Text

Rev 1 to Surry Power Station Unit 2 Inservice Insp Program, Interval 2,830501-930501.
	ML18130A444
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Site:	Surry
Issue date:	04/01/1987
From:	; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATiON UNIT 2 INSERVICE INSPECTION PROGRAM INTERVAL 2 MAY 01, 1983 - MAY 01, 1993 REVISION i i

S2-001-3 ------ - - - - - --------. Rev. 1 8704220238 870416 April 1, 1987 PDR ADOCK 05000280 G PDR

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM INTERVAL 2 MAY 01, 1983 - HAY 01, 1993 I

REVISION 1 DISTRIBUTION RECORD DISTRIBUTION DATE DISTRIBUTION DATE NO. ENTERED INITIAL NO. ENTERED INITIAL 1 21 2 22 3 23

(

4 24 5 25 6 26 7 27 8 28 9 29 10 30 11 31 12 32 13 33 14 34 15 35 16 36 17 37 18 38 19 39 20 40

Future distributions to this report wili be accompanied by two copies of the

.distribution memo, one of which is to be returned per instructions thereon, and the .other one is to be filed sequentially behind this page giving you a record of the contents of each distribution.

SZ-001-3 ii Rev. 1 April 1, 1987

- ABSTRACT VIRGINIA.ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INTERVAL 2 MAY 01, 1983 TO MAY 01, 1993 In accordance with 10CFR50.55a Surry Unit 2 was 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)(S)(iii).

The interval for which this program is applicable commenced on May 01, 1983, and will end on May 01, 1993.

The ISI Program was developed employing 10CFRSO and Reg. Guide 1.26. Quality Groups A, B, and C are the same as ASME Classes 1, 2, and 3 respectively .*

The list of drawings on the following pages identifies the drawings used in developing the program

Section 1 introduces the Inservice Inspection Program.

Section 2 describes the Class 1, 2, and 3 component Inservi~e Inspection Program developed in accordance with Subsections IWB, IWC, and IWD of ASME Section XI.

Section 3 describes the Inservice Inspection Program for component supports.

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

Section 5 describes the Inservice System Pressure Test Program .

S2-001-3 iii Rev. 1

April 1, 1987

TABLE OF CONTENTS SECTION TITLE PAGE REVISION i Assignment ii Distribution Record iii Abstract iv Table of Contents V List of Drawings 1 Introduction 2 Inservice Inspection Program for Components

3 4

Inservice Inspection Program for Component Supports Inservice Testing Program Plan for Pumps and Valves 5 System Pressure Tests Program Plan SZ-001~3 iv Rev. 1 April 1, 1987

LIST OF DRAWINGS

UNIT 2 11448-FB-4B FB DRAWINGS Fuel Oil Lines 11548-FB-6A . Air Cooling and Purging 11448-FB-46B Emergency Diesel Generator #2 11448-FB-47B Fire Protection UNIT 2 FM DRAWINGS 11548-FM-64A Main Steam 11548-FM-64B Steam Generator Nitrogen Connection 11548-FM-66A Auxiliary Steam and Air Removal 11548-FM-68A Feedwater 11548-FM-68B Cross-connect Auxiliary Feedwater 11548-FM-:71A Circulating and Service Water 11548-FM-71B Circulating and Service Water 11548-FM-72A Component Cooling 11548-FM-72B Component Cooling 11548-FM-72C Component Cooling 11448-FM-72D Component Cooling 11448-FM-n,E Component Cooling 11448-FM-72F Component Cooling 11448-FM-72G Component Cooling 11548-FM-75C Compressed Air System l 1548-FM-75E Compressed Air System 11448-FM-75G Compressed Air System S2-001-3 V Rev. 1 April 1, 1987 :

LIST OF DRAWINGS CONT .

UNIT 2 11548-FM-75J FM DRAWINGS Containment Instrument Air 11548-FM-82A Sampling System 11548-FM-83A Vent and Drains ll 548-FM-83B Vent and Drains 11548-FM-84A Containment Spray 11548-FM-84B Recirculation Spray 11548-FM-BSA Containment Vacuum and Leakage Monitoring 11548-FM-86A Reactor Coolant 11548-FM-86B Reactor Coolant 11548-FM-87A Residual Heat Removal 11548-FM-88A Chemical and Volume Control

11548-FM-BBB 11548-FM-88C l 1548-FM:..89A, Chemical and Volume Control Che~ical and Volume Control Safety Injectiod 11548-FM-89B Safety Injection 11448-FM-90A Gaseous Waste System 11448-FM-90C Gaseous Waste System 11448-FM-llBA Reactor Cavity Purification 11548-FM-123A Chemical Feed 11548-FH-124A Steam Generator Blowdown 11448-FM-130A Radiation Monitor Circ. and Service Water 11548-FH-138A Steam Generator Recirculation and Transfer UNIT 2 SPS DRAWINGS 11448-SPS-14A Containment Particulate SZ-001-3 vi Rev. l April 1, 1987

VIRGININA ELECTRIC AND POWER CO:MPANY SURRY POWER STATION UNIT 2

INSERVICE INSPECTION AND INSERVICE TESTING PROGRAM

1-1 Rev. 1 S2-001-3 April 1, 1987

1.0 INTRODUCTION

1.1 GENER.A.L INFORMATION Surry Power Station Unit 2 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.System.

The Inservice Inspection (ISI) and Inservice Testing (IST) Programs for Surry Nuclear Power Station Unit 2 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 ih writing.

The Inservice Inspection and Testing Program for Class 1, 2, and 3 Components, Components Supports, Pumps, and Valves are applicable for the ten year interval beginning May 01, 1983 and ending May 01, 1993. The present ten year interval is the second inspection interval for Surry Unit 2.

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.l.O, 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 10CFRSO and Regulatory Guide 1.26. Pursuant to 10CFRS0.55a paragraph (g)(l), 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 .

S2-001-3 1-2 Rev. 1 April 1, 1987

Descriptions of changes between Revision O and Revision 1 for the Surry Uriit 2 Inservice Inspection Program for Components are provided below. The page numbers refer to the Revision 1.

Description of Change 1 Item Descriptions were changed to better reflect the descriptions given by the Code. These changes occur throughout the document.

1 The flow diagram reference number (11715) was changed to read (11548). This change occurs throughout the document.

1 The vessel number, given in the column entitled "Line Number", was changed from RPRV to 2RCR1.

This change was applied to all of the occurrences of RPRV.

1 Also note that the unit designator "2" was added to the vessel number. The unit designator "2" was added to every vessel and pump number which did not have a unit designator in Revision 0.

3 6

Item Number Head" weld.

Bl.21 was changed to Bl.21T for "Top The vessel number unit designator in the column entitled "Line Number"' was changed from "l" to "2". This change was applied to all of the occurrences of vessel or pump numbers with "l" as the unit designator in Revision 0.

6 The Relief Request number ,was changed to a 3 digit number (ie. SR-5 is now SR-005). This change occurs throughout the document.

7 Relief Request SR-005 was added.

11 Item Number B3.120 was added to the program.

12 Item Number B3.140 was added to the program.

Item Number B3.150 was deleted from the program.

16 Exam method was changed to volumetric only and Relief Request SR-006 was added.

18 Surface exam added to Line Number RC305-2501R, and Relief Request SR-006 was added

27 Relief Request SR-011 was added.

41 Line Number SII81-1502 was changed to SI281-1502.

S2-002-3 April 1, 1987

Description of Change

43 52 Item Number B8.10 Welded Attachments" BB.20.

"Reactor Vessel Integrally was moved from Item Number Flow Diagrams and Coordinates were changed to reflect the proper FM. This change has occurred throughout the document. Relief Request 'SR-009 was added.

57 Line Number SI247-1502 for Item Number B9.31 was changed to RC324-1502 and Relief Request SR-003 was added.

59, 60, & 61 The following Line Numbers were changed from Item Number B9.31 to B9.32:

CH301-1502 RC353-1502 RC416-1502 RC431-1502 RC447-1502 64 The Flow Diagram Coordinate was changed from AB to A-8 for Line Number RC412-1502 .

66 68, 69, 70, & 71 The Flow Diagram Coordinate was changed from El to E-1 for Line Number SI280-1502.

The following Line Numbers were added to Item Number BlO .10:

CH426-152 RC339-1502 CH515-152 RC340-602 RC320-602 RC362-602 RC336-602 RC322-1502 RC337-1502 RH116-1502 RC338-1502 88 Line Number CHll-1502 was changed to CH411-1502.

98 Line Number RC447-1502 was changed from RC477-1502. This change occurs throughout the document.

101 & 118 Flow Diagram Coordinate was changed from 2-5 to I-5 for Line Number RC361-1502.

123 & 125 Relief Request SR-009 has been added to Line Number 2CHFL3.

125 Line Numbers CHTK2 and CHE3 have been deleted from Item Number Cl.10.

Line Number 2CHE3 was added to Item Number Cl.20.

S2-002-3 April 1, 1987

Description of Change

128, 129 & 130 Item Numbers C2.10 from the program.

Item Numbers program.

C2.21 and and C2.20 have been deleted C2.22 were added to 132, 133, 134 The following Line Numbers were added t_o Item 135 & 136 Number C3.40:

CC15-121 CS122-153 CC173-151 CS123-153 CHlSl-151 CS133-153 CH301-1502 CS134-153 CH505-152 CS188-153 SI317-152 CV108-151 SI318-152 DG202-152 SI319-152 DG237-152 SI372-152 RHllS-152 CH315-1502 RH120-152 CH365-152 RS103-153 CSlOl-153 RSll 1-153 CS102-153 RS115-153 CS103-153 SI170-153 CS104-153 SI279-1502

1~9 169 176 Line Number SDHV4-601 was changed to SDHV104.

Line Number RH2-602 was changed to RH102-602.

This change occurs throughout the document.

Line Number S190-1503 was changed to SI290-1503.

This change occurs throughout 'the document.

222 thru 249 Item Number Dl.10 was replaced by Item Numbers Dl.lOH and Dl.10S.

The following line numbers were deleted from replaced Item Numbers D1.10H and Dl.10S:

CC14-121 CC15-121 CC7-121 CC9-121 231 & 245 Line Number WAPD106-60 was changed to WAPD106-601.

234 & 248 Line Number WEMU109-151 was cll.anged to WCMU109-151.

250 thru 259 Item Number D2.10 was replaced by It~m Numbers D2.10H and D2.10S.

260 & 261 Item Number D2.20 was added to the program.

S2-002-3 April 1-, 1987

Description of Change 2-14 Relief Request SR-006 was added to the Program Submittal.

2-15 & 2-16 Relief Request SR-007 was added to the Program Submittal.

2-17 Relief Request SR-008 was added to the Program Submittal.

2-18 Relief Request SR-009 was added to the Program Submittal.

2-19 Relief Request SR-010 was added to the Program Submittal.

2-20 Relief Request SR-011 was added to the Program Submittal.

2-21 Relief Request SR-012 was added to the Program Submittal.

2-22 Relief Request SR-013 was added to the Program Submittal.

2-23 Relief Request SR-014 was added to the Program Submittal .

S2-002-3 April 1, 1987

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PROGRAM FOR COMPONENTS S2-002-3 2-'1 Rev. 1 April 1, 1987

SECTION 2 TABLE OF CONTENTS 2.0 INSERVICE INSPECTION PROGRAM FOR COMPONENTS 2.1 PROGRAM DESCRIPTION 2.2 INSERVICE INSPECTION PLAN

SUMMARY

S2-002-3 2-2 Rev. 1 April 1, 1987

2.0 INSERVICE INSPECTION PROGRAM FOR COMPONENTS 2.1 PROGRAM DESCRIPTION 2.1.1 The Inservice Inspection for 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 Addendum. Where these requirements are determined to be impractical, specific requests for relief have been written and included in this section.

2.1.2 Weld selection for piping shall be in accordance with 10CFR50 utilizing the ASME Section XI, 1974 Edition, through the Summer 1975 Addendum for selection criteria. The ASME Section XI 1980 Edition through the Winter 1980 Addendum criteria will be applicable when stress calculations to support that inspection program are available.

Vessel weld selection and hanger and support selection shall be in accordance with the ASME Section XI 1980 Edition through the Winter 1980 addendum.

2.1.3 Repairs and replacements shall be in accordance with Station Administrative Procedures.

2.1.4 The existing calibration standards/blocks for ultrasonic examinations used during the first interval were designed and manufactured to satisfy the intent of ASME Section V and ASME Section XI, Appendices I and III, 1974 Edition through the Summer 1975 Addenda. Use of the blocks will supercede all current code references to calibration block material requirements as per Code Case.N335-l and N355.

2.2 INSERVICE INSPECTION PLAN

SUMMARY

2.2.1 The Inservice Inspection Plan Summary for the Component Program is presented in Section 2.2.2 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 1, 2 and 3 components.

B. Item Number and Item D.escription The Item Number and Item Description as listed in Tables IWB-2500-1, IWC-2500-1 and IWD-2500-1. Item Numbers and the applicable Item Descriptions are listed for each Code Category.

C. Exam Method - Lists the examination method or methods as reflected by the requirements of ASME Section XI.

abbreviations used are as follows:

7he S,2-002-3 2-3 Rev. 1 April 1; 1987

VOL - Volumetric per IWA-2230 SUR - Surface per IWA-2220 VIS - Visual per IWA-2211, 12, 13 and 14 D. Relief Request 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 (rom volumetric and/or surface examination by the applicable code paragraph. Components exempted from examination by code allowed exemptions will not appear in the component table of this program in most cases. The following is a list of exemptions applicable to this program.

EX IWB-1220(b), lines 1-inch nominal pipe size (n.p.s.) and less EX Withdrawn EX Withdrawn EX IWB-1220(c), head connection, 2-inches n.p.s. and less made inaccess_ible by CRD penetrations

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, associated valves, and vessels piping and 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-8 IWC-1230, piping support 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 system 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.

S2-002 2-4 Rev. 1 April 1, 1987

2.2.2 EX IWD-5223(e), open ended vent and drain lines from components extending beyond lines.

the last shut-off ended safety or relief valve discharge The Inservice Inspection Plan Summary on the following pages lists the applicable Class 1,

2, and 3 systems which are covered in the Inservice Inspection Program .

SZ-002-3 2-5 Rev. 1 April 1, 1987

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE l *

ASME SECTION XI EDITION 80W80 REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-A PRESSURE RETAINING WELDS IN REACTOR VESSEL ITEM NUMBER. : Bl.11 ITEM DESCRIPTION: RV CIRCUMFERENTIAL SHELL WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM** LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A F-5 2RCR1 VOL

VIRGINIA ELECTRIC ANO POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SU1111ARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 2 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY B-A PRESSURE RETAINING WELDS IN REACTOR VESSEL **

ITEM NUMBER : Bl.12 ITEM DESCRIPTION : RV LONGITUDINAL SHELL WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM .. LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A F-5 2RCR1 VOL

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2

MMMMMMMMMMMMMiHHfiHHf*

INSERVICE INSPECTION PLAN SU!1MARY INTERVAL 2, 05/01/83 TO 05/01/93 3

PAGE

ASME SECTION XI EDITION 80W80 REVISION 0001 *

DATE 86/10/20 *

- - - - MMMMMMMMMMM************************************MMMMMMMMMMMM************************

CATEGORY B-A PRESSURE RETAINING WELDS IN REACTOR VESSEL **

ITEM NUMBER B1.21T ITEM DESCRIPTION RV CIRCUHFERENTIAL TOP HEAD WELDS ,I FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM REUEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RC Flt-86A f-5 2RCR1 VOL

VIRGINIA ELECTRIC AND POWER COMP~

SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN SUMl1ARY INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 4 ASME SECTION XI EDITION 80W80 REVISION 0001

DATE 86/10/20 *

CATEGORY .B-A PRESSURE R.ETAINING WELDS IN REACTOR VESSEL **

ITEM NUMBER Bl.30 ITEM DESCRIPTION RV SHELL-TO-FLANGE WELD FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) comm NUMBER METHOD REQUEST NOTES RC Ftt-86A f-5 2RCR1 VOL

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY .POWER STATION UNIT 2 INSERVICE INSPECTION PLAN SUl'11'1ARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 5 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20

CATEGORY S-A PRESSURE RETAINING WELDS IN REACTOR VESSEL ITEM NUMBER : Bl.40 ITEM DESCRIPTION: RV HEAO-TO-FLANGE WELD FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A f-S 2RCR1 SUR VOL

(

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 6 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY B-B PRESSURE RETAINING WELDS IN VESSELS OTHER THAN THE RV

ITEM NUMBER B2.ll ITEM DESCRIPTION PZR CIRCUMFERENTIAL SHELL-TO-HEAD WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86B S-6 2RCE2 VOL SR-005

1. *

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 7 *

ASME SECTION XI EDITION 80W80 REVISION 0001 *

DATE 86/10/20 *

- - - - It****************

CATEGORY S-B PRESSURE RETAINING WELDS IN VESSELS OTHER THAN THE RV

ITEM NUMBER B2.12 ITEM DESCRIPTION. PZR LONGITUDINAL SHELL-TO-HEAD WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM

LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86B S--6 2RCE2 VOL SR-005

If VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 If

If If INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 PAGE 8 ASME SECTION XI EDITION 80W80 .REVISION 0001 *

DATE 86/10/20 *

- lflflflf***lflf*****lf*******lfWWWlfWlflflf*******************************Wlflflflflflf*-**************************

CATEGORY B-B PRESSURE RETAINING WELDS IN VESSELS OTHER THAN THE RV ITEM NUMBER B2.40 ITEM DESCRIPTION SG PRIMARY TUBESHEET-TO-HEAD WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 115481 COORD NU1BER METHOD REQUEST NOTES RC Ftt-86A C--1 2RCE1A VOL RC Frt-86A C--6 2RCE1B VOL RC Ftt-86A J-1 2RCE1C VOL

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE' 9 *

ASME SECTION XI EDITION 80W80 REVISION 0001 *

-*

DATE 86/10/20 *

CATEGORY S-0 FULL PENETRATION WELDS OF NOZZLES IN VESSELS - PROGRAM B ITEM NUMBER : B3. 90 ITEM DESCRIPTION: RV NOZZLE-TO-VESSEL WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM REUEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A F-5 2RCR1 VOL

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SUtlMARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

- 10 *

PAGE

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-D FULL PENETRATION WELDS OF NOZZLES IN VESSELS - PROGRAM B

ITEM NUMBER* B3.100 ITEM DESCRIPTION RV NOZZLE INSIDE RADIUS SECTION FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM .LINE EXAM REUEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A F-5_ 2RCR1 VOL

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 11 *

ASMF. SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-D FULL PENETRATION WELDS OF NOZZLES IN VESSELS - PROGRAM B ITEM NUMBER B3.120 ITEM DESCRIPTION PZR NOZZLE INSIDE RADIUS SECTION FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86B S-6 2RCE2 VIS SR-0*07

VIRGINIA ELECTRIC AND POWER COMPANY

~SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 12 ASME SECTION XI EDITION 80W80 REVISION 0001

DATE* 86/10/20 *

CATEGORY B-D FULL PENETRATION WELDS OF NOZZLES IN VESSELS - PROGRAM B ITEM NUMBER B3.140 ITEM DESCRIPTION SG PRIMARY NOZZLE INSIDE RADIUS SECTION FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A C--1 2RCE1A VIS SR-007 RC Ftt-86A C--6 2RCE1B VIS SR-007 RC Ftt-86A J-1 2RCE1C VIS SR-007

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TD 05/01/93

PAGE 13 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE* 86/10/20 *

CATEGORY B-E. PRESSURE RETAINING PARTIAL PENETRATION WELDS IN VESSELS ITEM NUMBER B4.12 ITEM DESCRIPTION ALL VESSELS, CRD NOZZLE PARTIAL PENETRATION WELD FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM REUEF PROGRAM COMPONENT (11548) CDORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A F-S 2RCR1 VIS

VIRGINIA ELECTRIC AND POWER COHPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 14 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY B-E PRESSURE RETAINING PARTIAL PENETRATION WELDS IN VESSELS ITEM NUMBER : B4.13 ITEM DESCRIPTION: ALL VESSELS, INSTRUMENT NOZZLE PARTIAL PENETRATION FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM - LINE EXAM REUEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

RC FH-86A F-s 2RCR1 VIS

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

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 * . PAGE 15 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY B-E PRESSURE RETAINING. PARTIAL PENETRATION WELDS IN VESSELS

ITEM NUMBER B4.20 ITEM DESCRIPTION PRESSURIZER HEATER PENETRATION WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM REUEF PROGRAM COMPONENT !11548) COORD NUMBER METHOO REQUEST NOTES RC FH-868 2RCE2 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION .UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 16 *

ASHE SECTION XI EDITION 80W80 *' REVISION 0001 *

DATE 86/10/20 *

*CATEGORY S--F PRES~E RETAINING DISSIMILAR METAL WELDS ITEM NUl1BER 65.10 ITEM DESCRIPTION RV NOMINAL PIPE SIZE >= 4T NOZZLE-TO-SAFE END BUTT WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAM RELIEF PROGRAM COMPONENT (115481 COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A E-2 RC30l-2501R VOL SR-006 RC Ftt-86A C-:4 RC303-2501R VOL SR-006 RC Ftt-86A F-5 RC304-2501R VOL SR-006 RC Ftt-86A C-:8 RC306-2501R VOL SR-006

RC RC Ftt-86A Ftt-86A H-2 K-4 RC307-2501R RC309-2501R VOL VOL SR-:006 SR-006

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *'

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PASE 17 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-F PRESSURE RETAINING DISSIMILAR METAL WELDS

ITEM NUMBER B5.20 ITEM DESCRIPTION PZR. NOMINAL PIPE SIZE >= 4T NOZZLE-TO-SAFE END BUTT WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RElIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES RC Ftf-86B G-8 RC310-2501R SUR VOL RC Ftf-86B r-s RC315-1502 SUR VOL RC Ftf-86B H-5 RC334-1502 SUR -

VOL RC Ftf-86B H-5 RC337-1502 SUR VOL RC Ftf-86B G-5 RC33S-1502 SUR VOL RC Ftt-86B G-5 RC339-l502 SUR VOL

VIRGINIA ELECTRIC AHO POWER COMPANY

SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN SU!'91ARY INTERVAL 2,_05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE 18 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-F PRESSURE RETAINING DISSIMILAR METAL WELDS ITEM NUl1BER : B5.30 ITEM DESCRIPTION : -SG NOl1INAL PIPE SIZE >= 4T NOZZLE-TO-SAFE END BlJTT WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM

COMPONENT !11548) COORD NUMBER METHOD REQUEST NOTES

' -------- =======

RC Ftt-86A E-2 RC30l-2501R SUR SR-008 VOL RC Ftt-86A e-2* RC302:""2501R SUR SR-008 VOL RC Ftt-86A E-:5 RC304-2501R SUR SR-008 VOL RC Ftt-86A 8-6 RC30S-2501R SUR SR-008 VOL RC Ftt-86A . lt-2 RC307-2501R SUR SR-008 VOL RC Ftt-86A L-2 RC308-2501R SUR SR-008 VOL

VIRGINIA ELECTRIC ANO POWER COMPANY SURRY POWER STATION UNIT 2 *

INSERYICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 19 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-S---1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER

- - - - lflf***********************************************************.

ITEM NUMBER B6. 10 ITEM DESCRIPTION RY CLOSURE HEAD NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES*

======*== -------- -------

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

RC Ftt-86A F-S

2RCR1 SUR

VIRGINIA ELECTRIC AND POWER COMPANY *

- SURRY POWER STATION UNIT 2 *

INSERYICE INSPECTION PLAN SUMNARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 20 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY ~ l PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER ITEM NUNBER B6. 20 ITEM DESCRIPTION RV CLOSURE STUDS, IN PLACE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RElIEF PROGRAM COMPONENT C11548) COOlm NUMBER. METHOO REQUEST NOTES

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

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

RC FM-86A f-5 2RCR1 VOL

i

VIRGINIA ELECTRIC AND POWER COMPANY **

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 21

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

- - - - IHHf******************************************************************

CATEGORY s-s--1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER

ITEM NUMBER .: 86. 30 ITEM DESCRIPTION.: RV CLOSURE STUDS,WHEN REMOVED FLOW - FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT I 11548) COORD NUMBER METHOD REEST NOTES

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

RC Ftt-86A F-5 2RCR1 SUR VOL

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 22 *

ASHE SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-S--1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER

- - - - If******************************************************************

ITEM NI.JNBER B6. 40 ITEM DESCRIPTION RV THREADS IN FLANGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORO NUMBER METHOD REQUEST NOTES RC Ftt-86A F-5 2RCR1 VOL

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER.STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/pl/93 ASME SECTION XI EDITION 80W80

PAGE

REVISION 23

0001

DATE 86/10/20 *

- - - - IHf**if***************************************************************************

CATEGORY B-S-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER ITEM truMBER B6. ~O ITEM DESCRIPTION RV CLOSURE WASHERS,BUSHINGS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD RE~EST NOTES RC Ftt-86A . F-5 2RCR1 VIS

1

If VIRGINIA ELECTRIC AND POWER COMPANY If If SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 PAGE 24 ASME SECTION XI EDITION 80W80 REVISION 0001 *

*If*

DATE 86/10/20

CATEGORY B-s-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER ITEM NUMBER B6.180 ITEM DESCRIPTION PUt1P BOLTS AND STUDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT (11548) comm NUMBER METHOD REQUEST NOTES RC Ftt-86A A-1 2RCP1A VOL RC Ftt-86A A-6 2RCP1B. VOL RC Ftt-86A L-1 2RCP1C VOL

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER ~TATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, ~5/01/83 TO 05/01/93 PAGE 25

ASl1E SECTION XI EDITION 80W80 ** REVISION 0001 *

DATE 86/10/20 *

CATEGORY e-G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER

- - - - llllllllllllllllll lllllllllllllllHHf*****lfllllllllllll ll JI Jllllllt*******lf*******llllllllll.llll ll ll**lf***lfllll Jlllllllll ll*******

ITEM NUMBER B6.190 ITEM DESCRIPTION PUMP FLANGE SURFACE, WHEN CONNECTION DISASSEMBLED FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REEST NOTES RC Ftt-86A A-1 2RCPU VIS RC Ftt-86A A-6 2RCP1B VIS RC Ftt-86A L-1 2RCP1C VIS

- VIRGINIA ELECTRIC ANO POWER COMPANY SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01(83 TO 05/01/93

PAGE 26 * *

- ASME SECTION XI EDITION 80W80

REVISION 0001 DATE 86/10/20

CATEGORY B-S--1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER ITEM NUMBER : B6.200 ITEM DESCRIPTION: PUNP NUTS,BUSHINGS, AND WASHERS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A 2RCP1A VIS RC Ftt-86A 2RCP1B VIS RC Ftt-86.A 2RCP1C VIS

VIRGINIA ELECTRIC AND POWER COt1PANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN Sutl1ARY

INTERVAL 2, 05/01/83 TO 05/01/93 *********************

PAGE 27 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY B-S--1 PRES~E RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER *

- - - - lHHf******

ITEM NUMBER B6.210 ITEM DESCRIPTION VALVE BOLTS Al-I> STIJDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A 0-2 RC30l-2501R VIS SR-011 RC Ftt-86A C-4 RC303-2501R VIS SR-Oll RC Ftt-86A 0-6 RC304-2501R VIS SR-011 RC Ftt-86A 0-8 RC306-2501R VIS SR-011

RC RC Ftt-86A Ftt-86A I-2 I-4 RC307-2501R RC309-2501R VIS VIS SR-011 SR-011

_.

VIRGINIA ELECTRIC AND POWER COl1PANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 28 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY e-s-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER

ITEM NUMBER : 66.220 ITEM DESCRIPTION : VALVE FLANGE SURFACE, WHEN CONNECTION DISASSEMBLED FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD tM1BER METHOD REQUEST NOTES

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

RC Ftt-86A 0-2 RC30l-2501R VIS RC Ftt-86A 0-4 RC303-2501R VIS RC Ftt-86A 0-6 RC30'r2501R VIS RC Ftt-86A 0-8 RC306-2501R VIS RC Ftt-86A 1-2 RC307-2501R VIS RC Ftt-86A I:-4 RC309-2501R VIS

.)

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE

REVISION 29

0001

DATE 86/10/20 *

CATEGORY B-S-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER ITEM NUMBER B6.230 ITEM DESCRIPTION VALVE 1-UTS,BUSHINGS, AND WASHERS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM REUEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

=======

RC Ftt-86A 0-2 RC30l-2501R VIS RC Ftt-86A 0-4 RC303-2501R VIS RC Ftt-86A 0-6 RC304-2501R VIS RC FM-86A 0-8 RC306-2501R VIS RC FM-86A 1-2 RC307-2501R VIS RC FM-86A 1-4 RC309-2501R VIS

VIRGINIA ELECTRIC AND POWER COMP.ANY

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 30

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-G-2 PRESSURE RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER ITEM NUMBER 67.10 ITEM DESCRIPTION REACTOR VESSEL BOLTS, STUDS, AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM RELIEF PROGRAM COMPONENT (11548 J COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A F-5 2RCR1 VIS

VIRGINIA ELEC.TRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 31 *

ASME SECTION XI ~DITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY B-S--2 PRESSURE RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER ITEM NUMBER B7.20 ITEM DESCRIPTION PRESSURIZER BOLTS, STUDS, AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NU11BER METHOO REQUEST NOTES RC Ftt-86B S--6 2RCE2 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 PAGE 32

ASME SECTION XI EDITION 80W80 ** REVISION 0001

DATE 86/10/20 *

CATEGORY S-S-2 PRESSURE RETAINING BOLTING, TWO INCHES At-I> LESS IN DIAMETER ITEM NUMBER B7.30 ITEM DESCRIPTION STEAM GENERATOR BOLTS, STUDS, AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM -LINE EXAM REUEF PROGRAM COMPONENT (11548) COO!m NUt1BER METHOD REQUEST NOTES

=======

RC Ftt-86.A C-1 2RCE1A VIS RC Ftt-86.A C-6 2RCE1B VIS RC Ftt-86.A J-1 2RCE1C VIS I*

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

' INSERVICE INSPECTION PLAN

SUMMARY

- INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 33 *

ASME SECTION XI EDITION 80W80

REVISION oooi *

DATE 86/10/20 *

- - - - IHf********************************************************************

CATEGORY S-S-2 PRESSURE. RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER ITEM NUMBER : B7.50 ITEM DESCRIPTION: PIPING BOLTS, STUDS, AND NUTS FLOW FLOW SYSTEM/ DIAGRAl1 DIAGRAl1 LINE EXAM RE1.IEF *PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES CH Fl'r88C S-6 CH393-1502 VIS CH . Fl'r88C 0-6 CH39s-1so2 VIS CH Fl'r88C A-6 CH39r1502 VIS RC *Fl'r86A H-3 RC344-1502 VIS RC Fl'r86A E-3 RC345-1502 VIS RC Fl'r86A E,--7 RC346-1502 VIS RC Ftt-86A I-s RC40S-1502 VIS RC Fl'r86A C--7 RC416-1502 VIS RC Ftt-86A B-8 RC4lrl502 VIS

VIRGINIA ELECTRIC ANO POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 34 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-S-2 PRESSURE RETAINING BOLTING,- TWO JNCHES ANO LESS IN DIAMETER

ITEM NUMBER : B7.50 ITEM DESCRIPTION : PIPING BOLTS, STUDS, ANO NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RElIEF PROGRAM COMPONENT <11548) COORD NUMBER METHOD REQUEST NOTES RC FM-86A B-3 RC429-1502 VIS RC FM-86A B-3 RC431-1502 VIS RC FM-86A C-4 RC432-1502 VIS RC FM-86A K-3 RC446-1502 VIS RC FM-86A K-3 RC44rl502 VIS RC FM-86A J-3 RC451-2501R VIS RC Fl'1-86B H-5 RC33rl502 VIS RC FM-86B S-5 RC33S-1502 VIS RC Fl'1-86B S-5 RC339-1502 VIS

1

VIRGINIA ELECTRIC ANO POWER COMPANY

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 35 *

ASME SECTION XI EDITION 80W80

REVISION 0001 . *.

DATE 86/10/20 *

CATEGORY B-S-2 PRESSURE RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER

- - - - lE*******

ITEM NUMBER B7.70 ITEM DESCRIPTION ~ALVE BOLTS, STUDS, Am NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAH LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES CH Ftt-88C 0-2 CH305-1502 VIS CH Ftt-88C S--3 CH30S-1503 VIS CH Ftt-88C 0-2 CH36S-1502 VIS CH Ftt-88C S-3 CH379-1502 VIS CH Ftt-88C S--6 CH393-1502 VIS CH Ftt-88C 0-6 CH395-1502 VIS CH Ftt-88C S-7 CH397-1502 VIS RC Ftt-86A 0-3 RC311-1502 VIS RC Ftt-86A 0-7 RC312-1502 VIS

- - - - ii****************************

VIRGINIA ELECTRIC AND POWER COMPANY **

SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN Sut1t1ARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 36

ASHE SECTION XI EDITION 80W80

REVISION 0001

DATE 86/10/20 *

.* CATEGORY B-S-2 PRESSURE RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER ITEM NUMBER : B7.70 ITEM DESCRIPTION : VALVE BOLTS, STIJDS, AND NUTS FLOW FLOW SYSTEM/ .DIAGRAM DIAGRAM LINE EXAM .REl.IEF PROGRAM COMPONENT. C11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A 1-3 R_c313-1502 VIS RC Ftt-86A H-3 RC3¥t-1502 VIS RC Ftt-86A E-3 RC345-1502 VIS RC Ftt-86A E-7 RC346-1502 VIS RC Ftt-86A C-3 RC353-1502 VIS RC Ftt-86A B-2 RC355-1502 VIS RC Ftt-86A B-6 RC356-1502 VIS RC Ftt-86A C-5 RC357-1502 VIS RC Ftt-86A S-1 RC35S-l502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SU1111ARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 37 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-S----2 PRESSURE RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER

'ITEM l'M1BER : 67.70 ITEM DESCRIPTION : VALVE BOLTS, STUDS, Alt> NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM RELIEF PROGRAM

. COMPONENT (11548) COOlm l'M1BER METHOD REQUEST NOTES RC Ftt-86A K-2 RC359-1502 VIS RC Ftt-86A A-7 .RC360-1502 VIS RC Ftt-86A I-5 RC405-1502 VIS RC Ftt-:86A B-8 RC416-1502 VIS RC Ftt-86A C-8 RC4lrl502 VIS RC Ftt-86A C-8 RC419-1502 VIS

~c ' Frt-86A C-7 RC421-1502 VIS RC Ftt-86A B-4 RC426-1502 VIS RC Ftt-86A B-3 RC42.9-1502 VIS

VIRGINIA ELECTRIC AHO 'POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN SUl1MARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93 PAGE 38 ASHE SECTION XI EDITION 80W80

REVISION 0001 *

DATE 66/10/20 *

- - - - i!**************************************************************************************

CATEGORY S-S-2 PRESSURE RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER

ITEM NUl1BER B7.70 ITEM DESCRIPTION VALVE BOLTS, STUDS, AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) cornm NUMBER METHOD REQUEST NOTES RC Ftt-66A S-2 RC431-1502 VIS RC Ftt-86A C-3 RC43Z---1502 VIS RC Ftt-86A C-2 RC439-1502 VIS RC Ftt-86A K-3 RC44Z---1502 VIS RC Ftt-86A K-3 RC446-1502 VIS RC Ftt-86A K-2 RC44rl502 VIS RC Ftt-86A J-3 RC44S---1502 VIS RC Ftt-86A J-2 RC4S3-1502 VIS RC Ftt-86A A-2 RC49S---1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 *********************

PAGE. 39 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20

CATEGORY a-s-2 PRESSURE RETAINING BOLTING; TWO INCHES AND LESS IN DIAMETER

ITEM NUMBER B7.70 ITEM DESCRIPTION VALVE BOLTS, ST\.IJS, AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM REUEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A A-6 RC499-1502 VIS RC Ftt-86A L-2 RC500-1502 VIS RC Ftt-86B E-a RC314-1502 VIS RC Ftt-86B f-S RCJ15-1so2 VIS RC Ftt-86B 1-4 RC33S-1502 VIS RC Ftt-86B H-5 RC33rl502 VIS RC Ftt-86B S-5 RC338-l502 VIS RC Ftt-86B G-5 RC339-1502 VIS RC Ftt-86B 1-s RC361-1502 VIS Ii

VIRGINIA ELECTRIC AND POWER COMPANY *'

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

- - - - 111111111111111111111111111**~***

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE .40 ASME SECTION XI EDITION 80W80 REVISION 0001

DATE 86/10/20 *

- - - - 111111111111111111111************************************************************************

CATEGORY S-S--2 PRESSURE RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER *

- - - - 111111111111111111111111111111111111111111111111*****************************************************************

ITEM NUMBER : 67.70 ITEM DESCRIPTION : VALVE BOLTS, STUDS, AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM REUEF PROGRAM COMPONENT (11548) . COORD NUMBER METHOD RE~EST NOTES

======== ------- ======= ------ . ------- -------

RC Flt-896 A-3 RC316-1502 VIS RC Flt-896. A-1 RC317-1502 VIS RC Flt-898 A-2 RC31S-1502 VIS RC Flt-898 A-:1 RC319-1502 VIS RC Flt-898 A-2 RC320--1502 VIS RC Flt-898 A-3 RC321-1502 VIS RC Flt-898 A-7 RC323-1502 VIS RHR Flt-87A H-7 RHlOl-1502 VIS RHR Flt-87A L-5 RH116-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SUl1MARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 41 *

ASNE SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY B-S-2 PRESSURE RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER *

I.

- - - - lHHf***************************************************************

ITEM NUMBER : 87.70 ITEM DESCRIPTION : VALVE BOLTS, STIJDS, AND NUTS FLOW FLOW SYSTEM/ DIAGRAl1 DIAGRAH LINE EXAH REUEF PROGRAM COMPONENT (115481 COORD NUMBER METHOD REQUEST NOTES RHR Ftt-87A L-5 RHllrl502 VIS SI Ftt-898 B-5 SI245-1502 VIS SI Ftt-898 A-a SI24rl502 VIS SI Ftt-898 A-3 SI272-1503 VIS SI Ftt-898 B-1 SI274-1502 VIS SI Ftt-898 A-2 SI275-1502 VIS SI Ftt-898 A-3 SI27rl503 VIS SI FM-898 A-3 SI279-1502 VIS SI Ftt-898 A-2 SI281-1so2 VIS

*It VIRGINIA ELECTRIC AND POWER COMPANY SURRY .POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

- - - - ltltltltltltltlt*****

INTERVAL 2, 05/01/83 TO 05/01/93 42 *

PAGE

ASME SECTION.XI EDITION 80W80 * - REVISION 0001 *

DATE 86/10/20 *

- - - - 1t*!tltltltltltltltlt!t*****************************************************************

CATEGORY e-s-2 PRESSURE RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER

ITEM NUMBER B7.70 ITEM DESCRIPTION VALVE BOLTS, SlUlS, Am tlJTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM REUEF PROGRAM COMPONENT ( 11548) COORD NUMBER 11ETHOD REQUEST 'NOTES SI Ftt-898 B-:-1 sI2a5-1502 VIS SI Ftt-898 B-1 51344-1502 VIS SI Ftt-898 A-1 51345-1502 VIS SI Ftt-898 A-2 SI353-1502 VIS

VIRGINIA ELECTRIC ANO POWER COMPANY *

SURRY

POWER ST ATION UNIT 2 *

INSERVICE INSPECTION PLAN Sut!MARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 43 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-H INTEGRAL ATTACHMENTS FOR VESSELS

ITEM NUNBER B8.10 ITEM DESCRIPTION RV INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT C11548) comm NUNBER METHOD REQUEST NOTES RC Ftt-86A F-s 2RCR1 VOL

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 44 ASME SECTION XI EDITION 80W80 REVISION 0001 *

DATE

86/10/20 *

CATEGORY B-H INTEGRAL ATTACHMENTS FOR VESSELS

- - - - llllllllllllllllll***lf**lflflf****lflflflfif***lflflf***'lf**lfiflflflfiflf ITEM NUNBER* 68.20 ITEM DESCRIPTION PZR INTEGRALLY MELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORO NUNBER METHOD REQUEST NOTES RC Ftt-86B S--6 2RCE2 1/0L

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 45 *

" ASME SECTION XI EDITION 80W80

REVISION 0001

DATE 86/10/20 *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER : B9.ll ITEM DESCRIPTION : CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A E-2 RC30l-2501R SUR VOL RC FM-86A S-2 RC302-2501R SUR VOL RC FM-86A A-ft RC303-2501R SUR VOL RC FM-86A E-S RC304-2501R SUR VOL RC FM-86A S-6 RC30S-2501R SUR VOL RC FM-86A S-8 RC306-2501R SUR VOL

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE. 46 ASME SECTION XI EDITION 80W80 REVISION 0001

DATE 86/10/20 *

CATEGORY S-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER ~- B9.ll ITEM DESCRIPTION: 'CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAH LINE EXAH RELIEF PROGRAM COMPONENT ( 11548) COORD 'NUMBER METHOD REQUEST NOTES

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

RC Ftt-86.A H-2 RC307-2501R SUR VOL RC Ftt-86.A L-2 RC30S-2S01R SUR VOL RC Ftt-86A K-4 RC309-2501R SUR VOL RC Ftt-86A 0-2 RC311-2501R SUR VOL RC Ftt-86A 0-7 RC312-2501R SUR VOL RC Ftt-86.A 1-3 RC313-2501R SUR VOL

" If

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83.TO 05/01/93 47

PAGE

ASME SECTION XI EDITION aowao REVISION 0001

DATE 86/10/20 *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER : 89.ll ITEM DESCRIPTION : CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL 'PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT C11548~ COORD NUtlBER METHOD REQUEST NOTES RC Ftt-86B S-8 RC310-2501R SUR VOL RC Ftt-86B E-a RC314-1502 SUR VOL RC Ftt-86B F-S RC31S-1502 SUR VOL RC Ftt-86B tt-5 RCJY.-1502 SUR VOL RC Ftt-868 tt-5 RC337-1502 SUR VOL RC Ftt-868 S-5 RC338-1502 SUR VOL

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

~ INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 48 *

ASME SECTION XI EDITION eoweo

REVISION 0001 *

DATE 86/10/20 *

CATEGORY B-J PRESSURE RETAIN!~ WELDS IN PIPING

ITEM NUMBER : B9.ll ITEM DESCRIPTION : CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM - LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86B e-s RC339-l502. SUR VOL RHR Ftt-87A H-7 RH101-1502 SUR VOL RHR Ftt-87A K-S RH116-1502 SUR VOL RHR Ftt-87A K-S RH117-1502 SUR VOL SI Ftt-86A E-2 RC316-1502 SUR VOL SI Ftt-86A E-tt RC317-1502 SUR VOL

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN SI.Jl1MARY INTERVAL 2, 05/01/83 TO 05/01/93

. ASME SECTION XI EDITION 80W80

PAGE

REVISION 0001

49 *

DATE 86/10i20 *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER : B9.ll ITEM DESCRIPTION : CIRCU1FERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM

DIAGRAM LINE EXAM RE-LIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES SI Ftt-86A E-6 RC31B-1502 SUR VOL SI Ftt-86A E-7 RC319-1502 SUR VOL SI Ftt-86A lt-4 RC320--l502 SUR VOL SI Ftt-86A lt-2 RC321-1502 SUR VOL SI Ftt-86A E-7 RC344-:-1502 SUR VOL SI Ftt-86A E-4 SI24S-1S02 SUR VOL

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 50 *

ASME SECTION XI EDITION 80M80

REVISION 0001 *

DATE 86/10/20 *

- - - - ii********************************

CATEGORY S-J PRESSURE RETAINING WELDS IN PIPING ITEM NUl1BER : B9.ll ITEM DESCRIPTION : CIRCUHFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE FLOW. FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD . NUNBER METHOD . REQUEST NOTES SI Ftt-86A lt-3 SI24rl502 ~

VOL SI Ftt-86A lt-4 sI215-1502 ~

VOL SI Ftt-86A E:-7 SI285-1502 SUR VOL SI Ftt-898 S-1 RC3lrl502 SUR VOL SI Ftt-898 A-7 RC323-1502 ~

VOL SI Ftt-898 C-7'. SI246-1502 SUR VOL

VIRGINIA ELECTRIC AND POWER COMPANY *

- SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 51 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

- - - - ii*********************************************************************************

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER 89.11 ITEM DESCRIPTION CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RElIEF PROGRAM COMPONENT 111548) COORD NUMBER

METHOD REQUEST NOTES

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

SI Ftt-898 SI34S-1502 SUR VOL

VIRGINIA ELECTRIC ANO POWER COl1PANY .

