l-FW-27 c 2 Auxiliary Feedwater Header Check l-FW-58 Valves at Main Feedwater Header.

l-FW-59 l-FW-131 c 2 Auxiliary Feedwater Header l-FW-133 Check Valves at containment l-FW-136 Penetration.

l-FW-138 l-FW-142 c 3 Auxiliary Feedwater Pump l-FW-157 Discharge Check Valves l-FW-172 l-FW-272 c 3 Cross-Connect for Unit #1 Aux.

l-FW-273 Feed from Unit #2 check valves at Containment Penetration.

l-FW-309 c 3 Cross connect for Unit 1 Aux.

l-FW-310 Feed from Unit 2 check valves at containment Penetration

37 RELIEF REQUEST 5 System: Feedwater Valve(s): l-FW-10 l-FW-43 l-FW-12 l-FW-72 l-FW-41 l-FW-74 Category: c Class: 2 Function: Main Feedwater Check Valves at containment Penetrations.

Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request Closure of these valves during power operation would require securing feedwater which would result in reactor trip.

Alternate Testing Proposed Exercise these valves for operability every cold shutdown (but not more frequently than every three months).

38

~ RELIEF REQUEST 6 System: Service Water Valve(s): MOV-SW-103A MOV-SW-103C MOV-SW-103B MOV-SW-103D Category: B Class: 3 Function: Service Water to Recirculation Spray Heat ExchangersSection XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request Opening these valves would result in the introduction of service water into the recirculation spray heat exchanger and possibly cause fouling and degradation. To prevent this problem, draining of heat exchangers and piping is required which causes for a containment entry.

Alternate Testing Proposed Exercise these valves for operability every cold shutdown (but not more frequently than three months).

,~-

39 RELIEF REQUEST 7 System: Various Valve(s):

Category: See valves affected by this relief are identified by Table D.

Class:

Function:

Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request These check valves are located in the containment and may be normally open or closed depending on system lineup. A containment entry and manipulation of other system valves is necessary to test these valves. This is considered impractical during power operation.

Alternate Testing Proposed Exercise these valves for operability every cold shutdown (but not more frequently than three months).

40 TABLE D Valve Category Class Function l-CC-176 c 2 Component Cooling to RHR Heat l-CC-177 Exchangers Check valves l-CC-242 c 3 Component Cooling to Reactor l-CC-233 Containment Air Recirculation l-CC-224 Coolers

41

System: Component Cooling RELIEF REQUEST 8 Valve(s):

Category: See valves affected by this relief are identified by Table E.

Class:

Function:

Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request To perform operability test, the component cooling lines must be isolated and thereby stopping flow of cooling water to the Reactor Coolant Pump. Loss of cooling water to these pumps can be damaging, even for short periods.

Alternate Testing Proposed Exercise these valves for operability every cold shutdown (but not more frequently than three months).

42

Valve 1-CC-l Categor}'.'.

c TABLE E Class 2

Function Component Cooling to Reactor l-CC-58 Coolant Pumps l-CC-59 TV-CC-105A B 2 Component Cooling from Reactor TV-CC-105B Coolant Pumps TV-CC-105C TV-CC-107 B 2 Component Cooling from Reactor Coolant Pumps

43

System: Various RELIEF REQUEST 9 Valve(s):

Category: See valves affected by this relief are identified in Table F.

Class:

Function:

Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request These check valves cannot be aligned for a reverse flow test during power operation or cold shutdown. Do to the fact that removing system from operation is required and these systems are required even at cold shutdown, these valves will be tested every refueling shutdown.

Alternate Testing Proposed These valves will be subject to reverse flow during leakage test which are performed during each refueling.

44

Valve 1-IA-939 Category AC TABLE F Class 2

Function Instrument Air to Containment 1-IA-938 AC 2 Instrument Air to Containment 1-RM-3 AC 2 Isolation on Monitor return line.

1-RC-160 AC 2 Primary Grade water to PRZ Relief Tank 1-SI-234 AC 2 Nitrogen A~cumulators N2 supply.

l-CH-309 AC 2 Normal Charging Isolation Check Valve

45 RELIEF REQUEST 10 System: Containment and Recirculation Spray Valve(s): l-RS-11 l-CS-13 l-CS-105 l-RS-17 l-CS-14 l-CS-127 Category: AC Class: 2 Function: Spray Pump Discharge Check Valves Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request These valves are located inside the containment and not accessible during power operation. Using flow to exercise these valves would result in spraying the containment, therefore manual exercising of these valves will be done. Do to the fact scoffolding and dismantling of valves is required, they will be tested every refueling shutdown.

Alternate Testing Proposed I

Full stroke manual testing will be performed each refueling shutdown.

46 RELIEF REQUEST 11 System: Residual Heat Removal Valve(s): 1-RH-5 1-RH-11 Category: C Class: 2 Function: RHR Pump Discharge Check Valve Section XI Code Requirement For Which Relief is Requested Exercise valves for operability every three months.

Basis for Request The valves can only be cycled when RHR pumps are started. These valves will be tested with RHR pumps.

Alternate Testing Proposed Exercise these valves for operability every cold shutdown (but not more frequently than three months).

47 RELIEF REQUEST 12 System: Residual Heat Removal Valve(s): MOV-1700 MOV-1701 Category: A Class: I Function: RHR Suction from Reactor Coolant System Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request (1) Valves are interlocked with reactor coolant system pressure such that valves can not be opened at elevated reactor coolant system pressure.

(2) Over pressurization of the suction line may cause the LOCA.

(3) Interlocks cannot be bypassed with normal control circuits.

Alternate Testing Proposed Exercise these valves for operability every cold shutdown (but not more frequently than three months).

48 RELIEF REQUEST 13 System: Residual Heat Removal Valve(s): MOV-1720A MOV-1720B Category: A Class: I Function: RHR Discharge to Reactor Coolant System Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request (1) With MOV shut and if its respective check valve was leaking, there is no way to determine whether an overpressure condition exists before opening a MOV.

(2) Since MOV is also part discharging p1p1ng of an accumulator, there is a possibility of dumping an accumulator into RHR system and disabling it.

Alternate Testing Proposed Exercise these valves for operability every cold shutdown (but not more frequently than three months).

49 RELIEF REQUEST 14 System: Chemical and Volume Control Valve(s): l-CH-258 l-CH-267 l-CH-276 Category: c Class: 2 Function: Charging Pump Discharge Check Valve Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request With present plant design, these valves can only be partial stroke exercised during power operation and the charging pumps cannot achieve design accident flow when pumping into the reactor coolant system at operating pressure. The only available flow path to test these valves is into the reactor coolant system. During cold shutdown, stroke exercising these valves could result in an over-pressurization of the reactor coolant system and could force a safety system to function.

Alternate Testing Proposed These valves will be partially stroke every three months and full flow tested each refueling.

50

System:

RELIEF REQUEST 15 Chemical and Volume Control Valve(s): LCV-1115C LCV-l 115E Category: B Class: 2 Function: Charging Pump Suction from Volume Control TanksSection XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request Exercising these valves during power operation would require the charging pump suctions to be aligned with the refueling water storage tank. This would cause a sudden increase in reactor coolant system boron inventory, thereby a plant transient.

Alternate Testing Proposed.

These valves will be exercised during each cold shutdown (but not more frequently than every three months).

51 RELIEF REQUEST 16 System: Chemical and Volume Control Valve(s): MOV-1373 Category: B Class: 2 Function: Charging Pump Recirculation Header Stop Valve Section XI Code.Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request This valve cannot be exercised without possible damage to the charging pumps.

