ML18130A440

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Rev 3 to Surry Power Station Unit 1 Inservice Insp Program, Interval 2,821222-921222.
ML18130A440
Person / Time
Site: Surry Dominion icon.png
Issue date: 03/27/1987
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18130A441 List:
References
NUDOCS 8704220232
Download: ML18130A440 (591)
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Text

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM INTERVAL 2 DECEMBER 22, 1982 - DECEMBER 22, 1992 REVISION 3

------~~

8704220232 870416 PDR ADOCK 05000280 Q . PDR i

Re\'. '.:

March ~ ~ ,* 1%-7

VIRGINIA ELECTRIC AND POWER COMPANY

    • SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM INTERVAL 2 DECEMBER 22, 1982 - DECEMBER 22, 1992 REVISION 3 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 will be accompanied by two copies of the
  • distribution memo, one of which is to be returned per instru~tions thereon, and the other one is to be filed sequentially behind this page giving you a record of the contents of each distribution.

ii Sl-000 Rev. 3 March 27, 1987

ABSTRACT VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INTERVAL 2 DECEMBER 22, 1982 TO DECEMBER 22, 1992 In accordance with 10CFRS0.55a, the Surry Unit 1 Inservice Inspection and Testing Program was updated to meet the requirements of 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 December 22, 1982, and will end on December 22, 1992.

The Inservice Inspection Program was developed employing 10CFRSO and Reg.

Guide 1.26. Quality Groups A, B, and Care the same as ASME Classes 1, 2, and 3 respectively.

The List of Drawings 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 Inservice 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 Subsections IWP and IWV of ASME Section XI.

Section 5 describes the Inservice System Pressure Test Program .

  • iii Sl-000 Rev. 3 March 27, 1987
  • TABLE OF CONTENTS SECTION TITLE PAGE i Assignment ii Distribution Record iii Abstract iv Table of Contents V List of Drawings 1 Introduction 2 Inservice Inspection Program for Components 3 Inservice Inspection Program for Component Supports 4 Inservice Testing Program Plan for Pumps and Valves 5 System Pressure Tests Program Plan
  • iv Sl-000 Rev. 3 March 27, 1987

LIST OF DRAWINGS

  • UNIT 1 11448-FB-4B FB DRAWINGS Fuel Oil Lines 11448-FB-6A Air Cooling and Purging 11448-FB-46A 'A' Diesel Generator Air Starting System 11448-FB-46B 'B' Diesel Generator Air Starting System 11448-FB-46C 'C' Diesel Generator Air Starting System 11448-FB-47B Fire Protection UNIT 1 FM DRAWINGS 11448-FM-64A Main Steam 11448-FM-64B Steam.Generator Nitrogen Connection 11448-FM-'-66A Auxiliary Steam and Air Removal 11448-FM-68A Feedwater 11448-FM-68B Cross-connect Auxiliary Feedwater 11448-FM-71A Circulating and Service Water 11448-FM-71B Circulating and Service Water 11448-FM-7 lD Circulating and Service Water 11448-FM-72A Component Cooling l 1448-FM-72B Component Cooling 11448-FM- 72C Component Cooling 11448-FM-72D Component Cooling 11448-FM-72E Component Cooling 11448-FM- 72F Component Cooling 11448-FM- 72G Component Cooling 11448-FM-?SE Component Cooling
  • V Sl-000 Rev. 3 March 27, 1987

LIST OF DRAWINGS CONT .

  • UNIT 1 11448-FM-75G FM DRAWINGS Compressed Air System 11448-FM-75J Compressed Air System 11448-FM-82B Sampling System 11448-FM-83A Vent and Drains 11448-FM-83B Vent and Drains 11448-FM-84A,B Containment and Recirculation Spray 11448-FM-85A Containment Vacuum and Leakage Monitoring ll 448-FM-86A Reactor toolant 11448-FM-86B Reactor Coolant 11448-FM-87A Residual Heat Removal 11448-FM-88A Chemical and Volume Control ll 448-FM-88B Chemical and Volume Control 11448-FM-88C Chemical and Volume Control 11448-FM-89A Safety Injection 11448-FM-89B Safety Injection ll448-FM-90A Gaseous Waste System 11448-FM-90B Gaseous Waste System 11448-FM-90C Gaseous Waste System 11448-FM-118A Reactor Cavity Purification 11448-FM-123A Chemical Feed 11448-FM-124A Steam Generator Blowdown 11448-FM-130A Radiation Monitor Circ. and Service Water 11448-FM-138A Steam Generator Recirculation and Transfer
  • vi Sl-000 Rev. 3 March 27, 1987
  • UNIT 1 11448-SPS-14A LIST OF DRAWINGS (CONT.)

SPS DRAWINGS.

Containment Particulate

  • vii Sl-000 Rev. 3 March 27, 1987

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1

  • INSERVICE INSPECTION AND INSERVICE TESTING PROGRAM Sl-001 Rev. 3 1-1 March 27, 1987

1.0 INTRODUCTION

1.1 GENERAL INFORMATION Surry Power Station Unit 1 is a Pressurized Water Reactor located on Gravel Neck and adjacent to the James River in Surry County, Virginia. The plant employs a Westinghouse Electric Corp. Nuclear Steam System.

The Inservice Inspection (ISI) and Inservice Testing (IST) Programs for Surry Station Unit 1 are developed in compliance with the rules and regulations of 10CFRS0.55a and Section XI of the ASME.Boiler and Pressure Vessel Code, 1980 Edition including the Addenda through Winter 1980. Where these rules are determined to be impractical, specific relief is requested in writing.

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

  • 1.2 SYSTEM CLASSIFICATION The construction permits for Surry Units 1 and 2 were issued on June 25, 1968. At that time, the ASME Boiler and Pressure Vessel Code covered only pressure vessels. Piping, pumps, and valves were built primarily to the rules of USAS B31.l. Essentially, Surry Power Station was designed and constructed prior to the origination of the ASME Code classifications named Class 1, 2, and 3. Therefore 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 10CFRSO.SSa 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 .

Sl-001 Rev. 3 1-2 March 27, 1987

Descriptions of changes between Revision 1 and Revision 3 for the Surry Unit 1 Inservice Inspection Program for Components are provided below. The page numbers refer to the Revision 3.

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

1 The flow diagram reference number (11715) was changed to read (11448). This change occurs throughout the document~

1 The vessel number in the column entitled "LINE NUMBER" was changed from RPRV to lR{:Rl. This change was applied to all occurrences of RPRV.

1 Also note that the unit designator "l" was added.

to the vessel number. The unit designator "l" was added to every vessel and pump number which did not have a unit designator in Revision 1.

3 Item Number Bl.21 was changed to Bl.21T for "Top Head" weld .

  • 6 6

The vessel number in the column entitled "LINE NUMBER" was changed from PRZR to 1RCE2.

change occurs throughout the document.

Relief Request SR-005 was added.

This 6 Also note that the relief request number was changed to a 3 digit number (i.e. 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-008 was added.

18 Relief Request SR-008 was added.

27 Relief Request SR-011 was added.

36 Line Number CH8-1502 was deleted from the program.

36 System/Component was corrected. This change occurs throughout this document.

Sl-002 March 27,1987

Page Description of Change

  • 40 Flow Diagrams and Coordinates were changed to reflect the proper FM. This change has occurred throughout the document.

41 Line Number RHlB-1502 was changed to RHlB-602.

41 Line Number RH23-1502 was changed to RH23-602.

43 Item Number BS.IO "Reactor Vessel Integrally Welded Attachments" was moved from Item Number BS.20.

45 & 46 The following Line Numbers were added to Item Number B9.ll.

CH122-152 CH14-1502 CH15-1502 CH16-1502 CH214-152 CH215-152 CH216-152 CH99-152

  • 53 55 Relief Request SR-009 was added.

Line Number SI85-1502 was changed from Item Number B9.ll to B9.21.

Line Number RC15-1502 was deleted from Item Number 9.21.-

66 Lipe Number SI75-1502 was added to Item Number B9.40.

67 , 68 , 6 9 & 70 The following Line Numbers were added to Item Number BIO.IO.

CHl-1502 CH216-152 RC146-1502 RC20-1502 RC22-1502 RC36-602 RC62-602 RH17-1502 RHlS-602 SI145-1502

  • 87 87 106 106 Line Number CH93-1503 was changed to CH93-1502.

Line Number CH95-1503 was changed to CH95-1502 Sl-002 March 27,1987

Description of Change

  • 87 & 106 102 & 121 Line Number CH97-1503 was changed to CH97-1502 Line Number SI4-1502 was changed to SI41-1502.

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

125 & 127 Relief Request SR-012 was added to Line Number lCHFL3.

127 & 128 The following Line Numbers were added to Item Number Cl. 20.

1CHTK2 1CHE3 lRCElA lRCElB Item Numbers C2.10 and C2.20 have been deleted from the program.

130 Relief Request SR-007 was added.

130, 131 & 132 Item Numbers ,c2.21 and C2.22 have been added to the program.

134 thru 146 The following Line Numbers were added to Item Number C3.40.

WAPDl-601 CHSl-1503 SDHV4-121 WAPDl0-601 CH89-1503 SHPD16-601 WAPDll-601 CH90-1503 SHPDS-601 WAPD12-601 CH91-1503 SHPD6-601 WAPD13-601 CH99-152 SHPD7-601 WAPD14-601 DG26-152 SHPD8-601 WAPD2-601 CH68-1502 SHP29-601 WAPD9-601 CHl-1502 SHP30-601 WAPDS0-601 CH79-1503 SHP31-601 WAPDSl-601 CSl-153 SHP57-601 WGCBl-601 CS14-152 RHl0-602 WGCBlOS-601 CS2-153 RH12-602 WGCB2-601 CS22-153 RHlS-152 WGCB3-601 CS27-153 RH18-602 WGCB6-601 CS3-153 RH2-602 CClOl-151 CS33-153 RH20-152 CC16-121 CS34-153 RH4-602 CC262-151 CS36-153 RHS-602 CC93-151 CS4-153 RH7-602 CC78-151 RHS-602 CS8-153 CC80-151 CS80-153 RH9-602 CH25-152 CS85-153 RL6-152 CHll-1503 CS88-153 RSl-153 CH113-1503 CS91-153 RSl0-153 Sl-002 March 27,1987

Page Description of Change

  • 134 thru 146 CH12-150,3 CH120-152 CH13-1503 CH17-152 CH2-1503 CH23-152 CS94-153 CS95-153 CS98-153 CVB-151 WFPD9-601 RSll-153 RS12-153 RS13-153 RS14-153 RS2-153 SAEl-121 RS20-153 CH3-1503 SAE2-121 RS21-153 CH7-602 SAE3-121 RS22-153 CH79-1503 SAE37"'."121 RS23-153 CHB-1503 SAE38-121 RS3-153 CHB0-1503 SAE39,-l21 RS4-153 147 thru 152 The following Line Numbers were added "to Item Number C3.40.

RS9-153 SI17-152 SI146-1503 RTl00-601 SI170-152 SI147-1503 RTlOl-153 SI48-1502 SI45-1502 RTll0-601 SI5-153 SI46-1502 RTlll-153 SI57-1503 SI47-1502 RT120-601 SI58-1503 SI70-1503 RT121-153 S16-153 S172-1503 SI102-152 SI70-1503 SI74-1502 SI106-153 S172-1503 SI75-1502 SI130-152 SI83-152 SI76-1503 SI14-153 SI84-152 SI79-1502 SI147-1503 SI92-153 SIB0-1502 SI150-153 SI105-152 SI81-1502 SI85-1502 154 thru 162 The following Line Numbers were added to Item Number C5.ll. These changes occur throughout this document.

CH17-152 RC20-602 SI149-153 CHlS-152 RC40-602 SI150-153 CH19-152 RC41-602 SI151-153 CH201-152 RC42-602 SI17-152 CH202-152 RC62-602 SI170-152 CH203-152 SI46-1502 SI18-152 CH204-152 RH20-152 SI19-152 CH205-152 RS24-153 S12-153

  • CH206-152 RS7-153 S15-152 CH72-152 RSS-153 S15-153 CSl-153 Sil-153 S16-153 CS14-152 SI102-152 SI7-152 CS15-152 SI106-153 SI78-152 CS2-152 SI107-153 SI83-152 CSS-152 SI108-153 SI84-152 CS87-153 SI13-153 SI3-153 CS88-153 SI14-153 SI45-1502 CS89-153 SI148-153 S147-1502 Sl-002 . March 27, 198_7

_Page Description of Change

  • 154 thru 162 174 & 210 Line Number RH12-604 was deleted .from Item cs .11.

Line Number CH-125 was changed to CH125-602.

Number 187 & 188 The following Line Numbers 'had the piping specifications changed from 152 to 153. These changes occur throughout this document.

CS74-153 CS75-153 CS8-153 190 thru 192 The following Line Numbers had the piping specifications changed from 601 to 121. These changes occur throughout this document.

SSVl-121 SSVl0-121 SSVll-121 SSV12-121 SSV13-121 SSV14-121 SSV15-121 SSV2-121 SSV3-121 SSV4-121 SSV5-121 SSV6-121 SSV7-121 SSV8-121 SSV9-121 245 Line Numbers lRHPlA and lRHPlB have been changed from Item Number C7.20 to C7.30.

246 Line Numbers lRHPlA and lRHPlB have been changed from Item Number C7.21 to C7.31.

253 thru 306 Item Number Dl.10 was replaced by Item Numbers Dl.lOH and Dl.10S.

256 & 283 Line Number CC16-181 was changed to CC16-121.

266 & 293 Line Number CC234-121 was changed to CC234-151.

270 & 297 Line Number CH160-152 was-changed to CH180-152.

  • 307 thru 320 Item Number D2.10 was D2.10H and D2.10S.

replaced by Item Numbers Sl-002 March '27,1987

Description of Change

  • 312 & 319 The following Line Numbers had the specifications changed from 21B to 21X.

WS74-21X WS75-21X piping WS81-21X WS82-21X 321 thru 335 The following Item Numbers have been added to the program.

D2.20 D2.30

  • n2.4o 312 &*319 The following Line Numbers had the piping specifications changed from 21B to 21X.

WS74-21X WS75-21X WS81-21X WS82-21X 321 thru 335 The following Item Numbers have been added to the program.

D2.20 D2.30 D2.40 2-11 Thru 2-14 Reference drawing were added to SR-005.

2-15 Relief Request SR-006 was added to the program submittal.

2-16 & 2-17 Relief Request SR-007 was added to the program submittal.

2-18 Relief Request SR-008 was added to the program submittal.

2-19 Relief Request SR-009 was added to the program submittal.

2-20 Relief Request SR-010 was added to the program submittal.

2-21 Relief Request SR-011 was added to the program submittal.

Sl-002 March 27,1987

  • 2-22 2-23 Description'of Change Relief Request submittal.

SR-012 Relief Request SR-013 was was added to the program added to the program submittal.

2-24 Relief Request SR-014 was added to the program submittal .

Sl-002 March 27,1987

VIRGINIA ELECTRIC AND POWER COMPANY

- SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM FOR COMPONENTS Sl-002 2-1 Rev. 3 March 27, 1987

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

SUMMARY

Sl-002 Rev. 3 March 27, 1987

  • 2.0 INSERVICE INSPECTION PROGRAM FOR COMPONENTS 2.1 PROGRAM DESCRIPTION 2.1.1 The Inservice Inspection Program 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 p1p1ng is in accordance with 10CFR50 utilizing the selection criteria of ASME Section XI; 1974 Edition through the Summer 1975 Addendum. The ASME Section XI *1980 Edition through the Winter 1980 Addendum selection criteria will be applicable when stress calculations to support that inspection program are available. Vessel weld selection and hanger and support selection is in accordance with 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 Addendum. Use of the blocks will supercede 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 Tables IWB-2500-1, IWC-2500-1 and IWD-2500-1 for Class 1, 2 and 3 components.

B. Item Number and Item Description - The Item Number and Item Description as listed in Tables* IWB-2500-1, IWC-2500-1 and IWD-2500-1. All 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. The abbreviations used are as follows:

Sl-002 2-3 Rev. 3 March 27, 1987 L__.

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 from volumetric and/or surface examination by the applicable code paragraph. Components exempted from examination by code allowed exemptions will not appear in the component table of this program in most cases. The following is a list of code allowed 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 inaccessible by Control Rod Drive 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, piping and associated valves, and vessels and their attachments that are 4-in. n.p.s and smaller.

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

EX IWC-1230, piping support 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.Z(a), integral attachments of supports and restraints in systems whose function is not required in support of reactor residual heat removal and emergency core cooling.

Sl-002 2-4 Rev. 3 March 27, 1987

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

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

2.2.2 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

  • Sl-002 2-5 Rev. 3 March 27, 1987

i VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT l INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE l *
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY S-A PRESSURE RETAINING WELDS IN REACTOR VESSEL ITEM NUMBER Bl.11 ITEM DESCRIPTION RV CIRCUl1FERENTIAL SHELL WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A F-5 lRCRl VOL
  • SURRY POWER STATION UNIT 1
  • INSERVICE INSPECTION PLAN SUMl1ARY INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 2 *
  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • DATE 86/10/20 *
  • CATEGORY B-A PRESSURE RETAINING WELDS IN REACTOR VESSEL ITEM NUMBER Bl.12 ITEM DESCRIPTION RV LONGITIA>INAL SHELL WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES RC FM-86A f-5 lRCRl VOL

\.

  • VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT l INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

'*

  • PAGE 3
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20
  • ITEM NUMBER B1.21T ITEM DESCRIPTION RV CIRCUHFERENTIAL TOP HEAD WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES
=== -------- ------- ------ ------- =

RC lRCRl

  • SURRY POWER STATION UNIT l INSERVICE INSPECTION PLAN

SUMMARY

                  • KKKK*******

INTERVAL 2, 12/22/82 TO 12/22/92 PAGE 4 ASNE SECTION XI EDITION 80W80 REVISION 0003

  • DATE 86/10/20
  • CATEGORY S-A PRESSURE RETAINING 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 (11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A F-S lRCRl VOL
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 5 *
  • ASME SECTION XI EDITIOH"80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-A PRESSURE RETAINING WELDS IN REACTOR VESSEL
                                                                                                                                                • lfif**************************

ITEM HUMBER  : Bl.40 ITEM DESCRIPTION: RV HEAO---TO---FLANGE WELD FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* -- LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD HUMBER METHOD RE~EST NOTES -

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

RC f-S lRCRl SUR VOL

  • SURRY POWER STATION UNIT 1 INSERV:CE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 6
  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • DATE 86/10/20 *
                          • MKMKKKMJf***lfMMKKKKMM*lflflflf****************lflflflflflflflflflf**illfKKKKlflflflfMMlfMKlflflflf***************
  • CATEGORY S-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 (11448) COORD NUHBER METHOD REQUEST NOTES RC Ftt-86B S-6 1RCE2 VOL SR-005

VIRGINIA ELECTRIC AND POWER COMPANY

  • SURRY POWER STATION UNIT l
  • INSERVICE INSPECTION PLAN

SUMMARY

          • MMMMMMM********

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 7
  • REVISION 0003
  • DATE 86/10/20 *
                                  • MMMMMMMMMMMMMMMM*il***********************************MM*MMMMMMMMlf******************
  • CATEGORY S-B PRESSURE RETAINING WELDS IN VESSELS OTHER THAN THE RV.
                        • MMMMMMMMMMMM*M*if***if*******************MMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMMif*******if*

ITEM NUMBER B2.12 ITEM DESCRIPTION PZR LONGITUDINAL SHELL-TO-HEAD WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHDO REQUEST NOTES

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

RC Ftt-86B G-6 1RCE2 VOL SR-005

VIRGINIA ELECTRIC AND POWER COMPANY

  • SURRY POWER STATION ~IT l INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12(22/92

  • PAGE 8
  • ASME SECTION XI EDITION 80W80 REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY S-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 (11448) COORD tM1BER METHOD REQUEST NOTES

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

RC Ftt-86A C-1 lRCElA VOL RC Ftt-86A C-6 1RCE1B VOL RC Ftt-86A J-1 lRCElC VOL

  • \.
  • ~RY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 9 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • *" DATE 86/10/20 *
                                                                • ~*******************************************************************
  • "CATEGORY B-D 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 RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

RC FM-86A F-5 lRCRl VOL

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 10
  • 0003
  • DATE 86/10/20 *
  • CATEGORY B-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 RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A F-5 lRCRl VOL

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 11 *
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                                                                                            • ~*************************************
  • CATEGORY a-D FULL PENETRATION WELDS OF NOZZLES IN VESSELS - PROGRAM B ITEM NUMBER 63.120 ITEM DESCRIPTION PZR NOZZLE INSIDE RADIUS SECTION FLOW. FLOW SYSTEM/ DIAGRAM DIAGRAl't LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86B G-6 1RCE2 VIS SR-007

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

SUMMARY

.INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 12
  • 0003
  • 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 (11448) COORD NUMBER METHOD REQUEST. NOTES RC Ftt-86A C-1 lRCElA VIS SR-007 RC Ftt-86A C-6 lRCElB VIS SR-007 RC Ftt-86A J-1 lRCElC VIS SR-007

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 13 *

,. ASME SECTION XI EDITION 80W80

  • REVISION 0003 *
  • 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 RELIEF PROGRAM COMPONENT !11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A F-s lRCRl VIS

VIRGINIA SURRY INTERVAL E.LECTRIC AND POWER COMPANY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION.80W80

  • ~*MMMMMMM*******
  • PAGE
  • REVISION 14
  • 0003 DATE 86/10/20
  • CATEGORY B-E PRESSURE RETAINING PARTIAL PENETRATION WELDS IN VESSELS
  • ITEM NUMBER 64.13 ITEM DESCRIPTION ALL VESSELS, INSTRUMENT NOZZLE PARTIAL PENETRATION FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES

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

RC FM-86A F-S lRCRl VIS.

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 15 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 Ll:NE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REEST NOTES

=======

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

RC Ftt-86B S-6

  • 1RCE2 VIS
  • SURRY POWER STATION UHIT l *
  • IHSERVICE IHSPECTIOH PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 16
  • ASME SECTION XI EDITION aowao
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                    • lfiif************************************************************************

ITEM NUMBER B5.10 ITEM DESCRIPTION  : RV NOMINAL PIPE SIZE >= 4T NOZZLE-TO-SAFE ENO BUTT WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM RELIEF PROGRAM COMPONENT C11448 I C~D NUMBER. METHOD REQUEST NOTES

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

RC Ftt-86A E-2 RC1-2501R VOL SR-006 RC Ftt-86A C-4 RC3-2501R VOL SR-006 RC Ftt-86A F-5 RC4-2501R VOL SR-006 RC Ftt-86A C-8 RC6-2501R VOL SR-006 RC Ftt-86A H-2 RC7-2501R VOL SR-006 RC Ftt-86A K-4 RC9-2501R VOL SR-006

  • SURRY POWER STATION UNIT 1 *
  • INSERV:T:CE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 17 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                  • lHHHHf**********************************************************************

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 (11448) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86B S-8 RC10-2501R SUR VOL RC Ftt-86B F-5 RClS-1502 SUR VOL RC Ftt-86B H-5 RC34-1502 SUR VOL RC Ftt-86B H-5 RC37-1502 SUR

. VOL RC Ftt-86B S-5 RC3S-1502 SUR VOL RC Ftt-86B G-5 RC39-1502 SUR VOL

VIRGINIA ELECTRIC ANO POWER COMPANY SURRY INSERVICE POWER STATION UNIT 1 INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME S.ECTION XI EDITION 80W80

  • PAGE
  • REVISION 18 0003
  • DATE 86/10/20 *
                                                                                                                                                                                                    • ~*

ITEM NUMBER  : BS.30 ITEM DESCRIPTION : SG NOHINAL PIPE SIZE >= 4T NOZZLE-TO-SAFE ENO BUTT WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11448) COORD NUMBER METiiOO RE~EST NOTES

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

RC FH-86A E-2 RC1-2501R SUR sR-ooa VOL RC FH-86A B-2 RCZ-2501R SUR SR-008 VOL RC FH-86A F~s RC4-2501R SUR SR-008 VOL RC FH-86A B-6 RCS-2501R SUR SR-008 VOL RC FH-86A H-2 RC7-2501R SUR SR-ooa VOL RC FH-86A K-2 RCS-2501R SUR SR-008 VOL

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT l INSERVICE INSPECTION PLAN SUNMARY INTERVAL 2, 12/22/82 TO 12/22/92 ASHE SECTION XI EDITION 80W80

                                  • If**
  • PAGE
  • REVISION 0003
  • 19 *
  • DATE 86/10/20 *
  • CATEGORY B-S-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER
  • ITEM NUMBER B6. 10 ITEM DESCRIPTION RV CLOSURE HEAD NlfTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM .. LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

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

RC Ftt-86A F-S lRCRl SUR

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN SUMJ1ARY ****************lfif**
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 20 *
  • ASME SECTION XI EDITION 80W~O
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-S--1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER ITEM NUMBER B6. 20 ITEM DESCRIPTION RV CLOSURE STUDS,IN PLACE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) cornm NUMBER METHOD REQUEST NOTES RC Ftt-86A F-s lRCRl VOL
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN SUNMARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 21 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-S-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER*

ITEM NUMBER B6. 30 ITEM DESCRIPTION RV CLOSURE STUDS,WHEN REMOVED FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A F-S lRCRl SUR VOL

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 22 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-S-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER ITEM NUHBER B6. 40 ITEM DESCRIPTION RV THREADS IN FLANGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A F-S lRCRl VOL
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 23 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY S-S-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER ITEM NUMBER B6. 50 ITEM DESCRIPTION RV CLOSURE WASHERS,BUSHINGS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

RC FM-86A f-5 lRCRl VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 24 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-S--1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER
  • ITEM NUMBER B6.180 ITEM DESCRIPTION PU1P BOLTS AND STUDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

RC FH-B6A A-1 lRCPlA VOL RC FH-B6A A-6 lRCPlB VOL RC FH-86A L-1* lRCPlC VOL

  • I *
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 25
  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • DATE 86/10/20 *
                            • MMNNNNNNNNNNNNNNNNMNN*****************************************************************
  • CATEGORY B-S---1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER *
                      • NNNNNNNNNNNNNNNNNNNNNN********************NNNNNNN****************************************

ITEM NUMBER B6.190 ITEM DESCRIPTION PUMP FLANGE SURFACE, WHEN CONNECTION DISASSEMBLED FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES RC Fl"t-86A A-1 lRCPlA VIS RC Fl"t-86A A-6 1RCP1B VIS RC Fl"t-86A L-1 lRCPlC VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

                                • lfif**
  • ' INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 26 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY S-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 Cll448) COORO HUMBER METHOD REQUEST NOTES RC Flt-86A A-1 lRCPlA VIS RC Flt-86A A-6 1RCP1B VIS RC Ftt-86A L-1 lRCPlC VIS
                                                  • ~*************************************************************************
  • SURRY POWER STATION ln'IIT 1 *
  • IHSERVICE INSPECTION PLAN SUHMARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 27 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                      • ~****************************************************************************************
  • CATEGORY B-S-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER
  • ITEM NUMBER 86.210 ITEM DESCRIPTION VALVE BOLTS ANO STUDS FLOW FLOW

'3YSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM

  • OMPONENT ( 11448) COORD NUMBER METHOO REQUEST NOTES

=======

RC Fl't-86A E-2 RC1-2501R VIS SR-011 RC Fl't-86A C-4 RC3-2501R VIS SR-011 RC Fl't-86A . F-5 RC4-2501R VIS SR-011 RC Fl't-86A C-8 RC6-2501R VIS SR-011 RC .Fl't-86A H-2 RC7-2501R VIS SR-011 RC Fl't-86A K-4 RC9-2501R VIS SR-011.

  • Su'RRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN SUt111ARY "********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 28 *
  • ASHE SECTION XI EDITION aowao
  • REVISI~ 0003 *
  • DATE 86/10/20 *
                                                                                                                                              • M****************************
  • CATEGORY S--G-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER
  • ITEM NUMBER  : B6.220 ITEM DESCRIPTION : VALVE FLANGE SURFACE, WHEN CONNECTION DISASSEMBLED

-FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-B6A E-2 RC1-2501R VIS RC Ftt-86A C-4 RC3-2501R VIS RC Ftt-86A F-s RC4-2501R VIS RC Ftt-86A C-8 RC6-2501R VIS RC Ftt-86A H-2 RC7-2501R VIS RC .Ftt-86A K-4 RC9-2501R VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

                    • ii*********
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 29 *
  • ASNE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY S-S-1 PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER
  • ITEM NUMBER  : B6.230 ITEM DESCRIPTION : VALVE NUTS,BUSHINGS, AND WASHERS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A E-2 RC1-2501R VIS RC Ftt-86A C-4 RCJ-2501R VIS RC Ftt-86A F-5 RC4-2501R VIS RC Ftt-86A C-8 RC6-2501R VIS RC Ftt-86A H-2 RC7-2501R VIS RC Ftt-86A K-4 RC9-2501R VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, l~/22/82 TO 12/22/92
  • PAGE 30 *
    • ASME SECTION XI EDITION 80W80 ** REVISION 0003 *
  • DATE 86/10/20 *
  • _CATEGORY B-G-2 PRESSURE RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER ITEM NUMBER  : B7.10 ITEM DESCRIPTION: REACTOR VESSEL BOLTS, STUDS, AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

RC Flr86A F-S lRCRl VIS

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASHE SECTION XI EDITION 80W80

  • PAGE 31 *
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY S-S--2 PRESSURE RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER
  • ITEM NUMBER  : B7.20 ITEM DESCRIPTION : PRESSURIZER BOLTS, STUOS, AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORO NUMBER METHOD REQUEST NOTES RC FM-86B S--6 1RCE2 VIS

l,

  • VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PASE
  • REVISION 32
  • 0003
  • DATE 86/10/20 *
  • CATEGORY e-s-2 PRESSURE RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER ITEM NUMBER B7.30 ITEM DESCRIPTION STEAM GENERATOR BOLTS, STIJDS, AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C114481 COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A C-1 lRCElA VIS RC Ftt-86A c-6 1RCE1B VIS RC Ftt-86A J-1 lRCElC VIS
  • * ' VIRGINIA ELECTRIC AND POWER COMPANY *
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 33 *
  • ASME SECTION XI EDITION 80W80 * .REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY S-S-2 PRESSURE RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER If ITEM NUMBER  : B7.50 ITEM DESCRIPTION: PIPING BOLTS, STUDS, AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

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

CH Ftt-88C S-6 CH93-1502 VIS CH Ftt-88C 0-6 CH9S-1502 VIS CH Ftt-88C A-6 CH97-1502 VIS RC Ftt-86A I-s RClOS-1502 VIS RC Ftt-86A S-8 Rc11s-1so2 VIS RC Ftt-86A S-7 RC116-1502 VIS RC Ftt-86A C--:8 RC117-1502 VIS RC Ftt-86A S-3 RC129-1502 VIS RC Ftt-86A S-2 Rc131-1so2 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

          • MMMMMMMM*******
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 34 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-S-2 PRESSURE RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER
                          • iHIMMMMM*********M**M***lf***********************************M**M**M*********************

ITEM NUMBER  : B7.50 ITEM DESCRIPTION : PIPING BOLTS, STUDS, AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAM REtIEF PROGRAM COMPONENT (11448 l COORD NUMBER METHOD REQUEST NOTES

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

RC Frt-86A C-3 RC132-1502 VIS RC Frt-86A K-3 RC146-1502 VIS RC Frt-86A K-2 RC147-1502 VIS RC Frt-86A J-3 RC148-1502 VIS RC Frt-86A 1-3 RC44-1502 VIS RC Frt-86A E-3 RC45-1502 VIS RC Frt-86A E-8 RC46-1502 VIS RC Frt-86B H-5 RC37-1502 VIS RC Frt-86B S-5 RC3S-1502 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 35 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY s-s--2 PRESSURE RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER
  • ITEM NUMBER B7.50 ITEM DESCRIPTION FIIPING BOLTS, STUDS, AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAH RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REEST NOTES RC.: Ftt-86B S--5 RC39-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT l INSERVICE INSPECTION PLAN SUNMARY INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 36 *
  • REVISION 0003 *
  • 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, STUDS, AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (114481 comm NUMBER METHOD REQUEST NOTES CH Ftt-88C E-2 CHl-1502 VIS CH Ftt-88C H-4 CHlct-1503 VIS CH Fftc88C E-2 CHS-1502 VIS CH- Ftt-88C E-2_ CH6S-1502 VIS CH Ftt-88C B-3 CHS-1503 VIS CH Ftt-88C S-6 CH93-1502 VIS CH Ftt-88C 0-6 CH9S-1502 VIS CH Ftt-88C A-6 CH9rl502 VIS RC Ftt-86A 1-s RClOS-1502 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92 PAGE 37
  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • 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, STUDS, AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES RC FM-86A 0---2 RC11-2501R VIS RC FM-86A A-8 RC112-1502 VIS RC FM-86A S-7 RC116-1502 VIS RC FM-86A C--8 RCll?-1502 VIS RC FM-86A 0---7 RC12-2501R VIS RC FM-86A A-2 Rc12s-1so2 VIS RC FM-86A S-3 RC129-1502 VIS RC FM-86A 1-4 RC13-2501R VIS RC FM-86A e-2 RC131-1502 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 38 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-S--2 PRESSURE RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER

~***************************************************************************************************

ITEM NUMBER  : 87.70 ITEM DESCRIPTION : VALVE BOLTS, STUDS, AND NUTS FLOW. FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A C--3 RCI32-1502 VIS RC Ftt-86A C--2 RC139-1502 VIS RC Ftt-86A L-2 RC141-1502 VIS RC Ftt-86A K-3 RC146-1502 VIS RC Ftt-86A K-2 RC147-1502 VIS RC Ftt-86A J--3 RClcta-1502 VIS RC Ftt-86A J-2 RC1S3-I502 VIS RC Ftt-86A A-2 RC19S-1502 VIS RC Ftt-86A A-6 RC199-1502 VIS

  • SURRY ~ POW.ER STATION UNIT 1
  • INSERVICE INSPECTION PLAN

SUMMARY

                    • KKKKKKKKK*

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 39 *
  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • DATE 86/10/20 *
                                                • -KKKKKKKK*******************************************************************
  • CATEGORY B-S-2 PRESSURE RETAINING BOLTING, TWO INCHES ANO LESS IN DIAMETER *
                      • KKKKKKKKKKKKK**************************K*K***********************************************

ITEM NUMBER  : B7.70 ITEM DESCRIPTION : VALVE BOLTS, STUDS, AM> NI.ITS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD RElWEST NOTES RC Ftt-86A L-2 RC200-1502 VIS RC Ftt-86A 1-3 RCl'.;4-1502 VIS RC Ftt-86A E-3 RC45-1502 VIS RC Ftt-86A E-8 RC46-1502 VIS RC Ftt-86A C-2 RCS3-1502 VIS RC Ftt-86A e-2 RCSS-1502 VIS RC Ftt-86A B-6 RC56-1502 VIS RC Ftt-86A C-5 RCS?-1502 VIS RC Ftt-86A 1-1 RCSS-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION Ut:IIT l INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 40
  • 0003
  • DATE 86/10/20 *
                                                                                                                                                                  • IHf*****************
  • CATEGORY e-s----2 PRESSURE RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER
  • ITEM NUMBER  : 67.70 ITEM DESCRIPTION : VALVE BOLTS, STUl)S, AND NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAH LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

~

RC Ftt-86A K-4 RC59-1502 VIS RC Ftt-86A A-7 RC60-1502 VIS RC Flt-866 F-7 RC14-1502 VIS RC Ftt-866 F-5 RClS-1502 VIS RC Ftt-866 1-5 RCJS-1502 VIS RC Ftt-866 H-5 RC3J-1502 VIS RC Ftt-866 S----5 RC:SS-1502 VIS RC Ftt-866 S----5 RC39-1502 VIS RC Ftt-868 H-5 RC61-1502 VIS

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASHE SECTION XI EDITION 80W80

  • PAGE 41 *
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-G-2 PRESSURE RETAINING BOLTING, TWO INCHES AND LESS IN DIAMETER
                                                                                                              • ii********************************************

ITEM NUMBER  : B7.70 ITEM DESCRIPTION : VALVE BOLTS, STUDS, Am NUTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT* C11448) COORD NUMBER METHOD REQUEST NOTES RHR Ftt-87A L-S RH16-l502 VIS RHR Ftt-87A 0-7 RH18:.602 VIS RHR Ftt-87A J-5 RH23-602 VIS SI i=tt-898 B-1 5!144-1502 VIS SI Ftt-898 e-s sn4s-1so2 VIS SI Ftt-89B B-2 SI1S3-l502 VIS SI Ftt-898 e-s SI4S-1502 VIS SI Ftt-898 C-7 SI46-1502 VIS SI Ftt-898 B-8 SI47-1502 VIS

  • SURRY POWER STATION UNIT l
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 42 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-G-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 RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES SI Ftt-898 S-2 SI48-1502 VIS SI Ftt-898 S-2 SI49-1502 VIS SI Ftt-898 S-3 SI50-1502 VIS SI Ftt-898 C--1 SI74-1502 VIS SI Ftt-898 0--2 5175-1502 VIS SI Ftt-898 0--1 SI85-1502 VIS L
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 43 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-H INTEGRAL ATTACHMENTS FOR VESSELS
  • ITEM NUMBER B8.10 ITEM DESCRIPTION RV INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A F-S lRCRl VOL

VIRGINIA ELECTRIC AND POWER COMPANY *

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 44 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-H INTEGRAL ATTACHMENTS FOR VESSELS ITEM NUMBER B8.20 ITEM DESCRIPTION PZR INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES RC FM-86B S-6 1RCE2 VOL
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 45 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY S-J PRESSURE RETAINING WELDS IN PIPING
                            • ii*************************************************************************************

ITEM NUMBER  : B9.ll ITEM DESCRIPTION : CIR.CUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES

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

CH Ftt-88C H-5 CH122-152 SUR VOL CH Ftt-88C A-6 CH14-1502 SUR VOL CH Ftt-88C 0-6 CHlS-1502 SUR VOL CH Ftt-88C E-5 CH16-1502 SUR VOL CH Ftt-88C C--4 CH214-152 SUR VOL CH Ftt-88C 0-5 CH215-152 SUR VOL

  • SURRY POWER STATION UNIT l *
  • IHSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 46 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 C11448) COORD NUMBER METHOD REQUEST NOTES

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

CH Ftt-88C G-5 CH216-152 SUR VOL CH Ftt-88C G-4 CH99-152 SUR VOL RC Ftt-86A E-2 RC1-2501R SUR VOL RC Ftt-86A 0-2 RCll-2501R SUR VOL RC Ftt-86A 0-7 RC12-2501R SUR VOL RC Ftt-86A r-4 RC13-2501R SUR VOL

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN SUNMARY ******if*************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 47 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING '

ITEM NUMBER B9.ll ITEM DESCRIPTION CIRCUNFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A E-2 RC16-1502 SUR VOL RC Ftt-86A E-4 Rc11-1,so2 SUR VOL RC Ftt-86A E-6 RClS-1502 SUR VOL RC Ftt-86A E-7 RC19-1502 SUR VOL RC Ftt-86A - e-2 RC2-2501R SUR VOL RC FM-86A H-4, RC20-1502 SUR VOL L__

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1

  • INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 48 *
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING
                                                    • IHHHHf*********************************************************************

ITEM NUMBER  : 89.11 ITEM DESCRIPTION : CIRClR1FERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM RELIEF PROGRAM

  • COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

=======

RC Ftt-86A H-2 Rc21-1so2 SUR VOL RC Ftt-86A E-s RC22-1502 SUR VOL RC Ftt-86A e-a RC23-1502 SUR VOL RC Ftt-86A tt-4 RC24-1502 SUR VOL RC Ftt-86A C-4 . RC3-2501R SUR VOL RC Ftt-86A f-S RC4-2501R SUR VOL

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN SU1111ARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 49 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY S-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 (11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A S-6 RCS-2501R SUR VOL RC Ftt-86A C--8 RC6-2501R SUR VOL RC Ftt-86A H-2 R!;7-2501R SUR VOL RC Ftt-86A K-2 RC8-2501R SUR VOL RC Ftt-86A K-4 RC9-2501R SUR VOL RC Ftt-868 S--8 RCl0-2501R SUR VOL L_
  • SURRY POWER STATION UNIT l
  • *INSERVICE INSPECTION PLAN

SUMMARY

If*******************

  • INTERVAL 2, 12/22/82 TO 12/22/92 * ,PAGE 50 *
    • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY S-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER  : B9.ll ITEM DESCRIPTION : CIRCU"IFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST HOTES RC Ftl-86B f-S RClS-1502 SUR VOL RC Ftl-86B H-5 RC34-1502 SUR VOL RC Ftl-86B H-5 RC37-1502 SUR VOL RC Ftl-86B S--5 RC~l502. SUR VOL RC Ftl-86B S--5 RC39-1502 SUR VOL RHR Ftl-87A I-1 RHl-1502 SUR VOL
  • SURRY POWER STATION UNIT 1 *
  • IHSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 51 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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
  • LIHE EXAM RELIEF PROGRAM COMPONENT (11448) comm NUMBER METHOD REQUEST NOTES RHR Ftt-87A L-5 RH16-1502 SUR VOL RHR Ftt-87A J-5 RH23-602 SUR VOL SI Ftt-86A E-6 SI4a-1502 SUR VOL SI Ftt-898 e-1 5!144-1502 SUR VOL SI Ftt-898 e-5 5!145-1502 SUR VOL SI Ftt-898 e-2 5!153-1502 SUR VOL
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 _TO 12/22/92
  • PAGE 52 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM l'M'IBER  : B9.*ll ITEM DESCRIPTION : CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM
  • LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD l'M'IBER METHOD REQUEST NOTES SI Ftt-898 e-s SI4S-1502 SUR VOL SI Ftt-898 C---7 SI46-1502 SUR VOL SI Ftt-898 B-8 SI47-1502 SUR VOL SI Ftt-898 e-2 SI49-1502 SUR VOL SI Ftt-898 B-3 SI50-1502 SUR VOL SI Ftt-898 C---1 SI74-l502 SUR VOL
                          • iH'*************************************************************************************

VIRGINIA ELECTRIC AND POWER COMPANY

  • SURRY POWER STATION UNIT 1
  • IHSERVICE INSPECTION PLAN Sl/Mt1ARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 53 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING
  • ITEl1 HU11BER B9.12 ITEM DESCRIPTION LONGITIJOINAL WELDS IN PIPING FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE. EXAM RELIEF PROGRAM COMPONENT ( 11448) COORD tuIBER METHOD REQUEST NOTES

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

RC FH-86A B-2 RC2-2501R SUR VOL SR-009 RC FH-86A B-6 RC5-2501R SUR VOL SR-009 RC FH-86A K-2 RCS--2501R SUR VOL SR-009

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM INTERVAL 2 DECEMBER 22, 1982 - DECEMBER 22, 1992 REVISION 3 COPY NO:

ASSIGNED TO:

CONTROLLED: YES NO DATE: MARCH 1986 l

  • Sl-000 i

Rev. 3 March 27, 1987

VIRGINIA SURRY ELECTRIC AND POWER COMPANY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

-INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 54 *
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER  : 69.21 ITEM DESCRIPTION : CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

CH Ftt--88C E-2 CHl-:J,502 SUR RC Ftt--86A B-7 RC116-1502 SUR RC Ftt--86A B-2 RC131-1502 SUR RC Ftt--86A C-3 RC132-1502 SUR RC Ftt--86A K-2 RC147-1502 SUR RC Ftt--86A J-3 RC148-1502 SUR RC Ftt--86B F-7 RC14-1502 SUR RC Ftt--86B I-s RC35-1502 SUR RC Ftt--86B H-5 RC61-1so2 SUR

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN SU1111ARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE
  • 55 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING
  • ITEM NUMBER  : B9.21 ITEM DESCRIPTION : CIRCUMFERENTIAL WELDS IN PIPING, NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT 111448) COORD NUMBER METHOD REQUEST NOTES SI Ftt-898 C-1 SI74-1502 SUR SI Ftt-898 0-2 5175-1502 SUR SI Ftt-898 0-1 sra5-1502 SUR
                  • II II 111111111111****111!*****************************************************************************

II

  • SURRY POWER STATION UNIT 1 II*

INSERVICE INSPECTION PLAN

SUMMARY

  • - INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 56
  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • *II
  • II DATE 86/10/20 *
  • CATEGORY S--J PRESSURE RETAINING WELDS IN PIPING II *
                          • 11*****11*****11111111111111111!******************************************************************

ITEM NUMBER  : B9.31 ITEM DESCRIPTION : NOMINAL PIPE SIZE >= 4 IN., BRANCH PIPE CONNECTION FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOO REQUEST NOTES CH FM-88C E-2 CHl-1502 SUR SR-003 VOL RC FM-86A 9-7 RC116-1502 SUR SR-003 VOL RC FM-86A S--2 RC131-1502 SUR SR-003 VOL RC FM-86A K-2 RC147-1502 SUR SR-003 VOL RC FM-86A E-2 RC16-1502 SUR SR-003 VOL RC FM-86A E-4 RC17-1502 SUR SR-003 VOL

                                                                                                                                                          • ll llll llll ll ll ll llllll************
  • SURRY POWER STATION UNIT l INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 57 ASME SECTION XI EDITION 80W80 REVISION 0003
  • DATE 86/10/20 *
                          • llllllllllllllllllllllllllllllllllllllll*******************************************************************
  • CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING
                      • llllllllllllllllllllllllllllllllllllllll**********************************llllllllllllllll***************************

ITEM NUMBER B9.3l ITEM DESCRIPTION NOMINAL PIPE SIZE >= 4 IN., BRANCH PIPE CONNECTION FLOW FLOW SYSTEM/ DIAGRAH DIAGRAH LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES RC Ftr86A E-6 RC18-l502 SUR SR-003 VOL RC Ftr86A E-7 RC19-1502 SUR SR-003 VOL RC Ftr86A H-4 RC20--1502 SUR SR-003 VOL RC Ftr86A H-2 RC21:-1502 SUR SR-003 VOL RC Ftr86A E-5 RC22-l502 SUR SR-003 VOL RC Ftr86A E-8 RC23-1502 SUR SR-003 VOL

VIRGINIA ELECTRIC ANO POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASHE SECTION XI EDITION 80W80

  • PAGE 58 *
  • REVISION 0003 *
  • 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 CONNECTION FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOO REQUEST NOTES

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

RC Ftt-86A lt-4 RC24-1502 SUR SR-003 VOL RC Ftt-86B S-8 RC10-2501R SUR SR-003 VOL RC Ftt-86B F-7 RCI4-1502 SUR SR-003 VOL RC Ftt-86B F-5 RClS-1502 SUR SR-003 VOL RC Ftt-86B 1-5 RC35-1502 SUR SR-003 VOL RHR Ftt-87A 1-7 RHl-1502 SUR SR-003 VOL

  • SURRY POWER STATION UNIT 1* *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82-TO 12/22/92
  • PAGE 59 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-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 RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES CH Ftt-88C E-2 CHS-1502 SUR CH Ftt-88C E-2 CH6S-1502 SUR RC Ftt-86A 1-5 RClOS-1502 SUR RC Ftt-86A B---8 RC11s-1so2 SUR RC Ftt-86A C-8 Rc121-1so2 SUR RC Ftt-86A A-2 RC125-1502 SUR RC Ftt-86A B---3 RC129-1502 SUR RC Ftt-86A L-2 RC141-1502 SUR RC Ftt-86A K-3 RC146-1502 SUR

VIRGINIA ELECTRIC AND POWER COMPANY *

  • SURRY POWER STATION UNIT l.
  • INSERVICE INSPECTION PLAN SUHMARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 60
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-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 RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

RC FM-86A A-2 RC19S-1502 SUR RC FM-86A A-6 RC199-1502 SUR RC FM-86A L-2 RC200-1502 SUR RC FM-86A 1-3 RC44-1502 SUR RC FM-86A E-3 RC45,..1502 SUR RC FM-86A E-8 RC46-1502 SUR RC FM-86A C-2 RCSJ-1502 SUR RC FM-86A B-2 RCSS-1502 SUR RC FM-86A B-6 RCS6-1502 SUR

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 61 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-J PRES~E RETAINING WELDS IN PIPING ITEM NUl18ER 69.32 ITEM DESCRIPTION NOMINAL PIPE SIZE < 4 IN., BRANCH PIPE CONNECTION FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUl18ER METHOD REQUEST NOTES RC Frt-86A C-5 RC57-1502 SUR RC Frt-86A 1-1 RCSS-1502 SUR RC Frt-86A K-4 RC59-1502 SUR RC Frt-86A A-7 RC60-1so2 SUR L__ __
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 62 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B--J PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER  : B9.40 ITEM DESCRIPTION : PIPE SOCKET WELDS FLOW FLOW SYSTEM/ DIAGRAtl DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES

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

CH FH-88C H-4 CHl0-1503 SUR CH FH-88C E-2 . CHS-1502 SUR CH FH-88C E-2 CH6S--1502 SUR

  • CH CH CH FH-88C FH-88C FH-88C B--3 F-4 S-6 CHS--1503 CH9-1503 CH93-1502 SUR SUR SUR CH FH-88C 0-6 CH9S-1502 SUR CH FH-88C A-6 CH9r1502 .SUR RC FH-86A I-s RClOS-1502 SUR

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN SUNMARY*

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 63
  • 0003
  • DATE 86/10/20 *
  • CATEGORY B-J PRESSURE RETAINING .WELDS IN PIPING
                                            • If*****************************************************************************

ITEM NUMBER  : B9.40 ITEM DESCRIPTION : PIPE SOCKET WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT 111448) COORD NUMBER METHOD REQUEST NOTES

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

=======

RC Ftt-86A A-8 RC112-1502 SUR RC Ftt-86A S-8 RCllS-1502 SUR RC Fl1-86A C--8 Rc121-1so2 SUR RC Ftt-86A A-2 RC125-1502 SUR RC. Ftt-86A S-3 RC:.29-1502 SUR RC Ftt-86A C--3 RC132-1502 SUR RC Ftt-86A C--2 R(:139-1502 SUR RC Ftt-86A L-2 RC141-1502 SUR RC Ftt-86A K-3 RC146-1502 SUR

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80.