SURRY POWER STATION.UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 52 *

ASME SECTION XI EDI.TYON 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY B-J ~ESSURE RETAINING WELDS IN PIPING

ITEM HUt1BER B9.12 ITEM DESCRIPTION LONGITUDINAL WELDS IN PIPING FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAit RELIEF PROGRAM COMPONENT (11548) COORD N\Jt'SER METHOD RE~EST NOTES

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

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

RC Ftt-86A B-2 RC302-2501R SUR VOL SR-009 RC Ftt-86A B-6 RC30S-2501R SUR VOL SR-009

RC Ftt-86A L-2 RC30S-2S01R SUR VOL SR-009

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01(83 TO 05/01/93

PAGE. 53 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 ITEM NI.Jt1BER : 89.21 ITEM DESCRIPTION : CIRCUMFERENTIAL WELDS IN PIPING, NOHINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAN DIAGRAN LINE EXAM RELIEF PROGRAN COMPONENT (11548) COOOD NUT1BER METHOD REQUEST NOTES CH Ftt-86A F-8 CH301-1502 SUR CH Ftt-88C H-3 CH379-1503 SUR RC Ftt-86A B-7 RC416-1502 SUR RC Ftt-86A C--8 RC417-1502 SUR RC Ftt-86A B-2 RC431-1502 SUR RC Ftt-86A C--3 RC432:-1502 SUR RC Ftt-86A K-2 RC447-1502 SUR RC Ftt-86A J-3 RC448-1502 -Sl,JR RC Ftt-868 I-<+ RC335-1502 SUR

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN SU1'11ARY INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

- PAGE

REVISION 54

0001

DATE 86/10/20 *

CATEGORY e-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER B9.21 ITEM DESCRIPTION CIRCUT1FERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM** LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86B I-s RC361-1502 SUR SI Ftt-86A H-4 sI21s-1so2 SUR SI Ftt-86A E-1 SI280-l502 SUR SI . Ftt-86A E-S . SI281-1502 SUR SI Ftt-86A E-7 sI2ss-1so2 SUR SI Ftt-888 E-3 SI272-1503 SUR SI' Ftt-89A 1-3 SI272-1503 SUR SI Ftt-898 I~3 SI272-l503 SUR SI, Ftt-898 E-2 SI273-l503 . SUR

VIRGINIA ELECTRIC ANll POWER COMPANY

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN SUMHARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 55 *

ASME SECTION XI EDITION aowao

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-J PRESSURE RETAINING WELDS IN PIPING ,

ITEM NUMBER B9.21 ITEM DESCRIPTION CIRCUt1FERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM REUEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST. NOTES SI Ftt-898 S-1 SI274-1502 SUR SI Ftt-898 E-2 SI27rl503 SUR SI Ftt-898 C-3 SI279-1502 SUR SI Ftt-898 1-3 SI:347-1503 SUR

J-

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 56 *

PAGE

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-J PRESSURE RETAINING WELDS IN PIPING *

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

ITEM NUMBER : B9.31 ITEM DESCRIPTION : NOMINAL PIPE SIZE >= 4 IN., BRANCH PIPE CONNECT!

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM REUEF - PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86B S-8 RC310-2501R SUR SR-003 VOL RC Ftt-86B E-a RC314-1502 SUR SR-003 VOL RC Ftt-86B E-7 RC315-1502 SUR SR-003 VOL RHR Ftt-87A lt-7 RHlOl-1502 SUR SR-003 VOL RC Ftt-86A E-2 RC316-1502 SUR SR-003 VOL RC Ftt-86A E-4 RC317-1502 SUR SR-003 VOL

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN SUMHARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93, 57

PAGE

ASNE SECTION XI EDITION 80W80 REVISION 0001

DATE 86/10/20 *

- - - - Mlfif****************************************************M**************************

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER : B9.31 ITEM DESCRIPTION : NOMINAL PIPE SIZE >=*4 IN., BRANCH PIPE CONNECT!

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM REUEF PROGRAM COMPONENT I 11548) COORD NUMBER 11ETHOO REQUEST NOTES RC Ftt-86A E-6 RC31S-1502 SUR SR-003 VOL !

RC Ftt-86A E-7 RC319-1502 SUR SR-003 VOL RC Ftt-86A H-4 RC320-1502 SUR SR-003 VOL RC Ftt-86A H-2 RC321-1502 SUR SR-003 VOL RC Ftt-86A H-3 RC324-1502 s~ SR-003 VOL RC Ftt-898 A-7 RC323-1502 SUR SR-003 VOL

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN SUMHARY ********MWWMMMM*****

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 58 ASME SECTION XI EDITION 80W80 REVISION 0001 DATE 86/10/20

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING

ITEM NUMBER B9.31 ITEM DESCRIPTION NOMINAL PIPE SIZE >= 4 IN., BRANCH PIPE CONNECT!

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ------ =======* -------

SI Ft1-86A SI245-1502 SUR SR-003 VOL

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 IHSERVICE INSPECTION PLAN SUMHARY INTERVAL 2, 05/01/83 TO 05/01/93 ASHE SECTION XI EDITION 80W80

PAGE

REVISION 59

0001 *

*

DATE 86/10/20 *

CATEGORY B-J PRESSURE RETAINING WELDS IH PIPING ITEM HUMBER : B9.32 ITEM DESCRIPTION : NOMINAL PIPE SIZE < 4 IN., BRANCH PIPE C~ECTION FLOW FLOW SYSTEM/ DIAGRAM DIAGRAN ** LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD HUMBER METHOD REQUEST NOTES

.,. I CH Ftt-86A f-8 CH30l-1502 SUR CH Ftt-86A e-4 CH30S-1502 SUR CH Ftt-86B e-s CH36S-1502 SUR RC Ftt-86.A C-5 .RC327-1502 SUR RC Ftt-86.A H-2 RC344-1502 SUR RC Ftt-86.A e-3 RC34S-I502 SUR RC Ftt-86.A e-1 RC346-1502 SUR RC Ftt-86.A C-2 RC3S3-I502 SUR RC Ftt-86.A A-7 RC356-I502 SUR

(

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE

60 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S--J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER : B9.32 ITEM DESCRIPTION : NOHINAL PIPE SIZE < 4 IN., BRANCH PIPE COtf.lECTIOH FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM REt.IEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A S-1 RC35S-1502 SUR RC Ftt-86A. K-2 RC359-1502 SUR RC Ftt-86A A-7 RC360--1502 s~

RC Ftt-86A I-4 ,RC405-1502 SUR RC Ftt-86A S--8 RC415-1502 SUR RC Ftt-86A S-7 RC416-1502 SUR I RC Ftt-86A A-2 RC42s-1so2 SUR RC Ftt-86A e--2 RC431-1502 SUR RC Ftt-86A L-2 RC441-1so2 SUR

~

.)

- - - - lflflllflllll!IIIIMllllllll***lf***lf****"l(l(l!l(l(l(lll(*******l(l(l(lll!l!l(l!l(lfl(l(l!l(l(l!l!l(l(l(lf*************"l(l!l!l(l(III(******

VIRGINIA ELECTRIC ANO POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI'EDITION 80W80

- - - - lllfl(lll!llll***lf**lf

PAGE

REVISION 0001 61 *

DATE 86/10/20

11 CATEGORY S-J PRESSURE RETAINING WELDS IN PIPING

ITEM NUMBER : B9.32 ITEM DESCRIPTION : NOMINAL PIPE SIZE < 4 IN., BRANCH PIPE CONNECTION FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM REl.IEF PROGRAM COMPONENT ( 11548) COORD NUt1BER METHOD REQUEST NOTES RC FH-86A K-3 RC446-1502 SUR RC FH-86A K-2 RC447-1502 SUR RC FH-86A A-2 RC49S-1502 SUR RC FH-86A A-6 RC499-1502 SUR RC FH-86A L-2 RCS00-1502 SUR SI FH-86A E-1 SI280-1502 SUR SI FH-86A E-S sI281-1so2 SUR SI FH-896 C--3 SI279-1502 SUR

VIRGINIA ELECTRIC ANO POWER COMPANY

SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 62

PAGE

ASME SECTION XI EDITION 80W80 REVISION 0001

DATE 86/10/20 *

.CATEGORY S-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER : B9.40 ITEM DESCRIPTION : PIPE SOCKET WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAH LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER HETHOO REQUEST NOTES

-------- ------- ======*= ------ ------- -------

CH Ftt-86A F-8 CH30l-l502 SUR CH Ftt-86A E-4 CH30S-1502 SUR CH Ftt-86A A-2 CH30S-1503 SUR CH Ftt-86A A,-7 CH309-l503 SUR CH Ftt-86A L-2 CH310-l503 SUR CH Ftt-86B E-5 CH368-l502 SUR CH Ftt-88C S---6 CH393-l502 SUR CH Ftt-88C 0-6 CH39S-1502 SUR CH Ftt-88C S-6 CH397-1502 SUR I

VIRGINIA ELECTRIC AND POWER COHPANY SURRY POWER STATION UNIT 2

-INSERVICE INSPECTION PLAN SU111'1ARY INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE

REVISION 0001 63

'*

DATE 86/10/20 *

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM.NUMBER : B9.40 ITEM DESCRIPTION : PIPE SOCKET WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86.A C--5 RC327-1502 SUR RC Ftt-86.A H-2 RC344-15Q2 SUR RC Ftt-86.A E-3 RC345-1502 SUR RC Ftt-86.A E-7 RC346-1502 SUR RC Ftt-86.A K-S RC3S3-1502 SUR RC Ftt-86.A B-2 RC355-1502 SUR RC Ftt-86.A A-7 RC3S6-1502 SUR RC Ftt-86.A S-1 RC3SS-1502 SUR RC FM-86.A K-2 RC359-1502 SUR

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN Sutl1ARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 64 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER : B9.40 ITEM DESCRIPTION : PIPE SOCKET WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM REUEF_ PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A A-7 RC360-1502 SUR RC Ftt-86A 1-4 RC405-1502 SUR RC Ftt-86A A-8 RC412-l502 SUR RC Ftt-86A S-8 RC415-1502 SUR RC Ftt-86A C-8 RC417-1502 SUR RC Ftt-86A C-8 RC417-2501R SUR

/"

RC Ftt-86A C-7 . RC421-1502 SUR RC Ftt-86A A-2 RCl\25-1502 SUR RC Ftt-86A A:-2 RC42S-2501R SUR 1=

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 * *

INS ERV ICE INSPECTION-PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 65 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER B9.40 ITEM DESCRIPTION PIPE SOCKET WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM** LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

RC FM-86A A-3 RC429-1502 SUR RC Ftt-86A C-3 RC432-1502 SUR RC Ftt-86A C-2 RC439-1502 SUR L-2 RC Ftt-86A RC441-1502 SUR RC Ftt-86A L-3 RC442-1502 SUR RC Ftt-86A K-3 RC446-1502 SUR RC FM-86A .t-3 RC448-1502 SUR RC FM-86A .t-2 RC4S3-1502 SUR RC FM-86A A-2 RC49S--1502 SUR

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 66

ASME SECTION XI EDITION 80W80 REVISION 0001

DATE 86/10/20

CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING

ITEM NUMBER : B9.40 ITEM DESCRIPTION : PIPE SOCKET WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM RELIEF PROGRAM COMPONENT (11548) C~D NUMBER METHOD REQUEST NOTES RC Ftt-86A A-6 RC499-1502 SUR RC Ftt-86A L-2 RCS00-1502 SUR RC Ftt-868 1-4 RC335-1502 SUR r-s RC Ftt-86B RC361-1502 SUR SI Ftt-86A H-4 SI275-1502 SUR SI Ftt-86A E-:-1 SI280-1502 SUR SI Ftt-86A e-s SI281-1502 SUR SI Ftt-86A E-7 5!285-1502 SUR SI Ftt-888 e-3 SI27Z-1503 SUR

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 67 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-J PRESSURE RETAINING MELDS IN PIPING ITEM NUMBER B9.40 ITEM DESCRIPTION PIPE SOCKET WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM - LINE EXAM RE-LIEF PROGRAM COMPONENT (11548) COORD NUl1BER METHOD REQUEST NOTES SI Ftt-89A E-S SI273-1503 SUR SI Ftt-898- C--3 Sl272-1503 SUR SI Ftt-898 E-2 SI273-1503 SUR SI Ftt-898 S-1 SI274-1502 SUR SI Ftt-898 E-2 SI27rl503 SUR SI Ftt-898 C-,-3 SI279-1502 SUR

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 *********************

PAGE 68 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20

CATEGORY B-K-1 INTEGRAL ATTACHMENTS FOR PIPING, PUMPS, AND VALVES ITEM tM1BER : Bl0.10 ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD tM1BER METHOD REQUEST NOTES CH FM-86A f-8 CH30l-1502 SUR CH FM-86A L-2 CH310--1503 SUR CH FM-88A S-5 CH426-152 SUR CH FM-88C lt-3 CH37Crl503 SUR CH FM-88C 0-<t CH515-152 SUR RC FM-86A K-5 RC353-1502 SUR RC FM-86A S-1 RC35S-1502 SUR RC FM-86A B-7 RCC.16-1502 SUR RC FM-86A B-2 RC431-1502 SUR r

I

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER IHSERVICE INSPECTION '

STATION UNIT 2 PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93*

ASME SECTION XI EDITION 80W80

PAGE 69

REVISION 0001 *

DATE 86/10/20 *

- - - - IHHHI**********************

CATEGORY S-K-I INTEGRAL ATTACHMENTS FOR PIPING, PUMPS, AND VALVES

ITEM NUMBER : BIO.IO ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM REUEF PROGRAM COMPONENT (11548) COORD NUMBER MEJllOD REQUEST NOTES RC Ftt-86A K-2 RC447-1502 SUR RC Ftt-86A A-6 RC499-1502 SUR RC Ftt-86B S-8 RC310-2501R SUR RC Ftt-86B E-a RC3I4-I502 SUR RC Ftt-86B F-5 RC3IS-I502 SUR RC Ftt-86B H-4 RC320-602 SUR RC Ftt-86B H-5 RC334-I502 'SUR RC Ftt-86B I-s RC33S-I502 SUR RC Ftt-86B E-4 RC336-602 SUR

VIRGINIA ELECTRIC ANO POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN SU1111ARY INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE

REVISION 70

0001

DATE 86/10/20 *

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

- - - - lflf********************

ITEM NUMBER BlD.10 ITEM DESCRIPTION PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (115481 COORD NUMBER METHOD REQUEST NOTES RC Ftt-86B H-4 RC337-1502 SUR RC Ftt-86B S--5 RC338-1502 SUR RC Ftt-86B S--5 RC339-1502 SUR RC Ftt-86B

S--4 RC340-602 SUR RC Ftt-86B I-s RC361-1502 SUR RC Ftt-86B J-4 RC362-602 SUR RC Ftt-898 S--5 RC322-1502 SUR RC Ftt-898 A-7 RC323-1502 SUR RHR Ftt-87A H-7 RHlOl-1502 s~

/

- - - - )()()()( )( )()()()()()()(*******************

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2

- - - - )()()()()()()()()()()()()(jf INSERVICE INSPECTION PLAN SUMHARY INTERVAL 2, 05/01/83 TO 05/01/93

ASME SECTION XI EDITION 80W80

PAGE* 71 *

REVISION 0001 *

DATE 86/10/20

jf

- - - - )()()()()()()()()()()()(********************************************)()()()()()()(lHHHHf-)(jf*******************.

CATEGORY S-K-1 INTEGRAL ATTACHMENTS FOR PIPING, PUNPS, AND VALVES

ITEM NUMBER Bl0.10 ITEM DESCRIPTION PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RE1.IEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

------- ------- . ====== ======= -------

RHR Ftt-87A K-S RH116-1502 SUR RHR Ftt-87A K-S RHll 7-1502 SUR SI Ftt-86A E-4 SI245-1502 SUR SI Ftt-86A H-3 SI247-1502 SUR SI Ftt-86A E-1 SI280-l502 s~

SI Ftt-86A E-S sI2a1-1so2 SUR SI Ftt-898 A-7 RC323-1502 SUR SI Ftt-898 B-5 SI24S-1502 SUR SI F,tt-898 C-7 SI246-1502 SUR

_)

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 PAGE 72 ASME SECTION XI EDITION 80W80 REVISION 0001 DATE 86/10/20

I

(

I I

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 (11548) COORD NUMBER METHOD REQUEST NOTES SI Ftt-898 B-8 SI247-1502 SUR SI Ftt-898 C-3 SI27Z-1503 SUR SI Ftt-898 E-2 SI273-1503 SUR SI Ftt-898 E-2 SI277-1503 SUR SI Ftt-898 C-3 SI279-1502 SUR

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN Sutll1ARY /

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 73 *

ASME SECTION. XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY B-K-1 INTEGRAL ATTACHMENTS FOR PIPING, PUMPS, AND VALVES ITEM NUMBER Bl0.20 ITEM DESCRIPTION PUHP INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAH DIAGRAH

LINE EXAH REUEF PROGRAH COMPONENT (11548) COORD NUMBER METHOD RE~UEST NOTES RC Ftt-86A A-1 2RCP1A SUR RC Ftt-86A* A-6 2RCP1B SUR RC Ftf.86A L-1 2RCP1C SUR

VIRGINIA ELECTRIC AND POWER COMPANY **

SURRY POWER. STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 74 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20

INTEGRAL ATTACHMENTS FOR PIPING, PUMPS, AND VALVES ITEM NUMBER Bl0.30 ITEM DESCRIPTION VALVE INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT <11548) comm NUMBER METHOD REEST NOTES CH Ftt-86A CH310-1503 SUR

VIRGINIA ELECTRIC AND POWER COMPANY SURRY

" POWER STATION-UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 75

ASME SECTION XI EDITION 80W80 REVISION 0001 DATE 86/10/20

CATEGORY B-L-2 PU1P CASINGS ITEM NUMBER 612.10 ITEM DESCRIPTION PU1P CASING WELDS FLOW FLOW SYSTEM/ DIAGRAl1 DIAGRAM LINE EXAl1 REt.IEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A A-1 2RCP1A VOL RC Ftt-86A A-6 2RCP1B VOL RC Ftt-86A L-1 2RCP1C VOL

VIRGINIA ELECTRIC ANO POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 76 *

ASME SECTION XI EDITION 80W80

REVISION 0001

DATE 86/10/20

CATEGORY B-L-2 PUMP CASINGS ITEM NUMBER B12.20 ITEM DESCRIPTION PUMP CASING FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM REUEF PROGRAM COMPONENT (11548) COORD HUMBER METHOD REQUEST NOTES RC -Ftt-86A A-1 2RCP1A VIS RC Ftt-86A A-:6 2RCP1B VIS RC Ftt-86A L-1 2RCP1C VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURR°f POWER STATION UNIT 2

INSERVICE INSPECTION PLAN SutlMARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 77

ASHE SECTION XI EDITION 80W80

REVISION .0001 *

DATE 86/10/20 *

CATEGORY EHt-2

VALVE BODIES

ITEM NUl1BER : B12.40 ITEM DESCRIPTION : VALVE, VALVE BODY EXCEEDING 4 IN. NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM** LINE EXAM RElIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A E-1 RC30l-2501R VIS SR-001 RC Ftt-86A D-3 RC303-2501R VIS SR-001 RC Ftt-86A D-6 RC304-2501R VIS SR-001 RC Ftt-86A D-8 RC306-2501R VIS SR-001 RC Ftt-86A H-1 RC307-2501R .VIS SR-001 RC Ftt-86A H-3 RC309-2501R VIS SR-001 RC Ftt-86A C-4 RC3U-2501R VIS SR-001 RC Ftt-86A C-8 RC312-2501R VIS SR-001 RC Ftt-86A 1-4 RC313-2501R VIS SR-001

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

- - - - 4MMMMMMM******

INTERVAL 2, 05/01/83 TO 05/01/93 PAGE 78 ASME SECTION XI EDITION 80W80 REVISION 0001 DATE 86/10/20

CATEGORY S-tt-2 VALVE BODIES

ITEM NUMBER : 612.40 ITEM DESCRIPTION: VALVE, VALVE BODY .EXCEEDING 4 IN. NOHINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAl1 LINE EXAM ;, RELIEF PROGRAM COMPONENT (11548) COORD Nllt1BER METHOD REQUEST NOTES RC Ftt-86B H-4 RC337-1502 VIS SR-001 RC Ftt-86B S--4 RC338-1502 VIS SR-001 RC Ftt-86B F-4 RC339-1502 VIS SR-001 RC Ftt-898 A-2 RC316-1,02 VIS SR-001 RC Ftt-898 A-1 RC317-1502 VIS SR-001 RC Ftt-898 A-2 RC31S-1502 VIS SR-001 RC Ftt-898 A-1 RC319-1502 VIS SR-001 RC Ftt-898 A-1 RC320-1502 VIS SR-001 RC Ftt-898 A-3 RC321-1so2 VIS SR-001

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN Sl.Jt1HARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93 79 *

PAGE ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20

CATEGORY S-M-2 VALVE BOOIES

ITEM tM1BER : B12.40 ITEM DESCRIPTION : VALVE, VALVE BOOY EXCEEDING 4 IN. NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM

DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD tM1BER METHOD REQUEST NOTES RHR FM-87A H-7 RH101-1so2 VIS SR-001 RHR FM-87A L-5 RH116-1502 VIS SR-001 RHR FM-87A K-5 RH117-1502 VIS SR-001 SI FM-898 C-5 SI245-1502 VIS SR-001 SI FM-89B F-7 SI246-1502 VIS SR-001 SI FM-898 C-8 SI247-1502 VIS SR-001 SI FM-898 B-1 SI344-1502 VIS SR-001 SI FM-89B A-1 SI345-1502 VIS SR-001 SI FM-898 B-2 SI353-1502 VIS SR-001

r VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80 PAGE 80 REVISION 0001

DATE 86/10/20

CATEGORY B-trl INTERIOR OF REACTOR VESSELS ITEM NUMBER B13.10 ITEM DESCRIPTION RV VESSEL INTERIOR FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A F-S 2RCR1 VIS

- - - - MMMMMMlEMMMMMMMMlEMMMMMM***-*******MMMlEMMMMMMMMMMMMMMMMMMMM***MMMMMMMMMMMMMMMM*****MMMMMMlEMM****

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 81 *

ASHE SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

- - - - if*********************************

CATEGORY S-N-1 INTERIOR OF REACTOR VESSELS ITEM NUl1BER B13.30 ITEM DESCRIPTION RV CORE SUPPORT STRUCTURE ( PWR)

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUl1BER METHOD REQUEST NOTES RC Ftt-86A F-5 2RCR1 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 82 *

PAGE ASME SECTION XI EDITION 80W80 REVISION 0001 *

DATE 86./10/20 *

CATEGORY B-0 PRESSURE RETAINING WELDS IN CONTROL ROD DRIVE HOUSINGS ITEM NUMBER : B14.10 ITEM DESCRIPTION: RV WELDS IN CRD HOUSING FLOW FLOW SYSTEM/ tDIAGRAH. DIAGRAM LINE EXAM REUEF PROGRAM COMPONENT (11548) cocmo NUMBER METHOD REQUEST NOTES

-------- ------- ======= ------ ------- =.======

RC Ftt-86A F-5 2RCR1 VOL

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SUMNARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93 83 *

PAGE

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS **

ITEM NUMBER B15.10 ITEM DESCRIPTION RV PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* !,.INE EXAM REUEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A F-s 2RCR1 VIS

~

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SUl1MARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 84 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

./

CATEGORY S-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER B15.11 ITEM DESCRIPTION RV PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAH DIAGRAM LINE EXAM RE1.IEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A . F-5 2RCR1 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN SUMHARY INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE 85

REVISION 0001 *

DATE 86/10/20 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUNBER : B15.20 ITEM DESCRIPTION: PZR PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW/ FLOW SYSTEM/ DIAGRAM DIAGRAH- LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUNBER METHOD REQUEST NOTES

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

RC Ftt-86B S-6 2RCE2 VIS

* 'VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SI.Jt'l1ARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 86 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20. *

CATEGORY s-p ALL *PRESSURE RETAINING COMPONENTS ITEM NUMBER Bl5.21 ITEM DESCRIPTION PZR PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM - DIAGRAM LINE EXAM I RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86B G-6 2RCE2 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SUl1!1ARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 87 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY B-P ALL PRESSURE-RETAINING COMPONENTS ITEM NUMBER B15.50 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM REUEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES CH Fl't-88C D-2 ono1-1502 VIS CH Fl't-88C D-2 CH305-1502 VIS CH Fl't-88C 1-3 CH308-1503 VIS CH Fl't-88C S-3 CH309-1503 VIS CH Fl't-88C lt-3 CH310-1503 VIS CH Fl't-88C D-2 CH36S-1502 VIS CH Fl't-88C S-3 CH379-1503 VIS CH Fl't-88C C-6 CH405-1502 VIS CH Fl't-88C f-6 CH40S-1502 VIS

llllllllllllllllllllllllllllllllllllllllllllllllllllllllllllllllllllllllllllllllllllllll,lllllllllllllHfllll***-****IIIEIEJIIEl(l(JIJIJIIIJIIEJIIEIEIIIEIEIElllllllllfll***it*ll**II**

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN SUMHARY INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 88 ASME SECTION XI EDITION 80W80 REVISION 0001

DATE 86/10/20

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

- - - - lllllll!IEl!lllllllll!l!l!l!JIJ(J(*****lll(J(l(l(l(l(l(l(l(l(l(JIJ(J(J(J(***~*****lllll!lllllllll!lllllllllllllllll(J(***ifllllll***llllllllllllllllll*

ITEM NUMBER : B15.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW Fi.OW SYSTEM/ DIAGRAM DIAGRAM LINE EXAH RElIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES

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

CH Ftt-88C I-6 CH411-1502 VIS I-CH Ftt-88C C-3 CH423-1502 VIS CH Ftt-88C B-3 CH523-1502 VIS RC Ftt-86A e-2 RC30l-2501R VIS RC Ftt-86A B-2 RC302-2501R VIS RC Ftt-86A A-4 RC303-2501R VIS RC Ftt-86A e-s RC304-2501R VIS RC Ftt-86A A-6 RC30S-2501R VIS RC Ftt-86A B-8 RC306-2501R VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TD 05/01/93

PAGE 89 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY e-p ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : BIS.SO ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORO NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A H-2 RC307-2501R VIS RC Ftt-86A K-2 RC30S-2501R VIS RC Ftt-86A K-<+ RC309-2501R VIS

RC RC RC Ftt-86A Ftt-86A Ftt-86A H-1 0-2 0-7 RC310-2501R

RC311-2501R RC312-2501R VIS VIS VIS RC Ftt-86A 1-2 RC313-2501R VIS RC Ftt-86A E-<+ RC314-1502 VIS RC Ftt-86A H-<+ RC31s-1so2 VIS

- - i!MMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMM****************RMMMMMMMMMMMMMMMMMMMMMMM****************

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ********-*******

PAGE 90 *

ASME SECTION XI EDI~~QN_80W80~~- -

REVISION 0001 *

,*

DATE 86/10/20 *

- - - - ~***********************************************************************IHf***************

CATEGORY S-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : B15.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUtllARY-SYSTEH LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM- LINE EXAM REt.IEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOO REQUEST NOTES RC Fl"t-86A E-2 RC316-1502 VIS RC Fl"t-86A E-4 RC317-1502- VIS RC Ftt-86A E-6 RC31S-1502 VIS RC Ftt:-86A E-6 RC319-1502 VIS RC Ftt-86A ,H-4 RC320--1502 VIS RC Ftt-86A H-2 RC321-1502 VIS RC Ftt-86A E-5 RC322-1502 VIS RC Ftt:-86A E-a RC323-1502 VIS' RC Ftt-86A H-3 RC324-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2

if INSERVICE INSPECTION PLAN SU11MARY ****ififMMMMMMMM******

INTERVAL 2, 05/01/83 TO 05/01/93 PAGE 91

ASME SECTION XI EDITION 80W80

REVISION 0001

if

DATE 86/10/20 *

- - - - -****************-*****************************ifMMMMMMMMMMMMMMM**********************

CATEGORY S-P All PRESSURE RETAINING COMPONENTS

- - - - lfiHI**************************************************************************************

ITEM NUMBER : B15.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A H-3 RC344-1502 VIS RC Ftt-86.t. E-3 RC345-1502 VIS RC Ftt-86A E-7 RC346-1502 VIS RC Ftt-86.t. E-2 RC347-1502 VIS RC Ftt-86A E-1 RC348-1502 VIS RC Ftt-86.t. H-2 RC349-l502 VIS RC Frt-86.t. C-3 RC353-1502 VIS RC Ftt-86.t. S-2 RC35s-1502 VIS RC FM-86A A-7 RC356-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SUMHARY ****11111111************

INTERVAL 2, 05/01/83 TO 05/01/93 92 ASME SECTION XI EDITION 80W80

PAGE 0001

REVISION *

DATE 86/10/20 *

- - - - II 1111111111111111 II*******************************************************************************

CATEGORY 6-'-P - ALL PRES~E RETAINING COMPONENTS

ITEM NUl1BER : BIS.SO ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKA6E FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A B-'-5 RC357-1502 VIS RC Ftt-86A I-1 RC3S8-1502

VIS RC Ftt-86A. K-2 RC359-1502 VIS RC Ftt-86A A-'7, RC360--1502 .VIS RC Ftt-86A 0-3 RC363-1502 VIS RC Ftt-86A 0-8 RC364-1502 VIS RC Ftt-86A I-3 RC36S-1502 VIS RC Ftt-86A B-'-1 RC39Z-1502 VIS RC Ftt-86A . B-'-1 RC393-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 93 *

ASHE SECTION XI EDITION 80W80

REVISION 0001 *

CATE 86/10/20 **

CATEG,ORY S-P ALL PRESSURE RETAINING COMPONENTS **

ITEM NUMBER . : BIS.SO ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW

.SYSTEM/ DIAGRAM DIAGRAM LINE EXAM REUEF PROGRAM COMPONENT (11548) COORD NUMBER* METHOD REQUEST NOTES

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

RC FM-86.A e--1 RC394-1S02 VIS RC FM-86.A C--2 RC39S-1S02 VIS RC FM-86.A A-6 RC396-1S02 VIS RC FM-86.A A-6 RC39r1S02 VIS RC FM-86A A-6 RC398-1502 VIS RC ' FM-86.A C--6 RC399-1502 VIS RC FM-86.A K-1 RC400-1502 VIS RC FM-86.A K-1 RC40l-1502 VIS RC FM-86A K-1 RC402-1502 VIS

VIRGINIA ELECTRIC AND POWER COHPANY

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN SUMl1ARY ****************JHHHf

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 94 *

ASHE SECTION XI EDITION 60W80

REVISION 0001 *

* .DATE 86/10/20 *

CATEGORY B'-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : BIS.SO ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM .. LINE EXAM REUEF PROGRAM COMPONENT (11546) COORD NUMBER METHOD RE~EST NOTES RC Ftt-86A J-2 RC403-1502 VIS RC Ftt-86A I-5 RC40S-1502 VIS RC ' *Ftt-86A I-5 RC406-1502 VIS RC Ftt-86A A-8 RC412-1502 VIS RC Ftt-86A A-8 RC413-2501R VIS RC Ftt-86A A-8 RC414-1502 VIS RC Ftt-86A C-8 RC415-1502 VIS RC Ftt-86A A-7 RC416-1502 VIS RC Ftt-86A B'-6 RC417-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 95 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY e-p ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER BIS.SO ITEM .DESCRIPTION PIPING PRES~E RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RC FH-86A S-7 RC418-1502 VIS RC FH-86A S-8 RC419-2501R VIS RC FH-86A S-8 RC420-1502 VIS RC '-. FH-86A C-7 RC421-1502 VIS RC FH-86A C-7 RC422-1502 VIS RC FH-86A C-7 RC423-1502 VIS RC FH-86A C-6 RC424-1502 VIS RC FH-86A A-2 RC425-1502 VIS RC FH-86A S-3 RC426-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *"

SURRY POWER STATION UNIT 2 **

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 PAGE

96 ASME SECTION XI EDITION 80W80 REVISION 0001 DATE 86/10/20

CATEGORY e-p A.LL PRESSURE RETAINING COMPONENTS **

ITEM NUMBER : 815.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM** LINE EXAM RELIEF PROGRAM

cOMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ------- . ------ ------- ===*====

RC Ftt-86A A-3 RC427-1502 VIS

. RC Fttc86A B-3 RC42S--2501R VIS RC Ftt-86A S-3 RC429-1502 VIS RC Ftt-86A B-4 RC430-1502 VIS RC Ftt-86A B-2 RC431-1502 VIS RC Ftt-86A C--3 -RC432-1so2 VIS RC Ftt-86A S-3 RC433-2501R VIS RC Ftt-86A C--3 RC434-1502 VIS RC Ftt-86A C--2 RC436-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 IHSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 97 *

ASHE SECTION XI EDITION 80W80 * ~EVISION 0001 *

DATE 86/10/20

- - - - IHHHf****************************************************

CATEGORY S--P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER B15.50 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM L~AKA6E FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM REt.IEF PROGRAM COMPONENT. (11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A C--2 RC437-1502 VIS RC Ftt-86A C--2 RC438-l.502 VIS RC Ftt-86.A C--2 RC439-1502 VIS RC FH-86A A-7 RC440--1502 VIS RC Ftt-86A L-2 RC441-1502 VIS RC Ftt-86.A K-3 RC442-1502 VIS RC Ftt-86.A L-3 RC443-1502 VIS RC Ftt-86.A K-3 RC444-2501R VIS RC Ftt-86.A K-4 RC445-1502 VIS J_

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY PQI.IER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 98 ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER 615.50 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ D.IAGRAM DIAGRAM LINE EXAM REUEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A K-4 RC446-1502 VIS RC Ftt-86A K-2 RC44rl502 VIS RC Ftt-86A J-3 RC448-1502 VIS RC Ftt-86A J-3 RC449-1502 VIS RC Ftt-86A J-3 RC451-2501R VIS RC Ftt-86A J-4 RC452-1502 VIS RC Ftt-86A J-2 RC453-1502 VIS RC Ftt-86A J-2 RC454-1502 VIS RC Ftt-86A J-2 RC45S-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN SUl1t1ARY WWWWWWWWWWWWW**lf****

INTE_RVAL 2, 05/01/83 TO 05/01/93 PASE 99

ASME SECTION XI EDITION 80W80

REVISION 0001 **

DATE 86/10/20

CATEGORY e-p ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : B15.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ------- ------ =======* -------

i I

RC FH-86A J-2 RC456-1502 VIS I RC FH-86A J-4 RC461-1502 VIS RC FH-86A H-4 RC462-1502 VIS RC FH-86A I-2 RC463-1502 VIS RC FH-86A

0-2 RC465~1502 VIS RC FH-86A E-6 R~466-1502 VIS RC FH-86A 0-6 RC472-1502 VIS RC FH-86A G---5 RC473-1502 VIS RC FH-86A G---5 RC492-1502 VIS

]

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 100

ASHE SECTION XI EDITION 80W80 REVISION 0001

DATE 86/10/20 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : B15.SO ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAH LINE EXAM RElIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES.

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

RC Ftt-86A A-2 RC49S-1502 VIS RC Ftt-86A A-6 RC499.-1502 VIS RC *Ftt-86A l~2 RCS00-1502

VIS RC Ftt-86B . F-4 RC32S-602 VIS RC Ftt-868 S-4 RC326-602 VIS RC Ftt-868 H-4 RC327-602 VIS RC Ftt-86B S-5 RC334-1502 VIS RC Ftt-86B I-s RC335-1502 VIS RC . Ftt-86B H-4. RC337-1502 VIS

VIRGINIA ELECTRIC AND POWER COHPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION aowao

PAGE

REVISION 101

0001

DATE 86/10/20 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : 615.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE Fl,OW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

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

RC Ftt-86B S--4 RC338-1502 VIS RC Ftt-86B S--4 RC339-1502 VIS RC Ftt-86B H-7 RC350-1502 VIS RC Ftt-86B I-5 RC351-1502 VIS RC Ftt-86B I-5 RC361-1502 VIS RC Ftt-86B 0-5 RC366-1502 VIS RC Ftt-86B E-5 RC367-1502 VIS RHR Ftt-87A H-7 RHl~l-1502 VIS RHR Ftt-87A L-5 RHll?-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 102 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-P ALL PRES~E RETAINING COMPONENTS ITEM NUMBER : BlS.50 ITEM DESCRIPTION : PIPING PRES~E- RETAINING BoutllARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES

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

SI Ftt----898 S-6 SI239-1502 VIS SI Ftt----898 f-7 SI240-1502 VIS SI Ftt----898 S-8 SI241-1502 VIS

SI Ftt----898 S-5 SI245-1502 VIS SI Ftt----898 C-7 SI246-1502 VIS SI Ftt----898 S-8 SI247-1502 VIS SI Ftt----898 I-3 SI272-1503 VIS-SI Ftt----898 E-2 5!273-1503 VIS SI Ftt----8~ E-3 SI277-1503 VIS

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 103

ASME SECTION XI EDITION 80W80 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : B15.50 ITEM DESCRIPTION: PIPING PRESS~E RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RElIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

SI Ftt-898 S-3 SI279-1502 VIS SI Ftt-898 S-3 .SI281t-1502 VIS SI Ftt-898 S-2 s12a1-1502 VIS SI Ftt-898 1-2 SI347-1503 VIS

If

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN-

SUMMARY

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

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 104 *

ASM~ SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY-S-P ALL PRESS~E RETAINING COMPONENTS ITEM NUMBER : 815.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES

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

CH FH-88C 0-2 CH30l-1502 VIS CH FH-88C 0-2 CH305-1502 VIS CH FH-88C 1-3 CH30S-l503 VIS CH FH-88C S-3 CH309-1503 VIS CH FH-88C K-3 CH310-1503 VIS CH Ftt-88C 0-2 CH36S-1502 VIS cif FH-88C S-3 CH379-1503 VIS CH FH-88C C-6 CH405-1502 VIS CH FH-88C F-6 CH40S-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION l.tlIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 PAGE 105

ASME SECTION XI EDITION 80W~O REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-P ALL PRES~E RETAINING COMPONENTS ITEM NUMBER : B15.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING Boutt1ARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAH RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES CH Ftt-88C 1-6 CH411-1so2 VIS CH Ftt-88C C-3 CH423-1502 VIS CH Ftt-88C S-3 CH523-1502 VIS RC Ftt-86A E-2 RC30l-2501R* VIS RC Ftt-86A S-2 RC302-2501R VIS RC Ftt-86A A-4 RC303-2501R VIS RC Ftt-86A E-s RC304-2501R VIS RC Ftt-86A A-6 RC30S-2501R VIS RC Ftt-86A S-8 RC306-2501R VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT .2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 106 *

ASHE SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY S-P ALL PRESSURE RETAINING COMPONENTS

- - - - If***********************

ITEM NUMBER : B15.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM REUEF PROGRAM COMPONENT (11548) COORD

NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A H-2 RC30r2501R VIS RC Ftt-86A K-2 RC30S---2501R VIS RC FM-86A. K--4 RC309:-2501R VIS RC Ftf-86A H-1 RC310-2501R VIS RC FM-86A 0-2 RC311-2501R VIS RC Ftt-86A 0-7 RC312-2501R VIS RC FM-86A 1-2 RC313-2501R VIS RC Ftf-86A E-4 RC314-1502 VIS RC . Ftf-86A H-4 RC315-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 PAGE. 107

ASME SECTION XI EDITION 80W80 REVISION 0001 DATE 86/10/20 *

CATEGORY S-P ALL PRES~E RETAINING COMPONENTS

- ITEM NUMBER B15.51 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEi11 DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Frt-86A E-2 RC316-1502 VIS RC Frt-86A E-4 RC317-1502 VIS RC Frt-86A E-6 RC31S--1502 VIS

- RC RC RC FM-86A Ftt-86A FM-86A E-6 lt-4 .

lt-2 .

RC319-1502 RC320-1502 RC321-1502 VIS VIS VIS RC FM-86A E-5 RC322-1502 VIS RC FM-86A E-8 RC323-1502 VIS RC FM-86A lt-3 RC324-1502 VIS

\.

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY' POWER STATION UNIT 2

INSERVICE INSPECTION PLAN SUMHARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 108 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

- - - - lHHf****************************************************************

,CATEGORY S-P .ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER. : BlS.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUt,()ARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM REt.IEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A H-3 RC344-1502 VIS RC Ftt-86A E-3 RC34S-1502 VIS RC Ftt-86A E-7 RC346-1502 VIS RC Ftt-86A E-2 RC34rl502 VIS RC Ftt-86A E-7 RCYta-1502 VIS RC Ftt-86A H-2 RC349-1502 VIS RC Ftt-86A C-3 RC3S3-1502 VIS RC Ftt-86A

S-2 RC35s-1so2 VIS RC Ftt-86A A-7 RC3S6-1502 VIS

VIRGINIA ELECTRIC ANO POWER COMPANY *

SURRY POWER STATION UNIT 2 * , I

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 109 *

PAGE

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

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

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : 815.51 IfEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEl1/ DIAGRAM DIAGRAM LINE EXAM REUEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A a-s RC357-1502 VIS RC Ftt-86A 1-1 RC35S-1502 VIS RC Ftt-86A K-2 RC359-1502 VIS RC Ftt-86A A-7 RC360--1502 VIS

-RC Ftt-86A 0-3 RC363-1502 VIS RC Ftt-86A 0-8 RC364-1502 VIS RC Ftt-86A 1-3 RC365-1502 VIS RC Ftt-86A B-1 RC39Z-1502 VIS RC Ftt-86A B-1 RC393-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 PAGE 110 ASME SECTION XI EDITION 80W80 REVISION 0001

DATE. 86/10/20 *

CATEGORY B-P All PRESSURE RETAINING COMPONENTS ITEM NUMBER : B15.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM RElIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RC Fl't-86A s-i RC394-1502 VIS RC Fl't-86A C--2 RC395-1502 VIS RC Fl't-86A A-6 RC396-1502 VIS RC Fl't-86A A-6 RC397-1502 VIS RC Fl't-86A A-6 RC39S-l502 VIS RC Fl't-86A C--6 RC399-1502 VIS RC Fl't-86A K-1 RC400-1502 VIS RC Fl't-86A K-1 RC40l-1502 VIS RC Fl't-86A K-1 RC402-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 111 *

ASME SECTION XI EDITION 80W80 ** REVISION 0001 *

'*

DATE 86/10/20 *

.* CATEGORY S-P ALL.PRESSURE RETAINING COMPONENTS ITEM NUMBER :

B15.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM REUEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES

=======

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

RC Ftt-86A J-2 RC403-l502 VIS RC Ftt-86A I-s RC40S-1502 VIS RC Ftt-86A I-s RC406-1502 VIS RC Ftt-86A A-8 RC412-1502 VIS RC Ftt-86A A-8 RC413-2501R VIS RC Ftt-86A A-8 RC414-1502 VIS RC Ftt-86A C-8 RC41s-1sli2 VIS RC Ftt-86A A-7 RC416-1502* VIS RC Ftt-86A S-8 RC417-1502 VIS I

I 1~

/ ' ' , *. l.

VIRGINIA ELECTRIC AND POWER COMPANY

- SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN *sUHHARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 112 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

* 'DATE 86/10/20 *

-

CATEGORY S-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER 615.51 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUl-l)ARY-HYOROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAl'I RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Fl't-86A e-1 RC41S-1502 VIS RC Fl't-86A S-8 RC419-2501R VIS RC Fl't-86A S-8 RC420-1502 VIS RC Fl't-86A C-7 Rct+21-1502 VIS RC Ftr86A C-7 RC422-1502 VIS RC Fl't-86A C-7 RC423-1502 VIS RC Ftr86A C-6 RC424-1502 .VIS RC Fl't-86A A-2 RC425-1502 VIS RC Ftr86A S-3 RC426-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN SUNMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 113 **

ASME SECTION XI EDITION 80W80 REVISION 0001

DATE 86/10/20 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : BlS.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES RC Fl't-86A A-3 RC427-1502 VIS RC Fl't-86A B-3 RC42S-2501R VIS RC Fl't-86A B-3 RC429-1502 VIS RC Fl't-86A B-4 RC430-:-1502 VIS RC Fl't-86A e--2 RC431-1so2 VIS RC Fl't-86A C--3 RC432-1502* VIS RC Fl't-86A B-3 RC433-2501R VIS RC Fl't-86A C-3 RC434-1502 VIS RC .Fl't-86A C--2 RC436-1502 VIS

VIRGINIA ELECTRIC AND. POWER COMPANY SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN SU1111ARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93 PAGE 114 ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : B15.51 ITEM DESCRIPTION : PIPING PRES~URE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM REUEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

RC Fl"t-86A C-2 RC437-1502 VIS RC Fl"t-86A C-2 RC438-1502 VIS RC Ftt-86A C-2 RC439-l502 VIS RC Ftt-86A A-7 RC440-1502 VIS RC Fl"t-86A L-2 RC441-1502 VIS RC Ftt-86A K-3 RC442-1502 VIS RC Ftt-86A L-3 RC443-1502 VIS RC Ftt-86A K-3 RC444-2501R VIS RC Ftt-86A K-4 RC44S-1502 VIS

VIRGINIA ELECTRIC AND POWER COt1PANY *

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 115 ASME SECTION XI EDITION 80W80 REVISION 0001

DATE 86/10/20 *

CATEGORY S-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : BlS.51 ITEM DESCRIPTION : PIPING PRES~E RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEIV DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A K-4 RC"6-1502 VIS RC Ftt-86A K-2 RC44r1502 VIS RC Ftt-86A J-3 RC448-1502 VIS RC Ftt-86A J-3 RC"9-1502 VIS RC Ftt-86A J-3 RC4Sl-2501R VIS RC Ftt-86A J-4 RC452-1502 VIS RC Ftt-86A J-2 RC4S3-1502 VIS RC Ftt-86A J-2 RC4S4-1502 VIS RC Ftt-86A J-2 RC4SS-1502 VIS*

VIRGINIA ELECTRIC ANO POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 116 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

- - - - ltltltil~*******************~**************************************************************

CATEGORY B-P ALL.PRESSURE RETAINING COMPONENTS ITEM NUMBER 615.51 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAN REUEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REEST NOTES RC Ftt-86A J-2 RC456-1502 VIS RC Ftt-86A J-4 RC461-1502 VIS RC Ftt-86A H-4 RC462-1502 VIS RC Ftt-86A 1-2 RC463-1502 VIS RC Ftt-86A 0-2 RC465-1502 VIS RC Ftt-86A E-6 RC466-1502 VIS RC Ftt-86A 0-6 RC472-1502 VIS RC Ftt-86A S--5 RC473-1502 VIS RC Ftt-86A S--5 RC492-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SUM11ARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93 *- PAGE 117 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY B-P ALL PRESSURE. RETAINING COMPONENTS ITEM NI.Jt1BER : B15.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOU-IDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM - LINE EXAM REUEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES

========= -------- ------- ------- *====== ------- -------

RC Frt-86A A-2 RC498::"1502 VIS RC Frt-86A A---6 RC499-1502 VIS RC Frt-86A L-2 RCS00-1502 VIS RC Frt-86B f-4 RC32S-602 VIS RC Frt-86B S-4 RC326-602 VIS

RC Frt-86B H-4 RC327-602 VIS RC Ftt-86B S-5 RC334-1502 VIS RC Frt-86B I-s RC33S-1502 VIS RC Frt-86B H-4 RC337-1502 VIS I.