Alternate Testing Proposed This valve will be exercised each cold shutdown (but not more frequently than every three months).

52

System:

RELIEF REQUEST 17 Chemical and Volume Control Valve(s): MOV-1381 Category: A Class: 2 Function: Reactor Coolant Pump Seal Water Return Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request Closure of this valve with reactor coolant pumps in operation will cause a loss of seal flow resulting in possible pump seal damage.

Alternate Testing Proposed This valve will be exercised during each cold shutdown (but not more frequently than every three months).

53

System:

RELIEF REQUEST 18 Chemical and Volume Control Valve(s): TV-1204 Category: A Class: 2 Function: Reactor Coolant System Letdown Isolation Trip Valve Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request Exercising this valve during power operation could result in a loss of Reactor coolant inventory control and pressurizer level control.

Alternate Testing Proposed This valve will be exercised every cold shutdown (but not more frequently than every three months).

54

System:

RELIEF REQUEST 19 Chemical and Volume Control Valve(s): MOV-1289A Category: A Class: 2 Function: Normal Charging Header Isolation Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request Failure of these valves in the closed position during exercising would cause a loss of charging flow and could result in an inability to maintain reactor coolant inventory.

Alternate Testing Proposed This valve will be exercised every cold shutdown (but not more frequently than every three months).

54

System:

RELIEF REQUEST 19 Chemical and Volume Control Valve(s): MOV-1289A Category: A Class: 2 Function: Normal Charging Header Isolation Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request Failure of these valves in the closed position during exercising would cause a loss of charging flow and could result in an inability to maintain reactor coolant inventory.

Alternate Testing Proposed This valve will be exercised every cold shutdown (but not more frequently than every three months).

55 RELIEF REQUEST 20 System:* Safety Injection Valve(s): 1-SI-56 1-SI-47 Category: C Class: 2 Function: Low Head Safety Injection Pump Suction from Containment Sump Check Valve Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request This normally closed check valve cannot be exercised without isolating suction to Low Head Safety Injection by installing flanges and draining portions of the system.

Alternate Testing Proposed These valves will be partial-stroked exercised during each refueling.

~---~--~~---- ~- ~-

56 RELIEF REQUEST 21 System: Safety Injection Valve(s):

Category: See valves affected by this relief are identified in Table G.

Class:

Function:

Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request These valves cannot be full stroke exercised during plant power operation.

The only full flow path is into the reactor coolant system and Low Head Safety Injection pumps cannot overcome reactor coolant system operating pressure.

These valves will be partial stroked, exercised quarterly through pump recirculation line. During cold shutdown, the reactor coolant system presssure still prevents full flow of check valve. During cold shutdown, the charging flow could cause an over-pressurization condition.

Alternate Testing Proposed These valves will be partial-stroked every three months and full stroked every refueling.

57 TABLE G Valve Category Class Function l-SI-46A c 2 Low Head Safety Injection Pump l-SI-46B Suction from Refueling Water Storage Tank Check l-SI-58 c 2 Low Head Safety Injection l-SI-50 Pump Discharge Check

58 RELIEF REQUEST 22 System: Safety Injection Valve(s): MOV-1890C Category: A Class: 2 Function: Low Head Safety Injection to Reactor Coolant System Cold LegsSection XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request In accordance with Technical Specification 3.3.A.9, during power operation, the A.C. power shall be removed from MOV-1890C with valve in open position.

If this valve was stroked during power operations and failed in the closed position, Low Head Safety Injection system leg would be rendered inoperable.

Alternate Testing Proposed This valve will be exercised during each cold shutdown (but not more frequently than every three months).

59 RELIEF REQUEST 23 System: Safety Injection Valve(s): MOV-1869A MOV-1869B MOV-1842 Category: A Class: 2 Function: High Head Safety Injection to Reactor Coolant System Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request These valves cannot be exercised during power operation. Opening these valves would allow charging flow into the reactor coolant system causing reactivity transients and possible thermal shock to High Head Safety Injection System.

During cold shutdown, the charging flow could cause an over-pressurization of the reactor coolant system and could force a safety system to function.

Alternate Testing Proposed These valves are full stroked exercised during refueling outages as a minimum.

- - .., .,,~ - . ..,, ... *:* "'*"'.* -, ;~.. ....

60 RELIEF REQUEST 24 System: Safety Injection Valve(s): MOV-1867C MOV-1967D Category: A Class: 2 Function: Boron Injection Tank Outlet Isolation Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request Opening these valves during power operation would allow concentrated boric acid to flow into the piping systems that are not heat traced and a boron buildup could crystalize and block system flow.

Alternate Testing Proposed These valves will be exercised during each cold shutdown (but not more frequently than every three months).

61 RELIEF REQUEST 25 System: Safety Injection r

Valve(s): MOV-1867A MOV-1867B Category: B Class: 2 Function: Boron Injection Tank Inlet Isolation Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request To exercise these valves will allow lower concentrated borated water into the Boron Injection Tank, thereby causing .the tank's boron concentration to go below Technical Specification limits.

Alternate Testing Proposed These valves will be exercised during each cold shutdown (but not more frequently than every three months).

62 RELIEF REQUEST 26 System: Safety Injection Valve(s): 1-SI-107 1-SI-109 l-SI-128 1-SI-130 1-SI-145 1-SI-147 Category: C Class: 1 Function: Accumulator Discharge Check Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request These check valves are partially stroked at refueling shutdown by varying reactor coolant system pressure and observing increases and decreases in accumulator level and pressures. Stroke verification by passing design flow is not practical due to the large volume of water that would be added to the Reactor Coolant System. Calculations have shown that a differential pressure of approximately 25 psi will shear any particles that may attempt to prevent the valve from functioning. Based on this calculation and partial stroke testing presently performed, full stroke testing requirements are waived *

.Alternate Testing Proposed These valves will be pardally stroked each refueling

63

System: Safety Injection RELIEF REQUEST 27 Valve(s):

Category: See valves affected by this relief are identified in Table H.

Class:

Function:

Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request These valves cannot be exercised during power operation, because flow through these valves would thermal shock the injection system and cause unnecessary plant transients. During cold shutdown, the reactor coolant system pressure still prevents full design flow. Also, there could result an overpressurization of the reactor coolant system and force a safety system to function.

Alternate Testing Proposed These valves are full stroke exercised during refueling outages when the vessel head is removed.

64 TABLE Valve Category Class Function l-SI-88, 91 AC 1 Safety Injection to RCS Hot Legs l-SI-94, 238 l-SI-239, 240 l-SI-235 AC 1 High Head Safety Injection to l-SI-236 RCS Cold Legs l-SI-237 l-SI-241 AC 1 Low Head Safety Injection to l-SI-242 RCS Cold Legs l-SI-243 l-SI-224, 225 c 2 Head Head Safety Injection Check l-SI-226, 227 Valve at Containment Penetrations l-SI-228, 229 c 2 Low Head Safety Injection Check Valves at Containment Penetrations l-SI-79, 82, 85 A 1 Safety Injection to RCS Cold Legs

. .* . ; -**.~ .. *-

65 RELIEF REQUEST 28 System: R.W.S.T. Cross Tie Valve(s): l-SI-25 l-SI-410 Category: c Class: 2 Function: Charging Pump Suction From R.W.S.T. Cross Tie Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request Exercising these valves during power operation would require the charging pump suctions to be aligned with the refueling water storage tank. This would cause a sudden increase in reactor coolant boron inventory.

