Text

ISI Program,Interval 3,940510-040509, for Surry Power Station,Unit 2,rev 1
	ML18151A245
Person / Time
Site:	Surry
Issue date:	07/31/1994
From:	; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML18150A467	List: ML18150A466; ML18151A245; ML18153A246;
References
	PROC-940731-01, PROC-940731-1, NUDOCS 9804270408
	Download: ML18151A245 (187)
	v • d • e

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT-2 INSERVICE INSPECTION PROGRAM INTERVAL3 MAY 10, 1994 - MAY 9, 2004 REVISION 1

S2-001I3

~--9804270408-.. 980422.

PDR ADOCK 05000281 i

Rev. 1 7/94 G PDR

-i

ABSTRACT VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 INTERVAL 3 MAY 10, 1994 TO MAY 9, 2004 In accordance with 10CFR50.55a the Surry Unit 2 Inservice Inspection and Testing Program was updated to meet the requirements of ASME Section XI, 1989 Edition. Steam generator inspections will continue to be inspected under Plant Technical Specifications. Specific reliefs are requested in accordance with 10CFR50.55a(g) (5) (iii).

The interval for which this program is applicable commenced on May 10, 1994, and will end on May 9, 2004.

The Inservice Inspection Program was developed employing 10CFR50 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 on the following pages identifies the drawings used in developing the program.

Section 1 introduces the Inservice Inspection Program *

.Section 2 describes the Class 1, 2, and 3 component 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.

S2-001I3 Rev. 1 iii 7/94

TABLE OF CONTENTS SECTION TITLE PAGE PAGE NO. REVISION i Assignment i 1 ii Distribution Record ii 0 iii Abstract iii 1 iv Table of Contents iv 1 V List of Drawings V to vii 1 viii Relief Request Status viii 1 1 Introduction 1-1 to 1-2 1 2 Inservice Inspection Program 2-1 to 2-69 1 for Components 3 Inservice Inspection Program 3-1 to 3-6 1 for Component Supports 4 Interim Relief Requests and 4-1 to 4-2 1 Miscellaneous Documentation & Documents S2-001I3 Rev. 1 iv 7/94

UNIT 2 11548-CB-L&S-3 LIST OF DRAWINGS CB DRAWINGS Legend and Symbols UNIT 2 CBB DRAWINGS 11548-CBB-OOGA-3 Air Cooling and Purging System 11548-CBB-047B-3 Fire Protection System UNIT 2 CBM DRAWINGS 11548-CBM-064A-3 Main Steam System 11548-CBM-064B-3 Steam Generator Nitrogen Connection System 11548-CBM-066A-3 Auxiliary Steam and Air Removal System 11548-CBM-067A-3 Condensate System 11548-CBM-068A-3 Feedwater System 11548-CBM-O?lA-3 Circulating and Service Water System 11548-CBM-071B-3 Circulating and Service Water System 11548-CBM-072A-3 Component Cooling System 11548-CBM-072B-3 Component Cooling System 11548-CBM-072C-3 Component Cooling System 11548-CBM-O?SB-3 Compressed Air System 11548-CBM-O?SC-3 Compressed Air System 11548-CBM-O?SE-3 Compressed Air System S2-001I3 Rev. 1 V 7/94

~ LIST OF DRAWINGS CONT.

UNIT 2 CBM DRAWINGS 11548-CBM-075J-3 Containment Instrument Air System 11548-CBM-082A-3 Sampling System_

11548-CBM-083A-3 Vent and Drains System 11548-CBM-083B-3 Vent and Drains System 11548-CBM-084A-3 Containment Spray system 11548-CBM-084B-3 Recirculation Spray System 11548-CBM-OSSA-3 Containment Vacuum and Leakage Monitoring System.

11548-CBM-086A-3 Reactor Coolant System 11548-CBM-086B-3 Reactor Coolant system 11548-CBM-087A-3 Residual Heat Removal System 11548-CBM-OSSA-3 Chemical and Volume Control System 11548-CBM-OSSB-3 Chemical and Volume Control system 11548-CBM-OSSC-3 Chemical and Volume Control System 11548-CBM-089A-3 Safety Injection System 11548-CBM-089B-3 Safety Injection System 11548-CBM-llSA-3 Reactor Cavity Purification System 11548-CBM-124A-3 Steam Generator Blowdown and Recirc. and Transfer System 11548-CBM-130B-3 Containment Particulate System Additionally, several Unit 1 drawings contain Unit 2 Components.

These follow:

11448-CBM-068A-3 Feedwater System 11448-CBM-071B-3 Circulating and Service Water System S2-001I3 Rev. 1 vi 7/94

l

11448-CBM-071D-3 11448-CBM-072C-3 11448-CBM-072D-3 Circulating and Service Water System Component Cooling System Component Cooling System 11448-CBM-072E-3 Component Cooling System 11448-CBM-072G-3 Component Cooling System 11448-CBM-082A-3 Sampling System 11448-CBM-OBBA-3 Chemical and Volume Control System 11448-CBM-090C-3 Containment Hydrogen Analyzer System S2-00113 Rev. 1 vii 7/94

RELIEF REQUEST STATUS Relief No. Status VP Letter No. NRC Letter No.

SR-001 Granted 94-006 3/18/94 95-480 8/30/95 SR-002 Granted 94-006 3/18/94 95-480 8/30/95 With Conditions SR-003 Granted 94-006 3/18/94 95-480 8/30/95 SR-004 Granted 94-006 3/18/94 95-480 8/30/95 SR-005 Granted 94-006 3/18/94 95-480 8/30/95 SR-006 Granted 94-006 3/18/94 95-480 8/30/95 With Conditions SR-007 Granted 94-006 3/18/94 95-480 8/30/95 SR-008 Granted 94-006 3/18/94 95-480 8/30/95 SR-009 Granted 94-006 3/18/94 95-480 8/30/95 With Conditions SR-010 Granted 94-006 3/18/94 95-480 8/30/95 SR-011 Granted 94-006 3/18/94 95-480 8/30/95 SR-012 Granted 94-006 3/18/94 95-480 8/30/95 SR-013 Granted 94-006 3/18/94 95-480 8/30/95 SR-014 Granted 96-009 2/7/96 97-252 4/11/97 SR-015 Granted 96-009 2/7/96 97-252 4/11/97 With Conditions SR-016 Granted 96-009 2/7/96 97-252 4/11/97 With Conditions SR-017 Granted 96-009 2/7/96 97-252 4/11/97 With Conditions SR-018 Pending 96-606 1/2/97 SR-019 Pending 96-606 1/2/97 SR-020 Pending 96-606 1/2/97 SR- 021 Pending 96-606 1/2/97 SR-022 Withdrawn 97-286 6/2/97 SR-023 Pending 96-606 1/2/97 SR-024 Pending 96-606 1/2/97 SR-025 Granted 97-216 6/2/97 97-699 11/24/97 RR-001 Granted 94-006 *3/18/94 95-480 8/30/95 RR-002 Granted 94-006 3/18/94 95-480 8/30/95 RR-003 Granted 94-006 3/18/94 95-480 8/30/95 RR-004 Granted 94-006 3/18/94 95-480 8/30/95 RR-005 Removed - Superseded by RR-005 (Rev. 1)

RR-005 Rev. 1 Granted 96-167 6/24/96 96-524 10/8/96 With Conditions RR-006 Granted 94-006 3/18/94 95-480 8/30/95 IWE-1 Granted 97-264 5/22/97 97-579 10/1/97 S2-001I3 Rev. 1 viii 7/94

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT2 INSERVICE INSPECTION PROGRAM S2-00113 Rev. 1 1-1 7/94

1.0 INTRODUCTION

1.1 GENERAL INFORMATION Surry Power Station Unit 2 is a Pressurized Water Reactor located on Gravel Neck and adjacent to the James River in Surry County, Virginia. The plant employs a Westinghouse Electric Corp. Nuclear Steam System.

The Inservice Inspection (ISI) Program for Surry Nuclear Power Station Unit 2*was developed in compliance with the rules and regulations of 10CFR50.55a and Section XI of the ASME Boiler and Pressure Vessel Code, 1989 Edition. Where these rules are determined to be impractical, specific relief is requested in writing.

The Inservice Inspection Program for Class 1, 2, and 3 Components and Components Supports is applicable for the ten year interval beginning May 10, 1994 and ending May 9, 2004. This interval is the third inspection interval for Surry Unit 2.

1.2 SYSTEM CIASSIFICATION 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 10CFR50.55a paragraph (g) (1), inservice inspection requirements of Section XI of the ASME Code are then assigned to these components, within the constraints of existing plant design.

Classification boundary drawings (CBM's) documenting the system classifications were developed to aid in the review and implementation of the subject programs.

S2-001I3 Rev. 1 1-2 7/94

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT2 INSERVICE INSPECTION PROGRAM FOR COMPONENTS S2-002I3 Rev. 1 2-1 7/94

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

SUMMARY

2.3 RELIEF REQUESTS Rev. 1 S2-002I3 2-2 7/94

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, 1989 Edition. Where these requirements are determined to be impractical, specific requests for relief have been written and included in this section.

2.1.2 The 1989 Edition of ASME Section XI includes subsections IWE and IWL for Class MC and Class cc components. This program currently excludes these components as not being within the scope of 10CFR50.55a at this time.

2.1.3 Repairs and replacements shall be in accordance with Station Administrative Procedures, which assure Code Requirements are satisfied.

2.2 PROGRAM

SUMMARY

2.2.1 The Inservice Inspection Program for Surry Unit 2 utilizes the tables IWB-2500-1, IWC-2500-1, and IWD-2500-1 of the 1989 Edition of the ASME Section XI Code. Components selected for examination are identified in the Inservice Inspection Program Plan.

2.2.2 Categories B-E, B-P, C-H, D-A, D-B, and D-C constitute the scheduled 10-year interval pressure testing requirements. Additionally, Code Case N-498, see below, will be followed.

The following guidance will be utilized programmatically concerning pressure testing.

a) Pressure tests which meet the pressure, temperature, hold time, and VT-2 examination requirements of IWA-5000, IWB-5000, IWC-5000, IWD-5000, or Code Case N-498 as applicable will be treated as complete for inspection scheduling purposes.

b) Visual VT-2 examinations of tubes within the steam generators or other heat exchangers will not be conducted, as it is not considered within the scope of ASME Section XI.

S2-002I3 Rev. 1 2-3 7/94

2.2.3 c) Pressure tests required for ASME section XI repairs or replacements will be conducted in accordance with the station's repair replace-ment program as documented at the station.

The following Code Cases are in use at Surry Power Station Unit 2, subject to modification per Reg. Guide 1.147, and as specified below.

Code Case N-401-1 Eddy current Examination,Section XI Division 1.

Code Case N-402 Eddy Current Calibration st-andard Material,Section XI, Division 1.

Code Case N-416 Alternative Rules for Hydro-static Testing of Repair or Replacement of Class 2 Pip-ing,Section XI, Division 1.

Code Case N-416-1 Alternative Pressure Test Re-quirement for Welded Repairs or Installation of Replace-ment Items by Welding, Class 1, 2 and 3 Section XI, Divi-sion 1.

Approved with conditions by NRC Letter 94-623, Dated 10-14-94, see Section 4.0, paragraph 4.1.1.

Conditions: Additional surface ~xaminations are re-quired to be performed on the root {pass) layer of butt and socket welds on the pressure retaining boundary of Class 3 components when the surface examination method is used in accordance with Section III.

Code Case N-435-1 Alternative Examination Requirements for Vessels with Wall thickness 2 in. or less,Section XI, Division 1.

Code Case N-437 Use of Digital Readout and Digital Mea-surement Devices for Performing Pressure TestsSection XI, Division 1.

Code Case N-460 Alternative Examination coverage for Class 1 and Class 2 Welds,Section XI, Division 1.

S2-002I3 Rev. 1 2-4 7/94

Code Case N-461 Alternative Rules for Piping Calibration Block Thickness,Section XI, Division 1.

Code Case N-481 Alternate Examination Requirements for Cast Austenitic Pump Casings,Section XI, Division 1.

Code Case N-489 Alternative Rules for Level III NDE Qual-ification Examinations,Section XI, Divi-sion 1.

Code Case N-491 Alternative Rules for examination of Class 1, 2, 3, and MC Component Supports of Light-Water Cooled Power Plants Sec-tion XI, Division 1.

Approved by NRC Letter 95-480, Dated 8-30-95, see Sec-tion 3.0, paragraph 3.1.

Code Case N-498 Alternative Rules for 10-year Hydrostatic Pressure Testing for Class 1 and 2 Sys-tems,Section XI, Division 1.

Code Case N-509 Alternative Rules for the Selection and Examination of Class 1, 2, and 3 Inte-grally Welded AttachmentsSection XI, Division 1.

Approved by NRC Letter 95-480, Dated 8-30-95, see Relief Request SR-009.

Code Case N-522 Pressure Testing of Containment Penetra-tion Piping Section XI, Division 1.

Approved with conditions by NRC Letter 96-216, Dated 4-16-96, see Section 4.0, paragraph 4.1.3.

Conditions: The pressure-retaining integrity of the containment isolation valves and con-necting piping, and their associated safety functions, may be verified with an Appendix J, Type C test if it is conducted at the calculated peak con-tainment pressure. The seal between the connecting pipe segment and containment may be verified using an Appendix J, Type B test. Therefore, when the connecting pipe segment is subject to either a Type B or C test, its safety function is verified and the Code case may be used.