I 1.

VIRGINIA_ELECTRIC AHO POWER COMPANY SURRY ASME POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 SECTION XI EDITION 80W80

PAGE

- REVISION 118

0001

'lf

DATE 86/1_0/20 *

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

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : B15.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-HYDROSTATIC Fi.OW FLOW SYSTEM/ DIAGRAM DIAGRAM- LINE EXAM REUEF PROGRAM -

COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

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

RC Flt-868 S-4 RC338-1502 VIS RC Flt-868 S-4 RC339-l,502 VIS RC Flt-868 H-7 RC350-1502 VIS RC Ftt-868 I-s RC3s1-1so2 VIS RC Flt-868 I~5 RC361-1502 VIS

-RC Flt-868 0--5 RC366-150_2 VIS RC Flt-868 E-5 RC367-1502 VIS RHR Flt-87A H-7 RH101-1so2 VIS RHR Flt-87A L-5 RH117-1502 VIS

- - - - llllllllllllllll 1111111111111111***************************************************************************

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN SUM11ARY *******11111111111111111111***

INTERVAL 2, 05/01/83 TO 05/01/93 PAGE 119 ASME SECTION XI EDITION 80W80 REVISION 0001

DATE 86/10/20 *

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER : B15.51 ITEM, DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAM REl.IEF PROGRAM COMPONENT (11548) COORO NUMBER METHOD REQUEST NOTES

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

SI Ftt-898 B-6 SI23Crl502 VIS SI Ftt-898 F-7 SI240--1502 VIS SI Ftt-898 B-8 SI241-1502 VIS SI Ftt-898 e--s SI24S-1502 VIS

. SI Ftt-898 r;--7 SI246-1502 VIS SI Ftt-898 B-8 SI247-1502 VIS SI Ftt-898 1-3 SI272-1503 VIS SI Ftt-898 E-2 SI273-1503 VIS SI Ftt-898 E-3 SI277-1503 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 120 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

/

DATE 86/10/20 *

- - - - !Hf***************************************************************************

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER B15.51 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUtl)ARY~HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM REUEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES si Ftt-898 S-3 SI279-1502 VIS SI Ftt-898 B-3 SI280-1502 VIS SI Ftt-898 B-2 5!281-1502 VIS

SI Ftt-898 1-2 SI34rl503 VIS*

VIRGINIA ELECTRIC AND POWER COHPANY SURRY

POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

1111 lllf l(l(l(lHHHHHf*******

- INTERVAL 2, 05/01/83 TO 05/01/93 PAGE 121 ASl1E SECTION XI EDITION 80W80 REVISION 0001 DATE 86/10/20 *

- - - - lfl(l(l(l(lllllllllllllllllllllllllllllllllllllllllllllllt****if*********************"""*"****"""*""""""*"***************

CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : B15.60 ITEM DESCRIPTION: PUMP PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE *EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RC F~86A A-1 2RCP1A VIS RC F~86A A-6 2RCP1B VIS RC F~86A L-1 2RCP1C VIS

" VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 122

ASME SECTION XI EDITION eoweo

REVISION 0001 *

DATE 86/10/20 *

- - - - IHHHf********1fif************************************************************

CATEGORY S-P ALL PRESSURE RETAINING COMPONENTS ITEM HUMBER B15.61 ITEM DESCRIPTION PUMP PRES~E RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAl1 DIAGRAl1. LINE EXAM RELIEF PROGRAM COMPONENT I 11548) COORD HUMBER METHOD REQUEST NOTES RC Ftt-86A A-1 2RCP1A VIS RC Ftt-86A A-6 2RCP1B VIS RC Ftt-86A L-1 2RCP1C VIS

VIRGINIA ELECTRIC AND POWER CottPANY

SURRY POWER STATION UNIT 2 **

.INSERVICE INSPECTION PLAN SlH1ARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93 PAGE 123

- ASHE SECTION XI EDITION 80W80

REVISION 0001 **

- DATE 86/10/20

CATEGORY C-A PRESSURE RETAINING WELDS IN PRESSURE VESSELS ITEM NUteER Cl.10 ITEM DESCRIPTION .PRESSURE VESSEL SHELL CIRCU"IFERENTIAL WELDS FLOW FLOW SYSTEH/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD tu'BER NETHOO REQUEST NOTES

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

CH Ftt-72A F-4 2CHE4 VOL CH Ftt-888 S-3 2CHE1 VOL CH Ftt-888 C--2 2CHE2 VOL CH Ftt-888 J-1 2CHFL2 SUR SR-004

CH CH CH Ftt-888 Ftt-888 Ftt-888 E-3 B-6 B-7 2CHFL3 2CHFL4A 2CHFL48 SUR VOL VOL I

.MS Ftt-64A' A-2 2RCE1A VOL i1s Ftt-64A A-4 2RCE1B VOL

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

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 124 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C--A PRESSURE RETAINING WELDS IN PRESSURE VESSELS ITEM NUMBER Cl.IO ITEM DESCRIPTION PRESSURE VESSEL SHELL CIRCUMFERENTIAL* WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES MS Ftt-64A 2RCEIC VOL RHR Ftt-87A 2RHEIA VOL RHR Ftt-87A 2RHE1B VOL

VIRGINIA ELECTRIC ANO POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN Sutt1ARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 125 *

ASME SECTION XI EDITION 80W80 REVISION 0001 *

DATE 86/10/20 *

- - - - ll*ll***llllll*ll*ll*llll*llll*llllllllllllll*lllllllllllllfllll*ll*llllllll*****lllOIMllllllll**llll*llllll*ll**********IIIIMIIIIN**-

CATEGORY C-A PRESSURE RETAINING WELDS IH PRESSURE VESSELS

ITEM NUMBER Cl.20 ITEM DESCRIPTION PRESSURE VESSEL HEAD CIRCU1FERENTIAL WELDS FLOW FLOW SYSTEl1/ DIAGRAM DIAGRAM LINE EXAH RELIEF PROGRAM COMPONENT ! 11548) COORD HUMBER METHOD REQUEST NOTES

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

CH J;M-72A F-4 2CHE4 VOL CH FM-888 S--3 2CHE1 VOL CH FM-888 C-2 2CHE2 VOL CH FM-8& C-2 2CHE3 VOL CH FM-88B J-1 2CHFL2 SUR SR-004 CH FM-888 E-3 2CHFL3 SUR SR-012 CH FM-888 e-6 2CHFL4A VOL CH FM-888 S-7 2CHFL4B VOL CH FM-888 H-2 2CHT1<2 VOL

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION ~"NIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 126 *

ASHE SECTION XI EDITION 80W80

REVISION 0001

DATE 86/10/20 *

- - - - IHHHf********************

CATEGORY C--A PRESSURE RETAINING WELDS IN PRESSURE VESSELS IT;M NUMBER : Cl.20 ITEM DESCRIPTION : PRESSURE* VESSEL HEAD CIRCUMFERENTIAL WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM** LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES MS Flt-64A A-2 2RCE1A VOL MS Flt-64A A-4 2RCE1B VOL MS Flt-64A A-6 2RCE1C VOL RHR Flt-87A B--2 2RHE1A VOL RHR Flt-87A 0-2 2RHE1B VOL

VIRGINIA ELECTRIC ANO POWER COMPANY *

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 127 *

ASME SECTION XI EDITION 80W80

REVISION 0001

DATE 86/1.0/20 *

CATEGORY C-A PRESSURE RETAINING WELDS IN PRESSURE VESSELS ITEM NUMBER Cl.30 ITEM DESCRIPTION PRESSURE VESSEL TUBESHEET-TO-SHELL WELD FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES CH Ftt-88C F-2 2CHE3 VOL MS Ftt-64A A-2 2RCE1A VOL MS Ftt-64A -A-4 2RCE1B VOL MS Ftt-64A A-6 2RCE1C VOL

- - - - 111111111111111111111111*111111*1111**11.1111**11111111**1111*11111111*11111111*11**********************-llllllllllllllllllll*********

VIRGINIA ELECTRIC AND POWER COHPANY

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION- PLAN sutt"IARY INTERVAL 2, 05/01/83 TO 05/01/93 128 *

PAGE

ASHE SECTION XI EDITION 80W80 REVISION 0001

DATE 86/10/20

11*1111111111111111*111111 .* llllllllllllllllllll.l(lll(.llllllllllllllllllllllllllllllll_llllllll.llll*******11*111111llllllllll.lllllllllll(l(l()ll(l(l1*ll*llll*****ifllllllll***

CATEGORY c-B PRESSURE RETAINING NOZZLE WELDS' IN VESSELS )I*

- - - - 111111111111111111111111111111111111111111111111.1111111111*111111111111111111**11************111111111111111111111111111111111111111111111111111111*11***********

ITEM NUMBER C2.21 ITEM DESCRIPTION NOZZLE-TO-SHELL(OR *HEAD) WELDS IN PRESSURE VESSELS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAJ1 RELIEF PROGRAM COMPONENT (11548) COORD IU1BER 11ETHOD REQUEST NOTES

- - - - - - - - - "!4' -------- ======= ======= ====== ------- -------

FW 'Ftt-64A A-2 2RCE1A SUR SR-007 VOL "FM Ftt-64A A-4 2RCE1B SUR SR-007 VOL FM Ftt-64A A-6 2RCE1C SUR ., SR-007 t1S t1S Ftt-64A Ftt-64A A-2 A-4 2RCE1A 2RCE1B.

VOL SUR VOL SUR SR-007 SR-007 VOL t1S Ftt-64A A-6 2RCE1C SUR SR-007 VOL

!f VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STAT~ON UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE *

REVISION 129

0001

DATE 86/10/20 *

- - - - IHf*iHf*********************************************************************

CATEGORY C-B PRESSURE RETAINING NOZZLE WELDS IN VESSELS ITEM NUMBER C2.21 ITEM DESCRIPTION NOZZLES IN PRESSURE VESSELS > l/21" NOMINAL THICKNESS FLOW FLOW SYSTEM/ DIAGRAN DIAGRAM LINE EXAN RELIEF PROGRAM COMPONENT C 11548) COOlm NUMBER METHOO REQUEST NOTES

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

RHR Ftt-87A S-2 2RHE1A SUR SR-002

.VIS SR-002 RHR Ftt-87A 0-2 2RHE1B SUR SR-002 VIS SR-002

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 130 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

- - - - if***************************************************************************

CATEGORY C-B PRESSURE RETAINING NOZZLE WELDS IN VESSELS ITEM NUNBER : C2.22 ITEM DESCRIPTION : NOZZLES IN PRESSURE VESSELS > l/2"f NOMINAL THICKNESS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES FW Ftr64A A-2 2RCE1A VOL FM Ftt-64A A-4 2RCE1B VOL FW Ftt-64.A. A-6 2RCE1C VOL MS Ftt-64A A-2 2RCE1A VOL MS Ftt-64A A-4 2RCE1B VOL MS Ftt-64A A-6 2RCE1C VOL RHR Ftt-87A B-2 2RHE1A SUR SR-002 VIS SR-002 RHR Ftt-87A D-2 2RHE1B SUR SR-002 VIS SR-002

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

VIRGINIA ELECTRIC AHO POWER COMPANY *

SURRY POWER STATION UNIT .2 *

INSERVICE INSPECTION PLAN SUMNARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 131 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES ITEM NUMBER C3. 10 ITEM DESCRIPTION PRESSURE VESSEL INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM*

COMPONENT I 11548) COORD NUMBER METHOD REQUEST NOTES

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

CH FM-886 S-3 2CHE1 SUR CH FM-886 C--2 2CHE2 SUR CH FM-886 J-1 2CHFL2 SUR CH FM-886 E-3 2CHFL3 SUR CH FM-886 S--6 2CHFL4A SUR CH FM-886 5-7 2CHFL4B SUR CH FM-886 H-2 2CHTK2 SUR RHR FM-87A S--2 2RHE1A SUR RHR FM-87A 0--2 2RHE1B SUR

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 132 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

- - - - MMMMMMM***MMMMMMM***************************************lfMMMMMMM*********************

CATEGORY C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES ITEM NUMBER : C3. 40 ITEM DESCRIPTION: PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES cc FM-72A L-3 cc1s-121 SUR cc FM-72A 0-8 CC173-151 SUR cc FM-72A E-8 cc1a1-1s1 SUR CH FM-86A F-8 CH301-1so2 SUR CH FM-888 C-8 CHS05-152 *sUR CH FM-888 E-8 SI317-152 SUR CH FM-888 F-8 SI31S-152 SUR CH FM-888 H-8 SI319-152 SUR CH FM-888 E-8 SI372-152 SUR

M*********************M********************M*M**MMIHHflHHf*lf****if******M*M*MMMIHHf*********************

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

-* INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 133 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-C INTEGRAL ATTACHMENTS_FOR VESSELS, PIPING, PUMPS, AND VALVES ITEM NUMBER : C3. 40 ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATTACHMENTS

'FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 1154~) COORD NUMBER METHOD REQUEST NOTES CH FM-88C 0-5 CH315-1502 SUR CH FM-88C lf-2 CH365-152 SUR cs FM-84A F-5 cs101-153 SUR cs FM--84.A. F-5 CS102-153 SUR cs FM-84A J-3 cs103-1s3 SUR cs FM--84.A. J-3 CSl04-153 SUR cs FM-84A J-2 CS122-153 SUR cs FM-84A J-3 cs123-1s3 SUR cs FM--84.A. S-4 CS133-153 SUR

- - - - lllllllllllllllllllllf***************************************************************************

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 134 *

PAGE

ASME SECTION XI EDITION 80W80

REVISION 0001 **

,

DATE 86/10/20. *

- - - - llllllllllllllllllllllMllllllllllll*********************************************************************

CATEGORY C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES

- - - - llllllllllllllll*******************~***********************************************

ITEM NUMBER : C3. 40 ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAlt

LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD RE~UEST NOTES

=== *===== --------

cs Ftf-84A H-4 CS134-153 SUR cs Ftf-84A L-1 CSlSS-153 SUR CV Ftf-85A I-4 CVlOS--151 SUR DA Ftf-87A L-4 DG202-152 SUR DA Ftf-87A K-4 DG237-152 SUR FW Ftf-68A 0-5 WFPD109-601 SUR FW Ftf-68A 1)-;3 WFPD113-601 SUR FW Ftf-68A 0-2 WFPD117-601 SUR MS Ftf-64A E-2 SHPlOl-601 SUR

VIRGINIA ELECTRIC ANO POWER COMPANY

- SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN SU1111ARY INTERVAL 2, 05/01/83 TO 05/01/93 ASHE SECTION XI EDITION 80W80

PAGE 135 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, ANO VALVES

- - - - If********************************************************************

ITEM NUMBER C3. 40 ITEM DESCRIPTION PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM - LINE EXAM RELIEF PROGRAM COMPONENT (115481 COORD NUMBER METHOD I REQUEST NOTES MS FM-64A E-4 SHP102-60l SUR MS FM-64A E-6 SHPl03-601 SUR MS FM-64A 0--3 SHP145-601 SUR MS FM-64A 0--5 SHP146-601 SUR MS FM-64A 0--6 SHP14r601 SUR RHR FM-87A 0--3 RHll0-602 SUR RHR FM-87A J-5 RH112-602 SUR RHR FM-87A K-4 RHllS-152 SUR RHR FM-87A L-5 RH116-1502 SUR

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/0l/9l

PAGE 136 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

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

CATEGORY C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES ITEM NUMBER C3. 40 ITEM DESCRIPTION PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RHR Ftf-87A D-'-7 RH118-602 SUR RHR Ftf-87A 1-4 RH120-152 SUR RS Ftf-848 K-2 RSl03-153. SUR RS Ftf-84B H-2 RSlll-153 SUR RS Ftf-84B A-6 RSllS-153 SUR SI Ftf-88B a-a SI170-153 SUR SI Ftf-898 C-2 SI248-1502 SUR SI Ftf-898 C-3 SI249-1502 SUR SI Ftf-898 B-3 SI279-1502 SUR

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 137

ASME SECTION XI EDITION 80W80 REVISION 0001

DATE 86/10/20 *

- - - - MMMKMMMMKMMMM***************************************************************************

CATEGORY C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES.

- - - - MMMMMMM*MMK****************************************************************************

ITEM NUMBER C3. 40 ITEM DESCRIPTION PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAtt

LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES SI Flt-898 B-2 SI344-1502 SUR SI Flt-898 A-1 SI345-1502 SUR SI Flt-898 s-2 SI353-1502 SUR

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 138 *

ASHE S~CTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C--0 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER ITEM NUMBER C4.30 ITEM DESCRIPTION PUMP BOLTS AND STUDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES CH Ftr88B 0-7 2CHP1A VOL CH FH-88B E-7 2CHP1B VOL CH FH-88B S-7 2CHP1C VOL

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 --

PAGE 139

ASME SECTION XI EDITION 80W80 , REVISION 0001

DATE 86/10/20 *

CATEGORY C---F PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER : CS.11 ITEM DESCRIPTION : PIPING CIRCUMFERENTIAL WELD<= l/2 T NOMINAL WALL FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM -J RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES

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

cs Ftt-84A J-3 cs103-1s3 SUR cs Ftt-84A J-3 CSl04-153 SUR cs Ftt-84A J-3 CS123-153 SUR cs Ftt-84A S-4 CS133-153 SUR cs Ftt-84A H-4 CS134-153 SUR cs Ftt-89A J-2 cs122-1s3 SUR MS Ftt-64A C---4 SDHV104 SUR MS Ftt-64A A-2 SHP122-601 SUR MS Ftt-64A A-4 SHPll?J-601 SUR

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 140 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING

- - - - ii***********************************************************************************

ITEM NUMBER CS.11 ITEM DESCRIPTION PIPING CIRCUMFERENTIAL WELD<= 1/2 T NOMINAL WALL FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUi'1BER METHOD REQUEST NoTrs

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

MS Flt-64A A-6 SHP124-601 SUR MS Flt-64A C-3 SHP137-601 SUR MS .Flt-64A e-4 SHP138-601 SUR MS Frt'-64A C-6 SHP139-601 SUR MS Ftf-64A 0-3 SHP145-601 SUR MS Flt-64A 0-5 SHP146-601 SUR MS Flt-64A 0-6 SHP147-601 SUR RC Flt-84B E-4 RS109-153 SUR RHR Flt-87A 0-7 RH102-602 SUR

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 141 *

ASME SECTION XI EDITION aowao .* REVISION 0001 *

DATE 86/10/20 *

- CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER C5.ll ITEM DESCRIPTION PIPING CIRClR1FERENTIAL WELD <= 1/2 T NOMINAL WALL FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM-* LINE EXAM . RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RHR FM-87A B-6 RHl04-602 SUR RHR FM-87A 0-6 RHl05-602 SUR RHR FM-87A 0-3 RH107-602 SUR RHR FM-87A B-3 RHlOS-602 SUR RHR FM-87A B-3 RH109-602 SUR RHR FM-87A 0-3 RHll0-602 SUR RHR FM-87A J-5 RH112-602 SUR RHR FM-87A I-S RH114-602 SUR RHR FM-87A 0-7 RHllS-602 SUR

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 142 *

ASME SECTION XI EDITION 80W80 REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING ITEM NUNBER : C5.ll ITEM DESCRIPTION : PIPING CIRCUMFERENTIAL WELD<= 1/2 T NOMINAL WALL FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUNBER METHOD REQUEST NOTES

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

RHR FM-87A E-4 RH119-602 SUR RHR FM-87A K-5 RH137-602 SUR RS FM-84B J-4 RSIOI-153 SUR RS FM-84B H RSI02-I53 SUR RS FM-84B K-2 RSI03-I53 SUR RS FM-84B I-2 RSI04-I53 SUR RS FM-846 E'.-4 RS109-153 SUR RS FM-84B C-3 RSll0-153 SUR RS FM-84B H-2 RSlll-153 SUR J

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SUNMARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 143 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

llATE 86/10/20 *

CATEGORY C--F PRESSURE RETAINING WELDS IN PIPING

ITEM NUMBER : C5.ll ITEM DESCRIPTION: PIPING CIRCUMFERENTIAL WELD<= 1/2 T NOMINAL WALL FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C 11548) COORD NUMBER METHOD REQUEST NOTES RS FM-84B F-2 RS112-153 SUR RS FM-84B K-1 RS120-153 SUR RS FM-84B J-1 RS121-153 SUR RS FM-84B H-1 RS122-153 SUR RS FM-846 S-1 RS123-153 SUR SI FM-89A D-6 SI216-153 SUR SI FM-89A D-6 SI292-153 SUR SI FM-89A 0-6 SI35l-153 SUR SI FM-896 C--2 SI248-1502 SUR

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE 144 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER C5.ll ITEM DESCRIPTION PIPING CIRCUMFERENTIAL WELD <= 1/2 T NOMINAL WALL FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) comm NUMBER METHOD REQUEST NOTES SI FM-898 C-3 SI249-1502 SUR

- - - - If******************

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 145 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER C5.21 ITEM DESCRIPTION. PIPING CIRCUMFERENTIAL WELD > 1/2 T NOMINAL WALL FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM ** LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES FW Ftt-68A B-5 WFPD109-601 SUR VOL FW Ftt-68A B-3 WFPD113-601 SUR VOL FW Ftt-68A B-2 WFPDllr-601 SUR VOL MS Ftt-64A A-2 SHPlOl-601 . SUR VOL MS Ftt-64A A-4 SHPlOZ-601 SUR VOL MS. Ftt-64A A-6 SHPl03-601 SUR VOL

v

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 146 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER CS.21 ITEM DESCRIPTION PIPING CIRCUMFERENTIAL WELD > 1/2 T NOMINAL WALL FLOW FLOW SYSTEM/' DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C115481 COORD NUMBER METHOD REQUEST

NOTES

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

MS Ftt-64A A-2 SHP122-601 SUR VOL MS Ftt-64A A-4 SHP123-601 SUR VOL MS Ftt-64A A-6 SHP124-60.l SUR VOL RHR Ftt-87A L-s RH116-1502 SUR VOL

. SI Ftt-89B C-2 SI24S-1502 SUR VOL SI Ftt-898 C-3 SI249-1502 SUR VOL

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

.INTERVAL 2, 05/01/83 TO 05/01/93

PAGE ' 147 *

ASME SECTION XI EDITION 80W80

REVISION 0001

. .

DATE 86/10/20 .*

- - - - It*********************

CATEGORY C-F PRESSURE RETAINING '.~ELDS IN PIPING

ITEM NUMBER .. CS.21 ITEM DESCRIPTION : PIPING CIRCUMFERENTIAL WELD > 1/2 T NOMINAL WALL FLOW FLOW SYSTEM/ PIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES SI Fl't-898 A-1 SI34S-1502 SUR VOL SI Fl't-89A A-4 SI352-1502 SUR V.OL SI Fl't-898 C-3 SI250-1502 SUR VOL SI Fl't-898 B-2 SI344-1502 SUR VOL SI Fl't-898 B-2 SI353-1502 SUR VOL

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION _UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 148 *

ASME SECTION XI EDITION 80W80

REVISION 0001 **

DATE 86/10/20 *

- - - - M********************************************************************************

CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER : cs.22 ITEM DESCRIPTION : PIPING LONGITUDINAL WELD > 1/2 T NOMINAL WALL TH FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C 11548) cornm NUMBER METHOD REQUEST NOTES MS Ftt-64A A-2 SHPlOl-601 SUR VOL HS Ftt-64A A-4 SHP102-601 SUR VOL MS Ftt-64A A-6 SHP103-601 SUR VOL MS Ftt-64A. A-2 SHP122-601 SUR VOL HS Ftt-64A A-4 SHP123-601 SUR VOL MS Ftt-64A A-6 SHP124-601 SUR VOL

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

ASME SECTION XI EDITION 80W80

PAGE 149 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C--F PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER CS.31 ITEM DESCRIPTION PIPING CIRCUMFERENTIAL WELD, PIPE BRANCH CONNECTION FLOW FLOW SYSTEM/ DIAGRAM .DIAGRAM LINE EXAr:t RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

-------- ------- *======= ------ ------- -------

MS Ftt-64A A-2 SHP122-601 SUR MS FM-64A A-4 SHP123-601 SUR MS Ftt-64A A-6. SHP124-601 SUR MS FM-64A C--2 SHP137-601 SUR MS Ftt-64A 5-4 SHP138-601 SUR MS Ftt-64A C--6 SHP139-601 SUR MS FM-64A 0-3 SHP14S-601 SUR MS Ftt-64A 0-5 SHP146-601 SUR MS Ftt-64A 0-6 SHP147-601 SUR

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2

.INSERVICE INSPECTION ,PLAN

SUMMARY

-INTERVAL 2, 05/01/83 TO 05/01/93 ASHE SECTION XI EDITION 80W80

- PAGE 150 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM*NUMBER C7.10 ITEM DESCRIPTION PRESSURE VESSEL PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW

. SYSTEM/ DIAGRAM DIAGRAtf LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES CH FM-72A F-4 2CHE4 VIS CH FM-888 S-3 2CHE1 VIS CH FM-888 C-2 2CHE2 VIS CH FM-888 lt-2 2CHTK2 VIS MS FM-64A A-2 2RCE1A VIS MS FM-64A A-4 2RCE1B VIS MS FM-64A *A-6 2RCE1C ~ VIS RHR FM-87A e-2 2RHE1A VIS RHR FM-87A 0-2 2RHE1B VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 151 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

- - - - If***************************************************************************

ITEM NUMBER C7.ll ITEM DESCRIPTION PRESSURE VESSEL PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES CH Ftt-72A F-4 2CHE4 VIS CH Ftt-88B S--3 2CHE1 VIS CH Ftt-88B C-2 2CHE2 VIS CH Ftt-88B .H-2 2CHTK2 VIS

MS MS MS Ftt-64A FM-64A

. Ftt-64A A-2 A-4 A-6 2RCE1A 2RCE1B 2RCE1C VIS VIS VIS RHR Ftt-87A s-2 2RHE1A VIS RHR

Ftt-87A 0-2. 2RHE1B VIS

VIRGINIA ELECTRIC ANO POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 152 *

ASHE SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20. *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES CH FM-88A C-3 CH32s-1s2 VIS CH FM-88A F-4 CH329-152 VIS CH FM-888 S-1 CH194-152 VIS CH FM-88B F-6 CH302-1503 VIS CH FM-88B S-6 CHJOJ-1503 VIS CH FM-888 H-3 CH306-602 VIS CH FM-888 S-2 CH30r602 VIS CH FM-888' A-3 CH30S-1503 VIS CH FM-888 A-6 CHJll-1503 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/0l/83 TO 05/01/93

PAGE 153 *

ASME SECTION XI- EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C--H ALL. PRESSURE RETAINING COMPONENTS

ITEM NUMBER C7.20 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW /

SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES

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

CH FM-88B A-7 CH312-1503 VIS CH FM-888 A-7 CH313-1503 VIS CH FM-88B H-4 CH317-152 VIS CH FM-88B G-8 CH318-152 VIS CH FM-88B 1-7 CH319-152 VIS CH FM-888 F-6 CH321-1503 VIS CH FM-88B G-6 CH322-1503 VIS CH FM-888 G-2 CH323-152 VIS CH FM-88B H-2 CH324-152 VIS

VIRGIN!.~ ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 154 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C--H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER C7.20 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES CH Fl1-88B I-3 CH35S-152 VIS CH FH-888 1-3 CH359-152 VIS CH FH-888 G-2 CH367-152 VIS CH FH-888 C--6 CH369-1503 VIS CH FH-888 E-6 CH370-1503 CH

FH-888 G-6 CH371-1503 VIS CH FH-88B E-a CH372-152 VIS CH FH-888 H-3 CH373-152 VIS CH FH-888 S-6 CH374-1503 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 155 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

- - - - x*************************************************************

ITEM NUMBER : C7.20 ITEM DESCRIPTION: PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRArt LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES CH Ftt-888 S-6 CH375-152 VIS CH Ftt-888 B-6 CH376-1503 VIS CH Ftt-88B A-6 CH37rl503 VIS CH Ftt-88B A-4 CH379-1503 VIS CH Ftt-888 a-5 CH380-1503 VIS CH Ftt-888 0--6 CH381-1503 VIS CH Ftt-888 H-1 CH38rl52 VIS CH Ftt-888 C-4 CH389-1503 VIS CH Ftt-88B S-6 CH390-l503 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

.* SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 156 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES CH Ftt-886 A-6 CH391-1503 VIS CH Ftt-886 A-3 CH399-152 VIS CH Ftt-886 F-3 CH400-152 v~s CH Ftt-886 H-3 CH412-152 VIS CH Ftt-886 E-4 CH413-1503 VIS CH Ftt-886 0-6 CH414-1503 VIS CH Ftt-886 F-3 CH41?-152 VIS CH Ftt-886 S-3 CH41S-152 VIS CH Ftt-886 1-1 CH419-152 VIS

I

- - - - If*******************************

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER.STATION UNIT 2 IHSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

- - if*MMMMMMM********

PAGE 157 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM HUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (115481 COORD HUMBER METHOD REQUEST NOTES CH Ftt-88B H-2 CH420-152 VIS CH Ftt-88B J-1 CH421-152 VIS CH Ftt-88B 0--1 CH42S-602 VIS CH Ftt-88B 8-2. CH463-152 VIS CH Ftt-888 J-3 CH464-152 VIS CH Ftt-888 H-3 CH465-152 VIS CH Ftt-88B 8-7 CH487-1503 VIS CH Ftt-888 f-7 CH488-1503 VIS CH Ftt-88B 0--7 CH489-1503 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 158 *

ASHE SECTION XI EDITION 80W80

REVISION 0001 *

'*

DATE 86/10/20 *

CATEGORY C-H ALL .PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM Lil:IE EXAM RElIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES CH Ftt-88B F-4 CH491-152 VIS CH Ftt-8§8 0-3 CH492-152 VIS CH Ftt-888 J-1 CH493-152 VIS CH Ftt-888 S-1 CH494-152 VIS CH Ftt-88B S-2 CH499-152 VIS CH Ftt-88B H-7 CHSOl-152 VIS.

CH Ftt-888 S-7 CH502-152 VIS CH Ftt-88B E-7 CH503-152 VIS CH Ftt-888 e-s CH504-152 VIS

VIRGINIA ELECTRIC ANO POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN SU11MARY INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

- - - - M*********

PAGE 159 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS *

- - - - M*************************************************************~**************

ITEM NUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES CH FM-88B C-8 CHSOS-152 VIS CH FM-88B C-8 CHS06-152 VIS CH FM-886 0-8 CH507-1503 VIS CH FM-88B F-8 CHSOS-1503 VIS CH FM-886 lf-8 CH509-1503 VIS CH FM-886 1-4 CH512-152 VIS CH FM-886 C-7 CH524-1503 VIS CH FM-886 E-7 CH52S-1503 VIS CH FM-886 S-7 CH526-1503 VIS

if VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER *sTATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE 160 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNtJARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/

, DIAGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES

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

CH FM-88B A-4 CH531-1503 VIS CH FM-88B F-2 CH536-152 VIS CH FM-88B 1-1 CH53?-152 VIS CH FM-88B S-3 CH538-152 VIS CH FM-88B E-1 CH539-152 VIS CH FM-88B J-1 2CHFL2 VIS CH FM-88B E-3 2CHFL3 VIS CH FM-88B e-6 2CHFL4A VIS CH FM-888 B-7 2CHFL4B VIS

- - - - IHHHf***************************************************************************

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 161 *

ASHE SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

- - - - ii***************************************************************************************

CATEGORY C-H ALL PRESSURE.RETAINING COMPONENTS ITEM NUMBER C7.20 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE .EXAM RELIEF PROGRAM COMPONENT (11548) comm NUMBER METHOD REQUEST NOTES CH FM-88C E-2 CH305-1502 VIS CH FM-88C I-2 CH306-602 VIS CH FM-88C E-6 -CH31s-1so2 VIS CH FM-88C H-6 CH316-1502 VIS

' CH FM-88C F-2 CH382-1502 VIS CH FM-88C H-3 CH383-602 VIS CH FM-88C S-1 CH384-1502 VIS CH FM-88C ~3 CH385-602 VIS CH FM-88C H-2 CH386-602 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE

REVISION 162

0001

DATE 86/10/20 *

CATEGORY C--H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER C7.20 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES

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

CH Ftt-88C H-8 CH392-1503 VIS CH Ftt-88C E-8 CH394-1503 VIS CH Ftt-88C B-8 CH396-1503 VIS CH Ftt-88C B-5 CH39S-1502 VIS CH Ftt-88C G-4 CH399-152 VIS CH Ftt-88C E-5 CH40l-1502 VIS CH Ftt-88C H-5 CH402-1502 VIS CH Ftt-88C C---5 CH403-1502 VIS CH Ftt-88C I-4 CH422-152 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SUNNARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 163 *

ASHE SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF -PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

CH FH-88C B-4 CH424-152 VIS CH FH-88C C--4 CH514-152 VIS CH FH-88C C--5 CH515-152 VIS CH FH-88C S-5 CH516-152 VIS CH Ftt-88C C--5 CHSl?-152 VIS CH. FM-88C S-5 CH518-152 VIS CH FM-88C 1-4 CH519-152 VIS CH FM-88C H-2 CH532-602 VIS CH FM-88C 1-3 CH533-602 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *"

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 164 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER C7.20 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM-COMPONENT (11548) comm NUMBER METHOD REQUEST NOTES cs Ftt-84A f-S cs101-153 VIS cs Ftt-84A f-5 CS102'-153 VIS cs Ftt-84A J-3 CS103-153 VIS cs Ftt-84A J-3 CSl04-153 VIS cs Ftt-84A C-2 CS114-152 VIS cs Ftt-84A J-2 CS122'-153 VIS cs Ftt-84A J-3 cs123-153 VIS cs Ftt-84A C-2 CS124-ICN1 VIS cs Ftt-84A G-4 CS133-153 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 165 *

ASHE SECTION XI EDITION 80W80 REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM ~ER C7.20 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGR.&,M DIAGRAM .. LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES cs FM-84A H-4 CS134-153 VIS cs FM-84A S-4 cs135-153 VIS CS' FM-84A H-4 CSI36-I53 VIS cs FM-84A S-2 cs114-153 VIS cs FM-84A S-2 cs115-153 VIS FW FM-68A s-5 WFP0109-601 VIS FW FM-68.A s-4 WF:,0113-601 VIS FW FM-68A S-2 WFPDll 7-601 VIS MS FM-64A s-3 SAEl05-121 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93*

PAGE 166 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

-------- .;::==== ------- ------ ------- =======

MS FM-64A C-3 SDHVlOl-601 VIS l1S FM-:~4A C-4 SDHVlOZ-601 VIS l1S FM-64A C-6 SOHVl03-601 VIS l1S FM-64A C-3 SDHVl04-601 VIS l1S FM-64A A-2 SHPlOl-601 VIS MS FM-64A A-4 SHPlOZ-601 VIS l1S FM-64A A-6 SHPl03-601 VIS l1S FM-64A B-3_,, SHP12Z-601 VIS MS FM-64A B-4 SHP123-601 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 '*

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2,' 05/01/83 TO 05/01/93

PAGE 167 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

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

ITEM NUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAl'f. LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES MS FM-64A S--6 SHP124-601 VIS MS FM-64A C-8 SHP12S-601 VIS MS FM-64A C-8 SHP129-601 VIS MS FM-64A C-8 SHP130-601 VIS MS FM-64A F-8 SHP131-601 VIS MS FM-64A S--7 SHP132-601 VIS MS FM-64A C-8 SHP13S-601 VIS MS FM-64A C-2 SHP13r601 VIS MS FM-64.t. 5-4 SHP138-601 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 if

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 168 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL.PRESSURE RETAINING COMPONENTS ITEM NUMBER C7.20 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM RELIEF PROGRAM COMPONENT ( 11546) COORD NUMBER METHOD REQUEST NOTES MS Ftt-64A C-6 SHP13Cr601 VIS MS Ftt-64A 0-2 SHP145-601 VIS MS ~Ftt-64A 0-4 SHP146-601 VIS MS Ftt-64A C-6 SHP147-60l VIS MS Ftt-64A 9-3 SSVlOl-121 VIS HS Ftt-64A 9-3 SSV102-12l VIS MS Ftt-64A C-3 SSVli>3-12l VIS MS Ftt-64A C-3 ssv104-121 VIS MS Ftt-64A B-4 SSVl06-12l VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 169 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES

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

MS Ftt-64A B-4 SSV107-121 VIS MS Ftt-64A C-4 ssv1oe-121 VIS MS Ftt-64A C-4 SSV109-121 VIS Ftt-64:A. 5-4 SSVll0-121 VIS MS MS Ftt-64A S-6 SSVIll-121 VIS MS Ftt-64A C-6 SSV112-121 VIS MS Ftt-64A C-6 ssv114-121 VIS MS Ftt-64A S-6 ssvus-121 VIS RHR Ftt-87A E-7 RH102-602 VIS

VIRGINIA ELECTRIC AND. POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASHE SECTION XI EDITION 80W80

PAGE 170 *"

REVISION 0001 *

DATE 86/10/20 *

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

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

- - - - lHf**********************************************************

ITEM NUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RHR FM-87A G-3 RHl03-602 VIS RHR FM-87A B-6 RHl04-602 VIS RHR FM-87A C-6 RHl05-602 VIS RHR FM-87A A-4 RHl06-602 VIS RHR FM-87A C-4 RH10r602 VIS--

RHR FM-87A A-3 RHlOS-602 VIS RHR FM-87A B-3 RH109-602 VIS RHR Ftt-87A 0-3 RHll0--602 VIS RHR Ftt-87A F-6 RHlll-602 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASHE SECTION XI EDITION 80W80

PAGE 171 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS "*

ITEM HUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD HUMBER METHOD REQUEST NOTES RHR Flr87A E-5 RH112-602 VIS RHR Flr87A H-4 RH113-602 VIS RHR Flr87A 1-5 RH114-602 VIS

--* RHR RHR RHR Flr87A Flr87A' Flr87A K-5 E-7 E-4 RH116-602 RHllS-602 RH119-602 VIS VIS VIS RHR Flr87A B-5 RH121-602 VIS RHR Flr87A 1-5 RH122-602 VIS RHR Flr87A K-5 RH13r602 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POl~ER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 172 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER C7.20 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

-------- ------- =======* ------ ------- -------

RHR Ftt-87A C-6 RHlS0-602 VIS RS Ftt-848 J-4 RSlOl-153 VIS RS Ftt-848 H-4 RSlOZ-153 VIS RS . Ftt-848 K-2 RSl03-153 VIS RS Ftt-84B I-2 RS104:--153 VIS RS Ftt-848 E-8 RS107-153 VIS RS Ftt-848 E-8 RSl08-153 VIS RS Ftt-848 E-4 RS109-153 VIS RS Ftt-848 C-3 RSll0-153 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASHE SECTION XI EDITION 80W80

PAGE

REVISION 173

0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES.

RS FM-84B H-2 RSlll-153 VIS

~s FM-848 F-2 RS112-153 VIS RS FM-84B 0-6 RS114-153 VIS RS FM-84B K~l RS120-153 VIS RS FM-84B J-1 RS121-153 VIS RS FM-84B H-1 RS122-153 VIS RS FM-84B S--1 RS123-153 VIS RS FM-848 E-a RSi24-153 VIS SI FM-898 S--8 sI201-1s3 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SU1111ARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 174 *

ASHE SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

.* CATEGORY C--H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES

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

SI 0 Ftt-89B S-8 SI202-153 VIS SI Ftt-89A H-8 SI205-153 VIS SI Ftt-89A F-4 SI20rl52 VIS SI Ftt-89A S-5 SI213-153 VIS SI Ftt-89A S-5 SI214-153 VIS SI Ftt-89A 0-6 SI216-153 VIS SI Ftt-89A E-6 SI2lrl52 VIS SI Ftt-89A E-6 SI21S-152 VIS SI Ftt-89A E-6 SI219-152 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI.EDITION 80W80

PAGE' 175 *

REVISION 0001 *

' * 'DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

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

ITEM NUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES SI FM-89A F-2 SI220-1503 VIS SI Ftt-'-89A H-7 SI223-152 VIS SI FM-89A F-6 SI224-153 VIS SI FM-89A E-6 SI225-152 VIS SI FM-89A H-5 SI230-152 VIS SI FM-898 C-2 SI248-1502. VIS SI FM-898 C-3 SI249-1502 VIS SI FM-89A E-6 SI255-153 VIS SI FM-89A F-7 SI256-153 VIS

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

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 176 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES SI Ftt-89A H-2 SI257-1503 VIS SI Ftt-89A H-2 ,SI25~1503 . VIS SI Ftt-89A H-1 SI259-1503 VIS SI Ftt-89A E-1 SI26S-1503 VIS SI Ftt-89A A-2 SI272-1503 VIS SI Ftt-89A E-6 SI278-152 VIS SI Ftt-89A G-7 SI283-153 VIS SI Ftt-89A 0-8 SI284-152 VIS SI Ftt-89A e-2 SI290-1503 VIS I

I r

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 '*

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 177 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20* *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER C7.20 ITEM DESCRIPTION PIPIN1:i PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES SI FM-89A 0-6 SI292-153 VIS SI FM-89A F-2 SI293-1503 VIS SI FM-89A F-4 SI302-:152 VIS SI FM-89A 0-6 SI306-152 VIS SI FM-89A I-6 SI330-152 VIS SI FM-8.9A J-4 SI331-152 VIS SI FM-89A C-7 51332-153 VIS SI FM-89A _C-8 SI333-ICN9 VIS SI FM-89A E-7 SI334-ICN9 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 178 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

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

CATEGORY C-H ALL:PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES SI FM-89A 0-8 SI335-ICN9 VIS SI FM-89A E-7 SI336-ICN9 VIS SI FM-89A F-7 SI337-153 VIS SI FM-89A F-8 SI33S-ICN9 VIS SI FM-89A H-7 SI339-ICN9 VIS SI FM-89A H-8 SI340-ICN9 VIS SI FM-89A H-7 SI341-ICN9 VIS SI FM-89A S-2 SI347-1503 VIS SI FM-89A E-5 SI34a-153 VIS

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 179 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM ** LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES SI Ftf-89A E-5 SI349-153 VIS SI Ftt-89A 0-5. SI350-153 VIS SI Ftt-89A 0-6 SI351-153 VIS SI Ftf-89A A-ct SI35Z-1502 VIS SI Ftt-89A 0-6 SI360-153 VIS SI Ftt-89A C---2 SI361-1503 VIS SI Ftt-89A 0-8 SI36Z-153 VIS SI Ftt-89A F-8 SI363-153 VIS SI Ftt-898 S-7 sI234-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93.