  • PAGE 64 *
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY S-J PRESSURE RETAINING WELDS *1N PIPING ITEM NUMBER  : B9.40 ITEM DESCRIPTION : PIPE SOCKET WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt--86A J-3 RC148-1502 SUR RC Ftt--86A J-2 RClSJ-1502 SUR RC Ftt--86A A-2 RC19S--:1502 SUR

.RC Ftt--86A A-6 RC199-1502 SUR RC Ftt--86A L-2 RC200-1502 SUR RC Ftt--86A 1-3 RC44-1502 SUR RC Ftt--86A E-3 RC45-:-1502 SUR RC Ftt--86A E-8 RC46-1502 SUR RC Ftt--86A C-2 RCSJ-1502 SUR

  • SURRY POWER STATION UNIT 1 *
  • IHSERVICE INSPECTION PLAN

SUMMARY

              • ~*********
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 65 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 **
  • DATE 86/10/20 * -
  • CATEGORY B-J PRESSURE RETAINING WELDS IN PIPING ITEM NUl1BER  : B9.40 ITEM DESCRIPTION  : PIPE SOCKET WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAI1 COMPONENT C11448) COORD NUl1BER METHOD REQUEST NOTES RC Ftt-86A B-2 RCSS-1502 SUR RC Ftt-86A B-6 RCS6-1502 SUR RC Ftt-86A C-5 RC57-1502 SUR RC Ftt-86A 1-1 RCSS-1502 SUR RC Ftt-86A K-4 RC59-1502 SUR RC Ftt-86A A-7 RC60-1502 SUR RC Ftt-86B 1-s RC3S-1502 SUR RC Ftt-86B H-5 RC61-1so2 SUR SI Ftt-89B C-1 5174-1502 SUR

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2-; 12/22/82 TO 12/22/92 ASHE SECTION XI EDITION 80W80

  • PAGE
  • REVISION 66
  • 0003
  • DATE 86/10/20 *
  • CATEGORY S-J PRESSURE RETAINING WELDS IN PIPING
                                        • lfiflflf****************************************************************************

ITEM HUNBER B9.40 ITEM DESCRIPTION PIPE SOCKET WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD HUNBER METHOD REQUEST NOTES SI Ftt-898 0-2 sus-1so2 SUR SI Ftt-898* 0-1 SI8S-1502 SUR

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL.2, 12/22/82 TO 12/22/92
  • PAGE 67 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-K-1 INTEGRAL ATTACHMENTS FOR PIPING, PUMPS, ANO VALVES ITEM NUMBER  : B10.1D ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES

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

CH FH-88C E-2 cH1-1so2 SUR CH FH-88C tf-4 CHl0-1503 SUR CH FH-88C s-<t CH216-152 SUR CH FH-88C E-2 CHS-1502 SUR CH FH-88C E-2 CH6S-1S02 SUR CH FH-88C 5-3 CHS-1503 SUR CH FH-88C F-:-4 CH9-1503 SUR RC FH-86A B-7 RCU6-1502 SUR RC FH-86A B-2 RC131-1502 SUR

  • VIRGIN!~ 'ELECTRIC AND POWER COMPANY *
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 68 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-K-1 INTEGRAL ATTACHMENTS FOR PIPING, PUMPS, AND VALVES
                                                                • If*******************************************************************

.ITEM NUMBER .  : Bl0.10 ITEM DESCRIPTION: PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD mmBER METHOD REQUEST NOTES RC Ftt-86A C-3 RC132-1502 SUR RC Ftt-86A K-3 RC146-1502 SUR RC Ftt-86A K-2 RC147-1502 SUR RC Ftt-86A H-4 RC20-1502 SUR RC Ftt-86A E-s RC22-1502 SUR RC Ftt-86A H-4 RC24-1502 SUR RC Ftt-86A C-2 RCSJ-1502 SUR RC Ftt-86A

  • 1-1 RCSS-1502 SUR RC Ftt-86A K-4 RC59-1502 SUR
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 69 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-K-1 INTEGRAL ATTACHMENTS. FOR PIPING, PUMPS, AND VALVES ITEM NUMBER  : 810.10 ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD " REQUEST NOTES

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

RC Ftt-868 S--8 RC10-2501R SUR

  • RC,. FM-868 F-7 RC14-1502 SUR RC FM-868 F-s Rc1s-1so2 SUR RC Ftt-868 H-5 RCJ4-1502 SUR RC FM-868 1-5 RCJS-1502 SUR RC FM-868 E-4 RCJ6-602 SUR RC FM-868 H-s RC61-1502 SUR RC FM-868 J-4 RC62-602 SUR RHR Ftt-87A 1-7 RHl-1502 SUR
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 70 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • * -DATE 86/10/20 *
  • CATEGORY B-i<-1 INTEGRAL ATTACHMENTS FOR PIPING, PUMPS, AND VALVES ITEM NUMBER  : 610.10 ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM
  • LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

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

RHR FM-87A L-S RH16-1502 SUR RHR FM-87A L-S RHl?-1502 SUR RHR FM-87A 0-7 RHlS--602 SUR RHR FM-87A J-5 RH23-602 SUR SI FM-896 e-s SI14S-1502 SUR SI FM-896 B-2 SI153-1502 SUR SI FM-896 e-s SI4S-1502 SUR SI FM-896 C-7 SI46-1502 SUR SI FM-898 B-8 SI47-1502 SUR

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 71 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-K-1 INTEGRAL ATTACHMENTS FOR PIPING, PUMPS, AND VALVES ITEM NUMBER Bl0.20

, ITEM DESCRIPTION PUMP INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A A-1 lRCPlA SUR RC Ftt-86A A-6 1RCP1B SUR RC Ftt-86A L-1 lRCPlC SUR

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 PAGE 72

  • ASHE SECTION XI EDITION 80~80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-L-2* PUMP CASINGS ITEM NUMBER B12.10 ITEM DESCRIPTION PUMP CASING WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM-** LINE EXAM RELIEF PROGRAM COMPONENT 'C 11448) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A A-1 lRCPlA VOL RC Ftt-86A A-6 1RCP1B VOL RC Ftt-86A L-1 lRCPlC VOL

  • SURRY POWER STATION UNIT l
  • INSERVICE INSPECTION PLAN

SUMMARY

            • MMMMMMMM****it*

INTERVAL 2, 12/22/82 TO 12/22/92 PAGE 73 ASME SECTION XI EDITION 80W80 REVISION 0003

  • DATE 86/10/20 *
  • CATESORY B-L-2 PU1P CASINGS ITEM NUMBER 812.20 I

ITEM Dl;SCRIPTION PUMP CASING FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

RC FM-86A A-1 lRCPlA VIS RC FM-86A A-6 lRCPlB VIS RC Flt-86A L-1 lRCPlC VIS

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

~

  • PAGE 74 *
  • ASMESECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                                                                                                                  • 1111111111111111*******************
  • CATEGORY B-M-2 VALVE BODIES
  • ITEM NUMBER  : 812.40 ITEM DESCRIPTION : VALVE, VALVE BODY EXCEEDING 4 IN. NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

RC FM-86A E-2 RC1-2501R VIS SR-001 RC FM-86A 0-2 RCll-250lR VIS SR-001 RC FM-86A 0-7 RC12-2501R VIS SR-001 RC FM-86A 1-4 RC13-2501R VIS SR-001 RC FM-86A E-5 RC22-1502 VIS SR-001 RC FM-86A E-8 RC23-1502 VIS SR-001 RC FM-86A tt-4 RC24-l502 VIS SR-001 RC FM-86A C-4 RC3-2501R VIS SR-001 RC FM-86A F-5 RC4-2501R VIS SR-001

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN SUNMARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 75 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-tt-2 VALVE BODIES
  • ITEM NUMBER B12.40 ITEM DESCRIPTION VALVE, -VALVE BODY EXCEEDING 4 IN. NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448 J COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A C-8 RC6-2501R VIS SR-001 RC Ftt-86A H-2 RCr2501R VIS SR-001 RC Fi't-86A K-4 RC9-2501R VIS SR-001 RC . Ftt-86B H-5 RC3rl502 VIS SR-001 RC Ftt-86B S-5 RC38-1502 VIS SR-001 RC Ftt-86B S-5 RC39-1502 VIS SR-001 RHR Ftt-87A 1-7 RHl-1502 VIS SR-001 RHR Ftt-87A L-5 RH16-1502 VIS SR-001 RHR Ftt-87A J-5 RH23-602 VIS SR-001

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT l INSERVICE INSPECTION PLAN Sl.Jt1MARY INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 76 *
    • REVISION 0003 **
  • DATE 86/10/20 *
                                                          • ~**********************************************************************
  • CATEGORY B-tt-2 VALVE BODIES
  • ITEM NUMBER  : B12.40 ITEM DESCRIPTION: VALVE, VALVE BODY EXCEEDING 4 IN. NOHINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11448) COORD NUMBER METHOD REQUEST NOTES SI Ftr86A E-7 RC19-1502 VIS SR-001 SI Ftr86A lt-4 RC20-l502 VIS SR-001 SI Ftr86A lt-2 Rc21-1so2 VIS SR-OOl SI Ftt-898 B-1 su44-1so2

(

VIS SR-001 SI Ftt-898 e-s su4s-1so2 VIS SR-001 SI Ftt-898 e-2 SI1S3-1502 VIS SR-001 SI Ftt-898 e-s SI4S-1502 VIS SR-OOl SI Ftt-898 C-7 SI46-1502 VIS SR-001 SI Ftt-898 B-8 SI47-1502 VIS SR-001

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 77
  • 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-tt--2 VALVE BODIES
  • ITEM NUMBER Bl2.40 ITEM DESCRIPTION VALVE, VALVE BODY EXCEEDING 4 IN. NOMINAL PIPE SIZE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES SI Ftt--898 B-2 SI48-1502 VIS SR-001 SI FM-898 B-2 SI49-1502 VIS SR-001 SI FM-898 S--3 SI50-1502 VIS SR-001
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 78 *

  • PAGE ASME SECTION XI EDITION 80W80 REVISION 0003
  • DATE 86/10/20 *
  • CATEGORY S-H-1 INTERIOR OF REACTOR VESSELS ITEM NUMBER Bl3.10 ITEM DESCRIPTION RV VESSEL INTERIOR FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11448) COORD NUMBER METHOD REQUEST NOTES RPV Ftt-86A F-s lRCRl VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 79 *
  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • DATE 86/10/20 *
                                                                                                                                                    • ~*************************
  • CATEGORY B-tt-3 REMOVABLE CORE SUPPORT STRUCTURES *
                                                                                                                            • ii*************************************

ITEM NUMBER B13.30 ITEM DESCRIPTION RV CORE SUPPORT STRUCTURE CPWRJ FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM* LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES RPV Ftt-86A. Fc-5 lRCRl VIS I

VIRGINIA ELECTRIC ANO POWER COMPANY

  • SURRY POWER STATION UNIT 1
  • INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 80 *

  • PAGE ASME SECTION XI EDITION 80W80 REVISION 0003
  • DATE 86/10/20 *
  • CATEGORY S-0 PRESSURE RETAINING WELDS IN CONTROL ROD DRIVE HOUSINGS
  • ITEM NUMBER 614.10 ITEM DESCRIPTION RV WELDS IN CRD HOUSING FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORO NUMBER METHOD REQUEST NOTES RC Ftt-86.4. F-5 lRCRl VOL

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 81 *
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                  • lf**if***********************************************************************
  • CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS
  • ITEM NUMBER 615.10 ITEM DESCRIPTION RV PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOO REQUEST NOTES RC Ftt-86A F-5 lRCRl VIS
  • SURRY POWER STATION UNIT l INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 82
  • ASME SECTION XI EDITION 80W80 REVISION 0003 *
  • OATE 86/10/20 *
                                                        • ~***********************************************************************
  • CATEGORY S-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER B15.ll ITEM DESCRIPTION RV PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAl1 DIAGRAl1 LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES

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

RC FM-86A F-5 lRCRl VIS

  • SURRY POWER STATION UNIT 1
  • IHSERI/ICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 83 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                                                                                                                • lHHHf************************
  • CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER B15.20 ITEM DESCRIPTION PZR PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES RC FM-86B G-6 1RCE2 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 84
  • 0003
  • DATE 86/10/20 *
  • CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER 615.21 ITEM DESCRIPTION PZR PRESstmE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86B 1RCE2 VIS (1
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

        • if*KKMMKKK*******
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 85 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS
                                  • ~*********lfif*if*********************************************************************

ITEM NUMBER B15.50 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES CH Ftt-88C E-2 CHl-1502 VIS CH Ftt-88C lf-4 CHl0-1503 VIS CH Ftt-88C 0-5 CHl03-1502 VIS CH Ftt-88C C--6 CHl05-1502 VIS CH Ftt-88C S---6 CHl06-1502 VIS CH Ftt-88C F-6 CHlOS-1502 VIS

VIRGINIA ELECTRIC ANO POWER COMPANY SURRY POWER STATION UNIT 1

  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 86
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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/ DIA6RAl1 DIAGRAM LINE EXAM RELIEF PROGRAl1 COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES CH Ftt-88C I-6 CH109-l502 VIS CH Ftt-88C I-6 CHlU-1502 VIS CH Ftt-88C 0'-5 CH1s-1so2 VIS CH Ftt-88C B-7 CH261-1so2* VIS CH* Ftt-88C s-1 cH262-1so2 VIS CH Ftt-88C E-7 CH26J-1502 VIS CH Ftt-88C E-7 ' CH264-1502 VIS CH Ftt-88C H-7 CH26S-1502 VIS CH Ftt-88C H-7 CH266-1502 VIS
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERV~L 2, 12/22/82 TO *12/22/92
  • PAGE 87 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST -NOTES

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

CH FM-88C E-2 CHS-1502 VIS CH FM-88C B-3 CHS-1503 VIS CH FM-88C f-4 CH9-1503 VIS CH FM-88C S-6 CH93-1502 VIS CH FM-88C 0-6 CH95-1502 VIS CH FM-88C A-6 CH9rl502 VIS RC FM-86A E-2 RC1-2501R VIS RC FM-86A K-1 RC!00-1502 VIS RC FM-86A K-1 Rc101-1so2 VIS

                                                                                                                                                                                                      • ~
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • _PAGE 88 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER BlS.50 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUNBER METHOD REQUEST NOTES RC FM-86A K-1 RC102-1502 VIS RC FM-86A J-2 RCl03-l502 VIS RC FM-86A I-s RClOS-1502 VIS
  • RC RC RC.

FM-86A FM-86A FM-86A I-s D-2 A-8 RCl06-1502 Rc11-2so1R RC112-1502 VIS VIS VIS RC FM-86A A-a RC113-2501R VIS RC FM-86A A-8 RC114-1502 VIS RC FM-86A B-8 RCllS-.1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 89 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                        • ~*IHf****************************************************************************
  • CATEGORY S-P All. PRESSURE RETAINING COMPONENTS ITEM HUMBER  : BIS.SO ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD HUMBER METHOD REQUEST NOTES RC Ftt-86A S-7 RC116-1S02 VIS RC Ftt-86A C--8 RC117-1S02 VIS

~c Ftt-86A C--7 RC118-1S02 VIS RC Ftt-86A C--8 RC119-2S01R VIS RC Ftt-86A 0--7 .RC12-2S01R VIS RC Ftt-86A 0--8 RC120-1S02 VIS RC Ftt-86A C--7 Rc121-1so2 VIS

'Re Ftt-86A C--7 RC122-1S02 VIS RC Ftt-86A C--7 RC123-IS02 VIS

i

  • SURRY POWER STATION UNIT 1 **.
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 90 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                          • ii**************************************************************************************
  • 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 RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A C-6 RC124-1502 VIS RC Ftt-86A A-2 RC125-1502 VIS RC Ftt-86A B-4 RC126-1502 VIS RC Ftt-86A A-3 RC127-1502 VIS RC Ftt-86A B-3 RC12S-2501R VIS RC Ftt-86A B-3 RC129-1502 VIS RC Ftt-86A 1-4 RC13-2501R VIS RC Ftt-86A A-4 RC130-1502 VIS RC Ftt-86A B-2 Rcn1-1so2 VIS

~

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

SUMMARY

~NTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 91 *
  • REVISION 0003 *
  • DATE 86/10/20 *
                                  • ii**********************************************************************************
  • CATEGORY S-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 (11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86.A C-3 RC132-1502 VIS RC Ftt-86.A C-4 RC133-2501R VIS RC Ftt-86.A C-3 RC134-1502 VIS RC Ftt-86.A 0-3 RC13S-1502 VIS RC Ftt-86.A C-2 RC136-1502 VIS RC Ftt-86.A C-2 RC13rl502 VIS RC Ftt-86.A C-2 RC13S-1502 VIS RC Ftt-86.A C-2 RC139-1502 VIS RC Ftt-86.A A-'8 RC140-1502 VIS
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN SUNMARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 92 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY S-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 C11448 l COORD NUNBER METHOD REQUEST NOTES RC Ftt-86A L-2 RC141-1502 VIS RC Ftt-86A K-3 RC142-1502 VIS RC Ftt-86A L-3 RC143-1502 VIS RC Ftt-86A K-3
  • RC144-2501R VIS RC Ftt-86A K-3 RC145-1502 VIS RC Ftt-86A K-3 RC146-1502 -VIS RC Ftt-86A K-2 RC147-1502 VIS RC Ftt-86A J-3 RC148-1502 VIS RC Ftt-86A J-3 RC14Crl502 VIS
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 93 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY e-p ALL PRESSURE RETAINING COMPONENTS
                                                                                                                                  • IHHf********************************

ITEM NUMBER  : 815.50 ITEM DESCRIPTION  : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM

  • LINE EXAM RELIEF PROGRAM COMPONENT (11448) comm NUMBER METHOD REQUEST NOTES RC Ftt-86A J-3 RC151-2501R VIS RC Ftt-86A J-4 RC152-1502 VIS RC Ftt-86A J-2 RC153-1502 VIS RC Ftt-86A J-2 RC154-1502 VIS RC Ftt-86A J-2 RC155-1502 VIS RC Ftt-86A J-2 RC156-1502 VIS RC Ftt-86A E-2 RC16-1502 VIS RC Ftt-86A J-4 RC161-1so2 VIS RC Ftt-86A H-3 RC162-1502 VIS
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN ~ARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 94 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS **

ITEM NUNBER  : B15.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW

  • FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD. NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A 1-2 RC163-1502 VIS RC Ftt-86A D-2 RC16S-1502 VIS RC Ftt-86A E-6 RC166-1502 VIS RC Ftt-86A E-'t RC17-1502 VIS RC Ftt-86A D-6 RC172:-1502 VIS RC Ftt-86A S--5 RC173-1502 VIS

~c Ftt-86A E-6 RClS-1502 VIS RC Ftt-86A E-7 RC19-1502 VIS RC Ftt-86A A-2 RC19S-1502 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 95 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                • IHHf*************************************************************************
  • 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 RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES RC FM-86A A-6 RC199-1502 VIS RC FM-86A B-2 RC2-2501R VIS RC FM-86A lf-4 RC20--1502 VIS RC FM-86A L-2 RC200--1502 VIS RC FM-86A lf-2 Rc21-1so2 VIS RC FM-86A E-S RC22-1502 VIS RC FM-86A E-8 RC23-1502 VIS RC FM-86A lf-4 RC24-1502 VIS RC FM-86A C-4 RC3-2501R VIS

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

SUMMARY

INTERVAL 2, 12/22/82 T0.12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 96 *
  • REVISION 0003 *
  • DATE 86/10/20 *
  • ,CATEGORY S-P All PRESSURE RETAINING COMPONENTS ITEM tM1BER  : B15.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM l.EAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAH RElIEF PROGRAM COMPONENT (11448) COORO tM1BER HETiiOD REQUEST NOTES RC Ftt-86A F-5 RC4-2501R VIS RC Ftt-86A 1-3 RC44-1502 VIS RC Ftt-86A E-3 RC45-1502 VIS RC Ftt-86A E-8 RC46-1502 VIS RC Ftt-86A E-2 RC47-1502 VIS RC Ftt-86A E-7 RC48-1502 VIS RC Ftt-86A H-2 RC49-1502 VIS RC Ftt-86A S--6 RCS-2501R VIS RC Ftt-86A C-2 RCS3-1502 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 97 *
  • ASME SECTION XI EDITION 80W80
  • REVISION- 0003 *
  • DATE 86/10/20 *

-* CATEGORY S-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 (11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A S-2 RCSS-1502 VIS RC Ftt-86.A S-6 RC56-1502 VIS RC Ftt-86.A C--5 RC57-1502 VIS
  • - RC RC RC Ftt-86.A Ftt-86.A Ftt-86.A I~l K-4 C--8 RCSS-1502 RC59-1502 RC6-2501R VIS VIS VIS RC Ftt-86.A A-7 RC60-1502 VIS RC Ftt-86.A 0-3 RC63-1502 VIS RC Ftt-86.A 0-8 RC64-1502 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN SUHMARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 98 **
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY S-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER 615.50 ITEM DESCRIPTION PIPING PRES~E RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A 1-3 RC65-1502 VIS RC Ftt-86A H-2 RCr2501R VIS RC Ftt-86A K-2 RCS--2501R VIS
  • RC Ftt-86A K-4 RC9-2501R VIS RC Ftt-86A s-1 RC92-1502 VIS RC Ftt-86A S-1 RC93-1502 VIS RC Ftt-86A B-1 RC94-1502 VIS RC FM-86A C--2 RC95-1502 VIS RC FM-86A S-6 RC96-1502 VIS
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 99
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003
  • DATE 86/10/20 *
                                                                                                  • ~***************************IHf*********************
  • CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER  : BlS.SO ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A B-6 RC9rl502 VIS RC Ftt-86A B-6 RC9S-1S02 VIS RC Ftt-86A C--6 RC99-1502 VIS RC Ftt-86B G-8 RC10-2501R VIS RC Ftt-86B F-7 Rc14-1so2 VIS RC Ftt-86B F-S Rc1s-1so2 VIS RC Ftt-86B F-6 Rc22s-1so2 VIS RC Ftt-86B f-7 RC226-1502 VIS RC Ftt-86B G-6 RC22rl502 VIS

VIRGINIA SURRY INSERVICE ASME ELECTRIC POWER SECTION AND INSPECTION XI POWER STATION PLAN EDITION COMPANY UNIT 1

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 aowao

  • PAGE
  • REVISION 100
  • 0003 *
  • * *DATE 86/10/20 *
  • CATEGORY B-P ALL PRESSURE RETAINiNG COMPONENTS
  • ITEM NUMBER  : BlS.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86B ~6 RC22S--1502 VIS RC Ftt-86B H-6 RC229-1502 VIS RC Ftt-86B H-6 RC230--1502 VIS RC Ftt-86B F-4 Rc2s-1so2 VIS RC Ftt-86B ~4 RC26-1502 VIS RC Ftt-86B ~4 RC2rl502 VIS RC Ftt-86B H-5 RC34-1502 VIS RC Ftt-86B H-5 RC3rl502 VIS RC Ftt-86B ~s RC3s--1502 VIS
  • SURRY POWER STATION UNIT l **
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 101 *
  • ASME SECTION XI EDITION 80W80 '
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS
                                                        • llif**********************************************************************

ITEM NUMBER  : B15.50 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNOARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES RC 'nt-86B S--5 RC39-1502 VIS RC FM-86B H-6 RCS0-1502 VIS RC Ftf-86B I-S RCSl-1502 VIS RC FM-868 H-5 RC61-1so2 VIS RC FM-86B 0-5 RC66-1502 VIS RC FM-868 F-S RC67-1502 *vis RHR FM-87A I-7 RHl-1502 VIS RHR FM-87A L-S RH16-1502 VIS RHR FM-87A L-S RH17-1502 VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 102
  • ASME SECTION XI EDITION 80W80 REVISION 0003 *
  • DATE 86/10/20 *
                                              • If****************************************************************************
  • CATEGORY S-P ALL PRESSURE RETAINING COMPONENTS
                                              • lHf***************************************************************************

ITEM NUMBER  : B15.50 iTEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF' PROGRAM COMPONENT ( 11448) COORD NUMBER METHOD REQUEST NOTES SI FH-898 S-6 SI39-l502 VIS '

SI FH-898 E-7 SI40-l502 VIS SI FH-898 S-8 SI41-1502 VIS

  • ss ss ss FH-828 FH-828 FH-82B C-1 C-2 C-2 SS1-ICN9 SS100-ICN9 ss101-ICN9 VIS VIS VIS
  • SURRY POWER STATION UNIT. l *
  • INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 PAGE 103 *

  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 RELIEF PROGRAM COMPONENT (114481 COORD NUMBER METHOD REQUEST NOTES

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

ss Fl't-82B C-2 SSl02-ICN9 VIS ss Fl't-82B C-2 SS103-ICN9 VIS ss Fl't-82B C-1 SS2-ICN9 VIS ss Fl't-82B C-2 SS3-ICN9 VIS ss Ftt-82B C-2 SS4-ICN9 VIS ss Ftt-82B C-2 sss-ICN9 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 104 *
  • ASME SECTION XI .EDITION 80W80
  • REVISION 0003 *
  • 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 RELIEF PROGRAM COMPONENT ( 11448) COORD NUMBER METHOD .REQUEST NOTES

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

CH FM-SSC E-2 cH1-1502 VIS CH FM-SSC H-4 CHl0-151>3 VIS CH FM-SSC 0-5 cH103-1502 VIS CH FM-SSC C--6 CHl05-1502 VIS CH FM-SSC S--6 CHl06-1502 VIS CH FM-88C F-6 CHiOS-1502 VIS CH FM-SSC I-6 CH109-1502 VIS CH FM-SSC I-6 CH111-1502 VIS CH FM-SSC 0-5 cH15-1502 VIS

VIRGINIA ELECTRIC ANO POWER COMPANY' SURRY POWER STATION UNIT l INSERVICE INSPECTION PLAN Sutff1ARY INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 105 *
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS
                          • ii**************************************************************************************

ITEM NUMBER  : B15.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

CH Ftt-88C B-7 CH261-1502 VIS CH Ftt-88C B-7 CH262-1502 VIS CH Ftt-88C E-7 CH263-1502 VIS CH Ftt-88C E-7 CH264-1502 VIS CH Ftt-88C H-7 CH265-1502 VIS CH Ftt-88C H-7 CH266-1502 VIS CH Ftt-88C E-2 CHS-1502 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 106 *
  • ASME SECTION XI EDITION 80W80 REVISION 0003 *
  • 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 ( 11448) COORD NUMBER METHOD REQUEST NOTES CH Ftt-88C e-3 CH8-1503 VIS CH Ftt-88C F-4 CH9-1503 VIS CH Ftt-88C S-6 CH93-1502 VIS CH Ftt-88C [t-6 CH9S-1502 VIS CH Ftt-88C A-6 CH9rl502 VIS RC Ftt-86A E-2 RC1-2501R VIS RC Ftt-86A K-1 RCl00-1502 VIS RC Ftt-86A K-1 RClOl-1502 VIS RC Ftt-86A K-1 RC102-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION. 80W80

  • PAGE
  • REVISION 107
  • 0003
  • DATE 86/10/20 *
  • CATEGORY e-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 C11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A J--2 RClOJ-1502 VIS RC Ftt-86A 1-s RClOS-1502 VIS RC Ftt-86A 1-5 RC106-1502 VIS RC Ftt-86A 0-2 Rc11-2so1R VIS RC Ftt-86A A-8 RC112-1502 VIS RC Ftt-86A A-8 RC11J-2501R VIS RC Ftt-86A A-8 RC114-1502 VIS RC Ftt-86A B---8 RCllS-1502 VIS RC Ftt-86A B---7 RC116-1502 VIS
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 108 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) cocmD NUMBER METHOD REQUEST NOTES RC Ftt-86A C-8 RC117-1502 VIS RC Ftt-86A C-7 RC118-1502 VIS RC Ftt-86A C-8 RCll 9-2501R VIS RC Ftt-86A D-7 RC12-2501R VIS RC Ftt-86A D-8 RC120-1502 VIS RC Ftt-86A C-7 Rc121-1so2 VIS RC Ftt-86A C-7 RC122-1502 VIS RC Ftt-86A C-7 RC123-1502 VIS RC Ftt-86A C-6 RC124-1502 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92 PAGE 109 *
  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • DATE 86/10/20 *
                                                  • MMMMMMlfMlf**************************iflflflflflflfMlflflf***!flflflf**lflflflflflflflf**iflf********
  • CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NU118ER B15.51 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD RE~EST NOTES

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

RC Flt-86A A-2 RC125-1502 VIS RC Flt-86A B-4 RC126-1502 VIS RC FM-86A A-3 RC127-1502 VIS RC Flt-86A. S---3 RC12S-2501R VIS RC Flt-86A B-3 RC129-1502 VIS RC Flt-86A I-'-4 RC13-2501R VIS RC Flt-86A A-4 RC130-1502 VIS RC Flt-86A B-2 RC131-1502 VIS RC Flt-86A C-3 RC132-1502 VIS

VIRGINIA ELECTRIC ANO POWER COMPANY *

  • SURRY POWER STATION UNIT l
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 110 "*
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 ( 11448) COORD NUMBER METHOD REQUEST NOTES RC FM-86A C-4 RC133-2501R VIS RC FM-86A C-3 RC134-1502 VIS RC FM-86A 0-3 RC135-1502 VIS RC FM-86A C-2 RC136-1502 VIS RC FM-86A C-2 RC13rl502 VIS RC FM-86A C-2 RC138-1502 VIS RC FM-86A C-2 RC139-1502 VIS RC FM-86A A-8 RC140-1502 VIS RC FM-86A L-2 RC141-1502 VIS

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASHE SECTION XI EDITION 80W80

  • PAGE 111 *
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A K-3 RC142-1502 VIS RC Ftt-86A L-3 RC143-1502 VIS RC Ftt-86A K-3 RC144-2501R VIS RC Ftt-86A K-3 RC145-1502 VIS RC Ftt-86A K-3 RC146-1502 VIS RC Ftt-86A K.:..2 RC147-1502 VIS RC Ftt-86A J-:3 RCl<+S-1502 VIS RC Ftt-86A J-3 RC149-1502 VI~

RC Ftt-86A J-3 RC1Sl-2501R VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 112 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER  : 615.51 ITEM-DESCRIPTION: PIPING PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOO REQUEST NOTES RC Ftt-86A J-4 RC152-1502 VIS RC Ftt-86A J-2 RC153-1502 VIS RC Ftt-86A J-2 RC154-1502 VIS RC Ftt-86A J-2 RC155-1502 VIS RC Ftt-86A J-2 RC156-1502 VIS RC Ftt-86A E-2 RC16-1502 VIS RC Ftt-86A J-4 RC161-1502 VIS RC Ftt-86A H-3 RC162-1502 VIS RC Ftt-86A I-2 RC163-1502 VIS
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 113 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                                                                                                              • ~****************************
  • CATEGORY S-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER  : B15.51 ITEM DESCRIPTION: P:::PING PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

-------- ------- ------- ------ ------- -- ... ~---

RC FH-86A D-2 RC16S-1502 VIS RC Ftt-86A E-6 RC166-1502 VIS RC Ftt-86A. E-4 RClrl502 VIS

  • RC Ftt-86A 1)-6 RC172-l502 VIS RC Ftt-86A G-5 RC173-1502 VIS RC FH-86A E-6 RClS-1502 VIS RC Ftt-86A E-7 RC19-1502 VIS RC Ftt-86A A-2 RC198-1502 VIS RC FH-86A A-6 RC199-1502 VIS

)

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

111111111111 II*************

INTERVAL 2, 12i22/82 TO 12/22/92 114 *

  • PAGE
  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • DATE *a6/l0/20 *
                          • llllllllllllllllllllllllllllll*****if******************************************************************
  • CATEGORY S-P ALL PRESSURE RETAINING COMPONENTS
                                                  • 11111111111111******************************11111111~1111*******************************

ITEM NUMBER  : B15.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOU-IDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD tM1BER METHOD REQUEST NOTES RC Ftt-86A e-2 RC2-2501R VIS RC Ftf-86A H-4 RC20-1502 VIS RC Ftt-86A L-2 RC200-1502 VIS RC Ftf-86A H-2 Rc21-1so2 VIS RC Ftf-86A E-5 RC22-1502 VIS RC Ftt-86A E-8 RC23-1502 VIS RC Ftt-86A H-4 RC24-1502 VIS RC Ftf-86A C-4 RC3-2501R VIS RC Ftf-86A F-5 RC4-2501R VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN SUT111ARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PASE 115 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003
  • J
  • DATE 86/10/20 *
  • CATEGORY B-P
  • ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER  : 615.51 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11448 I COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A 1-3 RC44-1502 VIS RC Ftt-86A E-3 RC45-1502 VIS

- RC Ftt-86A E-8 RC46-1502 VIS RC Ftt-86A E-2 RC47-1502 VIS RC Ftt-86A E-7 RC48-1502 VIS RC Ftt-86A H-2 RC49-1502 VIS RC Ftt-86A S-6 RC5-2501R VIS RC Ftt-86A C---2 RC53-1502 VIS RC Ftt-86A B-2 RC55-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN.

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 116 *
  • REVISION ASME SECTION XI EDITION 80W80
  • 0003 *
  • 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 RELIEF PROGRAM COMPONENT ( 11448) COORD NUMBER METHOD REQUEST NOTES RC Ftt-86A S-6 RC56-I502 VIS RC Ftt-86A C--5 RC5r1502 VIS RC Ftt-86A r-1 RCSS-1502 VIS RC Ftt-86A K~4 RC59-1502 VIS RC Ftt-86A C--8 RC6-2501R VIS RC Ftt-86A A-7 RC60---1502 VIS RC Ftt-86A 0-3 RC63-1502 VIS RC Ftt-86A 0-8 RC64-1502 VIS RC

  • Ftt-86A I-3 RC6s-1so2 VIS
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 117 *
  • ASHE SECTION XI EDITION 80W80.
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY e-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 (11448) COORD NUMBER METHOD REQUEST NOTES RC FM-86A H-2 RC7-2501R VIS RC FM-86A K-2 RCS-2501R VIS RC FM-86A K-4 RC9-2501R VIS RC- FM-86A S-1 RC92-1502 VIS RC FM-86A S-1 RC93-1502 VIS RC FM-86A S-1 RC94-1502 VIS RC FM-86A C-2 RC95-1502 VIS RC FM-86A S-6 - RC96-1502 VIS RC FM-86A S-6 RC97-1502 VIS
                                      • <<1111111111111111 lllflf*********************************************************************

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 118 ASME SECTION XI EDITION 80W80 REVISION 0003
  • DATE 86/10/20 *
          • ~********111111111111111111*******************~********************************************************
  • CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS
                      • lllllllllllflfllll*********************************lllllfllllllllllllll**IIIIIIIIIIIIIIIIII**************************

ITEM NUMBER 615.51 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM

  • LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

RC Ftt-86A B-6 RC9S-1502 VIS RC Ftt-86A C-6 RC99-1502 VIS RC Ftt-86B S---8 RC10-2501R VIS RC Ftt-86B F-7 RC14-1502 VIS RC Ftt-86B F-S RClS-1502 VIS RC Ftt-86B F-6 Rc22s-1so2 VIS RC Ftt-86B F-7 RC226-1502 VIS RC Ftt-86B S---6 RC22J-1502 VIS RC Ftt-86B S---6 RC22S-1502 VIS

  • SURRY POWER STATION UNIT l
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 119 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COO!m NUMBER METHOD REQUEST NOTES RC Frt-86B lt-6 RC229"-l502 VIS RC Frt-86B lt-6 RC230--1502 VIS RC Frt-86B F-4 Rc2s-1so2 VIS RC Frt-86B G-4 RC26-1502 VIS RC Frt-86B G-4 RC2rl502 VIS RC Frt-86B lt-5 RC34-l502 VIS RC Frt-86B lt-5 RC3rl502 VIS RC Frt-86B G-5 RC:38-1502 VIS RC Frt-86B G-S RC39"-1502 VIS
  • SURRY POWER STATION UNIT l *
  • IHSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 120 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY B-P ALL PRESSURE RETAINING COMPONENTS
  • ITEM HUNBER  : B15.51.

.ITEM DESCRIPTION  : PIPING PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES RC FM-86B H-6 RCS0-1502 VIS RC FM-86B I-s Rcs1-1so2 VIS RC FM-86B H-5 RC61-l.502 VIS RC FM-86B 0--5 RC66-1502 VIS RC FM-86B F-S RC6rl502 VIS RHR FM-87A 1-7 RHl-1502 VIS RHR FM-87A L-5 RH16-1502 VIS

)

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 121 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES RHR Ftt-67A L-s RH17-1502 VIS SI Ftt-698 S-6 SI39-1502 VIS SI . Ftt-698 E-7 SI40-1502 VIS SI Ftt-698 S-6 SI41-1502 VIS ss Ftt-62B C--1 ss1-ICN9 VIS ss Ftt-62B C--2 SS100-ICN9 VIS ss Fl't-62B C--2 ss101-ICN9 VIS ss Fl't-62B C--2 ss102-ICN9 VIS ss Ftt-62B C--2 SSl03-ICN9 VIS
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 122 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                                  • IHf*****************************************************************
  • 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 RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES ss Ftt-82B C-1 SSZ-ICN9 VIS ss Ftt-82B C-2 SS3-ICN9 VIS ss Ftt-82B C-2 SS4-ICN9 VIS ss Ftt-82B C-2 sss-ICN9 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTER'.'AL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 123
  • 0003
  • DATE 86/10/20 *
  • CATEGORY S-P ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER 815.60 ITEM DESCRIPTION PUl1P PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) comm NUMBER METHOD REQUEST NOTES

=======

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

RC Ftt-86A A-1 lRCPlA VIS RC Ftt-86A A-6 lRCPlB VIS RC Ftt-86A L-1 lRCPlC VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 124 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY S-P ALL PRESSURE RETAINING COMPONENTS
  • ITEM NUMBER B15.61 ITEM DESCRIPTION PUMP PRESSURE RETAINING BOU'mARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD RE~UEST NOTES RC Ftt-86A A-1 lRCPlA VIS I

RC Ftt-86A A-6 1RCP1B VIS RC Ftt-86A L-1 lRCPlC VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 125 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-A PRESSURE RETAINING MELDS IN PRESSURE VESSELS ITEM NUMBER Cl.IO ITEM DESCRIPTION PRESSURE VESSEL SHELL CIRCUHFERENTIAL MELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAN LINE EXAM RELIEF PROGRAM COMPONENT C11448 l COORD HUMBER METHOD REQUEST NOTES CH Ftt-72A F-4 1CHE4 VOL CH Ftt-888 S-3 lCHEl VOL CH Ftt-888 C-2 1CHE2 VOL CH FM-888 J-1 1CHFL2 SUR SR-004 CH Ftt-888 E-3 1CHFL3 SUR SR-012 CH Ftt-888 B-6 1CHFL4A VOL CH Ftt-88B B-7 1CHFL4B VOL t1S Ftt-64A .4-2 lRCElA VOL MS Ftt-64A A-4 1RCE1B VOL

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT l INSERVICE INSPECTION PLAN SU1111ARY INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 126 *
  • REVISION 0003 *
  • DATE 86/10/20 *
      • ~*****************************~****************************************************************
  • CATEGORY C-A PRESSURE RETAINING WELDS IN PRESSURE VESSELS
  • ITEM NUMBER  : Cl.10 ITEM DESCRIPTION : PRESSURE VESSEL SHELL CIRCUMFERENTIAL WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES

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

MS Ftt-64A A-6 lRCElC VOL RHR Fl't"'.87A e--2 lRHElA VOL RHR Ftt-87A 0--2 lRHElB VOL

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 127 *
  • ASME SECTION XI EDITION aowao
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-A PRESSURE RETAINING WELDS IH PRESSURE VESSELS ITEM NUMBER  : Cl.20 ITEM DESCRIPTION: PRESSURE VESSEL HEAD CIRCU'1FERENTIAL WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD tM'IBER METHOD REQUEST NOTES

/====== ------- -------

CH lCHE4 VOL CH F~888 lCHEl VOL CH FH-888 1CHE2 VOL CH F~888 J-1 lCHFL2 SUR SR-004 CH F~88B E-3 1CHFL3 SUR SR-012 CH F~88B 1CHFL4A VOL CH F~888 B-7 1CHFL4B VOL CH F~888 H-2 1CHT1<2 VOL CH F~88C 1CHE3 VOL

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 IHSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION eoweo PAGE REVISION 0003 128

      • lflllflflflflflflflflf****iHf
  • DATE 86/10/20
  • CATEGORY C-A PRESSURE RETAINING WELDS IN PRESSURE VESSELS *
                    • lflflfllllllllll'llll'll'lf*****************************************lllllllllfllll******************************

ITEM HUMBER  : Cl.20 ITEM DESCRIPTION : PRESSURE VESSEL HEAD CIRCUMFERENTIAL WELDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM

  • LINE EXAM RELIEF PROGRAM COMPONENT (11448) comm NUNBER METHOD REQUEST NOTES

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

MS Flt-64A A-2 lRCElA VOL t1S Flt-64A A--4 1RCE1B VOL t1S Flt-64A A-6 lRCElC VOL RHR Flt-87A S-2 lRHElA VOL RHR Flt-87A 0-2 1RHE1B VOL

VIRGINIA ELECTRIC AND POWER COMPANY

  • SURRY POWER STATION UNIT l
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO_ 12/22/92 PAGE 129
  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • DATE 86/10/20 *
  • CATEGORY C-A PRESSURE RETAINING WELDS IN PRESSURE VESSE.LS ITEM NUMBER  : Cl.30 ITEM DESCRIPTION : PRESSURE VESSEL TIJBESHEET-TO-SHELL WELD FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORO NUNBER METHOD REQUEST NOTES CH FM--88C F-2 1CHE3 VOL 115 FM--64A A-2 lRCElA VOL 115 FM--64A A-4 lRCElB VOL l1S FM--64A A-6 lRCElC VOL

/

  • SURRY POWER STATION UNIT 1 *
  • If INSERVICE INSPECTION PLAN SUMHARY iHHHfiHflflflflflflflflflflf****
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 130 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 If If CATEGORY C-8 PRESSURE RETAINING NOZZLE WELDS IN VESSELS
  • If If ITEM NUl1BER  : c2.21 ITEH DESCRIPTION : NOZZLE-TO-SHE LLC OR HEAD J WELDS IH PRES~E VESSELS FLOW FLOW SYSTEH/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUHBER METHOD REQUEST NOTES FM Flr64A A-2 lRCElA s~ SR-007 VOL FM Flr64A A-4 1RCE1B SUR SR-007 VOL
  • FM HS Flr64A Flr64A A-6 A-2 lRCElC lRCElA

~

VOL s~

VOL SR-007 SR-007 HS Flr64A A-4 1RCE1B SUR SR-007 VOL HS Flr64A A-6 lRCElC s~ SR-007 VOL

VIRGINIA ELECTRIC AND POWER COMPANY

  • SURRY POWER STATION UNIT l
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 131 *
  • ASME SECTION XI EDITION 80W80 REVISION 0003 DATE 86/10/20
  • CATEGORY C-B PRESSURE RETAINING NOZZLE WELDS IN VESSELS
  • ITEM NUMBER C2.21 ITEM DESCRIPTION NOZZLE-TCH;HELL(OR HEAD) WELDS IN PRESSURE VESSELS fLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

RHR Flt-87A B-2 lRHElA SUR SR-002 VIS RHR Flt-87A 0-2 lRHElB SUR SR-002 VIS

VIRGINIA ELECTRIC ANO POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 132 *
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-B PRESSURE RETAINING NOZZLE WELDS IN VESSELS
  • ITEM NUMBER  : C2.22 ITEM DESCRIPTION : NOZZLE INSIDE RADIUS SECTIONS IN PRESSURE VESSELS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448 l COORD HUh13ER METHOD REQUEST NOTES F~ Flt-64A A-2 lRCElA VOL FW Flt-64A A-4 lRCElB VOL FW Flt-64A A-6 lRCElC VOL t1S Flt-64A A-2 lRCElA VOL t1S Flt-64A A-4 lRCElB VOL MS Flt-64A A-6 lRCElC VOL RHR Flt-87A B-2 lRHElA VIS SR-002 RHR Flt-87A 0-2 lRHElB VIS
                            • lllllllllllllllllllllfll************************************illllllflflflllllflflflflllflflfH***°*****************
  • SURRY POWER STATION UNIT 1 If INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 133
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003
  • DATE 86/10/20 *
  • CATEGORY C-C INTEGRAL ATIACHMENTS FOR VESSELS, PIPING, PUMPS, AHD VALVES
  • lf**********lflflllflflllflflflfllll*****************************************************************************

ITEM NUMBER  : C3. 10 ITEM DESCRIPTION : PRESSURE.VESSEL INTEGRALLY WELDED ATIACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD *REQUEST NOTES

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

CH Ftt-888 ~3 lCHEl SUR CH Ftt-888 C-2 1CHE2 SUR CH Ftt-888 J-1 1CHFL2 SUR CH Ftt-888 E-3 1CHFL3 SUR CH Ftt-88B B-6 1CHFL4A SUR CH Ftt-88B B-7 1CHFL4B SUR CH Ftt-888 H-2 1CHTK2 SUR RHR Ftt-87A e-2 lRHElA SUR RHR Ftt-87A 0-2 1RHE1B SUR

                          • 11111111111111111111**************************************1111111111 II II********************************
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 134 *

  • PAGE ASME SECTION XI EDITION 80W80 REVISION 0003 *
  • DATE 86/10/20 *
                            • 11**111111111111111111111111111111********************************************************************
  • CATEGORY C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES
                          • 111111111111111111111111111111***********************************111111111111111111************11111111111111111111******

ITEM NUl1BER C3 *.' 40 ITEM DESCRIPTION PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES AF Ftt-68A E-6 WAPDl-601 SUR AF Ftt-68A C-6 WAPDl0-601 SUR AF FM-68A a-s WAPDll-601 SUR

- AF Ftt-68A B-6 WAPDlZ--601 SUR AF Ftt-68A B-6 WAPD13-60l SUR AF Ftt-68A B-6 WAPD14-601 SUR AF Ftt-68A E-6 WAPDZ--601 SUR