S2-002I3 Rev. 1 2-5 7/94

Code Case N-522 (Conditions continued)

For Class 2 pipe segments between con-tainment isolation valves that are not subject to either a Type B or c test, the safety function is not verified and the Code Case may not be used.

Code Case N-524 Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping Section XI, Division 1.

Approved by NRC Letter 94-569, Dated 9-17-94, see Section 4.0, paragraph 4.1.2.

Code Case N-535 Alternative Requirements for Inservice Inspection IntervalsSection XI, Division 1.

Approved by NRC Letter 96-216, Dated 4-16-96, see Section 4.0, paragraph 4.1.3.

2.2.4 Isometric Drawings (WMKS) do not specifically identify underground piping welds, however weld selection in the ISI Plan has included the number of underground welds in the percentages selected.

2.2.5 New High Pressure Safety Injection Isometric Drawings (WMKS) were required for the third interval update. These new drawings were based upon drawings which do not give precise support information. These drawings will require further development to incorporate the required component support information. The drawing information and required component support examinations will be completed prior to the end of the third interval.

2.2.6 The requirements of Regulatory Guide 1.150, Rev.

1, Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations, will be followed.

2.2.7 Augmented inspections coordinated by the Inservice Inspection Group are identified within the Inservice Inspection Program Plan.

S2-002I3 Rev. 1 2-6 7/94

2.3 RELIEF REQUESTS 2.3.1 Nondestructive examination (NDE) relief requests are presented in a numeric sequence with a SR prefix.

Pressure tests relief requests are presented in a numeric sequence with no prefix.

S2-002I3 Rev. 1 2-7 7/94

I.

Status:

RELIEF REQUEST SR-001 Granted - NRC Letter No.95-480 Dated 8/30/95 IDENTIFICATION OF COMPONENTS Weld# Drawing # Class 1-0lDM 11548-WMKS-RC~l0-1 1 1-17DM 11548-WMKS-RC-10-1 1 1-0lDM 11548-WMKS-RC-ll-1 1 1-17DM 11548-WMKS-RC-ll-1 1 1-0lDM 11548-WMKS-RC-12-1 1 1-17DM 11548-WMKS-RC-12-1 1 The reactor vessel nozzle-to-safe end butt welds II. IMPRACTICAL CODE REQUIREMENTS Category B-F, Item B5.10 requires that a volumetric and surface examination be performed. The surface examination must be performed from the outside diameter of the reactor vessel nozzle-to-safe end welds.

III. BASIS FOR RELIEF The outside diameter volumetric examination would be extremely difficult to perform. Access to the area is restricted by permanent neutron shielding and support structures. Any planned removal to provide access is made difficult by the relatively small sandplug access on the floor of the refueling cavity. The difficult access restrictions are also complicated by the anticipated high dose level. The general area estimate around the perimeter of the vessel and nozzle area is 1000 to 2000 MR/HR. The contact estimate ranges from 4000 to 8000 MR/HR in the vicinity of the sliding foot support.

III. ALTERNATE REQUIREMENTS Alternately it is requested that an automated examination from the inside diameter, in conjunction with the vessel examination, be accepted in lieu of the surface examination from the O.D. This relief request was granted to permit this alternative for the second interval based upon examinations from the I.D. of a Surry calibration block which demonstrated sensitivity adequate to resolve a 5%

notch on the O.D. In addition, this ultrasonic technique demonstrated detection of a flaw in a mock-up which was estimated to be eighty percent of the critical flaw as S2-002I3 Rev. 1 2-8 7/94

RELIEF REQUEST SR-001 (CON'T) described in 1980 Edition, Winter 1980 Addenda of ASME Section XI, IWB-3000 Acceptance Standards for Flaw Indications.

The demonstration of the above ultrasonic technique was witnessed by Authorized Nuclear Inservice Inspector at the Westinghouse Waltz Mill Calibration Facility and found to be acceptable. This was also demonstrated to the NRC staff on June 24, 1986 (reference NRC Letter serial #86-759, dated Nov. 12, 1986).

S2-002I3 Rev. 1 2-9 7/94

RELIEF REQUEST SR-002 Status: Granted With conditions* -

NRC Letter No.95-480 Dated 8/30/95 I. IDENTIFICATION OF COMPONENTS Nozzle Inner Radius Sections (Primary Side Steam Generator}

Mark # Component # Drawing # Class 1-0lANIR 2-RC-E-lA 11548-WMKS~RC-E-lA.2 1 1-0lBNIR 2-RC-E-lA 11548-WMKS-RC-E-lA.2 1 1-02ANIR 2-RC-E-lB 11548-WMKS-RC-E-lB.2 1 1-02BNIR 2-RC-E-lB 11548-WMKS-RC-E-lB.2 1 1-03ANIR 2-RC-E-lC 11548-WMKS-RC-E-lC.2 1 1-03BNIR 2-RC-E-lC 11548-WMKS-RC-E-lC.2 1 II. IMPRACTICAL CODE REQUIREMENTS Category B-D, Item No. B3.140 requires the volumetric examination of the nozzle inside radius sections of the steam generator primary nozzles.

III. BASIS FOR RELIEF The only viable ultrasonic technique currently available to examine nozzle inner radii involves the fabrication of calibration blocks that closely simulate the O.D. and I.D.

nozzle geometry. This is necessary so that search units can be produced that will interrogate the inner radius section at precise angles. When the beam angle varies it is not possible to locate indications or discriminate between flaws and geometry. Also, in order to obtain meaningful results, the*

nozzle material grain structure must be such that a relatively high signal-to-noise ratio can* be obtained over the required metal path distance. Additionally, for nozzles with a complex O.D. profile, examination personnel need training on the proper placement and manipulation of the search unit.

Virginia Power has previously assessed the feasibility of performing examinations on the North Anna Unit 2 cast primary nozzle inner radii. Virginia Power performed examinations on a Westinghouse Model 44 channel head which was used to train welders for the North Anna Unit 1 steam generator replacement.

This channel head is made from the same cast material (ASTM 216-WGG} as Model 51 generators which are currently installed in Surry Unit 2. We believe that the general surface profile and acoustic properties are representative of the Surry Unit 2 steam generators.

S2-002I3 Rev. 1 2-10 7/94

RELIEF REQUEST SR-002 EXAMINATION RESULTS

1. Comparison of Material Noise (CON'T.)

Figures A and Bon Attachment 1 depict the respective responses from notches 4 and 6 from calibration &2block VPSGINRl. This calibration block was manufactured to examine the North Anna Unit 1 replacement steam generator forged carbon steel primary nozzle inner radii. Both notch responses exhibit a high signal to noise ratio with little evidence of material noise. Figure A on Attachment 2 depicts the material noise from the Model 44 primary nozzle at the same sensitivity level. At this sensitivity level, there is no evidence of clad roll.

The first indication of sound penetration (Attachment 1, Figure B) appeared at 12db above the reference level when evidence of clad roll was detected.

2. Surface Profile The O.D. surface of the nozzle had an irregular contour which is typical of large cast products. Due to the surface contour, it was necessary to apply a large amount of couplant to maintain contact with the examination surface. The irregular surface and large amount of couplant required caused an apparent change in the sound beam angle from point to point over the examination surface. Therefore, it could not be determined where the sound beam was directed with respect to the inner radius.

CONCLUSION The Surry Unit 2 steam generator primary nozzle inner radii were not designed for ultrasonic examination from the O.D.

The nozzles are integrally cast into the channel head.

Therefore, the nozzles contain examination limitations such as an irregular O.D. profile, a rough surface condition, and an attenuating grain structure. The irregular surface causes the beam angle to change from point to point around the nozzle. The varying beam angle combined with a relatively low signal-to-noise ratio makes evaluation of the results extremely difficult. Furthermore, it would be unduly difficult to design a practical search unit for this configuration. As a result of the above limitations, it is our opinion that a full scale cast mock-up of the nozzle would be necessary to develop an inner radius examination technique, and to correspondingly provide appropriate training for the examination personnel. As such, the Code prescribed examination is deemed impractical.

S2-002I3 Rev. 1 2-11 7/94

~ RELIEF REQUEST SR-002 (CON'T.)

IV. ALTERNATE PROVISIONS As an alternative, the areas will be visually (VT-1) examined from the nozzle I.D. using direct or remote methods per the schedule shown in Table IWB-2412-1.

Conditions: If a remote VT-1 visual examination is performed the system must have color capability.

S2-002I3 Rev. 1 2-12 7/94

ATTACHMENT 1 f.1*,~

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FIGURE A Response from Notch 4 in VPSGINRl at 9.05 11 Metal

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FIGURE B Response from Notch 6 in VPSGINRl at 13.27" Metal

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. s: ; ,. ::, n ; r, S2-002I3 Rev. 1 2-13 7/94

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First evidence of clad roll from I.D. at inner radius.

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Sensitivity is a 91.1 dB.

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,; [1£F'TH= * *-:s--**-.;.a-..._a Rev. 1 S2-002I3 2-14 7/94

~ RELIEF REQUEST SR-003 status: Granted - NRC Letter No.95-480 Dated 8/30/95 I. IDENTIFICATION OF COMPONENTS Nozzle Inner Radius Section (Pressurizer surge nozzle)

Weld# Component# Drawing# Class 15NIR 2-RC-E-2 11548-WMKS-RC-E-2 1 II. IMPRACTICAL CODE REQUIREMENTS Category B-D, Item B3.120 requires the volumetric examination of the nozzle inside radius section of the pressurizer surge nozzle.

III. BASIS FOR RELIEF The Surry Unit 2 pressurizer surge line nozzle is integrally cast into the bottom pressurizer head. The nozzle is located under the pressurizer skirt and is surrounded by 78 heater penetrations. Interference from the heater penetrations and heater cables, as well as the location of the nozzle under the pressurizer skirt restricts the access to the nozzle.

This limits the examiners ability to manipulate the search unit to examine the nozzle inner radius~

The only viable ultrasonic technique currently available to examine nozzle inner radii involves the fabrication of calibration blocks that closely simulate the O.D. and I.D.

nozzle geometry. This is necessary so that search units can be produced that will interrogate the inner radius section at precise angles. Also, in order to obtain meaningful results, the nozzle material grain structure must be such that an adequate signal-to-noise ratio can be obtained over a long metal path distance.

Integrally cast nozzles contain limitations such as an irregular O.D. profile, a rough surface condition, and an attenuating grain structure. The irregular surface condition causes the beam angle to vary from point to point around the nozzle. The attenuating grain structure results in a low signal-to-noise ratio at the nozzle inner radius. Limited access to the nozzle as well as the limitations imposed by the material conditions, area dose rates and the complicated nature of the examination technique would make evaluation of any indications very difficult.

S2-002I3 Rev. 1 2-15 7/94

RELIEF REQUEST SR-003 (CON'T)

Any examination on this nozzle could only be described as "best effort", and not commensurate with the anticipated exposure to perform this examination.

It is estimated that at least 3.675 man-rem would be required to perform this inspection and if the cables to the heater penetrations require removal to provide better access, then greater than 9 man-rem would be required.

IV. ALTERNATE REQUIREMENTS A visual {VT-2) examination of the pressurizer surge line nozzle area will be performed during the normally scheduled pressure test {Class 1) each refueling.

S2-002I3 Rev. 1 2-16 7/94

.

RELIEF REQUEST SR-004 Status: Granted - NRC Letter No.95-480 Dated 8/30/95 I. IDENTIFICATION OF COMPONENTS systems: outside Recirculation Spray (RS) and Safety Injection (SI)

Components: Pump casing welds identified below Component Weld Drawing# Class 2-RS-P-2A 2-01 11548-WMKS-RS-P-2A 2 2-RS-P-2A 2-02 11548-WMKS-RS-P-2A 2 2-RS-P-2A 2-03 11548-WMKS-RS-P-2A 2 2-RS-P-2A 2-04 11548-WMKS-RS-P-2A 2 2-RS-P-2B 2-01 11548-WMKS-RS-P-2B 2 2-RS-P-2B 2-02 11548-WMKS-RS-P-2B 2 2-RS-P-2B 2-03 11548-WMKS-RS-P-2B 2 2-RS-P-2B 2-04 11548-WMKS-RS-P-2B 2 2-SI-P-lA 2-01 11548-WMKS-SI-P-lA 2 2-SI-P-lA 2-02 11548-WMKS-SI-P-lA 2 2-SI-P-lA 2-03 11548-WMKS-SI-P-lA 2 2-SI-P-lA 2-04 11548-WMKS-SI-P-lA 2 2-SI-P-lB 2-01 11548-WMKS-SI-P-lB 2 2-SI-P-lB 2-02 11548-WMKS-SI-P-lB 2 2-SI-P-lB 2-03 11548-WMKS-SI-P-lB 2 2-SI-P-lB 2-04 11548-WMKS-SI-P-lB 2 II. IMPRACTICAL CODE REQUIREMENTS Category C-G, Item C6.10, Pump casing Welds, requires that a surface examination be performed on 100% of the welds each interval. The examination can be limited to one pump in the case of multiple pumps of similar design, size, function, and service in a system.