PAGE .180 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C--H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW

'SYSTEM/ DIAGRAM DIAGRAM 'LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES SI Ftt-898 0-5 SI236-602 VIS SI Ftt-898 e-s SI24S-1502 VIS SI Ftt-898 F-6. SI246-1502 VIS SI Ftt-898 C--3 SI250-1502 VIS SI Ftt-89B e-s SI263-602 VIS SI Ftt-898 i S--6 SI26S-602 VIS SI Ftt-89B 1-1 SI270-1503 VIS SI Ftt-898 E-1 SI271-1503 VIS SI Ftt-89B e-1 SI274-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 181 *

ASHE SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING Bot,JNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LiNE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

SI Ftf-898 e-2 SI275-1502 VIS SI Ftf-898 E-1 SI276-1503 VIS SI Ftf-89B e-1 SI285-1502 VIS SI Ftf-89B S-5 SI297-602 VIS SI Ftt-89B 0-4 SI300-602 VIS SI Ftf-898 1-3 ~I343;-1502 VIS SI Ftf-898 e-1 SI344-1502 VIS SI Ftf-898 A-1 SI345-1502 VIS SI Ftf-898 1-1 SI346-1503 VIS

VIRGINIA ELECTRIC ANO POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 182 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS frEM NUNBER C7.20 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES SI Ftt-898 B-2 5!353-1502 VIS SI Ftt-89B 0-1 SI354-1502 VIS SI Ftt-898 C-3 SI355-1502 VIS SI Ftt-89B 0-1

SI356-1502 VIS SI Ftt-898 C-2 SI357-1502 VIS SI Ftt-89B 0-2 5!358-1502 VIS SI FM-898 C-4 SI359-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 183 *

ASHE SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES CH FM-88A C-3 CH325-152 VIS CH FM-88A F-4 . CH329-152 VIS CH FM-888 S-1 CH194-152 VIS CH FM-888 F-6 CHJOZ-1503 VIS CH FM-888 S-6 CH303-1503 VIS CH FM-888 H-3 CH306-602 VIS CH FM-888 B-2 CH307-602 VIS CH FM-888 A-3 CH30S-1503 VIS CH FM-888 A-6 CH311-1503 VIS

VIRGINIA ELECTRIC ANO POWER COMPANY *

SU!(RY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 184 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY. C-H ALL PRESSURE RETAINING COMPONENTS

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

ITEM NUMBER : C7.21 ITEM.DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES CH FM-888 A-7 CH312-1503 VIS CH FM-888 A-7 CH313-1503 VIS CH FM-888 H-4 CH317-152 VIS CH FM-888 S-8 CH318-152 VIS CH FM-888 1-7 CH319-152 VIS CH FM-888 F-6 CH321-I503 VIS CH FM-888 S-6 CH322-1503 VIS CH FM-888 S-2 CH323-152 VIS CH FM-888 H-2 CH324'-152 VIS

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 185 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C--H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE*

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT l 11548) COORD NUMBER METHOD REQUEST NOTES CH FM-88B I-3 CH3SS-152 VIS CH FM-88B I-3 CH359-152 VIS CH FM-88B S---2 CH36.rl52 VIS CH FM-88B C---6 CH369-1503 VIS CH FM-88B E-6 CH370-1503 VIS CH FM-88B S---6 CH371-;-1503 VIS CH FM-88B E-8 CH372-152 VIS CH FM-886 H-3 CH373-152 VIS CH FM-886 S-6 CH374-1503 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE 186

REVISION 0001

lf

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

- - - - lHHI'.************************************************************************************

ITEM NUMBER C7.21 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES CH Ftt-88B B-6 CH375-152 VIS CH Ftt-88B B-6 CH376-1503 VIS CH Ftt-88B A-6 CH377-1503 VIS CH Ftt-88B A-4 CH379-1503 VIS CH Ftt-888 B-5 CH380-1503 VIS CH Ftt-88B 0-6 CH381-1503 VIS CH Ftt-88B H-1 CH387-152 VIS CH Ftt-88B C--4 CH389-1503 VIS CH Ftt-88B B-6 CH390-1503 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN SUNMARY INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE

REVISION 187

0001

DATE 86/10/20 *

- - - - ~**********************************************************"

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS **

(

ITEM NUMBER : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES CH Ftt-886 A-6 CH391-1503 VIS CH Ftt-88B A-3 CH399-152 VIS CH Ftt-888 F-3 CH400-152 VIS CH Ftt-888 H-3 CH412-152 VIS CH Ftt-88B E-4 CH413-1503 VIS CH Ftt-888 0-6 CH414-1503 VIS CH Ftt-888 F-3 CH417-152 VIS CH Ftt-888 S-3 CH41S-152 VIS CH Ftt-88B I-1 CH419-152 VIS

VIRGINIA ELECTRIC AND POWER.COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SUMHARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 188 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER : C7.21 ITEM DESCRIPTION: PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

*=======

CH Ftt-88B H-2 CH420-152 VIS CH Ftt-88B J-1 CH421-152 VIS CH Ftt-888 0-1 CH425-602 VIS CH Ftt-88B 6-2. CH463-152 VIS CH Ftt-88B J-3 CH464-152 VIS CH Ftt-88B H-3 CH465-152 VIS CH Ftt-88B 6-7 CH487-1503 VIS CH Ftt-88B F-7 CH488-1503 VIS CH .Ftt-88B 0-7 CH489-1503 VIS

VIRGINIA ELECTRIC ANO POWER COMPANY *

SURRY POWER STATION UNIT 2 - *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 189 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER C7.21 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM .. LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES CH FM-888 F-4 CH4_91-152 VIS CH FM-888 0-3 CH492-152 VIS CH FM-MB J-1 CH493-152 VIS CH FM-88B S--1 CH494-152 VIS CH FM-8813 'S--2 CH499-l52 VIS CH FM-88B lf-7 CH50l-152. VIS CH FM-888 S--7 CH502-152 VIS CH FM-888 E-7 CH503-152 VIS CH FM-88B S--8 CH504-152 VIS

VIRGINIA ELECTRIC AHO POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 190 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ,*

ITEM NUMBER : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUNBER METHOD REQUEST NOTES CH FM-88B C-8 CH505-152 VIS CH FM-888 C-8 CH506-152 VIS CH FM-88B 0-8 CH507-1503 VIS CH FM-88B F-8 CH508-1503 VIS CH FM-88B H-8 CH509-1503 VIS CH FM-888 1-4 CH512-152 VIS CH FM-886 C-7 CH524-1503 VIS CH FM-88B E-7 CH525-l503 VIS ----

CH FM-88B S---7 CH526-l503 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/0i/93 ASHE SECTION XI EDITION 80W80

PAGE

REVISION 191

0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUMBER ,METHOD REQUEST NOTES CH Ftt-888 A-4 CH53l-1503 VIS CH Ftt-888 F-2 CHS36-152 VIS CH Ftt-888 1-1 CHS3rl52 VIS CH Ftt-888 S--3 CHSJa-152 VIS CH Ftt-888 E-1 CHS39-l52 VIS CH .Ftt-888 J-1 2CHFL2 VIS CH Ftt-888 E-3 2CHFL3 VIS CH Ftt-888 S--6 2CHFL4A VIS CH Ftt-888 a-1 2CHFL4B VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATIQN UNIT 2 INSERVICE INSPECTION PLAN SUNMARY INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE.

REVISION 192

0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES CH FM-88C E-2 CH305-1502 VIS CH FM-88C 1-2 CH306-602 VIS CH FM-88C E-6 CH315-1502 VIS CH FM-88C H-6 CH316-1502 VIS CH FM-88C F-2 CH382-1502 VIS CH FM-88C H-3 CH383-602 VIS CH FM-88C S-1 CH384-1502 VIS CH FM-88C H-3 CH385-602 VIS CH FM-88C H-2 CH386-602 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SUNNARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 193 *

ASHE SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

.* CATEGORY C-H All PRESSURE RETAINING COMPONENTS

- - - - KKKKKKKKK*****************************************************************************

ITEM NUMBER : C7.21 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER' METHOD REQUEST NOTES CH Ftt-88C H-8 CH392-1503 VIS CH FH-88C *E-8 CH394-1503 VIS CH FH-88C S--8 CH396-1503 VIS CH Ftt-88C S--5 CH39S-1502 VIS CH FH-88C S-4 CH399-152 VIS CH Ftt-88C E-S CH40l-1502 VIS CH FH-88C H-S CH402-1502 VIS CH FH-88C c-s CH403-1502 VIS CH FH-88C 1-4 CH422-152 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY INSERVICE ASME POWER SECTION XI STATION INSPECTION PLAN EDITION UNIT 2 SUNMARY INTERVAL 2, 05/01/83 TO 05/01/93 80W80

PAGE

REVISION

194

0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER : C7.2l ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES CH Frt-BaC 9-4 CH424-152 VIS CH Frt-BaC C-4 CH514-152 VIS CH FH-88C C-5 CHSlS-152 VIS CH Frt-aac S---5 CH516-152 VIS CH Frt-BaC C-5 CH51rl52 VIS CH FH-88C S---5 CHSlS-:-152 VIS CH Frt-aac 1-4 CH519-152 VIS CH Frt-88C H-2 CH532-602 VIS CH FH-88C I-3 CH533-602 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 195 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER C7.21 I

ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

cs Flt-84A f-5 cs101-153 VIS cs Flt-84A f-5 cs102-153 VIS cs Flt-84A J-3 CSl03-153 VIS cs Flt-84A J-3 CSl04-153 VIS cs Flt-84A C-2 CS114-152 VIS cs Flt-84A J-2 CS122-153 VIS cs Flt-84A J-3 cs123-153 VIS cs Flt-84A C-2 CS124-ICN1 VIS cs Flt-84A S--4 CS133-153 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SlJl1MARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 196 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUNBER : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW r-SYSTEM/ DIAGRAM DIAGRAM- LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUNBER METHOD REQUEST NOTES cs Ftt-84A H-4 cs134-153 VIS cs Ftt-84A S-4 CS135-153 VIS cs - Ftt-84A H-4 CS136-153 VIS cs Ftt-84A S-2 CS174-153 VIS cs Ftt-84A S-2 CS175-153 VIS FW Ftt-68A S-5 WFPD109-601 VIS FW Ftt-68A 5-4 WFPD113-601 VIS FW Ftt-68A S-2 WFPDll'?-601 VIS MS Ftt-64A S-3 SAE105-121 VIS

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 197 *

PAGE

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

- - - - MKMMMMM***********************

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

- - - - MMMMMMMMMMMMMMMMM********************************MMMMMlf********************************

ITEM NUMBER : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES

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

MS Ftt-64A C-3 SDHVlOl-601 VIS MS Ftt-64A C-4 SDHV102-601 VIS MS Ftt-64A C-6 S0HV103-60l VIS MS Ftt-64A C-3 S0HV104-60l VIS MS Ftt-64A A-2 SHPlOl-601 VIS MS Ftt-64A A-4 SHPl02-601 VIS MS Ftt-64A A-6 SHPlOJ-601 VIS MS Ftt-64A B-3 SHP122-601 VIS MS ,Ftt-64A B-4 SHP123-601 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 198 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER C7.21 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES MS Ftt-64A B-6 SHP124-601 VIS MS Ftt-64A C-8 SHP128-60l VIS MS Ftt-64A C-8 SHP12~601 VIS MS FM-64A C-8 SHP130-601 VIS MS Ftt-64A F-8 SHP131-601 VIS MS Ftt-64A e-1 SHP13Z-601 VIS HS FM-64A C-8* SHP135-601 VIS HS Ftt-64A C-2 SHP137-601 VIS MS Ftt-64A B-4 SHP13S-601 VIS

- - - - KKKKKKK********************************************************************************

VIRGINIA ELECTRIC ANO POWER COMPANY

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PASE 199 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20

CATEGORY c--H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAtf - LINE EXAM RELIEF PROGRAM COMPONENT I 11548) COORD NUMBER METHOD REQUEST NOTES

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

MS FM-64.l C-6 SHP139-601 VIS MS FM-64A 0-2 SHP145-601 VIS MS FM-64A D-4 SHP146-601 VIS MS FM-64.l C-6 SHP147-601 -VIS MS FM-64A B-3 SSVlOl-121 VIS MS FM-64A B-3 SSV102-121 VIS MS FM-64A C-3 SSVlOJ-121 VIS MS FM-64A C-3 ssv104-121 VIS MS FM-64A B-4 SSVl06-121 VIS

VIRGINIA ELECTRIC ANO POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 200 *

ASHE SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C--H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.2l ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES MS Ftt-64A B-4 SSVlOr-121 VIS MS Ftt-64A C--4 SSVlOS-121 VIS MS Ftt-64A C--4 SSV109-121 VIS MS Ftt-64A a-4 SSVll0-121 VIS MS Ftt-64A a-6 ssvin-121 VIS MS Ftt-64A C--6 SSVllZ-121 VIS MS Ftt-64A C--6 ssv114-121 VIS MS Ftt-64A a-6 ssv115-121 VIS RHR Ftt-87A E-7 RHlOZ-602 VIS

VIRGINIA ELECTRIC ANO POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 201

ASME SECTION XI EDITION 80W80

REVISION 0001 *

*. DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE*

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM" LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES RHR Ftf-87A S--3 RHl03-602 VIS RHR Ftf-87A e-6 RHl04-602 VIS RHR Ftf-87.A C-6 RHlOS-602 VIS RHR

Ftf-87.A A-4 RHl06-602 VIS RHR Ftf-87A C-4 RH107-602 VIS RHR Ftf-87A ,A-3 RHlOS-602 VIS RHR Ftf-87A S-3 RH109-602 VIS RHR Ftf-87A 0-3 RHll0-602 VIS RHR Ftf-87A F-6 RHlll-602 VIS

- - - - ifi<<MMMMMMMMMMMMMMM************************************************************************

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 202 *

ASHE SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

- - - - MMMMMMMM*****************************************************MMMMMMMMMM*******************

_* CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER C7.21 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES RHR Ftt-87A E-5 RH112-602 VIS RHR ftt-87A H-4 RH113-6Q.2 VIS RHR Ftt-87A 1-5 RH114-602 VIS RHR Ftt-87A K-s RH116-602 VIS RHR Ftt-87A '

E-7 RHllS-602 VIS RHR Ftt-87A E-4 RH119-602 VIS RHR Ftt-87A S-5 RH121-602 VIS RHR Ftt-87A 1-s RH122-602 VIS RHR Ftt-87A K-5 RH137-602 VIS

VIRGINIA ELECTRIC AHO POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 * *PAGE 203 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOO REQUEST NOTES RHR FM-87A C-6 RHlS0-602 VIS RS FM-84B J-4 RSlOl-153 VIS RS FM-84B H-4 RS102'-153 VIS RS FM-84B K-2 RS103-153 VIS RS FM-84B I-2 RS104-153 VIS RS FM-84B E-8 RS107-153 VIS RS FM-84B E-c8 RSlOS-153 VIS RS FM-84B E-4 RS109-153 VIS RS FM-84B C-3 *.RSll0-153 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION. UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 204 *

ASME SECTION XI EDITION 80W80

REVISION* 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW* FLOW SYSTEM/ DIAGRAM DIAGRAlt - LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RS Ftt-84B H-2 RSlll-153 VIS RS Ftt-848 f-2 RS112-153 VIS RS Ftt-84B 0-6 RS114-153 VIS RS Ftt-84B K-1 RS120-153 VIS ..

RS Ftt-848 J-1 RS121-153 VIS RS Ftt-84B H-1 RS122-153 VIS 1 RS Ftt-84B S-1 RS123-153 VIS RS Ftt-848 E-8 RS124-153 VIS

' SI Ftt-898 S-8 sI201-1s3 VIS

- - - - lflflflflflflflfiHHHHUHHHllflflflflflflflfM*************lflflf***iflflflflf<<KKMlflfMKlflflf*lflfKKKlfKKMlflf**************

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2

- INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 * .PAGE 205 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H All PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES SI Ftt-896 S-8 sI202-1s3 VIS SI Ftt-89A H-8 SI205-l53 VIS SI Ftt-89A F-4 SI207-152 VIS SI Ftt-89A S-5 sI213-1s3 VIS SI Ftt-89A S-5 sI214-153 VIS*

SI Ftt-89A 6 SI216-153 VIS SI Ftt-89A E-6 SI217-152 VIS SI Ftt-89A E-6 SI21S--152 VIS SI Ftt-89A E-6 SI219-152 VIS

VIRGINIA ELECTRIC AND POWER -COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 206 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

SI Ftt-89A F-2 SI220-1503 VIS SI Ftt-89A H-7 SI223-152 VIS SI Ftt-89A F-6 SI224-153 VIS SI Ftt-89A E-6 SI225-152 VIS SI Ftt-89A H-5 SI230-152 VIS SI Ftt-898 C-2 SI248-1502 VIS SI Ftt-898 C-3 SI249-1502 VIS SI Ftt-89A E-6 'SI255-153 VIS SI Ftt-89A F-7 SI256-153 VIS

- - - - MMMMMMMMMMMMMMMMM****if************************MMMMMMMMMMMMM*MMMMMMMMMMMMMMMM*****-*********

VIRGINIA ELECTRIC AND POWER CONPANY SURRY POWER STATION UNIT *2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

/.

PAGE 207 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.21 ITEM DESCRIPTION: PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEty DIAGRAM DIAGRAM . LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER : METHOD REQUEST NOTES

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

SI FM-89A H-2 SI257-1503 VIS SI Ftt-89A H-2 SI25S-1503 VIS SI FM-89A H-1 SI259-1503 VIS SI Ftt-89A E-1 SI268-1503 VIS

.SI Ftt-89A A-2 SI272-1503 VIS SI i=tt-89A E-6 SI278-I52 VIS SI Ftt-89A G-1 SI283-153 VIS SI Ftt-89A 0-8 SI284-152 VIS SI Ftt-89A B-2 SI290-1503 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 208 *

ASHE SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C--H ALL PRESSURE.RETAINING COMPONENTS

ITEM NUl1BER : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C 11548) COORD NUMBER METHOD REQUEST NOTES

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

SI Ftt-89A 0-6 SI292-153 VIS SI Fl't-89A F-2 SI293-1503 VIS SI Ftt-89A F-4 SI302-152 VIS SI Ftt-89A 0-6 SI306-152 VIS SI Ftt-89A I-6 SI330-l52 VIS SI Ftt-89A J-4 SI331-152 VIS SI Ftt-89A C--7 SI332-153 VIS SI Ftt-89A C--8 SI333-ICN9 VIS SI Ftt-89A E-7 SI334-ICN9 VIS

- - - - il************************************lHHf*****************************

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPEC~ION PLAN SUNMARY INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80 PAGE 209 REVISION 0001

' DATE 86/10/20

- - - - lHHf************************************~***********************************

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES

\

SI

Ftt-89A 0--8 .SI335-ICN9 VIS SI Ftt-89A E-7 SI336-ICN9 VIS SI Ftt-89A f-7. SI33rl53 VIS SI Ftt-89A F-8. SI33S-ICN9 VIS SI Ftt-89A tt-7 SI339-ICN9 VIS SI Ftt-89A tt-8 SI340--ICN9 VIS SI Ftt-89A tt-7 SI341-ICN9 VIS SI Ftt-89A S-2 SI34rl503 VIS SI Ftt-89A E-5 SI348-153 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

, INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 210 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER C7.2l ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (1154-8) COORD NUMBER METHOD REQUEST NOTES

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

SI Ftt-89A E-5 SI349-153 VIS SI Ftt-89A 0-5 SI350-153 VIS SI Ftt-89A 0-6 SI351-153 VIS SI Ftt-89A A-4 SI35Z--1502 VIS SI Ftt-89A 0-6 SI360-153 VIS SI Ftt-89A C-2 SI361-1503 VIS SI Ftt-89A 0-8 SI362-153 VIS SI Ftt-89A F-8 SI363-153 VIS SI Ftt-896* S---7 SI234-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SUl1!1ARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 211 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C--H ALL PRESSURE RETAINING COMPONENTS

- - - - lf*************************************************************************

ITEM NUMBER : C7.21 ITEM DESCRIPTION: PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DI.AGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES SI Ftt-898

0-5 SI236-602 VIS SI Ftt-89B B-5 SI24S-1502 VIS SI Ftt-898 F-6 SI246-1502 VIS SI Ftt-898 C---3 SI250-1502 VIS SI Ftt-898 a-s SI263-602 VIS SI Ftt-898 S---6 SI26S-602 VIS SI Ftt-89B 1-1 SI270-1503 VIS SI Ftt-898 E-1 s1211-1503 VIS SI Ftt-898 a-1 SI274-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

. SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 212 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES SI Ftt-898 S--2 SI275-1502 VIS SI Ftt-898 E-1 SI276-1503 VIS SI Ftt-898 S--1 sI2a5-1502 VIS SI Ftt-898 S--5 SI297-602 VIS SI Ftt-898 0-4 SI300-602 VIS SI F/r89B I-3 51343-1502 VIS SI Ftt-898 e-1 SI344-1502 VIS SI Ftt-898 .A-1 51345-1502 VIS SI Ftt-89B

1-1 SI346-1503 VIS

.)

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 213 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C--H ALL*PRESSURE RETAINING COMPONENTS ITEM NUMBER C7.21 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) _COORD NUMBER METHOD REQUEST NOTES SI Ftt-898 B-2 51353-1502 VIS SI Ftt-898 0-1 51354-1502 VIS SI Ftt-898 C--3 SI355-1502 VIS SI Ftt-89B 0-1 5!356-1502 VIS SI Ftt-898 C--2 SI357'-1502 VIS SI Ftt-898 0-2 SI358-1502 VIS SI FM-898 C--4 5!359-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE

REVISION 214

0001

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.30 ITEM DESCRIPTION : PUMPS PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A A-1 2RCP1A VIS RC Ftt-86A A-6 2RCP1B VIS RC Ftt-86A L-1 2RCP1C VIS RHR Ftt-87A C-6 2RHP1A VIS RHR Ftt-87A C-6 2RHP1B VIS

VIRGINIA ELECTRIC AND POWER COMPANY '*

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 215

PAGE *

ASME SECTION XI EDITION 80W80 REVISION 0001

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.31 ITEM DESCRIPTION : PUl1PS PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM, LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86.t. A-1 2RCP1A VIS RC Ftt-86.t. A-6 2RCP1B VIS RC Ftt-86.t. L-1 2RCP1C VIS RHR Ftt-87.t. C-6 2RHP1A VIS RHR Ftt-87.t. C-6 2RHP1B VIS

VIRGINIA ELECTRIC AND POWER COMPANY **

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 216 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER : C7.40 ITEM DESCRIPTION : VALVES PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES

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

FW FM-68A C-5 WFP0109-601 VIS FW FM-68A C-3 WFPD113-60l VIS FW FM-68A C-2 WFPD117-601 VIS MS FM-64A B-3 SHPlOl-601 VIS Ms* FM-64A A-4 SHP102-60l* VIS

.MS FM-64A a-5 SHPl03-601 VIS MS FM-64A B-3 SHP122-601 VIS l1S FM-64A a-4 ., SHP.123-601 VIS MS FM-64A B-6 SHP124-601 VIS

VIRGINIA ELECTRIC ANO POWER COMPANY *

SURRY - POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE 217

REVISION 0001 ..

DATE 86/10/20 *

CATEGORY c-H ALL PRESSURE RETAINING COMPONENTS

ITEM NUMBER : C7.40 ITEM DESCRIPTION : VALVES.PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES

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

MS Ftt-64A 0-3 SHP14.5-601 VIS MS Ftt-64A 0-.5 SHP146-601 VIS MS Ftt-64A 0-6 SHP147-601 VIS RHR Ftt-87A E-6 RHl02-602. VIS RHR Ftt-87A B-6 RHl04-602 VIS RHR Ftt-87A 0-6 RHl0.5-602 VIS RHR Ftt-87A A-3 RHlOS-602 VIS RHR Ftt-87A I-.5 RH104r602 VIS RHR Ftt-87A 0-3 RHll0-602 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05~01/83 TO 05/01/93

PAGE 218

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY c-H ALL*PRESSURE RETAINING COMPONENTS

ITEM NUMBER C7.40 ITEM DESCRIPTION VALVES PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) comm NUMBER METHOD REQUEST NOTES RHR Flt-87A C-3 RHU2-602 VIS RHR Flt-87A B-3 RHU4-602 VIS RHR Flt-87A 0-3 RH116-602 VIS RHR Flt-87A C-6 RH118-602 VIS RHR Flt-87A S-4 RH119-602 VIS SI Flt-896 C-2 SI248-1502 VIS SI Ftt-898 C-3 SI249-1502 VIS SI Flt-89A B-6 SI352-1502 VIS

VIRGINIA ELE~TRIC.AND POWER COMPANY

SURRY POWER STATION UNIT 2

IHSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 219. *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER C7.41 ITEM DESCRIPTION VALVES PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES

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

FW Ftt-68A C-5 WFPD109-601 VIS FW Ftt-68A C-3 WFPOU3-601 VIS FW Ftt-68A C-2 WFPDll J-601 VIS MS Ftt-64A e-3 SHPlOl-601 VIS MS Ftt-64A A-4 SHP102-601 VIS MS Ftt-64A S-5 SHPl03-601 VIS MS Ftt-64A B-3 SHP122-601 VIS MS* Ftt-64A S-4

SHP123-601 VIS MS Ftt-64A S-6 SHP124-601 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE

REVISION 220

0001

DATE 86/10/20 *

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER C7.41 ITEM DESCRIPTION VALVES PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM** LINE EXAH RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES 115 Flt-64A 0-3 SHP145-601 VIS MS Flt-64A 0-5 SHP146-601 VIS 11S Flt-64A 0-6 SHP147-601 VIS RHR .Flt-87A E-6 RH102-602 VIS RHR Flt-87A B-6 RH104-602 VIS RHR Ftt:-87A 0-6 RHl05-602 VIS RHR Flt-87A A-3 RHlOS-602 VIS RHR Flt-87A 1-5 RH109-602 VIS RHR Flt-87A 0-3 RHH0-602 VIS

- - - - >>***********************IE lE l(l(l( lElE************************************************

VIRGINIA ELECTRIC ANO POWER COMPANY

'* SURRY POWER STATION UNIT 2 *

l(

- - - - l(l(l(l(l(l(l(l(l(l(**

INSERVICE INSPECTION PLAN

SUMMARY

I INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 221 *

ASME SECTION XI EDITION 80W80 REVISION 0001

DATE 86/10/20

- - - - l(l(l(l(l(l(l(l(l(l(l(l(***************************************l(l(l(l(l(l(l(l(l(l(l(l(l(l(l(l(l(*********************

CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

- - - - lllll(l(l(l(l(l(l(l(l(lf*******************************************lllll(l(l(l(l(l(********************

ITEM NUMBER : C7.41 ITEM DESCRIPTION : VALVES PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES

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

RHR FM-87A C-3 RH112-602 VIS RHR FM-87A S-3 RH114-602 VIS RHR FM-87A 0-3 RH116-602 VIS RHR FM-87A C-6 RH118-602 VIS RHR FM-87A S-4 RH119-602 VIS SI FM-89B C-2 SI248-1502 VIS SI FM-898 'c-3 SI249-1502 VIS SI FM-89A S-6 SI352-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/0.1/93

PAGE 222 *

ASHE SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER : Dl.lOH ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWl'rHYDROSTATIC FLOW .FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES cc Ftt-718 lt-7 CC36S-151 VIS cc Ftt-718 S--6 CC366-151 VIS cc Ftt-718 F-7 CC36rl51 VIS,

- cc cc cc Ftt-718 Ftt-718 Ftt-718 E-6 0-5 S--5 CC369-151 CC370-151 cc311-1s1 VIS VIS VIS cc Ftt-718 E-s CC372-151 VIS

. cc Ftt-718 C-5 cc373-1s1 . VIS cc Ftt-718 I-s CC374-151 VIS

- - - - ii**************************************************************

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SUNMARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 223 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

.* CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER : Dl.lOH ITEM DESCRIPTION: COMPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC FLOW FLOW SY.STEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES cc Ftt-71B S-5 CC37S-151 VIS cc Ftt-71B H-4 CC376-151 VIS cc Ftt-71B E-4 CC37rl51 -VIS cc Ftt-71B S-4 CC37S-151 VIS cc Ftt-71B S-5 CC379-151 VIS cc Ftt-71B H-S CC380-151 VIS cc Ftt-71B E-6 CC381-151 VIS cc Ftt-71B E-S CC385-151 VIS cc Fi1-72A A-a CC161-151 VIS 1*

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY PO'..iER STATION UNIT 2 *

.INSERVICE INSPECTION PLAN SU1111ARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 224 * '

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER ITEM DESCRIPTION 01.lOH COMPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC I

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST t:IOTES cc Flt-72A A-7 CC162-151 VIS cc Flt-72A A-7 CC163-151 VIS cc Flt-72A A-8 CC164-151 VIS cc Flt-72A A-8 CC165-::151 VIS cc Flt-72A C-8 CC166-151 VIS cc Flt-72.A C-8 CC167-151 VIS cc Flt-72A C-8 CC16S-151 VIS Cc Flt-72.A A-6 CC169-151 VIS cc Flt-72A B-4 CC17<t-151 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 225 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER : Dl.lOH ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) cooim NUMBER METHOD REQUEST NOTES

=======*= -------- ------- ------ ======= -------

cc FM-72A A-5 cc111-151 VIS cc FM-72A A-5 CC172-151 VIS.

cc FM-72A S--4 CC173-151 VIS

cc ct cc FM-72A FM-72A FM-72A 1)-5 1)-5 C-7 CC174-151 cc115-151 CC176-151 VIS VIS VIS cc FM-72A A-3 CC177-151 VIS cc FM-72A A-2 cc118-1s1 VIS cc FM-72A A-3 CC179-151 VIS

VIRGINIA ELECTRIC ANO POWER COMPANY *.

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 226 *

ASME SECTION XI *EDITION 80W80

REVISION 0001 *

DATE 86/10/20* *

CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION *

- - - - ii***************************************************************************

ITEM NUMBER : Dl.lOH IT-EM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC I

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT * (11548) COORD Ntr.1BER METHOD REQUEST NOTES cc FM-72A A-3 CC180-151 .VIS.

cc FM-72A C-2 cc1a1-151 VIS cc FM-72A 0-3 CC182-151 VIS

-* cc cc cc FM-72A FM-72A FM-72A C-3 F-7 F-4 CC183-151 cc1as-1s1 CC187-151.

VIS VIS VIS cc FM-72A F-s CC18S-l5l VIS cc FM-72A F-6 CC189-151 VIS cc FM-72A S-7 cc190-1s1 VIS

- - - - M************************************************************

VIRGINIA. ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

'* INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 227 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY O-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER : Dl.lOH ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM .. LINE EXAM RELIEF PROGRAM COMPONENT ( 115481 COORO NUMBER METHOD REQUEST NOTES cc FM-72A S-4 CC192-151 VIS cc FM-72A H-6 CC194-151 VIS cc FM-72A A.:..2 CC20S-l5l VIS cc FM-72A 0-2 CC209-151 VIS cc FM-72A B-4 CC2l0-151 VIS cc FM-72A 0-4 cc211-1s1 VIS cc FM-72A A-7 CC212-151 VIS cc FM-72A S-1 cc21s-1s1 VIS cc FM-72A S-2 CC219-151 VIS J

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN SUT111ARY INTERVAL 2, 05/01/83 TO 05/01/93 ASHE SECTION XI *EDITION 8~W80

PAGE

REVISION

. 228

0001

DATE 86/10/20 *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION *

- - - - lflflflfMlflf****lf**illflfMlflflflflflflflflflflflflflfMlfMMMMMlflflflflflflf***lflflf*************************************

ITEM NUMBER : Dl.lOH ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC I

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548)' COORD NUMBER METHOD RE~UEST NOTES

. ------- ------- ------ ======= -------

cc Frt-72A E-1 CC253-151 VIS cc Frt-72A G-8 CC254-151 VIS cc Frt-72A G-7 CC27~151 VIS cc Frt-72A G-7 cc215-1s1 VIS cc Frt-72B E-3 CC153-151 VIS cc Frt-72B C-2 CC154-151* VIS cc Frt-72B 0-3 cc15s-1s1 VIS cc Frt-72B 0-2 CC186-151 VIS cc Frt-72B C-2 cc191-1s1 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY PO.IER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/0li93 ASME SECTION XI EDITION 80W80

- PAGE 229 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER :.Dl.lOH ITEM DESCRIPTION: COMPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC

.FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUl1BER METHOD REQUEST NOTES

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

cc Ftt-72B G-2 CC263-151 VIS cc Ftt-72B F-2 CC276-151 VIS cc Ftt-72E F-6 CC143-121 VIS cc FM-'72E F-3 cc144-151 VIS cc Ftt-72E F-3 cc14s-1s1 VIS cc Ftt-72E H-3 CC146-151

VIS cc Ftt-72E. I-J CC14S-151 VIS cc Ftt-72E E-1 cc12-121 VIS cc Ftt-72F 0-3 CC149-151 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY

POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 230 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION

ITEM NUMBER : Dl.lOH ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC FLOW FLOW SYSTEM/ . DIAGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT (11548)

COORD. NUMBER METHOD REQUEST NOTES cc FH-72F B-3 cc152-121 VIS cc FH-72F E-3 CC156-151 VIS cc Frt-72F 0-2. CC159-151 VIS cc Frt-72F 0-3 CC160-151 VIS cc Flt-72F C-2 CC163-151 VIS cc Frt-72F B-3 cc181-121 VIS CH Flt-888 L-4 CH342-152 VIS CH Flt-888 L--4 CH3S6-152 VIS CH Flt-888 K-4 CH3Sr152 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *'

INSERVICE INSPECTION PLAN SUNMARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 231 *

'ASME SECTION XI EDITION 80W80

REVISION 0001 ,*

DATE 86/10/20 *

~**************************************************************************************************

CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FlJNcTION ITEM NUMBER : Dl.lOH ITEM DESCRIPTION: COMPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM ** LINE EXAM RELIEF PROGRAM

_COMPONENT (11548) COORD NUMBER METHOD _REQUEST NOTES CH Ftt-:;88B .r-4 CH358-152 VIS CH FH-886 .r-4 CH495-152 VIS FW FH-68A. S-8 WAP0-151 VIS FW FH-68A 0-:-6 WAPDlOl-601 VIS FW FH-68A 0-6 WAPOlOZ--601 VIS FW -FH-68A 0-7 WAPD103-601 VIS FW FH-68A 0-6 WAPD104-60l VIS FW *ftt-68A E-6 WAPOlQS-601 VIS FW .FH-68A E-6 WAP0106-601 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE .232 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION

ITEM NUMBER Dl.lOH ITEM DESCRIPTION COMPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES

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

FW FM-68A F-6 WAPOl0?-601 VIS FW FM-68A F:-6 WAPOlOS-601 VIS FW FM-68A C-4 WAP0109-601 VIS FW FM-68A C-6 WAPOll0-601 VIS FW FM-68A 9-5 WAPOlll-601 VIS FW FM-68A B-6 WAP0112-601 VIS FW FM-68A B-6 WAP0113-601 VIS FW FM-68A B-6 WAP0114-601 VIS FW FM-68A 0-7 WAP0115-601 VIS

)

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 233 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY 0-A' SYSTEMS IN SUPPORT ')f REACTOR SHUTDOWN FUNCTION ITEM NUMBER 01.lOH ITEM DESCRIPTION COMPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE* EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES

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

FW Ftt-68A 0-6 WAPD116-151 VIS FW Ftt-68A E-7 WAP0117-601 VIS FW Ftt-68A F-6 WAPOllS-151 VIS FW Ftt-68A F-L WAP0119-151 VIS FW Ftt-68A F-7 WAP0120-601 VIS FW Ftt-68A S-6 WAPD121-151 VIS FW . Ftt-68A e-1 WAP0150-601 VIS FW Ftt-68A B-L WAPOlSl-601 VIS FW Ftt-68A C--:6 WAPOS2-601 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASHE SECTION XI EDITION 80W80

PAGE

REVISION 234

0001

DATE 86/10/20 *

- - - - IHt*************************************************************************

CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION **

ITEM NUMBER : Dl.lOH ITEM DESCRIPTION : COMPONENTS IN .SUPPORT OF RX SHUTDOWN-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAN. LIN~ EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES FW FM-68A G-8 WCMlJ-151 VIS FW FM-68A H-8 WCMU104-151 VIS FW FM-68A H-8 WCMUlOS-151 VIS FW FM-68A H-8 WCMU106-151 VIS FW FM-68A H-8 WCMU107-151 VIS FW FM-68A E-8 WCMUlOS-151 VIS FW FM-68A F-8 WCMU109-151 VIS FW FM-68A E-8 WCMUll0-151 VIS MS FM-64A B-4 SHP12S-601 VIS

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 235 *

~ ASHE SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER Dl.lOS ITEM DESCRIPTION COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM

-COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES HS FM-64A B-6 SHP126-601 VIS MS Ftt-64A B-7 SHP127-601 VIS MS FM-64A G-8 SHP157-601 VIS

SI SI FM-89A FM-89A G-2 I-1 SI260-1503 SI28rl503 VIS VIS

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY 'POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 236 *

ASME SECTION XI.EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY D-A SYSTEMS IN SUPPORT *oF .RE.ACTOR SHUTDOWN FUNCTION ITEM NUNBER : Dl.lOS ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUNBER METHOD REQUEST NOTES

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

cc FM-71B 0-7 CC36S-151 VIS cc FM-71B S--6 CC366-151 VIS cc FM-71B f-7 CC36rl51 VIS cc FM-71B E-6 CC369-151 VIS cc FM-71B D-s cc310-1s1. VIS cc FM-71B S--5 CC371-151 VIS cc FM-71B E-s CC372-151 VIS cc FM-71B C--5 CC373-151 VIS cc FM-71B I-s CC374-151 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 237 *

ASHE SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION

ITEM NUMBER Dl.lOS ITEM DESCRIPTION COMPONENTS IN SUPPORT OF RX SHUTDOwtrSYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUNBER METHOD REQUEST NOTES

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

cc FM-71B S--5 cc37s-1s1 VIS cc FM-71B H-4 CC376-151 VIS cc FM-71B E-4 CC377-151 VIS cc FM-71B B-4 CC378-151 VIS cc FM-71B S--5 CC379-151 VIS cc FM-71B H-5 CC380-151 VIS cc FM-71B E-6 CC381-151 VIS

/

cc FM-71B E-5 CC385-151 VIS cc FM-72A A-8 CC161-151 VIS

VIRGINIA ELECTRIC AHO POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 238 *

. ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

- - - - ifif**************************

CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION

ITEM NUMBER : DI.IDS ITEM DESCRIPTION .* COMPONENTS IN SUPPQRT OF RX SHUTDOW!t-SYSTEl1 LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAM* RELIEF. PROGRAM COMPONENT (11548) .COORD NUMBER METHOD RE~UEST NOTES cc Ftt-72A A-7 CC162-I51 VIS cc Ftt-72A A-7 CC163-I51 VIS cc Ftt-72A A-8 CC164-I51 VIS cc Ftt-72A A~8 CC16S-151 VIS cc Ftt-72A C-8 CC166-151 VIS cc Ftt-72A C-8 CC16r151 VIS cc Ftt-72A .

C-8 CC16S-151 VIS cc Ftt-72A A-6 CC169-I51

VIS cc Ftt-72A B-4 CC170-I51 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT'2 *

INSERVICE INSPECTION PLAN SUNMARY ********************

INTERVAL 2, 05/01/83 TO, 05/01/93

PAGE 239 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY 0-A , SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER : .Dl.lOS ITEM DESCRIPTION: COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES

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

cc .FM-72A A-5 CC171:-151 VIS cc FM-72A A-5 CC17Z-151 VIS cc FM-72A S-4 cc173-151 VIS cc FM-72A 0-5 CC174-151 VIS cc FM-72A 0-5 cc11s-151 VIS cc FM-72A C-7 CC176-151 VIS cc Fl1-72A A-3 CC177-151 VIS cc FM-72A A-2 CC17S-151 VIS cc FM-72A A-3 CC179-151 VIS r

VIRGIN!&. ELECTRIC AND POWER COMPANY SURRY INSERVICE POWER STATION UNIT 2 INSPECTION PLAN SUNHARY INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE 240 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY 0-A SYSTEMS_IN SUPPORT OF REACTOR SHUTDOWN FUNCTION

ITEM NUMBER : Dl.lOS ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTUOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM -

LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES cc Ftt-72A .4-3 CC180-151 VIS cc Ftt-72A C-2 cc1a1-151 VIS cc Ftt-72A 0-3 CC182-151 VIS cc Ftt-72A C-3 CC183-151 VIS cc Ftt-72A F-7 cc1ss-1s1 VIS cc Ftt-72A F-4 CC187-151 VIS cc Ftt-72A F-5 cc1ss-1s1 VIS cc Ftt-72A F-6 CC189-151 VIS cc Ftt-72A S-7 CC190-151 VIS

VIRGINIA ELECTRIC AHO POWER COMPANY *

SURRY POWER STATION UNIT, 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE -241 *

ASME SECTION XI EDITION 80W80

REVISION -0001 *

DATE 86/10/20 *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER : D1:1os ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM . RELIEF PROGRAM

-COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES cc Ftf-72A S-4 CC192-151 VIS cc Ftf-72.A H-6 cc194-151 VIS cc Ftf-72A A-2 cc2oa-151 VIS cc Ftf-72A tt-2 CC209-151 VIS cc Ftf-72.A S-4 CC210-151 VIS cc Ftf-72A 0-4 cc211-151 VIS cc Ftf-72A A-7 CC212-151 VIS cc Ftf-72A S-1 cc215-151 VIS cc Ftf-72A S-2 CC219-151 VIS

VIRGINIA ELECTRIC ANO POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SUHNARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 242 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NU11BER : Dl.lOS ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM- LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NU11BER METHOD REQUEST NOTES

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

cc Ftt-72A E-1 CC253-151 VIS cc Ftt-72A S-8 CC254-151 VIS cc Ftt-72A S-7 cc212-1s1 VIS cc Ftt-72A S-7 cc21s-1s1 VIS cc Ftt-72B E-3 CC153-151 VIS cc Ftt-72B C-2 CC154-151 VIS cc Ftt-72B 0-3 cc1s5-1s1 VIS cc Ftt-72B 0-2 CC186-151 VIS cc Ftt-72B C-2 cc191-1s1 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 243 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER : Dl.lOS ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES cc Ftt-728 S---2 CC263-151 VIS cc *Ftt-728 F-z CC276_;151 VIS cc Ftt-72E F-6 CC143-121 VIS cc Ftt-72E F-3 cc144-151 VIS cc Ftt-72E F-3 CC14S-151 VIS cc Ftt-72E H-3 CC146-151 VIS cc Ftt-72E 1-3 CC148-151 VIS cc Fl'f:-72E e-1 cc12-121 VIS cc Ftt-72F 1)-:-3 CC149-151 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE

REVISION 244

0001

DATE 86/10/20 *

- - - - k**********************************************************************************

CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER : 01.lOS ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM .. LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES cc Ftt-72F e-3 CC152-121 VIS cc Ftt-72F E-3 CC156-151 VIS cc l'"tt-72F 0-2 CC159-151 VIS cc Ftt-72F 0-3 CC160-151 VIS cc Ftt-72F C-2 CC163-151 VIS cc Ftt-72F B-3 cc181-121 VIS CH Ftt-888 L-4 CH342-152 VIS CH Ftt-88B L-4 CH356-152 VIS CH Ftt-888 K-4 CH357-152 VIS

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN SUNMARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 245 *

ASHE SECTION XI EDITION 80W80 ** REVISION 0001 *

DATE 86/10/20 *

CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER : Dl.10S ITEM DESCRIPTION : CONPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE t

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAtt ** LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES CH FM-888 J-4 CH358-152 VIS CH FM-888 J-4 CH49S-152 VIS FW FM-68A S-8 WAPo-151 VIS FW FM-68A 0-6 WAPDlOl-601 VIS FW FM-68A 0-6 WAPD102-601 VIS FW FM-68A 0-7 WAPDl03-601 VIS FW FM-68A 0-6 WAPDl04-601

VIS FW FM-68A E-6 WAPDlOS-601 VIS FW FM-68A E-6 WAPDl06-601 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W89

PAGE 246 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER : Dl.lOS ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE*

I FLOW FLOW

~YSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES FW Ftt-68A F-6 WAPD10r601 VIS FW Ftt-68A F-6 WAPDlOS-601 VIS FW Ftt-68A C:-4 WAPD109-601. VIS FW Ftt-68A C-6 WAPDll0-601 VIS FW Ftt-68A B-5 WAPDlll-601 VIS FW Ftt-68A s-6 WAP0112-601 VIS FW Ftt-68A B-6 WAPD113-60l VIS FW Ftt-68A s-6 WAPD114-601 VIS FW FM-68A 0-7 WAPDllS-601 VIS

- VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

IHSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 247 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY o-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION

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

ITEM NUMBER : Dl.lOS

.ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE I

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM

COMPONENT ( 11548) COORD NUMBER METHOD REQUEST *NOTES

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

FW FM-68A 0-6 WAPD116-151 VIS FW FM-68A e-1 WAPD117-601 VIS FW FM-68A f-6 WAPDllS-151 VIS

FW FW FW FM-68A FM-68A FM-68A f-L F-7 S--6 WAPDll 9-151 WAPD120-:-601 WAPD121-151 VIS VIS VIS FW FM-68A S-7 WAPDlS0-601 VIS*

FW FM-68A S-L WAPDlSl-601 VIS*

FW FM-68A C-6 WAPDS2-601 VIS

- - - - K********************************************************************************

VIRGINIA ELEC~IC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 !Ii*

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 248 *

ASME SECTION XI EDITION 80W80 ** REVISION 0001 *

DATE 86/10/20 *

- - - - ~

CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION

ITEM NUMBER Dl.lOS ITEM DESCRIPTION COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES FW Ftf-68A S-8 WCMU-151 VIS FW Ftf-68A H-8 WCMUl04-151 VIS FW Ftf-68A H-8 WCMUl05-151 VIS FW Ftf-68A H-8 WCMUl06-151 VIS FW Ftf-68A H-8 WCMU107-151 VIS FW Ftf-68A E-8 WCMUlOS-151 VIS FW Ftf-68A F-8 WCMU109-151 VIS FW Ftf-68A E-8 WCMUU0-151 VIS MS Ftf-64A 9-4 SHP125-601 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 *

PAGE 249 *

ASME SECTION XI EDITION 80W80

REVISION 0001

DATE 86/10/20 *

CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER : Dl.lOS ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW*

SYSTEM/ DIAGRAM DIAGRAM LINE. EXAM - RELIEF PROGRAM COMPONENT (11548.) COORD NUMBER METHOD RE~UEST NOTES

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

MS Ftt-64A B-6 SHP126-601 VIS MS Ftt-64A B-7 SHP127-601 VIS MS Ftt-64A S-8 SHP157-601 VIS SI Ftt-89A S-2 SI260-l503 VIS SI Ftt-89A 1-1 SI287-1503 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PASE 250 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY 0-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS ITEM NUMBER : D2.10H ITEM DESCRIPTION : COMPONENT IN SUPPORT OF ECCS, CHR, ACU, ~ RHR - HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES

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

cc Ht-71B S-1 WS179-21B VIS SW FM-71A E-6 wc101-10 VIS SW FM-71A E-6 WClOZ-10 VIS SW FM-71A F-6 wc103-10 VIS SW FM-71A F-6 wc104-10 VIS SW FM-71A C-7 ws101-10 VIS SW FM-71A C-7 WSlOZ-10 VIS SW FM-71A C-7 ws104-10 VIS SW FM-71A E-7 ws121-10 VIS I

I

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

. INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 251 *

ASME SECTION XI EDITION aowao

REVISION 0001 *

DATE 86/10/20 *

CATEGORY 0--B - ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS ITEM NUMBER : D2.10H ITEM DESCRIPTION : COMPONENT IN SUPPORT OF ECCS, CHR, ACU, ~ RHR - HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (115~) COORD NUMBER METHOD. REQUEST NOTES SW Ftt-71A 0--6 WS12Z-10 VIS SW Ftt-71A 5-7 ws123-10 VIS SW 'Ftt-71.A B-7 ws124-10 VIS

- - SW SW Ftt-71A.