.6.F Ftt-68A C-4 WAPD9-601 SUR AF Ftt-688 J-6 WAPDS0-601 SUR

  • It
  • SURRY POWER STATION UNIT 1
  • It It It INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 135 *
  • ASME SECTION XI EDITION 80W80 It REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES
                                                  • ltltiE************************************************************************

ITEM NUMBER C3. 40 ITEM DESCRIPTION PIPING INTEGRALLY-WELDED ATTACHMENTS FLOW FLOW SYSTEry DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C 11448) COORD HUMBER METHOO REQUEST NOTES AF FH-688 1-7 MAPDSl-601 SUR BO Fl1124A A-2 WGCBl-601 SUR BO F11124A 0-2 WGCBlOS-601 SUR BO F11124A A-4 WGCB2-601 SUR BO FM124A A-5 WGCB3-601 SUR BO F11124A A-5 WGCB6-601 SUR cc FH-72A E-6 CClOl-151 SUR cc FH-72A L-3 CC16-121 SUR cc Ftt-72A S-2 CC262-151 SUR

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 136
  • 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES cc Flt-72A 0-6 CC93-151 SUR cc Flt-72B 0-4 CC7S-l5l SUR cc Flt-72B S--2 cc80-1s1 SUR CH Flt-88A C-1 cH2s-1s2 SUR CH Flt-88B A-6 CHU-1503 SUR CH Flt-88B F-6 CH113-1503 SUR CH Flt-886 A-6 CH12-1503 SUR CH Flt-886 H-2 CH120-152 SUR CH Flt-886 A-6 CH13-1503 SUR
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 137 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 C11448) COORD NUMBER METHOD REQUEST NOTES CH Ftt-888 S-8 CH17-152 SUR CH Ftt-888 F-6 CH2-1503 SUR CH Ftt-888 S-2 CH23-152 SUR CH Ftt-888 H-6 CHJ-1503 SUR CH Ftt-888 C-1 CH7-602 SUR CH Ftt-888 A-4 CH79-1503 SUR CH
  • Ftt-888 B-3 CHS-1503 SUR CH Ftt-88B 0-5 CH80-1s03 SUR CH Ftt-888 D-6 CH81-1503 SUR

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 138
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C--C INTEGRAL ATIACHMENTS FOR VESSELS, PIPING,* PUMPS, AND VALVES ITEM NUMBER  : C3. 40 ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATIACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES CH Ftt-888 F-6 CH89-1503 SUR CH Ftt-888 B-6 CH90-1503 SUR CH Ftt-888 A-6 CH91-l503 SUR CH Ftt-888 B-3 CH99-152 SUR CH Ftt-88B J-2 DG26-152 SUR CH Ftt-88C E-2 CHl-1502 SUR CH Ftt-88C E-2 CH6B-1502 SUR CH Ftt-88C S-3 CH79-1503 SUR cs Ftt-84A *F-5 CSl-153 SUR
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 139 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C---C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES ITEM NUMBER  : C3. 40 ITEM DESCRIPTION : PIPING INTEGRALLY WEl,.DED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM - LINE EXAM RELIEF PROGRAM COMPONENT (11448) cornm NUMBER METHOD REQUEST NOTES

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

cs Ftt-84A C-3 CS14-152 SUR cs *Ftt-84A f-5 CS2-153 SUR cs Ftt-84A J-2 CS22-153 SUR

  • cs cs cs Ftt-84A Ftt-84A Ftt-84A S-3 J-2 s-4 CS27-153 CS3-153 CS33-153 SUR SUR SUR cs Ftt-84A H-5 CS34-153 SUR cs Ftt-'84A S-4 CS36-153 SUR cs Ftt-84A J-3 CS4-153 SUR
  • SURRY POWER STATION UNIT 1 *
  • .INSERVICE INSPECTION PLAN SUNMARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 140 *
  • A'SME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-C INTEGRAL ATIACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES
                                                                                                                                          • lflf*****************************

ITEM NUMBER C3. 40 ITEM DESCRIPTION PIPING INTEGRALLY WELDED ATIACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST. NOTES cs Ftt-84A S-1\ CSS-153 SUR cs Ftt-84A E-7 CSS0-153 SUR j

cs Ftt-84A 0-6 csas-1s3 SUR

  • cs cs cs Ftt-84A Ftt-84A Ftt-84A K-2 0-6 1-4 CS8S-153 cs91-1s3 CS94-153 SUR SUR SUR cs Ftt-84A J-4 CS9S-153 SUR cs Ftt-84A C-6 CS9S-153 SUR CV Ftt-85A S-5 CVS-151 SUR
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • *INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 141 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES ITEM NUHBER  : C3. 40 ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUHBER METHOD REQUEST .NOTES

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

FW Ftt-68A 0---3 WFPD13-601 SUR FW Ftt-68A 0---2 WFPD17-601 . SUR FW Ftt-68A 0---5 WFPD9-601 SUR

    • HS HS HS Ftt-64A Ftt-64A Ftt-64A C-2 B-4 C-5 SAEl-121 SAEZ-121 SAE3-121 SUR SUR SUR MS Ftt-64A 0-4 SAE37-121 SUR MS Ftt-64A 0---4 SAEJS-121 SUR MS Ftt-64A 0---4 SAE39-121 SUR
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 142 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD HUMBER METHOD REQUEST NOTES MS Ftt-64A C-4 SDHV4-121 SUR MS Ftt-64A E-4 SHP016-601 SUR MS Ftt-64A S-7 SHPOS-601 SUR MS Ftt-64A E-3 SHP06-601 SUR MS Ftt-64A F-3 SHPD?-601 SUR MS Ftt-64A F-4 SHPOS-601 SUR MS Ftt-64A E-3 SHPl-601 SUR MS Ftt-64A E-5 SHPZ-601 SUR MS Ftt-64A 5-3 SHP22-601 SUR

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION aowao

  • PAGE
  • REVISION 143
  • 0003
  • DATE 86/10/20 .*
  • CATEGORY C--C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES *
                      • M********iHt**if***************************************************************************

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

  • EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

MS Ftt-64A C--5 SHP23-601 SUR MS Ftt-64A B-6 SHP24-601 SUR MS Ftt-64A C-8 SHP2'r601 SUR I

MS Ftt-64A E-6 SHP3-601 SUR MS Ftt-64A C--8 SHP30-601 SUR MS Ftt-64A f-8 SHP31-601 SUR MS Ftt-64A D-2 SHP4S-601 SUR MS Ftt-64A 0-4 SHP46-601 SUR MS Ftt-64A 0-6 SHP47-601 SUR

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 144 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES
                            • ii*************************************************************************************

ITEM NUMBER  : C3. 40 ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

MS Ftt-64A S-8 SHP57-601 SUR RHR FM-87A 0--3 RHllt-602 SUR RHR Ftt-87A E-5 RH12-602 SUR RHR FM-87A J-4 RH1s-1s2 SUR RHR Ftt-'87A 0--7 RHlS-602 SUR RHR Ftt-87A E-4 RH19-602 SUR RHR Ftt-87A E-7 RH2-602 SUR RHR Ftt-87A J-3 RH21t-152 SUR RHR FM-87A B-6 RH4-602 SUR

  • SURRY POWER STATION UNIT 1
  • INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 145 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES
                          • llll l(l(l(l(l(l(l!l!lllf********-*****************************************************************

ITEM NUMBER  : C3. 40 ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD . NUMBER METHOD REQUEST NOTES

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

RHR Ftt-87A 0-6 RHS-602 SUR RHR Ftt-87A C-4 RH7-602 SUR RHR Ftt-87A A-3 RHS-602 SUR RHR Ftt-87A B-3 RH9-602 SUR RL FM118A 0-1 RL6-152 SUR RS Ftt-848 ,J-4 RSl-153 SUR RS Ftt-848 C-3 RSl0-153 SUR RS Ftt-848 lt-2 RSll-153 SUR RS Ftt-848 f-2

  • RSlZ-153 SUR
  • , I*
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN SUNMARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 146 *
  • ASME SECTION XI EDITION 80W80
  • REVIS!ON 0003 *
  • 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 ( 11448) COORD NUMBER METHOD REQUEST NOTES

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

RS' Ftt-848 C-4 RS13-153 SUR RS Ftt-84B 0-6 RS14-153 SUR RS Ftt-848 lt-4 RS2-153 SUR RS Ftt-848 J-1 RS20-153 SUR RS Ftt-84B J-1 RS21-153 SUR RS Ftt-848 S--1 RS22-153 SUR RS Ftt-848 S--1 RS23-153 SUR RS Ftt-848 K-2 RS3-153 SUR RS Ftt-848 1-2 RS4-153 SUR

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/2U92 *
  • PAGE 147 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD *REQUEST NOTES

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

RS Ftt-848 0-4 RS9-153 SUR RT FM138A A-1 RTl00-601 SUR RT FM138A E-1 RTlOl-153 SUR RT Ft1138A A-<+ RTll0-601 SUR RT Ft1138A E-4 RTlll-153 SUR RT Ft1138A A~6 RT120-601 SUR RT Ft1138A 0-6 RT121-153 SUR SI Ftt-89A F--<+ SI102-152 SUR SI Ftt-89A E-8 SI106-l53 SUR

  • SURRY POWER STATION UNIT 1 *
  • INS ERV ICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 148 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                • "*IHHHHf*********************************************************************
  • 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 C11448) COORD NUMBER METHOD REQUEST NOTES SI Ftt-89A I-6 SI130-1S2 . SUR SI Ftt-89A S-6 sn4-1s3 SUR SI Ftt-89A e-2 SI14r1S03 SUR SI Ftt-89A C-6 SI1S0-1S3 SUR SI Ftt-89A B-4 SI1S2-1S02 SUR SI Ftt-89A D-6 SI1r1S2 SUR SI Ftt-89A E-4 SI170-1S3 SUR SI Ftt-89A e-3 SI48-1S02 .SUR SI Ftt-89A 1-6 SIS-1S3 SUR
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 149 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES ITEM NUMBER  : CJ. 40 ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES SI Ftt-89A J-2 SI57-1503 SUR SI Ftt-89A H-2 SISS-1503 SUR SI Ftt-89A 1-4 SI6-153 SUR SI Ftt-89A A-1 SI70-1503 SUR SI Ftt-89A A-3 SI72'-1503 SUR SI Ftt-89A 8-7 SISJ-152 SUR SI Ftt-89A 0-7 SI84-152 SUR SI Ftt-89A D-6 SI92'-153 SUR SI Ftt-898 H-5 snos-1s2 SUR
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 150 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                  • KKKKKKNKKK*****************************************************************
  • CATEGORY C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES K
                      • KKKKKNKKKKKKKKKK*****-*******************************KKKKKKK*****************************

ITEM NUMBER  : C3. 40 ITEM DESCRIPTION : PIPING INTEGRALLY WELDED ATTACHMENTS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES SI Ftt-890 S-1 SI144-1502 SUR SI Ftt-890 5-5 SI145-1502 SUR SI Ftt-890 1-1 SI146-1503 SUR

  • SI SI SI Ftt-890 Ftt-890 Ftt-890 1-2 S-2 S-5 SI147-1503 SI153-1502 5!45-1502 SUR SUR SUR SI Ftt-890 C--7 5!46-1502 SUR SI Ftt-890 S-8 SI47-1502 SUR SI Ftt-890 S-2 SI4S--1502 SUR

VIRGINIA ELECTRIC AND POWER COMPANY

  • SURRY POWER STATION UNIT l
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 151 *

_, SECTION XI EDITION 80W80

  • REVISION 0003 *
  • 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 111448) COORD NUMBER METHOD REQUEST NOTES

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

SI Ftt-898 S--2 SI49-1502 SUR

.SI Ftt-698 S--3 SI50-1502 SUR SI Ftt-698 F-1 SI70-1503 SUR SI Ftt-698 A-3 SI72-1503 SUR SI Ftt-698 C-1 SI74-1502 SUR SI Ftt-898 0-2 5175-1502 SUR SI Ftt-698 F-1 SI76-1503 SUR SI Ftt-698 0-3 SI79-l.502 SUR SI Ftt-898 0-2 SIB0-1502 SUR

  • SURRY POWER STATION UNIT.l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 152 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-C INTEGRAL ATTACHMENTS FOR VESSELS, PIPING, PUMPS, AND VALVES
  • ITEM NUMBER c3; 40 ITEM DESCRIPTION PTPING INTEGRALLY WELDED ATTACHMENTS FLOW ,FLOW SYSTEM/ DIAGRAM* DIAGRAM* LINE EXAM RELIEF PROGRAM COMPONENT- (11448) COORD NUMBER METHOD REQUEST NOTES SI Ftt-898 0-2 sia1-1so2 SUR SI Ftt-898 0-1 SISS-1502 SUR
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 153 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-D PRESSURE RETAINING BOLTS GREATER THAN TWO INCHES IN DIAMETER ITEM NUNBER  : C4.30 ITEM DESCRIPTION : PUtfP BOLTS AND STUDS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM
  • coMPONENT ( 11448) COORD NUMBER METHOD REQUEST NOTES

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

CH Ftt-888 0-7 lCHPlA VOL CH Ftt-888 E-1 lCHPlB VOL CH Ftt-888 S-7 lCHPlC VOL

  • SURRY POWER STATION UNIT 1 *
  • IHSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 154 *

  • PAGE ASME SECTION XI EDITION 80W80 REVISION 0003 *
  • DATE 86/10/20 *
                    • XXXXXXXXXXXXXXXXXXXXXXXXXX****************************************************************
  • CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING *
                            • .llXllllllllllll************************************~**************************************

ITEM NUMBER  : CS.11 ITEM DESCRIPTION: PIPiHG CIRCUMFERENTIAL WELD<= 1/2 T NOMINAL WALL THICKNESS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

CH Ftt-888 S-8 CHlrl52 SUR CH Ftt-888 F-7 CHlS-152 SUR CH Ftt-888 S-7 CH19-152 SUR CH Ftt-888 S-7 CH20l-152 SUR CH Ftt-88B F-7 CH202-152 SUR CH Ftt-888 E-7 CH203-152 SUR CH Ftt-888 B-8 CH204-152 SUR CH Ftt-888 C-8 cH2os-1s2 SUR CH Ftt-88B C-8 CH206-152 SUR

                      • l(l(l( l(l( l( l(l(******************************ll l(l(l(l(ll llllllll******lf l(l( 1111 l(l(l(l( ***************************
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

l(l(l(l(l(lfll*************

l( INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 155 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING
  • l(l(l(l(l(l(l(********l(l(l(l(lllllfl(lll(l(********************************l(l(l(l(l(l(l(l(l(l(l(l(*******************************

ITEM NUMBER  : C5.ll ITEM DESCRIPTION: PIPING CIRCUt1FERENTIAL WELD <= 1/2 T NOMINAL WALL THICKNESS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES CH Fl't-888 0-7 CH72-152 SUR cs Fl't-84A F-:-5 cs1-1s3 SUR cs Fl't-84A C--3 CS14-152 SUR cs Fl't-84A B-2 ,cs1s-1s2 SUR cs Fl't-84A F-5 cs2-1s3 SUR cs Fl't-84A F-2 css-1s2 SUR cs Fl't-84A K-2 CS87-153 SUR cs Fl't-84A K-2 csaa-1s3 SUR cs Fl't-84A K-2 CS89-153 SUR

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 156
  • REVISION 0003 *
  • DATE 86/10/20 *
                                              • MMXlfMMMXXXlf*lf*********************************XXXlfXMMMXX**********************
  • CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING
                            • XMXXMXXXXMMMMMMX**********************************************************************

ITEM NUMBER  : CS.11 ITEM DESCRIPTION : PIPING CIRCUMFERENTIAL WELD<= 1/2 .T NOMINAL WALL THICKNESS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RElIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES MS Ftt-64A C-4 SDHV4-601 SUR MS Ftt-64A B-3 SHP22-601 SUR MS Ftt-64A C-5 SHP23-601 SUR MS Ftt-MA B-6 SHP2<r601 SUR MS Ftt-64A C-3 SHP37-601 SUR MS Ftt-64A B-4 SHP:38-601 SUR MS Ftt-64A C-6 SHP39-601 SUR MS Ftt-64A 0-2 SHP45-601 SUR MS Ftt-64A 0-4 SHP46-601 SUR

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 157 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                              • IHf*******************************************************************
  • CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING
  • ITEM NUMBER CS.11 ITEM DESCRIPTION PIPING CIRCUMFERENTIAL WELD <= 1/2 T NOMINAL WALL THICKNESS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT lll448J COORD NUMBER METHOD REQUEST NOTES

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

MS FM-64A 0-6 SHP4r601 SUR RC FM-86B tt-4 RC20-602 SUR RC FM-86B S-4 RC40-602 SUR RC FM-86B S-4 RC41-602 SUR RC FM-86B F-4 RC42-602 SUR RC FM-86B J-4 RC62-602 SUR RC FM-898 F-6 SI46-1502 SUR RHR FM-87A 0-3 RHl0-602 SUR RHR FM-87A E-s RH12-602 SUR

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 158 *
  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • 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 THICKNESS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD *REQUEST NOTES

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

RHR Flt-87A 1-s RH14-602 SUR RHR Flt-87A 0-7 RHlS-602 SUR

., RHR RHR RHR Flt-87A Flt-87A Flt-87A E-4 E-7 1-4 RHlCr-602 RHZ--602 RH20--152 SUR SUR SUR RHR FH-:87A J-5 RH23-602 SUR RHR Flt-87A B-6 RH4-602 SUR RHR Flt-87A D-6 RHS-602 SUR RHR Flt-87A A-'5 RH6-602 SUR

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 159 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER C?.11 ITEM DESCRIPTION PIPING CIRCUMFERENTIAL WELD<= 1/2 T NOMINAL W~LL THICKNESS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES RHR Ftt-87A C---4 RH7-602 SUR RHR Ftt-87A A-3 RHS-602 SUR RHR Ftt-87A S-3 RH9-602 SUR RS Ftt-848 J-4 RSl-153 SUR RS Ftt-84B C---3 RSl0-153 SUR RS Ftt-84B H-4 RS2-153 SUR RS Ftt-84B E-8 RS24-153 SUR RS Ftt-84B E-7 RSJ-153 SUR RS Ftt-84B E-8 RSS-153 SUR
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 160 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                          • lfif*********************************************************************
  • CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING ITEM tu1BER  : CS.11 ITEM DESCRIPTION.: PIPING CIRCUMFERENTIAL WELD<= 1/2 T NOMINAL WALL THICKNESS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM L:INE EXAM RELIEF PROGRAM COMPONENT ( 11448) COORD NUl1BER METHOO REQUEST NOTES

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

RS FM-84B 0-4 RS9-153 SUR SI FM-89A A-8 sn-1s3 SUR SI FM-89A F-4 SI102-152 SUR

VIRGINIA ELECTRIC AND POWER COMPANY

  • SURRY POWER STATION UNIT l
  • INSERVICE INSPECTION PLAN

SUMMARY

    • MMMMMMMM**********

INTERVAL 2, 12/22/82 TO 12/22/92 161

  • PAGE
  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • DAlE 86/10/20 *
                            • MMMMMMM*******************************************************************************
  • CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING
                                • MMMM********************************************************************************

ITEM NUMBER CS.11 ITEM DESCRIPTION PIPING CIRCUMFERENTIAL WELD<= 1/2 T NOMINAL WALL THICKNESS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES SI Ftt-89A F-S SI149-153 SUR SI Ftt-89A C-5 SilS0-153 SUR SI Ftt-89A C-6 SilSl-153 SUR SI Ftt-89A 0-6 Silr-152 SUR SI Ftt-89A E-4 5!170-152 SUR SI Ftt-89A 0-6 SilS-152 SUR SI Ftt-89A E-6 SI19-152 SUR SI Ftt-89A' A-8 SI2-153 SUR SI Ftt-89A I-3 SIS-152 SUR

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 162 *
  • REVISION 0003 *
  • DATE 86/10/20 *
                                    • IHHHHf*****************************************************************************
  • CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING ITEM NUMBER  : CS.11 ITEM DESCRIPTION : PIPING CIRCUl1FERENTIAL WELD<= 1/2 T NOMINAL WALL THICKNESS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES SI FM-89A I-6 sis-1s3 SUR SI FM-89A H-4 SI6-153 SUR SI FM-89A S--4 SI7-152 SUR SI FM-89A E-6 SI7S--152 SUR SI FM-89A S--7 SI83-152 SUR SI FM-89A 0-7 SIM-152 SUR SI FM-898 H-8 513-153 SUR SI FM-898 B-S SI4S-1502 SUR SI FM-898 B-8 SI47-1502 SUR
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 163 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                              • MMMMMMMM*****************************************************************************
  • CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING ITEM NUNBER CS.11 ITEM DESCRIPTION PIPING CIRCUMFERENTIAL WELD<= 1/2 T NOMINAL WALL THICKNESS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11448) COORD NUMBER METHOD REQUEST NOTES SI Ftt-898 SI48-1502 SUR SI Ftt-898 S--2 SI49-1502 SUR
  • VIRGIN.IA ELECTRIC AND POWER COMPANY *
  • SURRY POWER STATION UNIT 1 *
  • ( *
  • INSERVICE INSPECTION PLAN SUMl1ARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 164 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING
                                                                                                                                                                              • ~********

ITEM HUMBER  : CS.21 ITEM DESCRIPTION: PIPING CIRCUMFERENTIAL WELD> 1/2 T NOMINAL WALL THICKNESS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) *cooRD HUMBER METHOD REQUEST NOTES

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

FW F~68A 0-3 WFPD13-601 SUR VOL FW F~68A 0-2 WFPD17-601 . SUR VOL

  • FW F~68A 0-5 WFPD9-6_0l SUR VOL MS F~64A A-2 SHPl-601 SUR VOL MS F~64A A-S SHP2-601 SUR VOL MS F~64A B-3 SHP22-601 SUR VOL
  • SURRY POWER STATION UNIT l *
  • IHSERVICE INSPECTION PLAN SUMNARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 165 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 THICKNESS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOO REQUEST NOTES MS Ftt-64A C-5 SHP23-601 SUR VOL MS Ftt-64A S--6 SHP24-601 SUR VOL MS Ftt-64A A-6 SHP3-601 SUR VOL

(

SI Ftt-89A S--4 sns2-1so2 SUR VOL SI Ftt-898 S--1 SI144-1502 SUR VOL SI Ftt-898 S--5 SI14S-1502 SUR VOL

VIRGINIA ELECTRIC AHO POWER COMPANY SURRY POWER STATION UNIT l IHSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION aowao

  • PAGE 166 *
  • R,EVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C--F PRESSURE RETAINING WELDS IN PIPING
  • ITEM NUMBER CS.21 ITEM DESCRIPTION PIPING CIRCUl1FERENTIAL WELD > 1/2 T NOMINAL WALL THICKNESS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPO_NENT C11448) comm NUMBER METHOD REQUEST NOTES SI Ftt-898 B-2 SI153-1502 SUR VOL SI Ftt-898 B-2 SI48-1502 SUR VOL SI Ftt-898 B-2 SI49-1502 SUR VOL SI Ftt-898 9-3 SIS0-1502 SUR VOL

~-

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

            • ii*************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 167 *
  • ASME SECTION XI EDITION 80W80 REVISION 0003 *
  • DATE 86/10/20 *
                                                                                    • iHE***iHE***************************************************
  • CATEGORY C-F PRESSURE RETAINING WELDS IN PIPING
                                                                                                  • iE********iE*****************************************

ITEM NUMBER CS.22 ITEM DESCRIPTION PIPING LONGITUDINAL WELD > 1/2 T NONINAL MALL THICKNESS FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES HS Ftt-64A A-2 SHPl-601 SUR VOL MS Ftt-64A A-5 SHPZ-601 SUR VOL MS Ftt-64A B-3 SHP22-601 SUR VOL HS Ftt-64A C-5 SHP23-601 SUR VOL HS Ftt-64A B-6 SHP24-601 SUR VOL MS Ftt-64A __ A-6 SHP3-601 SUR VOL

  • SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 168

  • PAGE
  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • 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 EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

MS Ftt-64A B-3 SHP22-601 SUR t1S Frt-64A c-s SHP23-601 SUR MS Ftt-64A S-6 SHP24-60l SUR 11S Frt-64A C-3 SHP37-601 SUR 115 Frt-64A B-4 SHP38-60l SUR 115 Frt-64A C-6 SHP39-601 SUR 115 Frt-64A 0-2 SHP4S-601 SUR MS Frt-64A 0-4 SHP46-60l SUR MS Frt-64A 0-6 SHP47-601 SUR

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 169 *
  • ASME SECTION XI EDITION.80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY c-tt ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER  : C7.10 ITEM DESCRIPTION : PRESSURE VESSEL PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD* NUMBER METHOD REQUEST NOTES CH Ftt-72A F-4 1CHE4 VIS CH Ftt-888 S--3 lCHEl VIS CH Ftt-88B C--2 1CHE2 VIS CH Ftt-888 J-1 1CHFL2 VIS CH Ftt-88B E-3 1CHFL3 VIS CH Ftt-888 B-6 1CHFL4A VIS CH Ftt-888 B-7 1CHFL4B VIS CH Ftt-888 H-2 1CHTK2 VIS l1S Ftt-64A A-2 lRCElA VIS

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

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 170 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                            • ii*************************************************************************************
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER  : C7.10 ITEM DESCRIPTION: PRESSURE VESSEL PRESSURE RETAINING BoutlJARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAH . LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES MS Ftt-64A A-4 1RCE1B VIS MS Ftt-64A A-6 lRCElC VIS RHR Ftt-87A S-2 lRHElA VIS ~

RHR Ftt-87.t. 0-2 1RHE1B VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 171 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-H ALL PRESSURE-RETAINING COMPONENTS
  • ITEM NUMBER  : C7.ll ITEM DESCRIPTION : PRESSURE VESSEL PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) coorm NUMBER METHOD REQUEST NOTES

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

CH Ftt-72A f-4 1CHE4 VIS CH Ftt-888 S-3 lCHEl VIS CH FH-888 C-2 1CHE2 VIS CH Ftt-888 J-1 1CHFL2 VIS CH Ftt-888 E-3 1CHFL3 VIS CH Ftt-888 B-6 1CHFL4A VIS CH Ftt-888 B-7 1CHFL4B VIS CH Ftt-888 H-2 1CHTI<2 VIS MS Ftt-64A A-2 lRCElA VIS

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 172
  • 0003 *
  • DATE 86/10/20 *
                                                                                                        • il********lE-**************************************
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS
  • ITEM HUMBER  : C7.ll ITEM DESCRIPTION: PRESSURE VESSEL PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAH DIASRAH LINE EXAH RELIEF PROGRAH COMPONENT C11448) COORD NUMBER METHOO REQUEST NOTES r
= ------ =

MS Ftt-64A A-4 1RCE1B VIS MS Ftt-64A *A-6 lRCElC VIS RHR Ftt-87A e-2 lRHElA VIS RHR Ftt-87A 0-2 1RHE1B VIS

VIRGINIA ELECTRIC ANO POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 173 ASME SECTION XI EDITION 80W80 REVISION Q003
  • 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 (11448) COORO NUMBER METHOD REQUEST NOTES BO FM124A B-5 WGCB-601 VIS BO FM124A A-2 WGCBl-601 VIS BO FM124A A-4 WGCB2-601 VIS BO FM124A A-S WGCBJ-601 VIS CH Ftt-88A C-1 cH2s-1s2 VIS CH Ftt-88A E-2 CH29-1S2 VIS CH Ftt-88A e-2 CH32-1S2 VIS CH Ftt-888 F-3 CHl00-152 VIS CH Ftt-888 A-6 CHll-1503 VIS L _ _ __
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 174
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES CH Ftt-888 H-3 CH112-152 VIS CH Ftt-888 E-5 CH113-1503 VIS CH Ftt-88B F-3 CH117-152 VIS CH Ftt-888 F-3 CHllS-152 VIS CH Ftt-88B I-2 CH119-152 VIS CH Ftt-88B A-6 CH12-1503 VIS CH Ftt-888 H-2 CH120--152 VIS CH Ftt-888 1-1 CH121-152 VIS CH Ftt-888 C-1 CH125-602 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN SUMl1ARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 175 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES 1

CH Ftt-88B A-7 CH13-1503 VIS CH Ftt-888 H-2 CH163-152 VIS CH Ftt-88B 1-3 CH164-152 VIS CH Ftt-88B S--3 CH165-152 VIS CH Ftt-888 B-7 CH16?-1503 VIS CH Ftt-88B B-8 CHl?-152 VIS CH Ftt-888 F-7 CHlS-152 VIS CH Ftt-88B 0-7 CH18?-1503 VIS CH Ftt-888 F-7 CH188-1503 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 176
  • 0003
  • 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

~YSTEM/ DIAGRAM DIAGRAM . LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

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

CH Ftt-888 S-7 CH189-1503 VIS CH Ftt-888 H-7 CH19-152 VIS CH Ftt-888 H-2 CH190-152 VIS CH Ftt-888 F-4 CH191-152 VIS CH Ftt-888 0-3 CH192-152 VIS CH Ftt-888 K-1 CH193-152 VIS CH Ftt-888 H-6 CH196-152 VIS CH Ftt-888 F-2 CH199-152 VIS CH Ftt-888 F-6 CH2-1503 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 177 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES

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

CH FM-888 D-6 CH20-1503 VIS CH FM-888 H-7 CH20l-152 VIS CH FM-888 f-7 CH202-152 VIS CH FM-888 E-7 CH203-152 VIS CH FM-888 S-8 CH204-152 VIS CH FM-888 C-8 cH2os-1s2 VIS CH FM-888 C-8 CH206-152 VIS CH FM-888 0-8 CH207-1503 VIS CH FM-888 f-8 CH20S--1503 VIS

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 178 *
  • REVISION 0003 *
  • '* DATE 86/10/20 *
  • CATEGORY: C-H ALL PRESSURE RETAIN!NG COMPONENTS
  • ITEM HUMBER  : C7.20 ITEM DESCRIPTION ; PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE I -

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11448) COORD HUMBER METHOD REQUEST NOTES

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

CH Ftt-888 H-8 CH209-1503 VIS CH Ftt-888 J-4 cH211-1s2 VIS CH Ftt-88B J-4 CH212-152 VIS CH Ftt-88B H-6 CH22-1503 VIS CH Ftt-888 0--8 CH224-1503 VIS CH Ftt-88B E-8 cH22s-1so3 VIS CH Ftt-88B S--8 CH226-1503 VIS CH Ftt-886 F-2 CH23-152 VIS CH Ftt-88B B-4 CH231-1503 VIS

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE REVISION 179
  • 0003
  • DATE. 86/10/20 *
                                                    • lflflflflf*********************************************************************
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS

'**************************************************************lHC*********lHf***********lflflf***********

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

SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11448) COORD NUMBER METHOD* REQUEST NOTES

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

CH Ftt-888 F-1 CH234-152 VIS CH Ftt-888 F-2 CH236-152 VIS CH Ftt-88B H-2 CH23rl52 VIS CH Ftt-888 S-3 CH23S-152 VIS CH Flt-888 E-2 CH239-152 VIS CH Ftt-88B H-2 CH24-152 VIS CH Ftt-888 A-6 CH276-1503 VIS CH Ftt-888 H-6 CH3-1503 VIS CH Ftt-888 1-3 *cH58-152 VIS

.\

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

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 180 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES CH Ftt-888 I-3 CH59-152 VIS CH Ftt-888 H-2 CH67-152 VIS CH Ftt-88B 0-5 CH69-1503 VIS
  • CH CH CH Ftt-888 Ftt-888 Ftt-888 C-2 E-6 S-6 CH7-602 CH70-1503 CH71-1503 VIS VIS VIS CH Ftt-888 E-7 CH72-152 VIS CH Ftt-888 H-3 CH73-152 VIS CH Ftt-88B B-6 CH74-1503 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

                      • lHf*******
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 181 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 ( 11448) COORD NUMBER METHOD REQUEST HOTES CH Ftt-888 Et-6 CH76-1503 VIS CH Ftt-888 Et-7 CH77-1503 VIS CH Ftt-888 F-2 CH7S-152 VIS CH Ftt-888 0-6 CHS0-1503 VIS CH Ftt-888 0-6 CHSl-1503 VIS CH Ftt-88B E-1 CH87-152 VIS CH Ftt-888 E-S CH89-l503 VIS CH Ftt-888 B-6 CH90-1503 VIS CH Ftt-886 A-6 CH91-1503 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 182 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES CH Ftf-888 B-3 CH99-152 VIS CH Ftf-88C E-2 CHl-1502 VIS CH Ftf-88C E-5 CHIOl-1502 VIS CH Ftf-88C lt-5 CH102-1502 VIS CH Ftf-88C D-5 CHlOJ-1502 VIS CH Ftf-88C S-6 CHl06-1502 VIS CH Ftf-88C I-6 CH109-1502 VIS CH Ftf-88C lt-5 CH122-152 VIS CH Ftf-88C B-3 CH123-1502 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 183 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY c-H ALL PRESSURE RETAINING COMPONENTS
                                                    • MMMMMMMM***********************MM**ifif*************************************

ITEM NUMBER  : C7.20 ITEM DESCRIPTION: PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11448) COORD NUMBER METHOD REQUEST NOTES

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

CH Ftt-88C E-4 CH124-152 VIS CH Ftt-88C A-5 CH14-1502 VIS CH Ftt-88C F-2 CH1502 VIS CH Ftt-88C E-5 CH16-1502 VIS CH Ftt-88C B-4 CH214-152 VIS CH Ftt-88C 0-5 cH21s-1s2 VIS CH Ftt-88C S--4 CH216-152 VIS CH Ftt-88C C-5 CH217-152 VIS CH. Ftt-88C f-5 CH21S--152 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE . INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 184 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 C11448) COORD NUMBER METHOD REQUEST NOTES CH Ftt-88C 1-4 CH219-152 VIS CH Ftt-88C S-3 CH223-1502 VIS CH Ftt-88C H-2 CH232-602 VIS

  • CH CH CH Ftt-88C Ftt-88C Ftt-88C I-3 E-3 E-2 CH233-602 CH240-l.502 CHS-1502 VIS VIS VIS CH Ftt-88C I-2 CH6-602 VIS CH
  • Ftt-88C* E-2 CH6S-1502 VIS CH Ftt-88C S-3 CH79-1503 VIS

(.,

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 185 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY ~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 C11448) COORD NUMBER METHOD REQUEST NOTES CH Ftt-88C B-3 CH8-1503 VIS CH Ftt-88C F-2 CH82-1so2 VIS CH FM-88C S-3 CH83-1502 VIS CH Ftt-88C H-2 CH8S-602 VIS CH Ftt-88C H-2 CH86-602 VIS CH Ftt-88C H-7 CH92-1503 VIS CH Ftt-88C E-7 CH94-1503 VIS CH Ftt-88C B-7 CH96-1503 VIS CH Ftt-88C B-5 CH9S-1502 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION-UNIT 1 INSERVICE INSPECTION PLAN SIJMMARY

.INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 186 *
  • REVISION 0003 *
  • 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 (11448 >
  • COORD NUMBER METHOD REQUEST NOTES cs Ftt-84A F-S cs1-1s3 VIS cs Ftt-84A C-3 cs14-153 VIS cs Ftt-84A A-2 CSl'rl52 VIS cs Ftt-84A F-S CS2-153 VIS cs* Ftt-84A J-2 CS22-153 VIS cs Ftt-84A J-2 CS23-153 VIS cs Ftt-84A K-2 CS26-153 VIS cs Ftt-84A J-3 CS2S-153 VIS cs Ftt-84A J-3 CS2'r1S3 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 187 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER C7.20 ITEM DESCRIPTION PIPING PR!:SSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11448) COORD NUMBER METHOD REQUEST NOTES cs Ftt-84A C--2 CS3-153 VIS cs Ftt-84A E-2 CS33-153 VIS cs Ftt-84A H-4 CS34-153 VIS cs Ftt-84A S-3 CS3S-153 VIS cs Ftt-84A H-3 CS36-152 VIS cs Ftt-84A J-3 CS4-153 VIS cs Ftt-84A F-2 css-1s2 VIS cs Ftt-84A S-4 CS6-152 VIS cs Ftt-84A H-3 CS74-153 VIS
  • SURRY POWER STATION UNIT l
  • IflSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 188 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • tf 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 Cll4481 COORD NUNBER METHOD REQUEST NOTES cs Ftt-84A S-2 CS75-153 VIS cs FM-84A S-3 CS76-152 VIS cs FM-84A S-2 CS77-152 VIS cs Ftt-84A S-3 CSS-153 VIS FW Ftt-68A 0-3 WFPD13-601 VIS FW FM-68A 0-2 WFPD17-601 VIS FW FM-68A 0-5 WFPD9-601 VIS MS Ftt-64A C-4 SDHVl-601 VIS MS Ftt-64A C-5 SDHV~601 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 189 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES MS Ftt-64A C-6 SDHV3-601 VI~*

MS Ftt-64A C-4 SDHV4-601 VIS MS Ftt-64A D-4 SHPD6-601 VIS

  • MS Ftt-64A F-3. SHPD7-601 VIS HS Ftt-64A F-:-4 SHPDS-601 VIS MS Ftt-64A A-2 SHPl-601 VIS HS Ftt-64A A-:-5 SHP:?-601 VIS MS Ftt-64A S-3 SHP22-601 VIS MS Ftt-64A C-5 SHP23-601 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN SUHMARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 190 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES HS Ftr64A B-6 SHP24-601 VIS MS Ftr64A A-6 SHP3-601 VIS MS Ftr64A C-3 SHP3?-601 VIS MS Ftr64A B-4 SHPJS-601 VIS MS Ftr64A C-6 SHP39-601 VIS MS Ftr64A 0-2 SHP45-601 VIS MS Ftr64A 0-4 SHP46-601 VIS MS Ftr64A 0-6 SHP4?-601 VIS MS Ftr64A s-2 ssV1-121 VIS
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN SUN11ARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 191 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-H ALL PRESSURE RETAINING.COMPONENTS ITEM NUMBER  : C7.20

. ITEM DESCRIPTION : l':rPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER. METHOD REQUEST NOTES MS Ftt-64A C-4 SSVl0-121 VIS 11S Ftt-64A S-6 ssvu-121 VIS MS Ftt-64A S-6 SSV12-121 VIS 115 Ftt-64A C-6 ssvn-121 VIS MS Ftt-64A C-6 ssv14-121 VIS 115 Ftt-64A C--6 ssvis-121 VIS MS Ftt-64A 9-2 SSV2-121 VIS 115 Ftt-64A C--2 SSVJ-121 VIS MS Ftt-64A C-2 ssv4-121 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 192 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES l1S Flt-64.A C--2 ssvs-121 VIS l1S Flt-64.A e-4 SSV6-121 VIS l1S Flt-64A S-4 SSV?-121 VIS MS Flt-64.A C--4 SSVS-121 VIS MS Flt-64A C--4 SSV9-121 VIS RHR Flt-87.A 0-3 RHl0-602 VIS RHR Flt-87A S-6 RHll-602 VIS RHR Flt-87.A e-s RH12-602 VIS RHR Flt-87A r-4 RH13-602 VIS
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 193 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 E.XAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST HOTES RHR Ftt-87A I-s RH14-602 VIS RHR Ftt-87A 0-7 RHlS-602 VIS RHR Ftt-87A E-4 RH19-602 VIS RHR Ftt-87A E-7 RH2:-602 VIS RHR Ftt-87A C-5 RH21-602 VIS RHR Ftt-87A 1-s RH22:-602 VIS RHR Ftt-87A J-5 RH23-602 VIS RHR Ftt-87A C-7 RH24-602 VIS RHR Ftt-87A C-7 RH25-602 VIS
                                                                            • MMMMMMM*******************************************************
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN SUMNARY ********************

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 194 *
  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • DATE 86/10/20
  • CATEGORY C--H ALL PRESSURE RETAINING COMPONENTS
                                • MMMMMMMMMMMMMMMMMMMMMM***********************MMMMMMMMMMMMMMMMMMM*************MMMMMMM ITEM NUMBER C7.20 ITEM DESCRIPTION .. PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES RHR Ftt-87.A G-3 RHJ-602 VIS RHR Ftt-87.A B-6 RH4-602 VIS RHR Ftt-87.A 0-6 RHS-602 VIS RHR Ftt-87A S-7 RHSl-602 VIS RHR Ftt-87A 0-7 RHS2-602 VIS RHR Ftt-87.A A-S RH6-602 VIS RHR Ftt-87.A C---4 RH7-602 VIS RHR Ftt-87.A ,A-3 RHS-602 VIS RHR Ftt-87.A S-3 RH9-602 VIS
  • VIRGINIA ELECTRIC ";&.NO POWER COMPANY *
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 195 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER  : p.20 ITEM DESCRIPTION  : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEl1/ DIAGRAM DIAGRAM LINE EXAM REl:,IEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

RS Ftt-848 J-4 RSl-153 VIS RS Ftt-84B C-3 RSl0--153 VIS RS Ftt-84B H-2 RSU-153 VIS RS Ftt-848 F-2 RS12-153 VIS RS FM-c-84B C-4 RS13-153 VIS RS Ftt-84B 0-6 RS14-153 VIS

.RS Ftt-84B A-6 RSlS-153 VIS RS Ftt-848 H-4 RS2-153 VIS RS Ftt-84B J-1 RS20--153 VIS

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 196
  • 0003.
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES

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

RS Ftt-848 J-1 RS21-153 VIS RS Ftt-848 G-1 RS22-153 VIS RS Ftt-84B G-1 RS23-153 VIS RS Ftt-848 K-2 RS3-153 VIS RS Ftt-848 I-2 RS4-153 VIS RS Ftt-84B E-7 RSr-153 VIS RS Ftt-848 E-:-8 RS8-153 VIS RS Ftt-848 0-4 RS9-153 VIS SI Ftt-89A E-8 Cll53 VIS

VIRGINIA ELECTRIC AND ~ER COMPANY SURRY INSERVICE POWER STATION Ut:lIT 1 INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 197 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                              • lH!***************************************************************************
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES

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

SI Ftt--89A A-8 sn-153 VIS SI Ftt--89A F-4 . 5!102-152 VIS SI Ftt--89A G-8 5!106-153 VIS SI Ftt--89A f-8 Sil0?-153 VIS SI Ftt--89A G-8 SilOS-153 VIS SI Ftt--89A G-5 5!13-153 VIS SI Ftt--89A I-6 5!130-152 VIS SI Ftt-89A .J-4 5!131-152 VIS SI Ftt-89A S-7 5!132-153 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 198
  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • DATE 86/10/20
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS
                    • lf llll llll ll llllllllllll******************************************************************************

ITEM NUMBER  : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES SI FH-89A C-8 SI133-ICN9 VIS SI FH-89A E-7 SI134-ICN9 VIS SI .Ftt-89A 0-8 SI135-ICN9 VIS SI Ftt-89A E-7 SI136-ICN9 VIS SI Ftt-89A F-7 SI137-153 VIS SI FH-89A E-a SI138-ICN9 VIS SI Ftt-89A lf-7 SI139-ICN9 VIS SI Ftt-89A S-8 SI140-ICN9 VIS SI FH-89A lf-7 SI141-ICN9 VIS

  • SURRY POWER STATION UNIT l *
    • INSERVICE INSPECTION PLAN SUHMARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92.
  • PASE 199 ~
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER  : C7.20 ITEM DESCRIPTION: PIPING PRESSURE RETAINING BOUNDARY-SYSTE'.M LEAKAGE FLOW FLOW SYSTEH/ DIAGRAM DIAGRAM LINE EXAM RELIEF
  • PROGRAM COMPONENT (11448)
  • COORD NUMBER METHOD REQUEST NOTES SI Ftt-89A F-S SI148-153 VIS SI Ftt-89A f-S SI149-153 VIS SI Ftt-89A . D-5 snso-1s3 VIS SI Ftt-89A D-6 SilSl-153 VIS SI Ftt-89A 5-4 SI152-1502 VIS SI Ftt'-89A C-6 sn&-1s3 VIS SI Ftt-89A E-6 SI160-153 VIS SI Ftt-89A D-6 Sil'?-152 VIS SI Ftt-89A E-6 SilS-152 VIS
  • SURRY POWER STATION UNIT l
  • INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 200
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                              • lflflflflflflflflflf***************************************************************************
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS
                                                    • lflflflflflf**************************lflflflflflflflflflflflflflHflf*************lflflflflflflflflf****

ITEM NUMBER  : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C 11448) COORD NUMBER METHOD REQUEST - NOTES SI FM-89A E-6 5!19-152 VIS SI FM-89A A-a s12-153 VIS SI FM-89A S-1 5!20-1503 VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PASE 201 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 ~
  • DATE 86/10/20
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS
  • ITEM NUMBER  : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SY~TEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER HE.THOD REQUEST NOTES SI Ftt-89A F-7 SI56-153 VIS SI Ftf-789A J-2 SI57-1503 VIS SI Ftt-89A H-1 SI59-1503 VIS SI Ftt-89A I-4 SI6-153 VIS SI Ftt-89A S-2 SI60-1503 VIS SI Ftt-89A C-1 SI6S-1503 VIS SI Ftt-89A A-3 SI72-1503 VIS SI Ftt-89A E-6 SI7S-153 VIS SI Ftt-89A S-7 SI83-152 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 202 *
  • REVISION 0003 *
  • DATE 86/10/20 *
                          • MMMMMMMMMMMMMMMMMM*********************************************************************
  • 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 C11448) COORD NUMBER METHOD REQUEST NOTES SI Ftr89A 0-7 SI84-152 VIS SI Ftr89A 1-1 SI8r1503 VIS SI Ftr89A B-2 SI90-1503 VIS SI Ftr89A C-6 SI92-153 VIS -

SI Ftr89A F-1 SI93-1503 VIS SI Ftr89B C-4 Sil00-602 VIS SI Ftt-898 E-4 SIIl-602 VIS SI Ftt-898 H-6 .Sil:?-602 VIS SI Ftr89B 1-3 SI143-1502 VIS

\

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT l

  • INSERVICE INSPECTION PLAN Sut111ARY INTERVAL 2, 12/22/82 TO 12/22/92 ASHE SECTION XI EDITION 80W80
  • PAGE
  • REVISION 203
  • 0003
  • 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 REl:.IEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES SI Ftt-898 B-1 SI144-1502 VIS SI Ftt-898 B-5 5!145-1502 VIS s;i: Ftt-898 1-1 5!146-1503 VIS SI Ftt-898 1-2 5!147-1503 VIS SI Ftt-898 B-2 5!153-1502 VIS SI Ftt-898 B-5 5!154-1502 VIS SI Ftt-898 B-3 5!155-1502 VIS SI Ftt-898 F-6 5!156-1502 VIS SI Ftt-898 B-2 5!157-1502 VIS
  • SURRY POWER STATION UNIT 1
  • INSERVICE INSPECTION PLAN SUl1MARY
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 204 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES

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

SI Ftt-898 0-8 Sil.58-1502 VIS SI Ftt-898 B-3 SI159-1502 VIS SI Ftt-898 H-8 513-153 VIS SI Ftt-896 C-6 5133-1502 VIS

' SI Ftt-898 S-7 SI34-1502 VIS SI Ftt-898 C-8 5135-1502 VIS SI Ftt-898 0-5 SI36-602 VIS SI Ftt-898 S-6 SI37-602 VIS SI Ftt-898 0-8 sn8-602 VIS

  • SURRY POWER STATION UNIT 1
  • i
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 205 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS
                                                                                                                                    • ~*********************************

ITEM NUNBER C7.20 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM *LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUNBER METHOD REQUEST NOTES SI Flt-898 B-5 SI45-1502 VIS SI Flt-898 F-6 SI46-1502 VIS SI Flt-89B B-8 SI47-1502 VIS SI Flt-898 B-2 SI48-1502 VIS SI Flt-898 B-2 SI49-1502 VIS SI Flt-89B B-3 SI50-1502 VIS SI Flt-898 0--7 SI61-602 VIS SI Flt-898 0--5 SI62-152 VIS SI Flt-898 C-5 SI63-602 VIS

~-

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASHE SECTION XI EDITION 80W80