III. BASIS FOR RELIEF These pumps are vertical, two-stage, centrifugal pumps, with an extended shaft and casing to allow suction from the containment sump. The motor and mechanical seals of the pumps are located at approximately the 12 foot elevation and the bottom of the casing is located at approximately the -30 foot elevation. The welds identified are at the bottom of the pump casing, and are embedded within the concrete building structure. This makes the welds inaccessible from the outside.

The small diameter of the casing (24 inch. O.D.) and the pump shaft prevent examination from the inside diameter.

S2-002I3 Rev. 1 2-17 7/94

e IV.

RELIEF REQUEST SR-004 (CON'T)

ALTERNATE REQUIREMENTS A visual examination (VT-1) of the accessible portions of the I.D. of the pump casing welds will be performed only if the pump is disassembled and the pump shaft removed for maintenance.

e S2-002I3 2-18 Rev. 1 7/94

I.

status:

RELIEF REQUEST SR-005 Granted - NRC Letter No.95-480 Dated 8/30/95 IDENTIFICATION OF COMPONENTS Ultrasonic calibration blocks II. IMPRACTICAL CODE REQUIREMENTS ASME Section XI, Appendix I specifies requirements for ultrasonic calibration blocks. Specifically, calibration blocks must meet the requirements of ASME Section V (vessels

> 2 11 thick) or ASME Section XI, Appendix III (piping and vessels ~ 2") as supplemented by Table I-2000-1. The existing calibration blocks at Surry Unit #2 were designed and fabricated before the guidelines ,of ASME Section XI were developed and approved.

The blocks for piping and vessels~ 2 11 do not meet the recommended design specified by Figure III-3230-2 for thicknesses< 1 11 in that the notches are not staggered. Also, the notches in most of the piping blocks are located 1 "t" from the end of the block instead of 1 1/2" as specified by Figure III-3230-1. The vessel calibration blocks used for the RV head-to-flange weld, SG primary side tubesheet-to-head weld, and pressurizer welds are partially clad instead of fully clad as shown by Figure T-441.1 of ASME Section V, Article 4.

III. BASIS FOR RELIEF Meeting the above new ASME Section XI requirements would require the fabrication of new calibration blocks.

Satisfactory ultrasonic system calibration can be performed with the existing calibration blocks. Use of the existing calibration blocks also allows correlation of ultrasonic data from previous interval examinations as required by IWA-1400(h). The location of the notches in the piping calibration blocks provides adequate signal separation for sweep calibration. Distance-amplitude calibration down to the clad-to-base metal interface, as delineated by Nonmandatory Appendix B to Section V, Article 4, can be performed from the unclad.portion of the clad side of the existing vessel calibration blocks.

IV. ALTERNATIVE REQUIREMENTS It is proposed that the existing calibration blocks be used during the third inspection interval.

S2-002I3 Rev. 1 2-19 7/94

I.

RELIEF REQUEST SR-006 Status: Granted With Conditions* -

NRC Letter No.95-480 Dated 8/30/95 IDENTIFICATION OF COMPONENTS ISI class 1 and 2 piping, vessel and component welds II. IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code. 1989 Edition, IWA-2600, weld reference system III. BASIS FOR RELIEF The original construction code used at Surry Power Station, ASA B31.1-1955 with the applicable nuclear code cases, did not establish a weld reference system. Immediate establishment of a weld reference system cannot be practically attained within the scope and schedule of existing outages.

IV. ALTERNATE REQUIREMENTS Surry Unit 2 has recently updated its weld isometrics, providing a detailed identification of weld location. These drawings will be used in tracking and locating welds.

In addition at the time welds are examined volumetrically for program requirements, a reference will be established for each weld, indicating a zero point and direction of examination.

Welds which contain recordable indications (RI) shall be marked to ensure location of the indication, using appropriate reference marks. This reference system and marks will be permanently fixed on the weld.

Conditions: Each Class 1 and 2 piping weld examined will receive all of the required reference marking as the inservice examinations are performed.

S2-002I3 Rev. 1 2-20 7/94

~ RELIEF REQUEST SR-007 status: Granted - NRC Letter No.95-480 Dated 8/30/95 I. IDENTIFICATION OF COMPONENTS Pressure retaining welds in the reactor vessel and vessel nozzle area examined by the automated vessel tool inspection device.

II. IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1989 Edition, IWA-2600, weld reference system III. BASIS FOR RELIEF The automated tool establishes its reference point using an existing zero reference in the reactor vessel. This point allows the device to repeat examination locations without the necessity of any other reference systems. It accomplishes this by the use of an electronic encoder system which provides for sufficient repeatability.

IV. ALTERNATE REQUIREMENTS The automated vessel tool examinations will continue to establish it's reference system based upon the existing zero reference. No other system is planned or deemed necessary.

S2-002I3 Rev. 1 2-21 7/94

~ RELIEF REQUEST SR-008 status: Granted - NRC Letter No.95-480 Dated 8/30/95 I. IDENTIFICATION OF COMPONENTS ISI Class 1 Pressure Retaining Welds in Piping II. IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1989 Edition, requires that notes l(b) and 2 of Category B-J, table IWB-2500-1 be used in the selection of welds for examination.

III. BASIS FOR RELIEF The second interval selection was based upon the 1974 Edition with Summer 1975 Addenda (74/S75) of ASME Section XI. As a result notes l(b) and 2 cannot be applied without some programmatic additions and modifications. In addition, although stress and utilization calculations exist for Surry Unit 2, no correlation exists with actual weld locations.

Total reuse of the second interval plan is not desirable, since even though the 74/S75 requirements were met, distribution of welds selected did not equitably cover certain line functions and designs ..

IV. ALTERNATE REQUIREMENTS ISI Class-1 piping welds will be selected for examination such that 25% of the total number of welds are examined during the interval. The 25% sampling will include terminal ends as they appear on our plant isometrics as no corresponding stress calculations exist (ref. NUREG-0800, BTP 3.6.2-13). Terminal ends will include extremities of piping runs connected to vessels and pumps. Pipe integral attachments that act as rigid constraints to piping motion and thermal expansion shall have the first weld upstream and downstream of the integral attachment selected. In piping runs which are maintained pressurized during normal plant conditions for only a portion of the run, the first normally closed valve is a terminal end.

The weld on the high pressure side of the valve will be included in the interval selection. Additionally all branch connections will be selected. Terminal end welds are identified in the third interval plan by the designation "Terminal End" in the comments column. The welds selected will be evenly distributed based upon line size, line function, and line design to the extent practicable. These selected welds will be examined in future successive inspection intervals to the extent allowed by code editions approved at that time.

S2-002I3 Rev. 1 2-22 7/94

I.

RELIEF REQUEST SR-009 Status: Granted with conditions* -

NRC Letter No.95-480 Dated 8/30/95 IDENTIFICATION OF COMPONENTS Class 1, 2, and 3 Integrally Welded Attachments II. IMPRACTICAL CODE REQUIREMENTS Examination Categories B-H, B-K-1, c-c, D-A, D-B, and D-C of ASME Section XI, 1989 Edition, with regard to Integrally Welded Attachments.

III. BASIS FOR RELIEF Code Case N-509, Alternate Rules for the Selection and Examination of Class 1, 2, and 3 Integrally Welded Attachments,Section XI, Division 1, is not currently approved by Regulatory Guide 1.147 for use. 10 CFR 50.55a footnote 6 notes that the use of other Code Cases may be authorized by the Director of the Office of Nuclear Reactor Regulation upon request pursuant to 10 CFR 50.55a(a) (3). As such, Code Case N-509 is requested for use on Surry Unit 2 in the third inspection interval.

The current Code requires a certain size base material design thickness before examination is required on Class 1 or 2 integrally welded attachments. This size limitation is apparently arbitrary with not technical basis. The current Code also has no inspection requirements for Class 1 integrally welded attachments for piping, pumps, and valves (B-K-1) for the third inspection interval of Inspection Program B (Surry's). Additionally, there is no selection criteria for Class 3 nonexempt integrally welded attachments, requiring 100% examination. These deficiencies have been corrected in Code Case N-509.

IV. ALTERNATE REQUIREMENTS Code Case N-509 will be used in its entirety. Code Case references to the 90 addendum of ASME Section XI are the same as the provisions in Code Case N-491, which has been implemented by our support program.

Conditions: At least a 10% sample of all Code Class 1, 2, and 3 integral attachments are examined.

S2-002I3 Rev. 1 2-23 7/94

~ RELIEF REQUEST SR-010 Status: Granted - NRC Letter No.95-480 Dated 8/30/95 I. IDENTIFICATION OF COMPONENTS System: Chemical and Volume Control (CH)

Component: Regenerative Heat Exchanger (2-CH-E-3)

Welds/Components Description Class 1-06 nozzle-to-vessel 1 NIR-06 nozzle inside radius 1 1-08 nozzle-to-vessel 1 NIR-08 nozzle inside radius 1 1-09 nozzle-to-vessel 1 NIR-09 nozzle inside radius 1 1-11 nozzle-to-vessel 1 NIR-11 nozzle inside radius 1 1-13 nozzle-to-vessel 1 NIR-13 nozzle inside radius 1 1-15 nozzle-to-vessel 1 NIR-15 nozzle inside radius 1 II. IMPRACTICAL CODE REQUIREMENTS Examination Category B-D (Inspection Program B) requires in item numbers B3-150 and B3.160 a volumetric examination of the nozzle-to-vessel weld and nozzle inside radius section.

III. BASIS FOR RELIEF The joint design of the above nozzle welds specifies a 3" schedule 160 weldolet jointed to a 9.25" O.D. x .875" thick vessel. These welds were not designed to be volumetrically examined from the outside diameter. The configuration of the weldolet precludes axial ultrasonic examination from the nozzle side and circumferential examination in either direction. This limits volumetric examination to a single axial scan from the vessel side of the nozzle. It is our opinion that a meaningful ultrasonic examination cannot be performed on the weld or inner radius with a single axial scan from the vessel side. This is due to the small diameter of the vessel and weldolet, the change in dihedral around the joint results in a correspondin9 change in the ultrasonic beam angle. This makes position measurements unreliable. It would also be necessary to extend the beam path to at least two full Vee paths, which will further complicate this examination.

S2-002I3 Rev. 1 2-24 7/94

RELIEF REQUEST SR-010 (CON'T)

These limitations would substantially limit our ability to discriminate flaw indications from geometry existing around the joint.

The configuration also precludes placement of film on the outside diameter for radiography, and the inside surfaces are inaccessible. It is our opinion that the gain in assurance of component integrity from this limited examination is not commensurate with the anticipated dose expenditure. Figures 1, 2, and 3 are provided to support this request.

IV. ALTERNATE REQUIREMENTS The outside surface of the nozzle-to-vessel welds shall receive a surface (liquid penetrant) examination. In addition a visual (VT-2) examination shall be performed in conjunction with the pressure testing required by IWB-5000 and/or Code Case N-498.

S2-002I3 Rev. 1 2-25 7/94

R[y_ENERA JIVE

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~ RELIEF REQUEST SR-011 status: Granted - NRC Letter No.95-480 Dated 8/30/95 I. IDENTIFICATION OF COMPONENTS Weld# Component ID# Description Class 1-07 2-RC-E-2 shell to head 1 1-02 2-RC-E-2 longitudinal 1 Drawing: 11548-WMKS-RC-E-002 II. IMPRACTICAL CODE REQUIREMENTS The 1989 Edition of ASME Section XI, Category B-B, items B2.ll and B2.12 requires a volumetric examination of 100% of the circumferential shell to head weld and 1 foot of the intersecting longitudinal weld.

III. BASIS FOR RELIEF The pressurizer is covered with an insulation support ring (attachment 1). The insulation support ring is 6 inches wide, where it interferes with the examination. This ring prevents complete volumetric coverage of both the upper shell to head weld and intersecting longitudinal weld. Total removal of the insulation support ring is considered impr3ctical due to high anticipated exposure levels estimated at 18.4 man-rem.

Partial removal of the support ring at the mechanical connection would allow some increase in coverage near the mechanical connection, where the support ring could be spread apart. However, the actual area of weld made accessible to this increased coverage is estimated to be very small in relation to the overall weld length, because the insulation support structure is rigid, interconnected with cross supports, and welded to the supports for the safety valves and power operated relief valves. The intersection of the circumferential shell to head weld and longitudinal welds is physically located behind one of these supports. Examination coverage of this area would not be improved by partial removal at the mechanical connection.

Any removal of the mechanical connection and spreading apart of the support structure would increase the risk of misalignment problems, and warping of the structure. This risk coupled with the marginal increase in examination coverage, makes partial removal of the insulation support structure also impractical.

S2-002I3 Rev. 1 2-26 7/94

IV.

RELIEF REQUEST SR-011 (CON'T)

ALTERNATE REQUIREMENTS A volumetric examination will be performed to the extent practical on welds 1-07 and 1-02. No extended beam path examinations can performed, since the pressurizer is a ciad vessel. The estimated coverage in the perpendicular beam path directions are detailed in attachment 2. The parallel beam path estimates are as follows:

Weld# 450 (7&8) 600 (7&8) 1-07 26% 26%

1-02* 100% 100%

(accessible length only - approximately 7.5")

S2-002!3 Rev. 1 2-27 7/94

Relief Request SR-011, Attachment 1, Page 1 of 4

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Relief Request SR-011, Attachment 2, Page 1 of 3

Surr~2 Press~r Veld 7 Partial Exanlnatlon Evaluation e

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ar th, Codi!' rl!'QUlrl!'d l!')(O.nlno.tlon o.r,o, -the ln5ulo. tlon support ring cov,rs th, top 4 lni;hl!'5 of' w,ld 2, *nit owing opproxlna t,ly 9 Inches to be accessible.