Ftt-71.A A-3 B-3 WS126-10.

- WS12S-10 VIS VIS SW Ftt-71.t. C--3 WS130-l0 VIS

- SW Ftt-71A C--3 WSl3Z-10 VIS SW Ftt-71.A A-3 1,15133-10 VIS SW Ftt-71.A B-3 ws134-10 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INS ERV ICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 252 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY 0-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS ITEM NUMBER : D2.10H ITEM DESCRIPTION : COMPONENT IN SUPPORT OF ECCS, CHR, ACU, ~ RHR - HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM RELIEF PROGRAM COMPONENT (11548) COORD NUMBER METHOD REQUEST NOTES SW FM-71A B-3 ws135-10 VIS SW FM-71A C-3 WS136-10 VIS SW FM-71A 0-3 WS13rl0 VIS SW FM-71A 0-3 wsn8-10 VIS SW FM-71B 0-8 WS170-136 VIS SW FM-71B 0-8 ws111-136 VIS SW FM-71B S-8 WS17Z-136 VIS SW FM-71B S-8 WS173-136 VIS SW FM-71B 0--7 WS174-21B VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE 253 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY 0-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS

ITEM NUMBER : D2.10H ITEM DESCRIPTION : COMPONENT IN SUPPORT OF ECCS, CHR, ACU, ~ RHR - HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (115481 COORD NUMBER METHOO REQUEST NOTES

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

SW FM-71B S-7 ws11s-21e VIS SW FM-71B E-8 WS176-21B VIS SW Ftt-71B B-6 WS17S--136 VIS SW Ftt-71B H-1 WS180-21B VIS SW Ftt-71B 0-1 ws1s1-21B VIS SW *Ftt-71B H-1 WS182-21B VIS SW FM-71B E-1 WS183-21B VIS SW FM-71B A-1 WS185-21B VIS SW Ftt-71B 0-1 WS186-21B VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE 254 *

REVISION 0001. *

DATE 86/10/20 *

CATEGORY D-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS

ITEM NUMBER D2.10H ITEM DESCRIPTION COMPONENT,IN SUPPORT OF ECCS, CHR, ACU, ~ RHR - HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM

~ COMPONENT ( 11548) COORD

NUMBER METHOD REQUEST NOTES

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

SW Ftt-71B WS187-21B VIS SW Ftt-71B 0-1 WSI88-21B VIS SW Ftt-71B 0-7 WS190-136 VIS

/

VIRGINIA ELECTRIC ANO POWER COMPANY

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 255 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

** DATE 86/10/20 *

CATEGORY 0--B ECCS, CHR, ACU, ANO RHR SUPPORT SYSTEMS

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

ITEM NUMBER : D2.10S ITEM DESCRIPTION : COMPONENT IN SUPPORT OF ECCS, CHR, ACU, ~ RHR - SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAK LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES cc FM-71B a-1 WS179-21B VIS SW FM-71A E-6 wc101-10 VIS SW FM-71A E-6 WC102-l0 VIS SW FM-71A F-6 wc103-10 VIS SW FM-71A F-6 wc104-10 VIS SW FM-71A C-7 ws101-10 VIS SW FM-71A C-7 WS102-10 VIS SW FM-71A C-7 WSl04-10 VIS SW FM-71A E-7 ws121-10 VIS

VIRGINIA ELECTRIC AND POWER COMPANY

SURRY POWER STATioN UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01!93 * .PAGE

256 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY D-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS ITEM NUMBER : D2.10S ITEM DESCRIPTION : COMPONENT IN SUPPORT OF ECCS, CHR, ACU, ~ RHR -*SYSTEM LEAKAGE I

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES SW FH-71A D-6 WS122-10 VIS SW FH-71A S-7. ws123-10

VIS SW FH-71A 5-7 ws124-10. VIS*

SW FH-71A A-3 WS126-10 VIS SW FH-71A S-3 ws128-10 VIS SW FH-71A C-3 WS130-10 VIS

.SW FH-71A C-3 WS132-10 VIS SW . FH-71A A-3 ws133-10 VIS SW FH-71A S-3 ws134-10 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 257 *

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY o-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS ITEM NUMBER D2.10S ITEM DESCRIPTION COMPONENT IN SUPPORT OF ECCS, CHR, ACU, ~ RHR - SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11548) COORD NUMBER METHOD REQUEST NOTES

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

SW FM-71A S-3 ws13s-10 VIS SW FM-71A C--3 WS136-10 VIS SW FM-71A 0-3 WS137-10 VIS SW FM-71A 0-3 WS138-10 VIS SW FM-71B 0-8 WS170-136 VIS SW FM-71B 0-8 ws111-136 VIS SW FM-71B S-8 WS172-136 VIS SW FM-71B S-8 WS173-136 VIS SW FM-71B 0-7 WS174-21B VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE 258 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY 0-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS ITEM NUMBER . : D2.10S ITEM DESCRIPTION : COMPONENT IN SUPPORT OF ECCS, CHR, ACU, ~ RHR - SYSTEM LEAKAGE I

FLOW .FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES SW FM-71B S---7 ws115-21e VIS SW FM-716- E-8 WS176-21B VIS SW FM-716 S-6 WSl7S--136 VIS SW FM-71B H-1 WS180-21B VIS SW FM-71B 0-1 ws181-21e VIS SW FM-716 H-1 ws1a2-21e VIS SW FM-71B E-1 WS183-21B VIS.

SW FM-71B A-1 WS185-21B VIS SW FM-716 0-1 WS186---:21B VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93 ASME SECTION XI EDITION 80W80

PAGE 259 *

REVISION 0001 *

DATE 86/10/20 *

CATEGORY 0-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS ITEM NUMBER : D2.10S ITEM DESCRIPTION : COMPONENT IN SUPPORT.OF ECCS, CHR, ACU, ~ RHR - SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM .. LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD NUMBER METHOD REQUEST NOTES SW Ftt-71B H-1 WS18r21B VIS SW Ftt-71B 0-1 WS188-21B VIS SW Ftt-71B 0-7 WS190-136 VIS

- '* VIRGINIA ELECTRIC AND POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 260

ASME SECTION XI EDITION 80W80 REVISION 0001 *

DATE 86/10/20 *

CATEGORY 0-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS

ITEM NUMBER : D2.20 ITEM DESCRIPTION : INTEGRAL ATTACHMENT-SUPPORTS ~ RESTRAINTS FOR ECCS, ETC.

FLOW FLOW

.SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT <11548) COORD NUMBER METHOD REQUEST NOTES AF -Frt-68A E-6 WAPDlOl-601 VIS AF Frt-68A E-6 WAPDlOZ-601 VIS AF Frt-68A E-6 WAPDl04-601 VIS AF Frt-68A H-8 WCMUl05-151 VIS AF Frt-68A H-8 WCMUl06-151 VIS AF Frt-68A H-8 WCMU107-151 VIS AF Frt-68A F-8 wcMU108-1s1 VIS cc Frt-72A K-3 CC7-121 VIS cc Frt-72B 0-3 CC156-151 VIS

VIRGINIA ELECTRIC AHO POWER COMPANY *

SURRY POWER STATION UNIT 2 *

INSERVICE INSPECTION PLAN Sutff1ARY ********************

INTERVAL 2, 05/01/83 TO 05/01/93

PAGE 261

ASME SECTION XI EDITION 80W80

REVISION 0001 *

DATE 86/10/20 *

CATEGORY 0-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS ITEM HUMBER D2,20 ITEM DESCRIPTION INTEGRAL ATTACHMENT-SUPPORTS ~ RESTRAINTS FOR ECCS, ETC, FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM- -- LINE EXAM RELIEF PROGRAM COMPONENT C11548) COORD. HUMBER METHOD REQUEST NOTES cc FM-72B F-3 CC160-151 VIS CH FM-88C S-4 CH399-152 VIS

RELIEF REQUEST NO. SR-001 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 ste~l. None of the valve bodies are welded.

Section XI of' the ASME Code, 1980 Edition through the Winter 1980 Addendum, requires that a visual examination be performed on 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 sampling of primary system valves and give adequate assurance that the integrity of these components is being maintained.

III. ALTERNATE PROVISIONS A valve wall thickness measurement will be performed on valves that are not disassembled for maintenance purposes and an examination of the internal pressure boundary surfaces will be performed,

to the exte:.:t practical, each time a valve is disassembled for maintenance purposes.

Note: This relief request has been modified as requested by letter from Lester S. Rubenstein dated January 24, 1986.

S2-002-3 2-6 Rev. 1 April 1, 1987.

RELIEF REQUEST NO. SR-002

I. 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.

Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addendum, 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 i~accessibility of the subject weld.

II. BASIS FOR RELIEF The fabrication of these welds precludes any type of surface 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

Note:

A surface examination on the fillet weld of the reinforcement pads will be performed.

This relief request has been modified as requested by letter from Lester S. Rubenstein dated January 24, 1986 S2-002-3 2-7 Rev. 1 April 1, 1987

RELIEF REQUEST NO. SR-003

I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The configuration of the Reactor Coolant branch nozzle wel_ds precluded complete examination.

connection Section XI of the ASME Boiler and Pressure Vessel 'Code, 1980 Edition through the Winter 1980 Addendum, requires a volumetric and surface examination of' branch pipe connecti.on 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 examations on these welds will be performed to the extent practical.

tfote: This relief request was granted by letter from Mr. Lester S. Rubenstein dated January 24, 1986 and is included for reference and information only .

SZ-002-3 2-8 Rev. 1 April 1, 1987

RELIEF REQUEST NO. SR-004

I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The Reactor Coolant Filter has three circumferential to examination.

welds subject Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addendum, 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 examinations will be performed in lieu of the volumetric examination.

Note: This relief request was granted by letter from Mr. Lester S. Rubenstein dated January 24, 1986 and is included for reference and information only .

. I S2-002-3 2-9 Rev. 1 April 1, 1987

RELIEF REQUEST NO. SR-005

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. Additionally the 1 foot intersecting longitudinal weld is also inaccessible.

Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addendum, requires a volumetric - examination for both the circumferential and longitudinal welds (Category B-B).

Relief is requested from this requirement due to the physical inaccessibility of the welds.

II. BASIS FO~ RELIEF The shell to top head circumferential weld and intersecting longitudinal weld are inaccessible for either a volumetric or surface examination due to interference .from the insulation support ring. The insulation support _ring covers weld #7 entirely.

Inspection of the intersection of longitudinal weld #2 with weld #7 is prevented by a support column. (see attached drawings).

III. ALTERNATE PROVISIONS

NOTE:

A visual (VT-2) examination for evidence performed during system pressure tests.

of leakage will In reference to the letter written 1/24/86 by Lester S. Rubenstein to W. L .1 Stewart, relief request SR-5 was denied because inadequate information was submitted. This relief request is now being be resubmitted, providing the necessary information. In addition to the problem with weld #7 mentioned in the first request, inaccessibility to weld #2 has also been discussed in this revised*

relief request .