Alternate Testing Proposed Exercise the valves for operability every cold shutdown (but not more frequently than every three months).

66 RELIEF REQUEST 29 System: Steam Generator Blowdown Valve(s): TV-BD-lOOA TV-BD-lOOD TV-BD-lOOB TV-BD-lOOE TV-BD-lOOC TV-BD-lOOF Category: B Class: 2 Function: Steam Generator Blowdown Isolation.

Section XI Code Requirement For Which Relief is Requested Exercise valves every three months.

Basis for Request Closing these valves during power operation causes the downstream piping to become empty due to drainage and water flashing to steam. When the valves reopened, a flow surge occurs which automatically isolates the inner valves due to high flow. Then a containment entry is necessary to reset these valves and upon reopening the process may occur again.

Alternate Testing Proposed Exercise the valves for operability every cold shutdown (but not more frequently than every three months).

67

NOTE 30 The following boundary valves in Reactor Coolant system are not leaked tested individually but leak tested as a system in accordance with Technical Specifications 3.1.C and 4.3 and ASME Section XI, subsection IWB-5000.

TABLE A Valve Category Class Function HCV-1156A A 1 Loop Fill Boundary HCV-1156B HCV-1156C SV-1551A AC 1 Pressurizer Safety Valves SV-1551B SV-1551C MOV-1535 A 1 PORV Block Valves MOV-1536 PCV-1456 A 1 PORV PCV-1456 1-SI-107, 109 AC 1 Accumulator Discharge Check 1-SI-128, 130 Valve 1-SI-145, 147 1-SI-88, 91 AC* 1 Safety Injection to RCS Hot Legs 1-SI-94, 238 1-SI-239, 240 1-SI-235 AC 1 High Head Safety Injection to l-SI-236 RCS Cold Legs 1-SI-237 MOV-1700 A 1 RHR Suction from Reactor Coolant MOV-1701 System MOV-1720A A 1 RHR Discharge to Reactor Coolant MOV-1720B System RV-1382A AC 1 Seal Water Return to Pressurizer Relief Tank

68 RELIEF REQUEST 31 System: Reactor Coolant Valves: SOV-RC-lOOA-1 SOV-RC-lOlA-1 SOV-RC-lOOA-2 SOV-RC-101A'.'"2 SOV-RC-lOOB-1 SOV-RC-lOlB-1 SOV-RC-lOOB-2 SOV-RC-lOlB-2 Category: B Class: 2 Function: Head Vent for Reactor Vessel and Pressurizer Section XI Code Requirements For Which Relief is Requested Exercise valves every three months.

Basis for Request Due to head vents location on Reactor Coolant System, valve cycling during power operation could put plant in unsafe condition. Also at cold shutdown and at power operation, cycling these valves could cause an airborne contamination problem due to the fact that they discharge to containment atmosphere.

Alternate Testing Proposed These valves will be tested each refueling by exercising and verifying flow.

I - ~~

69

System: Main Steam RELIEF REQUEST 32

+ -t-Valves: HCV-MS-104 Category: B Class: 2 Function: Decay Heat Release Control Valve Section XI Code Requirements For Which Relief is Requested Opening of this valve during power would result in added steam load to reactor. The opening and closing of this valve at power could result in a over power condition and possible reactor trip as reactor power increases to meet the new steam load.

Alternate Testing.Proposed

Exercise these valves for operability every frequently than every three months).

cold shutdown (but not more Rev. 1 12/22/82

70

4.0 REPORTING OF INSERVICE TEST RESULTS 4.1 Pump Inservice Program Records of Pump Inservice Test Results will be in accordance with the intent of Article IWP-6000. Files will be established for each pump and will include:

1) Pump identification by equipment number, manufacturer and serial number.

2) The record of test shall include ..*

a. date of test

b. measured and observed quantities

c. identification of instruments used,

d. comparison with allowable ranges of test valves and analysis of deviations

e. requirements for corrective actions

f. conducting and analyzing the test

3) Inservice test plans. This may be by surveillance test procedure by which the pump is tested with reference drawing.

4) Summaries of corrective action some by maintenance report number, etc.

The Pump Inservice Test Program, associated surveillance test procedures and results will be kept at Surry Power Station. They will be available for audit by Authorized Nuclear Inspector and the NRC.

4.2 Valve Inservice Program Records of Valve Inservice Test Results will be in accordance with the intent of Article IWV-6000, files will be established for each valve and will include ***

1) Valve identification by equipment number, manufacturer, size, valve type, actuator type.

2) The record of test shall include:

a. date of test

b. measured and observes quantities where applicable

71

c. identification of instruments used where applicable

d. comparisons with allowable ranges of test valves and analysis of deviations.

e. maintenance history

f. signature of the person or persons responsible for conducting and analyzing the test.

3. Summaries of maintenance history may be maintenance report numbers, etc.

The Valve .Inservice Test Program, associated surveillance test procedures and results will be kept at Surry Power Station. They will be available for audit by Authorized Nuclear Inspector and NRC Region Inspectors.

4.3 Reports to Regulatory Agencies Reports to Regulatory Agencies will be summary reports on pump and valve program which will give sufficient information to insure a test was performed. All procedures of test will be kept on site.

Each refueling outage, a report shall be submitted to regulatory agencies with NDE Report.

5.0 QUALITY ASSURANCE PROGRAM The Pump and Valve Inservice Test Program activities will be conducted in accordance with Nuclear Power Station Quality Assurance Manual and Technical Specifications for Surry Power Station .

5.0 SYSTEM PRESSURE TESTS 5.1 Program Description 5.1.l The Surry Unit 1 System Pressure Test program shall be in accordance with the ASME Boiler and Pressure Vessel Code Section XI 1980 Edition, Winter of 1980 Addenda inclusive.

All principles and guidelines established by this code shall be adopted while conducting system pressure tests, except in cases where relief has been requested and provided within this document. Relief requests will identify the specific deviation from code requirements and provide an alternative testing arrangement.

Surry Unit 1 is currently entering the second inspection interval of Inspection Program B, IWA-2420. This new interval starts December 22, 1982 and coincides with the planned implementation of the proposed inspection program contained within this document. This proposed program will be effective at Surry Unit 1 for the next 10 years or as modified by future ASME code changes which are adopted at this station.

5-1

II. CLASS I SYSTEM PRESSURE TESTS (10 YEAR SCHEDULE)

A. EXAMINATION CATEGORY B-E, PRESSURE RETAINING PARTIAL PENETRATION WELDS IN VESSELS.

ITEM PARTS TO BE EXAM. EXAM. ACCEPTANCE SCHEDULE NOTES RELIEF NO. BE EXAMINED METHOD REQRMT. CRITERIA REQUEST B4.10 PARTIAL VT-2 EXTERNAL IWA-5250 CONDUCTED 2,5 PENETRATION SURFACE DURING WELDS SYSTEM HYDROSTATIC TEST B4.ll VESSEL VT-2 EXTERNAL IWA-5250 CONDUCTED 2,5 NOZZLES SURFACE DURING SYSTEM HYDROSTATIC TEST B4.12 CONTROL VT-2 EXTERNAL IWA-5250 CONDUCTED 2,5 ROD DRIVE SURFACE DURING NOZZLES SYSTEM HYDROSTATIC TEST B4.13 INSTRUMEN- VT-2 EXTERNAL IWA-5250 CONDUCTED 2,5 TATION SURFACE DURING NOZZLES SYSTEM HYDROSTATIC TEST B4.20 PRESSURIZER VT-2 EXTERNAL IWA-5250 CONDUCTED 2,5 HEATER SURFACE DURING PENETRATION SYSTEM WELDS HYDROSTATIC TEST 5-2