~ RELIEF REQUEST SR-012 Status: Granted - NRC Letter No.95-480 Dated 8/30/95 I. IDENTIFICATION OF COMPONENTS Class 1 and 2 longitudinal welds in piping II. IMPRACTICAL CODE REQUIREMENTS Table IWB-2500-1, Examination Category B-J, items B9.12 and B9.22, and Table IWC-2500-1, Examination Category C-F-1, items cs.12, cs.11, and CS.42, and Examination C-F-2, items CS.52, C5.62, and C5.82 pertaining to longitudinal welds in piping.

III. BASIS FOR RELIEF ASME Section XI in Code Case N-524 provides alternative examination requirements for longitudinal welds in piping.

This Code Case is not currently approved for use in Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability ASME Section XI Division 1. Footnote 6 to 10 CFR 50.55a states that the use of other Code Cases may be authorized by the Director of the Office of Nuclear Reactor Regulation upon request pursuant to 10 CFR 50.55a (a) (3), which requires that the proposed alternative provide an acceptable level of quality and safety, or that compliance with the existing Code requirements would result in hardship or unusual difficulty without a compensating increase in level of quality and safety.

Code Case N-524 provides an acceptable level of safety and quality by concentrating the examination in the high risk location associated with the intersection of the circumferential and longitudinal weld in piping. Additionally the Code Case eliminates the portion of the current Code examination volume requirements beyond the intersection area.

This area is perceived by the ASME Code as being relatively low risk. Continued examination of this area would.

significantly increase the exposure of examination personnel with a minimal increase to safety.

IV. ALTERNATE REQUIREMENTS The requirements of Code Case N-524, Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping Section XI Division 1, shall be followed.

S2-002I3 Rev. 1 2-28 7/94

I.

status:

Relief Request SR-013 Granted - NRC Letter No.95-480 Dated 8/30/95 IDENTIFICATION OF COMPONENTS System: Residual Heat Removal Components: Integral Attachments on Drawings 11548-WMKS-RH-E-lA, and 11548-WMKS-RH-E-lB as listed below; Component Integral Attachment Class 2-RH-E-lA HOOl-1 2 2-RH-E-lA H002-1 2 2-RH-E-lB HOOl-1 2 2-RH-E-lB H002-1 2 II. IMPRACTICAL CODE REQUIREMENTS Category c-c of the 1980 Edition, Winter 1980 Addendum of ASME Section XI, item C3.10 requires a surface examination on 100% of the required areas of each integral attachment. In case of multiple vessels of similar design and service, the required examinations may be conducted on only one vessel. Where multiple vessels are provided with a number of similar attachments, the examination of attachments may be distributed among the vessels.

III. Basis For Relief These heat exchangers and integral attachments were designed and constructed to ASME Section VIII, 1965 Edition, Winter. 1966 Addendum. This Code limited the examination of the integral attachments to a visual type exam requiring (UW-38) that visible defects, such as cracks, pinholes, and incomplete fusion and defects detected by the hydrostatic test be removed. These fillet weld integral attachments never received nor were they required to receive a surface examination under the Construction Code. Additionally the initial preservice examinations at Surry were limited to Class 1 components, since Class 2 and 3 had not yet been placed into the Code, as such no preservice surface examination was conducted on these integral attachments. The actual surface condition is indicative of a visual only type exam from this time period.

S2-002I3 Rev. 1 2-29 7/94

Relief Request SR-013 (CON'T)

Attempts to examine these attachments as part of the present inservice inspection program ( surface exam) have resulted in reports which identify the general rough surface condition. The most recent attempt was rejected by the Level III, as unacceptable to perform the surface examination due to the rough surface condition. An evaluation of the man-hours and dose requirements necessary to properly prepare the surface, which will include both grinding and welding of the integral attachments, has been completed (attachment 1). This estimate calculates an expenditure of 11.74 man-rem, if all attachments are properly prepared for a Section XI preservice examination.

This dose expenditure and outage maintenance addition is considered impractical considering that the original Construction Code accepted the surface condition visually.

IV. ALTERNATE REQUIREMENTS The integral attachments shall be inspected visually (VT-3) for cracking or other conditions described as unacceptable in the original Construction Code. This alternative was approved for the Surry Unit 2 Interval 2 Program by letter #93-026 dated 1/12/93.

S2-002I3 Rev. 1 2-30 7/94

*VIRGINIA POWER MEMORANDUM To: Mr. D. L. Rogers Office/Location ISi Engineering From: M. S. Whitt Office/Location Civil Design Date December 20, 1991 RHR HEAT EXCHANGER SUPPORT WELD REPAIRS The purpose of this memorandum is to provide man-rem estimates for repair of the welds on the RHR heat exchanger support lugs for both heat exchangers in Unit 1 and Unit 2, as requested by your memorandum of October 3, 1991.

During the Unit 2 Refueling Outage, DR #S1-91-0582 was written due to the NDE failure of an intearc1llv attached support lug on 2-RH-E-1 A. During the subsequent e\,*u:ud Lion, *,,vh!ch inc \.;c,.:d visual examinatior,~ of supports on bot~ 2 RH-F.-1 A r.1nu

, 1 B, it was determm1:::..i that the welds in question had never been prepared to allow for a surface NDE exam as required by ASME Section XI, because the heat exchangers were originally fabricated to ASME Section VIII.

Your memorandum of October 3, 1991 requested that Design Engineering work with NSS Construction and the ALARA coordinator to develop comprehensive and accurate man-hour and radiation exposure dose estimates for weld repairs to provide acceptable welds to allow NDE inspections of the welds.

By memorandum of October 16, Engineering requested NSS Construction to develop the required man-hour estimates. These estimates were provided in the memorandum from Mr. W. D. Corbin of December 10, 1991 (Attachment 1). These man-hour estimates were used by the ALARA Coordinator to estimate man-rem exposure (Attachment 2). The total exposure for this work is calculated to be 11 .74 man-rem for each unit, and 23.48 man-rem for both units.

Mr. D. L. Rogers December 20, 1991 Page 2 If you have any questions or require further information, please contact me.

M. S. Whitt cc: T. B. Sowers A. R. Fletcher T. R. Huber E. W. Throckmorton - IN3W W. D. Grady M. A. Ringler L. J. C1_illiven T. F. 5i.eed - ALAR.l\ C0ordin2tcr C. E. Sorrell - IN1 NW DEO File

ATTACHMENT 1 The following man-hour estimates were calculated for the weld repair anti inspection work for the RHR heat exchanger supports.

l W

POWl!lf

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Memorandum Distribution Innsbrook Technical Center To Fram w. D. Corbin December 10, 1991 COIIPLE'l'ED ESTIIIA"l'E NUCLEA!l ENGIREEB.ING SERVICES SQRRI PQWP Sn'!'IQN Estimate no. SY 18 SAO TYPE or ESTIKA'!'E PROJECT TYPE

....L. STUDY IRt CONCEPTUAL DCP DE!"INITIVE EWR BID OTHER AI.ARA M-H EST, Attached is an estimate for RHR BX SUPPORT WELD REPAIR MANHOURS

Thi£ e~timate is being provided for the followi~g purpcs~:

Basis for Project Authorization Budget information Final controls pack~~e Cost benefit analysis or study Other (ALARA man-hour estimate)

Please review and provide your comments. The Estimator is Mr. I.

West ( ext. 3444). Corrections or revisions needed during the review process, however, should be brought to the attention of Bill Miller on ext. 2553.

w. D. Corbin ATTACHMENT cc: Mr. H. H. Blake, Surry Site Services Mr. R. M. Cramer, Surry Site Services Mr. D. W. Buster, Surry Site Services

~ ~ I!;. i., ha lfhi-tt.,a.*SUz*ry~*DBO ;-.

Mr. T. F. Steed,. Surry ALARA Coordinator Mr. M.A. Ringler; Surry Materials Engineering Estimating File - IN3NW

SURRY POWER STATION NUCLEAR ENGINEERING SERVICES ESTIMATE NO. SY 18 SAO SURRY RBR SUPPORT WELD REPAIRS

--*.-.. DATA SOURCES

1. Sketches and data received from VA Power - Surry DEO is the basis for the design evaluated in this estimate.

This information was contained in an estimate request memorandum from Mr. M. s. Whitt to Mr. H.B. Blake, dated October 16, 1991.

2. The information and scope of work was further defined through discussions with Mr. Mike Ringler, who is familiar with the condition of the existing welds.

3. Radiological conditions in the work area and in the general area were obtained from Station ALARA personnel.

METBC'!'QLOG'i Man-hour estimates were developed for Construction, NDE, QC, Materials Engineering and HP personnel who would be involved in the welding repair of RHR Pump supports. Composite labor costs are furnished for VA Power and NSS personnel.

SCOPE OF WORIC The scope of work covered by this estimate is based on weld repair of eight (8) RHR heat exchanger pump supports as per Attachment 1 of the above referenced memorandum (copy attached).

ASSID!PTIONS AND QUALIFICATIONS

1) It was assumed, through discussion with site personnel, that the weld repair would basically require one shift per support. Personnel involved in the repair work and verification would include one welder, one grinder, fire-watch, runner, Foreman, Material Engineer, NDE, QC, and BP tech.

2) It was further*assumed that personnel related to NDE, QC, Material Engineering and supervision would only require approximately 25\ of the time of the repair effort.

3) Through discussions with Station ALARA personnel, contact dose rates and dose rates within 12" of the weld area were obtained. These rates were utilized to determine the degree of difficulty and maximum stay-time for welders and grinders. It should be noted, due to the high radiation, that several welders and grinders may be regui red to sequentially complete the repairs. --

4) It was assumed that only one weld would be repaired at a time (including NOE and QC verification). This will allow sufficient strength in the remaining welds to support the heat exchangers without temporary supports.

5) All manhours allow 151 for rework of new welds to allow for NOE dye-penetrant testing and repair of further indications.

6) The following specific qualifications apply to the weld repairs:

a. The weld& are bi-metallic (CS - SS).

b. The existing welds will not be completely removed; existing NOE indications and flaws will be repaired.

c. A bi-metallic weld build up will be performed tc aimensions srec:fi~d on Attachment 1.

d. The ~~ttom horizanc~! ~dla is ~naccessible, and will not be worked.

e. The top horizontal weld will be 5/8".

f. No scaffolding is required.

g. Insulation consists of removable blankets.

3) As per directions in the referenced memorandum, man-hours were broken down to allow both Unit 2 heat exchangers to be worked in 1993, one Unit 1 heat exchanger in 1994 and one Unit 1 heat exchanger in 1995.

8) The manhours are further broken down by- very low dose rate, low dose rate and high dose rate in order to facilitate ALARA dose rate calculations.

TABLE l - RU PUKP SUPPORT REPAIR IJANBQtJR SQffllARY 1993 1994 1995 U2RO UlRO UlRO ACTIVITY 2A/B (MH> lA (MHl lB (ffl)

Very low dose- 180 90 90 Mob-demob & dressout Low dose in Containment 140 70 70 High dose at work area l.1Q il .fi TOTAL 450 225 225

[~~~~~~-----:~~=================================~~~~~~~~=~~~~~~=--- -=========================-======~=======~~~~~==~=~-~::

I STATION: suaar I ,aoJICT: an* BX SUPPORT a1PAIR W.P.

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EST. TYPE: STUDY ESTIMATE: sr 11 SAO I SHEET: ~ - 1 I I 1L.AIIT DISCaIPTIOR:

_ CHECKED Ill: WEST DATI ISTAII.: 4-DIC-1991 I l-----------------------------------------------------------------------*-----------------------------------------------------------

1 ACTIVITY IIAMI: 01 DISCRIPTIOK: RHR HEAT 11:XCHAROr.R .IJUPPORT WELD aEPAIRS 1----------------------------------------------------------------------------------------------------------------------------------

I I I I I KATIRIAL I KARH*lURs I LA11011. I con I su11co11TaAcTIRO I I COftH I I I I URIT I MATL I UNIT I ~ROI TOTAL I COHPI LABOR I IQUIP I UIIIT I SUIICRTRI TOTAL I coo1 I D1sca1PTI011 IUHI QTY I KATL I cosT I MIIHRS I rr*! KRHRS I aATBI cosT I TOTAL I su11c11TRI cosT I cosT

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-f,V ~4TE: gOT11UII\ ~o,t,t,. WELP Nor ~Cc&S-18L6 Pe.e N\.b... IZ

ATTACHMENT 2

The following man-rem exposure estimates were calculated by the ALARA Coordinator using the man-hour estimates provided by the memorandum from W. D. Corbin dated December 10, 1992.

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RELIEF REQUEST SR-014 Status: Granted - NRC Letter No.97-252 Dated 4/11/97 I. IDENTIFICATION OF COMPONENT Mark/Weld# Line# Drawing# Class 3-04A 3"-CH-381-1503 11548-WMKS-CH-11 2 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 edition of ASME Section XI Table IWC-2500-1, examination category C-F-1, item number CS.21 does not allow any limitations to the required volumetric or surface examinations.

Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10%.

III. BASIS FOR RELIEF The component listed is a three inch pipe to valve body weld.

This weld is located on the upstream side of the discharge check valve for the "A" charging pump. The component listed above has been examined to the extent practical as required by the Code.