  • PAGE
  • REVISION 207
  • 0003 *
  • DATE 86/10/20 *
  • CATEGORY C--H ALL PRESSURE RETAINING COMPONENTS ITEM HUMBER  : C7.20 ITEM DESCRIPTION: PI~ING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD HUMBER METHOD REQUEST NOTES J

SI Ftt--898 F-1 SI76-1503 VIS SI Ftt--898 F-2 SI77-1503 VIS SI Ftt--898 0-3 SI79-1502 VIS SI Ftt--898 0-2 SI80-1502 VIS SI Ftt--898 0-2 SI81-1so2 VIS SI Ftt--898 0-1 SISS-1502 VIS SI Ftt--898 S-5 SI97-602 VIS SI Ftt--898 0-7 SI99-602 VIS SI FM106C. C--3 SI170-153 VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 206 *
  • ASME SECTION XI EDITION 80W80 REVISION 0003 *
  • DATE 86/10/20 *
                                                                                                                                            • MMMMMMMMMM********************
  • CATEGORY'C-H ALL PRESSURE RETAINING COMPONENTS
                                      • MMMMMMM*****************************MMMMM****************************************

ITEM HUMBER C7.20 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES SI Ftf-898 S-6 SI64-152 VIS SI Ftf-898 S-6 SI65-602 VIS SI Ftf-898 0-8 SI66-152 VIS SI Ftf-898 C-8 SI6r602 VIS SI Ftf-898 I-1 SI70-1503 VIS SI Ftf-898 F-1 SHl-1503 VIS SI Ftf-898 F-2 SI73-1503 VIS SI Ftf-898 C-1 SI74-1502 VIS SI Ftf-898 0-2 SI75-1502 VIS

  • SURRY POWER STATION UNIT 1 *
  • CATEGORY C-H INSERVICE INSPECTION PLA~

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80 ALL PRESSURE RETAINING COMPONENTS

~

  • REVISION 0003
  • DATE 86/10/20 *
  • PAGE 208
  • ITEM NUMBER  : C7.20 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM
  • LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUNBER METHOD REQUEST NOTES

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

SI FM106C C-3 sn11-1s3 VIS SI FM106C A-3 SIS-153 VIS SI FM106C 0-3 51172-153 VIS ss FM-82B C-1 SS6-ICN9 VIS ss Ftt-82B C-1 SS7-ICN9 VIS

  • SURRY POWER STATION UNIT l *
    • IHSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 209 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                              • IHf***************************************************************************
  • 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 (11448) COORD NUMBER METHOO REQUEST NOTES

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

BO FM124A e-s WGCB-601 VIS BO FM124A A-2 WGCBl-601 VIS BO FM124A .4-4 WGCB2-601 VIS

  • BO CH CH FM124A Ftt-88A Ftt-88A A-5 C-1 E-2 MGCB3-601 cH2s-1s2 CH29-152 VIS VIS VIS CH Ftt-88A e-2 CH32-152 VIS CH Ftt-886 F-3 CHl00-152 VIS CH Ftt-886 A-6 CHll-1503 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 210 *.
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES CH FM-88B H-3 CH112-152 VIS CH FM-886 E-5 CHU3-1503 VIS CH FM-886 f-3 CH117-152 VIS CH Ftt-88B f-3 CHllS-152 VIS CH Ftt-886 r-2 CH119-152 VIS CH FM-88B A-6 CH12-1503 VIS CH Ftt-886 H-2 CH120-152 VIS CH FM-886 r-1 cH121-1s2 VIS CH FM-88B C-1 CH125-602 VIS

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 211 *
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES CH Flt-888 A-7 CH13-1503 VIS CH Flt-888 H-2. CH163-152 VIS CH Flt-888 I-3 CH16'rl52 VIS CH Flt-888 S--3 CH16S-152 VIS CH Flt-888 B-7 CH167-1503 VIS CH Flt-888 B-8 CH17-152 VIS CH Flt-888 F-7 CHlS-152 VIS CH Flt-88B 0-7 CH187-1503 VIS CH Flt-888 F-7 CHlSS-1503 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 212 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD. NUMBER METHOD REQUEST NOTES CH Ftt-888 S-7 CH189-1503 VIS CH Ftt-888 H-7 CH19-152 VIS CH Ftt-888 H-2 CH190-152 VIS CH FM-88B F-4 CH191-152 VIS CH FM-886 0-3 CH192-152 VIS CH FM-888 K-1 CH193-152 VIS CH FM-886 H-6 CH196-152 VIS CH FM-886 F-2 CH199-152 VIS CH Ftt-888 F-6 CH2-1503 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 213 *
    • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                  • IHHf************************************************************************
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS *
                                                                                                                              • ~********************************

ITEM HUMBER C7.21 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) cornm t-M1BER METHOD RE~UEST NOTES CH FM-888 0--6 CH20-1503 VIS

. CH FM-888 H-7 CH20l-152 VIS CH* FM-888 f-7 CH202-152 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 214 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-H ALL PRESSURE RETAINING CONPONEHTS ITEM HUMBER C7.21 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ .DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD HUMBER METHOD REQUEST NOTES CH Ftr88B H-8 CH20.9-l503 VIS CH Ftr88B J-4 CH211-152 VIS CH Ftr88B J-4 CH212-152 VIS
  • CH CH CH Ftt-888 Ftr88B Ftr88B H-6 0--8 E-s CH22-1503 CH224-1503 CH225-1503 VIS VIS VIS CH Ftr88B S--8 CH226--cl503 VIS CH Ftt-888 F-2 CH23-152 VIS CH Ftr88B S-4 CH231-1503 VIS
                          • MMMIIMMIIMIIMMMIHHHf***********************************************************************
  • SURRY POWER STATION UNIT 1
  • INSERVICE INSPECTION 'PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 215 *
  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES CH Ftt-888 F-1 CH234-152 VIS CH Ftt-888 F-2 CH236-152 VIS CH Ftt-888 H-2 CH237-152 VIS CH Ftt-888 S--3 CH238-152 VIS CH Ftt-888 E-2 CH239-152 VIS CH Ftt-888 H-2 CH24-152 VIS CH Ftt-888 A-6 J CH276-1503 VIS CH Ftt-888 H-6 CH3-1503 VIS CH Ftt-888 1-3 CH.SS-152 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT l INSERVICE INSPECTION PLAN SUMttARY INTERVAL 2, 12/22/82 TO 12/22/92 ASHE SECTION XI EDITION 80W80

  • PAGE
  • REVISION 216 0003
  • DATE 86/10/20 *
                          • 11111111111111111111*****************************************************************************
  • CATEGORY C-H ' All PRESSURE RETAINING COMPONENTS *
                      • 111111111111111111111111111111111111111111111111****************11111111111111111111*11111111111111111111****************************

. ITEM NUMBER C7.21 ITEM DESCRIPTION .. PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

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

CH Ftt-888 1-3 CH59-152 VIS CH Ftt-888 H-2 CH6rl52 VIS CH Ftt-888 0-5 CH69-1503 VIS CH Ftt-888 C-2 CHr602 VIS CH Ftt-888 E-6 CH70-1503 VIS CH Ftt-888 S---6 CH71-1503 VIS CH Ftt-88B E-1 CH72-152 VIS CH Ftt-88B lt-:3 CH73-152 VIS CH Ftt-888 S-6 CH74-1503 VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 217 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                                                                                                                                      • ~****************
  • CATEGORY C-H ALL PRESSURE RETAIN!NG COMPONENTS If ITEM NUHBER  : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAl1 DIAGRAM LINE EXAl1 RELIEF PROGRAM COMPONENT I 11448) cornm NUHBER METHOD REQUEST NOTES CH Ftt-888 S-6 CH76-1S03 VIS CH Ftt-888 e-7 'CH77-1S03 VIS CH Ftt-888 F-2 CH7S-1S2 VIS CH Ftt-888 0--6 CH80-1S03 VIS CH Ftt-888 0--6 CH8l-1S03 VIS CH Ftt-888 E-1 CH87-1S2 VIS CH Ftt-888 E-5 CH89-1503 VIS CH Ftt-88B S-6 CH90-1503 VIS CH Ftt-888 A-6 CH91-1503 VIS
  • VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 218
  • ASHE SECTION XI EDITION 80W80 REVISION 0003
  • DATE 86/10/20 *
  • CATEGORY C-H ALL PRESSURE RETAINING CQMPONENTS ITEM NUMBER  : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE  !

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) comm NUMBER METHOD REQUEST NOTES CH Fl'f-888 B-3 CH99-152 VIS CH Ftt-88C e-2 CHl-1502 VIS CH Ftt-88C e-s CH101-1so2 VIS CH Ftt-88C H-5 CH102-1502 VIS CH Ftt-88C 0--5 CH103-1502 VIS CH Ftt-88C S-6 CHl06-1502 VIS CH Ftt-88C -I~6 CH109-1502 VIS CH Ftt-88C H-5 CH122-152 VIS CH Ftt-88C 5-3 CH123-1502 VIS

                                                  • IHf*************************************************************************
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 219 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORP NUMBER METHOD REQUEST NOTES

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

CH Ftt-88C E-4 CH124-152 VIS CH Ftt-88C A-5 CH14-1502 VIS CH Ftt-88C f-2 CH1502 VIS

-Ftt-88C Ftt-88C E-5 S-4 0--5 CH16-1502 CH214-152 CH215-152 VIS VIS VIS CH Ftt-88C S-4 CH216-152 VIS CH Ftt-88C C-5 CH217-152 VIS CH Ftt-88C f-5 CH216-152 VIS

  • SURRY POWER STATION UNIT 1
  • INSERVICE INSPECTION PLAN Sut1MARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 220 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES CH J Ftt-88C 1-4 CH219-152 VIS CH Ftt-88C B-3 CH223-1502 VIS CH Ftt-88C H-2 CH232-602 VIS CH Ftt-88C I-3 *CH233-602 VIS
  • CH CH CH Ftt-88C Ftt-88C Ftt-88C E-3 E-2 I-2 CH240-1502 CHS-1502 CH6-602 VIS VIS VIS CH Ftt-88C E-2 CH6S-1502 VIS CH Ftt-88C S-3 CH79-1503 VIS
  • SURRY POWER ST ATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 221 *
  • ASME SECTION XI EDITION 80W80 '
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOO REQUEST NOTES CH Fl"t"-88C B-3 CH8-1503 VIS CH Fl"t"-88C F-2 CH82-1502 VIS CH Fl"t"-88C S--3 CH83-1502 VIS CH Fl"t"-88C H-,2 CH85-602 VIS CH FM-88C H-2 CH86-602 VIS CH FM-88C H-7 CH92-1503 VIS CH FM-88C E-7 CH94-1503 VIS CH Ftt-'88C B-7 CH96-1503 VIS CH FM-88C B-5 CH9S-1502 VIS
  • If VIRGINIA ELECTRIC ANO POWER COMPANY SURRY POWER STATION UNIT l INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80 If

            • lflfMlflfMlf*******
  • PAGE
  • REVISION 222
  • 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS
                                                          • If**********************************************************************

ITEM NUMBER  : C7.21 ITEM DESCRIPTION : PIPING .PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C 11448) COO!m NUMBER METHOD REQUEST NOTES

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

cs Ft1-84A F-s cs1-1s3 VIS cs Ft1-84A C-3 cs14-153 VIS cs Ft1-84A A-2 CS19-152 VIS cs Ft1-84A F-S CS2-153 VIS cs Ft1-84A J-2 CS22-153 VIS cs Ft1-84A J-2 cs23-1s3 VIS cs Fl't-84.A K-2 CS26-153 VIS cs Fl't-84.A J-3 CS2S--153 VIS cs Fl't-84.A J-3 CS29-153 VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN Sutff1ARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE . 223 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES cs Ftt-84A C-2 cs3-153 VIS cs Ftt-84A E-2 CS33-153 VIS cs Ftt-84A H-4 CS34-153 VIS cs Ftt-84A S-3 CS3S-153 VIS

' I cs Ftt-84A tf-3 CS36-152 VIS cs Ftt-84A J-3 csr+-1s3 VIS cs Ftt-84A F-2 css-1s2 VIS cs Ftt-84A S-4 CS6-152 V.IS cs Ftt-84A tf-3 C574-153 VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN SUNMARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 224 *
  • ASME SECTION XI EDITION 80W80 -* REVISION 0003 *
  • 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 SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUNBER METHOD REQUEST NOTES cs Ftt-84A S-2 cs1s-1s3 VIS cs Ftt-84A S-3 CS76-152 VIS cs Fi't-84A S-2 CS77-152 VIS
  • cs Ftt-84A S-3 CSS-153 VIS FW Ftt-68A 0-3 WFP013-601 VIS FW Ftt-68A 0-2 MFPD17-601 VIS FW Ftt-68A 0-5 WFPD9-601 VIS MS Ftt-64A C-4 SDHVl-601 VIS MS Ftt-64A C-5 SDHV2-601 VIS
  • SURRY POWER STATION UNIT l
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 225 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY~ 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 (11448) COORD NUMBER METHOD REQUEST NOTES

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

MS Ftt-64A C-6 SDHV3-601 VIS MS Ftt-64A C-4 SDHV4-601 VIS MS Ftt-64A 0-4 SHP06-601 VIS MS Ftt-64A f-3 SHP0r60l VIS MS Ftt-64.A f-4 SHPDS-601 VIS MS Ftt-64.A A-'-2 SHPl-601 VIS MS Ftt-64.A A-S SHP2-601 VIS MS Ftt-64.A B-3 SHP22-601 VIS MS Ftt-64.A C-5 SHP23-60l VIS

  • -SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 226 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY ~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 111448) COORD - NI..INBER METHOD REQUEST NOTES MS Ftt-64A B-6 SHP24-601 VIS MS Ftt-64A A-6 SHP3-601 VIS MS Ftt-6_4A ~3 SHP37-601 VIS MS Ftt-64A B-4 SHP3S-601 VIS MS Ftt-64A ~6 SHP39-601 VIS MS Ftt-64A 0-2 SHP4S-601 VIS MS Ftt-64A 0-4 SHP46-601 VIS MS Ftt-64A 0-6 SHP47-601 VIS MS Ftt-64A B-2 ssvi-121 VIS
  • VIRGINIA ELECTRIC AHO POWER COMPANY If SURRY POWER STATION UNIT 1
  • If *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92 PAGE 227 ASME SECTION XI EDITION 80W80 REVISION 0003
  • 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 ( 11448) COORD NUMBER METHOD REQUEST NOTES MS Ftf-64A C-4 SSVl0-121 VIS MS Ftf-64A B-6 ssvn-121 VIS MS Ftf-64A B-6 SSV12-121 VIS MS Ftf-64A C-6 ssvn-121 VIS MS Ftf-64A C-6 ssv14-121 VIS MS Ftf-64A C-6 ssvis-121 VIS MS Ftf-64A B-2 SSV2-121 VIS MS Ftf-64A C-2 SSVJ-121 VIS MS Ftf-64A C-2 SSV4-121 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN SUNMARY INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 228 *
  • REVISION 0003 *
  • DATE 86/10/20 - *
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS
                                                                                                                                                                                                    • ~*

ITEH NUMBER  : C7.21 ITEH DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

HS FH-:64A C-2 ssvs-121 VIS HS Ftt-64A B-4 SSV6-I21 VIS HS Ftt-64A B-4 SSV7-121 VIS HS Ftt-64A C-4 SSVS-121 VIS HS Ftt-64A C-4 SSV9-121 VIS RHR Ftt-87A 0---3 RHl0-602 VIS RHR Ftt-87A S-6 RHll-602 VIS RHR Ftt-87A E-s RH12-602 VIS RHR Ftt-87A 1-4 RH13-602 VIS

  • SURRY POWER STATION UNIT l *
  • INSER.VICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 229 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS
  • ITEM NUMBER  : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUt,EARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COHPONE~ (11448) COORD NUMBER METHOD REQUEST NOTES RHR Ftt-87A 1-5 RH14-602 VIS RHR Ftt-87A 0-7 RHlS-602 VIS RHR Ftt-87A E-4 RH19-602 VIS
  • RHR Ftt-87A E-7 RHZ-602 VIS RHR Ftt-87A C-5 RH2l-602 VIS RHR Ftt-87A I-s RH22-602 VIS RHR Ftt-87A J-5 RH23-602 VIS RHR .Ftt-87A C-7 RH24-602 VIS RHR Ftt-87A C-7 RH25-602 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 230
  • 0003
  • DATE 86/10/20 *
  • CATEGORY c-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER  : C7.21 ITEM DESCRIPTION : P!PING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE l;XAM RELIEF PROGRAM COMPONENT ( 11448) COORD NUMBER METHOD REQUEST NOTES RHR Ftt-87A S--3 RH3-602 VIS RHR Ftt-87A B-6. RH4-602 VIS RHR Ftt-87A 0-6 RHS-602 VIS RHR Ftt-87A B-7 RHSl-602 VIS RHR Ftt-87A 0-7 RH52-602 VIS RHR Ftt-87A A-5 RH6-602 VIS RHR Ftt-87A C-4 RHJ-602 VIS

.RHR Ftt-87A A-3 RHS-602 VIS RHR Ftt-87A B-3 RH9-602 VIS

  • SURRY POWER STATION UNIT 1 *
  • IHSERVICE INSPECTION PLAN SIJl1t1ARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 231 **
  • ASME *sECTION XI EDITION 80W80
  • REVISION 0003 **
  • 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/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONEt-n° (11448) COORD NUMBER METHOD .REQUEST NOTES

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

RS Ftt-84B J-4 RSl-153 VIS RS Ftt-848 C-3 RSl0--153 VIS RS Ftt-848 H-2 RSll-153 VIS

  • RS Ftt-848 F-2 RS12-153 VIS RS Ftt-848 C-4 RS13-153 VIS RS Ftt-848 0--6 RS14-153 , VIS RS Ftt-848 A-6 RSlS-153 VIS RS Ftt-848 H-4 RSZ--153 VIS RS Ftt-84B J-1 RS20--153 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 232 *
  • ASHE SECTION XI EDITION 80W80 REVISION 0003 *
  • 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 ( 11448) COORD NUMBER METHOD REQUEST NOTES RS Flt-846 J-1 RS21-153 VIS RS Flt-846 S---1 RS22-153 VIS RS Flt-846 S---1 RS23-153 VIS RS Flt-846 K-2 RS3-153 VIS RS Flt-846 1-2 RS4-153 VIS RS Flt-846 E-7 RS?-153 VIS RS Flt-846 E-a RSS-153 VIS RS Flt-846 0-4 RS9-153 VIS SI Flt-89A E-a CL153 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 233
  • 0003
  • 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 (11448) COORD HUMBER METHOD REQUEST NOTES SI Flt-89A A-8 sn-1s3 VIS SI Flt-89A f-4 SilOZ-152 VIS SI FM-89A S-8 SI106-l53 VIS SI Flt-89A F~a Sil0"?-153 VIS SI Flt-89A S-8 SilOS-153 VIS SI Flt-89A S-5 SI13-153 VIS SI Flt-89A I-6 SI130-152 VIS r,

SI Flt-89A J-4 SI131-152 VIS SI Flt-89A B-7 SI132-153 VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 234 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                                      • IHHHf*************************************************************
  • 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 (11448) COORD NUMBER . METHOD REQUEST NOTES SI FM-89A C-8 SI133-ICN9 VIS SI FM-89A E-7 SI134-ICN9 VIS SI FM-89A 0--8 SI135-ICN9 VIS SI FM-89A E-7 SI136-ICN9 VIS SI FM-89A F-7 SI137-153 VIS SI FM-89A E-8 SI138-ICN9 VIS SI FM-89A H-7 SI139-ICN9 VIS SI FM-89A S--8 SI140--ICN9 VIS SI FM-89A H-7 SI141-IC.N9 VIS

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 235 *
    • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES SI Ftt-89A f-5 *SI14S-153 VIS SI Ftt-89A f-5 SI149-153 VIS
  • SI Ftt-89A 0--5 SI150-153 VIS SI Ftt-89A 0--6 Sil.Sl-153 VIS SI Ftt-89A B-4 SI152-1502 VIS SI Ftt-89A C-6 SI16-153 VIS SI Ftt-89A E-6 SI160-153 VIS SI Ftt-89A 0--6 SI1r152 VIS SI Ftt-89A E-6 SilS-152 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 IHSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

          • ~*************
  • PAGE
  • REVISION 0003 236
  • DATE 86/10/20 *
                            • i!MKKKKKKKKMIHHf**it******************************MMMMMMMKMM*****************************
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS
                            • MMMMKKMMKMit****it*KKit******************************MKMMMMM*****************************

ITEM NUMBER C7.21 ITEM DESCRIPTION PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES SI Ftf-89A E-6 5!19-152 VIS SI Ftf-89A A-a SI2-153 VIS SI Ftt-89A G-1 SI20-1503 VIS SI Ftt-89A G-7 SI23-152 VIS SI Ftf-89A G-6 SI24-153 VIS SI Ftf-89A E-7 SI25-152 VIS SI Ftt-89A f-5 SI30-152 VIS SI Ftt-89A I-3 sis-153 VIS SI Ftf-89A E-6 SI55-153 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

                          • ~******
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE . 237 *
  • ASME SECTION XI EDITION. 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER  : C7.21 ITEM DESCRIPTION : PIPING PRES~E RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM.

COMPONENT (11448) COORD NUMBER METHOO REQUEST NOTES SI Ftt-89A F-7 SI56-153 VIS SI Ftt-89A J-2 SI57-1503 VIS SI Ftt-89A H-1 SIS9-1503 VIS SI Ftt-89A I-4 SI6-153 VIS SI Ftt-89A S-2 SI60-1503 VIS SI Ftt-89A C-1 SI6S-1503 VIS SI Ftt-89A A-3 SI72-1503 VIS SI Ftt-89A E-6 SI7S:-153 VIS SI Ftt-89A S-7 SI83-152 VIS

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASHE SECTION XI EDITION 80W80

                        • ~****
  • PAGE
  • REVISION
  • 2.38
  • 0003 *
  • DATE 86/10/20 *
                                                                • If*******************************************************************
  • 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 C11448) COORD NUMBER METHOD REQUEST NOTES SI Ftt-89A 0-7 SI84-152 VIS SI Ftt-89A 1-1 SI87-"1503 VIS SI Ftt-89A B-2 SI90-1503 VIS SI Ftt-89A C-6 SI92-153 VIS SI Ftt-89A- f-1 SI93-1503 VIS s:t Ftt-898 C-4 Sil00-602 VIS SI Ftt-898 E-4 Sill-602 VIS SI Ftt-898 H-6 SI12-602 VIS SI Ftt-898 1-3 SI143-1502 VIS

if VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN SUMNARY INTERVAL 2, 12/22/82 TO 12/22/92 ASHE SECTION XI EDITION 80W80

  • PAGE
  • REVISION 239 **

0003 *

  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES SI Ftt-898 e-1 SI144-1502 VIS SI Ftt-898 e-5 SI145-1502 VIS SI Ftt-898 1-1 5!146-1503 VIS SI Ftt-898 1-2 5!147-1503 VIS SI Ftt-898 e-2 5!153-1502 VIS SI Ftt-898 B-5 5!154-1502 VIS SI Ftt-898 e-3 sn55-1502 VIS SI Ftt-898 . F-6 5!156-1502 VIS SI Ftt-898 e-2 SI157-1502 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 240 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS ITEM NUMBER  : C7.21 ITEM DESCRIPTION  : PIPING PRESS~E RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM RElIEF PROGRAM COMPONENT (11448) comm NUMBER METHOD RE~EST NOTES SI Ftt-898 0-8 SilSS-1502 VIS SI Ftt-898 S-3 SI159-1502 VIS SI Ftt-898 H-8 SIJ-153 VIS SI Ftt-898 C-6 SIJJ-1502 VIS SI Ftt-898 S-7 SI34-1502 VIS SI Ftt-898 C-8 sns-1so2 VIS SI Ftt-898 0-5 SI36-602 VIS SI Fl't-898 S-6 SI37-602 VIS SI Ftt-898 0-8 SI3S-602 VIS
  • SURRY POWER STATION UNIT l
  • INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 241 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 ( 11448) COORD NUMBER METHOD REQUEST NOTES SI Fl"t-898 S-5 SI45-1502 VIS SI Fl"t-898 F-6 SI46-1502 VIS SI Fl"t-898 S-8 SI47-1502 VIS SI Fl"t-898 B-2 SI48-1502 VIS SI Fl"t-898 e-2 SI49-1502 VIS SI Ftt-898 S-3 SIS0-1502 VIS SI Fl"t-898 0-7 SI61-602 VIS SI Fl"t-89B 0-5 SI62'-152 VIS SI Fl"t-898 C-5 SI63-602 VIS
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 242 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD HUMBER METHOD REQUEST NOTES SI Ftt-898 S-6 SI64-152 VIS SI Ftt-898 S-6 SI65-602 VIS SI Ftt-898 0---8 SI66-152 VIS SI Ftt-898 C-8 SI6r602 VIS SI Ftt-898 1-1 SI70-1503 VIS SI Ftt-898 F-1 SI7l-1503 VIS SI Frt-898 F-2 SI73-1503 VIS SI Ftt-898 C-1 SI74-l502 VIS SI Flt-898 0---2 5175-1502 VIS

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 243 *
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C--H ALL PRESSURE RETAINING COMPONENTS *
                                                              • If********************************************************************

ITEM NUMBER  : C7.21 ITEM DESCRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES SI Fl"t-898 F-1 SI76-1503 VIS SI Fl"t-898 F-2 SI77-l503 VIS SI Fl"t-898 0-3 SI79-1502 VIS SI Fl"t-898 0-2 SI80-1502 VIS SI Fl"t-898 0-2 SI81-1502 VIS SI Fl"t-898 0-1 SI85-1502 VIS SI Fl"t-898 S-5 SI97-602 VIS SI Fl"t-898 0-7 5!99-602 VIS SI FM106C C--3 SI170-153 VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION .PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 244 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY c-H ALL PRESS~E RETAINING COMPONENTS ITEM NUMBER  : C7.21 ITEM DEStRIPTION : PIPING PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT <11448) COORD NIJNBER METHOD REQUEST NOTES SI FM106C C--3 5!171-153 VIS SI Fl1106C A-3 SI5-153 VIS SI Fl1106C 0-3 51172-153 VIS
  • ss ss Ftt-82B Ftt-82B C--1 C--1 SS6-ICN9 5SrICN9 VIS VIS
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECT~ON PLAN

SUMMARY

            • ~***********
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 245 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • -
  • DATE 86/10/20 *
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS *
                            • KMKKKKKK******************************************************************************

ITEM NUMBER  : C7.30 ITEM DESCRIPTION : PUMPS PRESSURE RETAINING BOUNDARY-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM

  • LINE EXAM RELIEF PROGRAM COMPONENT (114481 COORD NUMBER METHOD REQUEST NOTES CH Ftt-88B 0--7 lCHPlA VIS CH Ftt-888 E-7 1CHP1B VIS CH Ftt-888 G-7 lCHPlC VIS RC Ftt-86A A-1 lRCPlA VIS RC Ftt-86A A-6 1RCP1B VIS RC Ftt-86A L-1 lRCPlC VIS RHR Ftt-87A C-6 lRHPlA VIS RHR Ftt-87A 0--6 1RHP1B VIS
  • 'SURRY POWER STATION UNIT l *

"* INSERVICE INSPECTION PLAN.

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 246 *
  • ASME SECTION XI EDITION*80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS
  • ITEM NUMBER  : C7.31 ITEM DESCRIPTION : P\J1PS PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES CH Ftt-888 0--7 lCHPlA VIS CH Ftt-888 E-7 lCHPlB VIS CH Ftt-888 S-7 lCHPlC VIS RC Ftt-86A A-1 lRCPlA VIS RC Ftt-86A A-6 lRCPlB VIS RC Ftt-86A L-1 lRCPlC VIS RHR Ftt-87A C-6 lRHPlA VIS RHR Ftt-87A 0--6 1RHP1B VIS

('

                                                                                                                                        • ii*******************************

VIRGINIA ELECTRIC AND POWER COMPANY *

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 247 *
  • ASME SECTION XI EDITION aowao
  • REVISION 0003 *
  • DATE 86/10/20 *
                          • ii***********~**********************************************************************
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES FW Ftt-68A 0-3 MFPD13-601 VIS FW Ftt-68A 0-2 WFPDlr601 VIS FW Ftt-68A 0-5 MFPD9-601 VIS

  • MS MS '

t1S

  • Ftt-64A Ftt-64A Ftt-64A A-2 A-S e-3 SHPl-:-601 SHP2-601 SHP22-601 VIS VIS VIS t1S Ftt-64A C-5 SHP23-601 VIS MS Ftt-64A B-6 SHP24-601 VIS

\

MS Ftt-64A A-6 SHP3-:-601 VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 248 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER 11ETHOO REQUEST NOTES MS FM-64A D-2 SHP4S-601 VIS MS Ftt-64A D-4 SHP46-601 VIS MS FM-64A D-6 SHP47-601 VIS
  • RHR RHR RHR FM-87A Ftt-87A Ftt-87A D-3 E-S I-s RHl'0-602 RHlZ-602 RH14-602 VIS VIS VIS RHR Ftt-87A D-7 RH18-602 VIS RHR Ftt-87A E-4 RH19-602 VIS RHR FM-87A E-7 RH2-602 VIS
  • SURRY POWER STATION UNIT l
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92 *- PAGE 249 *
  • ASHE SECTION XI EDITION 80W80 REVISION 0003 *
  • DATE 86/10/20 *
                                        • lfifif*****************************************************************************
  • 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 I 11448) COORD NI.Jtl'BER METHOD REQUEST NOTES RHR Ftt-87A B-6 RH4~602 VIS RHR Ftt-87A 0-6 RHS-602 VIS RHR Ftt-87A C-4 RH7-602 VIS RHR Ftt-87A A-3 RHS-602 VIS RHR Ftt-87A B-3 RH9-602 VIS SI Ftt-89A 0-4 sns2-1so2 VIS SI Ftt-896 0-2 SI48-1502 VIS SI Ftt-896 B-2 SI49-1502 VIS

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 250 *
  • REVISION 0003 *
  • DATE 86/10/20 *
                      • il************IHHHHt***********************************************************************
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS *'
                                                                                                                    • lflf*lflflHHHHt********************************

ITEM NUMBER  : C7.41 ITEM DESCRIPTION : VALVES PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

FW Ftt-68A 0-3 WFPD13-601 VIS FW Ftt-68A 0-2 WFPDlr601 VIS FW Ftt-68A 0-5 WFPD9-601 VIS MS Ftt-64A A.,..2 SHPl-601 VIS MS Ftt-64A A-5 SHP2-601 VIS MS Ftt-64A B-3 SHP22-601 VIS MS Ftt-64A C-5 SHP23-601 VIS MS Ftt-64A B-6 SHP24-601 VIS MS Ftt-64A A-6 SHP3-601 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVI.CE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE
  • 251 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY c-tf ALL PRESSURE RETAINING COMPONENTS *
                            • ii*************************************************************************************

ITEM NUMBER  : C7.41 ITEM DESCRIPTION: VALVES PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

MS Ftt-64A 0--2 SHP4S-601 VIS 115 Ftt-64A 0--4 SHP46-601 VIS MS Ftt-64A o-6 SHP47-601 VIS RHR Ftt-87A 0--3 RHl0-602 VIS RHR Ftt-87A E-5 RH12-602 VIS RHR Ftt-87A I-s RH14-602 VIS RHR Ftt-87A 0--7 RHlS-602. VIS RHR Ftt-87A E-4 RH19-602 VIS RHR Ftt-87A E-7 RH?.-602 VIS

!fr VIRGINIA ELECTRIC AND POWER COMPANY

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 252 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY C-H ALL PRESSURE RETAINING COMPONENTS
                                                                                                                          • >HHt************************************

ITEM NUMBER  : C7.41 ITEM DESCRIPTION : VALVES PRESSURE RETAINING BOUNDARY-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM

SI FM-89A S-4 SI152-1502 VIS SI FM-898 e-2 SI48-1so2 VIS SI ftt-898 S-2 SI49-1502 VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 253 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NU11BER Dl.lOH ITEM DESCRIPTION COMPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES cc Flt-71B 0-7 CC33S-151 VIS cc Flt-71B G-6 CC336-151 VIS cc Flt-71B F-7 CC337-151 VIS cc Flt-71B F-6 CC33S-151 VIS cc Flt-71B S-6 CC339-151 VIS cc Flt-71B D-5 CC340-151 VIS cc Flt-71B G-5 CC341-151 VIS cc Flt-71B E-s CC342'-151 VIS cc Flt-71B 0-4 CC343-151 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 254 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY 0---A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION *
                                              • ~****************************************************************************

ITEM NUMBER  : Dl.lOH ITEM DESCRIPTION : COl1PONENTS IN.SUPPORT OF RX SHUTDOWN-HYDROSTATIC

  • FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

cc FM-71B 1-4 CC344-151 VIS cc FM-71B S-4 CC345-151 VIS cc FM-71B H-4 CC346-151 VIS

    • cc cc cc FM-71B FM-71B FM-71B E-4 S--4 S-4 CC347-151 CCY+S-151 CC349-151 VIS VIS VIS cc FM-71B H-6 CC350-151 VIS cc FM-71B E-6 CC351-151 VIS cc FM-72A A-3 CCl00-151 VIS
  • SURRY *POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 PAGE 255

  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • DATE 86/10/20 *
                                            • il*****************************************************************************
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES cc FH-72A E-6 cc101-151 VIS cc FH-72A 0-3 cc102-1s1 VIS cc FH-72A 0-3 CCl03-151 VIS cc FH-72A 0-4 cc104-1s1 VIS cc FH-72A E-7 CClOS-151 VIS cc FH-72A F-4 CC10rl51 VIS cc FH-72A F-5 CClOS-151 VIS cc FH-72A E-6 CC109-151 VIS cc FH-72A lt-7 CCll0-151 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 256 *
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST -NOTES cc Ftt-72.A H-4 CCllZ-151 VIS cc Ftt-72.A H-5
  • cc1u-1s1 VIS cc Ftt-72.A H-6 CC114-151 VIS cc Ftt-72.A L-3 CC16-121 VIS cc Ftt-72.A J-4 CC1rl21 VIS cc Ftt-72.A A-2 ~C200-151 VIS cc Ftt-72.A D-2 cc201-1s1 VIS cc Ftt-72A A-4 CC20Z-151 VIS cc *Ftt-72A 0-4 cc203-1s1 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 257 *
  • AS.ME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES cc Ftt-72A A-6 cc204-1s1 VIS cc Ftt-72A 0-6 cc2os-1s1 VIS cc Ftt-72A E-2 CC206-151 VIS cc Ftt-72A tf-5 . CC207-151 VIS c~ Ftt-72A E-2 CC246-151 VIS cc Ftt-72A tf-8 CC247-151 VIS cc Ftt-72A F-6 CCJOS-151 VIS cc Ftf-72A tf-6 CC306-151 VIS cc Ftt-72A F-7 CC307-151 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE
  • 258 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 I

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (114481 COORD NUMBER METHOD REQUEST NOTES

=

cc Ftt-72A S---7 cc308-1s1 VIS cc Ftt-72A F-1 ccs-121 VIS cc Ftt-72A A-6 CC82-151 VIS cc Ftt-72A A-7 CCSJ-151 VIS cc Ftt-72A A-7 ccs4-1s1 VIS cc Ftt-72A* 0--7 ccss-1s1 VIS cc Ftt-72A 0--7 CC86-151 VIS cc Ftl-72A C--7 CC87-151 VIS cc Ftt-72A E..:.7 ccss-1s1 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 259 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM-NUMBER ITEM DESCRIPTION Dl.lOH COMPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC I

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES cc Flt-72.A A-5 CC89-151 VIS cc Flt-72.A A-4 CC90-151 VIS cc Fl"t-72.A A-S CC91-151 VIS

  • cc cc cc Flt-72.A Flt-72.A Flt-72.A A-5 0-6 0-5 CC92-151 CC93-151 CC94-151 VIS VIS VIS

. cc Flt-72.A C-5 cc9s-1s1 VIS cc Flt-72.A 0-6 CC96-151 VIS cc Flt-72A A-3 CC97-151 VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 260 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                          • IHf*********************************************************************
  • "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/ DIAGRAl1 DIAGRAl1 LINE EXAl1 RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES cc Ftt-72A A-2 CC9S--151 VIS cc Ftt-72A A-3 CC99-151 VIS cc Ftt-728 A-1 CCl0-121 VIS cc Ftt-728 A-1. cc11s-1s1 VIS cc Ftt-728 E-3 CC120-151 VIS cc Ftt-728 1-4 cc1s-1s1 VIS cc Ftt-728 F-3 CC76-151 VIS cc Ftt-728 E-4 CC7rl51 VIS cc Ftt-728 E-1 CC7S--l5l VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY INSERVICE POWER STATION UNIT 1 INSPECTION PLAN SUl1MARY INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 261 *
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES

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

cc Flt-72B F-4 CC79-151 VIS cc Flt-72B S----2 CCS0-151 VIS cc Flt-72B I-2 ccs1-1s1 VIS cc

  • Flt-72B I-1 CC89-121 VIS cc Flt-72C S----8 cc14-121 VIS cc Flt-72C J-2 cc143-121 VIS cc Flt-72C S----8 cc1s-121 VIS cc Flt-72C K-1 cc1s1-1s1 VIS cc Flt-72C S----3 CC153-151 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UHIT 1 INSERVICE INSPECTION PLAN SUNNARY INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 262
  • 0003
  • DATE 86/10/20 *
  • CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM HUNBER  : Dl.lOH ITEM DESCRIPTION: COMPOHEHTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM D.IAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11448) COORD HUNBER METHOD REQUEST NOTES cc Fl'r72C F-2 'CC154-151 VIS cc Fl'r72C E-3 cc1ss-1s1 VIS cc FM-72C S-1 CC161-121 VIS cc Fl'r72C H-2 CC169-121 VIS cc Fl'r72C H-2 CC17rl51 VIS cc Fl'r72C L-4 CC30l-151 VIS cc F_l'r72C K-4 CC302-151 VIS cc Fl'r72C L-4 CC303-151 VIS cc Fl'r72C L-5 CC304-151 VIS
  • C
  • SURRY POWER STATION UNIT 1
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 263* *
  • ASNE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 I

FLOW FLOW SYSTEl1/ DIAGRAM DIAGRAM LINE EXAM RElIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES cc Ftt-72C J-5 CC364-151 VIS cc Ftt-72C K-4 CC383-121 VIS cc Ftt-72C K-5 CC385-151 VIS cc Ftt-72C tf-3 CC473-151 VIS cc Ftt-72C J-5 CC474-151 VIS cc Ftt-72C I-7 CC61-151 . VIS cc Ftt-72C I-6 CC62-151 VIS cc Ftt-72C 1-3 CC65-121 VIS cc Ftt-72C J-6 CC66-151 VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN SU11MARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 264 **
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER  : Dl.lOH 1-ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

cc Ftt-72C H-4 CC6rl51 VIS cc Ftt-72C 1-3 CC69-151 VIS cc Ftt-72C .r7 CC70--121 VIS cc Ftt-72C .r3 CC7,0--151 VIS cc Ftt-72C .r4 cc11-1s1 VIS cc Ftt-72C K-2 CC72-121 VIS cc Ftt-72C 1-1 cc81-121 VIS cc Ftt-72D C-2 cc1-121 VIS cc Ftt-72D e-2 CC19-121 VIS

  • SURRY POWER STATION UNIT l *
  • IHSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 265 **
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY D-A SYSTEMS IH SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM HUMBER  : Dl.lOH ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD HUMBER METHOD REQUEST NOTES

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

cc Ftt-72D C-2 cc2-121 VIS cc. Ftt-72D A-2 CC20-151 VIS cc Ftt-72D A-3 cc21-1s1 VIS cc Ftt-72D A-2 CC22-151 VIS cc Ftt-72D D-2 CC220-121 Vis cc Ftt-72D A-3. CC222-151 VIS cc Ftt-72D D-3 cc224-121 VIS cc Ftt-72D F-2 cc22s-121 VIS cc Ftt-72D J-1 CC226-121 VIS

  • SURRY POWER STATION UNIT l *
  • It:ISERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 266 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 SHUTDOWtrHYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST. NOTES cc Ftt-72D 0-2 CC227-121 VIS cc Ftt-72D 0--2 CC22S-l2l VIS cc Ftt-72D 0--3 CC229-121 VIS cc Ftt-72D 0--1 CC230-l21 VIS cc Ftt-72D E-1 cc231-121 VIS cc Ftt-72D E-2 CC232-121 VIS cc Ftt-72D E-3 cc233-121 VIS cc Ftt-72D E-4 cc234-1s1 VIS cc Ftt-72D S--1 cc23s-121 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 267 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER  : Dl.lOH ITEM DESCRIPTION : COt1PONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC
  • I FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD . REQUEST NOTES cc Ftf-72D f-1 CC236-121 VIS cc Ftf-72D f-1 CC23rl21 VIS cc Ftf-72D L-2 CC2rl21 VIS cc Ftf-72D C--3 CC3-121 VIS cc Ftf-72D f-8 CC311+-151 VIS cc Ftf-72D 0-3 CC319-151 VIS cc Ftf-72D e-1 CC320--151 VIS cc Ftf-72D C--3
  • cc4-121 VIS cc Ftt-72D 0-2 ccs-121 VIS
  • SURRY POWER STATION UNIT 1 *
  • .INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 268 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 ( 11448) COORD NUMBER METHOD REQUEST NOTES cc Ftt-72D 0-3 CC6-121 VIS cc Ftt-72D L-1 CC7-121 VIS cc Frt-72D K-1 CC9-121 VIS
  • CH CH CH Ftt-88A Ftt-88A Ftt-88A 0-4 F-4 H-8 CH139-152 CH140--:152 CH14:i-152 VIS VIS VIS CH Ftt-88A F-6 CH142-152 VIS CH Ftt-88A G-7 CH143-152 VIS CH Ftt-l}SA F-6 CH144-152 VIS

VIRGINIA ELECTRIC AHO POWER COMPANY

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 269 *
  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • DATE 86/10/20 *
  • CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER  : Dl.lOH ITEM DESCRIPTION  : CCMPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

CH Ftt-88A 0-5 CH145-152 VIS CH Ftt-88A 0-5 CH146-152 VIS CH Ftt-88A f-5 CH147-152 VIS

  • CH CH CH Ftt-88A Ftt-88A Ftt-88A C-7 0-6 0-6 CH148-152 CH149-152 CH150-152 VIS VIS VIS CH Ftt-88A C-4 CH152-152 VIS CH Ftt-88A 0-4 CH153-152 VIS CH Ftt-88A S-4 CH154-152 VIS

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 270 *
  • REVISION 0003 *
  • DATE 86/10/20 * ,
  • CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION
                                        • !HE******************************************************************************

ITEM NUMBER Dl.lOH ITEM DESCRIPTION COMPONENTS IN SUPPORT OF RX SHUTDowtrHYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM REtIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES CH Ftt-88A H-7 CHlSS-152 VIS

-CH Ftt-88A E-7 CH156-'-l52 VIS CH Ftt-88A E~6 CHlSS-152 VIS CH Ftt-88A H-5 CH179-152 VIS CH Ftt-88A. E-S CH180-152 VIS CH Ftt-88A a-s CH181-152 VIS CH Ftt-88A A-6 CH229-152 VIS CH Ftt-88A J-7 CH230-152 VIS.