B. EXAMINATION CATEGORY B-P, ALL PRESSURE RETAINING COMPONENTS ITEM PARTS TEST EXAM. ACCEPT. SCHEDULE NOTES RELIEF NO. EXAM. REQRMT. METHOD STANDARD REQUEST Bl5 .10 REACTOR SYSTEM VISUAL, IWA-5250 EACH 1,5,9 VESSEL LEAKAGE VT-2 REFUELING PRESSURE TEST, OUTAGE RETAINING IWB-5221 BOUNDARY Bl5 .11 REACTOR SYSTEM VISUAL, IWA-5250 ONE 1,2,5,9 VESSEL HYDRO- VT-2 TEST RETAINING STATIC BOUNDARY TEST, IWB-5222 Bl5.20 PRESS UR- SYSTEM VISUAL, IWA-5250 EACH 1,5,9 IZER LEAKAGE VT-2 REFUELING PRESSURE TEST, OUTAGE RETAINING IWB-5221 BOUNDARY Bl5.21 PRESS UR- SYSTEM VISUAL, IWA-5250 ONE 1,2,5,9 IZER HYDRO- VT-2 TEST PRESSURE STATIC RETAINING TEST, BOUNDARY IWB-5222 Bl5.30 STEAM SYSTEM VISUAL, IWA-5250 EACH 1,5,9 17 GENERATORS LEAKAGE VT-2 REFUELING PRESSURE TEST, OUTAGE RETAINING IWB-5222 BOUNDARY Bl5.31 STEAM SYSTEM VISUAL, IWA-5250 ONE 1,2,5,9 17 GENERATORS HYDRO- VT-2 TEST PRESSURE STATIC RETAINING TEST, BOUNDARY IWB-5222 Bl5.40 HEAT SYSTEM VISUAL, IWA-5250 EACH 1,5,6,9 EXCHANGES LEAKAGE VT-2 REFUELING PRESSURE TEST, OUTAGE RETAINING IWB-5221 BOUNDARY 5-3

I

B.

ITEM NO.

EXAMINATION CATEGORY B-P, ALL PRESSURE RETAINING COMPONENTS PARTS EXAM.

TEST REQRMT.

EXAM.

METHOD ACCEPT.

STANDARD SCHEDULE NOTES RELIEF REQUEST Bl5.41 HEAT SYSTEM VISUAL, IWA-5250 ONE 1,2,5,6,9 EXCHANGERS HYDRO- VT-2 TEST PRESSURE STATIC RETAINING TEST, BOUNDARY IWB-5222 Bl5.50 PIPING SYSTEM VISUAL, IWA-5250 EACH 1,3,5,9 7 +-t PRESSURE LEAKAGE VT-2 REFUELING RETAINING TEST, OUTAGE BOUNDARY IWB-5221 Bl5.51 PIPING SYSTEM VISUAL, IWA-5250 ONE 1, 2 ,5 '9 1,3,4, PRESSURE HYDRO- VT-2 TEST 5,6 RETAINING STATIC BOUNDARY TEST,

IWB-5222 Bl5.60 PUMPS SYSTEM VISUAL, IWA-5250 EACH 1,5,9 PRESSURE LEAKAGE VT-2 REFUELING RETAINING TEST, OUTAGE BOUNDARY IWB-5221 Bl5.61 PUMPS SYSTEM VISUAL, IWA-5250 ONE 1,2,5,9 3 PRESSURE HYDRO- VT-2 TEST RETAINING STATIC BOUNDARY TEST, IWB-5222 Bl5.70 VALVES SYSTEM VISUAL, IWA-5250 EACH 1,3,5,9 7 +!-

PRESSURE LEAKAGE VT-2 REFUELING RETAINING TEST, OUTAGE BOUNDARY IWB-5221 Bl5.71 VALVES SYSTEM VISUAL, IWA-5250 ONE 1,2,5,9 1,4,5,6 PRESSURE HYDRO- VT-2 TEST RETAINING STATIC BOUNDARY TEST, IWB-5222

5-4 Rev. 1 12/22/82

III. CLASS II SYSTEM PRESSURE TESTS (10 YEAR COMPONENTS)

A. EXAMINATION CATEGORY C-H. ALL PRESSURE RETAINING COMPONENTS ITEM PARTS TEST EXAM. ACCEPT. SCHEDULE NOTES RELIEF NO. EXAMINED REQRMT. METHOD STANDARD REQUEST C7.10 PRESSURE SYSTEM VISUAL, IWA-5250 ONCE 4,5,6,9 VESSELS FUNCTIONAL VT-2 PER PRESSURE TEST, INSPECTION RETAINING IWC-5221 PERIOD COMPONENTS C7 .11 PRESSURE SYSTEM VISUAL, IWA-5250 ONE 2,4,5,6,9 8 VESSELS HYDRO- VT-2 TEST PRESSURE STATIC RETAINING TEST, COMPONENTS IWC-5222 C7.20 PIPING SYSTEM VISUAL, IWA-5250 ONCE 4,5,9 11 PRESSURE FUNCTIONAL VT-2 PER RETAINING TEST, INSPECTION COMPONENTS IWC-5221 PERIOD C7.21 PIPING SYSTEM VISUAL, IWA-5250 ONE 2,4,5, 8,9,10,11, PRESSURE HYDROSTATIC VT-2 TEST 7,9 12,13,16 RETAINING TEST, COMPONENTS IWC-5222 C7.30 PUMPS SYSTEM VISUAL, IWA-5250 ONCE 4,5,9 PRESSURE FUNCTIONAL VT-2 PER RETAINING TEST, INSPECTION COMPONENTS IWC-5221 PERIOD C7.31 PUMPS SYSTEM VISUAL, IWA-5250 ONE 2,4,5,9 PRESSURE HYDROSTATIC VT-2 TEST RETAINING TEST, COMPONENTS IWC-5222 C7.40 VALVES SYSTEM VISUAL, IWA-5250 ONCE 4,5,9 PRESSURE FUNCTIONAL VT-2 PER RETAINING TEST, INSPECTION COMPONENTS IWC-5221 C7.41 VALVES SYSTEM VISUAL, IWA-5250 ONE 2,4,5, 8,9,10,11 PRESSURE HYDRO- VT-2 TEST 7,9 12,13,16, RETAINING STATIC COMPONENTS TEST, IWC-5222 5-5

IV.

ITEM NO.

CLASS III SYSTEM PRESSURE TEST (10 YEAR SCHEDULE)

A. EXAMINATION CATEGORY D-A, SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION.

PARTS EXAMINED TEST EXAM. ACCEPT. SCHEDULE NOTES RELIEF REQRMT. METHOD STANDARD REQUEST Dl.10 PRESSURE SYSTEM VISUAL, NO ONCE 5,6,8,9 18 RETAINING INSERVICE VT-2 LEAKAGE PER COMPONENTS TEST, INSPECTION IWD-5221 PERIOD Dl .10 PRESSURE SYSTEM VISUAL, NO ONE 2,5,6, 18, RETAINING HYDRO- VT-2 LEAKAGE 8,9 19, COMPONENTS STATIC 20 TEST, IWD-5223 5-6

-*: .:* -~--- ---. .... ,,.._,.~ ... ----**~ -- . **--** ., .. ' . . *- ...