S2-002-3 2-10 Rev. 1 April 1, 1987

ILLUSTRATIVE ONLY

V I R- 21 0 0 PRE:..SSUFff 'tR.-.e~ 10-~0-(j_b Rev. 1 2-12 April 1, 1987

PAGE ..£.OF _g_
f w£L o 4;0. 2
.I INSULATION ,
.SUPPORT 1 f\lNG- - '
., __ - PORV 8"
SUPPORT
,a* . " 18 ..
WHO IN !PEC. TION AREA SE.C.TION A-A SUPPORT RING-PRE SSUR I 'lER SECTJON B - B SURRY POWER STATION PRESSURIZER WELD UT INTERFERENCE UNIT 2 DRAWN BY: ENGINEER~ DATE:
Ylflf .e~ ,o-;ie:,~§6 Rev. 1 2-13 April-1, 1987
RELIEF REQUEST NO. SR-006 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The reactor vessel at Surry has six nozzle-to-safe end butt welds.
The Code currently specifies in Table IWB-2500-1 (Category B-F Item BS.10) that a volumetric and a surface examination of the outside diameter (OD) be performed.
II. BASIS FOR RELIEF The OD surface examination would require a significant amount of time for the removal of interference and shielding materials, surface preparation, and examination. High radiation exposures would be expected should this examination be performed.
III. ALTERNATE PROVISIONS Alternately it is requested that a full volumetric examination from the inside diameter (ID) be accepted in lieu of the surface examination from the OD. A full volumetric examination from the ID of a Surry calibration block has demonstrated sensitivity adequate to resolve a 5% notch on-the OD. Additionally, a flaw, which is an estimated eig~ty percent of the critical flaw as described in ASHE Section XI IWB-3000 Acceptance Standard for Flaw Indications, has
been induced interface.
into a mock-up block. This flaw has been satisfactorily detected and distinguished from the bimetallic Demonstration of both capabilities at the Westinghouse Waltz Mill Calibration Facility have been found acceptable by the Authorized Nuclear Inservice Inspector.
Note: This relief request was granted by letter from Lester S. Rubenstein dated October 29, 1986 and is included for reference and information only .
S2-002-3 2-14 Rev. 1 April 1, 1987
RELIEF REQUEST NO. SR-007
. I. IDENTIFICATION OF COMPONENTS AND It~RACTICAL. CODE REQUIREMENTS The Code requires that the nozzle inside radius section of Category B-D and C-B nozzles on the steam generator and pressurizer must be examined volumetrically in accordance with subsections IWB-2500 and IWC-2500 during each inspection interval. Categories B-D and C-B include nozzl~s with full penetration welds to the vessel shell (or head) and integrally cast nozzles, but exclude manways and handholes either welded to or integrally cast in the vessel. If the examinations are conducted from inside the component and the nozzle weld is examined by stra~ght beam ultrasonic method from the nozzle bore, the remaining examinations required to be conducte~ from the shell may be performed at or near the end of each inspection interval.
Relief is requested from the volumetric examination requirements of the nozzle inner radii for the steam generator and pressurizer nozzles.
II. BASIS FOR RELIEF Relief from examining the Code required volume is requested based upon the following criteria:
1) Nozzles in the pressurizer and steam generators contain inherent geometric constraints and clad inner surfaces which limit the ability to perform meaningful volumetric (UT) examinations of the inner radii areas. The pressurizer surge line nozzle I.D.
is physically restricted by the sparger, the thermal sleeve, and heater bank interierences. The steam generator main steam nozzles are physically restricted by the flow limiting devices.
2) Presently, there is no comprehensive examination technique, or guidance for such in the ASME Code, which would provide a conclusive assessment for the Code required volumetric examinations of these inner radii, particularly since no preservice results are available for review *
. 3) Radiography (RT) is not a viable examination technique due to the same inherent geometric constraints and accessibility limitations that restrict the effectiveness of the ultrasoni~
examination method. In addition, high radiation levels on primary system nozzles would expose radiographic film, causing it to "fog" beyond acceptable standards
S2-002-3 2-15 Rev. 1 April 1, 1987
RELIEF REQUEST SR-007 (CONT'D)
III. ALTERNATE PROVISIONS
1) All five (5) pressurizer upper head nozzles shall be visually examined from the I.D. using direct or remote techniques when accessible prior to the end of the inspection interval. Two nozzles were examined during the 1986 refueling outage.
2) The lower pressurizer nozzle was visually examined from the O.D.
following the 1986 refueling outage after the unit was restarted and reached normal operating pressure and temperature.
3) Category B-D, primary inlet and outle't nozzles on one steam generator were visually examined from the I.D., using manual or remote techniques during the 1986 refueling outage. The other two steam generators will be examined sequentially during upcoming inspection periods, prior to the end of the inspection interval.
4) The steam generator feedwater nozzle thermal sleeve restricts access to the inside radius area of the nozzle. A visual examination of the accessible areas of the inside radius was performed during the 1986 refueling outage for one steam generator and will be performed prior to the end of the inspection interval for the other two steam generators.
5) The flow limiting device installed in the steam generator main steam nozzle restricts access to the nozzle inside radius area.
One main steam nozzle was visually examined from the O.D.
following the 1986 refueling outage after the unit had restarted and reached normal operating pressure and temperature. The remaining two main steam nozzles will be inspected as above prior to the end of the inspection interval.
Note: This relief request was submitted by letter dated April 24, 1986 to Mr. Harold R. Denton and was approved by NRC letter dated June 27, 1986 .
S2-002-3 2-16 Rev. 1 April 1, 1987
RELIEF REQUEST NO: SR-008
I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The code requires that the steam generator nozzle-to-safe end welds and pipe-to-safe end welds in Category B-F be examined volumetrically ahd by surface examination each inspection interval in accordance with subsection IWB-2500. A full volumetric examination is not practicable.
II. BASIS FOR RELIEF The steam-generator nozzle-to-safe end welds and pipe-to-safe end welds are limited by the nozzle geometry, surface condition and the limited surface preparation on the pipe side of the weld. The surface on the pipe side of the weld, which is a cast elbow, is machined for a distance of approximately three inches from the edge of the weld. Ultrasonic examination is limited to this machined area of the pipe and weld since the nozzle side is in the rough as-cast-condition.
III. ALTERNATE PRpVISIONS A volumetric examination from the pipe side will be performed to the extent practicable. A surface examination will be performed on one hundred percent of the weld and the base metal on the pipe side .
S2-002-3 2-17 Rev. 1 April 1, 1987
RELIEF REQUEST NO. SR-009
I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The code requires that longitudinal piping welds in Category B-J be examined volumetrically and by surface examination in accordance with subsection IWB-2500 during each inspection interval. A volumetric examination is not practicable.
II. BASIS FOR RELIEF The ninety degree elbows on the crossover leg of the reactor coolant system are fabricated in two halves from austenitic stainless steel castings welded together by the electroslag process. The structure and nature of the electroslag weld in the cast austenitic elbows are such that the material is opaque to ultrasonic transmissions.
Radiography is the only other avilable technique for volumetric examination. Due to the wall thickness, two-inch thick splitter plates, and. high radiation levels, code acceptable double wall radiographs would be virtually impossible to obtain.
III, ALTERNATE PROVISIONS Only a surface examination will be performed on the electroslag welds
S2-002-3 2-18 Rev. 1 April 1, 1987
RELIEF REQUEST NO. SR-010
. I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The code requires circumferential piping welds in Category B-J be.
examined volumetrically and by surface examination in accordance with subsection IWB-2500 during each inspection interval. A full volumetric examination may not be practicable.
II. BASIS FOR RELIEF Limitations from full volumetric examination may occur at geometric discontinuities such as pipe to nozzle welds, pipe to fitting welds, or fitting to fitting welds. Full volumetric examination from the fitting side of a weld would be dependent upon the geometric configuration. Where elbows and tees are concerned, full volumetric examination may not be possible if the intradose prevents complete transducer contact and adequate ultrasonic coupling. No examinations can be performed from the fitting side where a valve and or flange is involved. In these cases, one hundred percent of the weld can be examined volumetrically. In instances where welds occur at fitting to fitting, access restrictions as outlined above occur on both sides of the weld.
III. ALTERNATE PROVISIONS
A volumetric exam'ination will be performed to the in addition to the surface examination .
extent practical S2-002-3 2-19 Rev. 1 April 1, 1987
RELIEF REQUEST NO. SR-011 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIRE}lENTS The code requires bolting greater than two inches in diameter in Category B-G-1 must be examined volumetrically and by visual examination in accordance with subsection IWB-2500 during each inspection interval. A meaningful volumetric examination is not possible.
II. BASIS FOR RELIEF The bolting used in the reactor coolant loop stop valves is ASTM Al93 grade B-8M with a square hex head and a 3/4" hole drilled completely through the stud. Due to the material characteristics of
-both the bolting and the valve body, removal of the- bolting may cause signficant damage to the studs and the valve body. Therefore, disassembly of the bolting soley for the purpose of examination has only a very small potential for increasing plant safety margins and a very disproportionate impact on expenditures of plant manpower and radiation exposure.
III. ALTERNATE PROVISIONS A visual examination of the bolting will be performed in place under tension to the extent required by Category B-G-1
S2-002-3 2-20 Rev. 1 April 1, 1987
RELIEF REQUEST NO. SR-012
I. IDENTIFICATION OF COMPONENTS Al~D IMPRACTICAL CODE REQUIREMENTS The seal water return filter has three circumferential welds subject to examination.
Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addendum, 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.
Note: A similar relief request was granted by letter from Mr. Steven A.
Varga dated January 24, 1984 for the reactor coolant filter .
2-21 Rev. 1 April 1, 1987
RELIEF REQUEST NO. SR-013 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The code requires circumferential piping welds in Category C-F Item Numbers CS.41 and CS.22 be examined volumetrically and by surface examination in accordance with subsection IWC-2500 during each inspec*tion interval. A full volumetric examination may not be practicable.
II. BASIS FOR RELIEF Limitations from full vplumetric examination may occur at geometric discontinuities such as pipe to nozzle welds, pipe to fitting welds, or fitting to fitting welds. Full volumetric examination from* the fitting side* of a weld would be dependent upon- the geometric
_configuration. Where elbows and tees are concerned, full volumetric examination may not be possible if the intradose prevents complete transducer contact and adequate ultrasonic coupling. No examinations can be performed from the fitting side where a valve and or flange is involved. In these cases, one hundred percent of the weld can be examined volumetrically. In instances where welds occur at fitting to fitting, access restrictions as outlined above occur on b6th sides of the weld.
III. ALTERNATE PROVISIONS A volumetric examination will be performed to the extent practical in addition to the surface examination
S2-002-3 *2-22 Rev. 1 April 1, 1987
RELIEF REQUEST NO. SR-014 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The Code gives certain requirements for the eddy current examination of steam generator tubing in Article IV of ASME Section XI and Article 8 (Appendix-I) of ASME Section V.
II. BASIS FOR RELIEF The MIZ-18 digital equipment represents the "state of the art" in eddy current technology and has provent to provide data collectj.on/data acquisition capapbilities that far exceed previous analog equipment such as the MIZ-12 multifrequency equipment. Code Case N-401 allows for the use of digitized collection and storag~ of data in lieu of magnetic tape and strip chart recorders.
III. ALTERNATE PROVISIONS The MIZ-18 data aquisition/data collection system will be utilized for steam generator eddy current examination .
S2-002-3 2-23 Rev. l April 1, 1987
Descriptions of changea between Revision O and Revision 1 for the Surry Unit 2
Inservice Inspection Program for Component Supports are provided below.
page numbers refer to Revision 1.
The Description of Change 3-1 Entire section (1 page) replaced Note that revision bars are not included in Section 3 because the entire Sectiori was replaced .
S2-003-3 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE INSPECTION PROGRAM
FOR COMPONENT SUPPORTS S2-003-3 3-1 Rev. 1 April 1, 1987
3.0 SECTION 3 TABLE OF CONTENTS INSERVICE INSPECTION PROGRAM FOR COMPONENT SUPPORTS
3.1 INTRODUCTION
3.2 SUPPORTS EXEMPT FROM EXAMINATION AND TEST 3.3 SUPPORTS EXAMINATION BOUNDARIES 3.4 INSPECTION SCHEDULE 3.4.1 Inspection Program 3.4.2 Successive Inspection Intervals 3.4.3 Additional Examinations 3.5 EXAMINATION REQUIREMENTS
. 3.6 STANDARDS FOR EXAMINATION EVALUATIONS 3.6.1 Evaluation of Inservice Examination Results 3.6.2 Repairs and Reexaminations 3.6.3 Acceptance Standards 3.7 REPAIR PROCEDURES 3.7.1 Materials 3.7.2 Welding and Welder Qualification.
3.7.3 Examinations 3.7.4 Repairs 3.7.5 Replacements 3.8 RECORDS AND REPORTS 3.8.1 Requirements 3.8.2 Summary Report Submittal 3.8.3 Retention S2-003-3 3-2 Rev. 1 April 1, 1987
3.0 INSERVICE INSPECTIONS PROGRAM FOR COMPONENT SUPPORTS
3.1 INTRODUCTION
This program will provide rules and requirements for inservice inspection, repair and replacement of Class l,~ 2 and 3 component supports in accordance with ASME Section XI, 1980 Edition through Winter 1980 addendum as modified by this program. Component -
supports are those metal supports that are designed to transmit loads from the component and piping to the load carrying building or foundation structures. This shall include the attachment portion of intervening element(s) to pressure retaining components, integral and nonintegral attachments of pressure retaining components, and integral and nonintegral supports. Component supports encompass those structural elements that are used solely to either support the weight of or provide structural stability to components and piping.
All component supports that are within the ASME Section XI piping class boundaries and are within the scope of the Show Cause Order, 79-14, will be included in this program *
NOTE 1: This program does not cover snubbers. Snubbers shall be inspected in accordance with Technical Specifications. The attachments of snubbers to pipes,"walls, vessels, etc. will be covered by the Support Program.
3.2 SUPPORTS EXEMPT FROM EXAMINATION AND TEST The following exemptions are for ASME Classes 1, 2, artd 3 component supports:
3.2.1 Component supports that are outside the scope of the Show Cause Order, . 79-14, are exempt from the preservice and inservice requirements of this support program.
3.2.2 Component and piping supports which are buried, encased in concrete or the portion of the supports which are made inaccessible by the-normal component or piping insulation are exempt from the preservice and inservice requirements of this support program .
S2-003-3 3-3 Rev. 1 Apr_il 1, 19B7
3.3 SUPPORTS EXAMINATION BOUNDARIES The support examination boundaries for both integral and nonintegral supports are shown in Figs. lA & lB. The following definitions apply.
(a) The boundary of an integral attachment (B) connected to a pressure retaining component (A) is the distance from the pressure retaining component (A) as indicated in Figures 2A, 2B, 2C, 3, and 4.
(b) The boundary of an integral support (C) connected to a building structure (E) is the surface of the building structure.
(c) The boundary of a nonintegral support (D) connected to a pressure ret~ining component (A) is the contact surface between the component and the support.
(d) The boundary of a nonintegral support (D) connected to a building structure (E) is the surface of the building structure.
(e) Where the mechanical connection of a nonintegral support is buried within the component insulation, the support boundary may extend from the surface of the component insulation provided the support either carries the weight of the component or serves as a structural restraint in compression *
(f) The examination boundary of 1n intervening element shall include the attachment portion of the intervening element to pressure retaining components, integral and nonintegral attachments of pressure retaining components, and integral and nonintegral supports. The examination boundary does not include the attachment of the intervening element to the building structure.
(g) All integral and nonintegral connections within the boundary governed by Support Programs rules and requirements are included.
NOTE: 'on new supports, the design package will define the examination b_oundaries for the support as above for inspections.
1 Attachment portion includes welds, bolting, pins, clamps, etc
S2-003-3 3-4 Rev. 1 April 1, 1987
3.4 INSPECTION SCHEDULE
3.4.1 INSPECTION PROGRAM All component supports will be inspected over a ten year interval. The 10 year interval shall be divided into inspection periods with minimum and maximum percent of supports to be inspected. After each 10 year interval the sequence will be repeated.
Minimum Maximum Examinations Examinations Inspection Period Completed Completed 0-3 years 16% 34%
4-7 years 50% 67%
8-10 years 100% 100%
The inspection periods specified above may be decreased or extended by as much as 1 year to enable an inspection to coincide with a plant outage. For units that are out of service continuously for 6 months or more, the inspection interval during which the outage OCGurred may be extended for a period equivalent to the length of the outage.
3.4.2 SUCCESSIVE INSPECTION INTERVALS
(a)
(b)
The sequence of component support .examinations established during the first inspection interval shall be repeated during each successive inspection interval, to the extent practical.
When a component support requires corrective measures in accordance with Section 6, that support shall be reexamined during the next inspection period. On Class 1 component supports, the support shall be reexamined during the next three inspection periods.
NOTE: Corrections to nonrelevant conditions shall not apply.
(c) If the reexaminations required by (b) above do not require additional corrective ~easures during the next three successive periods on Class 1 or the next successive period on Class 2 and 3, the inspection schedule may revert to the requirements of (a) above.
3.4.3 ADDITIONAL EXAMINATIONS
. (a) When the results of examinations render a support inoperable which require corrective measures, the examination shall be extended to include additional supports similar in type, design, and function. The additional supports shall include immediately adjacent component supports.
S2-003-3 3-5 Rev. 1 April 1, 1987
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'1e11urt Building ma,n,ng llfUC!Ufl , componem Suooon with or wi1t1out intermed,11* -ld9d join11 Cdl © @ @
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Figure lB
Rev. 1 3-7 April 1, 1987
A
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Rev. 1 April 1, 1987 3-8
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Rev. 1 April 1, 1987
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Rev. 1 3-10 April 1, 1987
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INTEGRAL ATTACHMENT - COMPONENT SUPPORTS CODE CLASS 3 F,igure 4 I
l Rev. 1 L_j__ April 1, 1987
(b) When these additional examinations require corrective measures in accordance with Section 6, the remaining component supports within the system of the same type, design, and function as (a) above shall be examined.
NOTE: Corrections to nonrelevant conditions shall not apply.
(c) Any spring hanger having a setting out-of-specification shall be adjusted to restore the unit within the specification range.
3.5 EXAMINATION REQUIREMENTS Component supports subject to examination shall be examined in accordance with Table 1.
NOTE 1: All integral attachments for Class 1 and 2 pipings, vessels, core support structures interior attachments to
NOTE 2:
reactor vessels removable core support structures are included in the NDE program. The remaining portion of the support will be included in this program.
All integral attachments to containment liner (IWE) will be examined as IWB or IWC of this program dependent on class of system being supported. Repairs on containment liner will be evaluated in accordance with Section 6 and 10CFRSO, Appendix J. If 10% of wall is penetrated, an Appendix J, 10CFRSO Test will be performed .
S2-003-3 3-13 Rev. 1 March 28, 1987
TABLE 1 REQUIREMENTS FOR COMPONENT SUPPORTS EXAMINATION CATEGORIES CAT.
F-A PLATE AND SHELL TYPE SUPPORTS Examination 1
ITEM Parts Requirements/ Examination Acceptance Extent Frequency of NO. Examined Fig. No. Method Standard of Examination Examination Fl.10 Mechanical connections Fig lA,B Visual, VT-3 Section 6.0
Section 2.0 Each inspection to pressure retaining Section 3.o* interval components and building structure Fl.20 Weld connections to Fig lA,B Visual, VT-3 Section 6.0 Section 2.0 Each inspection building structure* Section 3.0 interval Fl.30 Weld and mechanical Fig lA,B Visual, VT-3 Section 6.0 Section 2.0 Each*inspection connections at inter- Section 3.0 interval mediate joints in multiconnected integral and nonintegral supports Fl.40 Component displacement Fig lA,B Visual, VT-3 Section 6.0 Section 2.0 Each inspectior..
settings of guides and Section 3.0 interval stops, misalignment of multiconnected integral supports, assembly of support items NOTE:
(1) Reference IWA-2210.
S2-003-3 3-14 Rev. 1 April 1, 1987
TABLE 1 REQUIREMENTS FOR COMPONENT SUPPORTS EXAMINATION CATEGORIES CAT.
F-B LINEAR TYPE SUPPORTS Examination
.
1 ITEM Parts Requirements/ Exam1nat1on Acceptance Extent Frequency of NO. Examined Fig. No. Method Standard of Examination Examination F2.10 Mechanical connections Fig lA,B Visual, VT-3 Section 6.0 Section 2.0 Each inspection to pressure retaining Section 3.0 interval components and building structure F2.20 Weld connections to Fig lA,B Visual, VT-3 Section 6.0 Section 2.0 Each inspection building structure Section 3.0 interval F2.30 Weld and mechanical Fig lA,B *Visual, VT-3 Section 6.0 Section 2.0 Each inspection connections at inter- Section 3.0 interval mediate joints in" multiconnected integral and nonintegral supports F2.40 Component displacement Fig lA,B Visual, VT-3 Section 6.0 Section 2.0 Each inspection settings of guides and Section 3.0 interval stops, misalignment of multiconnected integral supports, assembly of support items NOTE:
(1) Reference IWA-2210.
S2-003-3 3-15 Rev. 1 April 1, 1987
TABLE 1 REQUIREMENTS FOR COMPONENT SUPPORTS EXAMINATION CATEGORIES CAT.
F-C LINEAR TYPE SUPPORTS Examination 1
ITEM Parts Requirements/ Examination Acceptance Extent Frequency of NO. Examined Fig. No. Method Standard of Examination Examination F3 .10 Mechanical connections Fig lA,B Visual, VT-3 Section 6.0 Section 2.0 Each inspection to pressure retaining Section 3.0 interval components and building structure F3.20 Weld connections to Fig lA,B Visual, VT-3 Section 6.0 Section 2.0 Each inspection building structure Section 3.0 interval F3.30 Weld and mechanical Fig lA,B Visual, VT-3 Section 6.0 Section 2.0 Each inspection connections at inter- Section 3.0 interval mediate joints in multiconnected integral and nonintegral supports F3.40 Component displacement Fig lA,B Visual, VT-3 Section 6.0 Section 2.0 Each inspection settings of guides and Section 3.0 interval stops, misalignment of multiconnected integral
supports, assembly of support items F3.50 Spring type Supports, Fig lA,B Visual, VT-i Section 6.0 Section 2.0 Each inspection constant load type Section 3.0 interval supports NOTE:
(1) Reference IWA-2210.
(2) See Relief Request SH-001.
S2-003-3 3-16 Rev. l April 1, 1987
3.6 STANDARDS FOR EXAMINATION EVALUATION 3.6.1 EVALUATION OF INSERVICE EXAMINATION RESULTS 3.6.1.1 Inservice examinations performed during or at the end of successive inspection intervals to meet the requirements of Table 1, and conducted in accordance with the procedures of Section 4 shall be evaluated by comparing the results of examinations with the evaluation standards specified in Section 6.3.
3.6.1.2 ACCEPTANCE 3.6.1.2.1 Acceptance by Examination Component supports whose examination reveals no unacceptable conditions listed in 6.3.1.a shall be accep~able for continued service.
3.6.1.2.2 Acceptance by Evaluation If unacceptable conditions are discovered by examinations performed as specified in Table 1, an engineering evaluation shall be performed in accordance with ASME XI Appendix A, . 1980 Edition through winter 1980 addendum, as modified by this program to determine if the component that contains these indications shall be acceptable for continued service.
3.6.1.2.3 Acceptance by Repair Components that contain unacceptable conditions and have been evaluated to be unacceptable for service shall be repaired prior to returning the component to service.
3.6.2 REPAIRS AND REXAMINATION Repairs and reexaminations shall comply with the requirements of Section 7. Reexaminations shall be conducted in accordance with the requirements of Section 4 and the recorded results shall demonstrate that the repair meets the acceptance standards of Section 6.3.
3.6.3 ACCEPTANCE STANDARDS 3.6.3.1 Acceptance Standards - Component Support Structural Integrity S2-003 3-17 Rev. 1 April 1, 1987
(a) Component unacceptable support for include the following:
(1) conditions which continued service shall Deformations or structural degr~dations of fasteners, springs, clamps or other are support items.
(2) Missing, detached or loosened support items.
(3) Arc strikes, weld spatter, paint, scoring 1 roughness or general corrosion on ~lose tolerance machined or sliding surfaces.
(4) Improper hot or cold positions (spring supports).
(b) Except as defined in (a) above, the following are examples of nonrelevant conditions:
(1) Fabrication marks (e.g., from punching, layout, bending, rolling, and machining).
(2) Chipped or discolored paint *
(3) Weld spatter on other than close tolerance machined or sliding surfaces.
(4) Scratches and surface abrasion marks.
(5) Roughness or general corrosion which does not reduce the load bearing capacity of the support.
(6) General conditions acceptable by the material, design, and/or construction specifications.
(c) Component supports, whose examinations reveal conditions as defined in (a) above, shall be repaired or replaced in accordance with the*
station's Repair and Replacement Program.
3.6.3.2 ACCEPTANCE STANDARDS FOR BOLTING 3.6.3.2.1 Support bolting shall be acceptable for continued service upon completion of an acceptable (passing) visual (VT,-3) examination
S2-003 3-18 Rev. 1 April 1, 1987
)
3.7 REPAIR PROCEDURES 3 . 7. 1 Yi.ATERIALS Material shall conform to the requirements of original Des.:._gn Specification or ASME Section III. All material will be Category I as per NODSM.
3.7.2 WELDING AND WELDER QUALIFICATION The welding procedures and the welders shall be qualified in accordance with ASME Section IX.
3.7.3 EXAMINATIONS Examinations shall be performed in accordance with rules of Section 6.3 of this procedure and the Non-Destructive Examination Manual for Surry.
3.7.4 REPAIRS All repairs will be performed to ensure the support is left in the same condition of original design, or an evaluation will be performed to ensure all design and ASME Section XI IWA-4000 requirements are met *
3.7.5
~
Replacements All replacements will be per original design specification or an evaluation will be performed to ensure all design and ASME Section XI IWA-7000 requirements are met.
3.8 RECORDS AND REPORTS 3.8.1 REQUIREMENTS 3.8.1.1 Virginia Electric and Power Company will prepare plans and schedules for inservice examinations and tests.
3.8.1.2 Virginia Electric and Power Company shall prepare a sunnnary report. As a minimum, the report will include:
(1) Numbers assigned to the components by the State, Municipality, or Province; (2) National Board Numbers assigned to the components by the manufacturer, where
.- applicable; S2-003 3-19 Rev. 1 April 1, 1987
(3) Name of the components and descriptions,
(4) including size, capacity, material, location, and drawings to aid identification; Name and applicable; address of manufacturers, where (5) Manufacturer's component identification numbers, where applicable; (6) Date of completion of the examination, test, replacement, or repair; (7) Name of Inspector who witnessed or otherwise verified the examinatjons, test, replacements, or repairs, and the Inspector's employer and business address, when required.
(8) Abstract of examinations, test, replacements, or repairs performed; conditions recorded; and corrective measures recommended or taken; (9) Signature of .Inspector, when required; (10) Owner's Data Report for inservice inspection, Form NIS-1
(a) Plans, schedules, records, and summary reports shall have a cover sheet providing the following information:
(1) date of document completion (2) name and address of Owner (3) name and address of generating plant (4) name or number designation of the unit (5) commercial operating date for the unit.
3.8.2
SUMMARY
REPORT SUBMITTAL Within 90 days of the completion of the inservice inspection conducted during a refueling outage, Virginia Electric and Power Company shall file inservice inspection summary reports for Class 1 and 2 supports with the enforcement and regulatory authorities having jurisdiction at the plant site.
3.8.3 RETENTION 3.8.3.1 Maintenance of Records Virginia Electric and Power Company shall retain records and reports for Class 1, 2 and 3 supports.
The records and reports shall be filed and maintain in a manner which will allow access by the Inspector. All records will be maintained for life of the plant.
S2-003 3-20 Rev. 1 April 1, 1987
3.8.3.2 Reproducing and Microfilming Records Management and Station Quality Assurance Department shall include a system of monitoring the accuracy of the reproduction process so that when the microfilm is projected to the original size it will provide the same information retrieval capability as the original. The accuracy of the reproduction process includes* the exposure (or multiple exposures for density coverage), focusing, contrast, and resolution. The Quality Assurance Program shall also provide a system for identifying film artifacts that might appear as material discontin~ities in the reproduction.*
S2-003 3-21 Rev. 1 April 1, 1987
Descriptions of changes between Revision O and Revision 1 for the Surry Unit 2 Pump and Valve Inservice Test Program are provided below. The page numbers refer to Revision 1.
Description of Change 4-2 The Section has been renumbered.
Section 4.2, "PROGRAM DESCRIPTION", has been deleted.
Old Section 4.3, "Reports to Regulatory Agencies", has been deleted.
Old Section 6. 0, "Piping and Diagrams'-', has been deleted.
4-3 References to Pump and Valve classes and code edition were deleted. This information is given on the following page.
4-6 The word "shall" was replaced by "should" in Sections 4.3.2 d) and e).
The word "administrative" was deleted.
Surry Unit 2 is currently in the second inspection interval.
The verb tense in Section 4.3.3 has been changed accordingly.
4-7 Drawing 11548-FM-84A was replaced by 11548-FM-84B for Pumps 2-RS-P-lA, lB, 2A and 2B.
4-8 Pump numbers EE-P-B, C and E were changed to 1-EE-P-lB, lC and lE.
4-8 Section 4.3.5 was expanded to explain the pump table and 4-9 headings 'and abbreviations.
4-10 NR (not required) *was replaced by NA (not applicable) throughout the Pump Inservice Test Table.
Relief Request 12 was added to Pumps 2-SI-f-lA and lB, 2-RS-P-2A and 2~, and 2-RH-P-lA and 2B.
Measurement of flow in Relief Request 4 was withdrawn from Pumps 2-RS-P-2A and 2B.
Relief Request O was deleted from Pump 2-FW-P-2 (pump speed is being measured).
The note (*) was deleted from the bottom of the page.
4-11 Relief Request 14 was added to Pumps I-CC-P-lC and lD.
Relief Request 12 was added to Pumps l-CH-P-2C and 2D.
Relief Request 13 was added to and Relief Request 10 withdrawn from Pumps 2-CC-P-2A and 2B, and 2-SW-P-lOA and lOB.
S2-4-DES April 1, 1987
Description of Change
4-11 In the columns for Inlet Pressure, Differential Pressure and Lubrication, Q (quarterly *testing) was replaced by NA for Pumps 1-EE~P-lB, lC and lE to accurately reflect the contents of the relief request.
Class 3 was replaced by NC (non-class) for Pumps l-EE-P-1'B, lC and lE.
The notes (*and**) were deleted from the bottom of the page.
4-12 Editorial change.
4-13 The format of the pump Relief Requests was changed to a format.similar to the valve Relief Requests ..
4-14 The Basis for Relief was reorganized to enhance clarity.
4-16 The allowable ranges of vibration velocity were changed.
4-17 The proposed installation date for flow instrumentation was deleted and a note was added.
4-18 References to lubrication level and pre$sure were deleted and a note was added .
4-19 Request for Relief from measuring flow has been withdrawn, and a note was added.
4-20 Technical detail was added to the Basis for Request .
4-21 The proposed installation date for flow instrumentation was deleted, and a note was added.
4-22 Reference to lubrication level or pressure was deleted.
The sentence, "These pumps are not engineered safety feature pumps", was deleted.
4-24 Reference to lubrication level was deleted.
The alternate testing method has been rewritten, the proposed installation date for flow instrumentation deleted, and a note was added.
4-25 Relief Request 10 has been withdrawn.
4-26 Pump numbers changed from EE-P-lB, lC, lE, to 1-EE-lB, lC, lE.
Reference to lubrication level or pressure was deleted
The sentence, "Hence all testing of these voluntary", was deleted from the Basis For Relief.
pumps is S2-4-DES April 1, 1987
Description of Change 4-26 The Alternate Testing Proposed was changed and a note was added.
4-28 Relief Request 12 has been added.
4-29 Relief Request 13 has been added.
4-30 Relief Request 14 has been added.
4-31 The paragraphs on leak rate testing were rewritten.
The paragraph on stroke times of solenoid controlled, air operated valves was rewritten.
4-33 Surry Unit 2 is currently in the second inspection interval.
The verb tense has been changed accordingly.
Reference to a traini,ng program was -deleted.
11 11 The designation for non-class valves was changed from - to "NC!'.
The sentence, "Valves marked- with an "E" are passive valves.", was added .
4-34 4-35 References to fail-safe tests were added.
Valve Numbers S0V-MS-202A and B were replaced by PCV-MS-202A and B.
A fail-safe (FS) test was added to Test Required for Valves PCV-MS-202A and B.
Valve Type "GA" was added to Valve HCV-MS-204.
Valves NRV~MS-202A B, and C were added.
4-36 Relief Request 34 has been added to Valve TV-MS-210.
The Drawing Locations for Valves 2-MS-176, 178 and 182 were changed.
4-37 Drawing Locations were changed for Valves TS-SV-202A and 2-VP-12.
Category for 2-VP-12 was changed from AC to ACE.
4-39 The Drawing Number was changed from 11548-FM-:68B to 11448-FM-68B *
Drawing Locations for valves on this page were changed.
The Function description for Valves 2-FW-272, 273, 305 and 306 were rewritten, and the Class of these valves was changed from "3" to "2".
S2-4-DES April 1, 1987
Description of Change 4-40 The System Name was changed.
Relief Request 6 has been withdrawn from Valves MOV-SW-203A, B, C and D.
The Size of Valves MOV-SW-202A, B was changed from "42" to "10".
4-41 The System Name was changed.
The Drawing Locations for Valves MOV-SW-201A, B were changed.
The Code Class for Valves MOV-CW-200A, B, C and D was changed "from*"3" to "NC".
The Code Class and Category for Valves 2-SW-206 and 208 were changed from "2" and "A" to "3" and "AE".
4-42 The Draw_ing Locations for Valves 2-cc.:.764, 329, and 2-SW-113, 108 were changed.
4-43 The Code Classes for Valves 2-CC-176, 177and 2-CC-l, 58, 59 were changed from "2" to "3" *
4-44 The Valve Sizes "l" to "l 1/2".
for RV-CC-216A, Band C were changed from The Valve Size for RV-CC-218 was changed from "1" to "3/4".
The Code Classes for Valves 2-CC-242, 233 and 224 were changed from "2" to "3".
4-45 The Drawing Number was changed from 11548-FM-72D to 11448-FM-72D.
The Drawing Locations were changed.
Thermal Relief Valves RC-CC-209 and 210 were deleted - from the program and the page that followed 4-45 was deleted.
Thermal Relief Valves are not subject to Section XI Testing.
4-46 The Drawing Number was changed from 11548-FM-72F to 11448-FM-72F.
The Code Class was changed from "2" to "3" for valves on this page.
Relief Request 34 was added to Valves TV-CC-205A, B, C*
TV-CC-207 and TV-CC-209A, B. '
The Valve Type was .changed from "BU" to "BF" for Valves TV-CC-209A, B, and TV-CC-210A, Band C.
Test Type FS was added to valves TV-CC-209A and B.
S2-4-DES Rev. 1 April 1, 1987
Page* Description of Change
4-48 The categories for Valves.2-SA-81 and 82 were. changed from "A" to "AE" and the valve type was changed from "GA" to "GL I I .
4-49 The Drawing Locations for Valves TV-IA-200, 1-IA-704 and 2-IA-704 were changed.
The *Size for valves TV-IA-201A, B was changed from "3" to "2".
Relief Request 34 was added to Valves TV-IA-201A, B and TV-IA-200.
The Category for Valves 1-IA-704 and 2-IA-704 was changed from "A" to "AE".
Note that the valves on page 14 of Revision 0 were moved from drawing 11548-FM-75C to 11548-FM-75J and that they now appear on page 4-53 of Revision 1.
4-50 The Drawing Number was changed from 11548-FM-82B to 11548-FM-82A.
Relief Request 34 was added to the valves on this page .
4-51 Category and Actuator Type were changed from "A" and "PN" to "AE" and "Man" for Valve 2-VA-1.
Relief Request 34 was added to the valves on this page except for 2-VA-1.
The Normal Position for Valve TV-VG-209B was changed from "C" to "O".
4-52 Drawing Number 11548-FM-83B was added.
The Valve number TV-DC208A was changed to TV-DG208A.
Size for Valve TV-VG209A was changed from "2" to "1 1/2".
Category and Normal Position for Valve 2-VA-9 were changed from "A" and "O" to "AE" and "C".
Relief Request 34 was added to valves on this page except for 2-VA-9.
4-53 Valves on this page were moved from drawing 11548-FM-84B to 11548-FM-84A.
~
The Drawing Locations for valves on this page were changed .
S2-4-DES Rev. 1 April 1, 1987
Description of Change
4-53 The Category for Valves 2-CS-105, 104 was changed from "AC" to 11 C".
The Valve Type and Normal Position for Valves MOV-CS-203A~
B, C and D were changed from "BF" and "O" to "GA" and "C".
4-54 The System Name was changed.
The Drawing Locations for valves on this page were changed.
The Valve Type for Valves MOV-RS-256A, B was changed from "GA" to "BF".
4-55 The Normal Position for Valves TV-LM-200A to H was changed from "C'r- to "O".
The Category for Valves HCV-CV-200 and 2-CV-2 was changed from "A" to "AE".-
Relief Request 34 was added to Valves TV-LM-200A to H and TV-CV-250A to D.
4-56 The Category and Valve Type for Valves HCV-2556A, B, C were changed from "A" and "GA" to "AE" and "PL" .
The Code Class for Valves S0V-RC-200B-1,-2 was changed form "1" to "2".
The Actuator Type for Valves S0V-RC-200A-l,-2 and S0V~RC-200A-1,-2 and S0V-RC-200B-1,-2 was changed from "PN" to "SOV" and "GA" was added to Valve Type.
4-57 Valve Number 2-RC-160 was changed to 2-PG-20.
The Valve -Type for Valves PCV-2456 and 2455C was changed from "GA" to "PL" and Relief Requests 34 and 35 were added.
Valve Numbers SOV-201-A-1,-B-1, -A-2 and -B-2 were changed to S0V-RC-201A-l,-2, and S0V-RC-201B-1,-2.
Valve Type "GA" was added to Valves S0V-RC-201A-1,-2 and S0V-RC-201B-1,-2 and actuator type was changed from "PN" to "SOV.
Test Type FS was added to valves PCV-2456 and 2455C.
4-58 Size for Valves MOV-2700 and 2701 was changed from "4" to "14".
Category for Valve MOV-RH-200 was changed from "A" to "AE" .
4-59 The Drawing Number was changed from 11548-FM-88A to 11448-FM-88A.
S2-4-DES Rev. 1 April 1, 1987
Description*of Change 4-60 Code Class for Valve MOV-2381 was changed from "2" to "1".
Relief Request 34 was added to Valve TV-2204.
Size for Valve RV-2209 was changed from "3" to "2".
4-61 Size for Valves MOV-:-2289-A,B was changed from "4" to "3".
Class for Valve FCV-2160 was changed from "1" to "2".
Category for Valve FCV-2160 was changed from "A" to"AE" and the stroke test EV was deleted.
The Valve Type for Valve FCV-2160 was changed from "GL" to "GA".
4-62 Relief Request 34 was added to Valves HCV-2200A, B, C.
Code class and category for Valve RV-2382A were changed from "1" and "AC" to "2" and "C", and reference to Relief Request 30 was deleted.
The size for Valve 2-CH-309 was changed from "4" to "3".
4-63 Drawing Locations for Valves MOV-2862B; MOV-2885A, B, C, D; and 2-SI-61, 53 were changed.
The Valve Number 2-SI-43 was changed to 2-SI-327.
4-64 Category for Valves MOV-2864A, B was changed from "A" to "B" and the test "LT*" was deleted.
Type for Valves RV-2845A, B, C was changed from "VE" to "RV".
Valves MOV-2867A, B were deleted and Relief Request 25 was withdrawn.
4.:..65 Valves TV-2884A, B, C and RV-2857B were deleted.
The Code Class for all valves on this page was changed from
"-" to "2".
Relief Request 34 was added to Valve TV-SI-200.
Category for Valves 2-SI-150 and 174 was changed from "A" to II AE".
Size and Normal Position for Valve 2-SI-150 were changed from *11 111 and "C" to "3/4" and "O".
Valve Type for Valve 2-SI-174 was changed from "GA" to "GL".
S2-4-DES Rev. 1 April 1, 1987
Description of Change
4-71 4-72 Relief Request 34 was added to valves on this page.
Drawing Locations were changed for valves on this page.
The Drawing Number was changed from 11548-SPS-14A to 11448-SPS-14A.
Relief Request 34 was added to Valves TV-RM-200A, Band C.
4-73 The Drawing Number was changed from 11548-FB-4B to 11448-FB-4B, Drawing Locations for valves on this page were changed.
The Code Class and Actuator Type were change from "3" and "PN" to *11 NC" and "SOV" for the valves on this page.
Relief Request 36 was added and test "VP" was deleted.
4-74 Category was changed from ",A to "AE" for the valves on this page.
11 Size for Valve MOV-VS-202 was changed from 8 11 to "18".
Size, Valve Type and Actuator Type for Valve MOV-VS-201 were change'd from "4", "GA" and "Man" to 11 8 11 , "BF" and "MOV".
Drawing Locations were changed for the valves on this page.
4-75 Valves S0V-EG-200A, B on Drawing 11448-FB-46B were added along with Relief Request 37.
4-76 Valves 2-FP-151 and 152 were placed on Drawing 11448-FB-47B.
Drawing Locations and Size were added.
Code' Class and Category were changed from "2" and "A".to "3" and "AE".
4-78 Relief Request 1 was reformatted to be consistent with other Relief Requests.
4-79 Valves RV-CC-211A, Band RV-CC-209, 210 were deleted from Relief Request 1.
Valve Number RV-1721 was change to RV-2721.
4-80 Class 'for RV-2382A was changed from "l" to "2".
Valve RV-2857 was deleted from Relief Request 1 *
4-83 Valves NRV-MS-202A, B, and C were added to Relief Request_
3.
Editorial change.
S2-4-DES Rev. 1 April 1, 1987
Description of Change
4-84 Valve 273.
numbers 2-FW-309 and 310 were changed to 2-FW-272 and Class for Valves 2-FW-272, 273, 305 and 306 was changed from "3" to "2" and the Function Description was rewritten.
4-85 Technical detail was added to the basis for relief.
The test frequency was changed from every cold shutdown to every reactor refueling.
4-86 Relief Request 6 has been withdrawn.
4-87 Editorial change.
4-88 Class for Valves 2-CC-176, 177 changed from "2" to "3".
4-89 Editorial change.
4-90 Class changed from "2" to "3" for valves on this page.
4-91 Editorial change.
Technical detail added to the Basis For Request *
4-92 4-93 Valve Number 2-RC-160 was changed to 2-RC-20.
The C~de Ciass of Valve 2-RC-20 was changed from "2" to "3".
Valve Number 2-CS-127 was changed to 2-CS-104.
The Category Description was expanded to enhance clarity.
4-96 Technical detail was added to the Basis for Request.
4-98 Editorial change.
4-99 Technical detail was added to and valve numbers corrected in the Basis for Request.
4-100 The Code Class was changed from "2" to "1".
4-102 The Category for MOV-2289B was changed from "A" to "B".
4-104 Editorial changes.
4-105 Valve Number 2-SI-43 changed to 2-SI-327.
4-106 Technical Specification reference changed from 3.3.A.9 to 3.3.A.8 .
Editorial changes.
S2-4-DES Rev. 1 April 1, 1987
Description of Change
4-108 4-109 The Basis for Request was changed from reference to flow blockage due to boron crystallization to excess charging flow causing a reactivity transient.
Relief Request 25 has been withdrawn.
4-110 Category was changed from "C" to "A and C".
Editorial change was made to the Basis for Request.
4-111 Editorial*changes.
4-112 Class for Valves 2-SI-226, 227 was corrected from "2" to "l".
4-115 Relief Request 30 was reformatted to be consistent with the other Relief Requests.
4-116 Valve Numbers HCV-2256A, B, C were changed to HCV-2556A, B, c.
Valves 2-SI-241, 242, 243 were added.
Valve RV-2382A was deleted *
4-119 4-120 Valves 2-SI-235, 236, 237 were deleted.
Relief Request 33 has been added.
Relief Request 34 has been added.
and 121 4-122 Relief Request 35 has been added.
4~123 Relief Request 36 has been added.
4-124 Relief Request 37 has been added.
S2-4-DES Rev. 1 April 1, 1987
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INSERVICE TESTING PROGRAM PLAN FOR PUMPS AND VALVES S2-0u4a 4-1 Rev. 1 April 1, 1987
SECTION 4 TABLE OF CONTENTS 4.0 INSERVICE TESTING PROGRAM PLAN FOR PUMPS AND VALVES
4.1 INTRODUCTION
4.2 PROGRAM DESCRIPTION 4.3 PUMP INSERVICE TEST PROGRAM DESCRIPTION 4.3.1 .Program Development Philosophy 4.3.2 Program Implementation 4.3.3 Program Administration 4.3.4 Pump Reference List 4.3.5 Pump Inservice Test Tables 4.3.6 Pump Test Program Relief Request 4.4 VALVE INSERVICE TEST PROGRAM DESCRIPTION 4.4.1 Program Development Philosophy 4.4.2 Program Implementation 4.4.3 Program Administration 4.4.4 Valve Inservice Test Table 4.4.5 Valve Test Program Relief Request 4.5 REPORTING OF INSERVICE TEST RESULTS 4.5.1 Pump Inservice Program 4.5.2 Valve Inservice Program 4.6 QUALITY ASSURANCE PROGRAM S2-004a 4-2 Rev. 1 April 1, 1987
4. 0 IN SERVICE TESTING PROGRAJ:vl PLAN FOR PUMPS AND VALVES
4.1 INTRODUCTION
This Pump and Valve Inservice Test Program Plan is applicable to_
the Surry Power Station Unit 2. This program plan is comprised of two independent subprograms - the Pump Inservice Test Program and the.../Valve Inservice Test Program. The development, implementation and administration of these two programs are detailed in subsequent sections
S2-004a 4-3 Rev. 1 April 1, 1987
4.2 PROGRAM DESCRIPTION -
This Inservice Testing Program for ISI Class 1, 2, 3 and NC pumps and valves meets the requirements of Subsections IWP and 11~1 of Section XI of the ASME Boiler and Pressure, Vessel Code, 1980 Edition through the Winter 1980 Addendum.* Where these requirements are determined to be impractical, specific requests for relief have been ¥ritten and included in the program plan attached .
S2-004a 4-4 Rev. 1 April 1, 1987
4.3 PUMP INSERVICE TEST PROGRAM DESCRIPTION
4. 3 .1 PROGRAM DEVELOPMENT PHILOSOPHY Highly reliable safety-grade equipment is consideration in the operation of a nuclear generating a vital station. To help assure operability, the Surry Power Station Unit 2 Pump Inservice Test Program has been developed.
The Program is designed to detect and evaluate significant hydraulic or mechanical changes in the operating parameters of vital pumps and to initiate corrective action when necessary. The Program is based on the requirements of the ASME Boiler and Pressure Vessel Code (B&PV), Section XI, Subsection IWP. To the maximum extent practical, the Program complies with the specifications of the ASME B&PV Code, Section XI, Subsection IWP, 1980 Edition with Addendum through Winter of 1980; 10CFR50.55a(g); and NRC Staff guidelines for complying with certain provisions of 10CFR50.55a(g) "Inservice Inspectfon Requirements."
The Nuclear . Regulatory Commission and Code Committee recognizes that design differences among plants may render impractical certain Code requirements. Where such impracticalities exist, they have been substantiated as exceptions as allowed by the Code. Alternate testing requirements have been proposed when warranted.
4.3.2 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 Unit 2 Inservice Test
(_
Program provides a schedule for testing safety-grade pumps and will be implemented as part of normal periodic surveillance testing.
Referen~e data will be gathered during initial surveillance test. In most cases, test parameters will be measured with normal plant instrumentation. This approach will simplify the t~st program and will promote timely completion o,f 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 th~ reference flow rate. Other hydraulic and mechanical performance parameters will be measured and evaluated against the appropriate reference values. The results of such evaluations will determine whether or not corrective action is warranted.
S2-004a 4-5 Rev. 1 April 1, 1987
Each pump in the Pump Inservice 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 should be included in the main body of the procedure as appropriate and should be identified as such.
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 should 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 acceptabl.e will be established and included in the test procedure. In the event that data fall outside the acceptable range, operator action will be governed by approved station procedures.
Finally, it is recognized that the Pump Inservice Test Program sets forth minimum testing requirements.
Additional testing will be performed, as required, after pump maintenance or as determined necessary by personnel at Surry Power Station.
4.3.3 PROGRAM ADMINISTRATION The operations and engineering staff at Surry Power Station
' are responsible for administration and execution of the Pump Inservice Test Program. The Program was officially implemented on May 1, 1983 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 CFR50.55a(g)(4). The Program will be updated a minimum of at least once every 40 months for new systems, relief request, etc.
S2-004a 4-6 Rev. 1 April 1, 1987
4.3.4 PUMP REFERENCE LIST This list gives a brief description of each pump identified in the Pump Test Program. The pump's ASME Code Classifications are specified in "PUMP INSERVICE TEST
TABLES."
2-CH-P-lA 2-CH-P-lB 2-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 l 1548-FM-8*8B.
2-SI-P-lA
2-SI-P-lB Low Head Safety Injection Pumps provide low pressure safety injection to the core for long term cooling and as a backup to accumulators. See drawing 11548-FM-89A.
2-CS-P-lA 2-CS-P-lB Containment-Spray Pumps provide a cooled, chem1cally treated, borated spray to reduce containment pressure following a loss of coolant accident. See drawing 11548-FM-84A.
2-RS-P-2A 2-RS-P-2B Out.side Recirculation Spray Pumps aid the Containment Spray System in reducing containment pressure rapidly following a loss of coolant accident. See drawing 11548-FM-84B.
2-RS-P-lA 2-RS-P-lB Inside Recirculation Spray Pumps aid the Containment Spray System in reducing containment pressure rapidly following a loss of coolant accident. See drawing 11548-FM-84B.
2-FW-P-3A 2.-FW-P-3B 2-FW-P-2 Auxiliary Feedwater Pumps supply the steam generator with feedwater in the event of a complete loss of normal
feedwater . See drawing 11548-FM-68A.
S2-004a 4-7 Rev. 1 April 1, 1987
2-RH-P-lA
2-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 11548-FM-87A.
1-CC-P-lC 1-CC-P-lD Component Cooling Water Pumps are used to supply water to remove heat from the Residual Heat Removal Systems. See drawings 11448-FM-72D.
1-CH-P-2C l-CH-P-2D Boric Acid Transfer Pumps supply boric acid to suction of charging pumps via normal coolant boron concentration and *emergency makeup. See drawing 11448-FM-88A.
2-CC-P-2A 2-CC-P-2B Charging Pumps Cooling Water Pump provide water to transfer heat from the charging pump mechanical seals. See drawing 11548-FM-71B .
2-SW-P-lOA 2-SW-P-lOB Charging Pump Service Water Pumps provide cooling water for Charging Pump Cooling Water Systems. See drawing 11548-FM-71B.
1-EE-P-lB 1-EE-P-lC 1-EE-P-lE Fuel Oil Pumps supply fuel oil to emergency diesel generators wall mounted tank. See drawing 11448-FB-4B.
4.3.5 PUMP INSERVICE TEST TABLES This tabulation identifies the pumps to be tested, code classes, required test quantities and frequencies. Relief from test requirements is requested in cases where test requirements have been determined to be impractical. Where relief is requested, technical justification is provided along with alternative test methods when applicable *
To aid the reader in interpreting the Pump Inservice Test Table, brief explanations of the abbreviations are provided below.
table headings and S2-004a 4-8 Rev. 1 April 1, 1987
1) Pump Number Each pump in the plant has a unique "tag 11 number which identifies the system to which the pump belongs.
2) Code Class ASME Code Class of each pump as per 10CFR50.55a and Regulatory: Guide 1.26.
.Note: NC is for non-class pumps
3) The required Section XI test quantities of Inlet Pressure, Differential Pressure (Discharge Pressure is not a required test quantity but is listed for clarity), Flow Rate, Vibration, Bearing Temperature, Pump Speed and Lubrication Level/Pressure are given as column headings.
The following abbreviations are used to describe the test status:
Q- the test will be performed on a quarterly basis.
CSD - the test will be performed every cold shutdown. A relief request explains the need for deviating from Section XI test frequency requirements NA - the test is not applicable, see corresponding relief request .
S2-004a 4-9 Rev. 1 April 1, 1987
PUMP INSERVICE TEST TABLE Pump ASME
Inlet Discharge Differential Flow Bearing Pump Lubrication ,Relief Identification Class Pressure Pressure Pressure Rate Vibration Temperature Speed Level/Pressure Request 2-CH-P-lA 2 NA Q NA NA Q NA NA Q 0,1,2 2-CH-P-lB 2 NA Q NA NA Q NA NA Q 0,1,2 2-CH-P-lC 2 NA Q NA NA Q NA NA Q 0,1,2 2-SI-P-lA 2 NA Q NA Q Q NA NA NA 0,1,3,12 2-SI-P-lB 2 NA Q* NA Q Q NA NA NA 0,1,3,12.
2-CS-P-iA 2 Q Q Q Q Q NA NA Q 0,1 2-CS-P-lB 2 Q Q Q Q Q NA NA Q 0, 1
. 2-RS-P-2A- 2 NA Q NA Q Q NA NA NA 0,1,4,12 2-RS-P-2B 2 NA Q
NA Q Q NA NA NA 0, 1 ,.4, 12 '
2-RS-P-lA 2 NA NA NA NA NA NA NA NA 0,1,5 2-RS-P-lB 2 NA NA NA NA NA NA NA NA 0,1,5 2-FW-P-3A 3 Q Q Q NA Q NA NA Q 0,1,6
2-FW-P-3B 3 Q Q Q NA Q NA NA Q 0,1,6.
2-FW-P-2 3 . Q, Q Q NA .Q NA Q Q 1,6 2-RH-P-lA 2 CSD CSD CSD CSD CSD NA NA NA 0,1,7,12 2-RH-P-lB 2 CSD CSD CSD CSD* CSD NA NA NA 0,1,7,12 S2-004a *4-10 Rev. 1 APril 1, 1987
PUMP INSERVICE TEST TABLE Pump ASME Inlet Discharge Differential Flow Bearing Pump Lubrication Relief Identification Class Pressure Pressure Pressure Rate Vibration Temperature Speed* Level/Pressure Request 1-CC-P-lC 3 Q Q Q NA Q NA NA Q 0,1,14 1-CC-P-lD 3 Q Q Q NA Q NA NA Q 0,1,14 l-CH-P-2C 3 NA Q NA NA NA NA NA NA 0,1,9,12 l-CH-P-2D 3 NA Q NA NA NA NA NA NA 0,1,9,12 2-C.C-P-2A 3 Q Q Q Q Q NA NA NA 0,1,13 2-CC-P-2B 3 Q Q Q Q Q NA NA NA 0,1,13 1
2-SW-P-lOA 3 Q Q Q Q Q NA NA NA 0,1,13 2-SW-P-lOB 3 Q Q Q Q Q NA NA NA 0,1,13 l-EE-P-11 NC NA NA NA NA NA NA NA Q 0,1,11 1-EE-P-lC NC NA NA NA NA NA NA NA Q 0,1,11 1-EE-P-lE NC NA NA NA NA NA NA NA Q 0,1,11 S2-004a 4-11
Rev. 1 April 1,1987
4.3.6 PUMP TEST PROGRAM RELIEF REQUEST Relief Requests identify code requirements which are impractical for Surry Unit 2 and provide justification for I.
the requested exception. Where appropriate, alternate testing to be performed in lieu of the code requirements is proposed .
S2-004a-3 Rev. 1 April 1, 1987
RELIEF REQUEST 0
Systems:
rump(s):
Class Various IWP Program Pumps except 2-FW-P-2. See PUMP INSERVICE TEST TABLE.
Section XI Code Re*quirements For Which Relief Is Requested Quarterly measurements of pump speeds.
Basis For Request IWP-4400 does not require pump speeds measurement if pump is directly coupled to a constant speed motor driver.
Alternate Testing Proposed None
S2-004a-3 4-13 Rev. 1 April 1, 1987
RELIEF REQUEST 1
Systems:
Pump(s):
Various TWP Program Pumps. See PUMP INSERVICE TEST TABLE Class 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 months 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 that are indicative of developing mechanical problems and hence more meaningful. Velocity measurements detect not only high amplitude vibrations that indicate a major
- mechanical prob'iem but also the equally harmful low amplitude high frequency vibrations due to misalignment in balance, _O{ 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 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 tests present problems which include the following:
1. Certain systems have no recirculation test loops and a limited source of water. An enforced thirty minute run time would deplete the source.
2. The lubricating fluid for some pumps is taken from the process water, which can change temperature depending on ambient conditions. Data trending for these cases is not meaningful.
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.
S2-004a-3 4-14 Rev. 1 April .1, 1987
Alternate Testing Proposed RELIEF REQUEST 1 (CONT'D)
Pump vibration measurements will be taken in vibration velocity (in/sec).
The evalu~tion 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 .
S2-004a-3 4-15 Rev. 1 April 1, 1987
RELIEF REQUEST 1 (CONT'D)
SURRY 2 ALLOWABLE RANGES OF VIBRATION VELOCITY FOR PUMP TESTING PER SUBSECTION IWP Test Band Test Quantity Acceptable Range Alert Range Required Action Range No. (in/sec) (in/sec) (in/sec) (in/sec) 1 Vt When osvr 1so.o5 0 to 0.075 0.075 to 0.1 >0.1 2 Vt When 0.05(Vr 2sO.l 0 to 0.15 0.15 to 0.2 >0.2 3 Vt When 0.l(Vr 3s0.15 0 to 0.2 0.2 to 0.25 >0.25 4 Vt When 0.15(Vr 4s0.25 0 to 0.285 0.285 to 0.314 >0.314 Definitions: V = Reference velocity measurement (in/sec filtered peak) r Vt= Surveillance test velocity measurement (in/sec filtered peak)
Note-: The frequency response range of the vibration measuring transducers and their readout system shall be from one-half minimum pump shaft rotational speed to at least 1,000 Hertz.
S2-004a 4-16 Rev. 1 April 1, 1987
RELIEF REQUEST 2 Systems: Chemical and Volume Control Pump(s): 2-CH-P-lA 2-CH-P-lB 2-CH-P-lC Class 2 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 Suction pressure instrumentation is not installed nor r~quired, therefore, differential pressure cannot be calculated. These pumps are capable of producin~ 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 gauge 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 pump testing.
NOTE: A Design Change has been initiated for inlet pressure and fiow measurement instrumentation. Installation of the inlet pressure instr~mentation will allow for the calculation of differential pressure. The instrumentation is scheduled for installation in accordance with the Nuclear Operations Department Five Year Plan for Surry Power St'ation .
S2-004a 4-17 REV. 1
RELIEF REQUEST 3
Systems:
Pump(s):
Safety Injection 2-SI-P-lA 2-SI-P-lB Class 2 Section XI Code Requirements For Which Relief Is Requested_
Measure inlet pressure and differential pressure.
Basis For Request 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 Specifications which will insure similar initial conditions for testing.
NOTE: A Design Change has been initiated for inlet pressure instrumentation, which will allow for the calculation of differential pressure. The instrumentation is scheduled for installation in accordance'with the Nuclear Operations Department Five Year Plan for Surry Power Station .
S2-004b-3 4-18 Rev. 1 April 1, 1987
RELIEF REQUEST 4
Systems:
Pump(s):
Recirculation Spray 2-RS-P-2A 2-RS-P-2B Class 2 Section XI Code Requirements For Which Relief Is Requested Measure inlet pressure and differential pressure.
Basis For Request*
Instrumentation is not installed.
Alternate Testing Proposed Suction pressure instrumentation is not installed, therefore differential pressure cannot be calculated. Suction pressure is the same for each test
.since suction pressure is only the head of water in the filled pump casing.
NOTE: A Design Change has been initiated for inlet pressure instrumentation, which will allow for the calculation of differential pressure. The instrumentation is scheduled for installation in accordance with the Nuclear Operations Department Five Year Plan for Surry Power Station .
S2-004b-3 4-19 Rev. 1 April 1, 1987
RELIEF REQUEST 5
Systems:
Pump(s):
Recirculation Spray 2-RS-P-lA 2-RS-P-lB Class 2 Section XI Code Requirements For Which Relief Is Requested Measure inlet pressure, discharge pressure, differential pressure, flow and vibration, and observe proper lubricant level or pressure.
Basis For Request Technical Specification 4.5.A.2 requires that the pumps be dry tested.
Testing of these pumps would require spraying water on components in containment. Also, dry testing of the pumps will not give meaningful data.
The pump and motor are totally enclosed and air cooled; therefore, the observation of lubricant level or pressure is not applicable to these pumps.
Alternate Testing Proposed
Motor current is measured monthly and. compared with previous readings.
Also, it can be determined that the pump shafts are turning by rotation sensors which indicate in the Main Control Room
S2-004b-3 4-20 Rev. 1 April 1, 1987
REL.IEF REQUEST 6
Systems:
Pump(s):
Feedwater 2-FW-P-3A 2-FW-P-3B z..:.FW-P-2 Class 3 Section XI Code Requirements For Which Relief Is Requested Measure flow.
Basis For Request Instrumentation not installed.
Alternate Testing Proposed Inservice testing data is collected except flow; therefore, there is sufficient data collected for evaluation of pump performance.
NOTE: Engineering Work Request "EWR 86-557" has been initiated for installation .
S2-004b-3 4-21 Rev. 1 April 1, 1987
RELIEF REQUEST 7
Systems:
Pump(s):
Residual Heat Removal 2-RH-P-lA 2-RH-P-lB Class 2 Section XI Code Requirements For Which Relief Is Requested Frequency of Pump Test.
Basis For Request It is .considered impractical to make a containment entry on a quarterly basis in order to test these pumps. Operability will be determined each cold shutdown when the system is placed into operation (but not more frequently than every three months).
Alternate Testing Proposed Pumps will be tested each cold shutdown (but not more frequently than every three months) .
S2-004b-3 4-22 Rev. 1 April 1, 1987
RELIEF REQUEST 8
Relief Request Withdrawn L...
4-23 Rev. 1 S2-004b-3 April 1, 1987
RELIEF REQUEST 9 Systems: Chemical and Volume Control Pump(s): l-CH-P-2C l-CH-P-2D Class 3 Section XI Code Requirements For Which Relief Is Requested Measure inlet pressure, differential pressure, vibration and flow.
- Basis For Request
1. No instrumentation installed for inlet pressure, differential pressure and flow.
2. Pumps are totally incased in insulation, ,therefore, vibration probes canno~ be placed in contact with pumps for a reading.
Alternate Testing Method
These pumps take suction from Boric Acid-storage Tanks .. Tank level will be observed to establish initial condition of testing, therefore, inlet pressure will not be measured.
currently installed.
NOTE:
No flow rate measurement device is A Design Change has been initiated for inlet pressure, flow and vibration instrumentation. Installation of inlet pressure instrumentation will allow for the calculation of differential pressure. The instrumentation is scheduled for installation in accordance with the Nuclear Operations Department Five Year Plan for Surry Power Station .
S2-004b-3 4-24 Rev. 1 April 1, 1987
RELIEF REQUEST 10
Relief Request Withdrawn
.S2-004b-3 4-25 Rev. 1 April 1, 1987
RELIEF REQUEST 11 Systems: Fuel Oil Pump(s): 1-EE-P-lB 1-EE-P-lC 1-EE-P-lE Class NC Section XI Code Requirements For Which Relief Is Requested Measure inlet pressure, differential pressure, flow rate and vibration.
Basis For Relief Code interpretations consider these pumps to be outside the scope of ASME Section XI. Attached is copy of specified inquiry and reply on which relief is based. '
Alternate Te~ting Proposed These pumps will be tested monthly by observing that the pumps , perform their intended function (fuel oil is flowing to the day tank when the pumps are running).
NOTE: Instrumentation for performing Section XI tests will be installed in accordance with the Nuclear Power Operations Department Five Year Plan for Surry Power Station *
- S2-004b-3 4-26 Rev. 1 April 1, 1987
INQUIRY AND REPLY AS *SENT TO INQUIRER 08/14/81 FILE NUMBER INQUIRER COMPANY REPLY SENT BC/77 /666 WPPSS . 78/02/17 SUBJECT SCOPE OF SECTION XI, DIVISION.l 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 Resp~nsibility, 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 .
. S2-004b-3 4-27 Rev. 1 April 1, 1987
RELIEF REQUEST 12 Systems: Srtfety Injection, Recirculation Spray, Residual Heat Removal, and Chemical and Volume Control Pump(s): 2-SI-P-lA 2-RH-P-lA 2-SI-P-lB 2-RH-P-lB 2-RS-P-2A l-CH-P-2C 2-RS-P-2B l-CH-P-2D Class 2 for 2-SI.;:_P-lA and B 2-RS-P-lA and B 2-RH-P-lA and B 3 for l-CH-P-2A and B Section XI Code Requirements For Which Relief Is Requested, Observe proper lubricant level or pressure.
Basis For Request These pumps are cooled by fluid through the pump. Therefore, the other Code required pump parameters will ensure proper level of lubrication *
Alternate Testing Proposed None *
. S2-004b-3 4-28 Rev. 1 April 1, 1987
RELIEF REQUEST 13
-I Systems: Component Cooling and Service Water Pump(s): 2-CC-P-2A 2-CC-P-2B 2-SW-P-lOA 2-SW-P-lOB Class 3 Section XI Code Requirements For Which Relief Is Requested Observe proper lubricant level or pressure.
Basis For Request Pump bearings are carried in the drive motor and are greased and lubricated. Therefore, the other Code required p~rameters will ensure proper level of lubrication.
Alternate Testing Proposed None.
r
Rev. l S2-004b-3 li-29 April v
1, 1987
RELIEF REQUEST 14
Systems:
Pump (s):
Component Cooling 1--CC-P-lC 1-CC-P-lD Class 3 Section XI Code Requirements For Which Relief Is Requested
. Measure pump flow rate during the quarterly testing.
Basis For Request Pump total flow is not a measurable parameter during pump quarterly testing, however during the quarterly testing a repeatable flow loop is established.
Alternate Testing Proposed During the quarterly testing, the flow is measured for the repeatable loop which gives enough data for trending purposes.
NOTE: A Design Change has been initiated for flow instrumentation. Th~
instrumentation is scheduled for installation in accordance with the Nuclear Operations Department Five Year Plan for Surry Power Station .
4-30 Rev.* 1 S2-004b-3 April 1, 19E'7
4.4 VALVE INSERVICE TEST PROGRAM DESCRIPTION
4.4.l PROGRAM DEVELOPMENT PHILOSOPHY Surry Power Station Unit 2 is a Pressurized Water Reactor being operated in *compliance with the ASHE 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 2 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. The scope includes all valves "which are required to perform a specific function in shutting down a reactor to a 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 Inservice Testing Program for its implementaion includes many valves 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 2 Valve Program, 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.
Surry Unit 2 is committed to meeting the leak rate testing requirements of:
1. 10CFRSO, Appendix J for containment isolation valves and
2. Section XI for other valves for which seat leakage is limited to a specific maximum amount (i.e. pressure isolation valves) unless relief is specifically requested from Section XI requirements.
The Code recognizes that certain of it's requirements may be impractical for a specific plant and contains provisions for requesting relief from impractical requirements.
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 time of solenoid controlled, air operated valves is both extremely rapid and subject to considerable variation. Exception is taken to complying with stroke time criteria defined by Paragraph IWV-3417(a).
S2-004b-3 4-31 Rev. 1 April 1, 1987
Virginia Electric and Power Company ~s confident that the Surry Unit 2 Valve Inservice Test Program complies with the intent of the applicable codes, regulation, and guidelines and that it will make a positive contribution to the safe operation of the plant.
4.4.2 PROGRAM IMPLEMENTATION The Valve Inservice Test Program will be executed as part of the normal plant surveillance routine. Three types of test will be conducted as part of the Valve Test Program:
1. Valve Operab'ility Tests
2. Valve Leak Rate Tests
3. Safety Valve Tests The Operability Tests will verify that: 1) the valve responds to control commands, 2) the valve stroke time is within specifed limits and 3) remote position indication accurately reflects the _observed valve position. Remote valve position indication will be verified every two years.
Fail-safe valves will be te-sted by o'bserving 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 exercised 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 shutdoym 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 Tests will verify that valves are leak tight in accordance with Appendix J or ASME Section XI. Relief and safety valves are not required to be leak rate "'teste<'
(IWV-3512) and are not included as valves to be leak tested.
Safety and relief valve setpoints are tested in accordance with ASME PTC-25.3-1976 as directed by IWV-3512. Main Steam safety valves will be tested in accordance w{th Section 4.09l(a)(2). Other safety and relief valves will be tested in acco;dance with Section 4.09l(c)(l).
4.4.3 PROGRAM ADMINISTRATION
The operations and engineering staffs at Surry Power Station are responsible for administration and execution of the Valve S2-004b-3 4-32 Rev. 1 April 1, -1987
Inservice Test Prq>;ram. The program was officially implemented on May 1, 1983 and governs valve testing for a 120
~onth period. Prior to the end of the 120 month period, the progrc.m will be reviewed_ and upgraded to .essure continued compliance with 10CFR50.55a(g)(4)_. The program will be u_pdated a minumum of at least once every 40 months or for a new system, relief request, etc.
4.4.4 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 position~ taken ii support of the relief requests.
To aid the reader in the interpretation of the tables, brief explanations of the table headings and abbreviations 2re provided.
1. Valve Number - Each valve in the plant has a unique "tag" number which identifies the system to which the equipment belongs and type of equipment.
2. Drawing Location - The specific coordinates of each valve are supplied to facilitate location of the valves on the flew diagrams provided.
3. Function A brief description of the function of the valve .
4.
NOTE:
Code Class ASME Code Class of each 10CFR50.55a and Regulatory Guide 1.26.
- NC is for non-class valves.
valve as per
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. Valves marked with an "E" are passive valves.
6. Size - Nominal diameter of pipe 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 S2-004b-3 4-33 Rev. l April 1, 1987
8. Actuator Type The following abbreviations are used to
describe actuator types. V2lves may be actuated in more than one way.
SA Self Actuating (actuated by a change in system parameters such as flow, or pressure, e.g., *check nnd relief valves).
MO Motor Operated PN Pneu~atic (Air Operated) r:1AN - Manually Operated SOV - Electronic Solenoid Operated Valves
9. Normal Position - The following abbreviations are used to describe normal 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, Subsubarticle IWV-3410 or as modified by specific relief request .
EV - Exercise Valve for operability at least once every 3 months per Section XI, Subsubarticle IWV-3410 or as modified by specific relief request.
LT - Leak Test shall be performed per Section XI, Subsubarticle IWV-3420 -or as modified by specific relief request. Valves mark~d by asterisk(*) will be tested in accordHnce with Appendix J, CV - Check Valves shall be exercised at least once every 3 months per Sectior.. XI, Subsubarticle IWV-3520 or as modified by specific relief request.
VP - Valve Position Indication Verification shall be verified per Section XI, Subsubarticle IWV-3300 or as modified by specific relief request.
SP - Set points of safety and relief valves shall be tested per Section IX, Subsubarticle IWV-3510 or as modified by specific relief request.
FS - Valves with fail-safe actuators shall be tested by
- observing the operation of the valves upon loss of actuator power
S2-004b-3 4-34 Rev. 1
' April l, l Sti 7 1

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves
Systein Name: Main Steam Drawing Number: 11548-FM-64A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location __F_u_.r_1c_t_1_*o_n______C_l_a_s_s_-'g~o_r-'y~__S_i_z_e__T~y~p_e_ _1-y'"""p~e____P_o_s_i_t_ion :Rcqu*j rc.;u Request SV-MS-20 l_A, B, C B-3, B-4, B~6 Main Steam Safety Valves 2 C 4 SF SA C l S\7-MS-202A,B,C C-3, C-4, C--G SV-MS-203A,B,C B-3, B-4, B-6 SV-MS-204A,B,C B-3, B-4, B-6 SV-MS-205A,B,C C-3, C-4, C-6 TV-MS-201A,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-201A D-3 NRV-MS-201B D-5 Main Steam Non Return NRV-MS-201C D--6 Valves 2 C 30 MOV 0 CV _,')
RV-MS-201A C-2 RV-MS-201B B-4 Mai.n Steam PORV 2 C 4 RV SA C SP 1 RV-MS-2.0lC C-6 PCV-MS-202A F-8 Nain Steam to Turbine 2 B J GA PN C EV ,ST None PCV-MS-202B G-8 Driven Aux.-FW Pump VP,, FS HCV-MS-204 B-4* Decay Heat Release 2 B CA PN C EV,VP 32 Control Valve TV-MS-209 F-7 Main Steam Drain to 2 B 3 GA FN 0 EV ,ST None Condenser vr NRV-MS-202A,B,C,C-3
Main Steam Non Return C-4 Valves 2 C 3 SCK Han 0 CV 3 C-6
~;2-004c-.'.;; 4--35 Rev. l
/,pri.1 l, ]~1f,i1

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1, 2, a~d 3 Valves System Name: Main Steam Drawing No.: 11548-FM-64A Valve Drawing Code Cc1te- Valve Actuator Normal Test Relief
_ _ _N_u_m_b_e_r_____L_o_c_a_*_t_i_on_._________F_u_n_c_t_i_o_n______C_l_a_s_s_~g_o_r~y_ _S_i_z_e__T~y~p~e_ _T~y~p_e_ _ _P_o_s_1_*t_*_io_n__1_~ec:u i *L-ecl Request TV-MS-210 E-7 Main Steam Drain to Blow- 2 B 2 GA PK () EV,ST down \il' 2-MS-176 E-8 Main Steam to Turbine Driven 2 C 3 CK SA C CV None 2--HS-178 E-8 Aux FW Check Valves 2-MS-182 E-8 r
S2-C04c-3 4-36 Rev. 1 April 1, 1Sl87

Surry Power Station Unit No.:?,
Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Aux. Steam and Air Removal Drawing No. 11548-FM-66A Valve Drawing, Code Cate- Valve Actuator Normal 'fef;t Relief Number Location Function Class gory Size Type Type Position Required Request TV-SV-202A A-6 Air Removal Direct to 2 A 6 GA PN C LT*,,, J:'.\I Ncne
, Reactor Containment ST, VP 2-VP-12 A-6 Air Removal Direct to 2 ACE 6 CK SA C LT>< None Reactor Containment S2-004c-3 4-37 Rev. l April 1, l (]87

Surry Power Station Unit No. 2 In service Testing ASME Code Class 1, ,_ ' end 3 Valves
')
Sysr:em Name: Feedwater Drawing No. 11548-FH-68A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size .Type Type Position Rr:::quire.d Request 2-FW-27 C-2 P.uxiliary Feedwater Header 2-FW-58 B-4 Check Valves at Main Feed- 2 C 3 CK . SA C CV 4 2-FW-89 B-5 water Header 2-FW-131 C-6 Auxiliary Feedwater Header 2-FW-133 C-6 Check Valves at Contain- ,_') C 6 CK SA C CV 4 2-FW-136 C-6 ment Penetration 2-FW-138 C-6 2-FW-142 D-7 Auxiliary Feedwater Pump 3 C 6 CK SA C CV 4 2-FW-157 E-7 Discharge Check Valves at 2-FW-172 F-7 Containment Penetration MOV-251A,B,C, B-6, B-6, B-6 Auxiliary Feedwater to EV, ST D,E,F B-6, C-6, C-6 Stearn Generators 2 B 3 GL MOV 0 VP None 2-FW-144 D-7 Auxiliary Feedwater Pump 2-FW-159 F-7 Re~irculation Check 3 C 1 CK SA C CV None 2-FW-174 G-7 Valves 2-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
)
l+-38 Rev. 1 Apr:i.l l, 1987

Surry Power Station Un.it No_. 2 Inservice Testing ASME Code Class l, 2, and 3 Valves SyLJtem Name: Auliliary Feed Cross Connect Drawing No. 11448-:-FM-68B Valve Drawing Code Cat.e.,- Valve Actuator Normal Test . Rd i ef Number Location Function Class gory Size Type Type Position lZequire<l Request MO\'-F'W-260A J-2 Cross-Connect for Unit 1 ET, 5",\'
MOV-FW-260B J-2 Aux. Feed. from Unit 2 3 B 6 GL EOV C VP NonE.
2 FW-2 72 J-4 Check Valves at Cont. Penet.
2-FW-273 1-4 (Cross-Connect for Unit 2 2 C 6 CK SA C CV 4 Aux. Feed from Unit 1) 2-FW-305 I-4 check Valves* at Cont. Penet.
2-FW-306 1-4 (Cross-Connect for Unit 2 2 C 6 CK SA C CV 4 Aux. Feed. from Unit 1)
S2-004e:-3 4-39 Rev. 1 Apr:L] l , 1987

Surry Power Station Unit No. 2 Inservice Testing ASME Code Clasf; 1' 2' and 3 Valves
I*
System Name: Circulating and Service Water Drawing No. 11548-FM-71A Valve Drawing . Code Cate- Valve Actuator Normal Tesi:: Relief Number Location Function (;lass gory Size Type Type Position Required Request MOV-CW-206A E-4 MOV-*CW-20613 :E-4 Condenser Inlet .3 B 96 BF :t-':OV 0 EV, ,,_....,., l'.one MOV-CW-206C F-4 lsolation Valves VP MOV-CW-206D F-4 MOV-SW-202A E-6 Service Water t:O Component EV, ST MOV-SW-202B F-6 Cooling Water Heat Ex- 3 B 10 P,F ~ov 0 VP None changers
}10\T-SW-203A B-6 Service Water to Recircu- EV, ST MOV-SW-203B B-6 lation Spray Heat Ex- 3 B 30 BF :tv':OV C VP None HCJ\1-SW-203C D*-6 changers MOV-SW--203D E-6 i\10V-SW-204A A-2 Recirculati0n Spray Heatr EV, ST M.OV-SW-204B I B-2 Exchangers Suction Isola- 3 B 24 BF MOV 0 Vl' None MOV-SW-204C C-2 tion Valves MOV-SW-204D C-2
}10V-SW-205A A-2 MOV-SW-205B A-2 Recirculation. Spray Heat EV,$T Jv10V-SW-205C B-2 Exchanger Discharge Isola- 3 B 24 BF MOV 0 VP None MOV-SW-205D C-2 tion Valves MOV-SW-20GA D-4 Recirculation Spray Heat EV ,ST HOV-SW-206H D-*4 Exchangers Cross-Connect 3 B 36 EF MOV 0 VP llcme
Valves S2-004c-3 4-40 Rev. I i\pdl l, 1987

Surry Power Station Unit No. 2
.Inservice Testing ASHE Code Class 1 ' 2, and 3 Valves I
System Name: Circulating and Service Water Drawing No. 11548-FM-71A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type
Position Required Request MOV-SW-201A B-7 BE:aring Cooling Water EV, ST MOV-SW-201B C-7 Heat Exchange isloti.on 3 B 36 BF NOV 0 VP None Valves MOV-CW-200A E-2 MOV-CW-200B E-2 Condenser Discharge. EV, ST MOV-CW-200C 1~-2 Isolation Valves NC B 96 BF HOV 0 VP None MOV-CW-200D F-:2 2-SW-206 A-1 Containment Isolation 2-SW-208 A-1 *Valves for Service Water 3 AE 2 GA Man C LT* 1'1one Drains to Heat Exchanger S2-00L,c-3 4-41 Rev. 1 Apr:il l, 1987

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class I ' 2, and 3 Valves System Name: Circulating and Service Water Drawing No. l 1548-FM-71B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type ~osition. Required Request 2-CC-764 D-5 Charging Pump Cooling 2-CC-329 G-5 Water Pump Discharge Check 3 C 2 CK SA oc C'..J None Valve 2-SW-113 E-9 Charging Pump Service 2-SW-108 H-8 Water Pump Check Valve 3 C 2 CK SA oc CV None S2-004c-3 4-42 Rev. I April 1, 1987