CH Ftt-88A E-7 CH241-152 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 271 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 F.LOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES CH Ftt-88A 0-5 CH24J-152 VIS CH Ftt-88A 0-4 CH245-152 VIS CH Ftt-88A F-4 CH246-152 VIS*

. CH Ftt-88A C-8 CH34-152 VIS CH Ftt-88A 1-1 CH342-152 VIS CH Ftt-88A C-8 CHJS-152 VIS CH Ftt-88A E-8 CHJ6-152 VIS CH Ftt-88A F-8 CH37-152 VIS CH Ftt-88A C-5 CHJa-152 VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN SUNMARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 272 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 PROSRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES CH FM-88A E-6 CH39-152 VIS CH FM-88A E-7 CH40-152 VIS CH Ftt-88A S----5 CH41-1s2 VIS CH FM-88A A-a CH42-152 VIS CH FM-88A B-6 CH43-152 VIS CH FM-88A E-8 CH52-152 VIS CH FM-88A F-8 CHSJ-152 VIS CH FM-88A F-7 CH61-152 VIS CH FM-88A 0-7 CH62-152 VIS

VIRGINIA ELECTRIC AND POWER COMPANY *

  • SURRY POWER STATION UNIT l
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 273
  • ASME SECTION XI EDITION 80W80 REVISION 0003 *
  • 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 I

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

CH Ftt-88A H-6 CH64-152 VIS CH Ftt-888 J-3 CH19S-152 VIS

.CH Ftt-888 K-4 CH56-152 \/IS CH Ftt-888 J-6 CH57-152 VIS CH Ftt-88B J-3 CHSS-152 VIS FW Ftt-68A F-8 WAP0-151 VIS FW Ftt-68A E-6 *WAPDl-601 VIS FW Ftt-68A C-6 WAPDl0-601 VIS FW Ftt-68A B-5 WAPDU-601 VIS

If If If VIRGINIA ELECTRIC AND POWER COMPANY

  • If SURRY POWER STATION UNIT 1
  • If If
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 274 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                                                                                                                              • lf*,lf*lf****************
  • CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION If ITEM NUMBER  : Dl.lOH ITEM DESCRIPTION : CONPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAl1 DIAGRAl1 LINE EXAM RELIEF PROGRAM COMPONENT {11448) COORD NUMBER METHOD REQUEST NOTES FW Ftt-68A B-6 WAPD12-601 VIS FM Ftt-68A B-6 WAPD13-601 VIS FW Ftt-68A B-6 WAPD14-601 \/IS FW Ftt-68A 0-7 WAPDlS-601 \/IS FW Ftt-68A K-2 WAPD152-601 VIS FW Ftt-68A 0-6 WAPD16-151 VIS FW Ftt-68A E-7 WAPD17-601 VIS FW Ftt-68A F-6 WAPDlS-151 VIS FW Ftt-68A F-6 WAPD19-151 J VIS
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN SIJMl1ARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 275 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                            • il**********IHHHf***********************************************************************
  • CATEGORY it-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 (114481 COORO NUMBER METHOD REQUEST NOTES FW Ftt-68A E-6 WAPD2-601 VIS FW Ftt-68A S-7 WAPD20-601 VIS FM Ftt-68A S-6 WAPD2l-151 VIS FW Ftt-68A [t-7 WAPD3-601 VIS FW Ftt-68A it-6 WAPD4-60l VIS FW Ftt-68A E-6 WAPDS-601 VIS FW Ftt-68A f-6 WAPD6-601 VIS FW Ftt-68A f-6 WAPD7-601 VIS FW Ftt-68A S-6 WAPDS-601 VIS
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 276 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                                                                                                                • iE***************************
  • CATEGORY.0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER Dl.lOH ITEM DESCRIPTION COMPONENTS IH SUPPORT OF RX SHUTDOWN-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM
  • coMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES FW Ftf-68A C--4 WAPD9-601 VIS FW Ftf-68A E-a WCMUl0-151 VIS FW Ftf-68A 0-8 WCMUll-151 VIS FM Ftf-68A S-8 WCMU151 VIS

. FM Ftf-68A lt-8 WCMU4-151 VIS FM Ftf-68A lt-8 WCMUS-151 VIS FM Ftt-68A E-a WCMU54-151 VIS FM Ftf-68A S-8 WCMU56-151 VIS FW Ftf-68A lt-8 WCMU6-151 VIS

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 277
  • 0003
  • DATE 86/10/20 *
  • CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION
                                                  • lHHHt***********************************************************************

ITEM NUMBER  : Dl.lOH ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448 I COORD NUMBER METHOD REQUEST NOTES FW FH-68A H-8 WCMU7-151 VIS FW FH-68A F-8 WCMUS-151 VIS FW . FH-68A S-8 WC!'l.19-151 VIS FW FH-688 K-4 WAPDlS0-601 VIS FW FH-688 1-3 WAPDlSl-601 VIS FW FH-68B J-6 WAPDS0-601 VIS FW FH-686 1-7 WAPDSl-601 VIS FW FH-688 K-6 WAP052-601 VIS FW Ftt-686 e-s WCMUlll-151 VIS

-VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

  • -****KKKKKKKKK~**

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 278 ASME SECTION XI EDITION 80W80 REVISION 0003
  • DATE 86/10/20 *
                            • KKKK~KKKKKKKKKKKKKKK************************************KKKKKKKK*if********************
  • CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION
                              • KKKKKKKK*****************************************************************************

ITEM NUMBER  : Dl.lOH -I ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF

  • PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

FW Ftt-688 E-6 WCMU153-151 VIS FW Ftt-688 E-7 WCl1Ul54-151 VIS FW Ftt-688 E-8 WCtn.Jl56-151 VIS FW Ftt-688 E-2 WCf'fU53-151 VIS MS Ftt-64A B-5 SHP25-601 VIS MS Ftt-64A B-6 SHP26-601 VIS HS Ftt-64A C-7 SHP27-601 VIS MS Ftt-64A C-8 SHP2S--601 VIS MS Ftt-64A C-7 SHP29-601 VIS

  • SURRY POWER STATION UNIT 1 * *
  • INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 PAGE 279 ASME SECTION XI EDITION aowao REVISION 0003

  • . 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 ( 11448) COORD NUMBER METHOD REQUEST. NOTES

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

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

MS Ftt-(,4A C-7 SHP30-601 VIS MS FH-64A F-8 SHP31-601 VIS MS FH-64A B-7 SHP32-601 VIS

  • MS FH-64A S--8 SHP57-601 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 280 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES cc FM-71B 0-7 CC33S-151 VIS cc FM-71B S-6 CC336-151 VIS cc FM-716 F-7 CC33rl51 VIS cc FM-71B F-6 CC338-151 VIS cc FM-716 S-6 CC339-151 VIS cc FM-716 0-5 CC340-151 VIS cc FM-71B S-5 CC341-151 VIS cc FM-716 e-s CC342-151 VIS cc FM-71B 0-4 cc343-1s1 VIS
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 281 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 I

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES cc FM-71B 1-4 CC344-151 VIS cc FM-71B S-4 CC345-151 VIS cc FM-71B H-4 cc346-1s1 VIS cc FM-71B E-4 CC347-151 VIS cc FM-71B 5-4 CC34s-151 VIS cc FM-71B S-4 CC349-151 VIS cc FM-71B H-6 CC350-151 VIS cc FM-71B E-6 CC351-151 VIS cc FM-72.A A-3 CCl00-151 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 282 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 C11448) COORD NUMBER METHOD REQUEST NOTES cc Ftt-72A E-6 cc101-1s1 vfs cc Ftt-72A 0-3 CClOZ--151 VIS cc Ftt-72A 0-3 CClOJ-151 VIS cc Ftt-72A 0-4 cc104-1s1 VIS cc Ftt-72A E-7 cc1os-1s1 VIS cc Ftt-72A f-4 CC107-151 VIS cc Ftt-72A F-5 CClOS-151 VIS cc Ftt-72A E-6 CC109-151 VIS cc Ftt-72A H-7 cc110-1s1 VIS
                            • MMMMMMMM**if*****'if*********************************************************************
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN SUMl1ARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 283 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 ( 11448) COORD NUMBER METHOD REQUEST NOTES

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

cc FM-72A H-4 cc112-1s1 VIS cc Frt-72A H-5 CC113-151 VIS cc Frt-72A H-6 CC114-151 VIS

  • I cc Frt-72A L-3 CC16-121 VIS cc Frt-72A J-4 CCl"?-121 VIS cc FM-72A A-2 cc200-1s1 VIS cc Frt-72A 0-2 cc201-1s1 VIS cc Frt-72A A-4 CC202-151 VIS cc Frt-72A 0-4 CC203-151 VIS
  • SURRY- POWER STATION UNIT l *
  • INSERVICE* INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 284 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY o-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION *
                            • KKKKKKKKKKKKMM****************************KKKMMMMK************************************

ITEM NUMBER  : Dl.lOS ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE I

FLO!,! FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORO NUMBER METHOD REQUEST NOTES cc Flt-72A A-6 cc204-1s1 VIS cc Flt-72A 0--6 cc2os-1s1 VIS cc Flt-72A e-2 CC206-151 VIS cc Flt-72A H-5 CC207-151 VIS cc Flt-72A E-2 CC246-151 VIS cc Flt-72A H-8 CC247-151 VIS cc FH-72A F-6 cc3os-1s1 VIS cc FH-72A H-6 CC306-151 VIS cc Flt-72A F-7 CC307-151 VIS

  • SURRY POWER STATION UNIT l *"
  • INSERVICE INSPECTION PLAN

SUMMARY

              • lHHHf*********
  • INTERVAL 2, 12/22/82 TO 12/22/92 * -PAGE 285 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • (-
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES cc Frt-72A S-7 cc305-1s1 VIS cc Frt-72.A F-1 CCS-121 VIS cc Frt-72A A-6 CC82-151 VIS cc Frt-72.A A-:-7 cc53-1s1 VIS cc Frt-72A A-7 CC84-151 VIS cc Frt-72A 0-7 cc8s-1s1 VIS cc Frt-72A 0-7 CC86-151 VIS cc Frt-72A C-7 CC87-151 VIS cc Frt-72.A E-7 CCSS-151 VIS

  • SURRY POWER STATION ~IT l
  • INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 286 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER  : Dl.lOS ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF R~ SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES cc FM-72A A-5 CC89-151 VIS cc FM-72A A-4 CC90--151 VIS cc FM-72A A-5 cc91-1s1 VIS cc FM-72A A-S CC92-151 VIS cc FM-72A D-6 cc93-1s1 VIS cc FM-72A 0-5 cc94-1s1 VIS cc FM-72A C--5 cc9s-1s1 VIS cc FM-72A 0-6 CC96-151 VIS cc FM-72A A-3 CC97-151 VIS
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 287 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 C11448) COORD NUMBER METHOD REQUEST NOTES cc FM-72A A-2 cc9a-1s1 VIS cc FM-72A A-3 CC9'rl51 VIS cc FM-726 A-1 CCl0-121 VIS cc FM-726 A-1 cc11s-1s1 VIS cc FM-726 E-3 CC120-151 VIS cc FM-726 I-4 cc1s-1s1 VIS cc FM-726 F-3 CC76-151 VIS cc FM-726 E-4 CC77-151 VIS cc FM-728 e-1 cc1a-1s1 VIS
                                        • KKKKKKKKKKK*********************************************************************

VIRGINIA SURRY ELECTRIC AND POWER COMPANY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASHE SECTION XI EDITION 80W80

  • PAGE 288 *
  • REVISION 0003 *
  • DATE 86/10/20 *
                                  • KKKKKKK****************************************************************************
  • CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEH NUMBER  : Dl.10S ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

cc FH-72B_ F-4 CC79-151 VIS cc FH-72B S-2 CC80-151 VIS cc FH-72B I-2 cc81-1s1 VIS cc FH-72B I-1 CC89-121 VIS cc FH-72C S-8 cc14-121 VIS cc FH-72C J-2 cc143-121 VIS cc FH-72C S-8 cc1s-121 VIS cc FH-72C K-1 cc1s1-1s1 VIS cc FH-72C S----3 CClSJ-151 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY* POWER STATION UNIT l INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASHE SECTION XI EDITION 80W80

  • PAGE
  • REVISION 289
  • 0003
  • DATE 86/10/20 *
  • CATEGORY 0-A SYSTEMS IN .SUPPORT OF REACTOR SHUTDOWN FUNCTION if ITEM NUMBER  : Dl.lOS ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448 > COORD NUMBER METHOD REQUEST NOTES

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

cc FM-72C F-2 CC154-151 VIS cc FM-72C E-3 cc1ss-1s1 VIS cc FM-72C S-1 cc161-121 VIS cc FM-72C H-2 CC169-12i VIS cc FM-72C H-2 CC17rl51 VIS cc FM-72C L-4 cc301-1s1 VIS cc FM-72C K-4 CC302-151 VIS cc FM-72C L-4 CC303-151 VIS cc FM-72C L-5 CC304-151 VIS

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

.* PAGE 290 *

  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY 1)-;-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 (11448) comm NUMBER METHOD REQUEST NOTES

=======

cc. Ftt-72C J-5 CC364-151 VIS cc Ftt-72C K-4 CC383-121 VIS cc Ftt-72C K-5 CC385-151 VIS cc Ftt-72C H-3 CC473-151 VIS cc Ftt-72C J-5 CC474-151 VIS cc Ftt-72C I-7 CC61-151 VIS cc Ftt-72C I-6 CC62-151 VIS cc Ftt-72C 1-3 CC6S-12l VIS cc Ftt-72C J-6 CC66-151 VIS

                            • IEIEIEIEIEIEIE*******************-IEIEIEIEIEIEIEIE***-*********************************************
  • SURRY POWER STATION UNIT l *
  • IHSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 291 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER  : 01.105 ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE

.I FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM . LINE EXAM RELIEF. PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES cc Ftt-72C H-4 CC67-151 VIS cc Ftt-72C 1-3 CC69-151 VIS cc FM-72C .r7 CC70-cl21 VIS cc Ftt-72C .r3 CC70-151 VIS cc Ftt-72C .r4 cc11-1s1 VIS cc Ftt-72C K-2 CC72-l21 VIS cc Ftt-72C 1-1 cca1-121 VIS cc Ftt-72D C-2 cc1-121 VIS cc Ftt-72D a-2 CC19-121 VIS

                                                                                                                                                                                                    • ~*
  • SURRY* POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 292 *
  • ASME SECTION XI EDITION 80W80 REVISION 0003
  • DATE 86/10/20 *
  • CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION
                                                  • IHf*************************************************************************

ITEM NUMBER Dl.lOS ITEM DESCRIPTION COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

cc FM-72D C-2 cc2-121 VIS cc FM-72D A-2 CC20-151 VIS cc FM-72D A-3 cc21-1s1 VIS cc FM-72D A-2 CC22-151 VIS cc FM-72i> 0-2 CC220-121 VIS cc FM-72D A-3 CC222-151 VIS cc FM-72D 0-3 cc224-121 VIS cc FM-72D F-2 cc22s-121 VIS cc FM-72D J-1 CC226-121 VIS

  • VIR_GINIA ELECTRIC AND POWER COMPANY *
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN ~ARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 293 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION ITEM NUMBER  : 01.105 ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE I

FLOW FLOW SYSTEM/ DIAGRAM . DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES cc Ftt-720 0-2 CC227-121 VIS cc Ftt-720 D-2 cc228-121 VIS cc Ftt-720 D-3 CC229-121 VIS cc Ftt-720 D-1 CC230-121 VIS cc Ftt-720 E-1 cc231-121 .VIS cc Ftt-720 E-2 CC232-121 VIS cc Ftt-720 E-3 CC233-121 VIS cc Ftt-720 E-4 CC234-151 VIS 1-cc Ftt-720 S-1 cc23s-121 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 294* *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 SYSTEM/ DIAGRAM DIAGRAtt LINE. EXAM RELIEF PROGRAM COMPONENT t 11448) COORD NUMBER METHOD REQUEST NOTES cc Ftt-72D F-1 CC236-121 VIS cc Ftt-72D F-1 CC23rl21 VIS cc Ftt-72D L-2 CC2rl21 VIS cc Ftt-72D C-3. CCJ-121 VIS*

cc Ftt-72D F-8 CC314-151 VIS cc Ftt-72D 0-~ CC319-151 VIS cc Ftt-72D S-1 CC320-151 VIS cc Ftt-72D C-3 cc4-121 VIS cc Ftt-72D 0-2 ccs-121 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 295 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY 0-A SYSTEMS IN SUPPORT.OF REACTOR SHUTDOWN FUNCTION
  • ITEM HUNBER Dl.lOS ITEM DESCRIPTION COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE* EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

cc Ftt-72D 0-3 CC6-121 VIS cc Ftt-72D L-1 CC7-121 VIS cc Ftt-72D K-1 CC9-121 VIS CH Ftt-88A 0-4 CH139-152 VIS CH Ftt-88A F-4 CH140-152 VIS CH Ftt-88A H-8 CH141-152 VIS CH Ftt-88A F-6 CH142-152 VIS CH Ftt-88A S-7 CH143-152 VIS CH Fl't-88A F-6 CH144-152 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 296 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION
                                                                                                                                              • ii****************************

ITEM NUMBER  : Dl.lOS ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT  ! 11448) COORD NUMBER METHOD REQUEST NOTES CH FM-88A 0-5 CH14S-152 VIS CH FM-88A 0-5 CH146-152 VIS CH FM-88A F-S CH14?-152 VIS CH FM-88A c-'"7 CH14S-152 VIS CH FM-88A 0-6 CH149-152 VIS CH FM-88A o-6 CHlS0-152 VIS CH F~88A c-'"4 cH1s2-1s2 VIS CH FM-88A 0-4 CHlSJ-152 VIS CH Fl1-88A G-4 CH154-152 VIS

                        • ll ll ll ll ll llll********************************************ll llllllll llllll ll****************************
  • SURRY POWER STATION UNIT l *
  • -./ INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 297 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20
  • ll******************~**********************************************************~f****************
  • CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION
                          • llllllllllllllllll******************************************************************************

ITEM NUMBER  : Dl.lOS ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES CH -Flt-88A tt-7 CHlSS-152 VIS CH Flt-88A E-7 CH156-152 VIS CH Flt-88A E-6 cH1ss-1s2 VIS CH Flt-88A tt-5 CH179-152 VIS CH Flt-88A E-S CH180--152 VIS CH Flt-88A a-s CH181-152 VIS CH Flt-88A A-6 CH229-152 VIS CH Flt-88A J-7 CH230--152 VIS CH Flt-88A E-7 CH241-152 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 298 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES CH Ftt-'88A 0-5 CH243-152 VIS CH FM-88A 0-4 CH24S-152 VIS CH FM-88A F-4 CH246-152 VIS CH FM-88A C-8 CH34-152 VIS CH FM-88A 1-7 CH342-152 VIS CH FM-88A C-8 CHJS-152 VIS CH FM-88A E-8 CH36-152 VIS CH FM-88A F-8 CH37-152 VIS CH FM-88A C-5 CHJS-152 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 299 *
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                              • ~******************************************************************
  • CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION
  • ITEM NUMBER ITEM DESCRIPTION
Dl.lOS
COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE I

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST, NOTES CH Ftt-88A E-6 CH39-152 VIS CH Ftt-88A E-7 CH40-152 -VIS CH Ftt-88A S-5 CH41-152 VIS CH Ftt-88A A-8 CH42'-152 VIS CH Ftt-88A S-6 CH43-152 VIS CH Ftt-88A E-8 CH52'-152 VIS CH Ftt-88A F-8 CHS3-152 VIS CH Ftt-88A F-7 CH61-152 VIS CH Ftt-88A 0-7 CH62'-152 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN SUl1MARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 300 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION
  • ITEM NUMBER Dl.lOS ITE~ DESCRIPTION COMPONENTS.IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM ** LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES CH Ftt-88A H-6 CH64-152 VIS CH Ftt-888 J-3 CH19S-152 VIS CH Ftt-888
  • K-4 CHS6-152 VIS CH Ftt-88B J-6 CHS?-152 VIS CH Ftt-88B J-3 CHSS-152 VIS FW Ftt-68A F-8 WAPD-151 VIS FW Ftt-68A E-6 . WAPDI-601 VIS FW Ftt-68A C-6 WAPDI0-601 VIS FW Ftt-68A e-s
  • WAPDll-601 VIS
  • SURRY* POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 301 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11448) COORD NUMBER - METHOD REQUEST NOTES FW FM-68A B-6 WAPD12-601 VIS FW FM-68A S-6 WAPD13-601 VIS FW FM-68A B-6 WAPD14-601 VIS FW FM-68A 0-7 WAPD15-601 VIS FW FM-68A K-2 WAPD152-601 VIS FW FM-68A D-6 WAPD16-151 VIS FW FM-68A E-'7 WAPD17-601 VIS FW FM-68A F-6 WAPD18-151 VIS FW FM-68A i=-6 WAPD19-151 VIS
  • SURRY POWER STATION UNIT 1 *
  • IHSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 302 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY D-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION
  • ITEM HUMBER  : Dl.lOS ITEM DESCRIPTION : COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C 11448) COORD HUMBER METHOD REQUEST NOTES FW Ftt-68A E-6 WAPD2-601 VIS FW Ftt-68A G-7 WAPD20-601 VIS FW Ftt-68A G-6 WAPD~l-151 VIS
  • FW FW FW Ftt-68A Ftt-68A Ftt-68A 0-7 0-6 E-6 WAPD3-601 WAPD4-601 WAPDS-601 VIS VIS VIS

. FW Ftt-68A F-6 WAPD6-601 VIS FW Ftt-68A F-6 WAPD7-601 VIS FW Ftt-68A G-6 WAPDS-601 VIS

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

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASHE SECTION .XI EDITION 80W80

  • PAGE 303 *
  • REVISION 0003 *
  • 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 PROGRAl"'I

, COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES FW Ftt-68A C-4 WAPD9-601 VIS FW Ftt-68A E-8 WCMUl0-151 VIS FW Ftt-68A 0-8 WCMUll-151 VIS FW Ftt-68A S-8 WCMU151 VIS FW Ftt-68A H-8 WCMU4-1s1 VIS FW Ftt-68A H-8 WCMUS-151 VIS FW Ftt-68A E-8 WCMU54-151 VIS FW Ftt-68A S-8 WCMU56-151 VIS FW Ftt-68A H-8 WCMU6-151 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

    • PAGE
  • REVISION 304
  • 0003*
  • 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 DIAGRAl't LINE EXAM RELIEF PROGRAM COMPONENT ( 11448) COORD NUMBER METHOD REQUEST NOTES FW Ftt-68A lt-8 WCMUrlSl VIS FW Ftt-68A F-8 WCMUS-151 VIS FW Ftt-68A G-8 WCMU9-151 VIS FW Ftt-68B K-4 WAPOlS0-601 VIS FW Ftt-68B 1-3 WAPOlSl-601 VIS FW Ftt-688 J-6 WAPOS0-601 VIS FW Ftt-688 1-7 WAPOSl-601 VIS FW Ftt-68B K-6 WAP052-601 VIS FW Ftt-688. E-S WCMUlll-151 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 305
  • 0003
  • 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 C11448) COORD NUMBER METHOD REQUEST NOTES FW Ftt-68B E-6 WCl1Ul53-151 VIS FW Ftt-68B E-7 WCl1Ul54-151 VIS FW Ftt-68B E-8 WCMU156-151 VIS

-* FW MS MS Ftt-688 Ftt-64A Ftt-64A E-2 s-s B-6 WCl1U53-151 SHP25-601 SHP26-601 VIS VIS VIS MS Ftt-64A C-7 SHP2?-601 VIS MS Ftt-64A C-6 SHP2S-601 VIS MS Ftt-64A C-7 SHP29-601 VIS

  • ,If
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 306 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY 0-A SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCTION
  • ITEM NUMBER Dl.10S ITEM DESCRIPTION COMPONENTS IN SUPPORT OF RX SHUTDOWN-SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUi'1BER METHOD REQUEST NOTES

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

MS FM-64A C---7 SHP30-601 VIS MS Ftt-64A F-8 SHP31-601 VIS MS FM-64A S--7 SHP32-601 VIS MS FM-64A S-8 SHP5r601 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 307 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES SW FM-71A E-6 wc1-10 VIS SW FM-71A E-6 WC2-10 VIS SW FM-71A F-6 wc3-10 VIS SW FM-71A F-6 wc4-10 VIS SW FM-71A C-7 ws1-10 VIS SW FM-71A S-6 ws12-10 VIS SW FM-71A S-6 wsn-10 VIS SW FM-71A H-4 ws14-10 VIS SW FM-71A H-s ws1s-10 VIS
  • SURRY POWER STATION UNIT l
  • INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 308 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
    • CATEGORY o-s ECCS, CHR, ACU, ANO RHR SUPPORT SYSTEMS *
  • \.
  • ITEM NUMBER  : D2.10H ITEM DESCRIPTION : C011PONENT IN SUPPORT OF ECCS, CHR, ACU, ~ RHR - HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM *DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11448) COORD NUMBER METHOD REQUEST NOTES SW Ftt-71A H-5 WS16-10 VIS SW Ftt-71A S-3 WSlrlO VIS SW Ftt:"71A s-4 WSlS-10 VIS SW Ftt-71A S-5 WS19-10 VIS SW Ftt-71A C-7 ws2-10 VIS SW Ftt-71A 0-5 ws21-10 VIS SW Ftt-71A 0-7 ws22-10 VIS SW Ftt-71A A-6 ws23-10 VIS SW Ftt-71A S---7 WS24-10 VIS
  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 309 *
  • ASME *SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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, r RHR - HYDROSTATIC FLOW FLOW SYSTEM/ DIAGR-AM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

SW Ftt-71A A-3 WS26-10 VIS SW Ftt-71A S-3 WS2S-10 VIS SW Ftt-71.A C-3 WS30-10 v*Is SW FM-71A C-3 WS32-10 VIS SW FM-71A A-3 ws33-10 VIS SW FM-71A S-3 W534-10 VIS SW Ftt-71A 9-3 WS35-10 VIS SW Ftt-71A C-3 WS36-10 VIS SW Ftt-71A 0-3 WS37-10 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 310 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY o-e ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS

VIRGINIA ELECTRIC ANO POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN SUNMARY INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 311
  • 0003
  • DATE 86/10/20 *
  • CATEGORY D-B EC.CS, CHR, ACU, AND RHR SUPPORT SYSTEMS
  • ITEM NUMBER D2.10H ITEM DESCRIPTION COMPONEITT IN SUPPORT OF ECCS, CHR, ACU, ~ RHR - HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONEITT (11448) COORD NUMBER METHOD REQUEST NOTES

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

SW FH-71A J-7 WS55-136 VIS SW FH-71A J-7 WS56-136 VIS SW FH-71A J-7 WS5?-136 VIS SW FH-71A K-7 WS58-l36 VIS SW FH-718 S-7 WS178-136 VIS SW FH-718 0-8 WS?0-136 VIS SW Flt-718 0-8 WS71-136 VIS SW Flt-718 S--8 WS72-136 VIS SW Flt-718 S--8 WS73-136 VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 312 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY 0-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS ITEM NUNBER D2.10H ITEM DESCRIPTION .: COMPONENT IN SUPPORT OF ECCS, CHR, ACU, r RHR - HYDROSTATIC FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT 111448) COORD NUNBER METHOD REQUEST NOTES

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

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

SW FH-71B 0-7 ws14-21x VIS SW FH-71B S-7 ws1s-21x VIS SW FH-71B F-8 WS76-21B VIS SW FH-71B C-8 WS7r21B VIS SW FH-71B S-6 WS78-136 VIS SW FH-71B C-1 WS79-21B VIS SW FH-71B H-1 wsao-21B VIS SW FH-71B 0-1 wsa1-21x VIS SW FH-71B H-1 WS82-21X VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN SUW1ARY ********************

INTERVAL 2, 12/22/82 TO 12/22/92

  • PAGE 313 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 I 11448) COORD NUMBER METHOD REQUEST NOTES

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

SW FM-71B E-1 WS83-21B VIS SW FM-71B E-1 WS84-21B VIS SW FM-716 A-1 wsas-210 VIS SW FM-71B E-1 WS86-21B VIS SW FM-716 H-2 WS8r21B VIS SW FM-716 0-2 WS88-21B VIS SW FM-716 A-6 WS8~136 VIS SW FM-71B E-7 WS90-l36 VIS

                  • ~******************************************************************************************
  • SURRY . POWER STATION UNIT 1 '*
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 314 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY 0-B ECCS, CHR, ACU, ANO RHR SUPPORT SYSTEMS
                                                          • ~**********************************************************************

ITEM NUMBER  : D2.10S *1 ITEM DESCRIPTION : COMPONENT IN SUPPORT OF ECCS, CHR, ACU, r RHR - SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES SW Ftt-71A E-6 wc1-10 VIS SW Ftt-71A E-6 WC2"-10 VIS SW Ftt-71A F-6 WC3-10 VIS SW Ftt-71A F-6 wc4-10 VIS SW F:tt-71A C-7 ws1-10 VIS SW Ftt-71A S-6 WS12"-10 VIS SW Ftt-71A S-6 ws13-10 VIS SW Ftt-71A H-4 ws14-10 VIS SW Ftt-71A H-5 ws1s-10 VIS

VIRGINIA ELECTRIC ANO POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASHE SECTION XI EDITION 80W80

  • PAGE
  • REVISION 315
  • 0003
  • DATE 86/10/20 *
  • CATEGORY D-B - ECCS, CHR, ACU, ANO RHR SUPPORT SYSTEMS
  • ITEH NUMBER 02.lOS ITEH DESCRIPTION COMPONENT IN SUPPORT OF ECCS, CHR, ACU, ~ RHR - SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORO NUMBER METHOD RE']UEST NOTES

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

SW FM-71A lt-5 WS16-10 VIS SW FM-71A S-3 WSlrlO VIS SW FM-71A S-4 MS18-10 VIS SW FM-71A S-5 WS19-10 VIS SW FM-71A C-7 WS2-10 VIS SW FM-71A 0-5 ws21-10 VIS SW FM-71A 0-7 ws22-10 VIS SW FM-71A A-6 ws23-10 VIS SW FM-71A S-7 ws24-10 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY INSERVICE POWER STATION UNIT l INSPECTION PLAH

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 316
  • 0003 *
  • DATE 86/10/20 *
    • CATEGORY D-e ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS HEM NUMBER D2.10S ITEM DESCRIPTION COMPONENT IN SUPPORT OF ECCS, CHR, ACU, ~ RHR - SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAN DIAGRA?t
  • LINE EXAM RELIEF PROGRAM COMPONENT I 11448) COORD l'M1BER METHOD REQUEST NOTES

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

SW Ftt-71A A-3 WS26-10 VIS SW Ftt-71A B-3 WS2S--10 VIS SW Ftt-71A . C--3 1_,1530-10 VIS.

SW Ftt-71A C--3 WS32-10 VIS SW Ftt-71A A-3 WS33-10 VIS SW Ftt-71A B-3 W534-10 VIS SW Ftt-71A B-3 ws3s-10 VIS SW Ftt-71A C--3 WS36-10 VIS SW Ftt-71A 0-3 WS3rl0 VIS

    • SURRY POWER STATION UNIT l *
  • INS ERV ICE 'INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 317 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY 0-B ECCS, CHR, ACU, ANO RHR SUPPORT SYSTEMS *
                                                                                                                                                              • If********************

ITEM NUMBER D2.10S ITEM DESCRIPTION COMPONENT IN SUPPORT OF ECCS, CHR, ACU, r RHR - SYSTEM LEAKAGE FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) .COORD NUMBER METHOD REQUEST NOTES SW Ftt-71A 0-3 WS38-10 VIS SW Ftt-71A I-6 WS39-10 VIS SW Ftt-71A C-7 WS4-10 VIS SW Ftt-71A H-6 WS40-l0 VIS SW Ftt-71A S-6 ws41-10 VIS SW Ftt-71A F-6 WS42-136 VIS SW Ftt-71A r-a wss1-10 VIS SW Ftt-71A I-a WS52-10 VIS SW Ftt-71A I-a WSS3-136 VIS

  • SURRY. POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 318 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
                                                  • lHt*************************************************************************
  • CATEGORY o-B ECCS, .CHR, ACU, AND RHR SUPPORT SYSTEMS
  • I ITEM NUMBER 02.lOS ITEM DESCRIPTION COMPONENT IN SUPPORT OF ECCS, CHR, ACU, ~ RHR - SYSTEM LEAKAGE FLOW FLOW I SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (114481 COORD NUMBER METHOD REQUEST NOTES SW Ftt-71A J-7 wsss-136 VIS SW Ftt-71A J-7 WS56-136 VIS SW Frt-71A J-7 WSSr-136 VIS SW Ftt-71A K-7 WSSS-136 vis SW Ftt-71B 5-7 WS178-136 . VIS SW Ftt-71B o-a WS70-136 VIS SW Ftt-71B 0-8 wsn-136 VIS SW Ftt-71B S--8 WS72-136 VIS SW Ftt-71B S--8 WS73-136 VIS
  • SURRY POWER STATION UNIT 1 *
  • *INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 319 *
  • ASME SECTION XI EOITION 80W80
  • REVISION 0003 *
  • 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, J RHR - SYSTEM LEAKAGE I

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM. LINE EXAM RELIEF PROGRAM COMPONENT ( 11448) COORD NUMBER METHOD REQUEST NOTES SW FM-71B 0-7 ws14-21x VIS SW FM-71B S--7 ws1s-21x VIS SW FM-71B F-8 WS76-21B VIS SW FM-71B C-8 WS77-21B VIS SW FM-71B B-6 WS7S--136 VIS SW FM-71B C-1 WS79-21B VIS SW FM-71B lf-1 wsao-210 VIS SW FM-71B 0-1 wss1-21x VIS SW FM-71B H-1 ws02-21x VIS

VIRGIN!., ELECTRIC AND POWER COMPANY SURRY

. ASHE POWER STATION UNIT l INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 SECTION XI EDITION. 80W80

  • PAGE
  • REVISION 320
  • 0003 *
  • 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 FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

SW Ftt-71B E-1 WS83-21B VIS SW Ftt-71B E-1 WS84-21B VIS SW Ftt-71B A-1 wsss-21a VIS SW Ftt-71B E-1 W586-2lB VIS SW Ftt-71B H-2 WS8r21B VIS SW Ftt-71B 0-2 wsss-210 VIS SW Ftt-71B A-6 WS89-136 VIS SW Ftt-71B E-7 WS90-136 VIS I

I*

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN SUMNARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 321 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY D-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS ITEM NUMBER 02.20 ITEM DESCRIPTION INTEGRAL ATTACHMENT-SUPPORTS ~ RESTRAINTS FOR ECCS, ETC.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

AF Ftt-68A E-6 WAPOl-601 VIS AF Ftt-68A 0-7 WAPOIS-601 VIS AF Ftt-68A 0-7 WAPDIS0-601 VIS AF Ftt-68A H-8 WCMUS-151 VIS AF Ftt-68A H-8 WCMU6-151 VIS AF Ftt-68A H-8 WCl1Url51 VIS AF Ftt-68A F-8 WCMUS-151 VIS AF Ftt-688 J-6 WAPOS0-601 VIS AF Ftt-688 0-2 WCMU52-151 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN

SUMMARY

    • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 322 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES

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

AF Ftt-688 E-2 WCMU53-151 VIS AF Ftt-688 0-3 WCMUSS-151 VIS AF Ftt-720 A-1 WCMU14-301 VIS cc Ftt-72A E-7 CClOl-151 VIS cc Ftt-72A 0-7 cc104-1s1 VIS cc Ftt-72A H-4 CCllZ--151 VIS cc Ftt-72A L-3 CC16-121 VIS cc Ftt-72A J-4 CCl?-121 VIS cc Ftt-72A 0-7 cc2os-1s1 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 323 *
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY 0-B- ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS ITEM NUMBER 02.20 ITEM DESCRIPTION INTEGRAL ATTACHMENT-SUPPORTS r RESTRAINTS FOR ECCS, ETC.

FLQlo,I FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) COORD NUMBER METHOD REQUEST NOTES cc Ftt-72A S-2 CC262-151 VIS cc Ftt-72A S-2 cc296-1s1 VIS cc Ftt-72A F-1 CCS-121 VIS cc Ftt-72A 1..-6 CC82-151 VIS cc Ftt-72A 0-7 cces-1s1 VIS cc F~72A E-7 CC'IB-151 VIS cc Ftt-72A A-5 CC89-151 VIS cc Ftt-72A A-4 CC90--l51 VIS cc Ftt-72A 0-6 CC93:-151 VIS

                                                  • MMMMMMM********************************************************************

VIRGINIA ELECTRIC ANO POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE 324 *
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY D-B ECCS, CHR, ACU, ANO 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 ( 11448) COORD NUMBER METHOD REQUEST NOTES

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

cc FM-72A A-3 CC97-151 VIS cc FM-72B A-1 CCl0-121 VIS cc FM-72B A-1 cc11s-1s1 VIS cc FM-72B 1-4 CC7S-151 VIS cc FM-72B F-3 CC76-151 VIS cc FM-72B E-3 CC77-151 VIS cc FM-726 E-1 cc1a-1s1 VIS cc FM-726 f-4 CC79-151 VIS cc FM-72B S-2 CC80-151 VIS

                                    • KKKKKKK***************************************************************************

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASME SECTION XI EDITION 80W80

  • PAGE
  • REVISION 325
  • 0003
  • DATE 86/10/20 *
                                                                                                                                • KKKKKKK*****************************
  • CATEGORY D-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS
                              • KKKKKKKKlt****************************************************************************

ITEM NUNBER D2.20 ITEM DESCRIPTION INTEGRAL ATTACHMENT-SUPPORTS ~ RESTRAINTS FOR ECCS, ETC.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUNBER METHOD REQUEST NOTES cc FM-72B 1-2 cc8i-1s1 VIS cc FM-72C S-8 cc14-121 VIS cc FM-72C J-2 *CC143-121 VIS cc FM-72C S-8 cc1s-121 VIS cc FM-72C K-8 cc1s2-1s1 VIS cc FM-72C S-3 cc1s3-1s1 VIS cc FM-72C F-2 cc1sa-1s1 VIS cc FM-72C J-5 CC364-151 VIS.

cc FM-72C H-3 CC473-151 VIS

                              • MMMMMMMMlHf***************************************************************************
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 326 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10120 *
  • CATEGORY 0-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEM.S ITEM NUMBER - : D2.20 ITEM DESCRIPTION INTEGRAL ATIACHMENT-SUPPORTS ~- RESTRAINTS FOR ECCS, ETC.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT I 11448) COORD NUMBER METHOD REQUEST NOTES

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

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

cc Ftt-72C J-5 CC474-151 VIS cc Ftt-72C J-6 CC66-151 VIS cc FM-72C H-2 CC6J-121 VIS cc Ftt-72C H-4 CC6J-151 VIS cc Ftt-72C H-2 CCJ-121 VIS cc Ftt-72C J-7 cc10-121 VIS cc Ftt-72C J-3 CC70-151 VIS cc FM-72C K-2 CC72-121 VIS cc Ftt-72C 1-1 cc81-121 VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN SUNNARY . ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 327 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY 0-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS ITEM NUMBER D2.20 ITEM*DESCRIPTION INTEGRAL ATTACHMENT-SUPPORTS ~ RESTR.AINTS FO~ ECCS, ETC.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES cc FM-72D C-2 cc1-121 VIS cc FM-72D B-2 CC19-121 VIS cc FM-72D C-2 CC2-121 VIS

  • cc cc cc FM-72D FM-72D FM-72D A-2 F-2 J-1 CC20-151 cc22s-121 CC226-121 VIS VIS VIS cc FM-72D 0-2 CC22r121 VIS cc FM-72D 0-2 cc22a-121 VIS cc FM-72D 0-3 CC229-121 VIS
  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN SUM!1ARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 328 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (114481 COORD NUMBER METHOD REQUEST NOTES cc FM-72D S-1 cc23s-121 VIS cc Ftt-720 F-1 CC236-121 VIS cc Ftt-720 F-1 CC23rl21 VIS cc Ftt-720 L-2 CC2rl21
  • VIS cc Ftt-720 F-8 CC28rl51 VIS cc FM-720 C-3 cc3-121 VIS cc Ftt-720 C-3 cc4-121 VIS cc Ftt-720 L-1 CCrl21 VIS cc Ftt-72E H-3 CC146-151 VIS

VIRGINIA ELECTRIC ANO POWER COMPANY SUHRY POWER STATION UNIT l INSERVICE INSPECTION PLAN SUNNARY INTERVAL 2, 12/22/82 TO 12/22/92 ASHE SECTION XI EDITION 80W80

  • PAGE
  • REVISION 329
  • 0003
  • DATE 86/10/20 *
  • CATEGORY D-B ECCS, CHR, ACU, ANO 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 C11448 l comm NUMBER METHOD REQUEST NOTES

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

cc FM-72E H-2 cc148-1s1 VIS cc FM-72F F-3 CC149-151 VIS cc FM-72F D-2 CC1S6-151 VIS cc FM-72F D-2 CC159-151 VIS

(

cc FM-72F 0-2 CC160-151 VIS cc FM-72F C-2 CC165-151 VIS cc Fl't-72F A-2 CC184-I51 VIS MS FM-68A K-2 WAPDlSZ-601 VIS MS FM-68A E-6 WAPDZ-601 VIS

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PLAN

SUMMARY

INTERVAL 2, 12/22/82 TO 12/22/92 ASHE SECTION XI EDITION 80W80

  • PAGE
  • REVISION 330
  • 0003
  • 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 ( 11448) COORD NUMBER METHOD REQUEST NOTES

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

RC Flt-86A H-4 RC20-1502 VIS RC Flt-86B E-4 RC36-602 VIS RC Flt-86B H-4 RC40-602 VIS RC Flt-86B F-4 RC41-602 VIS RC Flt-86B J-4 RC62-602 .VIS RHR Flt-87A J-4 RHlS-152 VIS SW Frt-71A A-3 WS26-10 VIS SW Flt-71A A-3 WS26-136 VIS SW Frt-71A B-3 ws2a-10 VIS

  • SURRY POWER STATION-UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 331 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • 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 (11448) COORD NUMBER METHOD REQUEST NOTES

=======

SW FM-71A a-3 WS28-l36 VIS SW FM-71A C-3 ws30-10 VIS SW FM-71A C-3 WS30-136 VIS SW Ftt-71A C-3 WS32-l0 VIS SW FM-71A C-3 WS32-136 VIS SW FM-71A B-3 WS33-136 VIS SW FM-71A B-3. -WSJ4-136 VIS SW FM-71A S-:-3 WS35-136 VIS SW Ftt-71A B-3 WS36-136 VIS

  • SURRY POWER STATION UNIT 1 *
  • INSERVICE INSPECTION PLAN SUNMARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 332 *
  • ASHE SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY D-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS ITEM NUMBER D2.20 ITEM DESCRIPTION INTEGRAL ATIACHMENT-SUPPORTS ~ RESTRAINTS FOR ECCS, ETC.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES

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

SW Fl"r71A .J-7 WS5rl36 VIS SW Fl"r71A 'WSSS-136 VIS SW Fl"r71D WS30S-9107 VIS

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 333 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY 0-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS
                                                    • ~**********************************************************************

ITEM NUMBER D2.30 ITEM DESCRI~TION INTEGRAL ATTACHMENT-MECH. r HYD. SNUBBERS FOR ECCS, ETC.

FLOW FLOW l SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT C11448) . COORD NUMBER METHOD REQUEST NOTES cc Ftt-72C S-3 cc1s3-1s1 VIS

I I

I * *

  • SURRY POWER STATION UNIT l *
  • INSERVICE INSPECTION PLAN

SUMMARY

  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 334 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 **
  • CATEGORY 0-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS ITEM NUMBER D2.40 ITEM DESCRIPTION INTEGRAL ATTACHMENT-SPRING TYPE SUPPORTS FOR ECCS, ETC.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT (11448) COORD NUMBER METHOD REQUEST NOTES cc Ftt-72A J-4 CC:17-121 VIS cc Ftt-726 A-1 CCl0-121 VIS cc Ftt-72C S-8 cc14-121 VIS cc Ftt-72C S-8 cc1s-121 VIS cc Ftt-72C S-3 cc1s3-1s1 VIS cc Ftt-72C S-1 CC161-121 VIS cc Ftt-72C H-2 CC169-121 .VIS cc Ftt-72C H-2 CC177-1Sl VIS cc Ftt-72C 1-3 CC69-151 VIS

  • SURRY POWER STATION UNIT l **
  • INSERVICE INSPECTION PLAN SUNMARY ********************
  • INTERVAL 2, 12/22/82 TO 12/22/92
  • PAGE 335 *
  • ASME SECTION XI EDITION 80W80
  • REVISION 0003 *
  • DATE 86/10/20 *
  • CATEGORY 0-B ECCS, CHR, ACU, AND RHR SUPPORT SYSTEMS ITEM NUMBER 02.40 ITEM DESCRIPTION INTEGRAL ATIACHMENT-SPRING TYPE SUPPORTS FOR ECCS, ETC.

FLOW FLOW SYSTEM/ DIAGRAM DIAGRAM LINE EXAM RELIEF PROGRAM COMPONENT ( 11448) cornm NUMBER METHOD REQUEST NOTES cc Ftt-72F 0-2 CC159-151 VIS cc Ftt-72F C-2 CC165-151 VIS cc Ftt-72F S-2 cc173-1s1 VIS cc Ftt-72F A-2 cc1s1-1s1 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 steel.

None of the valve bodies are welded.

Section XI-of the ASME Code, 1980 Edition through the Winter 1980 Addendum, requires that a visual examinat'ion 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 ad~erse 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 extent practical, each time a valve is disassembled for maintenance purposes.

Note: This relief request has been modified as requested by letter from Mr. Steven A. Varga dated. January 24, 1984.

Sl-002 2-6 Rev. 3 March 27, 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 inaccessibility 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 A surface examination on the fillet pads will be performed.

weld of the reinforcement Note: This relief request has been modified as requested by letter from Mr. Steven A. Varga dated January 24, 1984 .

Sl-002 2-7 Rev. 3 March 27, 1987

RELIEF REQUEST NO. SR-003

  • I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The configuration of the Reactor Coolant branch nozzle connection welds precluded complete examination.

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 connection welds on piping having a nominal pipe size of four inches or greater. In particular, paragraph III-4430 requires an angle beam examination of the weld root from the weld crown.

Relief is requested from the requirements of paragraph III-4430 due to physical configuration of these branch nozzle connection welds.

II. BASIS FOR RELIEF Due to the configuration of the weld crown, transducer contact cannot be maintained on the weld. The slope of the weld crown precludes examination of the weld root when scanning from the weld crown.

III. ALTERNATE PROVISIONS The volumetric examinations on these welds will be performed to the extent practical.

Note: This relief request was granted by letter from Mr. Steven A.

Varga dated January 24, 1984 and is included for reference and information only .

Sl-002 2-8 Rev. 3 March 27, 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 examinatlon by ultrasonic examination.

III. ALTERNATE PROVISIONS A surface examination will be performed in lieu of the volumetric examination.

Note: This relief request was granted by letter from Mr. Steven A. Varga dated January 24, 1984 and is included for reference and information only .

Sl-002 2-9 Rev. 3 March 27, 1987

RELIEF REQUEST NO. SR-005

  • I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The shell to top head circumferential weld on the Surry Unit 1 Pressurizer is not accessible for examination. Additionally, the one foot long 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 FOR 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 an area 6 inches wide just below the weld. Inspection of the intersection of longitudinal weld

/115 with weld f!7 is prevented by a support column which span.s_

between the two upper insulation support rings. The column covers weld #15 for a length of approx~mately two feet from the intersection (see attached drawings) .

III. ALTERNATE PROVISIONS A visual (VT-2) examination for evidence of leakage will be performed during system pressure tests.

NOTE: In reference to the letter written 1/24/84 by Steven A. Varga to W. L. Stewart, relief request SR-5 was denied because inadequate information was* submitted. This relief request is now being resubmitted, providing the necessary information. Also, in addition to the problem with weld #7 mentioned in the first request, inaccessibility to weld #15 has also been disc~ssed in this revised relief request .

Sl-002 2-10 Rev. 3 March 27, 1987

WESTINGHOUSE ELECTRIC CORPORATION

\

ILLUSTRATIVE ONLY VPA-1-2100 PRESSURIZER Re v . I 6- I 8 _8 5 2

C 0

to 1-4501 12 II

  • -------+---..5

_ 6__ T to 1-4503 51 11 28 11 CENTERLINE OF MANHAY

  • - _ ~ _ f1 o_or 9

~~

INCHES

. 8 11 CCW 8 11 CCW 51"

________. . ___ 13 1

3711 12 13 14 l8 11 CW 1Z"CCW l6"CW lO"CCW

+-

. I 15 123".CW

- - - - - - - - - - - - - - - - ' - 4 __ J_ Welds 1 thru 15: 4.375"T SA302 Grade B Carbon Steel

+-i------,...~

51" Diameter: 92.375";

Circumference: 290.05" 3

WELDS 17 THRU 23: Reference only (welds are cast to 51" vessel)

+-----11 J_~-~ . 2 Support Skirt Weld 16: 1.S"T Carbon Steel Plate to SA516 Grade 70

~ Carbon Stee 1: Diameter: 92. 375";

Ci re umference: 290" Manway Bolting: 16-1.875" Dia.

  • 28 t

11 8.0" Length 2-11 Rev. 3

____ M~r,..h 27 1 O.Q.

/NSULATIO~

SUPPORT f\lNG'5 PORV SUPPORT RING WELo*,s ~---- CONNECTION BE.HIND PRE.S~URIZER SUPPORT WELOE.D (TYP)

INSULATION 5UPPORT 150 (FOR STUDY OF INT£.RFE.RE.~C£.S WITH IS I NOE. OF PRE.S~URIZ£R WE.LOS "'7 t IS)

PRE SSURIIER IN5ULATION SUPPORT.

2-12 Rev. 3 March 27. 1987

  • PRESSURIZER~~

f W£L D A/0. 15 INSULATION I~*

SUPPORT RING,.-...._...;

!-PORV I SUPPORT

  • IZ" /2..

WE LO IN SPEC. T ION AREA***

.l SE_C,T\ON A-A N. T. S.

JW5 PR£5SUR.1Z£R INSULATION SUPPORT Rev. 3 DATE: 2-13 March 27, 1987

\__ INSULATION SUPPORT RING,

  • PRE~SUR.1 'ZER 5ECT)ON B - B N.T S.

PR£5SUR\l£R INSULATION SUPPORT DATE: 2-14 Rev. 3 L. /. ?-_tt? tf..., ,.... . (). 7

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 Number 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 eighty percent of the critical flaw as described in ASME Section XI IWB-3000 Acceptance Standard for Flaw Indications, has

  • been induced into a mock-up satisfactorily interface.

block. This flaw has detected and distinguished from the bimetallic Demonstration of both capabilities at the Westinghouse Waltz Mill Calibration Facility have been found acceptable by,the Authorized been 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 .

Sl-002 2-15 .Rev. 3 March 27, 1987

RELIEF REQUEST NO. SR-007 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL 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 nozzles with full penet~ation 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 straight beam ultrasonic method from the nozzle bore, the remaining examinations required to be conducted 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 interferences. 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 ultrasonic examination method. In addition, high radiation levels on primary system nozzles would expose radiographic film, causing it to "fog" beyond acceptable standards
  • Sl-002 2-16 Rev. 3 March 27. 1987

III. ALTERNATE PROVISIONS.

1) The five 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 refueli~g outage.
2) The lower pres~urizer 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 outlet 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 *inspectfon 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 restarted temperature.

the 1986 refueling outage after the unit had and reached normal operating pressure The remaining two main steam nozzles will be and 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

  • Sl-002 2-17 Rev. 3 March 27, 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 and 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. Since the nozzle side is in the rough as-cast condition, ultrasonic examination is limited to the weld and this machined ar~a of the pipe.

III. ALTERNATE PROVISIONS 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 of the weld .

Sl-002 2-18 Rev. 3 March 27, 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 from two halves of 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 available technique for volumetric examination. Due to the wall thickness, two-inch thick splitter plates, and higq 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 .

Sl-002 2-19 Rev. 3 March 27, 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 examination will be performed to the in addition to the surface examination
  • extent practical Sl-002 2-20 Rev. 3 March 27, 1987

RELIEF REQUEST NO. SR-011 I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS The Code_ requires that bolting greater than two inches in diameter in Category B-G~l 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 for the sole 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 .

Sl-002 2-21 Rev. 3 March 27, 1987

RELIEF REQUEST NO. SR-012 I. IDENTIFICATION OF COMPONENTS AND 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

  • Sl-002 2-22 Rev. 3 March 27, 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.21 and CS.22 be examined volumetrically and by surface examination in accordance with subsection IWC-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 t~

fitting, access restrictions as outlined above occur on both sides of the weld *

  • III. ALTERNATE PROVISIONS A volumetric examination will be performed to practical in addition to the surface

-, examination.

the extent Sl-002 2-23 Rev. 3 March 27, 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 ASHE 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 been proven to provide data collection/data acquisition capabilities 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 storage of data in lieu of magnetic tape and*

strip chart recorders.