B.

ITEM NO.

EXAMINATION CATEGORY D-B, SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAINMENT HEAT REMOVAL, ATMOSPHERE CLEANUP, AND REACTOR RESIDUAL HEAT REMOVAL.

PARTS EXAMINED TEST REQRMT.

EXAM.

METHOD ACCEPT.

STANDARD SCHEDULE NOTES RELIEF REQUEST D2.10 PRESSURE SYSTEM VISUAL, NO ONCE 5,6,8, RETAINING IN SERVICE VT-2 LEAKAGE PER 9 COMPONENTS TEST, INSPECTION IWD-5221 PERIOD D2.10 PRESSURE SYSTEM VISUAL, NO ONE 2,5,6, 14,15, RETAINING HYDRO- VT-2 LEAKAGE TEST 8,9 19,20 COMPONENTS STATIC TEST, IWD-5223 5-7

c. EXAMINATION CATEGORY D-C, SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM SPENT FUEL STORAGE POOL ITEM PARTS TEST EXAM. ACCEPT. SCHEDULE NOTES RELIEF NO. EXAMINED REQRMT. METHOD STANDARD REQUEST D3.10 PRESSURE SYSTEM VISUAL, IWA-5250 ONCE 5,6, RETAINING IN SERVICE VT-2 PER 8,9 COMPONENTS TEST, INSPECTION IWD-5221 PERIOD D3.10 PRESSURE SYSTEM VISUAL, IWA-5250 ONE 2,5,6, 19 RETAINING HYDRO- VT-2 TEST 8,9 COMPONENTS STATIC TEST, IWD-5223 5-8

- - --**---- ... ~ --- ........ *~ ,,... ..... :-~*-*,.,.---.-* -'*....

NOTES Note 1 Class I Systems are drawn on the following station prints:

11448-FM-64A 11448-FM-68A 11448-FM-72A 11448-FM-82B 11448-FM-86A 11448-FM-86B 11448-FM-87A 11448-FM-88C 11448-FM-89B 11448-FM-88B These systems are designatd by an A and are enclosed by brackets on the station prints.

Note 2 Class I, II and III System Hydrostatic Tests shall be conducted near the end of the second interval within the last period. This coincides with the inspection conducted in the first interval.

Note 3 The piping between the following valves will be tested prior to reaching 1000 psig when entering a refueling shutdown. The piping is normally pressurized to 660 psig but depressurizes at 1000 psig on the primary.

1-SI-109 AND 1-SI-107, HCV-1850B 1-SI-130 AND 1-SI-128, HCV-1850D, MOV-1720A 1-SI-147 AND 1-SI-145, HCV-1850F, MOV-1720B Note 4 Class II systems are drawn on the following station prints:

11448-FM-64A 11448-FM-84A 11448-FM-124A FM-64B FM-85A FM-138A FM-66A FM-86A SPS-14A FM-68A FM-86B FB-6A FM-71A FM-87A FB-38A FM-72A FM-88A FB-41B FM-72B FM-88B FM-72C FM-88C FM-75C FM-89A FM-75E FM-89B FM-75G FM-90A FM-75J FM-106C FM-82B FM-118A FM-83A FM-123A FM-83B 5-9

Class II systems or components will be designated by a B and will be enclosed in brackets.

Note 5 This station will use the following guidance for determining the completion of scheduled system pressure tests (i.e. Category B-D, B-P, C-H, D-A, D-B, D-C); All tests which meet the pressure, temperature, hold time; and VT-2 examination requirements as stipulated in the code will be treated as complete for scheduled inspection purposes. All discrepancies will be treated in accordance with IWA 5250 and the station's repair/replacement program. Weld leaks and excessive mechanical leaks will be addressed through a station engineering evaluation to determine continued operability. (NOTE: this does not apply to repair/replacements which must exhibit no leakage at the area of examination determined in the repair/replacement).

Note 6 Visual Examination of Heat Exchangers will be conducted using the following methods:

a) When pressurizing the tube side of a heat exchanger, the tube integrity will be checked by the following methods. Fill and vent the shell side of the heat exchanger prior to the test and monitor an open vent path on the shell side during pressurization for overflow. Any overflow, will be an indication of leakage. A drain method can be used by draining the shell side and observing leakage out the open drain path on the shell side.

b) When pressurizing the shell side of a heat exchanger, the tube integrity can be checked by the following method. Fill and vent the tube side of the heat exchanger prior to pressurization. Monitor an open vent path on the tube side for overflow. Any overflow will be an indication of leakage.

The required visual examination of heat exchanger will be considered complete using either method above. All discrepancies will be referred to the stations repair/replacement program.

5-10

Note 7 For identification purpose piping extending beyond the below listed valves on station print 11448-FM-85A will be considered open ended and in accordance with the requirements of IWC-5222(d) for test purposes.

PIPING 1-LM-28 3/8"-LM-ll-N7 1-LM-29 3/8"-LM-12-N7 1-LM-30 3/8"-LM-13-N7 1-LM-31 3/8"-LM-16-N7 Note 8 Class III Systems are on the following station prints:

11448-FM-64A 11448-FM-72G 11448-FM-68A 11448-FM-84A 11448-FM-68B 11448-FM-87A 11448-FM-71A 11448-FM-88A 11448-FM-71B 11448-FM-88B 11448-FM-72A 11448-FM-88C 11448-FM-72B 11448-FM-89A 11448-FM-72C 11448-FB.;....4B 11448-FM-72D 11448-FM-71D 11448-FM-72E 11448-FM-130A 11448-FM-72F These systems will be enclosed in brackets and designated by a C symbol.

Note 9 Pressure tests required by repairs or replacements will be conducted in accordance with the station's repair/replacement program as documented at the station.

5-11

RELIEF REQUESTS Relief Requests from code required system pressure tests will be in the following format:

1. Identification of the component for which relief is requested:

a. Name and number as located on staion drawings.

b. Function

c. ASME code class

2. Specific identification of the ASME code requirement that has determined to be impractical for each component.

3. Information to support the determination that the requirement in (2) is impractical; i.e. the basis of the relief.

4. Specification of the inservice pressure testing that will be performed in lieu of the ASME code Section XI requirements, if any.

5. The schedule for implementation of the procedure(s) in (4).

5-12

RELIEF REQUESTS RR-1 la) Piping between following check valves located on station print:

11448-FM-89B 11448-FM-88C 1-SI-79 AND l-SI-235, l~SI-241 1-SI-82 AND 1-SI-236, 1-SI-242 1-SI-85 AND 1-SI-237, 1-SI-243 1-SI-88 AND 1-SI-238 1-SI-91 AND 1-SI-239 1-SI-94 AND 1-SI-240 1-CH-430 AND 1-CH-312 b) Safety Injection System Chemical Volume and Control c) Class I

2. Class I System Hydrostatic Test, IWB-5222

3. The double check valve combination prevents pressurization of the area in between the check valves when conducting IWB-5222 on the primary system.

4. The alternative test proposed is to pressurize the primary system to 2335 psig while the reactor is in a shutdown condition. The reactor will be borated to equal to or greater than cold shutdown Boron Concentration. The pressurized primary will act as a boundary for the test forcing closed the first check valve in the pressure boundary. A charging test pump will provide test pressure and a VT-2 examination will be conducted on the area.