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1 ' 2, and 3 Valves System Name: Component Cooling Drawing No. 11548-FM-72A Valve Drawing Code Cate- Valve Actuator Normal .*Te.st Relief Number* Location Function Class gory Size Type Type Position Required Request RV-CC-219A L-2 Component Cooling from RHR RV-CC-219B 1-3 Heat Exchanger Relief 3 C 1 1/2 RV SA C SP 1 Valve 2-CC-176 A-1 Component Cooling to RHR 2-CC-177 A-1 Heat Exchanger Check Valve 3 C 18 CK SA oc CV 7 2-CC-l A-1 Component Cooling to 2-CC-58 A-2 Reactor Coolant Pumps 3 C 6 CK SA 0 CV 8 2-CC-59 A-2 RV-CC-2f6A B-3 Component Cooling Reactor RV-CC-216B B-5 Coolant Pump Relief 3 C 1 1/2 RV SA C SP 1 RV-CC-216C B-8 Component Cooling P1ping RV-CC-224 F..:.l Relief Valve 3 C 3/4 RV SA C SP 1 Component Cooling Excess RV-CC-218 G-4 Letdown Heat Exchanger 3 C 3/4 RV SA C SP l Relief Valve S2-004c-3 4-43 Rev. 1 April 1, l 987

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Component Cooling Water Drawing No. 11548-FM-72B Valve Drawing Code Cate- Valve Actuator Normal Test ~elief Number Location Function Class gory Size Type Type Position Required Request

="--~----------'------"-~----------

2-CC-242 C-2 Component Cooling to 2-CC-233 D-2 Reactor Containment Air 3 C 6 CK SA 0 CV 7 2-CC-224 E-2 Recirculation Coolers S2-004c-3 Rev. 1 Apr.il 1, 1 %7

Surry Power Station Unit No. 2 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 l-CC-569 B-3 Component Cooling Pump l-CC-578 B-3 Discharge Check 3 C 18 CK SA oc CV None r
S2--004c-3 4-45 Rev. 1.
April 1,. l~JB7

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1' 2', an_d 3 Valves System Name: . Component Coolin~ Drawing No. 11448-FM-72F Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request TV-CC-205A A-1 Component Cooling from EV, VP TV-CC-205B B-1 Reactor Coolant Pumps 3 B 6 BA PN 0 ST 8,34 TV-CC-205C C-1 Component Cooling from EV, VP TV-CC-207 A-1 Reactor Coolant Pumps 3 B 2 1/2 GL PN 0 ST 8,34 TV-CC-209A E-4 Component Cooling from RHR FS, ST TV-CC-209B E-3 Heat_ Exchangers. 3 B 18 BF PN 0 EV, VP 34 TV-CC-210A E-2 Component Cooling from EV, VP TV-CC-210B D-2 Reactor Containment Air 3 B 6 BF PN 0 ST None TV-CC-210C C-2 Recirculation Coolers S2-004c-3 4-46 Rev. 1 April 1, 1087
)
Surry Power Station Unit No. 2 Inservice Testing, ASME Code Class 1, 2, and 3 Valves System Name: Compressed Air System Drawing No. 11548-FM-?SC--
Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request Instrument Air to Contain-2-IA-864 H-2 ment 2 AC 2 CK SA 0 CV, LT>'< 9 Instrument Air to Contain-2-IA-868 H-2 ment 2 AC 2 CK SA 0 CV, LT* 9 S2-004c-3 4-47 Rev. 1 April l , 1987

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Compressed Air System Drawing No. 11548-FM-75E Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type , Position Required Request 2-SA-81 D-7 Service Air to Containment 2 AE 2 GL Man C LT* None 2-SA-82 E-7 Service Air to Containment 2 AE 2 GL Man C None S2-004c-3 4-48 Rev. 1 AprH 1, 1987

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1, 2. and 3 Valves System Name: Containment Instrument Air Drawing No. 11548-FM-75J Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Ty,pe Position Required Request TV-IA-201A K-7 Instrument Air Suction LT>~, EV TV-IA-201B J-7 from Containment 2 A 2 GA PN 0 ST, VP JL, Instrument Air Discharge LT*, EV TV-IA-200 K-2 from Containment 2 A 2 GA PN 0 'ST, VP 34 Back up Instrument Air 2-IA-704 J-2 to Containment 2 AE 2 GA Man C LT* None Back up Instrument Air to l-IA-704 J-1 Containment from Unit 1 2 -* AE 2 GA Man C LT* None S2-004c-3 4-49 Rev. 1 April,1, 1987

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Sampling System Drawing No. 11548-FM-82A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type .
Position Required Request TV-SS-203A D-1 Residual Heat Removal LT*, EV TV-SS-203B E-1 System Sample 2 A 3/8 GA PN , C ST, VP 34 TV-SS-200A D-1 Pressurizer Liquid Space LT*, EV TV-SS-200B E-1 Sample 1 A 3/8 GA PN C ST, VP 34 TV-SS-201A D-1 Pressuriz~r Vapor Space LT*, EV TV-SS-201B E-1 Sample 1 A 3/8 GA PN C ST, VP 34 TV-SS-206A D-2 Primary Coolant Hot Leg LT*, EV TV-SS-206B E-2 Samples 1 A 3/8 GA PN C ST, VP 34 TV-SS-202A D-2 Primary Coolant Cold Leg LT*, EV TV-SS-202B E-2 Sample 1 A 3/8 GA PN C ST, VP 34 TV-SS-204A D-2 Pressurizer Relief Tank LT*, EV TV-SS-204B E-2 Gas Space Sample 2 A. 3/8 GA PN C ST, VP 34 S2-004c-3 4-50 Rev. 1
.April 1, 1"987

Suq*y Power Station Unit No *. 2 Inservice Testing ASME Code Class 1' 2 '* and 3 Valves System Name: Vents and Drains Drawing No. 11548-FM-83A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function *Class gory Size Type Type Posttion Required Request Reactor Containment Sump LT*, VP TV-DA-200B I-8 Pump Disch~rge Isolation 2 A 2 GA PN C EV, ST 34 TV-DA-203A I-9 Post Accident Sample LT*, VP TV-DA-203B I-9 Return Line 2 A 2 GA PN C EV, ST 34.
2-VA-l I-5 Primary Vent Pot Vent 2 AE 2 GA Man C LT* None Primary Drain Transfer LT*, VP TV-DG-208B I-4 Pump Discharge Isolation 2 A 2 GA PN C EV; ST 34 LT*, VP TV-VG-209B I-2 Gas Vent Header Isolation 2 A 2 GA PN 0 EV, ST 34 S2-004c-3 4-51 Rev. 1
. April 1, 1987
__ __J

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Vents and Drains Drawing No. 11548-FM-83B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request TV-DA200A J-8 R. c. Sump Pump 2 A 2 GA PN oc LT*, EV 34 Discharge Isolation ST, VP TV-DG208A L-4 Pr. Dr. Transfer Pump 2 A 2 GA PN oc LT*, EV 34 Disch. Isolation ST, VP TV-VG209A L-2 Gas Vent Hdr. Isolation 2 A 1 1/2 GA PN 0 LT*, EV 34 ST, VP 2-VA-9 L-4 Containment Isolation 2 AE 2 GA MAN C LT* None S2-004c-3 4-52 Rev. 1 April 1, 1987

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Containment Spray System Drawing No. 11548-FM-84A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position* Required Request MOV-CS-201A H-2 MOV-CS-201B ,H-2 Containment Spray 2 A 8 GA MOV C LT*, EV 'None MOV-CS-201C H-3 Pump Discharge ST,VP MOV-CS-2010 H-3 2-CS-13 1-2 Containment Spray 2-CS-24 I-3 Discharge* Check Valves 2 AC 8 CK SA C CV, LT* 10 2-CS-105 K-3 Containment Spray Pump 2-CS-104 K-1
Discharge Check Valve 2 C 8 CK SA C CV 10 MOV-CS-202A C-6 Chemical Addition Tank to EV, ST MOV-CS-202B C-6 RWST Isolation Valve 2 B 6 *cA MOV C VP Non*e MOV-CS-203A D-6 Chemical Addition Tank MOV-CS-203B D-6 Discharge to Suction 2 B 3 GA MOV C . EV, ST None MOV-CS-203C D-7 Containment Spray VP MOV-CS-203D D-6 Pump S2-004c-3 4-53 Rev. 1 April 1, 1987

Surry Power Station Un.it No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Recirculation Spray System Drawing No. 11548-FM-84B Valve Drawing Code Cate- Val:ve Actuator Normal Test Relief
,-Number Location Function Class gory Size Type Type Position Required Request MOV-RS-255A D-8 Recirculation Spray Pump LT*, EV MOV-RS-255B D-8 Suction from Containment 2 A 12 PL MOV 0 ST, VP None Sump MOV-RS-256A E-4 Recirculation Spray Pump LT*, EV MOV-RS-256B E-3 Discharge 2 A 10 BF MOV 0 ST, VP None 2-RS-11 F-3. Recirculation Spray Pump 2-RS-17 F-4 Discharge Check Valves 2 AC 10 CK SA C CV, LT~~ 10 S2-004c-3 4-54 Rev. 1 April 1, 1987

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1' 2, and 3 Valves System Name: Containment Vacuum and Leakage Monitoring Drawing No. 11548-FM-85A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory* Size Type Type Position Required Request TV-LM-200A E-3 TV-LM-200B E-3 TV-LM-200C E-3 TV-LM-200D E-3 Leakage Monitoring System LT-1,, EV TV-LM-200E E-3 Isolation 2 A 3/8 GA PN 0
-I ST, VP 34 TV-LM-200F E-3 TV-LM-200G D-3 TV-LM-200H E-3 Containment Air Ejector HCV-CV-200 J-5 Isolation 2 AE 8 GA PN C LT*, VP None Containment Air Ejector 2-CV-2 I-5 Isolation ' 2 AE 8 GA Man C LT* None TV-CV-250A H-7 TV-CV-250B H-7 Containment Vacuum Pump LT*, EV TV-CV-250C H-8 Suction Isolation 2 A 2 GA PN 0 VP ,ST 34 TV-CV-250D H-8 S2-004c-3 4-55 Rev. 1 April 1, 1987

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1 ' 2, and 3 Valves System Name: Reactor Coolant System Drawing No. 11548-FM-86A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request HCV-2556A A-2 HCV-2556B A-7 Loop Fill Boundary 1 AE 2 PL Pl';l C LT,VP 30 HCV-2556C L-2 SOV-RC-200A-1 G-7 SOV-RC-200A-2 G-7 Reactor Vessel Head Vent 2 B 1
GA sov C EV, ST 31 SOV-RC-200B-1 G-7 SOV-RC-200B-2 G-7 S2-004c-3 4-56 Rev. 1
April 1, 1987
,. Surry Pow~r Station Unit No. 2 Inservice Testing
ASME Code Class 1, 2, and 3 Valves System Name: Reactor Coolant System Drawing No. 11548-FM-86B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request SV-2551-A F-4 SV-2551-B G.:..4 Pressurizer Safety SV-2551-C H-4 Valves 1 AC 6 SF SA C SP, LT 1, 30 Primary Grade Water to LT*, EV TV-2519A A-6 PZR Relief Tank 2 A 3 GA PN C ST, VP None Primary Grade Water to 2-RC-20 B-7 PZR Relief Tank 3 AC 3 CK SA C LT*, CV 9 MOV-2535 I-4 EV_, ST MOV-2536 1-5 PORV Block Valve 1 A 3 BF MOV 0 VP, LT 30 FS PCV-2456 J-4 EV, ST PCV-2455C J-5 PORV Pressurizer 1 A 3 PL PN C VP, LT 30,34,35 SOV-RC-201A-l J-7 S0V-RC-201A-2 J-7 S0V-RC-201B-l J-7 Pressurizer Head SOV-RC-201B-2 J-7 Vent 2 A 1 GA sov C EV, ST 31 S2-004c-3 4-57 Rev. l April 1, 1987-

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Residual Heat Removal Drawing No. 11548-FM-87A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request MOV-2700 H-7 RHR Suction from Reactor ST, EV MOV-2701 G-7 Coolant System 1 A 14 GA MO C LT, VP 12, 30 MOV-2720A K-5 RHR Discharge to Reactor ST, EV MOV-2720B K-5 Coolant System 1 A 10 GA MO C LT, VP 13' 30 RV-2721 I-4 RHR System Relief Valve 2 C 3 RV SA C SP 1 2-RH-5 D-6 RHR Pump Discharge Check 2-RH-11 C-6 Valve 2 C 10 CK SA C CV 11 MOV-RH-200 K-3 RHR to RWST 2 AE 6 GA MO C LT*, VP None S2-004c-3 4-58 Rev. 1 April 1, 1987

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves 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-109 E-7 Boric Acid Transfer Pump l-CH-116, G-7 Discharge Valve 3 C 2 CK SA oc CV None S2-004c-3 4-59 Rev. 1 April 1, 1987

Surry Power. Stat.ion.Unit No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Chemical and Volume Control Drawing No. 11548-FM-88B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Cl.ass gory Size Type Type Position Requir.ed Request 2-CH-258 D-6 2-CH-267 F-6 Charging Pump Discharge 2 C 3 CK SA oc CV 14 2-CH-276 G-6 Check Valve Charging Pump Suction from LCV-2115B C-9 Refueling Water Storage 2 B 8. GA* MOV C EV, ST None LCV-2115D C-9 Tank VP LCV-2115C H-3 Charging Pump Suction from EV, ST LCV-2115E H.:.3 Volume Control Tanks 2 B 4 GA MOV 0 VP 15 MOV-2275A D-6 MOV-2?75B F-6 Charging Pump Recirculation EV, ST MOV-2275C H-6 Flow Path Isolation 2 B 2 GA MOV 0 VP None Charging Pump Recirculation EV,ST MOV-2373 F-5 Header Stop Valve 2 B 3 GA MOV 0 VP 16 Reactor Coolant Pump Seal EV, ST MOV-2381 A-3 Water Return 1 A 3 GA MOV 0 VP, LT*. 17 Reactor Coolant System Let- LT*,EV TV-2204 A-3 down Isolation Trip Valve 2 A 2 'GA PN 0 ST, VP 18,34 Reactor Coolant System Let-RV-2209 F-1 down Relief Valve 2 C 2 RV SA C SP 1 Volume Control Tank Relief RV-2257 H-1 Valve 2 C 3 RV SA C SP 1
'S2-004c-3 4-60 Rev. 1
. April 1, 1987 .

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Chemical and Volume Control Drawing No. 11548-FM-88B Valve Drawing Code Cate- Valve Actuator Normal *Test Relief Number: Location Function Class gory S-ize Type Type Position Required Request MOV-2289A B-5 Norihal Charging Header LT*, EV Isolation 2 A 3 GA MOV 0 ST, VP 19 RCS Loop Fill Header FCV-2160 A-3 Isolation 2 AE 2 GA PN C LT*, VP None Seal Water Return Line*
RV-2382B F-3 to VCT 2 C 2 RV SA C SP 1 MOV-2289B B-5 Normal Charging Header 2 B 3 GA MOV 0 EV, ST 19 Isolation VP S2-004c-3 4_-61 Rev. 1
April 1, 1987

Surry Power Station Unit No. 2 Inservice Testing ASME Code. Class 1, 2, and 3 Valves System Name: Chemical and Volume Control Drawing No. 11548-FM-88C Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request RV-2203 H-1 Letdown Header Rel:i,.ef 2 C 2 RV SA C SP 1 HCV-2200A H-2 HCV-2200B H-2 LT*, EV HCV-2200C H-2 Letdown Orifice Isolation 2 A 2 GA PN oc ST, VP 34 Seal Water Return to RV-2382A H-4 Pressurizer Relief Tank 2 C 2 RV SA C SP 1 2-CH-309 J-3 Normal Charging 2 AC 3 CK SA 0 CV, LT* 9 Isolation Check Valve S2-004c-3 l~-62 Rev. 1 April 1, 1987
,.
Surry Power Station Unit No. 2 Inservice Testing
ASME Code Class 1, 2, and 3 Valves System Name: Safety Injection Drawing No. 11548-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-2860A, B B-8, E-8 ment Sump 2 A 12 GA MO *C ST, VP None Low Head Safety Injection Pump Suction from 'contain-2-SI-56, 47 C-8, F-8 ment Sump Check 2 C 12 CK SA C CV 20 Low Head Safety Injection Pump Suction from Refueling EV ,ST MOV-2862A, B G-9, G-8 Water Storage Tank 2 B 12 GA MO 0 VP None Low Head Safety Injection Pump Suction from Refueling 2-SI-46A, B G-9, G-8 Water Storage Tank Check 2 C 12 CK SA C CV 21 Low Head Safety Injection 2-SI-327, 50' D-7, G-7 Pump Discharge Check 2 C 10 c;;K SA C CV 21 Low Head Safety Injection Pump Discharge to High Head EV ,ST MOV-2863A, B E-6, G-6 Safety Injection Pump 2 B 8 GA MO C VP Suction None Low Head Safety Injection MOV-2885A, B D-7, G-7 Pump Recirculation to ' EV, ST C, D G-7, E-7 Refueling Water Storage 2 B 2 GA MO 0 VP None Tank Low Head Safety Injection Pump Recirculation to 2-SI-61~ 53 D-7, G-7 Refueling Water Storage 2 C 2 CK SA C CV None I
S2-004c-3 4-63 Rev. I April 1, 1987
System Name: Safety Injection
Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves Drawing No.
11548-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 Discharge to Reactor EV, MOV-2864A, B D-6, G-5 Coolant System Cold Legs 2 B 10 GA MO 0 ST, VP None RV-2845A, 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-2890 A, B B-6, B-5 Hot Legs 2 AE 10 GA MO C ST, VP None Low Head Safety Injection to Reactor Coolant System LT*,EV MOV-2890C B-6 Cold Legs 2 AE 10 GA MO 0 ST, VP 22 MOV-2869A, B A-3, I-3 High Head Safety Injection LT*, EV 2842 A-1 to Reactor Coolant System 2 AE 3 GA MO C ST, VP 23 Boron Injection Tank LT*, EV MOV-2867 C, D B-1, B-2 Outlet Isolation 2 A 3 GA MO C ST, VP 24 S2-004c-3 4-64 Rev. 1 April l, 1987

Surry Power Station Unit No. 2 Inservice Testing 1 ASME Code Class 1' 2, and 3 Valves System Name: Safety Injection Drawing No. 11548-Fl1-89A Valve Drawing Code .Cate- Valve Actuator Normal ' Test Relief Number Location C Function Class gory Size Type Type Position Required Request LT*, EV TV-SI-200 B-4 Nitrogen Accumulators 2 A 1 GA PN 0 . ST, VP 34 2-SI-73 A-5 Accumulators Isolation 2 AE 3/4 GL Man C LT* None 2-SI-32 A-5 Accumulator Isolation 2 AE 1 GL Man C LT* None 2-SI-150 C-1 Boron Injection Tank 2 AE 3/4 GL Man 0 LT* None High Head Safety Injection 2-SI-174 B-3 to RC System 2 AE 3/4 GL Man C LT* None S2-004c-3 4-65 Rev. 1 April 1, 1987

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: R.W.S.T. Cross Tie Drawing No. 11548-FM-89A Valve Drawing Cod,e Cate- Valve Actuator Normal Test Relief Number Location Function Class gory. Size Type Type Position Required Request TV-SI-202A F-4 Unit No. 1 RWST to Unit ST, EV TV-SI-202B F-4 No. 2 RWST Cross Tie 2 B 8 GA PN C VP None.
Charging Pump Suction from 2-SI-25 F-4 RWST Check Valve 2 C 8 CK SA C CV 28 Charging Pump Suction from 2-SI-400 H-4 RWST Che.ck Valve 2* C 10 CK SA C CV 28 S2-004c-3. 4-66 Rev. 1 April 1, 1987

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Safety Injection Drawing No. 11548-FM-89B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request RV-2858 A, B C-4, G-5 Accumulator Tank Relief C C-7 2 C 1 RV SA C SP 1 2-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, 30 MOV-2865 A, B C-5, G-6 EV, ST C C-8 Accumulator Discharge 2 B 12 GA MO 0 VP None 2-SI-88, 91 A-2, A-2 94, 238 A-3, B-2 Safety Injection to RCS 239, 240 B-2, A-3 Hot Legs 1 AC 6 CK SA C CV, LT 27, 30 2-SI-235, 236 B-1, B-1 High Head Safety Injection 237 B-2 to RCS Cold Legs 1 c 2 CK SA C CV 27 2-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, 30 2-SI-224, 225 J-1, J-1 High Head Safety Injection Check Valves at Containment 2 C 3 CK SA C CV 27 Penetrations Low Head Safety Injection 2-SI-228, 229 J-3, J-3 Check Valves at Containment 2 C 6 CK SA C CV 27 Penetrations 2-SI-226, 227 J-2, J-3 High Head Safety Injection 1 C 3 CK SA C CV 27 Check Valves at Containment Penetrations S2-004c-3 4-67
Rev. 1 April 1, 1987

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Na:me :' Safety Injection Drawing No. 11548-FM-89B Valve Drawing Code Cate- Valve* Actuator Normal Test Relief Number Location Fu:nction Class gory Size Type. Type Position Required Request 2-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~201A, B J-5, J-5 Retief Line Isolation 2 A 1 GA PN 0 ST, VP 34 2-SI-234 J-;4 Nitrogen Accumulators 2 AC 1 CK SA C CV, LT* 9 Accumulator Return to RV-2859. I-4 RWST Relief 2 C .3/4 RV SA C SP 1 S2-004c-3. 4-68 Rev. 1 April 1, 1987
*
Surry Power Station Unit No. 2 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-200 G-5 Suction Line to Hydrogen LT*, ST TV-GW-201 G-5 Analyzer - Unit 1 2 A 3/8 GA sov C EV, VP 33,34 TV-GW-202 G-6 Discharge Line to TV-GW-203 F-6 Hydrogen LT*, ST Analyzer - Unit 1 2 A 3/8 GA sov C EV, VP 33,34 TV-GW-204 G-3 Suction Line to TV-GW-205 G-2 Hydrogen LT*, ST Analyzer - Unit 2 2 A 3/8 GA sov C EV, VP 33,34 TV-GW-206 G-4 Discharge Line to Hydrogen LT*, ST TV-GW-207 F-4 Analyzer - Unit 2 2 A 3/8 GA sov C EV, VP 33,34 TV-GW-211A H-2 LT*, ST TV-GW-211B G-2 Containment 'Grab Sample 2 A 3/8 GA sov C EV, VP 34 S2-004c-3 4-69 Rev. 1 April 1, 1987

Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Reactor Cavity Purification Drawing No. i1448-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-2-RL-5, 2-RL-3 H-4, G-4 tion Return Line 2 AE 3 DA Man C LT* I None Reactor Cavity Purifica-2-RL-13, 2-RL-15 H-6, G-6 tion Return Line 2 AE 3 DA Mnn C LT* None S2-004c-3 4-70 Rev. 1 April 1, 1987
System Name: Steam Generator Blowdown
Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves Drawing No. 11548-FM-124A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request TV-BD-200 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 *o VP 29,34 S2-004c-:-3 4-71 .Rev. 1 April 1, 1987

Surry Power Station Unit No. 2 Inse~vice 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 2-RM-03 D-8 Return Line 2 AC 3/4 CK SA 0 LT*, CV 9 Isolation on Monitor LT*, EV TV-RM-200A F-8 Return Line 2 A 3/4 GA PN 0 ST, VP 34 TV-RM-200B F-4 Isolation on Monitor LT*, EV TV-RM-200C E-4 Return Line 2 A 3/4 GA PN 0 ST, VP 34 S2-004c-3 4-72 Rev * .1 April 1, 1987
I.
Surry Power Station Unit No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves 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-103 J'-5 SOV-EE-102 J-5 Diesel Fuel Oil Pump SOV-EE-104 H-7 Discharge Valves NC B 1 GA sov C EV 36 S2-004c-3 4-73
Rev. 1 April 1, 1987

Surry Power Statfo~ Uri.it No. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Containment Purge Drawing No. 11548-FB-6A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request MOV-VS-200A B-5 Containment Purge Supply MOV-VS-200B B-5 MOV's 2 AE 36 BF MOV C LT>'<, VP. None J
MOV-VS-202 B-5 Containment Vacuum Breaker 2 AE 18 BF MOV C LT*, VP None MOV-VS-200C B-5 Containment Purge Exhaust MOV-VS-200D B-5 MOV's 2 AE 36 BF MOV C LT*, VP None Containment Purge Exhaust MOV-VS-201 B-5 Bypass 2 AE' 8 BF MOV C LT* None S2-004c-3 > Lf-7 4 Rev. 1 April 1, 1987

Surry Power Station Unit No. 2 Inservice Testing ASHE Code Class 1, 2, and 3 Valves System Name: Diesel Air Starting System Drawing No. 11448-FB-46B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request SOV-EG-'200A I-4 Diesel Air Start System SOV-EG-200B K-4 Solenoid Valves NC B 1 GA sov C EV,VP 37 S2-004c-3 4-75 Rev. 1 April 1, 1987