Due to interferences from a branch connection and an adjacent valve body the reduction in coverage of the volumetric examination is detailed in Table SR-14-1. The required surface examination had no limitations. Figure SR-14-1 is provided detailing the limitations experienced.

IV. ALTERNATE PROVISIONS It is proposed that the examination completed at the reduced coverage be counted as meeting the Code preservice requirements.

S2-002I3 Rev. 1 2-31 7/94

e Table SR-14-1 Surry Unit 2 Examination coverage Estimates 11548-WMKS-CH-11 category c-F-1, Item cs.11 UT Scan Coverage% Surface Examination Mark/Yeld# 1 ?. ~ Coverage% Reason For Partial f

3-04A 73 73 100 100 100 A branch connection limits the 2 and 5 scan to 8 out of 11 inches. A valve body limits the examination to one side. The 2 scan was performed using an extended beam.

UT Scan Direction Definitions 2 - Axial scan, 180 degrees from isometric flow direction.

5

Axial scan, the same direction as the isometric flow.

7 - Circumferential scan, clockwise rotation when viewing in the direction of isometric flow.

8 - Circumferential scan, counterclockwise rotation when viewing in the direction of isometric flow.

S2-002I3 Rev. 1 2-32 7/94

3"-CH-381 -1 503 RESTRICTED AREA Flo1,1

.... 5 SIDE/

3-04A 1 1 S4 8- WM K S - C.H - 1 1 Figure SR-1 ~-1

RELIEF REQUEST SR-015 Status: Granted With Conditions - NRC Ltr No.97-252 Dated 4/11/97 I. IDENTIFICATION OF COMPONENT Mark/Weld# Drawing# Class 1-01 11548-WMKS-CH-E-2 2 1-02 11548-WMKS-CH-E-2 2 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 edition of ASME Section XI Table IWC-2500-1, examination category C-A, item numbers Cl.10 and Cl.20 do not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10%.

III. BASIS FOR RELIEF One third of the welds listed above have been examined to the extent practical as required by the Code. The examinations were limited due to interferences from the non-regenerative heat exchanger inlet nozzle and a component support. Similar restrictions are expected for the remaining two thirds. The anticipated reduction in coverage of the volumetric examination is detailed in Table SR-15-1. Figure SR-15-1 is provided detailing the limitations experienced.

IV. ALTERNATE PROVISIONS It is proposed that the examinations completed at the reduced coverage and scheduled examinations at the coverage stated in Table SR-15-1 be counted as meeting the Code requirements.

V. CONDITIONS Following the completion of the examinations, if the actual volumetric coverage obtained is not equal to or greater than the coverage(s) specified, then Virginia Power must submit for additional relief.

S2-002I3 Rev. 1 2-33 7/94

Table SR-15-1 Surry Unit 2 Examination coverage Estimates 11548-WMKS-CH-E-2 Category c-A, Items Cl.10 and Cl.20 UT Scan Coverage% Section XI Mark[\.leld# ~ 2 !. !! Item Number Reason For Partial Completed Examinations 011 to 28" 1-01 93.75 93. 75 50 50 Cl.20 A component support limits the 7 and 8 scan to 14 inches out of 28 inches CO inches to 14 inches). An extended beam path was used for the 2 and 5 scans.

1-02 88.39 88.39 100 100 Cl .10 A 3 inch 00 inlet nozzle 0.6 inches from the toe of weld, a welded support between 17.75 inches and 19.5 inches, the 5 side of the weld is flanged with studs and nuts blocking access.

Scheduled Examinations 28 11 to 85 11 1-01 93.75 93. 75 44 44 Cl .20 Two component supports limit the 7 and 8 scans to 25 out of 57 inches.

An extended beam path will be used for the 2 and 5 scans.

1-02 84.7 84.7 100 100 Cl .10 The 2 and 5 scans will be restricted by two 3 inch 00 nozzles 0.6 inches from the toe of weld, three welded supports restricting 1.25 inches. The 5 side of the weld is flanged with studs and nuts blocking access. Extended beam path will be used.

Total Coverage 011 to 85" 1-01 93. 75 93. 75 46 46 Cl.20 1-02 85.93 85.93 100 100 Cl .10 UT Scan Direction Definitions 2 - Axial scan head side of weld 5 - Axial scan vessel side of weld 7 - Circunferential scan, clockwise when looking down on the vessel 8 - Circunferential scan, counterclockwise when looking down on the vessel S2-002I3 Rev. 1 2-34 7/94

CH-E-2 0- . 2" RESTRICTEI BY NOZZLE VELD I *2 TOP VIEW WELD 1 -02 85" l!

O'

0 1.5 I .5"

) C WELD 1 -01 FOUNDATION SIDE VIEW FIGURE SR-1 5-1

RELIEF REQUEST SR-016 Status: Granted With Conditions - NRC Ltr No.97-252 Dated 4/11/97 I. IDENTIFICATION OF COMPONENT Mark/Weld# Drawing# Class 1-01 11548-WMKS-CH-FL-4A 1 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 edition of ASME Section XI Table IWC-2500-1, examination category C-A, item number Cl.20 does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10%.

III. BASIS FOR RELIEF The component listed above is the lower head to shell weld of the "A" seal water injection filter. One third, 0" to 12", of the component listed above has been examined to the extent practical as required by the Code. Due to interferences from a support leg the reduction in coverage of the volumetric examination is detailed in Table SR-16-1. Figure SR-16-1 is provided detailing the limitations experienced. Interferences were encountered when the remaining two thirds of the weld was examined during the second interval. It is anticipated that the same limitations will exist when the remaining two thirds of the weld are examined during the third inspection interval.

IV. ALTERNATE PROVISIONS It is proposed that the examination completed at the reduced coverage be counted as meeting the Code requirements. The remaining two thirds will be examined to the extent practical.

The estimated coverage is for the remaining two thirds is expected to be similar to the coverage presented in Table SR-16-1.

V. CONDITIONS Following the completion of the examinations, if the actual volumetric coverage obtained is not equal to or greater than the coverage(s) specified, then Virginia Power must submit for additional relief.

S2-002I3 Rev. 1 2-35 7/94

Table SR-16-1 Surry unit 2 Examination coverage Estimates category c-A, Item c1.20 Mark/Weld# Beam Angle Exam Area Scan Direction % Exam Reason For Partial 1-01 (0 11 - 12 11 ) 45 Weld 2 ~ Support leg 45 Weld 5 62 45 Weld 7 82 45 Weld 8 82 45 Base 2 62 45 Base 5 60 45 Base 7 82 45 Base 8 82 Surface Examination coverage 62.5% (7.5"/12")

UT Scan Direction Definitions 2 - Axial scan vessel side of weld 5 - Axial scan flange side of weld 7 - Circumferential scan, clockwise (looking down on flange) 8 - Circumferential scan, counterclockwise (looking down on flange)

S2-002I3 Rev. 1 2-36 7/94

CH-FL-4A A A 34" t----,

O" 12' EXAMINATION AREA O" - 12'

~SUPPORT LEG LIMITS A-A EXAMINATION AREA Figure SR-16-1

RELIEF REQUEST SR-017 Status: Granted With Conditions - NRC Letter No.97-252 Dated 4/11/97 I. IDENTIFICATION OF COMPONENT Mark/Weld# Drawing# Class 1-01 11548-WMKS-RC-R-1.2 1 II. IMPRACTICABLE CODE REQUIREMENTS The 1989 edition of ASME Section XI Table IWB-2500-1, examination category B-A, item number Bl.40 does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class .1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10%.

III. BASIS FOR RELIEF The component listed above is the reactor head to flange weld.

One third, 0" to 179", of the component listed above has been examined to the extent practical as required by the Code. Due to interferences from a lifting lug and the geometry of the weld the reduction in coverage of the volumetric examination is detailed in Table SR-17-1. Figures SR-17-1 and SR-17-2 are provided detailing the limitations experienced. The surface examination had no limitations.

Limitations were encountered when the remaining two thirds of the weld was examined during the second interval. It is anticipated that the same limitations will exist when the remaining two thirds of the weld are examined during the third interval.

IV. ALTERNATE PROVISIONS It is proposed that the examination completed at the reduced coverage be counted as meeting the Code requirements. The remaining two thirds will be examined to the extent practical.

The estimated coverage for the remaining two thirds is expected to be similar to the coverage presented in Table SR-17-1 for 0" to 179".

V. CONDITIONS Following the completion of the examinations, if the actual volumetric coverage obtained is not equal to or greater than the coverage(s) specified, then Virginia Power must submit for additional relief.

S2-002I3 Rev. 1 2-37 7/94

Table SR-17-1 Surry Unit 2 Examination Coverage Estimates (Reactor Vessel) category B-A, Item Bl.40 Mark£Weld# Beam Angle Exam Area Scan Direction % Exam Reason For Partial 1 (0 11 - 179 11 ) 0 Weld & Base 96.6S Joint Configuration 45 Weld 2 91.84 and Li ft ing Lug 45 Weld 5 96.65 45 Weld 7 96.65 45 Weld 8 96.65 60 Weld 2 56.71 60 Weld 5 90.16 60 Weld 7 96.65 60 Weld 8 96.65 45 Base 2 70.96 45 Base 5 96.65 45 Base 7 95.19 45 Base 8 95. 19 6D Base 2 44.23 60 Base 5 83.02 60 Base 7 94.86 60 Base 8 94.86 Surface coverage 100%

UT Scan Direction Definitions 2 - Axial scan flange side of weld 5 - Axial scan head side of weld 7 - Circumferential scan; clockwise (looking down on head) 8 - Circumferential scan, counterclockwise (looking down on head)

S2-002I3 Rev. 1 2-38 7/94

60 5 SIDE START 60 5 SIDE STOP 60 5 SIDE START 45 2 SIDE STOP 5 SIDE 2 SIDE 60 2 SIDE START 45 2 SIDE START FLANGE SIDE FIGURE SR-1 7-1 11 5-48-WMKS-RC-R-1 .2 WELD 1 -01

__ I 6" I__

I I LIFTING LUG Ji I 1 .S" WELD 1 -01 oO Figure SR-1 7-2

e Virginia Electric and Power Company Surry Power Station Unit 2 Third Ten Year Interval RELIEF REQUEST SR-018 status: Pending - Virginia Power Letter No.96-606 Dated 1/2/97 I. IDENTIFICATION OF COMPONENT:

Weld No. Line No. Drawing No. Class Weld 1-01 2 11 -CH-397-1502 11548-WMKS-RC-12Z5 1 Weld 1-01 2"-CH-395-1502 11548-WMKS-RC-11Z3 1 Weld 1-01 2"-CH-393-1502 11548-WMKS-RC-10Z4 1 The above welds are socket welds in the reactor coolant pump seal injection piping lines.

II. CODE REQUIREMENTS:

For Surry Unit 2, Relief Request SR-008 was used for weld selection of Class 1 pressure retaining welds in piping in conjunction with ASME Section XI, 1989 Edition, Table IWB-2500-1, Notes 1 (b) and 2 of Category B-J. Relief Request SR-008 was approved by NRC Letter 95-480, dated 8-30-95.

The relief request requires that all terminal ends of piping runs connected to vessels and pumps be examined.

Th~~1989 Edition of ASME Section XI Table IWB~2500-1, examination category B-J, item number B9.40 requires an OD surface examination of the weld and adjacent base metal as defined by Figure IWB-2500-8, (s*ocket weld).

III. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED Relief is requested from performing the Code-required sur-face examination on the above identified reactor coolant system piping.

S2-002I3 Rev. 1 2-39 7/94

RELIEF REQUEST SR-018 (CON'T)

IV. BASIS FOR RELIEF:

The components listed above are terminal ends on seal injection piping connected to the reactor coolant pumps.

The welds are completely inaccessible due to their close-ness to the pump flange; i.e., they are underneath the flange. The attached picture shows the configuration.

However, when the reactor coolant pump main flange is disassembled, the weld is accessible for examination.

However, disassembly of the pump would cause a burden without a compensating increase in quality and safety. All terminal end welds are scheduled for examination. There-fore, substitution with another weld is not feasible.

However, another weld will be selected for examination in order to ensure that 25% of examination category B-J welds will be examined.

V. PROPOSED ALTERNATE REQUIREMENT:

It is proposed that the substitution with another weld be counted as meeting the Code requirements. In addition:

1. A visual (VT-2) examination will be performed during the normally scheduled system leakage test each refueling outage;

2. Technical Specifications require that the reactor cool-ant system leak rate be limited to one gallon per minute unidentified leakage. This value is calculated at least once per 72 hou~~; and

-~

3. The containment atmosphere particulate radioactivity is checked every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

4. If a reactor coolant pump main flange is disassembled, thereby making the weld accessible for examination, the weld will be examined consistent with Code requirements.

The proposed alternative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised.

S2-002I3 Rev. 1 2-40 7/94

SR-018 - Picture Virginia Electric and Power Company Surry Power Station Unit 2 Third Ten Year Interval RELIEF REQUEST SR-019 Status: Pending - Virginia Power Letter No.96-606 Dated 1/2/97 I. IDENTIFICATION OF COMPONENT:

Weld No. Line No. Drawing No. Class Weld 4-llBC 3"-RC-335-1502 11548-WMKS-0124Al 1 Weld 4-llBC is a branch connection piping weld.