III. ALTERNATE PROVISIONS The MIZ-18 data acquisition/data collection system will be utilized for steam generator eddy current examination .

Sl-002 2-24 Rev. 3 March 27, 1987

Descriptions of changes between Revision 1 and Revision 3 for the Surry Unit 1 Inservice Inspection Program for Component Supports are provided below. The page numbers refer to Revision 3.

Description of Change 3-1 Entire section (1 page) replaced Note that revision bars are not included in Section 3 because the entire Section was replaced.

Sl-003-3 March 27, 1987

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 INSERVICE INSPECTION PROGRAM

  • FOR COMPONENT SUPPORTS Sl-003-3 3-1 Rev. 3 March 27, 1987

SECTION 3 TABLE OF CONTENTS 3.0 INSERVICE INSPECTION PROGRAM FOR COMPONENT SUPPORTS

3.1 INTRODUCTION

3.2 SUPPORTS EXEMPT FROM EXAMINATION AND TEST 3.3 SUPPORT 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 Inser.vice 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 Sl-003-3 3-2 Rev. 3 March 27, 1987

  • 3.0 INSERVICE INSPECTION PROGRAM FOR COMPONENT SUPPORTS

3.1 INTRODUCTION

This program will provide rules and requirements for inservice inspection, repair and replacement of Class 1, 2 and 3 component supports in accordance with ASME Section XI, 1980 Edition through the 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.

The component supports that are within the ASME Section XI piping class boundaries and are within the scope of the Show Cause Order regarding the I & E Bulletin 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 this program.

3.2 SUPPORTS EXEMPT FROM EXAMINATION AND TEST The following exemptions are for ASME Class 1, 2, and 3 component supports:

3.2.1 Component supports that are outside the scope of the Show Cause Order regarding the I & E Bulletin 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 that 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 .

Sl-003-3 3-3 Rev. 3 March 27, 1987

3.3 SUPPORT 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 retaining 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 fn intervening element shall include the attachment portion of the intervening element to pressure retaining components, integral

  • and nonintegral attach~ents 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 boundaries for the support as above for inspections *

  • 1 Attachment portion includes welds, bolting, pins, clamps, etc.

Sl-003-3 3-4 Rev. 3 March 27, 1987

3.4 INSPECTION SCHEDULE

  • 3.4.1 INSPECTION PROGRAM The component supports will be inspected over a 10 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 occurred 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. Corrections to nonrelavent conditions shall not apply.

,(c) If the reexaminations required by (b) above do not require additional corrective measures during next three successive periods on Class 1 or 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 innnediately adjacent

  • component supports.

Sl-003-3 3-5 Rev. 3 March 27, 1987

  • Bu,ldrng structure Suppon w1tll or 111111h0u1 Pressure retaining componen1 inttrmtd1a1t welded ,o,nu lal © ln11gr1I m1chn,-n1 IUPDOl"l 1-lded) 1..

IWF Suppc,n J .!.

IWB, IWC. IWD, or IWE J *I exam. boundary eum. boundary_

Pre11ure Building nnaining nructure Suppon with or without component imerrnecl i11e non-lded conc;on I l-----.t-1 (bl

© @ @

f..,______.:

Nonantegral Integral ettachment

-support least or forged I 1~ IWF Suppon _J . *I.

IWB. IWC, IWD. or IWE ~

J .,

eum. boundary a.um. boundary .

Pressure Building rtt1ining struaure component Suppon with or without intermediate -lded joinu le)

© @

Non integral Integral m1ehmen1 auppon least or forged I 1

IWF S~P&>Oft _j l.--...-.

IWB. IWC, IWD. or IWE j .. ,

1a1m. bound1ry ea1m. bouncllry ILLUSTRATIONS OF TYPICAL SUPPORT EXAMINATIO~ BOUNDARIES

  • Figure lA Rev. 3 3-6 March 27, 1987

Preuure Build,n; rwta1n1n; ltrUC1Ur! component Suppen with or withou1 intermed11te -lded joints (di

© @ © lnngral Noninte1jr1l 1uppon suppon 1..

IWF Suppon exam. boundary

..1 Preaure

  • Building retaining nruc:ture component (1)

© Nonintegrai 1uppon t @

t @

Non integral suppon IWF Suppc,rt exam. boundary I 14 ..-1 ILLUSTRATIONS OF TYPICAL SUPPORT EXAMINATION BOUNDARIES CCONT'Dl Figure lB

  • Rev.* 3 3-7 March 27, 1987 7

Integral attachment

' r l --

IWB Boundary Surf. axam . .,.. A

  • 8 and C. C INTEGRAL ATIACHMENT WELD CODE CLASS 1 Figure 2A
  • 3-8 Rev. 3 March 27, 1987

4 - C.n. forged or weld built-up int~rill attachment

  • A

' C,rcumf_erential

,L

't. _,d ---4--~~;~>-.,,.c..+-

D C

-... IWB Boundar~

Surf. ***m. *raa A

  • D arid B
  • C GENERAL NOTE:

A ll'Olumetric e**mination of volume A - B - C - D from one aide IB - Cl of the circumferential weld mav be performed in lieu of the ,unac:e eumination, ..

  • SUPPORT CIRCUMFERENTIAL WELD JOINT CODE CLASS 1 Figure 2 B Rev. 3 March 27, 1987 3 9

Pressure retaining component l C

  • 1ru A - B A D Surf. exam.

1reaC-D IWB B0und1rv Suppon lug INTEGRAL ATIACHMENT CODE CLASS 1 Figure 2 C

  • Rev. 3 3-10 March 27, 1987
  • Component -----..A

% in. 111 eround

~. I r

% in.

L.- Component "B

.f A I I

-I D lnte;r1I 1tachment I 'I., in. 'I., in.

B C B

_ lntegr1I 1tuchment r

A  % in.all IWC 6ound.1rv (al Examination 1urfacH A - Band C - D around (bl Ex1min1tion 1urf1ces A - B

~

  • Component

'h ,n. Component

'h in_ beyond weld area B

'h in.

lntegr1I I Integral 11nacnment A

1tachment IWC Bounoa*)

IWC Boundary icl Examination Miriaces A - B (di Examination 1urf1ces A - B INTEGRALLY WELDED ATTACHMENTS CODE CLASS 2 Figure 3 Rev. 3 3-11 March 27, 1987

Component Componrn1 t

r r

--T

---IWO _ _J_ r Boundary Suppon IWO Boundary

__J_

la) (bl r Componen, r----

Compon1n1 t

I IWO Boundary Cweld length I I

Suppon Suppon IWO I Boundary le) (di Support Lugs 1wo~

Boundary I

Lesser of [ or r IWO Boundary l*ser of £or r

' - . Component Anacnment

,., (fl INTEGRAL ATTACHMENT - COMPONENT SUPPORTS CODE CLASS 3 Figure 4 Rev. 3 Ifarch 27, 1987 3-12

(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.

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 Requ-irements 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 reactor vessels removable core support structures are included in the NDE program. The remaining portion of the support will be included-in this program.

NOTE 2: 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, 10CFR50 Test will be performed

  • Sl-003-3 3-13 Rev. 3 March 27, 1987

TABLE 1 REQUIREMENTS FOR COMPONENT SUPPORTS EXAMINATION CATEGORIES CAT.

F-A PLATE AND SHELL TYPE SUPPORTS Examination

. . . 1 ITEM Parts Requirements/ Exam1nat1on Acceptance Extent Frequency of NO. Examined Fig. No. Method Standard of Examination Examination Fl.10 Mechanical connections Fig lA,B Visual, VT-3 Section 3.6 Section 3.2 Each inspection to pressure retaining Section 3.3 interval components and building structure Fl.20 Weld connections to Fig lA,B Visual, VT-3 Section 3.6 Section 3.2 Each inspection building structure Section 3.3 interval Fl.30 Weld and mechanical Fig lA,B Visual, VT-3 Section 3. 6 Section 3.2 Each inspection connections at inter- Section 3.3 interval mediate joints in multiconnected integral and nonintegral supports Fl.40 Component displacement Fig lA,B Visual, VT-3 Section 3.6 Section 3.2 Each inspection settings of guides and Section 3.3 interval stops, misalignment of multiconnected integral supports, assembly of support items NOTE:

(1) Reference IWA-2210.

Sl-003-3 3-14 Rev. 3 March 27, 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 3.6 Section 3.2 Each inspection to pressure retaining Section 3.3 interval components and building structure F2.20 Weld connections to Fig lA,B Visual, VT-3 Section 3.6 Sectipn 3.2 Each inspection building structure Section 3.3 interval F2.30 Weld and mechanical Fig IA,B Visual, VT-3 Section 3.6 Section 3.2 Each inspection connections at inter- Section 3.3 interval mediate joints in multiconnected integral and nonintegral supports F2.40 Component displacement Visual, VT-3 Section 3.6 Section 3. 2 Each inspection settings of guides and Section 3.3 interval stops, misalignment of multiconnected integral supports, assembly of support items NOTE:

(1) Reference IWA-2210.

Sl-003-3 3-15 Rev. 3 March 27, 1987

TABLE 1 REQUIREMENTS FOR SOMPONENT 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 Ex?mination F3.10 Mechanical connections Fig lA,B Visual, VT-3 Section 3.6 Section 3.2 Each inspection to pressure retaining Section 3.3 interval components and building structure F3.20 Weld connections to Fig lA,B Visual, VT-3 Section 3.6 Section 3.2 Each inspection building structure Section 3.3 interval F3.30 Weld and mechanical Fig. lA,B Visual, VT-3 Section 3.6 Section 3.2 Each inspection connections at inter- Section 3.3 interval mediate joints in multiconnected integral and nonintegral supports F3.40 Component displacement Fig lA,B Visual, VT-3 Section 3.6 Section 3.2 Each inspection settings of guides and Section 3.3 interval stops, misalignment of multiconnected integral supports, assembly of support items F3.50 Spring type Supports, Fig lA,B Visual, VT-i Section 3.6 Section 3.2 Each inspection constant load type Section 3.3 interval supports NOTE:

(1) Reference* IWA-2210.

(2) See Relief Request SH-001.

Sl-003-3 16 Rev. 3 March 27, 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 3.4 shall be evaluated by comparing the results of examinations with the evaluation standards specified in Section 3.6.3.

3.6.1.2 Acceptance 3.6.1.2.1 Acceptance by Examination Component supports whose examination reveals no unacceptable conditions listed in 3.6.3.1.a shall be acceptable 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 accordance with ASME XI Appendix A, 1980 Edition through the Winter 1980 Addendum as modified by this program, to determine if the component that contains in 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 REEXAMINATION Repairs and reexaminations shall comply with the requirements of Section 3.7. Reexaminations shall be conducted in accordance with the requirements of Section 3.4 and the recorded results shall demonstrate that the repair meets the acceptance standards of Section 3.6.3.

3.6.3 ACCEPTANCE STANDARDS 3.6.3.1 Acceptance Standards - Component Support Structural Integrity Sl-003-3 3-17 Rev. 3 March 27 1987

(a) Component support conditions which are unacceptable for

  • continued service shall include the following:

(1)

(2)

Deformations or structural degradations fasteners, springs, clamps or other support items.

Missing, detached or loosened support items.

of (3) Arc strikes, weld spatter, pajnt, scoring, roughness or general corrosion on close 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)

(6)

Roughness or general corrosion which does not reduce the load bearing capacity of the support.

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.

3.7. REPAIR PROCEDURES 3.7.1 MATERIALS Material shall conform to the requirements of original Design Specification or ASME Section III. All material will be Category I as per Nuclear Operations Department Standards Manual (NODSM).

Sl-003-3 3-18 Rev. 3 March 27, 1987

3.7.2 WELDER 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 3.6.3 of this procedure and the Non-Destructive Examina.tion Manual for Surry.

3.7.4 REPAIRS All repairs will be performed to ensure the support is left in the same condition of the original design, or an evaluation will be performed to ensure that the 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; (3) Name of the components and descriptions, including size, capacity, material, location, and drawings to aid identification; (4) Name and address of manufacturers, where applicable; (5) Manufacturer's component identification numbers, where applicable; (6) Date of completion of the examination, test, replacement, or repair; Sl-003-3 3-19 Rev. 3 March 27, 1987

  • (7)

(8)

Name of Inspector who witnessed or otherwise verified the examinations, test, replacements; *or repairs, and the Inspector's employer and business address, when required; Abstract of .examinations, test, replacements, or repairs performed; conditions recorded; and corrective measures recommended or taken; (9) Signature of Inspector, when required; and (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. Records will be maintained for the life of the plant .

Sl-003-3 3-20 Rev. 3 March 27, 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 discontinuities in the reproduction .

Sl-003-3 3-21 Rev. 3 March 27, 1987

RELIEF REQUEST NO. SH-001

  • I. IDENTIFICATION OF COMPONENTS AND IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter 1980 Addendum, descriges visual examinations in IWA-2210 of the code. Examination VT-3 (IWA-2213) and examination VT-4 (IWA-2214) are utilized for inspection as described in subsection IWF table 2500-2 for category F-C supports.

Relief is requested from the requirement of a VT-4 examination (IWA-2214) due to unnecessary and impractical duplication.

II. BASIS.FOR RELIEF The VT-4 examination is only required for support examinations on category F-C components (spring hanger, snubber etc.), where operability and functional adequacy need to be determined. It was recognized by the Code that these examinations (VT-3, VT-4) were closely related, and generally performed by the same individual qualified to each discipline. Although not endorsed in 10CFRS0.55a, the Winter 1984 Addenda of the Code combined the VT-3 and VT-4 examinations to a singular VT-3 examination. Applying this -

reduction administratively, would reduce qualification documents, examination records, review requirements, and reporting without eliminating the intent of the examination .

III. ALTERNATE PROVISIONS It is proposed that the definition of a VT-3 examination as written in the Winter 1984 Addenda be substituted for the current VT-4 requirement. This definition follows; Winter 1984 IWA-2213 Visual Examination VT-3.

a) The VT-3 visual examination shall be conducted to determine the general mechanical and structural condition of components and their supports, such as the .verification of clearances, settings, physical displacements, loose or missing parts, debris, corrosion, wear, erosion, or the loss of integrity at bolted or welded connections.

b) The VT-3 examination shall include examinations for conditions that could affect operability or functional adequacy of snubbers, and constant load and spring type supports.

c) For component supports and component interiors, the visual examination may be performed remotely with or without optical aids to verify the structural integrity of the component .

Sl-003-3 3-22 Rev. 3 March 27, 1987

Descriptions of changes between Revision 1 and Revision 3 for the Surry Unit 1 Pump and Valve Inservice Test Program are provided below. The page numbers refer to Revision 3.

Description of Change 4-2 The Section has been renumbered.

Section 4.2, "Program Description" has been added.

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.

4-5 The phrase "relief request which are" was replaced by J "exceptions as".

4-6 The word "shall" was replaced by "should 11 in Sections 4.3.2 d) and e).

The word "administrative 11 was deleted, Surry Unit 1 is currently in the second inspection interval

  • The verb tense in Section 4.3.3 has been changed accordingly.

4-7 Drawing 11448-FM~84A was replaced by 11448-FM-84B for Pumps 1-RS-P-lA, lB, 2A and -2B.

4-8 Pump numbers EE-P-A, D and F were changed to 1-EE-P-A, D and F.

4-8 Section 4.3.5 was expanded to explain the pump table headings and 4--9 and abbreviations.

4-10 NR (not required) was replaced by NA (not applicable) throughout the Pump Inservice Test Table.

Relief Request 13 was added to Pumps 1-Sl-P-lA and lB, l-RS-P-2A and 2B, and 1-RH-P-lA and 2B.

Measurment of flow in Relief Request 4 was withdrawn from Pumps l-RS-P-2A and 2B.

Relief Request O was delete_d from Pump l-FW-P-2 (pump speed is being measured) .

The note(*) was deleted from the bottom of the page .

S1-004a-3 March 2 7, 19 8 7

Description of Change 4-11 Relief Request 13 was added to Pumps l-CH-P-2A and 2B

  • Relief Request 14 was added to and Relief Request 10 withdrawn from Pumps l-CC-P-2A and 2B, and 1-SW-P-lOA and

!OB.

In' the columns for Inlet Pressure, Differential Pressure and Lubrication, Q (quarterly testing) was replaced by NA for Pumps 1-EE-P-lA, lD and lF to accurately reflect the contents of the relief requests.

Class 3 was replaced by NC (non-class) for Pumps 1-EE-P-lA, 1D and lF.

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 pressure 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.

4-42 The sentence, "These pumps are not engineered safety feature pumps", was deleted.

4-24 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 Discharge pressure was deleted from alternate proposed testing and a note was added.

  • 4-27 References to lubrication level and pressure were deleted.

The sentence, "Hence all testing of these voluntary", was deleted from the Basis For Relief.

pumps is S1-004a-3 -'2- March 27, 1987

Page Description of Change

  • 4-27 4-29 4-30 The alternate added.

testing proposed Relief Request 13 has been added.

Relief Request 14 has been added.

was changed and a note was 4-31 Relief Request 15 has been added.

4-32 The paragraphs on leak rate testing were rewritten.

The paragraph on stroke times of solenoid controlled, air operated valves was rewritten.

4-34 Surry Unit 1 is currently in the second inspection interval.

The verb tense has been changed accordingly.

Reference to a training program was deleted.

The designation for non-class valves was changed from"-" to "NC".

The sentence, "Valves marked with an "E" are passive valves.", was added.

4-35 Fail-safe (FS) Test was added.

4-36 Valve Numbers SOV-MS-102A and B were replaced by PCV-MS-102A and Band FS was added to Test Required.

4-37 Relief Request 34 has been added to Valve Number TV-MS-110.

Valves NRV-MS-102A, Band C were added.

4-38 Drawing Locations were changed for valves TS-SV-102A and 1-VP-12.

Category for l-VP-12 was changed from AC to ACE.

4-39 Valve RV-1322 was moved from Drawing No. 11448-FM-SSA to 11448-FM-66B.

Code Class NC was added.

4-41 Drawing Locations for *Valves 1-FW-272, 273, 309 and 310 were changed.

The Function description for Valve 1-FW-272, 273, 309 and 310 were rewritten and the Code Class changed from "3" to "2".

4-42 The System Name was changed.

Relief Request 6 has been withdrawn from Valves MOV-SW-103A, B, C and D.

S1-004a-3 March 27, 1987

Description of Change 4-43 The System Name was changed .

  • The Code Class for Valves MOV-CW-lOOA, B, C and D was changed from "3" to "NC".

The Category for Valves l-SW-206 and 208 was changed from "A" to "AE".

4-44 The. Drawing Locations for Valves l-SW-113 and 108 were changed.

4-45 The Code Classes for Valves l-CC-176, 177; l-CC-1, 58, 59; TV-CC-105A, B, C; TV-CC-107; and TV-CC-109A, B were changed from "2" to "3".

The Valve Sizes for RV-CC-116A, Band C were changed from "l" to "l 1/2".

The valve Size for RV-CC-118 was changed from "l" to ."3/4".

Relief Request 34 was added to Valves TV-CC-105A, B, C, D*,

TV-CC-107; and TV-CC-109A, B. Test FS was added to TY-CC-109A, B.

4-46 The Code Classes for Valves l-CC-242, 233, 224; and

  • TV-CC-llOA, B, C were changed from "2" to "3" .
  • 4-47 4-48 Thermal Relief Valve.s RV-CC-llO, 109 were deleted from the program. Thermal Relief Valves are not subject to Section XI testing.

Valve RV-CC~l2.J was replaced by Valve RV-CC-122.

4,...50 The Categories for Valves l-SA-62 and 60 were changed from "A" to "AE".

4-51 The Drawing Locations for Valves TV-IA-101A, B; TV-IA-100, l-IA-446 and 2-IA-446 were changed.

Relief Request 34 was added *to Valves TV-IA-lOlA, Band TV-IA~lOO.

The Size for Valves TV-IA-lOlA, B was changed from "2" to "3".

The Category for Valves l-IA-446 and 2-IA-446 was changed from "A" to "AE".

Note that the valves on page 13 of Revision 1 were moved from drawing 11448-FM-75C to 11448-FH-75J and that they

  • now appear on page 4-53 of Revision 3 .
  • S1-004a-3 March 27, 1987

Description of Change

  • '4-52 4-53 Code Class "NC" was added to Valves SV-BR-100, RV-BR-120 RV-BR-108.

Code Class RV-BR-ll*5. -

"NC" was added to Valves SV-BR-101A, and Band 4-54* Relief Reqtiest34 was added to the valves on. this page.

.I 4-55 Category and Actuator Type were changed from "A" and "PN" to*

"AE" and "Man" for Valve l-VA-1.

Relief Request 34 was added to the valves on this page except for l-VA-1.

4-56 Normal Positions for Valves TV-DA-lOOA and 108A were changed from "C" to "OC".

Categqry for Valve-1-VA-6 was changed from "A" to "AE".

Valve Types for Valves TV-DA-lOOA and 108A were changed from "GN" to "GA"~

Relief Request 34 was added to the valves on this page except for l-VA-6 *

    • 4-57 The System Name was changed.

Valves MOV-RS-155A, B; MOV-RS-156A, B; and 1-RS-11, 17 were moved to Drawing No.* 11448-FM-84B on page 4-60.

The Drawing Locations for the valves on this page were changed.

The Category for Valves l-CS-105, 127 was changed from "AC

to "C".

The Valve Type and Normal Position for Valves MOV-CS-103A, B,

.C and D were changed from "BF" and-"O" to "GA" and "C".

4-58. The Drawing Locations for. the valves on this page were changed.

The Valve Type for Valves MOV~RS-156A, B was changed* from "GA"* to ."BF".

4-59 The Normal Position for Valves TV-LM-lOOA to H was changed from "C" to "O".

The Category for Valves HCV-CV-100 and 1-CV-,,2 was changed from-"A" to "AE" .

  • . Relief Reque!'lt* 34 *was TV-CV-150A to D.

added to Valves TV-LM-lOOA to Hand S1-004a-3 March 27, 1987

Description of Change 4-60 The Category and Valve Type for Valves HCV-1556A, B, C were

  • changed from "A" and "GA" to "AE" and "PL" .

The Actuator Type for Valves SOV-RC-lOOA-1,-2 SOV-RC-lOOB-1,-2 was changed from "PN" to "SOV", and "GA" was added-to Valve Type.

and 4-61 Valve Number l-RC-160. was changed to l-PG-65.

The Valve Type for Valves PCV-1456 and 1455C was changed from "GA" to "PL" and Relief Requests 34 and 35, and Test FS were added.

Valve Type "GA" was added to Valves SOV-RC-lOlA-1,-2 and SOV-RC-lOlB-1,-2, and Actuator Type was changed from "PN" to II SOV".

4-62 Size for Valves MOV-1700 and 1701 was changed from "4" to "14".

Category for Valve MOV-RH-100 was changed from "A" to "AE".

4-64 Code Class for Valve MOV-1381 was changed from "2" to II}"

  • Relief Request 34 was added to Valve TV-1204.

Size for Valve RV-1209 was changed from "3" to "2".

4-65 Size for Valves MOV-1289A, B was changed from "4" to "3".

Category for Valve MOV-1289B was changed from "A" to "B", and the leak test "LT*" was deleted from Test Required.

Category for Valve FCV-1160 was changed from "A" to "AE" and the stroke test "EV" was deleted from Test Required.

4-66 Relief Request 34 was added to' Valves HCV-1200A, B, C.

Code Class and Category for Valve! RV-1382A were changed from "1" and "AC" to "2" and "C", and reference to Relief Request 30 was deleted.

Valve 1-CH-309 was added.

4-67 Drawing Locations for Valves*MOV-1863A, B; MOV-1885A, B, C, D were changed .

  • S1-004a-3 March 27, 1987

Description of Change

  • 4-68 Category for Valves, MOV-1864A, B was changed from "A" to "B" and the test "LT*" was deleted from Test required.

Drawing Locations for Valves l-SI-61, 53 were changed.

Valves MOV-1867A, B were deleted and Relief Request 25 was withdrawn.

4-69 Valves TV-1884A, B, C and RV-1857 were deleted.

Relief Request 34 was added to Valve TV-SI-100.

Category for Valves l-SI-73, 32, 150 and 174 was changed from "A" to "AE".

Size for Valve l-SI-150 was changed from "l" to "3/4".

Valves TV-SI-102A, B; l-SI-25; and l-SI-410 were moved from Drawing No. 11448-FM-106C to 11448-FM-89A and their Drawing Locations were changed. Drawing_ No. 11448-FM-106C was deleted *.

4-70 Drawing Location for Valve l-SI-240 was changed.

Relief Request 30 was added to Valves l-SI-107, 109, 128, 130, 145 , 147 and l-SI-241, 242, and 243 to correctly reflect the contents of the Relief .Request.

Category for Valves.l-SI-235, 236, 237 was changed,from "AC" to "C".

4-71 Relief Request 34 was a.dded to Valves TV-SI-lOlA, B.

4-72 Valves TV-GW-100 to 107, and TV-GW-lllA, B were moved from Drawing No. 11448-FM-90A to 11448-FM-90C.

Code *class "NC" was added tQ Valves RV-GW-lOOA, B; RV-GW-102A, B; and RV-GW-103.

4-73 Code Class "NC" was added and Size changed from "3/4" to "1" for Valve RV-GW-107.

4-74 Drawing Locations were changed for the valves on this page.

Relief Request 33 was added to the valves on this page *except for valves TV-GW-lllA, B.

Relief Request 34 was added to the valves on this page.

4-75 Category was changed from "A" to "AE" for the valves on this page.

S1-004a-3 March 27, 1987

Page Description of Change 4-76

  • Relief Request 34 was added to the valves on this page .

4-77 Relief Request 34 was added to Valves TV-RM-lOOA, B and c.

4-78 The Code Class and Actuator Type were change from "3" and "PN" to "NC" and "SOV" for the valves on this page.

Relief Request 36 was added and Test "VP" was deleted.

4-79 Category was changed from "A" to "AE" for the valves on this page.

Size for Valve MOV-VS-102 was changed from "8" to "18".

Size, Valve Type and Actuator Type for Valve MOV-VS-101 were changed from "4", "GA" and "Man" to 11 8 11 , "BF" and "MOV".

4-80 Valves l-FP-151 and 152 were placed on Drawing* No.

11448-FB-47B.

Drawing Locations and Size were added.

Code Class and Category were changed from "2" and "A" to "3"

  • and "AE".

4-81 Valves SOV-EG-lOOA, Bon Drawing No. 11448-FB-46A were added along with Relief Request 37.

4-82 Valves S0V-EG-300A, Bon Drawing No. 11448-FB-46C were added along with Relief Request 37.

4-84 Relief Request 1 was reformatted to be consistent with the other Relief Requests.

4-85 Valve RV-1893 was deleted from ReJief Request 1.

4-85 and Code Class "NC" was added to Valves SV-BR-100, RV-BR-120, 4-86 RV-BR-108, SV-BR-101A&B, RV-BR-115 and RV-1322.

4-86 Code Class for RV-1382A was changed from "l" to "2".

Code Class "NC" was added to Valves RV-GW-lOOA,B; 102A,B; 103 and 107.

4-88 Valves NRV-MS-102A, Bang C were added.

4-89 Editorial change.

4-90 Valve Number l-FW-59 was changed to l-FW-89.

Code Class for Valves l-FW-272, 273, 309 and 310 wa:s changed

  • S1-004a-3 from "3" to "2" and the Function description was rewritten .

March 27, 1987

Description of Change

  • 4-91 4-92 Technical detail was added to the Basis For *Relief ..

The test frequency was changed from every every reactor refueling.

Relief Request 6 has been withdrawn.

cold shutdown to 4-93 Editorial change.

4-94 Code Class for Valves l-CC-176, 177 changed from "2" to "3".

4-95 Editorial change.

4-96 Code Class changed from "2" to "3" for the valves on this page.

4-97 Editorial change.

Technical detail added* to the Basis for Request.

4-98 Valve.number l-RC-160 changed to l-PG-65.

4-102 Technical detail was added to the Basis for Request.

4-104 Editorial change .

  • 4-105 4-106 4-108 Technical detail was added to the Basis for Request.

The Code Class was changed from "2" to "l".

The Category for MOV-1289B was changed from "A" to "B".

4-110 Editorial changes.

4-112 Technical Specification reference changed from. 3.3.A.9 to 3.3.A.8.

Editorial changes.

4-114 The Basis for Request was changed from reference to flow blockage due to boron crystallization to excess charging flow causing a reactivity transient.

4-115 Relief Request 25 has been withdrawn.

4-116 Category was changed from "C" to "A and C".

Editorial change was made to the Basis for Request.

4-117 Editorial changes.

4-121 Rel.ief Request 30 was refo~matted to be consistent with the other Relief Requests.

- S1-004a-3 March 27, 1987

Page Description of Change 4-122 Valve RV-1382A was deleted. Valves l-SI-235, 236 and 237 were

  • deleted and Valves 1-SI-241, 242, and 243 were added.

4-125 Relief Request 33 has been added.

4-126 Relief Request 34 has been added.

and 127 4-128 Relief Request 35 has been added.

4-129 Relief Request 36 has been added.

4-130 Relief Request 37 has been added.

  • Sl-004a-3 March 27, 1987

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1

  • INSERVICE TESTING PROGRAM PLAN FOR PUMPS AND VALVES
  • Sl-004a-3 4-1 Rev. 3 March 27, 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

  • Sl-004a-3 4-2 Rev. 3 March 27, 1987

4.0 INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES

4.1 INTRODUCTION

This Pump and Valve Inservice Test Program Plan is applicable to the Surry Power Station Unit 1. 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 *

  • - Sl-004a-3 4-3 Rev. 3 March 27, 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 IWV 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 the program plan attached *

  • S1-004a-3 4-4 Rev. 3 March 27, 1987

4.3 PUMP INSERVICE TEST PROGRAM DESCRIPTION 4.3.1 PROGRAM DEVELOPMENT PHILOSOPHY

  • Highly reliable safety-grade equipment consideration in the operation of a nuclear station.

is a To help.assure operability, the Surry Power Station Unit 1 Pump Inservice Test Program has been developed,'

The Program is designed to detect and evaluate .significant vital generating

  • 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 ASME B&PV Code, Section XI, Subsection IWP, 1980 Edition with Addendum through Winter of 1980; 10CFR50.55a(g); and NRC Staff guidelines for C!)mplying with certain provisions of 10CFR50.55a(g) "Inservice Inspection

,Requirements."

The Nuclear Regulat'ory Commission and Code Committee recognized that design. differences among plants may render impractical certain Code requirements. Where such impracticalities exist,. they have been substantiated as.

exceptions as allowed by the Code. Alternate testing

. requirements have been proposed when warranted, -1 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 1 Inservice Test Program provides a schedule for testing safety-grade pump~ an'd will be implemented as part of normal periodic surveillance testing.*

Reference data will be gathered during initial surveillance tests. In most cases, test parameters will be measured with normal plant instrumentation. This approach will simplify the

  • test program and will promote timely completion of periodic surveillance testing~ When* permanently installed instrumentation is not available, portable. instrumentation
  • will be used to record the required parameters.
  • During subsequent surveillance tests, flow rate will normally be selected as the independent test parameter and will be set up to match the reference flow rate. .Other hydraulic and mechanical performance parameters will be measured and -

evaluated against the appropriate reference values. The results of such evaluations will determine whether or not corrective action is warrant.ed.

Each pump in the Pump.Inservice Test Program will be tested according to a detailed test procedure. The* procedure will

.include, as minimum:

Sl-004a-3 4-5 Rev. 3 March 27, 1987

a)

References:

This section wil~ identify references applicable to Technical Specifications and other necessary material as drawings .

  • b) c)

Purpose:

This section will identify test objectives.

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 snould 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 r~nges within which test data will be considered acceptable 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 staffs at Surry Power Station are responsible for administration and execution of the Pump Inservice Test Program. The* Program was officially implemented on December 22, 1982 and will govern pump testing for a 120 month period. Prior to the end of the 120 month period, the Program *will be reviewed and upgraded to assure continued compliance with 10CFR50.55a(g)(4). The Program will be updated a minimum of at least once every 40 months for new systems, relief req{iest*, etc.

4.3.4 PUMP REFERENCE LIST This list gives a brief description of each pump identified in ,

~he Pump Inservice Test Program. The pump's ASME Code Classifications are specified in "PUMP INSERVICE TEST TABLES".

Sl-004a-3 4-6 Rev. 3 March 27, 1987

1-CH-P-lA

  • 1-CH-P-lB 1-CH-P-lC High Head Safety Injection or Charging Pumps provide high pressure flow for the Safety Injection System and during normal operation, maintain pressurizer level and seal water injection to the Reactor Coolant Pumps. See drawing 11448-FM-88B.

1-SI-P-lA 1-SI-P-lB Low Head Safety Injec.tion Pumps provides low pressure safety injection to the core for long term cooling and as a backup to accumulators. See drawing 11448-FM-89A.

1-CS-P-lA 1-CS-P-lB Containment Spray Pumps provide a cooled, chemically treated, b_orated spray to reduce containment pressure following a loss of coolant accident. See drawing 11448-FM-84A.

1-RS-P-2A 1-RS-P-2B Outside Recirculation Spray Pumps aid the Containment Spray System in reducing containment pressure rapidly following a loss of coolant accident. See drawing 11448-FM-84B.

1-RS-P-lA 1-RS-P-lB Inside Recirculation Spray Pumps aid the containment spray system in r_educing containment pressure rapidly following a loss of coolant accident. See drawing 11448-FM-84B.

1-FW-P-3A l-FW-P-3B 1-FW-P-2 Auxiliary Feedwater Pumps supply the steam generator with feedwater in the event of a complete loss of normal feedwater. See drawing 11448-FM-68A.

1-RH-P-:-lA 1-RH-P-lB The function of Residual Heat Removal Pumps is to remove heat energy from the core when the Reactor Coolant System is below 350°F. See drawing 11448-FM-87A.

  • Sl-004a-3 1-CC-P-lA 1-CC-P-lB 4-7 Rev. 3 March 27, 1987

Component Cooling Water Pumps are used to supply water to remove heat from the Residuaf Heat Removal System. See drawing 11448-FM-72D

  • l-CH-P-2A l-CH-P-2B Boric Acid Transfer Pumps supply boric acid to suction of charging pump*s via normal coolant boron concentration and emergency makeup. See drawing 11448-FM-88A.

l-CC-P-2A l-CC-P-2B Charging Pump. Cooling Water Pumps provide water to transfer heat from the charging pump mechanical seals. See drawing 11448-FM-71B.

1-SW-P-lOA 1-SW-P-lOB Charging Pump Service Water Pumps provide cooling water for Charging Pump Cooling Water Systems. See drawing 11448-FM-71B.

  • 1-sw-P-lA 1-SW-P.-lB 1:..sw-P-1c
  • Emergency Service Water Pumps supply the required service water to the canal to provide for minimum safeguards operation in the unlikely event of a loss of site power*coincident.with a DBA. See drawing 11448-FM..;..71A.

1-EE-P-lA 1-EE-P-lD 1-EE-P-lF 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 applicab'ie.

  • To aid the reader in interpreting the Pump Inservice Test Table, brief explanations of the table headings* and abbreviations are provided below.

Sl-004a-3 4-8 Rev. 3 March 27, 1987

1) Pump Number - Each pump in the plant has a unique
  • 11 tag" number
  • 2) which identifies the system to which the pump belongs .

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

  • Sl-004a-3 4-9 Rev. 3 March* 27, 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-CH-P-lA 2 NA Q NA NA Q NA NA Q 0,1,2 1-CH-P-lB 2 NA Q NA NA Q NA NA Q 0,1,2 1-CH-P-lC 2 NA Q NA NA Q NA NA Q 0,1,2 1-Sl-P-lA 2 NA Q NA Q Q NA NA NA 0,1,3,13 1-SI-P-lB 2 NA Q NA Q Q NA NA NA 0,1,3,13 1-CS-P-lA 2 Q Q Q Q Q NA NA Q 0,1*

1-CS-P-lB 2 Q Q Q Q Q NA NA Q 0, 1 l-RS-P-2A 2 NA Q NA Q Q NA "NA NA 0,1,4,13 l-RS-P-2B 2 NA Q NA Q Q NA NA NA 0,1,4,13 1-RS-P-lA 2 NA NA NA NA NA NA NA NA 0,1,5 1-RS-P-lB 2 NA NA NA NA NA NA NA NA 0, 1,5 l-FW-P-3A 3 Q Q Q NA Q NA NA Q 0,1,6 l-FW-P-3B 3 Q Q Q NA Q NA NA Q 0,1,6 l-FW-P-2 3 Q Q Q NA Q NA Q Q 1,6 1-RH-P-lA 2 CSD CSD CSD CSD CSD NA NA NA 0,1,7,13 1-RH-P-lB 2 CSD CSD CSD CSD CSD NA NA NA 0,1,7,13 1-CC-P-lA 3 Q Q Q NA Q NA NA Q 0,1,15 1-GC-P-lB .3 Q Q Q NA Q NA NA Q 0,1,15 Sl-004a-3 4..:.10. Rev. 3 March 27, 1987

Pump Identification ASME Class Inlet Pressure Discharge Pressure Pressure PUMP*INSERVICE TEST TABLE Differential Flow Rate Vibration Bearing Temperature Pump Speed Lubrication Level/Pressure Relief Reques*

l-CH-P-2A 3 NA Q NA NA NA NA NA NA 0,1,9, l-CH-P-2B 3 NA Q NA NA NA NA NA NA 0,1,9, l-CC-P-2A 3 Q Q Q Q Q NA NA NA 0,1,14 l-CC-P-2B 3 Q Q Q Q Q NA NA NA 0,1,14 1-SW-P-lOA 3 Q Q Q Q Q NA NA NA 0,1,14 1-SW-P-lOB 3 Q Q Q Q Q NA NA NA 0,1,14 1-SW-P-lA 3 NA NA NA NA Q NA NA Q 0,1,11, 1-SW-P-lB 3 NA NA NA NA Q NA NA Q 0,1,11 1-SW-P-lC 3 NA NA NA NA Q NA NA Q 0,1,11 1-EE-P-lA NC NA NA NA NA NA NA NA Q 0,1,12 1-EE-P-lD NC NA NA NA NA NA NA NA Q 0,1,12 1-EE-P-lF NC NA NA NA NA NA NA NA Q 0,1,12 Sl-004a-3 4-11 Rev. 3 March 27, 1987

4.3.6 PUMP TEST PROGRAM RELIEF REQUEST Relief Requests identify code requirements which are

  • impractical for Surry Unit 1 and provide justification for the requested exception. Where appropriate, alternate testing to be performed in lieu of the code requirements is proposed *
  • S1-004a-3 4-12 Rev. 3 March 27, 1987

RELIEF REQUEST 0

  • Systems:

Pump(s):

Class Various IWP Program Pumps except l-FW-P-2. See PUMP INSERVICE TEST TABLE.

Section XI Code Requirements For Which Relief Is Requested Quarterly measurements of pump speed.

Basis For Request IWP-4400 does not require pump speed measurement if pump is directly coupled to a constant speed motor driver.

Alternate Testing Proposed None .

  • Sl-004a-3 4-13 Rev. 3 March 27, 1987

RELIEF REQUEST 1

  • Systems: Various Pump(s): IWP 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 problem, but also the equally harmful low amplitude high frequency

~ibrations due to misalignment in balance, or bearing wear that usually go undetected by simple displacement measurements.

In addition, these readings go far beyond the capabilities of a bearing temperature monitoring program. A bearing will be seriously 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 lubrication fluid for some pumps is taken from the process water, which can chang~ temperature depending qn ambient conditions. Data trending for these cases is not meaningful.

Therefore, the detection of possible bearing failure by a yearly temperature measurem.ent 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 .

  • s1:..004b-3 4-14 Rev. 3 March 27, 1987

RELIEF REQUEST 1 (CONT'D)

  • Alternate Testing Proposed Pump vibration measurements will be taken in vibration velocity (in/sec). The evaluation of the readings will be per the attached table. For more infonp.ation, 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 *
  • S1-004b-3 4-15 Rev. 3 March 27, 1987

RELIEF RE'QUEST 1 (CONT'D)

SURRY 1 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 O~Vr ~0.05 0 to 0.075 0.075 to 0.1 >0.1 1

2 V* When 0.05<Vr ~0.1 0 to 0.15 0.15 to 0.2 >O ..2 t 2 3 Vt When O.l(Vr

. ~0.15 0 to 0.2 0.2 to 0.25 * >O. 25 3

4 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.

Sl-004b-3 4-16 Rev.'3 March 27, 1987

RELIEF REQUEST 2

  • System :

Pump(s):

Chemical and Volume Control 1-CH-P-lA 1-CH-P-lB 1-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 press~re instrumentation is not installed nor required, therefore differential pressure can not be calculated. These pumps are capable of producing greater than 2400 psig discharge pressure, while the suction pressure is normally 20 psig. Therefore,. differential pressure developed by the pump is more than 100 times the suction pressure and a 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 flow measurment instrumentation. Installation of the 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 .

S1-004b-3 4-17 Rev. 3 March 27, 1987

RELIEF REQUEST 3

  • System:

Pump(s):

Safety Injection 1-SI-P-lA 1-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 Specification which will insure initial conditions for testing.

Note: A Design Change has been initiateted 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 .

S1-004b-3 4-18 Rev. 3 M'arch 27, 1987

RELIEF REQUEST 4

  • System:

Pump(s):

Recirculation Spray l-RS-P-2A l-RS-P-2B Class 2

    • section XI Code Requirements For Which Relief Is Requested Measure inlet pressure and differential pressure Basis For Request Instrumentation 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 the suction pressure is only the head of water in the filled pump casing.

NOTE: -A Design Change has been initiated for inlet instrumentation, which will allow for the calculation of differentiai pressure. The instrumentation is scheduled for installation in accordance with the Nuclear Operations Department Five Year Plan for Surry Power Station .

Sl-,004b-3 4-19 Rev. 3 March 27, 1987

RELIEF REQUEST 5

  • System:

Pump(s):

Recirculation Spray 1-RS-P-lA 1-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 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 .

Sl,-004b-3 4-20 Rev. 3 March 27, 1987

  • RELIEF REQUEST 6
  • System :

Pump(s):

Feedwater 1-FW-P-3A 1-FW-P-3B 1-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 flow

  • measurement'installation .
  • S1-004b-3 4-21 Rev. 3 March 27, 1987

RELIEF REQUEST 7

  • System:

Pump(s):

Class Residual Heat Removal 1-RH-P-lA 1-RH-P-lB 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 Pump will be tested each cold shutdown (but not more frequently than every three months) .

S1-004b-3 4-22 Rev. 3 March 27, 1987

RELIEF REQUEST 8 Relief Request Withdrawn S1-004b-3 4-23 Rev. 3 March 27, 1987

RELIEF REQUEST 9

  • System:

Pump(s):

Class Chemical and Volume Control l~CH-P-2A l-CH-P-2B 3

  • Sectton XI Code Requirements

'For Which Relief Is Requested Measure inlet pressure, differential pressure, flow, and vibration.

  • Basis For Request
1. No instrumentation installed for inlet pressure, .differential pressure and flow.
2. Pumps are totally encased in insulation. Therefore, probes for vibration cannot be placed in contact with pumps for a reading.*

Alternate Testing Proposed 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. No flow rate measurement device is currently installed.*

  • NOTE: A Design* Change has been initiated for
  • inlet pressure, flow and vibration instrumentat{on.

instrumentation pressure.

will Installation of inlet The instrumentation is scheduled for installation pressure allow for the calculation of differential accordance with the Nuclear Operations Department Five Year Plan for in Surry Power Station *

  • Sl-004b-3 4-24 Rev. 3 March 27, 1987

RELIEF REQUEST 10

  • Relief Request Withdrawn S1-004b-3 4-25 Rev. 3 March 27., 1987

RELIEF REQUEST 11

  • System:

Pump(s):

Service Water 1-SW-P-lA 1-SW-P-lB 1-SW-P-lC Class 3 Section XI Code Requirements For Which .Relief Is Requested Measure inlet pressure, differential pressure arid flow rate.

Basis For Request No installed inlet pressure, differential pressure and flow instrumentation exists. Pumps take suction from James River through seismic structure and discharge through a seismic structure. These restrictions makes it impractical to iristall instrumentation on these pumps.

_Alternate Testing Proposed None, but vibration and lubricant level are monitored which should be adequate indication of pump performance .

    • NOTE: A Design Change has. been initiated
  • for discharge pressure and flow*

instrumentation. The instrumentation is scheduled for installation in accordance with the Nuclear Op~rations*Department Five Year Plan for Surry Po~ei Station

  • Sl...;004b-3 4-26 Rev. 3 March 27, 1987

RELIEF REQUEST 12

  • System:

Pump(s):

Fuel Oil 1-EE-P-lA 1-EE-P-lD 1-EE-P-lF 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 Testing Proposed These pumps will be tested monthly by observing th_at the pumps perform their intended function (fµel oil is flowing to the day tank when the pumps are running) *

  • NOTE: Instrumentation to perform Section XI tests will accordance with the Nuclear Operations Department Five Surry Power Station .

be installed in Year Plan for

  • Rev. 3 S1-004b-3 4-27 March 27, ] 987

INQUIRY AND REPLY AS SENT TO INQUIRER 08/14/81

    • FILE NUMBER BC/77 /666 INQUIRER COMPANY WPPSS SUBJECT SCOPE OF SECTION XI, DIVISION 1 REPLY SENT 78/02/17 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 connnittee 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 Sections XI, Article IWA-1100 on Scope and Responsibility, specifically paragraph IWA-1400, requires the owner of the nuclear plant to determine the appropriate code, class or classes for each component of the nuclear power plant to be examined according to Section XI rules.

  • Sl-004b-3 4-28 Rev. 3 March 27, 1987

RELIEF REQUEST 13

  • Systems:

Pump(s):

Safety Injection, Recirculation Spray, Residual Heat Removal and, Chemical and Volume Control 1-SI-P-lA 1-SI-P-lB 1-RH-P-lA 1-RH-P-lB 1-RS-P-2A l-CH-P-2A 1-RS-P-2B l-CH-P-2B Class 2 for 1-SI-P-lA and B 1-RS-P-2A and B 1-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 Those 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 .

Sl-004b-3 4-29 Rev. 3 March 27, 1987

_______J

RELIEF REQUEST 14

. System: Component Cooling and Service Water

  • Pump(s): l-CC-P-2A l-CC-P-2B 1-SW-P-lOA 1-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 parameters will ensure proper level of lubrication.

Alternate Testing Proposed None .

  • Sl-004b-3 4-30 Rev. 3 March 27, 1987

RELIEF REQUEST 15

  • System:

Pump(s):

Component Cooling 1-CC-P-lA 1-CC-P-lB 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 flow loop which gives enough data for trending purposes .

Sl-004b-3 4-31 Rev. 3

  • 4.4 VALVE INSERVICE TEST PROGRAM DESCRIPTION 4.4.1 PROGRAM DEVELOPMENT PHILOSOPHY Surry Power Station Unit 1 is a Pressurized Water Reactor being operated in compliance with the ASME Boiler and Pressure Vessel Code. The Code requires periodic testing of certain safety related valves in order to verify their operability and physical integrity. The Surry Unit 1 Valve Inservice Test Program satisfies these requirements.

The program will detect potentially adverse changes in the mechanical condition of valves within the scope of Section XI, Subsection IWV of the Code. This includes all valves "which are required to perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of an accident." It is important to note that the scope of ASME Section XI and the Surry Inservice Testing Program for its implementation 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 1 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 1 is committed to meeting the leak rate testing requirements of:

1. 10CFRSO, Appendix J for contaiment 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 its 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 times of solenoid controlled, air operated valves is both extremely rapid and variation.

subject to considerable Exception is taken to complying with stroke time variations defined by Paragraph IWV-3417(a).

Sl-004b-3 4-32 Rev. 3

Virginia Electric and Power Company is confident that the Surry Unit 1 Valve Inservice Test Program complies with the intent of the applicable codes, regulations 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 tests will be conducted as part of the Valve Test Program:

1. Valve Operability Tests
2. Valve Leakage 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 specific 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 tested by observing the valve operation upon loss of actuating power. In most cases, this can be accomplished using normal control circuits.