5. This test will be conducted toward the end of the second interval within the third inspection period.

5-13

RR-2 Relief Request Withdrawn ++

Rev. 1 12/22/82 5-14

RR-3 la) Pumps located on station drawing 11448-FM-88C as listed:

1-RC-P-lA 1-RC-P-lB 1-RC-P-lC Piping associated from the flange to the pump b) Chemical volume control system c) Class I

2. Class I System Hydrostatic Test, IWB-5222

3. The number one seal return is the pressure boundary for the reactor coolant pumps. The nature of the design of this system precludes the use of an external pressure source for this test; as excessive pressure could damage the seal.

4. The norma~ system leakage tests and VT-2 examination of the piping from the flanges to the pumps will be adequate, and an alternative test is not necessary.

5. N/A.

5-15

RR-4 la) Piping and valves as follows located on station print 11448-FM-88C:

l-CH-323 to the flange prior to 1-RC-P-lA l-CH-333 to the flange prior to 1-RC-P-lB l-CH~349 to the flange prior to 1-RC-P-lC b) Chemical and Volume Control System c) Class I

2. Class I System Hydrostatic Test, IWB-5222

3. It is requested that the piping and valves described be examined during the Class II hydrostatic test which will be conducted on the attached piping. This hydrostatic test will be conducted at 1.25 times the pressurizer safety set point (2485 psig). The hold time for this hydro is the same as a Class I hydro. A Class II +-'-

hydrostatic test will be the more restrictive test.

4. The alternative test is a Class II hydrostatic test.

5. The end of the interval, within the last period .

5-16 Rev. 1 12/22/82

RR-5 la) Piping and valves as listed located on station print 11448-FM-88C:

HCV-1311 to l-CH-313 b) Chemical and Volume Control System c) Class I

2. Class I System Hydrostatic Test, IWB-5222.

3. The one-way check valve placement prevents pressurization of the area in between the valves when conducting IWB-5222 on the primary system.

4. Alternate testing will be proposed at later date.

5. End of interval, within last period *

5-17

RR-6 la) Piping and Valves located on station print 11448-FM-87A Component MOV-1701 Connected Piping 14"-RH-18-602 Component MOV-1700 b) Residual Heat Removal c) Class I

2. Class I System Hydrostatic Test, IWB-5222

3. During a normal hydrostatic test of the primary, MOV-1700 is closed in addition to MOV 1701. This prevents pressurization of MOV 1701 and the piping between the two MOVS.. Both valves are closed to prevent possible overpressurization of the Residual Heat Removal System.

4. As an alternative MOV 1701 and the p1p1ng between MOV 1701 and MOV 1700 .will be tested in accordance with the Class II hydrostatic test to be administered to 14"-RH-18-602 on the suction side of the Residual Heat Removal pumps. This piping is protected from overpressure by RV-1721 which is set at 600 psig. Class II test pressure will be 750 psig. A VT-2 examination at this test ++

pressure will identify any leakage and eliminate the overpressurization risk the Class I hydrostatic test presented *

5. End of interval, within the last period *

5-18. Rev. 1 12/22/82

RR-7 la) Piping and Valves located on station print 11448-FM-87A Component Connected Piping Component MOV-1701 14"-RH-18-602 MOV-1700 b) Residual Heat Removal c) Class I

2. Class I System Leakage Test, IWB-5221

3. The system leakage test conducted on the primary system is done with both MOV 1700 and MOV 1701 closed for reasons expounded upon in relief request 6. This prevents pressurization of MOV 1701 and piping between the two MOVs.

4. As an alternative, during the conduct of the Class II functional test on 14"-RH-18-602, MOV 1701 will be open as well as MOV 1700.

This piping will be examined to the normal VT-2 requirements at the functional test conditions.

5. Once per inspection period.

5-19

RR-8 la) Steam generators and piping located on station prints:

11448-FM-64A 11448-FM-64B 11448-FM-68A 11448-FM-124A 11448-FM-138A 11448-FM-123A Component Connected Piping Component 1-RC-E-lA 30"-SHP-1-601 SV-MS-101A to 30"-SHP-22-601 SV-MS-102A to 4"-SHP-37-601 SV-MS-103A SV-MS-104A SV-MS-105A RV-MS-101A 1-RC-E-lA 30"-SHP-1-601 1-GN-1 to 2"-GN-23 1 601 1-RC-E-lA 30"-SHP-1-601 NRV-MS-lOlA to 6"-SHP-45-601 1-MS-80,81,266,74 1-RC-E-lA 30"-SHP-1-601 HCV-MS-104 to 30"-SHP-22-601 to 3"-SDHV-1-601 to 4"-SDHB-4-601 1-RC-E-lA 14"-WFPD-17-601 l-FW-27 1-FW-10 1-WT-174 1-RC-E-lA 1-BD-1 1-BD-2 1-BD-4 1-RT-1 1-RC-E-lA 30"-SHP-1-601 1-MS-379 1-MS-87 5-20

Component Connected Piping Component 1-RC-E-lB 30"-SHP-2-601 SV-MS-101B to 30"-SHP-23-601 SV-MS-102B to 4"-SHP-38-601 SV-MS-103B SV-MS-104B SV-MS-105B RV-MS-101B 1-RC-E-lB 30"-SHP-2-601 l-GN-2 to 211 -GN-24-601 1-RC-E-lB 30"-SHP-2-601 NRV-MS-101B to 6"-SHP-46-601 1-MS 112,268,113,106 1-RC-E-lB 30"-SHP-2-601 HCV-MS-104 to 30"-SHP-23-601 to 3"-SDHV-2-601 to 4"-SDHV-4-601 1-RC-E-B 14"-WFPD-13-601 l-FW-41,58 l-WT-177 1-RC"'.'"E-lB l-BD-11 l-BD-12 l-BD-14 l-RT-20 5-21

Component Connected Piping Component 1-RC-E-lC 30"-SHP-3-601 SV-MS-lOlC to 30"-SHP-24-601 SV-MS-102C to 4"-SHP-39-601 SV-MS-103C SV-MS-104C SV-MS-105C RV-MS-101C 1-RC-E-lC 30"-SHP-3-601 1-GN-3 to 2"-GN-25-601 1-RC-E-lC 30"-SHP-3-601 NRV-MS-lOlC to 6"-SHP-47-601 1-MS-152,149,208,143 1-RC-E-lC 30"-SHP-3-601 HCV-MS-104 to 30"-SHP-24-601 to 3"-SDHV-3-601 to 4"-SDHV-4-601 1-RC-E-lC 30"-SHP-3 .... 601 1-MS-158 1-MS-377 1-RC-E-lC 14"-WFPD-9-601 l-FW-72 l-FW-89 1-WT-182

1-RC-E-lC 1-BD-21 1-BD-22 1-BD-24 1-BD-39 5-22

... - **--.. ~----*-'t*---*-*--**--*------**** *-* <>***---,,, * . -* **- .,, ~-* *- - - ' -... ....

~ ~ -.

b) Main Steam Feed Water Stm Gen Nitrogen Conn Chemical Feed Blow Down Recirc and Transfer c) Class II

2. IWA 5213(d) System Hydrostatic Tests - 4 hr. holding time required after attaining test pressure and temperature conditions for insulated systems.

3. Westinghouse requires specific testing requirements in order to maintain integrity and warranty of the steam generators. These requirements are found in the Westinghouse Technical Manual Steam Generator Vepco Surry Power Station Units 1 & 2 Volume 1, March 1979, Section 3.10.2, "Secondary Side Hydrostatic Test."