II. CODE REQUIREMENTS:

The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-J, item number B9.32 requires an OD surface examination of the weld and adjacent base metal as defined by Figure IWB-2500-11. The Code does not allow any limitations to the required surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent.

III. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED Relief is requested from performing the Code-required sur-face examination on the above identified reactor coolant system piping.

IV. BASIS FOR RELIEF:

The weld listed above is covered by a reinforcement pad/s-addle weld, which totally covers the examination area de-scribed in the Code. Therefore, examination coverage cannot be achieved due to the configuration of the piping.

This weld is a branch connection and, as such, all welds of this type are scheduled for examination. Therefore, sub-stitution with another weld is not feasible.

V. PROPOSED ALTERNATE EXAMINATION:

It is proposed that a surface examination performed on the fillet weld of the reinforcement pad be substituted for the Code surface examination. In addition:

1. A visual (VT-2) examination will be performed during the normally scheduled system leakage test each refueling outage; S2-002I3 Rev. 1 2-41 7/94

RELIEF REQUEST SR-019 (CON'T)

2. Technical Specifications require that the reactor cool-ant system leak rate be limited to one gallon per minute unidentified leakage. This value is calculated at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and

3. The containment atmosphere particulate radioactivity is checked every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The proposed alternative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised.

S2-002I3 Rev. 1 2-42 7/94

Virginia Electric and Power Company Surry Power Station Unit 2 Third Ten Year Interval RELIEF REQUEST SR-020 Status: Pending - Virginia Power Letter No.96-606 Dated 1/2/97 I. Identification of Components:

Weld No. Line No. Drawing No. Class Weld 1-0SDM 29"-RC-301-2501R 11548-WMKS-RC-12-1 1 Weld 1-06DM 31"-RC-308-2501R 11548-WMKS-RC-10-1 1 Weld 1-0SDM is a nozzle-to-safe end weld on the steam generator on the reactor coolant piping on loop "A". Weld 1-06DM is a nozzle-to-safe end weld on the steam generator on the reactor coolant piping o~ loop "C".

II. CODE REQUIREMENTS:

The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-F, item number BS.70 requires an OD surface examination of the weld and adjacent base metal and a volumetric examination of the weld and adjacent base metal (interior one-third volume) as defined by Figure IWB-2500-8. The Code does not allow any limitations to the required volumetric or surface examinations. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent.

III. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED Relief is requested from fully performing the Code-required volumetric examination on the above identified reactor coolant piping.

IV. BASIS FOR RELIEF:

The components listed above has been examined to the extent practical as required by the Code. However, full volumet-ric coverage could not be achieved due to joint configura-tion and material characteristics. Coverage of the volu-metric and surface examinations are detailed in Tables SR-020-1 and SR-020-2. Figure SR-020-1 is provided as graphic detail of the limitations experienced. Substitution with another weld is not feasible because all welds in this Category and Item must be examined.

S2-002I3 Rev. 1 2-43 7/94

RELIEF REQUEST SR-020 (CON'T)

V. PROPOSED ALTERNATE EXAMINATION:

It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code re-quirements. In addition:

1. A visual (VT-2) examination will be performed during the normally scheduled system leakage test each refueling outage;

2. Technical Specifications require that the reactor cool-ant system leak rate be limited to one gallon per minute unidentified leakage. This value is calculated at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and

3. The containment atmosphere particulate radioactivity is checked every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The proposed alternative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised.

S2-002I3 Rev. 1 2-44 7/94

Figure __... -020-1

,~,J Seace!; u,,;, J Seacch uc;t /

-~,,,-~----'--s~~---~---------~

Elbow f'IOZZ le v

Rough 00 Surface 45* Beam Angle Longitudinal Wa*;e Hatched area is volume examined. Exam Volume S2-002I3 2-45 Rev. 1 7/94

Table SR-020-1 Surry Unit 2 Examination Coverage Estimates (Piping) 11548-WMKS-RC-12-1 C~tegory B-F, Item BS.70 UT Scan Coverage%

Surface Weld No. 2 5 7 8 Coverage% Reason For Partial 1-05DM 0 28 55 55 100 Weld is limited by the nozzle geometry, surface condition and limited surface preparation on the pipe side of the weld. The surface on the pipe side of the weld, which is a cast elbow, is machined for a distance of approximately three inches from the edge of the weld. Ultrasonic exam-ination is limited to this machined area of the pipe and weld since the nozzle side is in the rough as-cast condi-tion. The use of alternate angles would not have im-proved volumetric coverage. Because of the use of the longitudinal wave form only~ node examinations were possible.

UT Scan Direction Definitions 2 axial scan, 180 degrees from Isometric flow direction.

5 axial scan, the same direction as the isometric flow.

7 circumferential scan, clockwise rotation when viewing in the direction of isometric flow.

8 circumferential scan, counter-clockwise rotation when viewing in the direction of isometric flow.

S2-002I3 Rev. 1 2-46 7/94

Table SR-020-2 Surry Unit 2 Examination Coverage Estimates (Piping) 11548-WMKS-RC-10-1 Category B-F, Item BS.70 UT Scan Coverage%

Surface Weld No. 2 5 7 8 Coverage% Reason For Partial 1-06DM 28 0 55 55 100 Weld is limited by the nozzle geometry, surface condition and 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. Ultrasohic examination is limited to this machined area of the pipe and weld since the nozzle side is in the rough as-cast condition. The use of alternate angles would not have improved volumetric coverage. Because of the use of the longitudinal wave form only%

node examinations were possible.

UT Scan Direction Definitions 2 axial scan, 180 degrees from Isometric flow direction.

5 axial scan, the same direction as the isometric flow.

7 circumferential scan, clockwise rotation when viewing in the direction of isometric flow.

8 circumferential scan, counter-clockwise rotation when viewing in the direction of isometric flow.

S2-002I3 Rev. 1 2-47 7/94

Virginia Electric and Power Company Surry Power Station Unit 2 Third Ten Year Interval RELIEF REQUEST SR-021 status: Pending - Virginia Power Letter No.96-606 Dated 1/2/97 I. IDENTIFICATION OF COMPONENT:

Weld No. Line No. Drawing No. Class Weld 2-30 4 11 -RC-315-1502 11548-WMKS-0125Al 1 Weld 2-30 is on pressurizer spray piping from reactor cool-ant cold leg on loop "C" to the pressurizer.

II. CODE REQUIREMENTS:

The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-J, item number B9.11 requires an OD surface examination of the weld and adjacent base metal and a volumetric examination of the weld and adjacent base metal (interior one-third volume) as defined by Figure IWB-2500-8. This weld is not a terminal end or dissimilar metal weld, but is included in the examination category as additional piping welds to ensure that 25% of the reactor coolant piping is examined. The Code does not allow any limitations to the required volumetric or surface examina-tions. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in cover-age, if it is less than 10 percent.

III. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED Relief is requested from fully performing the Code-required surface examination on the above identified reactor coolant piping.

IV. BASIS FOR RELIEF:

The component listed above has been examined to the e~tent practical as required by the Code. However, full surface coverage could not be achieved due to interferences from an adjacent pipe support. The required volumetric examination had limitations, but they where less than 10%. Coverage of the volumetric and surface examinations are detailed in Table SR-021-1. Picture SR-021-1 is provided as graphic detail of the limitations experienced. Substitution with another weld of the same size would not necessarily improve the examination coverage since this weld is representative of plant design and similar geometric conditions are ex-pected.

S2-002I3 Rev. 1 2-48 7/94

RELIEF REQUEST SR-021 (CON'T)

V. PROPOSED ALTERNATE EXAMINATION:

It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code re-quirements. In addition:

1. A visual (VT-2) examination will be performed during the normally scheduled system leakage test each refueling outage;

2. Technical Specifications require that the reactor cool-ant system leak rate be limited to one gallon per minute unidentified leakage. This value is calculated at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and

3. The containment atmosphere particulate radioactivity is checked every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The proposed alternative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised.

S2-002I3 Rev. 1 2-49 7/94

Table SR-021-1 Surry Unit 2 Examination coverage Estimates (Piping) 11448-WMKS-0125Al category B-J, Item B9.ll UT Scan Surface

\Jeld No. Coverage% Coverage% Reason For Partial 2-30 93.3 81 A \Jhip restraint located on the piping and on the pipe side with the weld extending across the weld to the weld toe prevents 100% surface examination.

The whip restraints (4 total) are located at 0°,

90°, 180° and 270°. Each restraint at the pipe is 0.500" in length.

S2-002I3 Rev. 1 2-50 7/94

SR-021- Picture Virginia Electric & Power Company Surry Power Station Unit 2 Third Ten Year Interval Request for Relief No. SR-022 Status: Withdrawn, but not removed from manual.

Hold this relief request until all examina-tions are completed and resubmit.

Virginia Power Ltr. No.97-286 Dated 6-2-97 I. IDENTIFICATION OF COMPONENT Weld No. Component Drawing No. Class Weld 2-06 2-SI-P-lA 11548-WMKS-SI-P-lA 2 Weld 2-06 is a pump casing weld on the safety injection pump 02-SI-P-lA.

II. CODE REQUIREMENTS The 1989 Edition of ASME Section XI Table IWC-2500-1, examination category C-G, item number C6.10 requires an OD or ID surface examination of the weld and adjacent base metal as defined by Figure IWC-2500-8. The Code does not allow any limitations to the required surface examinations.

Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in coverage, if it is less than 10 percent.

III. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED Relief is requested from fully performing the Code-required surface examination on the above identified safety injec-tion pump casing weld.

IV. BASIS FOR RELIEF The component listed above has been examined to the extent practical as required by the Code. Approximately sixty-three (63) percent of the required examination was complet-ed. Full surface coverage could not be achieved due to interferences from an adjacent wall, bolting and the pump casing support. Figure SR-022-1, pictures SR-022-1, SR-022-2 and SR-022-3 are provided as graphic detail of the limitations experienced. Substitution with another weld is not feasible because the "B" pump has the same limitation.

Disassembly of the pump would cause a burden without a S2-002I3 Rev. l 2-51 7/94

Request for Relief No. SR-022 (CON 1 T) compensating increase in quality and safety.

V. PROPOSED ALTERNATE EXAMINATION It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code re-quirements. The proposed alternative examination will ensure that the overall level of plant quality and safety will not be compromised.

S2-002I3 Rev. 1 2-52 7/94

Figure SR-022-1 02-SI-P-lA Wal I FI an,Je

'"'"Weld 2-06 f;I.

\

Suppor*t Str-uc:tun?

DI *n.anr.:':' f1*r.,m FI o.nt;i":"

To Wa I I I c; 8 I n,: hi;:>~

Side View S2-002I3 2-53 Rev. 1 7/94

SR-022 Picture SR-022 Picture SR-022 Picture Virginia Electric and Power Company Surry Power Station Unit 2 Third Ten Year Interval RELIEF REQUEST SR-023 status: Pending - Virginia Power Letter No.96-606 Dated 1/2/97 I. IDENTIFICATION OF COMPONENT:

Weld No. Component Drawing No. Class lONIR 2-RC-E-2 11548-WMKS-RC-E-2 1 llNIR 2-RC-E-2 11548-WMKS-RC-E-2 1 NIR's 10 and 11 are nozzle inside radius sections integral-ly cast to the top of the pressurizer.

II. CODE REQUIREMENTS:

The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-D, item number B3.120 requires a volumetric examination of the nozzle inside radius section as defined by Figure IWB-2500-7(d). The Code does not allow any limitations to the required volumetric examina-tions. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in cover~

age, if it is less than 10 percent.

III. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED Relief is requested from fully performing the Code-required volumetric examination on the above identified pressurizer nozzle inside radius sections lONIR and llNIR.

IV. BASIS FOR RELIEF:

The components listed above have been examined to the extent practical as required by the Code. However, full volumetric coverage could not be achieved due to inherent interferences from a rough and bumpy surface, which causes the ultrasonic search unit to lose contact and change angles. The use of alternate angles would not have im-proved volumetric coverage. The nozzles are integrally cast to the pressurizer, therefore, weld contour prepara-tion (grinding or weld buildup and grinding) prior to examination will result in vessel wall reduction and is not recommended.

S2-002I3 Rev. 1 2-54 7/94

e RELIEF REQUEST SR-023 (CON'T)

The reduction in coverage is approximately ninety-five (95) percent. Picture SR-023-2 (NIR-11) is provided as graphic detail of the pressurizer nozzles, and is representative of existing conditions. Substitution with another nozzle inside radius section is not feasible because all of the pressurizer nozzle inside radius sections must be examined.

V. PROPOSED ALTERNATE EXAMINATION:

It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code re-quirements. In addition,

1. The nozzle inside radius sections will be visually exam-ined from the inside using direct or remote techniques prior to the end of the inspection interval.

2. A visual (VT-2) examination will be performed during the normally scheduled system leakage test each refueling;

3. Technical Specifications require that the reactor cool-ant system leak rate be limited to one gallon per minute unidentified leakage. This value is calculated at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and

4. The containment atmosphere particulate radioactivity is checked every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The proposed alternative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised.