The following clarification shall apply to those valves which are

  • scheduled to be 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 shutdown and continue until complete or unit is ready to return to power. Completion of the valve testing is not a prerequisite to return to power.

Any testing not completed at one cold shutdown should be performed during the subsequent scheduled cold shutdowns to meet the code specified testing frequency."

Valve Leakage 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 tested (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 with Section 4.09l(a)(2). Other safety and relief valves will be tested in accordance with Section 4.09l(c) (1)

  • S1-004b-3 . 4-33 Rev. 3
  • 4.4.3 PROGRAM ADMINISTRATION The operations and engineering staffs at Surry Power Station are responsible for administration and execution of the Valve Inservice Test Program. The program was officially implemented on December 22, 1982 and g*overns valve testing for a 120 month period. Prior the to end of the 120 month period, the program will be reviewed and upgraded to assure continued compliance with 10CFR50.55a(g)(4). The program will be updated a minumum of at least once every 40 months or for a new system, relief request, etc.

4.4.4 VALVE INSERVICE TEST TABLES The Valve Inservice Test Tables are the essence of the Valve Program to meet ASME Section XI, Subsection IWV requirements. The tables reflect the positions taken in support of the relief requests. To aid the reader in the interpretation of the tables, brief explanations of the table headings and abbreviations are 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) 3)

Drawing Location - The specific coordinates of each valve are supplied to facilitate location of the valves on the flow diagrams provided.

Function - A brief description of the function of the valve.

4) Code Class - ASME Code Class of each valve as per 10 CFR 50.55a and Regulatory Guide 1.26.

NOTE: NC is for non-class valves

5) Category Categories are defined by ASME Section XI.

Subsection IWV. Each valve has specific testing requirements which are determined by the category to which it belongs.

Valves marked with an "E" are passive valves.

6) Size - Nominal pipe diameter to which valve connects is given in inches.
7) Valve Type - The following abbreviations 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 - Diaphragm Sl-004b-3 4-34 Rev. 3.

8) Actuator Type The following abbreviations are used to describe actuator types. Valves 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 and relief valves).

MOV- Motor Operated PN - Pneumatic (Air Operated)

MAN- Manually Operated SOV- Electronic solenoid Operated Valves

9) Normal Position The following abbrevi~tions 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 marked by asterisk(*) will be tested in accordance with Appendix J.

CV - Check Valves shall be exercised at least once every 3 months per section XI, 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 the actuator power.

Sl-004b-3 4-35 Rev. 3

NRV-MS-lOlA D-3 NRV-MS-lOlB D-5 Main Steam Non Return NRV-MS-lOlC D-6 Valves 2 C 30 SCK MOV 0 CV 3 RV-MS-lOlA C-2 RV-MS....:lOlB B-4 RV-MS-101C C-6 Main Steam PORV 2 C 4 RV SA C SP 1 PCV-MS-102A F-8 Main Steam to Turbine 2 B 3 GA PN C EV ,ST None PCV-MS-102B G-8 Driven Aux. FW Pump VP,FS HCV-MS-104 B-4 Decay Heat Release 2 B 4 GA PN C EV,VP 32 Control Valve TV-MS-109 F-7 Main Steam Drain to EV,ST Condenser 2 B 3 GA PN 0 VP None Sl-004bc-3 4-36 Rev. 3 M.,.,,.,..1, ')7 1 Qs:l7

  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Main Steam Drawing No. 11448-FM-64A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request TV-MS-llO E-7 Main Steam Drain to Blow- EV,ST down 2 B 2 GA PN 0 VP 34 l-MS-176 F-8 Main Steam to Turbine l-MS-178 F-8 Driven Auxiliary'FW l-MS-182 F-8 check valves 2 C 3 CK SA C CV None NRV-MS-102A C-3 NRV-MS-102B C-4 Main Steam Non Return NRV-MS-102C C-6 Valves 2 C 3 SCK MAN 0 CV 3 Sl-004bc-3 4-3'7 Rev. 3 M,,.,-,..h ?7 1 QR7
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Aux. Steam and Air Removal Drawing No. 11448-FM-66A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request TV-SV-102A A-5 Air Removal Direct to 2 A 6 GA PN C LT*, EV None Reactor Containment ST, VP Air Removal Direct to l-VP-12 A-5 Reactor Containment 2 ACE 6 CK SA C LT* None S1-004bc-3 4-38 Rev. 3 L_ M-,~~'h '>7 10Q7
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Auxiliary Steam Drawing No. 11448-FM-66B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request Batching Tank Heating RV-1322 D-3 Jacket Relief NC C 2 RV SA C SP 1 Sl-004b~-3 4-39 Rev. 3 M~..-~l, 'l7 1 OR7

"-K- ~* - 1. t') f 1 () ()-,

  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Auxiliary Feed Cross Connect Drawing No. 11448-FM-68B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request MOV-FW-160A J-5 Cross-Connect for Unit #1 EV, ST MOV-FW-160B J-6 Aux. Feed. from Unit #2 3 B 6 GL MOV C VP None l-FW-272 I-8 Check Valves at Cont. Penet.

l-FW-273 I-8 (Cross-connect for Unit 1 2 C 6 CK SA C CV 4 Aux. Feed. from Unit 2) l-FW-309 I-7 Check Valves at Cont. Penet.

l-FW-310 I-7 (Cross-connect for Unit 1 2 C 6 *CK SA C CV 4 Aux. Feed. from Unit 2)

Sl-004b.c-3 4-41 Rev. 3 M::irrh ?7. lqfn

  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Circulating and Service Water Drawing No. 11448-FM-71A.

Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request MOV-CW-106A E-4 MOV-CW-106B E-4 Condenser inlet 3 B 96 BF MOV 0 EV, ST None MOV-CW-106C F-4 Isolation Valves VP MOV-CW-106D F-4 MOV-SW-102A E-6 Service Water to Component EV, ST MOV-SW-102B F-6 Cooling Water Heat Ex- 3 B 42 BF MOV 0 VP None changers MOV-SW-103A B-6 rService Water to Recircu- EV, ST MOV-SW-103B B-6 lation Spray Heat Ex- 3 B 30 BF MOV C VP None MOV-SW-103C D-6 changers MOV-SW-103D E-6 MOV-SW-104A A-2 Recirculation Spray Heat EV, ST MOV-SW-104B B-2 Exchangers Suction Isola- 3 B 24 BF MOV 0 VP None MOV-SW-104C C-2 tion Valves MOV-SW-104D c-2 MOV-SW-105A A-2 MOV-SW-105B A-2 Recirculation Spray Heat EV ,ST MOV-SW-105C B-2 Exchanger Discharge Isola- 3 B 24 BF MOV 0 VP None MOV-SW-105D C-2 tion Valves MOV-SW-106A D-4 Recirculation Spray Heat EV,ST MOV-SW-106B D-4 Exchangers Cross-Connect 3 B 36 BF MOV 0 VP None Valves Sl-004bc-3 4-42 Rev. 3

, r,-, , "n-,

  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Circulating and Service Water Drawing No. 11448-FM-71A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request MOV-SW-lOlA C-7 Bearing Cooling Water EV, ST MOV-SW-lOlB C-7 Heat Exchanger Isolation 3 B 36 BF MDV 0 VP None Valves MOV-CW-lOOA E-2 MOV-CW- lOOB E-2 Condenser Discharge EV, ST MOV-CW-lOOC F-2 Isolation Valves NC B 96 BF MOV 0 VP None MOV-CW- lOOD F-2 l-SW-206 A-2 Containment Isolation l-SW-208 A-2 Valves for Service Water 2 AE 2 GA Man C LT* None Drains to Heat Exchanger Sl-004bc-3 4-43 Rev. 3 M,,-,..,..1-, ?7 1 QA7
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Circulating and Service Water Drawing No. 11448-FM-?lB Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request l-CC-764 D-6 Charging Pump Cooling l-CC-752 G-6 Water Pump Discharge Check 3 C 2 CK SA oc CV None Valve l-SW-113 E-8 Charging Pump Service l-SW-108 I-8 Water Pump Check Valve 3 C 2 CK SA oc CV None Sl-004bc-3 4-44 Rev. 3 M,:,,-,-.h ?7 1 QR7
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Component Cooling Drawing No. l 1448-FM-72A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request RV-CC-119A L-2 Component Cooling from RHR RV-CC-119B L-3 Heat Exchanger Relief 3 C 1 1/2 RV SA C SP 1 Valve l-CC-176 B-1 Component Cooling to RHR l-CC-177 B-1 Heat Exchanger Check Valve 3 C 18 CK SA oc CV 7 l-CC-1 A-2 Component Cooling to l-CC-58 A-2 Reactor Coolant Pumps 3 C 6 CK SA 0 CV 8 l-CC-59 4-2 TV-CC-lOSA D-8 Component Cooling from 3 B 6 BA PN 0 ST 8,34 TV-CC-105B D-8 Reactor Coolant Pumps EV, VP TV-CC-lOSC E-8 Component Cooling from 3 B 2 1/2 GL PN 0 ST 8,34 TV-CC-107 D-8 Reactor Coolant Pumps EV, VP TV-CC-109A F-8 Component Cooling from 3 B 18 BF PN 0 ST, FS 34 TV-CC-109B F-9 RHR Heat Exchangers EV, VP RV-CC-116A B-3 Component Cooling Reactor 3 C 1 1/2 RV SA C SP 1 RV-CC-116B B-5 Coolant Pump RV-CC-116C B-8 RV-CC-124 F-1 Component Cooling 3 C 3/4 RV SA C SP 1 Piping Relief Valve RV-CC-118 G-4 Component Cooling Excess 3 C 3/4 RV SA C SP 1 Letdown Heat Exchanger Relief Sl-004bc-3 4-45' Rev. 3 M~~nl, 'J7 1 OQ7
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Component Cooling Water Drawing No.. 11448-FM-72B Valve Drawing Code Cate..;, Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request l-CC-242 C-4 Component Cooling to l-CC-233 E-4 Reactor Containment Air 3 C 6 CK SA 0 CV 7 l-CC-224 I-4 Recirculation Coolers TV-CC-llOA D-3 Component Cooling from 3 B 6 BF PN 0 EV, ST NONE TV-CC-llOB F-3 Reactor Containment Air VP TV-CC-llOC H-3 Recirculation Coolers Sl-004bc-3 4-46 Rev. 3 M:irch 77. 1 g87
  • Surry Power Station Unit No. 1 Inservice Testing ASHE Code Class 1, 2, and 3 Valves System Name: Component Cooling Water Drawing No. 11448-FM-72C Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request Component Cooling to RV-CC-lllA 1-3 Fuel Pit Coolers 3 C 3/4 RV SA C SP 1 RV-CC-lllB I-4 Relief Valves Sl-004bc-3 4-47 Rev. 3 M~~~l-, ')7 10Q7
  • Surry Power Station Unit No. 1 Ins.ervice Testing ASME Code Class 1, 2, and 3 Valves System Name: Component Cooling Water Drawing No. 11448-FM-72b Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request l-CC-557 C-2 Component Cooling Pump 1-CC-563 C-2 Discharge Check 3 C 18 CK SA oc CV None RV-CC-122 A-1 Component Cooling Surg~ 3 C RV* SA C SP 1 Tank Relief Valve

(

Sl-OQ4bc-3 4-48 Rev. 3 1

"-----l, 'l7 l 007

  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Compressed Air Drawing No. 11448-FM-75E Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request Instrument Air to Contain-l-IA-939 G-5 ment 2 AC 2 CK SA 0 CV, LT* 9 Instrument Air to Contain-l-IA-938 G-5 ment 2 AC 2 CK SA 0 CV, LT* 9 Sl-004bc-3 4-49 Rev. 3

"-"--l-- .,, 1 (107

  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Compressed Air System Drawing No. 11448-FM-75G Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request l-SA-62 D-7 Service Air to Containment 2 AE 2 GL Man* C LT* None l-SA-60 E-7 Service Air to Containment 2 AE 2 GL Man C LT* None 4-50 Rev. 3 M~r"'h ?7 1QR7

Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Va:lves System Name: Containment Instrument Air Drawing No. 11448-FM-75J Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request TV-IA-lOlA J-7 Instrument Air Suction LT*, EV TV-IA-lOlB I-7 from Containment 2 A 3 GA PN 0 ST, VP 34 Instrument Air Discharge LT*, EV TV-IA-100 K-2 to Containment 2 A 2 GA PN 0 ST, VP 34 Back up Instrument Air l-IA-446 J-,2 to Containment 2 AE 2 GA Man C LT* None Back up Instrument Air to 2-IA-446 J-1 Containment from Unit 2 2 AE 2 GA Man C LT* None Sl-004bc-3 4-51 Rev. 3 M~-,,.~'h ')7 1 (JQ7 '

  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Boron Recovery System Drawing No. 11448-FM-79A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function. Class gory Size Type Type Position Required Request SV-BR-100 G-5 Gas Stripper Relief NC C 2 SF SA C SP 1 RV-BR-120 G-1 Gas Stripper Surge NC C 1 RV SA C SP 1 Tank Relief RV-BR-108 A-5 Primary Drain Tank NC C 4 RV SA C SP 1 Relief 4-52 Rev. 3 L~=004bc-3 M,-,..-,..1, '>7 1 QA7
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Boron Recovery System Drawing No. 11448-FM-79B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request SV-BR-lOlA c-*1 Boron Evaporator and NC C 10 SF SA C SP 1 SV-BR-lOlB H-1 Boron Overhead Condenser Relief RV-BR-115 K-5 Evaporator Bottoms Tank NC C . 2 SF SA C SP 1 Relief Sl-004bc-3 4-53 Rev. 3
  • Sutry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Sampling System Drawing No. 11448-FM-82B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request TV-SS-103A D-1 Residual Heat Removal LT*, EV TV-SS-103B E-1 System Sample 2 A 3/8 GA sov C ST, VP 34 TV-SS-lOOA D-1 - Pressurizer Liquid Space LT*, EV TV-SS-lOOB E-1 Sample 1 A 3/8 GA sov C ST' VP I 34 TV-SS-lOlA D-1 Pressurizer Vapor Space LT*, EV Tv..:.ss-101B E-1 Sample 1 A 3/8 GA sov C ST, VP 34 TV-SS-106A D-2 Primary Coolant Hot Leg LT*, EV TV-SS-106B E-2 Samples 1 A 3/8 GA sov C ST, VP 34 TV-SS-102A D-2 Primary Coolant Cold Leg LT*, EV TV-SS-102B E-2 Sample 1 A 3/8 GA sov C ST, VP 34 TV-SS-104A D-2 Pressurizer Relief Tank LT*, EV TV-SS-104B E-2 Gas Space Sample 2 A 3/8 GA sov C ST, VP 34 Sl-004bc-3 4-54 Rev. 3 M-,-v-"'h ?7 1 QA7
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Vents and Drains Drawing No. 11448-FM-83A Valve Drawing Code Cate- Valve , Actuator Normal Test Relief

'Number Location Function Class gory Size Type Type Position Required Request Reactor Containment Sump LT*, VP TV-DA-lOOB A-8 Pump Discharge Isolation 2 A 2 GA PN C EV, ST 34 TV-DA-103A A-6 Post Accident Sample LT*, VP TV-DA-103B Return Line 2 A 2 GA PN C EV, ST 34 1-VA-l A-3 Primary Vent Pot Vent 2 AE 2 GA Man C LT* None Primary Drain Transfer LT*, VP TV-DG-108B A. . . 3 Pump Discharge Isolation 2 A 2 GA PN C EV, ST 34 LT*, VP TV-VG-109B A-1 Gas Vent Header Isolation 2 A 2 GA PN C EV, ST 34 Sl-004bc-3 4-55 Rev: 3 M-~-1-- '17 1 ()Q7

  • .! Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Vents and Drains Drawing No. 11448-FM-83B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request Reactor Containment Sump LT*, EV TV-DA-lOOA *H-8 Pump Discharge Isolation 2 A 2 GA PN oc ST, VP 34 1-VA-6 J-5 Primary Vent Pot Vent 2 AE 2 GA MAN C LT* None Primary Drain Transfer LT*, EV TV-DG-108A L-5 Pump Discharge I$olation 2 A 2 GA PN oc ST, VP 34 LT*, EV TV-VG-109A L-2 Gas Vent Header Isolation 2 A 2 GA PN 0 ST, VP 34 Rev. 3 I . S1-004bc.~3 4-56 M-,-,-,.h ')7 1 Q~7
  • Surry Power Station_Unit No. 1 In.service Testing ASME Code Class 1, 2, and 3 Valves System Name: Containment Spray System Drawing No. 11448-FM-84A Valve Drawing Code Cate- Valve Actuat<>"r Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request MOV-CS-101A H-2 MOV-CS-101B H-2 Containment Spray Pump 2 A 8 GA MOV C LT*,EV None MOV-CS-lOlC H-3 Discharge ST, VP MOV-CS-lOlD H-3 l-CS-13 I-2 Containment Spray Pump l-CS-24 I-3 Discharge Check Valves 2 AC 8 CK SA C CV, LT* 10 l-CS-105 K-1 Containment Spray Pump l-CS-127 K-3 Discharge Check Valve 2 C 8 CK SA C CV 10 MOV-CS-102A C-6 Chemical Addition Tank to EV, ST MOV-CS-102B C-6 RWST Isolation Valve 2 B 6 GA MOV C VP None MOV-CS-103A D-6 Chemical Addition Tank MOV-CS-103B D-6 Discha'rge to Suction 2 B 3 GA MOV C EV, ST None MOV-CS-103C D-7 Containment Spray Pump VP MOV-CS-103D D-6 Sl-004bc-3 4-57 Rev.. 3

~.,:..~ ,lo '>7 1 007

  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Recirculation Spray System Drawing No. 11448-FM-84B Valve Drawing Code Cate- Valve Actuator Normal Test. Relief Number Location Function Class gory Size Type Type Position Required Request MOV-RS-155A D-6 Recirculation Spray Pump LT*, EV MOV-RS-155B D-6 Suction from Containment 2 A 12 PL 'MOV 0 ST, VP None Sump MOV-RS".""156A E-4 Recirculation Spray Pump LT*, EV MOV-RS-156B E-4 Discharge 2 A 10 BF MOV 0 ST, VP None l-RS-11 F-3 Recirculation Spray Pump CV l-RS-17 F-4 Discharge Check Valves 2 AC 10 CK SA C LT* 10 S1-004bc-3 4-58 Rev. 3 M.-,.,-,-.h ?7 . l QR7
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Containment Vacuum and Leakage Monitoring Drawing No. 11448-FM-85A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request TV-LM-lOOA E-3 TV-LM-lOOB E-3 TV-LM-lOOC E-3 TV-LM-lOOD E-3 Leakage Monitoring System LT*, EV TV-LM~lOOE E-3 Isolation 2 A 3/8 GA PN 0 ST, VP 34 TV-LM-lOOF E-3 TV-LM.;..lQOG D-3 TV-LM-lOOH E-3 Containment Air Ejector HCV-CV-100 J-5 Isolation 2 AE 8 GA PN C LT*, VP None Containment Air Ejector l-CV-2 1-5 Isolation 2 AE 8 GA Man C LT* None TV-CV-150A H-7 TV-CV-150B H-7 Containment Vacuum Pump LT*, EV TV-CV-150C H-8 Suction Isolation 2 A 2 GA PN 0 VP, ST 34 TV-CV-150D H-8 S1-004bc-3 4-59 Rev. 3 M,irf'h ?7 Jq87
  • **: Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Reactor Coolant System Drawing No. 11448-FM-86A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request HCV-1556A A-2 HCV-1556B A-7 Loop Fill Boundary 1 AE 2 PL PN C LT, VP 30 HCV-1556C L-2 SOV-RC-lOOA-1 H-7 SOV-RC-lOOA-2 H-7 Reactor Vessel Head Vent 2 B 1 GA sov C EV, ST 31 SOV-RC-lOOB-1 H-'7 SOV-RC-lOOB-2 H-7 Sl-004bc-3 4-60 Rev. 3
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Reactor Coolant Drawing No. ll 448-FM-86B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request SV-1551A F-4 SV-1551B G-4 Pressurizer Safety 1 AC 6 SF SA C SP, LT 1, 30 SV-1551C H-4 Valves Primary Grade Water LT*, EV TV-1519A A-6 to PZR Relief Tank 2 A 3 GA PN C ST, VP None Primary Grade Water l-PG-65 A-6 to PZR Relief Tank 2 AC 3 CK SA C LT*, CV 9 MOV-1535 I-4 Power Operated Relief EV, ST MOV-1536 I-5 Block Valves 1 A 3 BF MOV 0 LT, VP 30 PCV-1456 J-4 Pressurizer Power EV, ST

~CV-1455C J-5 Operated Relief. Valve 1 A 3 PL PN C FS, VP 30,34,35 LT SOV-RC-lOlA-1 I-6 Pressurizer Head Vent 2 B 1 GA sov C EV, ST 31 SOV-RC-lOlA-2 J-6 SOV-RC-lOlB-1 I-6 SOV-RC-lOlB-2 J-6 S1-004bc-3 4-61 Rev. 3

  • Surry Power Station Unit No*. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Residual Heat Removal Drawing No. 11448-FM-87A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request MOV-1700 H-7 RHR Suction from Reactor ST, EV MOV-1701 H-7 Coolant System 1 A 14 GA MO C
  • LT, VP 12, 30 MOV-1720A K-5 RHR Discharge to Reactor - ST, EV MOV-1720B K-5 Coolant System 1 A 10 GA MO C LT, VP 13, 30 RV-1721 I-4 RHR System Relief Valve 2 C 3 RV SA C SP 1 l-RH-5 D-6 RHR Pump Discharge Check l-RH-11 B-6 Valve 2 C 10 CK SA C CV 11 MOV-RH-100 K-3 RHR to RWST 2 AE 6 GA MO C LT*, VP None Sl-004bc-3 4-62 Rev. 3 v,, ... ,...., ?7 1 Qj:l7
  • Surry Power Station Unit No. 1 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-76 C-7 Boric Acid Transfer Pump l-CH-92 D-7 Discharge Valve 3 C 2 CK SA oc CV None S1-004bc-3 4-63 Rev. 3 M<11*rh ?7 1 Q~7
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Chemical and Volume Control Drawing No. 11448-FM-BBB Valve . Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request l-CH-258 D-6 l-CH-267 F-6 Charging Pump Discharge 2 C 3 CK SA oc CV 14 l-CH-276 G-6 Check Valve Charging Pump Suction from LCV-1115B C-9 Refueling Water Storage 2 B 8 GA MOV C EV, ST None LCV-1115D C-9 Tank VP LCV-1115C H-3 Charging Pump Suction from EV, ST LCV-1115E H-3 Volume Control Tanks 2 B 4 GA MOV 0 VP 15 MOV-1275A D-6 MOV-1275B F-6 Charging Pump Recirculation EV, ST MOV-1275C H-6 Flow Path Isolation 2 B 2 GA MOV 0 VP ,None Charging Pump Recirculation EV, ST MOV:---1373 F-5 Header Stop Valve 2 B 3 GA MOV 0 VP 16 Reactor Coolant Pump Seal EV, ST MOV-1381 A-3 Water Return 1 A 3 GA MOV 0 VP' LT* 17 Reactor Coolant System Let- LT*, EV TV-1204 A-3 down Isolation Trip Valve 2 A 2 GA PN 0 ST, VP 18,34 Reactor Coolant System Let-RV-1209 F-1 down Relief Valve 2 C 2 RV SA C SP 1 Volume Control Tank Relief RV-1257 H-1 Valve 2 C 3 RV SA C SP 1 S1-004bc-3 4-64 Rev. 3 v~~r"h '17 1 ()Q7
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Chemical and Volume Control Drawing No. 11448-FM-88B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request MOV-1289A B-5 Normal Charging Header LT*, EV Isolation 2 A 3 GA MOV 0 ST, VP 19 RCS Loop Fill Header LT*,

FCV-1160 A-3 Isolation 1 AE 2 GL PN C VP None Seal Water Return Line RV-1382B F-3 to VCT 2 C 2 RV SA C SP 1 MOV-1289B B-5 Normal Charging 2 B 3 GA MOV 0 EV, ST Header Isolation VP 19 Sl-004bc-3 4-65 Rev. 3 M-,..-,-1-, ')7 10~7

  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class l, 2, and 3 Valves System Name: Chemical and Volume Control Drawing No. U448-FM-88C Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request RV-1203 H-1 Letdown Header Relief 2 C 2 RV SA C SP 1 HCV-1200A H-2 HCV-1200B H-2 LT*, EV HVC-1200C H-2 Letdown Orifice* Isolation 2 A 2 GA PN OC ST, VP 34 Seal Water Return.to RV-1382A H-4 Pressurizer Relief Tank 2 C 2 RV SA C SP 1 l-CH-309 J-3 Normal Charging 2 AC 3 CK SA 0 CV, LT* 9 Isolation Check Valve Sl-004bc-3 4-66 Rev. 3
  • " .... ,. ,.,, , no,
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Safety Injection Drawing No. 11448-FM-89A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request Low Head Safety Injection Pump Suction from Contain- LT*, EV MOV-1860A, B . B-8, E-8 ment Sump 2 A 12 GA MOV C ST, VP None.

Low Head Safety Injection Pump Suction from Contain-:-

1.:...sI-56, 47 C-8, F-8 ment Sump Check 2 C 12 CK SA C CV 20 Low Head Safety Injection Pump Suction from Refueling EV, ST MOV-1862A, B G-9, G-8 Water Storage Tank 2 B 12 GA MOV 0 VP None Low Head Safety Injection Pump Suction from Refueling l-SI-46A, B G-9, G-8 Water Storage Tank Check* 2 C 12 CK SA C CV 21

.Low Head Safety Injection l-SI-58, so D-7, G-7 Pump Discharge Check 2 C 10 CK SA C CV 21 Low Head Safety Injection Pump Discharge to High Head EV, ST MOV-1863A, B D-6, G-6 Safety Injection Pump 2 B 8 GA MOV C VP Suction None Low Head Safety Injection MOV-1885A, B D-7, G-7 Pump Recirculation to EV, ST C, D* G-7, E-7 Refueling Water Storage 2 B 2 GA MOV 0 VP Tank None S1-004bc-3 4-67 Rev. 3 M~rr-h ?7 1QR7

  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Safety Injection Drawing No. 11448-FM-89A Valve Drawing Code Cate- Valve Actuator Normal Test Relief
  • Number Location Function Class gory Size Type Type Position Required Request Low Head Safety Injection Pump Recirculation to l-SI-61, 53 D-7, G-7 Refueling Water storage 2 C 2 CK SA C CV None Low Head Safety Injection Pump Discharge to Reactor EV, MOV-1864A, B D-6, G-5 Coolant System Cold legs 2 B 10 GA MOV 0 ST, VP None RV-1845A, B C-6, D-5 Low Head Safety Injection 2 C 1 RV SA C SP 1 C C-5 Flow Path Relief Low Head Safety Injection to Reactor Coolant System LT*, EV MOV-1890 A, B B-6, B-5 Hot Legs 2 AE 10 GA MOV C ST, VP None

. Low Head Safety Injection to Reactor Coolant System LT*, EV MOV-l890C B-6 Cold Legs 2 AE 10 GA MOV 0 ST, VP 22 MOV-1869A, B A-3, I-3 High Head Safety Injection LT*, EV 1842 A-1 to Reactor Coolant System 2 AE 3 GA MOV C ST, VP 23 Boron Injection Tank LT*, EV MOV-1867 C, D B-1, B-2 Outlet Isolation 2 A 3 GA MOV C ST, VP 24 Sl-004bc-3 4-68 Rev. 3 M,:n*rh ?7 1 QR7

  • Surry Power Station Unit No. 1 Inservice,Testing ASME Code Class 1, 2, and 3 Valves System Name: Safety Injection Drawing No. 11448-FM_-89A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request LT*, EV TV-SI-100 B-4 Nitrogen Accumulators 2' A 1 GA PN 0 ST, VP 34 l-SI-73 A-5 Accumulator Isolation 2 AE 3/4 GL Man C LT* None l-SI-32 A-5 Accumulator Isolation 2 AE 1 GL Man C LT* None l-SI-150 B-1 Boron Injection Tank 2 AE 3/4 GL Man 0 LT* None High Head Safety Injection l-"SI-174 C-2 to Reactor Coolant System 2 AE 3/4 GL Man C LT* None TV-SI-102A F_-4 Unit No. 1 RWST to Unit ST, EV TV-SI-102B F-4 No. 2 RWST Cross Tie 2 B 8 GA PN C VP None Charging Pump Suction from l-SI-25 F-4 RWST Check Valve 2 C 8 CK SA C CV 28 Charging Pump Suction from l-SI-410 G-4 RWST Check Valve 2 C 10 CK SA C CV 28 S1-004bc-3 4-69 Rev. 3
  • ., Surry Power Station Unit No. 1
  • Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Safety Injection Drawing No. 11448-FM-89B Valve Drawing Code Cate- Valve Actuator Normal *Test Relief Number Location Function Class gory Size Type Type Position Required Request RV-1858 A, B C-4, G-5 Accumulator Tank Relief C C-7 2 C 1 RV SA C SP 1 l-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-1865 A, B C-5, G-6 EV, ST C C-8 Accumulator Discharge 2 B 12 GA MOV 0 VP None l-SI-88, 91 A-2, A-2 94, 238 A-3, B-2 Safety Injection to RCS 239, 240 B-2, B-3 Hot Legs 1 AC 6 CK SA C CV, LT 27, 30 l-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 l-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 l-SI-224, 225 J-1, J-1 High Head Safety Injection 226, 227 J-2, J-3 Check Valves at Containment 2 C 3 CK SA C CV 27 Penetrations Low Head Safety Injection l-SI-228, 229 J-3, J-3 Check Valves at Containment 2 C 6 CK SA C CV ~7 Penetrations Sl-004bc-3 4-70 Rev. 3
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Safety Injection Drawing No. il448-FM-89B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class .gory Size Type Type Position Required Request 1-sI:....19, 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-lOlA, B J-5, J-5 Relief Line Isolation 2 A 1 GA PN 0 ST, VP 34 l-SI-234 J-4 Nitrogen Accumulators 2 AC 1 CK SA C CV, LT* 9 Accumulator Return to RV-1859 I-4 RWST Relief 2 C 3/4 RV SA C SP 1 Sl-004bc-3 4-71 Rev. 3 M~~~'h 'J7 1007
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Gaseous Waste Disposal Drawing No. 11448-FM-90A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request RV-GW-lOOA C-6 Waste Gas Decay Outer NC C 1 1/2 RV SA C SP 1 RV-GW-lOOB H-6 Tank Relief RV-GW-102A C-6 Waste 'Gas Decay Inner NC C 1 1/2 RV SA C SP 1 RV-GW-102B G-6 Tank Relief RV-GW-103 K-1 Waste Gas Surge Drum NC C 1 1/2 RV SA C SP 1 Relief Sl-004bc-3 4-72 Rev. 3 M"r,-,h ?7 l QP.7
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Gaseous Waste Disposal Drawing No. 11448-FM-90B Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request RV-GW-107 K-5 Relief Valve on Gases NC C 1 RV SA C SP 1 Going to Waste Gas Surge Drain for Storage

)

Sl-004bc-3 4-73 Rev. 3 M~,,..,..1--, "17 1 OP7

  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves

/

System Name: Containment Hydrogen Analyzer Drawing No. 11448-FM-90C Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request TV-GW-100 C-6 Suction Line to Hydrogen LT*, ST TV-GW-101 C-5 Analyzer - Unit 1 2 A 3/8 GA sov C EV, VP 33,34 TV-GW-102 C-7 Discharge Line to Hydrogen LT*, ST TV-GW-103 C-7 Analyzer - Unit 1 2 A 3/8 GA sov C EV, VP 33,34 TV-GW-104 C-3 Suction Line to Hydrogen LT*, ST TV-GW-105 C-3 Analyzer - Unit 2 2 A 3/8 GA sov C EV, VP 33,34 TV-GW-106 C-4 Discharge Line to Hydrogen LT*, ST TV-GW-107 C-4 Analyzer - Unit 2 2 A 3/8 GA sov C EV, VP 33,34 TV-GW-lllA B-2 LT*, ST TV-GW-lllB C-2 Containment Grab Sample 2 A 3/8 GA sov C EV, VP 34 S1-004bc-3 4-74 Rev. 3

~A'-~~-.1- ')f 1()()1

  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Reactor Cavity Purification Drawing No. 11448-FM-llSA Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request Reactor Cavity Purifica-RL-5, RL-3 C-4, .D-4 tion Return Line 2 AE 3 DA Man C LT* None Reactor Cavity Purifica-RL-13, RL-15 c.:..6, D-6 tion Return Line 2 AE 3 DA Man C LT* None Sl-004bc-3 4-75 Rev. 3 M.,,r"" '17 1 QR7
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Steam Generator Blowdown Drawing No. 11448-FM-124A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request TV-BD-100 A, B C-2, C-2 C, D C-4, C-4 Steam Generator Blowdown EV, ST E, F C-5, C-5 Isolation 2 B 3 GA PN 0 VP 29,34 Sl-004bc-3 4-76 Rev. 3

><-- '17 1 ()Q7

  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Radiation Monitor - Containment Particulate Drawing No. ll448-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 l-RM-03 D-8 Return Line 2 AC 3/4 CK SA 0 LT*, CV 9 Isolation on Monitor LT*, EV TV-RM-lOOA F-8 Return Line 2 A 3/4 GA PN 0 ST, VP 34 TV-RM-lOOB F-4 Isolation on Monitor LT*, EV TV-RM-lOOC E-4 Return Line 2 A 3/4 GA PN 0 ST, VP 34 Sl-004bc-3 4-77 Rev. 3 M.-,,-~l-, ')7 1 QQ7
  • Surry Power Station Unit No. 1 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-100 J-3 SOV-EE-101 J-3 Disel Fuel Oil Pump SOV-EE-105 J-5 Discharge Valves NC B 1 GA sov C EV 36 Sl-004bc-3 4-78 Rev. 3 M,irl"h ')7 1 Ql<7
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Containment Purge Drawing No. 11448-FB-6A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request MOV-VS-lOOA D-5 Containment Purge Supply MOV-VS-lOOB D-5 MOV's 2 AE 36 BF MOV C LT*, VP None MOV-VS-102 D-5 Containment Vacuum Breaker 2 AE 18 BF MOV C LT*, VP None MOV-VS-lOOC D-5 Containment Purge Exhaust MOV-VS-lOOD D-5 MOV's 2 AE 36 BF MOV C LT*, VP Norie Containment Purge Exhaust MOV-VS-101 D-5 Bypass 2 AE 8 BF MOV C LT* None Sl-004bc-3 4-79 Rev. 3 M.,,.-"l, '17 1 OA7
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System 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 l-FP-151 D-3 Containment Stand Pipe 1-FP-152 D-3 Supply 3 AE 4 BA Man C LT* None Sl-004bc-3 4-80 Rev. 3
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Diesel Air Starting System Drawing No. 11448-FB-46A Valve Drawing Code Cate- Valve Actuator Normal Test Relief Number Location Function Class gory Size Type Type Position Required Request SOV-EG-lOOA I-4 Diesel Air Start System SOV-EG-lOOB K-4 Solenoid Valves NC B 1 GA sov C EV,VP 37 Sl-004bc-3 4-81 Rev. 3 M,-,r,-,h ?7 1 QP7
  • Surry Power Station Unit No. 1 Inservice Testing ASME Code Class 1, 2, and 3 Valves System Name: Diesel Air Starting System Drawing No. 11448-FB-46C Valve Drawing Code Cate- Valve Actuator Normal Test Relief Numher Location Function Class gory Size Type Type Position Required Request SOV-EG-300A J-4 Diesel Air Start System SOV-EG-300B K-4 Solenoid Valves NC B 1 GA sov C EV,VP 37 S1-004bc-3 4-82 Rev. 3 M.,,,..,..l, ?7 1 QR7 L_

4.4.5 VALVE TEST PROGRAM RELIEF REQUEST

  • Relief the Requests requested identify exception.

code requirements which are impractical for Surry Unit 1 and provide justification for Where appropriate, alternate testing to be performed in lieu of code requirements is proposed .

Sl-004d-3 4-83 REV. 3

  • RELIEF REQUEST 1 System Various Valve(s): Valves affected by this request are identified by Table A.

Category:

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

  • 0 9 1 (a) ( 2) and 4
  • 0 91 ( c) (1 )
  • Alternate Testing Proposed Main Steam safety valves will be tested in accordance with PTC-25.3-1976 Section 4.091 (a) (2). All other safety and relief valves will be tested in accordance with Section 4.091 (c) (1)
  • Sl-004d-3 4-84 REV. 3

RELIEF REQUEST 1

  • Valve SV-MS-lOlA, B, C Category C

TABLE A Class 2

Function Main Steam Safety Valves SV-MS-102A, B, C SV-MS-103A, B, C SV-MS-104A, B, C SV-MS-105A, B, C RV-MS-lOlA C 2 Main Steam PORV RV-MS-lOlB RV-MS-lOlC RV-CC-119A c* 3 Component Cooling from RHR RV-CC-119B Heat Exchanger Relief Valve RV-CC-116A C 3 Component Cooling Reactor RV-CC-116B Coolant Pump RV-CC-116C RV-CC-124 C 3 Component Cooling Piping Relief Valve RV-CC-118 C 3 Component Cooling from Excess Letdown Heat Exchanger Relief.

RV-1721 C 2 RHR System Relief Valve RV-CC-lllA C 3 Component Cooling to Fuel Pit RV-CC-11 lB Coolers Relief Valves RV-CC-123 C 3 Component Cooling to Surge Tank Relief Valve SV-1551A AC 1 Pressurizer Safety Valves SV-1551B SV-1551C RV-1209 C 2 Reactor Coolant System Letdown Relief Valve RV-1257 C 2 Volume Control Tank Relief Valve RV-1203 C 2 Letdown Header Relief RV-1845A, B, C C 2 Low Head Safety Injection Flow Path Relief RV-1858A, B, C C 2 Accumulator Relief Valve*

SV-BR-100 C NC Gas Stripper Relief Sl-004d-3 4-85 REV. 3

RELIEF REQUEST 1 TABLE A (CONT'D)

Valve Category Class Function RV-BR-120 C NC Gas Stripper Surge Tank Relief

_RV-BR-108 C NC Primary Drain Tank Relief SV-BR-101A&B C NC Boron Evaporator and Boron Overhead Condenser Relief RV-BR-ll5 C NC Evaporator Bottoms Tank Relief RV-1322 C . NC Batching Tank Heating Jacket Relief RV-1382B C 2 Seal Water Return Line to VCT RV-1382A C 2 Seal Water Return to Pressurizer Relief Tank RV-1859 C 2 Accumulator Return to RWST Relief

  • RV-GW-lOOA, B RV-GW-102A, B C

C NC NC Waste Gas Decay Outer Tank Relief Waste Gas Decay Outer Tank Relief RV-GW-103 C NC Waste Gas Decay Inner Tank Relief RV-GW-107 C NC Relief Valve on Gases going to Waste Gas Surge Drum for Stor~ge Sl-004d-3 4-86 REV. 3

  • RELIEF REQUEST 2 System Main Steam Valve(s): TV-MS-101A TV-MS-lOlB TV-MS-lOlC Category: B Class 2 Function: Main Steam Line Trip Valves Section XI Code Requirement For Which Relief Is Requested Exercise valves every three, months.

Basis For Request Full Stroke or partial stroke exercise of these valves during power operation-_

could result in a turbine and reactor trip.

  • Alternate Testing Proposed Full stroke exercise during each cold shutdown or startup in Technical Specification .

accordance with Sl-004n-".\ REV. 3

  • System Valve(s):

Main Steam NRV-MS-101A RELIEF REQUEST 3 NRV-MS-102A NRV-MS-101B NRV-MS-102B NRV-MS-101C NRV-MS-102C Category: C Class 2 Function: Main Steam Non-Return Valves Section XI Code Requirements For Which Relief Is Requested Exercise valves every three months.

Basis For Request Full stroke or partial stroke exercise of these valves during power operation-.

could result in a turbine and reactor trip.

Alternate Testing Proposed Full stroke exercise during each cold shutdown (but not more frequently than every three months) .

Sl-004d-3 4-88 REV. 3

  • System Valve(s):

Auxiliary Feedwater RELIEF REQUEST 4 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 these valves for operability every cold shutdown (but not more frequently than every three months) .

  • Sl-004d-3 4-89 REV. 3 March 27, 1987

RELIEF REQUEST 4

  • Valve 1-FW-27 Category C

Class 2

TABLE B Function Auxiliary Feedwater Header Check 1-FW-58 .Valves at Main Feedwater Header.

1-FW-89 1-FW-131 C 2 Auxiliary Feedwater Header 1-FW-133 Check Valves at Containment 1-FW-136 Penetration.

l-FW-138 l-FW-142 C 3 Auxiliary Feedwater Pump 1-FW-157 Discharge Check Valves 1-FW-172 1-FW-272 C 2 Check Valves at Containment 1-FW-273 Penetration (Cross-Connect for Unit 1 Aux. Feed. from Unit 2) 1-FW-309 C 2 Check Valves at Containment 1-FW-310 Penetration (Cross-Connect for Unit l Aux. Feed

  • from Unit 2)
  • S1-004d-3 4-90 REV. 3 March 27, 1987
  • System Feedwater RELIEF REQUEST 5 Valve(s): l-FW-10 l-FW-41 l-FW-72 l-FW-12 l-FW-43 l-FW-74 Category: C Class 2 Function: Main Feedwater check valves at Containment Penetrations.

Section XI Code Requirement For Which Relief Is Requested Exercise valve every three months.

Basis For Request Closure of these valves during power operation would require securing -

feedwater which would result in reactor trip. 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 to exceed 2 years)

  • S1-004d-3 4-91 Rev. 3 March 27, 1987
  • RELIEF REQUEST 6 Relief Request Withdrawn
  • 4-92 REV. 3 S1-004d-3 March 27, 1987
  • System Valve(s):

Component Cooling RELIEF REQUEST 7 Valves affected by this request are identified by Table C.

Category:

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 f9r operability every cold shutdown (but not more frequently than three months) .

  • Sl-004d-3 4-93 REV. 3 March 27, 1987

RELIEF REQUEST 7

  • TABLE C Valve Category Class Function l-CC-176 C 3 Component Cooling to RHR Heat l-CC-177 Exchanger Check valves l-CC-242 C 3 Component Cooling to Reactor l-CC-233 Containment Air Recirculation l-CC-224 Coolers
  • S1-004d-3 4-94 REV. 3 March 27, 1987

I

  • RELIEF REQUEST 8 System Component Cooling Valve(s): Valves affected by this request are identi_fied by Table D.

Category:

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 shor-t periods.

Alternate Testing Proposed Exercise these valves for 'operability every cold shutdown (but not more frequently than three months) *

  • Sl-004d-3 4-95 REV. 3 March 27, 1987

RELIEF REQUEST 8

  • Valve Category Class TABLED Function l-CC-1 C 3 Component Cooling to Reactor l-CC-58 Coolant Pumps l-CC-59 TV-CC-105A B 3 Component Cooling from Reacto,r TV-CC-105B Coolant /umps TV-CC-105C TV-CC-107 B 3 Component Cooling from Reactor Coolant Pumps
  • S1-004d-3 4-96 REV. 3 March 27, 1987
  • System Valve(s):

Various RELIEF REQUEST 9 Valves affected by this request are identified in Table E.

Category:

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 fact that removing system from operation is required and these systems are required even at cold shutdown,_

these valves will be tested every refueling shutdown. 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 Te~ting Proposed These valves will be subject to reverse flow during leakage test which are performed during each refueling *
  • Sl-004d-3 4-97 REV. 3 March 27; 1987

RELIEF REQUEST 9 TABLE E Valve Category Class Function l-IA-939 AC 2 Instrument Air to Containment l-IA-938 AC 2 Instrument Air to Containment l-RM-3 AC 2 Isolation on Monitor return line.

l-PG-65 AC 2 Primary Grade water to PRZ Relief Tank l-SI-234 AC 2 Nitrogen Accumulators N supply.

2 l-CH-309 AC 2 Normal Charging Isolation Check Valve

  • S1-004d-3 4-98 REV. 3 March 27, 1987

RELIEF REQUEST 10 System Containment and Recirculation Spray Valve(s): l-RS-11 l-CS-13 l-CS-105 l-RS-17 l-CS-24 l-CS-127 Category: AC (l-RS-11, 17 and l-CS13, 24) and C (l-CS-105,127)

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 is required, they will be tested every refueling shutdown

  • Alternate Testing Proposed Full stroke manual testing will be performed each refueling shutdown .
  • Sl-004d-3 4-99 REV. 3 March 27, 1987

RELIEF REQUEST 11 System Residual Heat Removal Valve(s): l-RH-5 l-RH-11 Category: C Class 2 Function: RHR Pump Discharge Check Valve Section XI Code Requirement For Which Relief Is Requested Ex~rcise 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 frequently than three months)
  • every cold shutdown (but not more
  • Sl-004d-3 4-100 REV. 3 March 27, 1987
  • RELIEF REQUEST 12 System Residual Heat Removal Valve(s): Mov.:...1700 MOV-1701 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 can not be opened at elevated reactor coolant system 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 frequently than three months).

every cold shutdown (but not more

/

  • S1-004d-3 4-101 REV. 3 March 27, 1987

RELIEF REQUEST 13

  • System Valve(s):

Residual Heat Removal MOV-1720A MOV-l 720B 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 MOV was opened an over pressure 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 than three months) *

  • S1-004d-3 4_-102 REV. 3 March 27, 1987

_RELIEF REQUEST 14 System Chemical and Volume Control Valve(s): l-CH-258 l-CH-267

  • 1-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 th~ 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 partially stroked every three months and full flow tested each refueling *

  • S1-004d-3 4-103 REV. 3 March 27, 1987

RELIEF REQUEST 15 System Chemical and Volume Control Valve(s): LCV-1115C LCV-1 llSE 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 frequently than every three months) .

each cold shutdown (but not more

  • Sl-004d-3 4-104 REV. 3 March 27, 1987

_j

RELIEF REQUEST 16 System Chemical and Volume Control Valve(s): MOV-1373 Category: B Class 2 Function: Charging Pump Recirculation Header Stop Valve Section XI Code Requirement For Which Relief Is Requested Exercise valves every three months.

Basis For Request MOV-1373 is not cycled quarterly because its failure in the closed position would challenge the operation of the Charging Pumps. The individual recirculation valves (MOV-1275 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-1373, 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 than three months) .

  • S1-004d-3 4-105 REV. 3 March 27, 1987
  • System Valve(s):

RELIEF REQUEST 17 Chemical and Volume Control MOV-1381 Category: A Class 1 Function: Reactor Coolant Pump Seal Water Return Section XI Code Requirement For Which Relief Is Requested Exercise valves every three months.

Basis For Request Closure of this valve with Reactor Coolant Pumps in operation will cause a loss of seal flow resulting in possible pump seal damage.

Alternate Testing Proposed This valve will be exercised during each cold shutdown (but not more frequently than every three months) .

  • S1-004d-3 4-106 REV. 3 March 27, 1987

RELIEF REQUEST 18 System Chemical and Volume Control Valve(s): TV-1204 Category: A Class 2 Function: Reactor Coolant System Letdown Isolation Trip Valve Section XI Code Requirement For Which Relief Is Requested Exercise valves every three months.

Basis For Request Exercising this valve during power operation could result in a loss of reactor coolant inventory control and pressurizer level control.

Alternate Testing Proposed This valve will be exercised every cold shutdown (but not more frequently than every three months) .

  • Sl-004d-3 4-107 REV. 3 March 27, 1987

RELIEF REQUEST 19 System Chemical and Volume Control Valve(s): MOV-1289A MOV-1289B Category: A (MOV-1289A) and B (MOV-1289B)

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) .

  • Sl-004d-3 4-108 RE.V. 3 March 27, 1987

RELIEF REQUEST 20 System Safety Injection Valve(s): l-SI-56 l-SI-47 Category: C Class Function: Low Head Safety Injection Pump Suction from Containment Sump Check Valve Section XI Code Requirement For Which Relief Is Requested Exercise valves every three months.

Basis For Request This normally closed check valve cannot be exercised without isolating suction_

to Low Head Safety Injection by installing flanges and draining portions of the system *

  • Alternate Testing Proposed These valves will be partial stroke exercised during each refueling *
  • Sl-004d-3 4-109 REV. 3 March 27, 1987

RELIEF REQUEST 21 System Safety Injection Valve(s): Valves affected by this request are identified in Table F.