4. The requirements of 3.10.2 of the Westinghouse Technical Manual require the following: "The secondary side hydrostatic test shall be conducted in accordance with the ASME Code Section XI for Class 2 Components. The secondary side pressure is to be raised to 1356 psig, held for 30 minutes and then reduced to 1085 psig for a time sufficient to permit proper examination of welds, closures and surfaces for leakage or weeping.

5. End of interval, within last period.

5-23

RR-9 la Valves and piping on the following station drawings:

Component l-FW-12 l-FW-43 l-FW-74 Connected Piping 14"-WFPD-17-601 14-WFPD-13-601 14"-WFPD-9-601 Component 1-FW-10 l-FW-41 l-FW-72 1-FW-31 3"-WAPD-10-601 1-FW-27 to 3"-WAPD-9-601 1-FW-30 3"-WAPD-9-601 l-FW-27 1-FW-62 3"-WAPD-12-601 1-FW-58 to 3"-WAPD-11-601 1-FW-61 3"-WAPD-11-601 l-FW-58 l-FW-93 3"-WAPD-14-601 1-FW-89 to 3"-WAPD-13-601 1-FW-92 3"-WAPD-13-601 1-FW-89 b) Feedwater and auxilliary feedwater connections.

c) Class II

2. IWA 5213(d) System Hydrostatic Tests - 4 hr. holding time required after attaining test pressure and temperature conditions for insulated systems.

3. The check valves associated with the piping as listed open to the steam generators. Hydrostatic test pressure would therefore pressurize the steam generator area and would subject them to the conditions discussed in relief request 8.

4. As an alternative these areas will be tested to the pressure and conditions discussed in relief request 8. As the individual steam generators are tested the piping and valves attached in this request will be tested.

5. End of inspection interval, within last period.

5-24

RR-10 la) Piping and valves as listed located on station print 11448-FM-BBC:

Component Piping Connected Component 1-CH-311 3/4"-CH-~40-1502 1-CH-312 HCV-1310A 3"-CH-1-1502 1-CH-312 b) Chemical and Volume Control System c) Class II

2. Class II System Hydrostatic Test, IWC-5222

3. The double one-way check valve placement of 1-CH-430 and 1-CH-312 makes it impossible to isolate the primary Class I system from the Class II pressure test required. Since no safety or relief valve exists for this hydrostatic test boundary design pressure of the pipe, Pd, (IWC-5222a) must be used as a substitute for Psv. This valve Pd is 2735 psig therefore required test pressure would be 1.25 times Pd or 3419 psig. Since the primary cannot be isolated this test pressure would over pressurize the primary system which is limited to the Class I Hydrostatic test condition described in IWB 5222.

4. As an alternative during the test described in relief request 5 the piping and components covered by this relief will receive a VT-2 examination.

5. End of interval, within the last period.

5-25

RR-11 la) Piping and valves located on station prints 11448-FM-89'A 11448-FM-89B:

Component Connected Piping Component MOV-1890C 10"-SI-152-1502 to 6"-SI-153-1502 1-SI-243 to 6"-SI-145-1502 1-SI-241 to 6"-SI-144-1502 1-SI-242 MOV-1890A 6"-SI-49-1502 1-SI-229 MOV-1890B 6"-SI-48-1502 2"-SI-81-1502 to 6"-SI-143-1502 6"-SI-49-1502 to 6"-SI-48-1502 to 6"-SI-50-1502 2"-SI-79-1502 1-SI-174 and 3"-SI-72-1503 MOV-1869A to 2"-SI-72-1503/ 1-SI-240 2"-SI-79-1502 1-SI-257 2"'SI-77-1503/ 1-SI-239 2"-SI-80-1502 1-SI-255 MOV-1869B 3"-SI-147-1503 to 2"-SI-73-1503 to 2"-SI-81-1502 1-SI-238 1-SI-253 1-SI-150 3"-SI-70-1503 MOV-1867D to 2"-SI-70-1503/ 1-SI-237 2"-SI-75-1502 1-SI-250 MOV-1867C 2"-SI-76-1503/ 1-SI-236 2"-SI-85-1502 1-SI-248 MOV-1842 3"-SI-146-1503 to 2"-SI-71-1503/ 1-SI-235 2"-SI-74-1502 1-SI-245 b) Safety Injection System c) Class II

2. Class II System Hydrostatic Test, IWC-5222

3. Check valve boundaries between Class II and Class I systems make it impractical to establish hydrostatic test boundaries so that the primary system is not included. Design pressure for this piping is 2800 psig (Pd), therefore normal test pressure would be 3080 psig (T<200°F). This pressure would overpressurize the primary since it cannot be isolated.

4. As an alternative these systems will be tested in conjunction with the Class I Hydrostatic test at a pressure of 2335 psig. A VT-2 examination will be performed on the componenets and piping listed above.

5. Once each period.

5-26

RR-12 la) Piping and valves located on station print 11448-FM-89b; Component MOV-1865A l-SI-105 MOV-1865B Connected Piping 12"-SI-45-1502

,3/4"-SI-33-1502 12"-SI-46-1502 Component l-SI-107 l-SI-107 l-SI-128 l-SI-126 3/4"-SI-34-1502 l-SI-128 MOV-1865C 12"-SI-47-1502 l-SI-145 l-SI-143 3/4"-SI-35-1502 l-SI-145 b) Safety Injection System c) Class II

2. Class II System Hydrostatic Test, IWC-5222

3. The check valve boundary prevents isolation of the adjoining Class I system from the Class II system mentioned. The lack of

overpressure protection within the boundary r~quires a valve Pd (Design Pressure) equal to 2485 psig times 1.1 (T < 200°F) for a test pressure of 2733.5 psig. The nominal operating pressure Po for the adjoining Class I system is 660 psig which at 100°F requires a test pressure of 726 psig. As is evident since isolation is not practical the normal Class II test pressure will be far in excess of the test pressure for the Class I system.

4. As an alternative it is requested that the Class II components and piping mentioned in (la) be examined (VT-2) to the conditions required for the adjacent Class I piping. (PO = 660 psig) (See Note 3)

5. End of interval, within the last period.

5-27

RR-13 la) Piping and valves located on station print 11448-FM-84A.

Component Connected Piping Component l-CS-48 6"-CS-15-152 l-CS-47 6"-CS-14-152 l-CS-46 2"-CS-19-152 l-CS-45 b) Containment and Recirculation Spray System c) Class I I

2. Class II System Hydrostatic Test, IWC-5222(a)

3. Tank 1-CS-TK-l (RWST) and piping up to l-CS-48 will be tested to system hydrostatic test criteria of IWC-5222(b,c). The piping and components in la attach to the system and are included only do to the requirements of Reg. Gude 1.26 (Feb. 1976) to include piping up to the first valve that is either normally closed or capable of automatic closure. Since the requirements of IWC-5222(b,c) can only be applied from the RWST to l-CS-48 the piping mentioned in la must be tested in accordance with IWC-5222(a). This test would be excessive since the piping would only see pressure associated with the RWST when performing its safety function.

4. As an alternative it is requested that the piping and components mentioned in la be tested to the requirements of IWC-5.222(b,c) associated with l-CS-TK-1 (RWST).

5. End of interval, within the last period.

5-28

RR-14 la) Components and associated piping to the first isolation valve as follows located on station print 11448-FM-71A.