Surry Power Station Unit No*. 2 Inservice Testing ASME Code Class 1, 2, and 3 Valves' Sys.tern Name: Containment Fire Protection Drawing No. 11448-FB-47B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request 2-FP-151 H-3 Conta~nment Stand Pipe 2-FP-152 G-3 Supply 3 AE 4 BA Man C LT* None i '
S2-004c-3 4-76 Rev. 1 April 1, 1987
4.3.5 VALVE TEST PROGRAM RELIEF REQUEST
Relief request identify Code requirements which are impractical for Surry Unit 2 and provide justification for the requested exception. Where appropriate, alternate testing to be performed in lieu of Code requirements is proposed .
S2-004d 4-77 Rev. 1 April 1, 1987
RELIEF REQUEST 1
Systems :
Valve(s):
Category:
Various Valves affected by this request are identified by Table A Class Function:
Section XI Code Requirement For Which Relief Is Requested Safety and relief valve setpoints are tested in accordance with PTC-25.3-1976 as directed by IWV-3512.
Basis For Request These valves are adequately tested in Accordance with PTC-25.3-1976 Sections 4.09l(a) (2) and 4.091(c) (1).
Alternate Testing Proposed Main Steam safety valves will be tested in accordance with PTC-25.3-1976 Section 4.091 (a) (2). Other safety .and relief valves will be tested in accordance with Section 4.091 (c) (1) .
S2-004d 4-78 Rev. 1 April 1, 1987
RELIEF REQUEST 1 TABLE A Valve Category Class Function SV-MS-201A, B, C C 2 Main Steam Safety Valves SV-MS-202A, B, C SV-MS-203A, B, C SV-MS-204A, B, C
, SV-MS-205A, B, C RV-MS-201A C 2 Main Steam PORV RV-MS-201B RV-MS-201C RV-CC-219A C 3 Component Cooling from RHR RV-CC-219B Heat Exchanger Relief Valve RV-CC-216A C 3 Component Cooling Reactor RV-CC-216B Coolant Pump RV-CC-216C RV-CC-224 C 3 Component Cooling Piping Relief Valve RV-CC-218 C 3 Component Cooling from Excess Letdown Heat Exchanger Relief.
RV-2721 C 2 RHR System Relief Valve
S2-004d 4-79 Rev. 1 April 1, 1987
RELIEF REQUEST 1
SV-2551A SV-2551B Valve Category AC TABLE A (CONT'D)
Class 1
Function Pressuri~er Safety Valves SV-2551C RV-2209 C 2 Reactor Coolant System Letdown Relief Valve RV-2257 C .2 Volume Control Tank Relief Valve RV-2203 C 2 Letdown Header Relief RV-2845A, B, C C *2 Low Head Safety Injection Flow Path Relief RV-_2858A, B, C C 2 Accumulator Tank Relief Valve RV-2382B C 2 Seal Water Return Line tci VCT RV-2382A C 2 Seal Water Return to Pressurizer Relief Tank RV-2859 C 2 Accumulator Return to RWST Relief
S2-004d 4-80 Rev. 1 April 1, 1987
RELIEF REQUEST 2
System Valve(s):
Main Steam TV-MS-201A TV-MS-201B TV-MS-201C Category: B Class 2 Function: Maih Steam Line Trip Valves Section XI Code RequireTQent -
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 Propo~ed Full stroke exercise during each cold shutdown or startup in Technical Specification .
accordance with
S2-004d 4-81 Rev. 1 April 1, 1987
RELIEF REQUEST 3
System Valve(s):
Hain .Steam NRV-MS-201A NRV-MS-201B NRV-MS-201C NRV-MS-202A NRV-MS-202B NRV-MS-202C Category: C Class 2 Function: Main Steam Non-Return Valves Section XI Code Requirements For Which Relief Is Requested I
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) *
S2-004d 4-82 Rev. 1 April 1, 1987
RELIEF REQUEST 4
System Valve(s):
Auxiliary Feedwater Valves affected by this request are identified by Table B.
Category:
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 the~e valves for operability frequently than every three months)
every cold shutdown (but not more
S2-004d 4-83 Rev. 1
~pril 1, 1987
RELIEF REQUEST 4 TABLE B Valve Category
Class Function 2-FW-27 C 2 Auxiliary Feedwater 2-FW-5.8 Header Check Valves at 2-FW-89 Main Feedwater Header.
2-Ftv..:.131 C 2 Auxiliary Feedwater 2-FW-131 Header Check Valves 2-FW-133 at Containment 2-FW-:-136 Penetration.*
2-FW-138 2-FW-142 C 3 Auxiliary Feedwater Pump 2-FW-157 Discharge Check Valves.
2-FW-172 2-FW-272 C 2 Check Valves at 2-FW-273 Containment penetration (Cross-Connectfor Unit 2 Aux. Feed. from Unit 1).
2-FW-305 C 2 Check Valves at Con-2-FW-306 tainment Penetration
( Cr o's s-Connec t for Unit 2 Aux
Feed. from Unit 1) .
S2-004d 4-84 Rev. 1 April 1, 1987
RELIEF REQUEST 5
System Valve(s):
Feedwater 2-FW-10 2-FW-12 2-FW-41 2-FW-43 2-FW-72 2-FW-74 Category: C Clas.s 2 Function: Main Feedwater check valves at Containment Penetrations.
Section XI Code Requirement For Which Relief Is Requested Exercise valve every three months.
Basis For Request Closure of these valves during power operation would require securing feedwater which would result in reactor ttip. Cold shutdown testing of valves /.
using flow to. verify closure is inconclusive due to the low ~P across the valve disc.
Alternate Testing Proposed These check valves will be tested by disassembling and inspecting them every refueling shutdown for full stroke (not more than 24 months) *
S2-004d " 4-85 Rev. 1 April 1, 1987
RELIEF REQUEST 6
Relief Request Withdr2.wn
S2-004d 4-86 Rev. 1 April 1, 1987
RELIEF REQUEST 7
System Valve(s):
Category:
Component Cooling Valves affected by this request are identified by Table C.
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 qperability frequently than three months) .
every cold shutdown (but not more
S2-004d 4-87 Rev. 1 April 1, 1987
RELIEF REQUEST 7
Valve 2-CC-176 Category C
TABLE C Class 3
Function Component Cooling to 2-cc-177 RHR Heat Exchangers Check valves 2-CC-242 C 3 Component Cooling to 2-CC-233 Reactor Containment 2-CC-224 Air Recirculation Coolers
S2-004d 4-88 Rev. 1 April 1, 1987
RELIEF REQUEST 8
System Valve(s):
Category:
Component Cooling Valves affected by this request are identified by Table D.
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) *
S2-004d 4-89 Rev. 1 April 1, 1987
RELIEF REQUEST .8
TABLED Valve Category Class Function 2-CC-l C 3 Component Cooling to
.2-CC-58 Reactor Coolant 2-CC-59 Pumps TV-CC-205A B 3 Component Cooling TV-CC-205B from Reactor TV-CC-205C Coolant Pumps TV-CC-207 B 3 Component Cooling from Reactor Coolant Pumps
S2-004d 4-90 Rev. 1 April 1, 1987
RELIEF REQUEST 9
System Valve(s):
Category:
Various Valves affected by this request are identified in Table E.
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. Due to the Jfact that removing system from operation is required and these systems are required even at cold shutdown, these valves will be tested every refueling shutdown. The only way to verify valve closure is- leak rate testing which will be performed at refueling outages when the Appendix J leak rate testing is performed *
Alternate Testing Proposed These valves will be subject to reverse flow during performed during each refueling
leakage test which are
S2-004d 4-91 Rev. 1 April 1, 1987
RELIEF REQUEST 9 TABLE E Valve Category Class Function 2-IA-864 AC 2 Instrument Air to Containment 2-IA-868 AC 2 Instrument Air to Containment 2-RM-3 AC 2 Isolation on Monitor Return line.
2-RC-20 AC 3 Primary Grade water to PZR Relief Tank 2-SI-234 AC 2 Nitrogen Accumulators N supply.
2 2-CH-309 AC 2 Normal Charging Iso-lation Check Valve
S2-004d Rev. 1 April 1, 1987
RELIEF REQUEST 10
System Valve(s):
Containment and Recirculation Spray 2-RS~ll 2-RS-17 2-CS-13 2-CS-14 2-CS-105 2-CS-104 Category: AC (2-RS-11,17 and 2-CS-13,14) and C (2-CS-105, 104)
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.
Because scaffolding and dismantling of valves are required, they will be tested every refueling shutdown *
Alternate resting Proposed Full stroke manual testing will be performed each refueling shutdown *
S2-004d 4-93 Rev. 1 April 1, 1987
RELIEF REQUEST 11
System Valve(s):
Residual Heat Removal 2-RH-5 2-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 montqs) .
S2-004d 4-94 Rev. 1 April 1, 1987
RELIEF REQUEST 12
System Valve(s):
Residual Heat Removal MOV-2700 HOV-2701 Category: A Class 1 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 cannot be opened at elevated Reactor Coolant s*ystem pressure.
2. Overpressurization of the suction line may cause a 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)
S2-004d 4-95 Rev. 1 April 1, 1987
RELIEF REQUEST 13
System Valve(s):
Residual Heat Removal MOV-2720A MOV-2720B Category: A Class 1 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 the MOV shut and if its respective check valve is leaking, there is no way to determine whether or not an overpressure condition exists before opening the MOV.
If a MOV was opened and an overpressure condition did exist between the MOV and the RCS, the primary pressure of 2235 psig will be released on the Residual Heat Removal System with a relief valve of 700 psig. This would be an unnecessary challenge to the Residual Heat Removal System.
2. Since the MOV is also part of the discharge piping of an accumulator, there is a possibility of discharging an accumulator into the RHR system and disabling it. The accumulators are maintained at pressure above the normal operating or shutdown pressure of the Residual Heat Removal System. Opening of these valves would dump accumulator water into the Residual Heat Removal System. This will dilute the boron concentration of the accumulator as well as lower its level and pressure, which is a violation of Technical Specifications.
Alternate Testing Proposed Exercise these valves for operability every cold shutdown (but not more frequently then three months) *
S2-004d 4-96 Rev. 1 April 1; 1987
RELIEF REQUEST 14
System Valve (s):
Chemical and Volume Control 2-CH-258 2-CH-267 2-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 overpressurization of the Reactor Coolant System and could force a safety system to function.
Alternate Testing Proposed These valves will be partialiy stroked every three months and full flow tested each refueling *
S2-004d 4-97 Rev. 1 April 1, 1987
RELIEF REQUEST 15
System Valve(s):
Chemical and Volume Control LCV-2115C LCV-2115E Category:
B Class 2 Function: Charging Pump Suction from Volume Control Tanks 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 System boron inventory, which would cause a plant transient.
Alternate Testing Proposed These valves will be exercised during each cold shutdown (but not more frequently than every three months) .
S2-004d 4-98 Rev. 1 April 1, 1987
RELIEF REQUEST 16
System Valve(s):
Category:
Chemical and Volume Control MOV-2373 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 MOV-2373 is not cycled quarterly because its failure in the closed position would challenge the operation of the Charging Pumps. The individual recirculation valves (MOV-2275 A,B,C) are cycled, but if one of them were to fail in the closed position, the other pumps can be used. Since the three recirculation lines go through MOV-2373, its failure in the closed position would jeopardize the operation of the three charging pumps *
Alternate Testing Proposed This valve will be exercised each cold shutdown (but not more frequently three months) .
than
S2-004d Lf-99 Rev. 1 April 1, 1987
RELIEF REQUEST 17
System Valve(s):
Category:
Chemical and Volume Control MOV-2381 A
Class 1 Function: Reactor Coolant Pump Seal Water Return Section XI Code Requirement For Which Relief ts 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) *
S2-004d 4-100 Rev. 1 April 1, 1987
RELIEF REQUEST 18
System Chemical and Volume Control Valve(s):. TV-2204 Category: A Class 2 Function: Reactor Coolant System Letdown Isolation Trip Valve Secti9n 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) *
S2-004d 4-101 Rev. 1 April 1, 1987
RELIEF REQUEST 19
System Valve(s):
Chemical and Volume Control MOV-2289A MOV-2289B Category: A (MOV-2289A) and B (MOV-2289B)
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) .
S2-004d Rev. 1 April 1, 1987
RELIEF REQUEST 20
System Valve(s):
Safety Injection 2*-SI-56 2....;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 portiqns of the system.
Alternate Testing Proposed These valves will be partial stroked exercised during each refueling.
r
S2-004d 4-103 Rev. 1 April 1, 1987
RELIEF REQUEST 21
System Valve(s):
Category:
Safety Injection Valves affected by this request are identified in Table F.
Class Function:
Section XI Code Requirement For Which Relief Is Requested Exercise valves every three months.
Bapis 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 partially stroked every three months through the pump recirculation line. During cold shutdown, the Reactor Coolant System presssure still prevents full flow testing of the check valve. During cold shutdown, the charging flow could cause an overpressurization condition
Alternate Testing Proposed These valves will be partially stroked every three months and full stroked every refueling .
S2-004d 4-104 Rev. 1 April 1, 1987
RELIEF REQUEST 21 TABLE F Valve Category Class Function 2-SI-46A C 2 Low Head Safety 2-SI-46B Injection Pump Suction from Refueling Water Storage Tank Check 2-SI-327 C 2 Low Head Safety 2-SI-50_ Injection Pump Discharge Check S2-004d 4-105 Rev. 1 April 1, 1987
RELIEF REQUEST 22
System Valve(s):
Category:
Safety Injection MOV-2890C A
Class 2 Function: Low Head Safety Injection to Reactor Coolant System Cold Legs Section XI Code Requirement For Which Relief Is Requested Exercise valve every three-months.
Basis For Request In accordance with Technical Specification 3.3.A.8, during power operation, the A.C. power shall be removed from MOV-2890C with the valve in the open position. If this valve was stroked during power operation and failed in the closed position, the Low Head Safety Injection System would be rendered inoperable.
Alternate Testing Proposed This valve will be exercised during each cold shutdown (but not more frequently than every three months) *
S2-004d 4-106 Rev. 1 April 1, 1987
RELIEF REQUEST 23
System Valve(s):
Safety Injection MOV-2869A MOV-2869B MOV-2842 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 the High Head Safety Injection system. During cold shutdown, the charging flow could cause an overpressurization of the Reactor Coolant System and could force a safety system to function.
Alternate Testing Proposed These valves are full stroke exercised during refueling outages *
S2-004d 4-107 Rev. 1 April 1, 1987
RELIEF REQUEST 24
System Valve(s):
Safety Injection NOV-2867C MOV-2967D 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 These valves cannot be exercised during power operation. Opening these valves would allow excess charging flow into the Reactor Coolant System causing a reactivity transient.
Alternate Testing Proposed
These valves will be exercised during frequently than every three months) .
each cold shutdo¥O (but not more
S2-004d 4-108 Rev. 1 April 1, 1987
RELIEF REQUEST 25
Relief Request Withdrawn
S2-004d 4-109 :Itev~ 1 April 1, 1987
RELIEF REQUEST 26 System Safety Injection Valve(s): 2~sI-107 2-SI-109 2-SI-128 2-SI-130 2-SI-145 2-'SI-147 Category: A and 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 fiow 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 thfs calculation and partial stroke testing presently performed, full stroke testing will not be performed.
Alternate Testing Proposed These valves will be partially stroked each refueling *
S2-004d 4-110 Rev. 1 April 1, 1987
RELIEF REQUEST 27 System Safety Injection Valve(s): Valves affected by this request are identified in Table G.
Category:
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, an overpressurization of the Reactor Coolant System could occur 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 *
S2-004d 4-111 Rev. 1 April 1, 1987
RELIEF REQUEST 27 TABLE G Valve Category Class Function
~
2-SI-88, 91 AC 1 Safety Injection to RCS Hot Legs 2-SI-94, 238 2-SI-239, 240 2-SI-235 AC 1 High Head .Safety Injection to 2-SI-236 RCS Cold Legs 2-SI-237 2-SI-241 AC 1 Low Head Safety Injection to 2-SI-242 RCS Cold Legs 2-SI-243 2-SI-224, 225 C 2 High Head Safety Injection Check 2-SI-226, 227 *C 1 Valve at Containment Penetrations 2-SI-228, 229 C 2 Low Head Safety Injection Check Valves at Containment 2-SI-79, 82, 85
. ~
A 1 Penetrations Safety Injection to RCS Cold Legs
S2-004d 4-112 Rev. 1 April 1, 1987
RELIEF REQUEST 28
System Valve(s):
R.W.S.T. Cross Tie 2-SI-25 2-SI-400 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 storag~ tank. This would cause a sudden increase in reactor coolant boron inventory.
Alternate Testing Proposed
Exercise the valves for operability frequently than every three months) .
every cold shutdown (but not more
S2-004d 4-113 Rev. 1 April 1, 1987
RELIEF REQUEST 29
System Valve(s):
Steam Generator Blowdown TV-BD-200A TV-BD-200B TV-BD-200C TV-BD-200D TV-BD-200E TV-BD-200F 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 reopen, 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) *
-S2-004d 114 Rev. 1 April 1, 1987
RELIEF REQUEST 30
Sytems Valve(s):
Various Valves affected by this request are identified by Table H.
Category:
Class Function:
Section XI Code Requirement For Which Relief Is Requested Valves shall be leak tested in accordance with IWV-3426 and IWV-3427.
Basis For Request These valves are adequately leak tested in accordance with Technical Specification Sections 3.1.C and 4.3 and ASME Section XI, Subsection IWB-5000.
Alternate Testing Proposed The valves in Table H will be leak tested in accordance with Technical Specification Sections 3.1.C and 4.3 and ASME Section XI, Subsection IWB-5000 .
S2-004d 4-115 Rev. 1 April 1, 1987
Valve Category RELIEF REQUEST 30 TABLE H Class Function HCV-2556A A 1 Loop Fill Boundary HCV-2556B HCV-2556C SV-2551A AC 1 Pressurizer Safety Valves SV-2551B SV-2551C MOV-2535 A 1 PORV Block Valves MOV-2536 PCV-2456 A 1 PORV PCV-2455C 2-SI-107, 109 AC 1 Accumulator Discharge Check 2-SI-128, 130 Valve 2-SI-145, 147 2-SI-88, 91 AC 1 Safety Injection to RCS Hot Legs 2-SI-94, 238 2-SI-239, 240 MOV-2700. A 1 RHR Suction from Reactor Coolant MOV-2701 System MOV-2720A A 1 RHR Discharge to Reactor Coolant MOV-2720B System 2-SI-241 AC 1 Low Head Safety Injection to RCS 2-SI-242 Cold Legs 2-SI-243
S2-004d 4-116 Rev. 1 April 1, 1987
RELIEF REQUEST 31 System Reactor Coolant Valve(s): SOV-RC-200A-l S0V-RC-201A-l S0V-RC-200A-2 S0V-RC-201A-2 SOV-RC-200B-l S0V-RC-201B-l SOV-RC-200B-2 S0V-RC-201B-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 vent locations 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 because they discharge to containment atmospher~ .
Alternate Testing Proposed These valves will be tested each refueling by exercising and verifying flow .
S2-004d 4-117 Rev. 1 April 1, 1987
RELIEF REQUEST 32 System Main Steam Valve(s): HCV-MS-204 Category: B Class 2 Function: Decay Heat Release Control Valve Section XI Code Requirements For Which Relief Is Requested Exercise valves every three months.
Basis For Request Opening of this valve during power would result in added steam load to the reactor. The opening and closing of this valve at power could result in an overpower condition and possible reactor trip as reactor. power increases to meet the new steam load.
Alternate Testing Proposed
Exercise these valves for operability frequently than every three months).
every cold shutdown (but not more
S2-004d 4-118 Rev. 1 April 1, 1987
RELIEF REQUEST 33
System Valve(s):
. Gaseous Waste TV~GW-200 TV-GW-204 TV-GW-201 TV-GW-205 TV-GW-202 TV-GW-206 TV-GW-203 TV-GW-207 Category: A Class 2 Function: Suction line/discharge line to hydrogen analyzer *
.Section XI Code Requirement For Which Relief Is Requested Valve position indicator verification at least once every 2 years.
Basis For Request These valves are 3/8" solenoid valves whose valve movement cannot be locally observed *
Alternate Testing Method Alternatively these valves will be subjected to a leak rate test every refueling (not to exceed 2'4 months). During this leak rate test, the local valve position and remote valve position indication are verified the same .
S2-004d 4-119 Rev. 1
'April 1, 1987
RELIEF REQUEST 34
sy*stem Valve(s):
Various Valves affected by this request are identified in Table J.
Category.:
Class Function:
Section XI Code Requirement For Which Relief Is Requested
- Section XI, IWV-3417 (a) "Corrective Action" Basis For Request These valves have a normal stroke time of 2 seconds or less, they are rapid acting valves.
Alternate Test Proposed Whenever the stroke of these valves exceed 2 seconds, IWV-3417(a) will be applied .
S2-004d 4-120 Rev. 1 April 1, 1987
RELIEF REQUEST 34
Valve TV-MS-210 TV-CC-205 A,B,C Category B
B TABLE J Class 2
3 Function Main Steam Drain to Blowdown Component Cooling from RCP Tv-cc...:.207 B 3 Component Cooling from RCP TV-CC-209 A,B B 3 Component Cooling from RHR Heat Exchanger TV-IA-201 A,B A 2 Instrument Air Suction from Containment TV-IA-200 A 2 Instrument Air Discharge to Containment TV-SS-203 A,B A 2 Residual Heat Removal System Sample TV-SS-200 A,B A 1 Pressurizer Liquid Space Sample TV-SS-201 A,B A 1 Pressurizer Vapor Space Sample TV-SS-206 A,B A 1 Primary Coolant Hot Leg Sample TV-SS-202 A,B A 1 Primary Coolant Cold Leg Sample*
TV-SS-204 A,B A 2 Pressurizer Relief Tank Gas Space Sample TV-DA-200 A,B A 2 Reactor Containment Sump Pump Discharge Isolation TV-DA-203 A,B A 2 Post Accident Sample Return Line TV-DG-208 A,B A "
L. Primary Drain Transfer Pump Discharge Isolation TV-VG-209 A,B A 2 Gas Vent Header Isolation TV-LM-200 A-H A 2 Leakage Monitoring System Isolation TV-CV-250 A-D A *2 Containment Vacuum Pump Suction Isolation PCV-2456 A 1 Pressurizer Power Operated Relief Valve PCV-2455C A 1 Pressurizer Power Operated Relief Valve TV-2204 A 2 RCS Letdown Isolation Trip Valve HCV-2200 A,B,C A 2 Letdown Orifice Isolation TV-SI-200 A 2 Nitrogen Accumulators TV-SI-201 A,B A 2 Accumulator Nitrogen Relief Line Isolation TV-GW-200-207 A 2 Suction/Discharge Line to Hydrogen Analyzer TV-GW-211 A,B A 2 Containment Grab Sample TV-BD-200 A-F B 2 Steam Generator Blowdown Isolation TV-RM-200 A,B,C A 2 Isolation on Monitor Return Line
S2-004d 4-121 Rev. 1 April 1, 1987
RELIEF REQUEST 35
System Valve(s):
~c PCV-2456 PCV-2455C Category: A Class 1 Function: Pressurizer Power Operated Relief Valves.
Section XI Code Requirement For Which Relief Is Requested Exercise valves every three months.
Basis For Request These pressurizer power operated relief valves have shown a high probability of sticking open and are not needed for overpressure protection at normal operation conditions. Routine exercising during normal power operation is not practical since valves are not required for overpressure protectiop unless the primary system is under 500 psig
Alternate"Testing Proposed Exercise these valves for operability every cold shutdown (but not more frequently than three months) .
S2-004d 4-122 Rev. 1 April 1, 1987
RELIEF REQUEST 36
System Valves EE SOV-EE-102 SOV-EE-104 SOV-EE-103 Category: B Class NC Function: Diesel Fuel Oil pump discharge values.
Section XI Requirement For Which Relief Is Requested Exercise valves for operability every three months.
Basis For Request These valves have actuation times considerably under a second and there is no visual reference on the solenoid valve to indicate when it has stroked.
Alternate Testing Proposed
These solenoid .valves will be stroke tested monthly by observing that the solenoid valves perform their intended function (fuel oil is flowing to the day tank after the solenoid valve has been opened) .
S2-004d 4-123 Rev. 1 April 1, 1987
RELIEF REQUEST 37
System Valve(s):
EG S0V-EG-200A S0V-EG-200B Category: B Class NC Function: Diesel Air Start System Solenoid Valves.
Section XI Code Requirement For Which Relief Is Requested Exercise valves for operability every three months.
Basis For Request These valves have actuation times considerably under a second and there is no visual reference on the solenoid valve to indicate when it has stroked.
Alternate Testing Proposed
These solenoid valves will be stroke tested monthly by observing that the solenoid valves perform their intended function (signal the diesel to start and if it does, the solenoid valve was stroked successfully) *
S2-004d 4-124 Rev. 1 April 1, 1987
4.4 REPORTING OF INSERVICE TEST RESULTS
4.4.1 PUMP INSERVICE PROGRAM Records of Pump Inservice Test Results will be in accordance with the intent of Article IWP-6000.
established for each pump and will include:
Files will be
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. values 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 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 the Authorized Nuclear Inservice Inspector and the NRC.
4.4.2 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 observed quantities where applicable
c. identification of instruments used where applicable
d. comparisons with allowable ranges of test values and analysis of deviations.
e. maintenance history
f. signature of the person or persons responsible for conducting and analyzing the test .
-S2-004d
3. Summaries of maintenance report numbers, etc.
4-125 histories may be maintenance Rev. 1 April 1, 1987
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 the. Authorized Nuclear Inservice Inspector and the NRC .
S2-004d 4-126 Rev. 1 April 1, 1987
4.5 QUALITY ASSURANCE PROGRAM
The Pump conducted Standard Station .
and Valve Inservice Test Program activities will be in accordance with the Nuclear Operation Department Manual and Technical Specifications for Surry Power
S2-004d 4-127 Rev. 1 April 1, 1987
Descriptions of changes between Revision O and Revision 1 for Surry Unit 2 System Pressure Tests Program are provided below. The page numbers refer to Revision 1.
Description of Change 5-2 The Section has been renumbered and Section 5.4 renamed.
5-3 An introduction was added.
5-4 Surry Unit 2 is currently in the second inspection interval. The verb tense has been changed accordingly.
5-5 Relief Request 21 has been added to Item B4.10.
5-7 Relief Request 4 has been withdrawn from Items Bl5.51 and Bl5.71.
5-8 Relief Request 16 has been withdrawn from Items C7.21 and C7.41.
Relief Requests 20 and 22 have been added to Items C7.21 and C7.41 .
5-10 5-12 Relief D2.10.
Request 14 has been withdrawn from Item Class I, II and III has been replaced by Class 1, 2 and 3.
document.
This change occurs throughout the The phrase, "but depressurizes at 1000 psig on the primary", has been deleted.
For Note 4, the following drawings were added or deleted:
Added Deleted 11448-FM-68B l 1548-FM-72B 11448-FM-72E 11448-FM-72C 11548-FM-84B 11448-FM-72F 11448-FM-90C 11448-FM-90A 11448-FB-47B l 1448-FM-106C For Note 4, the following drawings had the unit suffix (i.e. 11448 for Unit 1, 11548 for Unit 2) changed:
Revision 0 11548-FM-75C 11448-FM-123A 11448-FM-124A 11448-FB-6A Revision 1 11448-FM-75C 11548-FM-123A 11548-FM-124A 11548:._FB-6A S2-005a April 1, 1987
Description of Change
5-13 5-14 Note 5 was rearranged to enhance clarity.
Column title VALVE added to Note 7.
For Note 8, the following drawings were deleted:
added or Added Deleted
11448-FM-130A 11548-FM-84A
11548-FM-89A 5-15 Section 5.4 was rewritten.
5-16
The format of the pressure testing Relief Requests was changed'to a format similar to the valve Relief Requests.
Piping between check valves l-CH-312 and HCV-2310A, 2-CH-310 was moved to Relief Request 5.
Technical detail was added to the Alternate Testing Method.
5-19 Relief Request 4 was withdrawn.
5-20 Piping between check valves l-CH-312 and HCV-2310A, 2-CH-310 was added to Relief Request 5.
Alternate testing is proposed.
5-23 The following changes were made to the* column entitled, "Connected Piping":
Revision 0 Revision 1 30"-SHP-101-601 30"-SHP-101-601 to 2"-GN-123-601 to 6"-SHP-145-601 to 2"-GN-33-601 30"-SHP-122-601 30"-SHP-101-601 to 30"-SHP-122-601 to 30"-SHP-122-601 to 3"-SDHV-101-601 to 3"-SDHV-101-601 to 4"-SDHB-104-601 to 4"-SDHV-104-601 30"-SHP-101-601 30"-SHP-101-601 to 4"-,SHP-125-601 14"-WFPD-117-601 14"-WFPD-117-601 to 3/4"-CFPD-103-601 S2-005a April 1, 1987
Description of Change
5-23 The following additions were made*
entitled, "Connected Piping":
2 1/2"-WGCB-601 1"-WGCB-601 3"-RT-200-601 to the column 30"-SHP-101-601 to 1 1/2"-SHPD-106-601 The following changes were made to the column entitled, "Component":
Revision 0 Revision 1 NRV-MS-201A NRV-MS-201A 2-MS-80,81,266,74 2-MS-83,81,266 2-FW-27 2-FW-27 2-FW-10 2-FW-10 2-WT-10 2-WT-176 The following addition was made to the column entitled, "Component":
5-24 2-MS-74 The- following changes were entitled, "Connected Piping":
Revision 0 made to the column Revision 1 30"-SHP-102-601 30"-SHP-102-601 to 2"-GN-124-601 to 6"-SHP-146-601 to 2"-GN-34-601 30"-SHP-102-601 30"-SHP-102-601 to 4"-SHP-126-601 14"-WFPD-113-601 14!'-WFPD-113-601 to 3/4"-CFPD-102-601 The following additions were made to the column entitled, "Connected Piping":
2 1/2"-WGCB-601 1"-WGCB-601 3"-RT-210-601 30"-SHP-102-601
to 1 1/2"-SHPD-108-601 S2-005a April 1, 1987
Description of Change
5-24 The following changes were entitled, "Component":
Revision 0 NRV-MS-201B made to Revision 1 NRV-MS-201B the column 2-MS-112,268,113,106* 2-MS-115, 268,113 2-FW-41,58 2-FW-41,58 2-WT-177 2-WT-179 The following addition was made to the column entitled", Component":
2-MS-106 5-25 The following changes were made to the column entitled, "Connected Piping":
Revision 0 Revision 1 30"-SHP-103-601 30"-SHP-103-601 to 2"-GN-125-601 to 6"-SHP-147-601 to 2"-GN-35-601
30"-SHP-103-601 14"-WFPD-109-601 30"-SHP-103-601 to 4"-SHP-127-601 14"-WFPD-109-601 to 3/4"-CFPD-101-601 The following additions were made to the column entitled, "Connected Piping":
2 l/2"-WGCB-601 l"-WGCB-601 3"-RT-220-601 30"-SHP-103-601 to 1 l/2"-SHPD-107-601 The following changes were made to column entitled, "Component":
Revision 0 Revision 1 NRV-MS-201C NRV-MS-201C 2-MS-152,149,208 2-MS-152,151,208 143
2-FW-72 2-FW-89 2-WT-182 2-FW-72 2-FW-89 2-WT-180 S2-005a April 1, 1987
Description of Change
5-25 the following addition entitled, "Component":
2-MS-143 Editorial Change was made to the column 5-29 5-30 The following addition was made to the column entitled, "Connected Piping":
3/4"-SI-222-152 The following changes were made to the column entitled, .!.'Component":
Revision 0 Revision 1 2-SI-229 2-SI-238 2"-SI-281-1502 2-SI-239 6"-SI-249-1502 2-SI-240 5-31 Schedule For Implementation was changed from "Once each period" to "End of interval, within the last period" *
5-32 The Component Section was clarity.
rearranged to enhance Basis For Relief was rewritten to enhance clarity.
Reference to Note 3 was deleted in the Alternate Testing Method.
5-33 Technical detail was added to the Basis For Relief.
5-34 Relief Request 14 was withdrawn.
5-36 Relief Request 16 was withdrawn.
5-39 Drawing 11448-FM-71D was added to the Component Section.
The Basis For Relief was rewritten to enhance clarity.
5-40 Relief Request 20 was added.
5-41 Relief Request 21 was added.
5-42 Relief Request 22 was added .
S2-005a April 1, 1987
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 SYSTEM PRESSURE TESTS PROGRAM PLAN S2-005a 5-1 Rev. 1
{\ 0 ...
-5. 0 SECTION 5 TABLE OF CONTENTS SYSTEM PRESSURE TESTS PROGRAM PLAN
5.1 INTRODUCTION
I 5.2 - PROGRAM DESCRIPTION 5.3 SYSTEM PRESSURE TESTS 5.3.1 Class 1 Components 5.3.2 Class 2 Components
.5. 3. 3 Class 3 Components 5.3.4 Notes 5.4 SYSTEM PRESSURE TEST PROGRAM RELIEF REQUESTS S2-005a 5-2 Rev. 1
5.0 SYSTEM PRESSURE TESTS PROGRAM PLAN
5.1 INTRODUCTION
This System Pressure Test Program is applicable to the Surry Power Station Unit 2. This program covers the system pressure test requirements for ASME Class 1, 2, and 3 Components. The development, implementation and administration of the program for each class are detailed in subsequent sections
S2-005a 5-3 Rev. 1 A~ri1 1 10R7
5.2 PROGRAM DESCRIPTION 5.2.l The Surry Unit 2 System Pressure Test Program is in accordancewith the ASME Boiler and Pressure Vessel Code Section XI, 1980 Edition, Winter of 1980 Addendum-inclusive.
The 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 2 is currently in the second inspection interval of Inspection Program B, IWA-2420. This interval started May 1, 1983, and coincides with the planned implementation of the proposed inspection program contained within this document.
This proposed program will be effective at Surry Unit 2 for the second inspection interval or as modified by future ASME Code changes which are adopted at this station
S2-005a 5-4 Rev. 1
5.3 SYSTEM PRESSURE TESTS 5.3.1 CLASS 1 COMPONENTS (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 21 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
S2-005b-3 5-5 Rev. 1 April 1, 1987
ITEM NO.
'PARTS EXAM.
B. EXAMINATION CATEGORY B-P, PRESSURE RETAINING COMPONENTS TEST REQRMT.
EXAM.
METHOD ACCEPT.
STANDARD SCHEDULE NOTES RELIEF 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. ll REACTOR SYSTEM VISUAL, IWA-5250 ONE 1, 2 ,*5, 9 VESSEL HYDRO- VT-2 TEST PRESSURE STATIC RETAINING TEST, BOUNDARY TWB-5222 B15.20 PRESSUR- SYSTEM VISUAL, IWA-5250 EACH 1,5,9 IZER LEAKAGE VT-2 . REFUELING PRESSURE TEST, OUTAGE RETAINING IWB-5221 BOUNDARY Bl5.21 PRESSUR- 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-5221 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
S2-005b-3 5-6 Rev. 1 Ap*ril 1, 1987
B. EXAMINATION CATEGORY B-P, PRESSURE RETAINING COMPONENTS ITEM PARTS TEST EXAM. ACCEPT. SCHEDULE NOTES RELIEF NO. EXAM. REQRMT. METHOD STANDARD REQUEST B15.41 HEAT SYSTEM VISUAL, IWA-5250 ONE 1,2,5,6,9 EXCHANGERS HYDRO- VT-2 TEST PRESSURE STATIC RETAINING TEST, BOUNDARY IWB-5222 B15.50 PIPING SYSTEM VISUAL, IWA-5250 EACH 1,3,5,9 7 PRESSURE LEAKAGE VT-2 REFUELING RETAINING TEST, OUTAGE BOUNDARY IWB--5221 B15.51 PIPING SYSTEM VISUAL, IWA-5250 ONE 1,2,5*,9 1,3,5, PRESSURE HYDRO- VT-2 TEST 6 RETAINING STATIC BOUNDARY TEST, IWB-5222 B15.60 PUMPS SYSTEM VISUAL, IWA-5250 EACH 1,5,9 PRESSURE LEAKAGE VT-2 REFUELING RETAINING TEST, OUTAGE*
BOUNDARY IWB-5221 B15.61 PUMPS SYSTEM VISUAL, IWA-5250 ONE 1,2,5,9 3 PRESSURE HYDRO- VT-2 TEST RETAINING STATIC BOUNDARY TEST, IWB-5222 BlS.70 VALVES SYSTEM VISUAL, IWA-5250 EACH 1,3,5,9 7 PRESSURE LEAKAGE VT-2 REFUELING RETAINING TEST, OUTAGE BOUNDARY IWB-5221 BlS.71 VALVES SYSTEM VISUAL,. IWA-5250 ONE 1,2,5,9 1,5,6 PRESSURE HYDRO- VT-2 TEST RETAINING STATIC BOUNDARY TEST, IWB-5222
S2-005b-3 5-7 Rev. 1 April 1, 1987
5.3.2 CLASS 2 COMPONENTS (10 YEAR SCHEDULE)
A. EXAMINATION CATEGORY C-H. PRESSURE RETAINING COMPONENTS ITEN 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 8 VESSELS HYDRO- VT-2 TEST 6,9 PRESSURE STATIC RETAINING TEST, COMPONENTS IWC-~222 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 12,13,20,22 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 PERIOD C7.41 VALVES SYSTEM VISUAL, IWA-5250 ONE 2,4,5, 8,9,10,11 PRESSURE HYDRO- VT-2 TEST 7,9 12,13,20,22 RETAINING STATIC COMPONENTS TEST, IWC-5222
S2-005b-3 5-8 Rev. 1 April 1, 1987
5.3.3 CLASS 3 COMPONENTS (10 YEAR SCHEDULE)
A. EXAMINATION CATEGORY D-A, SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION.
ITEM PARTS TEST EXAM. ACCEPT. SCHEDULE NOTES RELIEF NO. EXAMINED REQRMT. METHOD STANDARD REQUEST Dl.10 PRESSURE SYSTEM VISUAL, NO ONCE 5,6,8,9 RETAINING INSERVICE VT-2 LEAKAGE PER COMPONENTS TEST, INSPECTION IWD-5221 PERIOD Dl.10 PRESSURE SYSTEM VISUAL, NO ONE 2,5,6, RETAINING HYDRO- VT-2 LEAKAGE 8,9 18, 19 COMPONENTS STATIC TEST, IWD-5223
S2-005b-3 5-9 Rev. 1 April 1, 1987
B~ EXAMINATION CATEGORY D-B, SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTATNMENT HEAT REMOVAL, ATMOSPHERE CLE.Af.itJP, AND REACTOR RESIDUAL HEAT REMOVAL.
ITEM PARTS TEST EXAM. ACCEPT. . SCHEDULE NOTES RELIEF NO. EXAMINED REQRMT. METHOD STANDARD. REQUEST D2 .10 PRESSURE SYSTEM VISUAL, NO ONCE 5,6,8 RETAINING IN SERVICE VT-2 LEAKAGE PER 9 C COMPONENTS TEST, INSPECTION IWD-5221 PERIOD D2.10 PRESSURE SYSTEM VISUAL, NO ONE 2,5,6 15,18 RETAINING HYDRO- VT-2 LEAKAGE TEST 8,9 19 COMPONENTS STATIC TEST;-*
IWD-5223
S2-005b-3 5-10 Rev. 1 April 1, 1987
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, niA-5250 ONCE 5,6 RETAINING INSERVICE VT-2 PER 8,9 COMPONENTS TEST, INSPECTION IWD~5221 PERIOD D3.10 PRESSURE SYSTEM VISUAL, IWA-5250 ONE 2,5,6 18 RETAINING HYDRO- VT-2 TEST 8,9 COMPONENTS STATIC TEST, IWD-5223
S2-005b-3 5-11 Rev. 1 April 1, 1987
5.3.4 NOTES
Note 1 Class 1 Systems are drawn prints:
11548-FM-64A 11548-FM-68A 11548-FM-72A on the following station 11548-FM-82A 11548-FM-86A 11548-FM-86B 11548-FM-87A 11548-FM-SSC 11548-FM-88B 11548-FM-89B These- systems are designated by a bracketed A on the station*prints.
Note 2 Class 1, 2 and 3 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 departing hot shutdown conditions when exiting a refueling shutdown. The piping is normally
pressurized to 660 psig .
2-SI-109 2-SI-130 2-SI-147 AND 2-SI-107, HCV-2850B AND 2-SI-128, HCV-2850D, MOV-2720A AND 2-SI-145, HCV-2850F, MOV-2720B Note 4 Class 2 Systems are drawn on the following station prints_:
11548-FM-64A 11548-FM-82A 11548-FM-89B 11548-FM-64B 11548-FM-83A 11448-FM-90C 11548-FM-66A 11548-FM-83B 11448-FM-llSA 11548-FM-68A 11548-FM-84A 11548-FM-123A 11448-FM-68B 11548-FM-84B 11548-FM-124A 11548-FM-71A 11548-FM-85A 11548-FM-138A l 1548-FM-72A 11548-FM-86A 11448-SPS-14A 11448-FM-72E 11548-FM-86B 11548-FB-6A 11448-FM-75C 11548-FM-87A 11448-FB-47B 11548-FM-75E 11548-FM-88A 11548-FM-75J l 1548-FM-88B 11548-FM-88C 11548-FM-89A Class 2 systems or components will be designated by a
_br~cketed Bon the station prints .
S2-005b-3 5-12 Rev. 1 April 1, 1987
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):
a) The 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.
b) Any discrepancies will be treated in accordance with IWA-5250 and the station's Repair/Replacement Program.
c) Weld leaks and excessive mechanical leaks will be addressed through* a station engineering evaluation to determine continued operability. Note that this does not apply to repair/replacements which must exhibit no leakage at the area of examination determined.in the repair/r~placement.
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 a heat exchanger will be considered complete using either method above.
Any discrepancies will be referred to the station's Repair/Replacement Program *
S2-005b-3 5-13 Rev. 1 April 1, 1987
Note 7 For identification purposes, 'piping extending beyond the valves listed below on station print 11548-FM-85A will be considered open ended and in accordance with the requirements of IWC-5222(d) for test purposes.
VALVE PIPING 2-LM-28 3/8"-LM-l ll-N7 2-LM-29 3/8"-LM-112-N7 2-LM-30 3/8"-LM,-l 13-N7 2-LM-31 3/8"-LM~fl6-N7 Note 8 Class 3 Systems are on the following station prints:
11548-FM-64A 11548-FM-72C 11548-FM-68A 11548-FM-87A 11548-FM-68B 11548-FM-88B 11548-FM-71A 11548-FM-88C 11548-FM-71B 11448-FM-130A 11548-FM-72A 11548-FM-72B These systems will be enclosed in brackets and designated by a bracketed Con the station prints
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 *
S2-005b-3. 5-14 Rev. 1 April 1, 1987
5.4. SYSTEM PRESSURE TEST RELIEF REQUESTS Relief Requests identify code requirements which are impractical for Surry Unit 2 and provide justification for the requested exception. Where appropriate, alternate testing to performed in lieu of the code requirements is proposed .
S2-005b-3 5-15 Rev. 1 April 1, 1987
RELIEF REQUEST 1
Component(s): Piping between prints:
11548-FM-89B
. 11548-FM-SSC following check valves located on station 2-SI-79 AND 2-SI-235, 2-SI-241 2-SI-82 AND 2-SI-236, 2-SI-242 2-SI-85 AND 2-SI-237, 2-SI-243
.2-SI-88 AND 2-SI-226, 2-SI-227 and 2-SI-238 2-SI-91 AND 2-SI-226, 2-SI-227 and 2-SI-239 2-SI-94 AND 2-SI-226, 2-SI-227 and 2-SI-240 Function Safety Injection System Chemical Volume and Control Class 1 Section XI Code Requirements For Which Relief Is Requested Class 1 System Hydrostatic Test, IWB-5222 Basis For Request The double check valve combination prevents pressurization of the area in between the check valves when conducting IWB-5222 on the primary system.
Alternate Testing Method 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 system will act as a boundary for the test forcing closed the first check valve in the pressure boundary.
A hydrostatic test pump will provide pressure up to 2235 psig creating a differential pressure of 100 psid, thus keeping the first check valve closed and providing a pressure boundry for the test. A normal VT-2 examination will then be conducted. Chemistry samples will be taken every 30 minutes to prevent accidental dilution of the primary system.
Schedule For Implementation This test will be conducted toward the end of the second interval within the third inspection period .
S2-005b-3 5-16 Rev. 1 April 1, 1987
RELIEF REQUEST 2 Relief Request Withdrawn
S2-005b-3 5-17 Rev. 1 April 1, 1987
RELIEF REQUEST 3
, Component(s): Pumps located on station drawing 11548-FM-88C as listed:
2-RC-P-lA 2-RC-P-lB 2-RC-P-lC Piping associated from the flange to the pump Function Chemical and Volume Control ~ystem Class 1 Section XI Code Requirements For Which Relief Is Requested Class 1 Sys~em Hydrostatic Test, IWB-5222 Basis For Request 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 *
Alternate Testing Method The normal 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 .
S2-005b-3 5-18 Rev. 1 April 1, 1987
RELIEF REQUEST 4 Relief Request Withdrawn
S2-005b-3 5-19 Rev. 1 April 1, 1987
Component(s):
11548-FM-SSC:
RELIEF REQUEST 5 Piping an4 valves as listed located on station print HCV-2311 and 2-CH-313 2-CH-312 and HCV-2310A, 2-CH-310 Function Chemical and Volume Control System Class 1 Section XI Code Requirements For Which Relief IS Requested:
Class 1 System Hydrostati~ Test, IWB-5222.
Basis For Request The one-way check valve placement prevents pressurization of the area in between the valves when conducting IWB-5222 on the primary system.
Alternate Testing Method
The alternate test proposed is to pressurize the primary system to 2335 psig while the reactor is in a shutdown condition.
borated The reactor will be to equal to or greater than cold shutdown boration. The pressurized primary will act as a boundary for the test forcing closed the first check valve in the pressure boundary.*
A hydrostatic test pump will provide pressure up to 2235 psig creating a differential pressure of 100 psid, thus keeping the first check valve closed and providing a pressure boundary for the test. A normal VT-2 examination will then be conducted. Chemistry samples will be taken every
30 minutes to prevent accidental dilution of the primary.
Schedule *For Implementation End of interval, within last period .
S2-005b-3 5-20 Rev. 1 April 1, 1987
RELIEF REQUEST 6
Component(s): Piping and Valves located on station print 11548-FM-87A:
Component HOV-2701 Connected Piping 14"-RH-101-1502 Component MOV-2700 Function Residual Heat Removal Class 1 Section XI Code Requirements.
For Which Relief Is Requested Class 1 System Hydrostatic Test, IWB-5222 Basis For Relief During a normal hydrostatic test of the primary, MOV-2700 is closed in addition to MOV-2701. This prevents pressurization of MOV-2701 and the piping between the two MOVS. Both valves are closed to prevent possible overpressurization of the Residual Heat Removal System.
Alternate Testing Method As an alternative, MOV-2701 and the piping between MOV-2701 and MOV-2700 will be tested in accordance with the Class-2 hydrostatic test to be administered to 14"-RH-118-602 on the suction side of the Residual Heat Removal pumps.
This piping is protected from overpressure by RV-2721 which is set at 600 psig. Class 2
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 1 hydrostatic tesc presented.
Schedule For Implementation End of interval, within the last period *
S2-005c-3 5-21 Rev. 1 April 1, 1987
RELIEF REQUEST 7
Cornponent(s): Piping and Valves located on station print 11548-FM-87A:
Component Connected Piping Component MOV-2701 14"-RH-101-1502 MOV-2700 Function Residual Heat Removal Class 1 Section XI Code Requirements For Which.Relief Is Rquested Class 1 System Leakage Test, IWB-5221 Basis For Request The system leakage test conducted on the primary system is done with both MOV-2700 and MOV-2701 closed for reasons expounded upon in Relief Request
6. This prevents pressurization of MOV-2701 and piping between the two MOVs.
Alternate Testing Method As an alternative, during the conduct of the Class 2 functional test on 14"-RH-118-602, MOV-2701 will be open as well as MOV-2700. This piping will be examined to the normal VT-2 requirements at the functional test conditions.
Schedule For Implementation Once per inspection period .
S2-005c-3 5-22 Rev. 1 April 1, 1987
Component(s):
RELIEF REQUEST 8 Steam generators and piping located on station prints:
11548-FM-64A 11548-FM-64B 11548-FM-68A 11548-FM-124A 11548-FM-138A 11548-FM-123A Component Connected Piping Component 2-RC-E-lA 30"-SHP-101-601 SV-MS-201A to 30"-SHP-122-601 SV-MS-202A to 4"-SHP-137-601 SV-MS-203A SV-MS-204A SV-MS-205A RV-MS-201A 2-RC-E-lA 30"-SHP-101-601 2-GN-l to 6"-SHP-145-601 to 2"-GN-33-601 2-RC-E-lA 30"-SHP-101-601 NRV-MS-201A
2-RC-E-lA to 6"-SHP-145-601 30"-SHP-101-601 to 30"-SHP-122-601 to 3"-SDHV-101-601 to 4"-SDHV-104-601 2-MS-83,81,266 HCV-MS-204 2-RC-E"'."lA 30"-SHP-101-601 2-MS-379 to 4"-SHP-125-601 2-MS-87 2-RC-E-lA 14"-WFPD-117-601 2-FW-27 to 3/ 4"-CFPD-103-601 2-FW-10 2-WT-176 2-RC-E-lA 2 l/2"-WGCB-601 2-BD-l l"-WGCB-601 2-BD-2 3"-RT-200-601 2-BD-4 2-RT-l 1-RC-E-lA 30"-SHP-1-601 2-MS-74 to 1 l/2"-SHPD-106-601 S2-005c-3 S:-23 Rev. 1 April 1, 1987
RELIEF REQUEST 8 (CONT'D)
Component 2-RC-,E-lB Connected Piping 30"-SHP-102-601 to 30"-SHP-123-601 to 4"-SHP-138-601 Component SV-MS-201B SV-MS-202B SV-MS-203B SV-MS-204B SV-MS-205B RV-MS-201B 2-RC-E-lB 30"-SHP-102-601 2-GN-2 to 6"-SHP-146-601 to 2"-GN-34-601 2-RC-E-lB 30"-SHP-102-601 NRV-MS-201B to 6"-SHP-146-601 2-MS-115, 268,113 2-RC-E-lB 30"-SHP-102-601 HCV-MS-204 to 30"-SHP-123-601 to 3,"-SDHV-102-601 to 4"-SDHV-104-601 2-RC-E-lB 30"-SHP-102-601 2-MS-120,2-MS-378 to 4"-SHP-126-601 2-RC-E-lB 14"-WFPD-113-601 2-FW-41,58 to 3/4"-CFPD-102-601 2-WT-179 2-RC-E-lB 2 l/2"-WGCB-601 2-BD-11 1"-WGCB-601 2-BD-12 3"-RT-210-601 2-BD-14 2-RT-20 2-RC-E-lB 30"-SHP-102-601 2-MS-106 to 1 l/2"-SHPD-108-601 S2-005c-3 5-24 Rev. 1 April 1, 1987
RELIEF REQUEST 8 (CONT'D)
Component 2-RC-E-lC Connected Piping 30"-SHP-103-601 to 30"-SHP-124-601 to 4"-SHP-139-601 Component SV-MS-201C sv-Ms:...202c SV-MS-203C SV-MS-204C SV-MS-205C RV-MS-201C 2-RC-E-lC 30"-SHP-103-601 2-GN-3 to 6"-SHP-147-601 to 2"-GN-35-601 2-RC-E-lC 30"-SHP-103-601 NRV-MS-201C to 6"-SHP-147-601 2-MS-152,151,208 2-RC-E-lC 30"-SHP-103-601 HCV-MS-204 to 30"-SHP-124-601 to 3"-SDHV-103-601 to 4"-SDHV-104-601 2-RC-E-lC 30"-SHP-103-601 *2-MS-158
to 4"-SHP-127-601 2-MS-377 2-RC-E-lC 14"-WFPD-109-601 2-FW-72 to 3/ 4"-CFPD-101-601 2-FW-89 2-WT-180 2-RC-E-lC 2 l/2"-WGCB-601 2-BD-21 l"-WGCB-601 2-BD-22 3"-RT-220-601 2-BD-24 2-RT-39 2-RC-E-lC 30"-SHP-103-601 2-MS-143 to 1 l/2"-SHPD-107-601 S2-005c-3 5-25 Rev. 1 April 1, 1987
RELIEF REQUEST 8 (CONT'D)
Function Main Steam Feedwater Steam Generator Nitrogen Connection Chemical Feed Steam Generator Blowdown Steam Generator Recirculation and Transfer Class 2 Section XI Code Requirements For Which Relief Is Requested IWA 5213(d) System Hydrostatic Tests - 4 hr. holding time required after attaining test pressure and temperature conditions for insulated systems.
Basis For Relief 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."
Alternate Testing Method 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.
Schedule For Implementation End of interval, within last period
S2-005c-3 5-26 Rev. 1 April 1, 1987
Component(s): Valves and 11548-FM-68.A:
Component RELIEF REQUEST 9 piping on the following Connected Piping station drawings Component 2-FW-12 14"-WFPD-117-601 2-FW-10 2-FW-43 14"-WFPD'.""113-601 FW-41 2-FW-74 14"-WFPD-109-601 . 2-FW-72 2-FW-31 3"-WAPD-110-601 2-FW-27 to 3"-WAPD-109-601 2-FW-30 3"-WAPD-109-601 2-FW-27 2-FW-62 3"-WAPD-112-601 2-FW-58 to 3"-WAPD-111-601 2-FW-61 3"-WAPD-111-601 2-FW-58 2-FW-93 3"-WAPD-114-601 2-FW-89 to 3"-WAPD-113-601
Function Class 2-FW-92 3"-WAPD-113-601 Feedwater and Auxilliary Feedwater Connections.
2 2-FW-89 Section XI Code Requirements For Which Relief Is Requested IWA-5213(d) System Hydrostatic Tests - 4 hr. holding time required after attaining test pressure and temperature conditions for insulated systems.
Basis For Request The check valves associated with the p1p1ng 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.
Alternate Testing Method As an alternative, these areas will be tested to the pressure and conditions discussed in Relief Requ.est 8. As the individual steam generators are tested the piping and valves attached in this request will
be tested .
S2-005c-3 5-27 Rev. 1 April 1, 1987
RELIEF REQUEST 9 (CONT'D)
Schedule For Implementation End of inspection interval, within last period *
Rev. 1 S2-005c-3 5-28 April 1, 1987
RELIEF REQUEST 10
Component(s): Piping and valves 11548-FM-88C:
Component as listed located Piping Connected on station print Component 2-CH-310 3/4"-CH-540-1502 2-CH-311 Function Chemical and Volume Control System Class 2 Section XI Code Requirements For Which Relief Is Requested Class 2 System Hydrostatic Test, IWC-5222 Basis For Request The one-way check,valve placement of 2-CH-310 makes it impossible to isolate the primary Class 1 system from the Class 2 pressure test required.
Since no safety or relief valve exists for this hydrostatic test boundary, design pressure of the pipe (PD) must be used as a substitu'te for PSV (IWC-5222a). The PD for this pipe is 2735 psig, therefore the required test pressure would be 1.25 times PD or 3419 psig. Since the primary cannot be isolated this test pressure would overpressurize the primary system which is limited to the Class 1 hydrostatic test condition described in IWB-5222.
Alternate Testing Method As an alternative, the piping and components covered by this request will receive a VT-2 examination during the test described in Relief Request 5.
Schedule For Implementation End of interval, within the last period
S2-005c-3 5-29 Rev. 1 April 1, 1987
RELIEF REQUEST 11
Component(s): Piping and valves located on station prints 11548-FM-89A and 11548-FM-89B:
Component MOV-2890C Connected Piping 10"-SI-352-1502 Component
.2-SI-243 to 6"-SI-353-1502 2-SI-241 to 6"-SI-345-1502 2-SI-242 to 6"-SI-344~1502 MOV-2890A 6"-SI-249-1502/ 2-SI-238 MOV-2890B 6"-SI-248-1502 2-SI-239
. to 6"-SI-343-1502 to 611 -SI-249-1502 2-SI-240 to 6"-SI-250-1502 2-SI-174 and 3"-SI-272-1503 2-SI-227 MOV-2869A MOV-2869B 3"-SI-347-1503 2-SI-226 2-SI-150 3"-SI-270-1503 2-SI-237 MOV-2867C to 2"-SI-270-1503/ 2-SI-250 MOV-2867D 2"-SI-275-1502 2-SI-236 3"-SI-290-1503/ 2-SI-248 3"-SI-270-1503 2"-SI-276-1503/
2"-SI-285-1502 3/4"-SI-222-152 MOV-2842 3"-SI-346-1503 2-SI-235 to 2"-SI-271-1503/ 2-SI-245 2"-SI-274-1502 Function Safety Injection System Class 2 Section XI Code Requirements For Which Relief Is Requested Class 2 System Hydrostatic Test, IWC-5222 Basis For Relief Gheck valve boundaries between Class 2 and Class 1 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 system since it cannot be
isolated
S2-005c-3 5-30 Rev. 1 April 1, 1987
RELIEF REQUEST 11 (CONT'D)
Alternate Testing Method As an alternative, these systems will be tested in conjunction with the Class 1 hydrostatic test at a pressure of 2335 psig. A VT-2 examination will be performed on the componenets and piping listed above.
Schedule For Implementation End of interval, within the last period
s2~005c-3 5-31 Rev. 1 April 1, 1987
RELIEF REQUEST 12 Component(s): Piping and valves locat*ed on station print 11548-FM-89B:
Component Connected Piping Component MOV-2865A 12"-SI-245-1502 2-SI"""'.107 2-SI-105 3/4"-SI-233-1502 MOV-2865B 12"-SI-246-1502 2-SI-128 2-SI-126 3/4"-SI-234-1502 MOV-2865C 12"-SI-247-1502 2-SI-145 2-SI-143 3/4"-SI-235-1502 Function Safety Injection System Class 2 Section XI Code Requirements For Which Relief Is Requested Class 2 System Hydrostatic Test, IWC-5222 Basis For Request
The check valve boundary prevents isolation of the adjoining Class 1 system from the Class 2 system mentioned. The lack of overpressure protection within the boundary requires a test pressure equal to 1.1 (multiplier for T~200°F) times the design pressure (PD) of 2485 psig. This test pressure is 2733.5 psig for the Class 2 system. The nominal operating pressure (PO) for the adjoining Class 1 system is 660 psig which at 100°F requires a test pressure of 726 psig. As is evident, since isolation is not practical, the Class 2 test pressure will be far in excess of the test pressure for the Class 1 system.
Alternate Testing Method As an alternative, it is requested that the Class 2 components and piping mentioned above be examined (VT-2) to the conditions required for the adjacent Class 1 piping (PO= 660 psig).
Schedule For Implementation End of interval, within the last period .
S2-005c-3 5-32 Rev. 1 April 1, 1987
RELIEF REQUEST 13
Compcnent(s): Piping and valves located on station print 11548-FM::-84A.
Component Connected Piping Component 2-CS-48 6"-CS-115-152 2-CS-47 6"-CS-114-152 2-:-CS-46 2"-CS-119-152 2-CS-45 Function Containment and Recirculation Spray System Class 2 Section XI Code Requirements For Which Relief Is Requested Class 2 System Hydrostatic Test, IWC-5222(a)
Basis For Request:
Tank 2-CS-TK-l (RWST) and piping up to 2-CS-48 will be tested to system hydrostatic test criteria of IWC-5222(b,c). The piping and components above attach to the system and are included only due to the requirements of Reg. Guide 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 2-CS-48, the piping mentioned above must be tested in ac~ordance with IWC-5222(a). -
Boundary valves necessary to isolate IWC-5222(a) include piping (3"-FP-38-152 w/design pressure=lOO psig) which cannot be isolated frotn the test zone. Design pressure for the piping described above is 150 psig.
The low~r design pressure would limit the pressure test required by IWC-5222(a). This test would be excessive since the piping would only see pressure associated with the RWST when performing its safety function.
Alternate Testing Method As an alternative, it is requested that the piping and components mentioned above be tested to the requirements of IWC-5222(b,c) associated with 2-CS-TK-l (RWST).
Schedule For Implementation End of interval, within the last period .
S2-005c-3 5-33 Rev. 1 April 1, 1987
RELIEF REQUEST 14 Relief Request Withdrawn S2-005c-3 5-34 Rev. 1 April 1, 1987 j
Component(s):
Function RELIEF REQUEST 15 Open ended intake piping before the first shut-off valve in non-closed systems located on 11548-FM-71A.
Circulating and Service Water _System Class 3 Section XI Code Requirements For Which Relief Is Requested System Hydrostatic Test, IWD-5223 Basis For Relief The Code addresses the problem of performing hydrostatic tests on .open ended portions of discharge lines beyond the last shut-off valve in non-closed systems in IWD-5223(d). A similar problem exists for the intake p1p1ng at* Surry Unit 2 as it is non-i'solatable for the increased pressure requirements of a hydrostatic test.
Alternate Testing Method 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.
Schedule For Implementation End of interval, within the last period .
S2-005c-3 5-35 Rev. 1 April 1, 1987
i RELIEF REQUEST 16 Relief Request Withdrawn S2-005c-3 5-36 Rev. 1 April 1, 1987
RELIEF REQUEST 17 Component(s): Steam Generators located on station print 11548-FM-86A.
2-RC-E:..lA 2-RC-E-lB 2-RC-E-lC Function Reactor Coolant System Class 1 Section XI Code Requirements For Which Relief Is Requ~sted System Leakage Test, IWB-5221; System Hydrostatic Test, IWB-5222; Visual Examination, IWA-5240 Basis For Request Prim~ry to secondary leakage detection using Code described visual detection techniques would be limited in usefulness and hazardous to conduct.
Alternate Testing Method
The normal primary to secondary leakage surveillance requirements of Surry's Technical Specifications provide the necessary intended Code examination requirements for leakage identification.
Schedule For Implementation In accordance with Technical Specifications at Surry
S2-005c-3 5-37 Rev. 1 April 1, 1987
Component(s):
RELIEF REQUEST 18 Piping and components located on the following prints:
l 1548-FM-72A 11548-FM-72B 11548-FM-72C Function Component Cooling Class 3 Section XI Code Requirements For Which Relief Is Requested System Hydrostatic Test, IWD-5223 Basis For Request 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.
Alternate Testing Method 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 IWD-5221, which will be normally conducted, and will be more than sufficient. Determination of testing will be done with emphasis on practicality, and in conducting IWD-5223 System Hydrostatic. Test whenever possible. It should be noted that this is an upgrade of testing, requirements over the first 10 year interval.
Schedule For Implementation End of the interval within the last period .
S2-005c-3 5-38 Rev. 1 April 1, 1987
Component(s):
RELIEF REQUEST 19 Piping and components located on the following print:
11548-FM-7 lB l 1448-FM-71D Function Service Water System Class 3 Section XI Code Requirements For Which Relief'Is Requested System Hydrostatic Test - IiID-5223 Basis For Request The service water system as seen on the above mentioned drawing is used for cooling component cooling water 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 2-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 2-CC-P-2A or 2B. It is felt that having to use a design pressure (PD) of 100 psig would be excessive for this system as the maximum pressure potential is 50 psig.
Alternate Testing Method As an alternative, it is requested that 50 psig be used as this systems PD until a safety or relief valve is placed within the system to make use of PSV.
Schedule For Implementation End of interval, within the last period .
S2-005c-3 5-39 Rev. 1 April 1, 1987
Component(s): Piping and l 1548-FM-89A:
Component RELIEF REQUEST 20 valves located Connected Piping on the following Component prints:
2-SI-195 3/4"-SI-360-153 2-SI-196 Function Safety Injection Class 2 Section XI Code Requirements For Which Relief Is Requested System Hydrostatic Test, IWC-5222 Basis For Request The one way check valve, 2-SI-196, provides a pressure retaining boundary for two system hydrostatic tests (IWC-5222(a) and IWC-5222(Q,c)). The Class 2 component is adequate as a pressure boundary when performing IWC-5222 (b,c) on the adjacent Class 2 system. However when performing system hydrostatic test, Iwc.:.s222(a), on 2-SI-P-lA, the one way check valve does not retain pressure for that flow direction
Alternate Testing Method As an alternative, the upstream isolation valve 2-SI-195 will be closed in order to provide a pressure boundary to perform the system hydrostatic test, IWC-5222(a), on 2-SI-P-lA. This enables the above mentioned piping to be hydrostatic tested up to the isolation valve, 2-SI-195. The remaining piping.
and components mentioned above will be tested to the requirements of IWC-5221(a,b), functional test.
Schedule For Implementation End of interval, within the last period
S2-005c-3 5-40 Rev. 1 Apr.il 1, 1987
RELIEF REQUEST 21 Component(s): Penetrations located in the lower head of the Reactor Vessel.
Funct.ion Reactor Coolant System Class 1 Section XI -Code Requirements For Which Relief Is Requested Class 1 System Hydrostatic Test, IWB-5222 Class 1 System Leakage Test, IWB-5221 Visual Examination, IWA-5240 Basis For. Request Primary leakage detection using Code described visual detection techniques would be limited in usefulness and hazardous to conduct. During the time the primary system is at test pressure, environmental and subatmospheric conditions restrict the area required to be accessed for visual inspection.
Alternate Testing Method The normal primary leakage surveillance requirements of the plant's Technical Specifications provide the necessary intended Code examination requirements for leakage identification.
Schedule For Implementation In accordance with Technical Specifications at Surry S2-005c-3 5-41 Rev. 1 April 1, 1987
RELIEF REQUEST 22 Component(s): Piping and valves, as li~ted, located on station prints:
11548-FM-88B,C:
Component Piping Connected Component HCV-231 OA, HC.V-2311 3"..:.CH-301-1502 2-CH-304, 2-CH-305 2-CH-311 2"-CH-368-1502 3/4"-CH-540-1502 3"-CH-379-1503 Function Chemical and Volume Control System Class 2 Section XI Code Requirements For Which Relief Is Requested Class 2 System Hydrostatic Test, IWC-5222 Basis For Relief The valve design of HCV-2310A prevents pressurization of the area listed above when conducting IWC-5222. The valve is required to be closed for IWC-5222 but when the required test pressure (3419 psig) is applied, the valve lifts off its seat. In previous tests, a mechanical jack has been installed to prevent the valve seat f£om *fifting. The hydrostatic test would be completed but valve damage was incurred. (bending stem, disc, seat, etc.)
Alternate Testing Method As an alternative, the piping. and components covered by this request will receive a VT-2 examination during the test described in Relief Request 5.
Schedule For Implementation End of interval, within the'last period
S2-005c-*3 5-42 Rev. 1 April 1, 1987

ML18130A444

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