S2-002I3 Rev. 1 2-55 7/94

SR-023 Picture Virginia Electric and Power Company Surry Power Station Unit 2 Third Ten Year Interval Request for Relief No. SR-024 status: Pending - Virginia Power Letter No.96-606 Dated 1/2/97 I. IDENTIFICATION OF COMPONENT:

Weld No. Line No. Drawing No. Class Weld 1-03 29"-RC-307-2501R 11548-WMKS-RC-10-1 1 Weld 1-03 is on the reactor coolant (hotleg) piping on loop "C from the reactor vessel to the steam generator.

II. CODE REQUIREMENTS:

The 1989 Edition of ASME Section XI Table IWB-2500-1, examination category B-J, item number B9.ll requires an OD surface examination of the weld and adjacent base metal and a volumetric examination of the weld and adjacent base metal (interior one-third volume) as defined by Figure IWB-2500-8. This weld is not a terminal end or dissimilar metal weld, but is included in the examination category as additional piping welds to ensure that 25% of the reactor coolant piping is examined. The Code does not allow any limitations to the required volumetric or surface examina-tions. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, allows a reduction in cover-age, if it is less than 10 percent.

III. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED Relief is requested from fully performing the Code-required volumetric examination on the above identified reactor coolant piping.

IV. BASIS FOR RELIEF:

The component listed above has been examined to the extent practical as required by the Code. However, full volumet-ric coverage could not be achieved due to joint configura-tion. Coverage of the volumetric and surface examinations are detailed in Table SR-024-1. Figure SR-024-1 is provid-ed as graphic detail of the limitations experienced.

S2-002I3 Rev. 1 2-56 7/94

RELIEF REQUEST SR-024 (CON'T)

Substitution with another weld of the same size would not necessarily improve the examination coverage since this weld is representative of plant design and similar geometric conditions are expected.

IV. PROPOSED ALTERNATE EXAMINATION:

It is proposed that the examination already completed at the reduced coverage be counted as meeting the Code require-ments. In addition:

1. A visual (VT-2) examination will be performed during the normally scheduled system leakage test each refueling outage;

2. Technical Specifications require that the reactor coolant system leak rate be limited to one gallon pe+ minute unidentified leakage. This value is calculated at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and

3. The containment atmosphere particulate radioactivity is checked every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The proposed alternative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised.

S2-002I3 Rev. 1 2-57 7/94

Figure SR-024-1 Search Unit Valve MOV-2594 45' Beam Angle 29"-RC-307-2501R 60' Beam Angle Exam . Vo Iume S2-002I3 2-58 Rev. 1 7/94 l.

Table SR-024-1 Surry Unit 2 Examination Coverage Estimates (Piping) 11548-WMKS-RC-10-1 category B-J, Item B9.ll UT Scan Coverage%

Surface Weld No. 2 5 7 8 Coverage% Reason For Partial 1-03 0 100 25 25 100 Pipe to valve configuration prevented scanning from the 2 side, (valve side). A 60° supplemental examination was performed to increase examina-tion coverage. The use of alternate angles would not have improved volu-metric coverage. Because of the use of the longitudinal wave form only~

node examinations were possible.

UT Scan Direction Definitions 2 axial scan, 180 degrees from Isometric flow direction.

5 axial scan, the same direction as the isometric flow.

7 circumferential scan, clockwise rotation when viewing in the direction of isometric flow.

8 circumferential scan, counter-clockwise rotation when viewing in the direction of isometric flow.

S2-002I3 Rev. 1 2-59 7/94

Virginia Electric & Power Company Surry Power Station Unit 2 Third Ten Year Interval Request for Relief No. SR-025 Status: Granted - NRC Letter No.97-699 Dated 11-24-97 I. Identification of Component:

Mark No. Component No. Drawing No.Class N-01 thru N-58 2-RC-R-l 11548-WMKS-RC-R-l.4 1 The above are reactor vessel closure head nuts.

II. Code requirements:

The 1989 Edition of ASME Section XI Table IWB-2500-1, exami-nation category B-G-1, item number B6.10 requires a surface examination of the reactor vessel closure head nuts.

III. Code Requirement From Which Relief Is Requested:

Relief is requested from performing the Code-required sur-face examination on the above identified reactor vessel closure head nuts.

IV. Basis for Relief:

The 1989 Addenda of ASME Section XI Table IWB-2500-1, exami-nation category B-G-1, item number B6.10 has changed the requirement from a surface examination to a visual (VT-1) examination.

Extensive cleaning of these nuts is required for a surface examination to be performed. This extensive cleaning re-sults in additional costs and the inefficient use of avail-able manpower resources.

Due to design factors, the stripping areas of the female threads in a nut are approximately 1.3 times the areas of the mating male threads (see ASME Bl.1, Unified Inch Screw Threads). Accordingly, if a defect were to be developed during s~rvice, they would occur in the threads of the bolt or stud before developing in the nut's threads because of higher stresses in the male threads. When reactor vessel head fasteners are tightened for closure or loosened for opening, the studs are tensioned and the nuts are run on the threads with no load as the load is taken by the stud or S2-002I3 Rev. 1 2-60 7/94

RELIEF REQUEST SR-025 (CON'T) bolt through the tensioning device.

v. Proposed Alternate Requirement:

It is proposed that the requirements of the 1989 Addenda of ASME Section XI Table IWB-2500-1, examination category B-G-1, item number B6.10 (visual, VT-1) be substituted for the Code surface examination. In addition:

1. A visual (VT-2) examination will be performed during the normally scheduled system leakage test each refuel-ing outage;

2. Technical Specifications require that the reactor coolant system leak rate be limited to one gallon per minute unidentified leakage. This value is calculated at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and

3. The containment atmosphere particulate radioactivity is checked every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The proposed alternative examinations stated above will ensure that the overall level of plant quality and safety will not be compromised.

S2-002I3 Rev. 1 2-61 7/94

RELIEF REQUEST l Status: Granted - NRC Letter No.95-480 Dated 8/30/95 Component(s): Piping and Valves located on station print 11548-CBM-087A-3:

Component Connected Piping Component MOV-2701 14" -RH-101-1502 MOV-2700 Function Residual Heat Removal (RH)

Class Class 1 Section XI Code Requirements For Which Relief Is Reguested Class 1 System Hydrostatic Test, IWB-5222, as modified by Code Case N-498.

Basis For Relief During a normal hydrostatic test of the primary, MOV-2700 is closed in addition to MOV-2701. This prevents pressurization of MOV-2701 and the piping between the two MOVs. Both valves are closed to prevent possible overpressurization of the Residual Heat Removal System.

Alternate Testing Method This area will be tested in conjunction with the normal Class 2 N-498 pressure test at the pressure required by the adjoining Class 2 system.

S2-002I3 Rev. 1 2-62 7/94

RELIEF REQUEST 2 Status: Granted - NRC Letter No.95-480 Dated 8/30/95 Component(s): Open ended intake piping before the first shut-off valve in non-closed systems located on 1~548-CBM-071A-3.

Function Circulating (CW) and Service Water (SW) System Class 3 Section XI Code Requirements For Which Relief Is Requested System Hydrostatic Test, IWD-5223 Basis For Relief The Code addresses the problem of performing hydrostatic tests on open ended portions of discharge lines beyond the last shut-off valve in non-closed systems in IWD-5223(d). A similar problem exists for the intake piping at Surry Unit 2 as it is non-isolat-able for the increased pressure requirements of a hydrostatic test.

Alternate Testing Method As an alternative, the requirements applied to open ended por-tions of discharge lines (IWD-5223(d)) will be applied. In this case confirmation of adequate flow during system operation shall be.acceptable* in lieu of system hydrostatic test.

S2-002I3 Rev. 1 2-63 7/94

RELIEF REQUEST 3 Status: Granted - NRC Letter No.95-480 Dated 8/30/95 Component(s): Piping and components located on the following print: 11548-CBM-071B-3 Function Service Water System Class 3 Section XI Code Requirements For Which Relief Is Requested System Hydrostatic Test - IWD-5223 Basis For Reguest The service water system 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 50 psig (max). The only other possible pressure source for the system would occur if an extensive heat exchanger leak occurred at either 2-SW-E-lA or lB between component cooling and service water. This pressure could be rio more than 57 psig the maximum discharge pressure of 2-CC-P-2A or 2B. Using a design pressure (PD) of 100 psig would be excessive for this system as the maximum pressure potential is 57 psig. Additionally this piping connects to fiberglass reinforced plastic piping, which has a design pressure of 60 psig. In some instances this piping could be included in the hydrostatic test boundary.

Alternate Testing Method As an alternative, it is requested that 60 psig be used as this systems PD value.

S2-002I3 Rev. 1 2-64 7 /94

RELIEF REQUEST 4 Status: Granted - NRC Letter No.95-480 Dated 8/30/95 I. IDENTIFICATION OF COMPONENTS System: Auxiliary Feedwater (AFW)

Component: Piping and components between the following valves located on drawing 11548-CBM-068A-3, Sh. 3 of 4: ,)

Valves Line Valves Class 2-FW-145 1-WAPD-115-601 2-FW-149 3 2-FW-146 3 2-FW-629 3 2-FW-160 1-WAPD-117-601 2-FW-164 3 2-FW-161 3 2-FW-628 3 2-FW-175 1-WAPD-120-601 2-FW-179 3 2-FW-176 3 2-FW-627 3 II. IMPRACTICAL CODE REQUIREMENTS ISI Class 3 System Hydrostatic Test required in IWD-5223 of ASME Section XI, where design pressure is 1432 psig and the resultant test pressure is 1576 psig.

III. BASIS FOR RELIEF Three pressure reducing orifices 2-FW-R0-200A, 2-FW-R0-200B, and 2-FW-R0-200C provide during normal operation a pressure drop from approximately 1200 psig to 110 psig. The system design takes advantage of this pressure. drop by incorporating lower pressure rated piping downstream,of the orifices. However the higher pressure rated piping contin-ues beyond 'the orifices for some distance. The actual pipe design pressure class change occurs at downstream check valves 2-FW-148, 2-FW-163, and 2-FW-178 and manual valves, 2-FW-146, 2-FW-161, and 2-FW-176. The check valve opera-tion, however, does not allow separation of the lower pressure class system, when testing the higher class piping in accordance with IWD-5223. IWD-5223 .requires a test pressure of 1576 psig on the higher pressure class compo-nents in question. The downstream connecting piping has a design pressure of 150 psig and a corresponding test pres-sure of only 165 psig. As such, the connecting components would be overpressurized during the S2-002I3 Rev. 1 2-65 7/94

~

RELIEF REQUEST 4 (CON'T) required Section XI test.

The test boundary could be backed up to manual isolation valves 2-FW-147, 2-FW-162, and 2-FW-177, however hydrostat-ically testing this test boundary would also pressurize the auxiliary feedwater pumps and their suction connection.

These pumps have welded discharge connections and cannot be isolated from the test boundary due to the absence of a drain or vent valve in the area identified above. There is a flange connection on the suction side of each pump, however using this flange for isolation purposes is consid-ered difficult due to the piping arrangement, and suscepti-bility to cold spring misalignment problems. Typically centrifugal pumps are hydrostatically tested at a pressure based on the suction side of the pump as described in IWA-5224(d) of the Code, which prevents any potential overpres-surization concerns, or the need to use pump flanges as isolation points.

The basis for relief then is two-fold. The first impracti-cality is the overpressurization of piping and components downstream of the pressure reducing orifice and the design pressure class rating change. The second impracticality is the incorporation of the auxiliary feedwater pumps into the test boundary due to the lack of vent, drain, and manual isolation valves.

IV. ALTERNATE TESTING The identified components will be tested in accordance with IWD-5222, Functional Test Requirements, in conjunction with the associated auxiliary feedwater pump at normal operating pressure.

S2-002I3 Rev. 1 2-66 7/94

Relief Request No. RR-5 Revision 1 Status: Granted with Conditions NRC Letter No.96-524 Dated 10/8/96 I. IDENTIFICATION OF COMPONENT Class 1, 2 and 3 pressure retaining bolting II. IMPRACTICAL CODE REQUIREMENTS IWA-5250 (a) (2) states, "if leakage occurs at a bolted connection, the bolting shall be removed, VT-3 visually examined for corrosion, and evaluated in accordance with IWA-3100;"

III. BASIS FOR RELIEF Leaking conditions at a bolted connection may be an impor-tant variable in the degradation of fasteners. However, leakage is not the only variable, and some cases may not be the degradation mechanism. Other variables to be consid-ered** are: bolting materials, leaking medium, duration of the leak, and orientation of the leak (not all bolts may be wetted). These variables are important to consider before disassembling a bolted connection for a visual VT-3 exami-nation. Removal of bolting at a mechanical connection may not be the most prudent decision and may cause undue hard-ship without a compensating increase in the level of quali-ty or safety. Virginia Power proposes an alternative to the requirements of IWA-5250 (a) (2) that will provide an equivalent level of quality and safety at Class 1, 2, and 3 bolted connections.

IV. ALTERNATE REQUIREMENTS Leakage discovered at a bolted connection by visual VT-2*

examination during a system pressure test will be evaluated to determine the susceptibility of the bolting to corrosion and potential failure. This evaluation will consider the following variables:

1. Location of leakage;

2. History of leakage;

3. Fastener materials;

4. Evidence of corrosion with the connection assembled;

5. Corrosiveness of the process fluid;

6. History and studies of similar fastener material in a similar environment; and

7. Other components in the vicinity that may be degraded due to the leakage.

S2-002I3 Rev. 1 2-67 7/94

Relief Request No. RR-5 Revision 1 (CON'T)

When evaluation of the above variables is concluded and the evaluation determines that the leaking condition has not degraded the fasteners, then no further action is neces-sary.