Recirculation Spray Heat Exchangers Associated Piping Between Below Listed Valves Connecting Heat Exchangers 1-RS-E-lA MOV-SW-105A,MOV-SW-104A 1-RS-E-lB MOV-SW-105B,MOV-SW-104B 1-RS-E-lC MOV-SW-105C,MOV-SW-104C 1-RS-E-lD MOV-SW-105C,MOV-SW-104D b) Circulating and Service Water System c) Class III

2. Class III System Hydrostatic Test, IWD-5223.

3. The design specification for this component (station # NUS 85) limits the recirculation spray coolers to design pressure (25 psig) and temperature between 42 and 95°F. Under the conditions specified in IWD-5223(a) a value 1.1 times the design pressure or 27.5 psig must be used as test pressure. No substantial gain ++

would be realized at the required test pressure of 27.5 psig considering the design limitation of 25 psig *

4.

5.

As an alternative it is requested that the test pressure for IWD-5223 Class III system hydrostatic test be the design pressure 25 psig. The normal VT-2 examination will be conducted at this pressure.

End of interval, within the last period *

- 5-29 Rev. 1 12/22/82

RR-15 la) b)

c)

Open ended intake piping before the first shut-off valve in non-closed systems located on 11448-FM-71B.

Circulating and Service Water System Class III

2. System Hydrostatic Test, IWD-5223

3. The code addresses the probiem of performing hydrostatic test on open ended portions of discharge lines beyond the last shut-off

. valve in non-closed systems in IWD-5223(d) of the code. A similar problem exists for the intake piping at Surry Unit 1 as it is nonisolatable for the increased pressure requirements of a hydrostatic test.

4. As an alternative the requirements applied to open ended portions of discharge lines (IWD-5223(d)) will be applied in this case; that is confirmation of adequate flow during system operation shall be acceptable in lieu of system hydrostatic test.

5. End of interval, within the last period.

5-30

RR-16 la) Components and piping as listed located on station print 11448-FM-72B.

Component l-CC-241 TV-CC-llOA Piping 6"..,CC-76-151 6"-CC-78-151 Component l-CC-242 RO-CC-100, l-CC-246 l-CC-232 6"-CC-77-151 l-CC-233 TV-CC-llOB 6"-CC-79-151 TV-CC-llOC 6"-CC-80-151 RO-CC-101, l-CC-228 l-CC-223 6"-CC-75-151 l-CC-224 b) Component Cooling Water c) Class II

2. System Hydrostatic Test, IWC-5222

3. The piping and components listed above cannot be isolated from the Class III system encompassing the reactor containment air recirculation coolers. Since the Class II boundary contains no safety or relief valve, Pd (150 psig) will be used in determining test pressure or 165 psig. This p~essure is higher than the test pressure to be used on the Class III side which is based on Psv of 146 psig for a test pressure of 160.6 psig.

4. As an alternative to two separate Class II and Class III hydrostatic tests it is requested that a Class III hydro be run utilizing the relief valves RV-CC-112A,B,C set at 146 psig as Psv for the test. This test will encompass the components and piping listed in item la and a normal VT-2 examination will take place.

5. End of interval, within the last period.

5-31

RR-17 la) Steam Generators located on station print 11448-FM-86A.

1-RC-E-lA 1-RC-E-lB 1-RC-E-lC b) Reactor Coolant System c) Class I

2. System Leakage Test, IWB-5221 System Hydrostatic Test, IWB-5222 Visual Examination, IWA-5240

3. Primary to secondary leakage detection using code described visual detection techniques would be limited in usefullness and hazardous to conduct.

4. The normal primary to secondary leakage surveillance requirements of the plant's technical specifications provide the necessary intended code examination requirements for leakage identification.

5. In accordance with Technical Specifications at Surry.

5-32

RR-18 la) Piping and components located pn station print 11448-FB-4B.

All piping and components identified within the Class III boundaries.

b) Fuel Oil Lines; Emergency Generators c) .Class III

2. System Inservice Test, IWD-5221 System Hydrostatic Test, IWD-5223

3. This system transports fuel oil to the emergency generators so that the 550.gallon generator base tank can be refilled to maintain generator capacity. These components although of an important nature are beyond the original concept designed for Section XI testing. (That testing originally was for water, steam systems see attached inquiry; BC/77/666). In any event high pressure testing of fuel oil systems using the fuel oil as the pressurizing medium would be hazardous to conduct.

4. As an alternative, a modified system inservice test will be conducted requiring only visual examination of exposed piping; and the verification of adequate fuel transfer to the base tank to verify functional adequacy of underground piping.

5. Each period as scheduled for a system inservice test.

5-33

INQUIRY AND REPLY AS SENT TO INQUIRER 08/14/81 FILE NUMBER INQUIRER COMPANY REPLY SENT BC/77/666 UPPWSS 78/02/17 SUBJECT SCOPE OF SECTION XI, DIVISION 1 Question:

Is it the intent of Subarticle IWA-1100 that the rules and requirements of Section XI, Division 1 for inservice inspection of Class 1, 2, & 3 pressure retaining components (and their supports) be applied only to water and steam systems in light water cooled nuclear power plants?

Reply:

Systems containing other than steam or water were not originally considered by the committee in formulating the rules in Section XI; they may, however, be included for further consideration and for revisions to future editions of Section XI. The requirements shown in Section XI, Article IWA-1100 on Scope and Responsibility, specifically paragraph IWA-1400, requires the owner of the nuclear plant to determine the appropriate code, class or classes for each component of the nuclear power plant to be examined according to Section XI rules.

'5-34

- RR-19 la) Piping and Components located on the following prints:

11448-FM-72A 11448-FM-72B 11448-FM-42C 11448-FM-72D 11448-FM-72E 11448-FM-72F 11448-FM-72G lb) Component Cooling le) Class III

2) System Hydrostatic Test - IWD-5223

3) Component Cooling is utilized for cooling important safety related components associated with the nuclear core. This system cannot be isolated in most instances without removing fuel totally from the core. This action would be time consuming and delay unnecessarily the refueling process.

4) As an alternative systems which *can be isolated from the main flow path and which do not place the station in violation of its technical specifications, while the core is loaded, will be hydrostatically tested in accordance with IWD-5223. Systems which cannot be isolated will be tested in accordance with +-f-IWD-5221, which will be normally conducted, will be more than sufficient. Determination of testing will be done with emphasis on practicality, and in conducting IWD-5223 System Hydrostatic Test whenever pnssible; it should be noted that this is an upgrade of testing requirements over the first 10 year interval.

5) End of the interval within the last period .

5-35 Rev. l 12/22/82

RR-20 la) Piping and components located on the following print:

11448-FM-71B b) Service water c) Class III

2) System Hydrostatic Test - IWD-5223

3) The service water system as seen on the above mentioned drawing is used for cooling component cooling for the charging pumps and lube oil for the charging pumps. The system was designed without the use of a safety or relief valve due to the low pressure output of the charging pump service water pumps which is 29 psig (max). The maximum possible pressure source for the system would occur if an extensive heat exchanger leak occurred at either 1-SW-E-lA or lB between component cooling and service water. This pressure could be no more than 50 psig the maximum discharge pressure of l-CC-P-2A or 2B. It is felt that having to use PD or 100 psig would be excessive for this system as the maximum pressure potential is 50 psig.

4) As an alternative it' is requested that 50 psig be used as this systems Pd valve until a safety or relief valve is placed within the system to make use of P

sv

5) End of the interval, with the last period.

5-36

ML18130A376

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