Category:

Class Function:

Section XI Code Requirement For Which Relief Is Requested Exercise valves every three months.

Basis For Request These valves cannot be full stroke exercised during plant power operation.

The only full flow path is into the Reactor Coolant System and Low Head Safety Injection pumps cannot overcome Reactor Coolant System operating pressure._

These valves will be 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 .

  • Sl-004d-3 4-110 REV. 3 March 27, 1987

RELIEF REQUEST 21

  • Valve l-SI-46A Category C

TABLE F Class 2

Function Low Head Safety Injection Pump l-SI-46B Suction from Refueling Water Storage Tank Check l-SI-58 C 2 Low Head Safety Injection l-SI-50 Pump Discharge Check

  • Sl-004d-3 4-111 REV. 3 March 27, 1987
  • System Valve(s):

Safety Injection MOV-1890C

'RELIEF REQUEST 22 Category: 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-1890C 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 frequently than every three months)
  • each cold shutdown (but not more
  • Sl-004d-3 4-112 REV. 3 March 27, 1987

RELIEF REQUEST 23 System Safety Injection Valve(s): MOV-1869A MOV-1869B MOV-1842 Category: A Class 2 Function: High Head Safety Injection to Reactor Coolant System Section XI Code Requirement For Which Relief Is Requested Exercise valves every three months.

Basis For Request These valves cannot be exercised during power operation. Opening these valves -

would allow charging flow into the Reactor Coolant System causing reactivity transients and possible thermal shock to 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 as a minimum .

  • Sl-004e-,-3 4-113 Rev. 3 March 27, 1987

RELIEF REQUEST 24

  • System Valve(s):

Safety Injection MOV-1867C MOV-1967D

  • Category: A Class 2 Function: Boron Injection Tank Outlet Isolation Section XI Code Requirement For Which Relief Is Requested Exercise valves every three months.

Basis For Request 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 each cold shutdown (but not more frequently than every three months) .
  • Sl-004e-3 4-114 Rev. 3 March 27, 1987

RELIEF REQUEST 25 Relief Request Withdrawn

  • S1-004e-3 4-115 Rev. 3 March 27, 1987
  • System Valve(s):

Safety Injection l-SI-107 RELIEF REQUEST 26 l-SI-109 l-SI-128 l-SI-130 l-SI-145 l-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 flow is not practical due to the large volume of water that would be added to the Reactor Coolant System. Calculations have shown that a differential pressure of approximately 25 psi will shear any particles that may attempt to prevent the valve from functioning. Based on this calculation and partial stroke testing presently performed, full stroke testing will not be performed.

Alternate Testing Proposed These valves will be partially stroked each refueling *

  • Sl-004e-3 4-116 Rev. 3 March 27, 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 .
  • Sl-004e-3 4-117 Rev. 3 March 27, 1987

RELIEF REQUEST 27 TABLE G Valve Category Class Function l-SI-88, 91 AC 1 Safety Injection to RCS Hot Legs l-SI-94, 238*

l-SI-239, 240 l-SI-235

  • AC 1 High Head Safety Injection to l-SI-236 RCS Cold Legs 1-sI....;237' l-SI-241 AC 1 Low Head Safety Injection to l-SI-242 RCS Cold Legs l-SI-243 l-SI-224, 225 C 2 Head Head Safety Injection Check l-SI-226, 227 Valve at Containment Penetrations l-SI-228, 229 C 2 *Low Head Safety Injection Check Valves at Containment Penetrations l-SI-79, 82, 85 A 1 Safety Injection to RCS Cold Legs
  • s1:..004e-3 4-118 Rev. 3 March 27, 1987

RELIEF REQUEST 28

\

System R.W.S.T. Cross Tie Valve(s): l-SI-25 l-SI-410 Category: C Class 2 Function: Charging Pump Suction From R..W.S.T. Cross Tie Section XI Code Requirement For Which Relief Is Requested Exercise valves every three months.

Basis For Request Exercising these valves during power operation would req~ire the charging pump suctions to be aligned with the refueling water storage tank. This would cause a sudden increase in reactor coolant boron inventory.

Alternate Testing Proposed Exercise the valves for operability every cold shutdown (but not more frequently than every three months) *

  • S1-004e-3 4-.119 Rev. 3 March 27, 1987

RELIEF REQUEST 29 System Steam Generator Blowdown Valve(s): TV-BD-lOOA TV-BD-100D TV-BD-lOOB TV-BD-lOOE TV-BD..::1ooc TV-BD-lOOF Category: B Class 2 Function: Steam Generator Blowdown Isolation.

Section XI Code Requirement For Which Relief Is Requested Exercise valves every three months.

Basis For Request Closing these valves during power operation causes the downstream piping to become empty due to drainage and water flashing to steam. When the valves reopened, a flow surge occurs which automatically isolates the inner valves due to high flow. Then a containment entry is necessary to reset these valves and upon reopening the process may occur again.

Alternate Testing Proposed Exercise the valves for operability every cold shutdown (but not more frequently than every three months) *

  • Sl-004e-3 4-120 Rev. 3 March 27, 1987

RELIEF REQUEST 30

  • System Valve(s):

Category:

Class Various Valves affected by this request are identified by Table H Function:

Section XI Code Requirement For Which Relief Is Requested Valves shall be leal< tested in accordance with IWV-3426 and IWV-3427 Basis For Relief 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 3.1.C and 4.3 and ASME Section XI, Subsection IWB-5000 .

  • S1-004e-3 4-121 Rev. 3 March 27, 1987

RELIEF.REQUEST 30

  • Valve HCV-1556A Category A

Table H Class 1

Function Loop Fill Boundary HCV-1556B HCV-1556C SV-1551A AC 1 Pressurizer Safety Valves SV-1551B SV-1551C MOV-1535 A 1 PORV Block Valves MOV-1536 PCV-1456 A 1 PORV PCV-1455C l-SI-107, 109 AC 1 Accumulator Discharge Check 1-SI-128, 130 . Valve 1-SI-145, 147 1-SI-88, 91 AC 1 Safety Injection to RCS Hot Legs 1-SI-94, 238 1-SI-239, 240 1-SI-241 AC 1 Low Head Safety Injection to l-SI-242 RCS Cold Legs l-SI-243 MOV-1700 A 1 RHR Suction from Reactor Coolant MOV-1701 System MOV-1720A A 1 RHR Discharge to Reactor Coolant MOV-1720B System

  • Sl-004e-3 4-122 Rev. 3 March 27, 1987

RELIEF REQUEST 31 System Reactor Coolant Valve(s): SOV-RC-lOOA-1 SOV-RC-10 lA-1 SOV-RC-lOOA-2 SOV-RC-lOlA-2 SOV-RC-lOOB-1 SOV-RC-lOlB-1 SOV-RC-lOOB-2 SOV-RC-lOlB-2 Category: B Class 2 Function: Head Vent for Reactor Vessel and Pressurizer Section XI Code Requi~ements For Which Relief Is Requested Exercise valves every three months.

Basis For Request Due to head vents location on Reactor Coolant System, valve cycling during_

power operation could put plant in unsafe condition. Also at cold shutdown and at power operation, cycling these valves could cause an airborne contamination problem due to the fact that they discharge to containment atmosphere.

Alternate Testing Proposed These valves will be tested each refueling by exercising and verifying flow .

  • S1-004e-3 4-123 Rev. 3 March 27, 1987

RELIEF REQUEST 32

  • System Valve(s):

Category:

Hain Steam HCV-MS-104 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 a overpower condition and possible reactor trip as reactor power increases to meet the new steam load.

Alternate Testing Proposed Exercise these valves for operability every cold shutdown (but not more frequently than every three months) .

  • Sl-004e-3 4-124 Rev.3 March 27, 1987

RELIEF REQUEST 33

  • System Valve(s):

Gaseous Waste TV-GW-100 TV-GW-104 TV-GW-101 TV-GW-105 TV-GW-102 TV-GW-106 TV-GW-103 TV-GW-107 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 Proposed Alternatively these valves will be subjected to a leak rate test every refueling (not to exceed 24 months). During this leak rate test, the local valve position and remote valve position indication is verified the same *
  • S1-004e-3 4-125 Rev.3 March 27, 1987
    • System Various RELIEF REQUEST 34 Valve(s): 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 Testing Proposed Whenever the stroke time of these valves exceeds 2 seconds, IWV-3417(a) will be applied .

  • Sl-004e-3 4-126 Rev. 3 March 27, 1987

RELIEF REQUEST 34

  • Valve TV-'MS-110 Category B

TABLE J Class 2

Function Main Steam Drain to Blowdown TV-CC-105 A,B, C B 3 Component Cooling from RCP TV-CC-107 B 3 Component Cooling from RCP TV-CC-109 A,B B 3 Component Cooling from RHR Heat Exchanger TV-IA-101 A, B A 2 Instrument Air Suction from Containment TV-IA-100 A 2 Instrument Air Discharge to Containment TV-SS-103 A,B A 2 Residual Heat Removal System Sample TV-SS-100 A,B A* 1 Pressurizer Liquid Space Sample TV-SS-101 A,B A 1 Pressurizer Vapor Space Sample TV-SS-106 A,B A 1 Primary Coolant Hot Leg Sample TV-SS-102 A,B A 1* Primary Coolant Cold Leg Sample TV-SS-104 A,B A 2 Pressurizer Relief Tank Gas Space Sampl_e TV-DA-100 A,B A 2 Reactor Containment Sump Pump Discharge Isolation TV-DA-103 A,B A 2 Post Accident Sample Return Line TV-DG-108 A,B A 2 *Primary Drain Transfer Pump Discharge Isolation TV-VG-109 A,B A 2 Gas Vent Header Isolation TV-LM-100 A-H A 2 Leakage Monitoring System Isolation TV-CV-150 A-D A 2 Containment Vacuum Pump Suction Isolation PCV-1456 A 1 Pressurizer Power Operated Relief Valve PCV-1455C A 1 Pressurizer Power Operated Relief Valve TV-1204 A 2 RCS Letdown Isolation Trip Valve HCV-1200 A,B,C A 2 Letdown Orifice Isolation TV-SI-100 A 2 Nitrogen Accumulators TV-SI-101 A,B A 2 Accumulator Nitrogen Relief Line Isolation TV-GW-100-107 A 2 Suction/Discharge Line to Hydrogen Analyzer TV-GW-111 A,B A 2 Containment Grab Sample TV-BD-100 A-F B 2 Steam Generator Blowdown Isolation TV-RM-100 A,B,C A 2 Isolation on Monitor Return Line

  • Sl-004e-3 4-127 Rev. 3 March 27, 1987

RELIEF REQUEST 35 System RC Valve(s): PCV-1456 PCV-1455C 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 power operation is not practical -since valves are not required for overpressure protection 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) .

  • Sl-004e-3 4-128 Rev. 3 March 27, 1987

RELIEF REQUEST 36 System EE Valve(s): SOV-EE-100 SOV-EE-101 SOV-EE-105 Category: B Class NC Function: Diesel Fuel Oil Pump Discharge 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 considerally under a second and there is no -

visual reference on the solenoid valve 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),

  • Sl-004e-3 4-129 Rev. 3 March 27, 1987

RELIEF REQUEST 37 System EG Valve(s): SOV-EG-lOOA SOV-EG-lOOB SOV-EG-300A SOV-EG-300B 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 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) .
  • Sl-004e-3 4-130 Rev. 3 March 27, 1987
  • 4.5 REPORTING OF INSERVICE TEST RESULTS 4.5.1 PUMP INSERVICE PROGRAM Records of Pump Inseryice Test Results will be in accordance with the intent of Article IWP-6000. Files will be established for each pump and will include:
1. Pump identification by equipment number, manufacturer and serial number.
2. The record of test shall include:
a. date of test
b. measured and observed quantities
c. identification of instruments used,
d. comparison with allowable ranges of test valves and analysis of deviations
e. requirements for corrective actions
f. conducting and analyzing the test
3. Inservice test plans. This may be by surveillance test procedure by which the pump is tested with reference-drawing.
4. Summaries of corrective action some by maintenance report number, etc.

The Pump Inservice Test Program, associated surveillance test procedures and results will be kept at Surry Power Station.

They will be available for audit by the Authorized Nuclear Inservice Inspector and the NRC.

4.5.2 VALVE INSERVICE PROGRAM Records of Valve Inservice Test Results will be in accordance with the intent of Article IWV-6000, files will be established for each valve and will include:

1. Valve identification by equipment number, manufacturer, size, valve type, actuator type.

2~ The record of test shall include:

a. date of test
b. measured and observes quantities where applicable
c. identification of instruments used where applicable
d. comparisons with allowable ranges of test valves and analysis of deviations .
e. maintenance history
f. signature of the person or persons responsible for conducting and analyzing the test.

Sl-004~-3 4-131 Rev. 3 March 27, 1987

3. Summaries of maintenance history may be maintenance report numbers, etc.

The Valve Inservice Test Program, associated surveillance test procedures and results will be kept at Surry Power Station. They will be available for audit by the Authorized Nuclear Inservice Inspector and the NRC .

  • 4-132 Rev. 3 Sl-004e-3 March 27, 1987

4.6 QUALITY ASSURANCE PROGRAM The Pump and Valve Inservice Test Program activities will be conducted in accordance with the Nuclear Operations Department Standards Manual and Technical Specifications for Surry Power Station .

  • Sl-004e-3 4-133 Rev. 3 March 27, 1987

Descriptions of changes between Revision 1 and Revision 3 for the Surry Unit 1 System Pressure Tests Program are provided below. The page numbers refer to Revision 3.

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 1 is currently in the second inspection interval.

The verb tense has been changed accordingly.

5-5 Relief Request 22 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 21 and 23 have been added to Items C7.21 and C7. 41.

5-9 Relief Request 18 has been withdrawn from Item Dl .10.

5-10 Relief Request 14 has been withdrawn from Item D2.10.

5-12 Class I, II and III has been replaced by Class 1, 2 and 3.

This change occurs throughout the document.

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 11448-FM-72B 11448-FM-84B 11448-FM-75C 11448-FM-90C 11448-FM-90A 11448-FB-47B 11448-FM-106C 11448-FB-38A 11448-FB-41B 5-13 Note 5 was rearranged to enhance clarity.

5-14 Column title "VALVE" added to Note 7.

Drawings 11448-FM-84A, 11448-FM-89A and 11448-FB-4B were deleted from Note 8.

  • 5-15 Sl-OOSa-3 Section 5.4 was rewritten.

Rev.3 March 27, 1987

Description of Change

  • 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-430 and l-CH-312 was moved to Relief Request 5.

Technical detail was added to the Alternate Testing Method.

5-19 Relief Request 4 has been withdrawn.

5-20 Piping between check valves l-CH-430 and l-CH-312 was added to Relief Request 5.

Technical detail was added to the Alternate Testing Method.

5-23 The following changes were made to the column entitled, "Connected Piping":

Revision 1 Revision 3 30"-SHP-1-601 30"-SHP-1-601 to 2"-GN-23-601 to 6"-SHP-45-601 to 2"-GN-23-601 to 4"-SDHB-4-601 to 4"-SDHV-4-601

  • 14"-WFPD-17-601 30"-SHP-1-601 14-WFPD-17-601 to 3/4"-CFPD-3-601 30"-SHP-1-601 to 4"-SHP-25-601 The following additions were made to the column entitled, "Connected Piping":

2 l/2"-WGCB-601 30"-SHP-1-601 1"-WGCB-601 to 1 1/2"-SHPD-6-601 3"-RT-100-601 The following changes were made to the column entitled,

'Component"

Revision 1 Revision 3 NRV-MS-101A NRV-MS-101A l-MS-83,81,266,74 1-MS-83,81,266 l-WT-174 l-WT-176 The following addition was made to the column entitled, "Component":

l-MS-74 S1-005a-3 Rev.3 March 27, 1987

Description of Change

  • 5-24 The following changes "Connected Piping":

Revision 1 30"-SHP-2-601 were. made to the column entitled, Revision 3 30"-SHP-2-601 to 2"-:GN-24-601 to 6"-SHP-46-601 to 2"-GN-24-601 14"-WFPD-13-601 14"-WFPD-13-601 to 3/4"-CFPD-t-601 3"-SHP-2-601 30"-SHP-2-601 .

to 4"-SHP-26-601 The following additions were made to the column entitled, "Connected Piping":

2 1/2"-WGCB-601 30"-SHP-2-601 1"-WGCB-601 to 1 1/2"-SHPD-8-601 3"-RT-110-6,01 30"-SHP-2-601 to 4".-SHP-26-601 The following change was made to the column entitled, "Component":

Revision 1 Revision 3 NRV-MS....,lOlB NRV-MS-lOlB l-MS-115,268,113,106 l-MS-115, 268,113 1-WT-177 l-WT-179 The following additions were made to the column entitled, "Component":

l-MS-120,1-MS-378 l-MS-106 5.;.25 The following changes were made to the column entitled, "Connected Piping":

Revision 1 Revision 3 30"-SHP-3-601 30"-SHP-3-601 to 2"-GN-,25-601 to 6"-SHP:..47-601 to 2"-GN-25-601 14"-WFPD-9-601 14"-WFPD-9-601 to 3/4"-CFPD-1-601 S1-005a-3 Rev.3 March 27, 1987

Description of Change 5-25 The following additions were made to the column entitled, "Connected Piping":

2 1/2"-WGCB-601 1"-WGCB-601 3"-RT-120-601 30"-SHP-3-601 to 1 1/2"-SHPD-7-601 The following change was made to the column entitled, "Component":

Revision 2 Revision 3 NRV-MS-lOlC NRV-MS-lOlC 1-MS-152,151,208,143 1-MS-152,151,208 1-WT-182 1-WT-180 The following addition was made to the column entitled, "Component":

1-MS-143 5-29 Editorial change 5-30 The following changes were made to the column entitled, "Connected Piping":

Revision 1 Revision 3 6"-SI-49-1502 6"-SI-49-1502/

6"-SI-48-1502 6"-SI-48-1502 3"-SI-72-1503 3"-SI-72-1503 to 2"-SI-72-1503/

2"-SI-79-1502 2"-SI-77-1503/

2"-SI-80-1502 3"-:SI-14 7-1503 3"-SI-147-1503 to 2"-SI-73-1503 to 2"-SI-81-1502 3"-SI-70-1503 3"-SI-70-1503 to 2"-SI-70-1503/ to 2"-SI-70-1503/

2"-SI-75-1502 2"-SI-75-1502 2"-SI-76-1503/ 3"-SI-90-1503/

2"-SI-85-1502 3"-SI-70-1503

  • S1-005a-3 2"-SI-76-1503/

2"-SI-85-1502 3/4"-SI-68-1503 Rev.3 March 27, 1987

Description of Change

  • 5-30 The following changes were "Component":

Revision 1 l-SI-229 made to the Revision 3 l-SI-238 column entitled, l-SI-239 2"-SI-81-1502 l-SI-240 6"-SI-49-1502 2"-SI-79-1502 l-SI-240 l-SI-227 l-SI-257 l-SI-239 l-SI-255 l-SI-238 l-SI-226 l-SI-253 5-31 The Schedule For Implementation Section was changed from "Once each period" to "End of interval, within the last period".

5-32 The Component Section was rearranged to enhance clarity.

  • The Basis clarity.

for Relief Section Reference to Note 3 was deleted Method.

was in rewritten the Alternate to enhance Testing 5-33 Technical detail was added to the Basis for Relief.

5-34 Relief Request 14 has been withdrawn.

5-35 The drawing number was changed from* 11448-FM-71B to 11448-FM-71A.

5-36 Relief Request 16 has been withdrawn.

5-38 Relief Request 18 has been withdrawn.

5-39 Drawing number 11448-FM-42C was changed to 11448-FM-72C.

5-40 Drawing 11448-FM-71D was added to the components.

The Basis for Relief was rewritten to enhance clarity.

5-41 Relief Request 21 has been added.

  • 5-42 5-43 Relief Request 22 has been added.

Relief Request 23 has been added.

Note that Page 5-34 in Revision 1 was deleted.

S1-005a-3 Rev.3 March 27, 1987

VIRGINIA ELECTRIC AND POWER COMPANY SURRY .POWER STATION UNIT 1 SYSTEM PRESSURE.TESTS PROGRAM PLiW

  • S1-005a-3 5-1 Rev.3 March 27, 1987

SECTION 5 TABLE OF CONTENTS 5.0 SYSTEM PRESSURE TESTS PROGRAM PLAN

5.1 INTRODUCTION

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

  • Sl-005a-3 Rev.3 March 27, 1987

5.0 SYSTEM PRESSURE TESTS PROGRAM PLAN

  • 5.1. INTRODUCTION This System Pressure Test Program is applicable to the Surry Power Station Unit 1. This program covers the system pressure test requirements for ASME Class 1, 2 and 3 components.

development, implementation and administration of the program The for each class is detailed in subsequent sections .

  • Sl-005a-3 5-3 Rev.3 March 27, 1987

5.2 PROGRAM DESCRIPTION 5.2.1 The Surry Unit 1 System Pressure Test Program is in accordance with 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 1 is currently in the second inspection interval of Inspection Program B, IWA-2420. This interval started December 22, 1982 and coincides with the planned implementation of the proposed inspection program contained within this document. This proposed program will be effective at Surry Unit 1 for the second inspection interval or as modified by future ASME Code changes which are adopted at this station .

  • Sl-005a-3 5-4 Rev.3 March 27, 1987

5.3 SYSTEM PRESSURE TESTS

  • 5.3.1 CLASS 1 COMPONENTS (10 YEAR SCHEDULE)

A. EXAMINATION CATEGORY. B-E, PRESSURE PENETRATION WELDS IN VESSELS.

RETAINING PARTIAL 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 22 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

  • B4.13 INSTRUMEN-TATION NOZZLES VT-2 EXTERNAL SURFACE IWA-5250 TEST CONDUCTED DURING SYSTEM HYDROSTATIC 2,5 TEST B4.20 PRESSURIZER VT-2 EXTERNAL IWA-5250 CONDUCTED 2,5 HEATER SURFACE .DURING PENETRATION SYSTEM WELDS HYDROSTATIC TEST
  • Sl-005b-3 5-5 Rev. 3 March 27, 1987

B* EXAMINATION CATEGORY B-P, PRESSURE RETAINING COMPONENTS

  • ITEM NO.

B15.10 PARTS EXAM.

REACTOR VESSEL TEST REQRMT.

SYSTEM LEAKAGE EXAM.

METHOD VISUAL, VT-2 ACCEPT.

STANDARD IWA-5250 SCHEDULE

  • EACH REFUELING NOTES 1,5,9 RELIEF REQUEST 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 IWB-5222 Bl5.20 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 S1-005b-3 5-6 Rev. 3 March 27, 1987

B. EXAMINATION CATEGORY B-P, PRESSURE RETAINING COMPONENTS

  • ITEM NO.

B15.41 PARTS EXAM.

HEAT EXCHANGERS TEST REQRMT.

SYSTEM HYDRO-EXAM.

METHOD VISUAL, VT-2 ACCEPT.

STANDARD IWA-5250 SCHEDULE ONE TEST NOTES 1,2,5,6,9 RELIEF REQUEST 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 PRESSURE RETAINING BOUNDARY SYSTEM HYDRO-STATIC TEST, IWB-5222 VISUAL, VT-2 IWA-5250 ONE TEST 1,2,5,9 3 B15.70 VALVES SYSTEM VISUAL, IWA-5250 EACH 1,3,5,9 7 PRESSURE LEAKAGE VT-2 REFUELING RETAINING TEST, OUTAGE BOUNDARY IWB-5221 B15.71 VALVES SYSTEM VISUAL, IWA-5250 ONE 1,2,5,9 1,5,6 PRESSURE HYDRO- VT-2 TEST RETAINING STATIC BOUNDARY TEST, IWB-5222
    • S1-005b-3 5-7 Rev. 3 March 27, 1987

5.3.2 CLASS 2 COMPONENTS (10 YEAR SCHEDULE)

  • ITEM NO.

PARTS EXAMINED A. EXAMINATION CATEGORY C-H.

TEST REQRMT.

EXAM.

METHOD. STANDARD PRESSURE RETAINING COMPONENTS ACCEPT. SCHEDULE NOTES RELIEF REQUEST C7.10 PRESSURE SYSTEM VISUAL*, IWA-5250 ONCE 4,5,6,9 VESSELS FUNCTIONAL VT-2 PER PRESSURE TEST, INSPECTION RETAINING IWC-5221 PERIOD COMPONENTS C7 .11 PRESSURE SYSTEM VISUAL, IWA-5250 ONE 2,4,5,6,9 8 VESSELS HYDRO- VT-2 TEST PRESSURE STATIC RETAINING TEST, COMPONENTS IWC-5222 C7.20 PIPING SYSTEM VISUAL, IWA-5250 ONCE 4,5,9 11 PRESSURE FUNCTIONAL VT-2 PER RETAINING TEST, INSPECTION COMPONENTS IWC-5221 PERIOD C7.21 PIPING SYSTEM VISUAL, IWA-5250 ONE 2,4,5, 8,9,10,11, PRESSURE HYDROSTATIC VT-2 TEST 7,9 12,13,21,23 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 12,13,21,23 RETAINING STATIC COMPONENTS TEST, IWC-5222

  • Sl-005b-3 5-8 R~v. 3 March 27, 1987

5.3.3 CLASS 3 COMPONENTS (10 YEAR SCHEDULE)

  • ITEM NO.

PARTS EXAMINED A. EXAMINATION CATEGORY D-A, SYSTEMS IN SUPPORT FUNCTION.

TEST REQRMT.

EXAM.

METHOD ACCEPT.

STANDARD SCHEDULE OF NOTES REACTOR RELIEF REQUEST SHUTDOWN Dl.10 PRESSURE SYSTEM VISUAL, NO ONCE 5,6,8,9 RETAINING INSERVICE VT-2 LEAKAGE PER COMPONENTS +EST, INSPECTION IWD-5221 PERIOD Dl.10 PRESSURE SYSTEM VISUAL, NO ONE 2,5,6, RETAINING HYDRO- VT-2 LEAKAGE 8,9 19, 20 COMPONENTS STATIC TEST, IWD-5223

  • S1-005b-3 5-9 Rev. 3 March 27, 1987

B. EXAMINATION CATEGORY D-B, SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING,CONTAINMENT HEAT REMOVAL, ATMOSPHERE CLEANUP, 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 COMPONENTS , TEST, INSPECTION IWD-5221 PERIOD D2.10 PRESSURE SYSTEM VISUAL, NO ONE 2,5,6, 15, RETAINING HYDRO- VT-2 LEAKAGE TEST 8,9 19,20 COMPONENTS STATIC TEST, IWD-5223

  • Sl-OOSb-3 Rev. 3 March 27, 1987

C. EXAMINATION CATEGORY D-C, SYSTEMS IN SUPPORT OF RESIDUAL HEAT

  • ITEM NO.

D3.10 PARTS EXAMINED PRESSURE REMOVAL FROM SPENT FUEL STORAGE POOL TEST REQRMT.

SYSTEM EXAM.

METHOD

. VISUAL, ACCEPT.

STANDARD IWA-5250 SCHEDULE ONCE NOTES 5,6,

'8, 9 RELIEF REQUEST RETAINING INSERVICE VT-2 PER COMPONENTS TEST, INSPECTION IWD-5221 PERIOD D3.10 PRESSURE SYSTEM VISUAL, IWA-5250 ONE 2,5,6, 19 RETAINING HYDRO- VT-2 TEST 8,9 COMPONENTS STATIC TEST, IWD-5223

  • Sl-005b-3 5-11 Rev. 3 March 27, 1987

5.3.4 NOTES

  • Note 1 Class 1 Systems are drawn prints:

11448-FM-64A 11448-FM-68A on the following station 11448-FM-72A ll 448-FM-82B 11448-FM-86A 11448-FM-86B 11448-FM-87A 11448-FM-88C 11448-FM-89B 11448-FM-88B 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.

l-SI-109 l-SI-130 l-SI-147 AND l-SI-107, HCV-1850B AND l-SI-128, HCV-1850D, MOV-1720A AND l-SI-145, HCV-1850F, MOV-1720B Note 4 Class 2 Systems are drawn on the following station prints:

11448-FM-64A 11448-FM-84A 11448-FM-124A 11448-FM-64B 11448-FM-84B .' 11448-FM-138A 11448-FM""766A 11448-FM-85A 11448-SPS-14A 11448-FM-68A 11448-FM-86A -11448-FB-6A 11448-FM-68B 11448-FM-86B 11448-FB-47B 11448-FM.:..71A 11448-FM-87A 11448-FM-72A 11448-FM-88A.

11448-FM-72 C 11448-FM-88B 11448-FM-75E 11448-FM-88C*

11448-FM-75G 11448-FM-89A 11448-FM-75J 11448-FM-89B 11448-FM-82B 11448-FM-90C U448-FM-83A l 1448-FM-118A 11448-FM-83B 11448-FM-123A

  • Sl-005b-3 5-12 Rev. 3 March 27, 1987

Class 2 systems or components will be designated by a bracketed Bon the station prints .

Note 5 This station will use the following guidance for determining the completion of scheduled system pressure tests (i.e. Category B-E, 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/replacement.

Note 6 Visual Examination of Heat Exchangers will be conducted using the following methods:

a) When pressurizing the tube side of a heat exchanger, the tube integrity will be checked by the following methods. Fill and vent the shell side of the heat exchanger prior to the test and monitor an open vent path on the shell side during pressurization for overflow. Any overflow will be an indication of leakage. A drain method can be used by draining the shell side and observing leakage out the open drain path on the shell side.

b) When pressurizing the shell side of a heat exchanger, the tube integrity can be checked by the following method. Fill and vent the tube side of the heat exchanger prior to pressurization.

Monitor an open vent path on the tube side for overflow. Any overflow will be an indication of leakage.

The required visual examination of heat exchanger will be considered complete using either method above. Any

,discrepancies will be referred to the station's Repair/Replacement Program .

  • Sl-OOSb-3 5-13 Rev. 3 March 27, 1987

Note 7 For identification purposes, p1p1ng extending beyond

  • the valves listed below on station print 11448-FM-SSA will be considered open ended and in accordance with the requirements of IWC-5222(d) for test purposes.

VALVE PIPING l-LM-28 3/8"-LM-11-N7 l-LM-29 3/8"-LM-12-N7 l-LM-30 3/8"-LM-13-N7 l-LM-31 3/8"-LM-16-N7 Note 8 Class 3 Systems are on the following station prints:

11448-FM-64A 11448-FM-72G 11448-FM-68A 11448-FM-87 A 11448-FM-68B 11448-FM-88A 11448-FM-71A 11448-FM-88B 11448-FM-71B 11448-FM-88C 11448-FM-72A l 1448-FM-71D l 1448-FM-72B 11448-FM-130A 11448-FM-72C 11448-FM-72D 11448-FM-72E 11448-FM-72F 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 statron's Repair/Replacement Program as documented at the station .

  • Sl-OOSb-3 5-14 Rev. 3 March 27, 1987

5.4. SYSTEM PRESSURE TEST RELIEF REQUESTS

  • Relief Requests identify code requirements which are impractical for Surry Unit 1 and provide justification for the requested exception. Where appropriate, alternate testing t*o performed in lieu of the code requirements is proposed.

/

  • S1-005b-3 5-15 Rev. 3 March 27, 1987

_J

RELIEF REQUEST 1

  • Component(s): Piping between prints:

11448-FM-89B 11448-FM-88C following check valves located on station l-SI-79 AND l-SI-235, l-SI-241 l-SI-82 AND l-SI-236, l-SI-242 l-SI-85 AND l-SI-237, l-SI-243 l-SI-88 AND l-SI-238 l-SI-91 AND l-SI-239 l-SI-94 AND l-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

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 lOO-psid, thus ke~ping 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.

I Schedule For Implementation This test will be conducted toward the end of the second interval within the.third inspection period .

  • S1-005b-3 5-16 Rev. 3 March 27, 1987

RELIEF REQUEST 2

  • Relief Request Withdrawn
  • S1-005b-3 5-17 Rev. 3 March 27, 1987

RELIEF REQUEST 3

  • Component(s): Pumps located on station drawing 11448-FM-88C as listed:

1-RC-P-lA 1-RC-P-lB 1-RC-P-lC Piping associated from the flange to the pump Function Chemical and Volume Control System Class 1 Section XI Code Requirements For Which Relief Is Requested Class 1 System Hydrostatic Test, IWB-5222 Basis For Request The number one seal retur~ 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 damag~

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 .
  • . Sl-OOSb-3 5-18 Rev. 3 March 27, 1987

RELIEF REQUEST 4 Relief Request Withdrawn

  • Sl-OOSb-3 5-19 Rev. 3 March 27, 1987
  • Component(s):

l 1448-FM-88C:

RELIEF REQUEST 5 Piping and valves as listed located on stati9n print HCV-1311 and l-CH-313 l-CH-430 and l-CH-312 Function Chemical and Volume Control System Class Class 1 Section XI Code Requirements For Which Relief IS Requested:

Class 1 System Hydrostatic 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. The reactor will be borated 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* .

  • Sl-005b-3 5-20 Rev. 3 March 27, 1987

RELIEF REQUEST 6

  • Component(s): Piping and Valves located on station print 11448-FM-87A:

Component MOV-1701 Connected Piping 14"-RH-1-1502 Component MOV-1700 Function Residual Heat Removal Class 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-1700 is closed in addition to MOV-1701. This prevents pressurization of MOV-1701 and the piping between the two MOVS. Both valves are closed to prevent possible overpressurization of the Residual Heat Removal System.

Alternate Testing Method As an alternative, MOV-1701 and the piping between MOV-1701 and MOV-1700 will be tested in accordance with the Class 2 hydrostatic test to be administered to 14"-RH-18-602 on the suction side of the Residual Heat Removal pumps. This piping is protected from overpressure by RV-1721 which is set at 600 psig.

Class 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 test presented.

Schedule For Implementation End of interval, within the last period .

  • S1-005c-3 5-21 Rev. 3 March 21, 1987

RELIEF REQUEST 7 Component(s): Piping and Valves located on station print 11448-FM-87A:

  • Function Component MOV-1701 Residual Heat Removal Connected Piping 14"-RH-1-1502 Component MOV-1700 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-1700 and MOV-1701 closed for reasons expounded upon in Relief Request
6. This prevents pressurization of MOV-1701 and piping between the two MOVs.

Alternate Testing Method As an alternative, during* the conduct of the Class 2 functional test on 14"-RH-18-602, MOV-1701 will be open as well as MOV-1700. This piping will be examined to the normal VT-2 requirements at the functional test conditions.

Schedule For Implementation Once per inspection period .

  • Sl-005c-3 5-22 Rev. 3 March 21, 1987

RELIEF REQUEST 8

11448-FM-64A 11448-FM-64B 11448-FM-68A 11448-FM-124A 11448-FM-138A 11448-FM-123A Component Connected Piping Component 1-RC-E-lA 30"-SHP-1-601 SV-MS-lOlA to 30"-SHP-22-601 SV-MS-102A to 4"-SHP-37-601 SV-MS-103A SV-MS-104A SV-MS-105A RV-MS-lOlA 1-RC-E-lA 30"-SHP-1-601 1-GN-1 to 6"-SHP-45-601 to 2"-GN-23-601 1-RC-E-lA 30"-SHP-1-601 NRV-MS-101A to 6"-SHP-45-601 1-MS-83,81,266

  • 1-RC-E-lA 1-RC-E-lA 30"-SHP-1-601 to 30"-SHP-22-601 to 3"-SDHV-1-601 to 4"-SDHV-4-601 14"-WFPD-17-601 HCV-MS-104 1-FW-27 to 3/4"-CFPD-3-601 1-FW-10 1-WT-176 1-RC-E-lA 2 1/2"-WGCB-601 1-BD-1 1"-WGCB'.""6_01 1-BD-2 3"-RT-100-601 1-BD-4 l-RT-1 1-RC-E-lA 30"-SHP-1-601 1-MS-379 to 4"-SHP-25-601 1-MS-87 1-RC-E-lA 30"-SHP-1-601 l-MS-74 to 1 1/2"-SHPD-6-601
  • S1-005c-3 5-23 Rev. 3 March 21, 1987

RELIEF REQUEST 8 (CONT'D)

Component Connected Piping Component 1-RC-E-lB 30"-SHP-2-601 SV-MS-101B to 30"-SHP-23-601 SV-MS-102B to 4"-SHP-38-601 SV-MS-J03B SV-MS-104B SV-MS-105B RV-MS-101B 1-RC-E-lB 30"-SHP-2-601 1-GN-2 to 6"-SHP-46-601 to 2"-GN-24-601 1-RC-E-lB 30"-SHP-2-601 NRV-MS-101B to 6"-SHP-46-601 1-MS-115, 268,113 1-RC-E-lB 30"-SHP-2-601 HCV-MS-104 to 30"-SHP-23-601 to 3"-SDHV-2-601 to 4"-SDHV-4-601 1-RC-E-lB 14"-WFPD-13--601 1-FW-41,58 to 3/4"-CFPD-2-601 1-WT-179 1-RC-E-lB 2 1/2"-WGCB-601 1-BD-11 1"-WGCB-601 1-BD-12 3"-RT-110-601 1-BD-14 l-RT-20 1-RC-E-lB 30"-SHP-2-601 1-MS-120,1-MS-378 to 4"-SHP-26-601 1-RC-E-lB 30"-SHP-2-601 1-MS-106 to 1 1/2"-SHPD-8-601

  • S1-005c-3 5-24 Rev. 3 March 21, 1987

RELIEF REQUEST 8 (CONT'D)

  • Component 1-RC-E-lC Connected Piping 30"-SHP-3-601 to 30"-SHP-24-601 to 4"-SHP-39-601 Component SV-MS-101C SV-MS-102C SV-MS-103C SV-MS-104C SV-MS-105C RV-MS-lOlC 1-RC-E-lC 30"-SHP-3-601 l-GN-3 to 6"-SHP-47-601 to 2"-GN-25-601 1-RC-E-lC 30"-SHP-3-601 NRV-MS-101C to 6"-SHP-47-601 1-MS-152-, 151,208 1-RC-E-lC 30"-SHP-3-601 HCV-MS-104 to 30"-SHP-24-601 to 3"-SDHV-3-601 to 4"-SDHV-4-601 1-RC-E-lC 30"-SHP-3-601 1-MS-158 1-MS-377 1-RC-E-lC 14"-WFPD-9-601 1-FW-72 to 3/4"-CFPD-1-601 1-FW-89 1-WT-180 1-RC-E-lC 2 1/2"-WGCB-601 1-BD-21 1"-WGCB-601 1-BD-22 3"-RT-120-601 1-BD-24 1-RT 1-RC-E-lC 30"-SHP-3-601 1-MS-143 to 1 l/2"-SHPD-7-601
  • S1-005c-3 ,5-25 Rev. 3 March 21, 1987

RELIEF REQUEST 8 (CONT'D)

Function Main Steam Feedwater Steamm 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.

/

Sl-005c-3 5-26 Rev. 3 March 21, 1987

RELIEF REQUEST 9

  • Component(s): Valves and piping 11448-FM-68A:

Component 1-FW-12 on the following Connected Piping 14"-WFPD-17-601 station drawings Component 1-FW-10 1-FW-43 14"-WFPD-13-601 1-FW-41 1-FW-74 14"-WFPD-9-601 1-FW-72 1-FW-31 3"-WAPD-10-601 1-FW-27 to 3"-WAPD-9-601 1-FW-30 3"-WAPD-9-601 1-FW-27 1-FW-62 3"-WAPD-12-60.1 1-FW-58 to 3"-WAPD-11-601 1-FW-61 3"-WAPD-11-601 1-FW-58 1-FW-93 3"-WAPD-14-601 1-FW-89 to 3"-WAPD-13-601 1-FW-92 3"-WAPD-13-601 1-FW-89

2 Section XI Code Requirements For Which Rlief 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 piping as listed open to the steam generators. HydrostatiG 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 Request 8. As the individual steam generators. are tested the piping and valves attached in this request will be tested .

  • S1-005c-3 5-27 Rev. 3 March 21, 1987

RELIEF REQUEST 9 (CONT'D)

  • Schedule For Implementation End of inspection interval, within last period,
  • S1-005c-3 5-28 Rev. 3 March 21, 1987

RELIEF REQUEST 10

  • Component(s): Piping and valves 11448-FM-88C:

Component l-CH-311 as listed located Piping Connected 3/4"-CH-240-1502 on station print Component l-CH-312 HCV-1310A 3"-CH-1-1502 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 double one-way check valve placement of 1-CH-430 and l-CH-312 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 substitute 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 .

  • Sl-OOSc-3 5-29 Rev. 3 March 21, 1987

RELIEF REQUEST 11

  • Component(s): Piping and valves located on station prints 11448-FM-89A and 11448-FM-89B:

Component MOV-1890C Connected Piping 10"-SI-152-1502 Component to 6"-SI-153-1502 l-SI-243 to 6"-SI-145-1502 l-SI-241 to 6"-SI-144-1502 l-SI-242 MOV-1890A 6"-SI-49-1502/ l-SI-238 MOV-1890B 6"-SI-48-1502 l-SI-239 to 6"-SI-143-1502 to 6"-SI-49-1502 l-SI-240 to 6"-SI-50-1502 l-SI-174 and 3"-SI-72-1503 l-SI-227 MOV-1869A MOV-1869B 3"-SI-147-1503 l-SI-226 l-SI-150 3"-SI-70-1503 MOV-1867D to 2"-SI-70-1503/ l-SI-237 MOV-1867C 2"-SI-75-1502 l-SI-250 3"-SI-90-1503/

3"-SI-70-1503 2"-SI-76-1503/ l-SI-236 2"-SI-85-1502 l-SI-248 3/4"-SI-68-1503  !

MOV-1842 3"-SI-146-1503 l-SI-235 to 2"-SI-71-1503/ l-SI-245 2"-SI-74-1502 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 Check 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:5200°F). This pressure would overpressurize' the primary system since it cannot be isolated .

S1-005c-3 5-30 Rev. 3 March 21, 1987

RELIEF REQUEST 1.1 (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 *

  • Sl-005c-3 5-31 Rev. 3 March 21, 1987

RELIEF REQUEST 12

  • Component(s): Piping and valves located on station print 11448-FM-89B:

Component MOV-1865A l-SI-105 Connected Piping 12"-SI-45-1502 3/.4"-SI-33-1502 Component l-SI-107

, MOV-1865B , 12"--SI-46-1502 l-SI-128 l-SI-126 3/4"-SI-34-1502 MOV-1865C 12"-SI-47-1502 l-SI-145 l-SI-143 3/4"-SI-35-1502 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 273*3. 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-sy~tem.

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 pipirig (PO= 660 ~sig).

Schedule 'For Implementation_

End of interval, within the last perio*d *

  • S1-005c-3 5-32 Rev. 3 March 21, 1987

RELIEF REQUEST 13 Component(s): Piping and valves located on station print 11448-FM-84A .

Component Connected Piping Component l-CS-48 6"-CS-15-152 l-CS-47 6"-CS-14-152 l-CS-46 2"-CS-19-152 l-CS-45 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 1-CS-TK-1 (RWST) and piping up to l-CS-48 will be tested to system hydrostatic test criteria of IWC-5222(b,c). The piping and components 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 1-CS-48 the piping mentioned above must be tested in accordance with IWC-5222(a) .

Boundary valves necessary to isolate* IWC-5222(a) include piping (3"-FP-37-152 w/design pressure=lOO psig) which cannot be isolated from the test zone. Design pressure for the piping described above is 150 psig.

The lower design pressure would limit the pressure test required by IWC-5222(a). This test would be excessive sJnce the piping would only see pressure associated with the RWST when performing its safety function.

Alternate Testing Methoc!_

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 1-CS-TK-l" (RWST).

Schedule For Implementation End of interval, within the last period .

  • S1-005c-3 5-33 Rev. 3 March 21, 1987

RELIEF REQUEST 14

  • Relief Request Withdrawn

\

  • S1-005c-3 5-34 Rev. 3 March 21, 1987

RELIEF REQUEST 15

  • Component(s):

Function.

Cl~ss Open ended intake piping before the first shut-off valve non-closed systems located on 11448-FM-71A.

Circulating and Service Water System 3

in 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 test on open ende*d 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 piping at Surry Unit 1 as .it is non-isolatable 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,

.~onfirmation of adequate flow during system operation shall be acceptable in lieu of system hydrqstatic test.

Schedule For Implementation End of interval, within the last period *

  • S1-005c-3 5-35 Rev.* 3 March 21, 1987

RELIEF REQUEST 16 Relief Request Withdrawn

  • S1-005c-3 5-36 Rev. 3 March 21, 1987

RELIEF REQUEST 17

1-RC-E-lA 1-RC-E-lB 1-RC-E-lC Function Reactor Coolant System Class 1 Section XI Code Requirements For Which Relief Is Requested System Leakage Test, IWB-5221; System Hydrostatic Test, IWB-5222; Visual Examination, IWA-5240 Basis For Request Primary 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 *

  • Sl-005c-3 5-37 Rev. 3 March 21, 1987

RELIEF REQUEST 18

  • Relief Request Withdrawn
  • S1-005c-3 5-38 Rev. 3, March 21, 1987

RELIEF REQUEST 19

  • Component(s): Piping and Components located on the following prints:

11448-FM-72A 11448-FM-72B l 1448-FM-72C 11448-FM-72D 11448-FM-72E 11448-FM-72F 11448-FM-72G Function Component Cooling Water System Class Section XI Code Requirements For Which Relief Is Requested System Hydrostatic Test - IWD-5223 Basis For Relief 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 con~uming and delay unnecessarily the refueling

  • process.

Alternate Testing Method As an alternative, systems which can be isoiated 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 perio.d .

  • Sl-OOSc-3* 5-39 Rev. 3 March 21, 1987

RELIEF REQUEST 20

  • Component(s):

Function Piping and components located on the following print:

11448-FM-71B 11448-FM-71D Service Water System Class 3 Section XI Code Requirements For Which Relief Is Requested System Hydrostatic Test - IWD-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 1-SW-E-lA or lB between component cooling and service water. This pressure could be no more than 50 psig the maximum discharge pressure of 1-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 .
  • S1-005c-3 5-40 Rev. 3 March 21, 1987

RELIEF REQUEST 21 Component(s): Piping and valves located on the following prints:

11448-FM-89A:

Component Connected Piping Component l-SI-195 3/4"-SI-160-153 l-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, 1-SI-196, provides a pressure retaining boundary for two system hydrostatic tests (IWC-?222(a) and IWC-5222(b,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-5222(a), on 1-SI-P-lA, the one way check valve does not retain pr~ssure for that flow direction.

Alternate Testing Method As an alternative, the upstream isolation valve 1-SI-195 will be closed in order to provide a pressure boundary to perform the system hydrostatic test, IWC-5222(a), on 1-SI-P-lA. This enables the above mentioned piping to be hydrostatic tested up to the isolation valve, l-SI-195. The remaining piping and components mentioned in Section la will be tested to the requirements of IWC-5221(a,b), functional test.

Schedule For Implementation End of interval, within.the last period *

  • S1-005c-3 5-41 Rev. 3 March 21, 1987

RELIEF REQUEST 2*2

  • Component(s):

Function Class Penetrations located in the lower head of the Reactor Vessel .

Reactor Coolant System 1

Section XI Code Requirements For Which Relief Is Requested Class 1 System Hydrostatic Test, IWB-5222 Class 1 System Leakage rest, 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
  • Sl-OOSc-3 5-42 Rev. 3 March 21, 1987

RELIEF REQUEST 23 Component(s): Piping and valves, as listed, located on station prints:

11448-FM-SBB,C:

.component Piping Connected Component HCV~l310A,HCV-1311 3"-CH-1-1502 l-CH-304, l-CH-305 l-CH-311 2"-CH-68-1502 3/4"-CH-240-1502 3"-CH-79-1503 Function Chemical and Volume Control System Class 2 Section XL Code Requirements For Which Relief Is Requested Class 2 System Hydrostatic Test, IWC-5222 Basis For Relief The valve design of HCV-1310A prevents pressurization of the area listed above when condu~ting IWC-5222. The valve is required to be closed for IWC-5222 but when the* r~quired 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 from lifting. The hydrostatic test would be completed qut valve damage was incurred (bending stem, disc, seat, etc.)

Alternate Testing Method As an alternative, t~e 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.

Sl-005c-3 5-43

  • Rev. 3 March 21, 1987
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