If evaluation of the variables above indicates the need for further evaluation, or no evaluation is performed, then the bolt closest to the source of leakage will be removed. The bolt will receive a visual VT-3 examination, and be evalu-ated in accordance with IWA-3100 (a). This visual VT-3 examination may be deferred to the next outage of suffi-cient duration if the evaluation supports continued ser-vice. When the removed bolting shows evidence of reject-able degradation, all remaining bolts shall be removed and receive a visual VT-3 examination and evaluation in accor-dance with IWA-3100 (a).

V. CONDITIONS All of the seven evaluating factors listed in this relief request must be considered, if a bolt is removed.

S2 - 002I3 Rev. 1 2-68 7/94

RELIEF REQUEST 6 Status: Granted - NRC Letter No.95-480 Dated 8/30/95 I. IDENTIFICATION OF COMPONENTS System: Reactor Coolant (RC)

Charging (CH)

Safety Injection (SI)

Components: Pressure retaining bolting located inside containment, which are normally tested in subatmospheric conditi?ns.

ISI Class: 1 and 2 II. IMPRACTICAL CODE REQUIREMENTS Subparagraph IWA-5242(a) requires, for systems borated for the purposes of controlling reactivity, insulation shall be removed from pressure retaining bolted connections for visual examination VT-2.

III. BASIS FOR RELIEF In some cases the reactor coolant system and systems connected to the reactor coolant system are tested in subatmospheric conditions, when the reactor coolant tem-perature is greater than 500° Fahrenheit. Typically this testing is done just prior to startup. Removing and rein-stalling insulation under these conditions is difficult to perform and considered impractical, when compared to the alternate proposal.

IV. ALTERNATIVE REQUIREMENTS It is proposed that bolted connections on Class 1 systems containing boric acid be examined each refueling outage at zero or static pressure. The examination would be per-formed with insulation removed. Class 2 bolting will be examined similarly once a period. This alternative only applies to systems that are pressure tested under subatmo-spheric conditions. In addition the Code required testing will still be conducted without removing the insulation.

The test will be held at nominal operating pressure for four hours for insulated systems and ten minutes for noninsulated systems prior to performing the visual VT-2 examination.

S2-002I3 Rev. 1 2-69 7/94

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT2 INSERVICE INSPECTION PROGRAM FOR COMPONENT SUPPORTS S2-003I3 Rev. 1 3-1 7/94

SECTION 3 TABLE OF CONTENTS 3.0 INSERVICE INSPECTION PROGRAM FOR COMPONENT SUPPORTS 3.1 PROGRAM DESCRIPTION 3.2 PROGRAM EXCLUSIONS S2-003I3 Rev. 1 3-2 7/94

3.0 INSERVICE INSPECTION PROGRAM FOR COMPONENT SUPPORTS 3.1 PROGRAM DESCRIPTION The Inservice Inspection Program for ISI Class 1,2, and 3 component supports meets the requirements of Section XI of the ASME Boiler and Pressure Vessel Code, 1989 Edition, and the alternative provisions found in Code Case N-491, "Alternative Rules for Examination of Class 1, 2, 3, and MC Component Supports of Light-Water Cooled Power PlantsSection XI, Division 1."

3.2 PROGRAM EXCLUSIONS This program does not cover the functional testing of snubbers. Snubbers will be tested to the functional testing requirements described in Technical Specifications_.

3.3 COMPONENT SUPPORT RELIEF REQUESTS Component Support relief requests are presented in a numeric sequence with a SH prefix.

S2-003I3 Rev. 1 3-3 7/94

--~I I

3.3 COMPONENT SUPPORT RELIEF REQUESTS Relief ~

Request a No. status Letter No. Date LJ 0-6/8/95 I SH-1 Granted 95-303

~

cJ Rev. 1 S2-003I3 7/94 3-4

RELIEF REQUEST SH-1 status: Granted - NRC Letter No.95-303 Dated 6/8/95 I. IDENTIFICATION OF COMPONENTS Class 1, 2, and 3 Snubbers II. IMPRACTICAL CODE REQUIREMENTS Section XI of the ASME Boiler and Pressure Vessel Code, 1989 Edition, IWF-5000 with regard to visual examination and repairs/replacements o-f snubbers as required in the first addenda to ASME/ANSI OM-1987, Part 4 (published in 1988).

III. BASIS FOR RELIEF Differences exist between the referenced standard requirements and the Surry Technical Specification 4.17. The first addenda to ASME/ANSI OM-1987, Part 4 (published in 1988} contains requirements, which were removed from technical specifications by Generic Letter 90-09, "Alternative Requirements For Snubber Visual Inspection Intervals and Corrective Actions." This document was issued on December 11, 1990 to reduce the burden placed upon utilities by the then excessively restrictive inspection schedule contained in technical specifications.

The referenced standard in ASME Section XI again requires this excessively restrictive inspection schedule for snubberso This is not a technical issue, but simply a case of the administrative aspects of the Code lagging behind the technical achievements of the industry. Later Code, ASME 0Mb Code-1992, Addenda to ASME OM Code-1990, subsection ISTD, Table ISTD 6.5.2-1, contains the newer inspection schedule requirements. Therefore, requiring the use of the referenced standard's inspection schedule is considered impractical.

The referenced standard. additionally contains requirements eliminated by the later !STD Code (1992 addenda) with regard to visual failure evaluation groupings. As this is not perceived by the industry as a significant technical issue, performance of this requirement would be an unnecessary administrative burden, and therefore impractical to perform.

The remaining aspects of the referenced standard contain requirements, which are essentially the same as those already delineated in the Surry Technical Specification 4.17, and the ASME Section XI Repair/Replacement program. Requiring the use of the referenced standard in these remaining areas is an unnecessary duplication and therefore impractical.

S2-003I3 Rev. 1 3-5 7/94

RELIEF REQUEST SR-1 (CON'T)

"IV. ALTERNATE REQUIREMENTS In lieu of the Code *requirements specified in IWF-5000 for snubber visual examination, the requirements of Surry Technical Specification 4.17 with regard to snubber visual examination shall be followed. The required examination shall be performed by personnel certified visual (VT-3) as required by the Code. Repairs and replacements shall be performed as required by the general requirements (IWA-4000 and IWA-7000) of ASME Section XI.

S2-003I3 Rev. 1 3-6 7/94

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT2 INTERIM RELIEF REQUESTS AND MISCELLANEOUS DOCUMENTATION S2-004I3 Rev. 1 4-1 7/94

--1 SECTION 4 TABLE OF CONTENTS 4.0 INTERIM RELIEF REQUESTS AND MISCELLANEOUS DOCUMENTATION 4.1 RELIEF REQUESTS 4 .1.1 Letter No.94-320 Approved-(Code Case N-416-1) (94-623 Dated, 10/14/94) 4 .1.2 Letter No.93-754 Approved (Code Case N-524) (94-569 Dated 9/17/94) 4 .1. 3 Letter No.95-593 Approved (Code Case N-522) (96-216 Dated 4/16/96)

(Code Case N-535) 4 .1. 4 Letter No.97-264 Approved (Relief Request IWE-1) (97-579 Dated 10/1/97) 4.2 Miscellaneous Documentation (None at this time)

S2-004I3 Rev. 1 4-2 7 /94

VIRGINIA POWER INSERVICE INSPECTION PROGRAM CHANGE / ISSUE APPROVAL FORM STATION: --~S_P-S~~~ UNIT NO.: 1 &2 INTERVAL NO. : 3 SUBMITTAL TITLE: Inservice Inspection_Program for Components and Component Supports CHANGE NO.: ____.N-L~A-- SECTION NO.:-£... REVISION: Ul - RO. U2 - RO Cl F APPLI CA=B=LE=)===

DESCRIPTION OF CHANGES:

Deleted Relief Request 9 - Unit 1 Incorporate Code Case N-416-1 for both units (ATTACH PAGE(S) SHOWING EXACT WORDING OF PROPOSED CHANGE)

REASON FOR CHANGE:

Code Case N-416-1 approved by the ASME Code. which incorporated the alternative requirements proposed in Relief Request 9.

ORIGINATED BY: Alex McNeil! DATE: 5/24/94 DEPARTMENT: ISI/NDE and Engineering Programs SUPERVISOR - ISI/NDE INSPECTION PROGRAMS REVIEWED AND APPROVED: DATE:

SUPERVISOR - ISI/NDE INSPECTION PROGRAMS (STATION)

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REVIEWED: ~f~ DATE: .fi:. j (-'1~

STATION NUCLEAR AND OPERATING COMMITTEE ( SNSOC).

REVIEWED AND APPROVED:~~~~~+IP~~~~~~~~~~~~ DATE:

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

AFTER APPROVAL, RE Joyce A. Lindsay, IN-3NW Virginia Power, 5000 Dominion Blvd., Glen Allen, VA 23060 DISTRIBUTION NO. :: 2 DISTRIBUTION DATE: JUL 05199,

VIRGINIA ELECTRIC AND PowER CoMPAXY RICHMOND, VIRGINIA 23261 June 22, 1994 United States Nuclear Regulatory Commission Serial No.94-320 Attention: Document Control Desk SPS/ETS Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen, VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS l AND 2 INSERVICE INSPECTION PROGRAM ASME COPE CASE N-416-1 ASME Code Case N-416-1 (attached), "'Alternative Pressure Test Requirement for Welded Repairs or Installation of Replacement Items by Welding~ Class 1, 2, and 3 Section XI, Division 1,

was approved by the ASME Code on February 15, 1994.

However, this Code Case has not yet been endorsed in Regulatory Guide 1.147,

"'lnservice Inspection Code Case Acceptability ASME Section XI Division 1,* due to its recent approval by ASME. Therefore, pursuant to 10 CFR 50.55a(a)(3), it is requested that Code Case N=416-1 be approved for use during the Surry Units 1 and 2 third 10-year intervals in lieu of the previously submitted relief request.

By letter dated July 16, 1993 (Serial No.93-420), Relief Request 9 of the third interval ISi Program tor Surry Unit 1 was submitted to the NRC for approval. This request addresses post weld repair and replacement testing requirements, which are similar to the requirements delineated in Code Case N-416-1. Since the ASME Code now addresses post weld repair and replacement hydrostatic testing requirements through Code Case N-416-1, Relief Request 9 of the Unit 1 ISi Program is no longer necessary and is hereby withdrawn.

In past situations we have found it necessary to defer hydrostatic tests or ask relief from post ASME Section XI hydrostatic tests following repair or replacement activities.

This was due to various reasons of impracticality in testing, ranging from boundary valve isolation problems to incorporation of the steam generators within the hydrostatic test boundary. These situations are typically unexpected and are usually only identified during the actual inservice inspection. As a consequence, some of these situations have necessitated immediate communication with the NRC to avoid exceeding limiting conditions of operation or startup delays.

Use of hydrostatic test deferrals, which are presently allowed in the current Code Case N-416 for Class 2 components, are not a satisfactory solution because the test must eventually be performed, and it is the *performance of the test itself that is considered*

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burdensome. Deferred hydrostatic testing requirements should be assessed considering that the 10-year hydrostatic test is no longer required with the NRC, endorsement of Code Case N-498, Alternative Rules for 10-year Hydrostatic Pressure Testing for Class 1 and 2 SystemsSection XI, Division 1.

Code Case N-416-1 provides increased testing flexipility to the Owner, which should considerably reduce, if not eliminate, relief request requirements associated with post welded repair/replacement hydrostatic testing. This is accomplished while maintaining an acceptable level of safety and quality as determined by the ASME Code.

Unit 2 is currently scheduled to start its refueling outage .in January of 1995. The Unit 1 refueling outage is currently scheduled to start in September of 1995. If permanent approval for use of Code Case N-416-1 cannot be obtained in the time period remaining prior to the refueling outages, it is requested that Surry be granted interim approval to use Code Case N-416-1 for the next refueling outages.

If you have any questions, please contact us.

Very truly yours,

/J, __ ,. 'V.(fJ/~

~'Hanlon Senior Vice President - Nuclear Attachment cc: U.S. Nuclear Regulatory Commission Region II 1o1 Marietta Street, N.W.

Atlanta, Georgia 30323 Mr. Morris Branch NFiC Senior Resident Inspector Surry Power Station

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CASE N-416-1 CASES OF ASME BOILER AND PRESSURE VESSEL CODE Approval Data: February 15, 1994 SH Numeric Index tor expiration and any reattlnnatlon dates Case N-416-1 placement items by welding, system leakage test may Altfmafive Pressure Test RequireDEDt for Welded be used provided the following requirements arc met Repairs or Im1allaion or Replacement Iiem; by (a) NDE shall be performed in accordance with the Welding, Clau 1, 2 and 3 methods and acceptancc criteria of the applicable Sub-Section XI, Division 1 section of the 1992 Edition of Section m.

(b) Prior to or immediately upon rcDJm to service, a visual examination (VI'-2) shall be performed in con-junction with a system leakage test, using the 1992 Edi-Inquiry: What alternative ~ssure test may be per- tion of Section XI, in accordance with para. 1WA-5000 formed in lieu of the hydrostatic pressure test required at nominal operating ~ssurc and temperature.

by para. 1WA4000 for welded repairs or installation of (c) Use of this Case shall be documented on an NIS-rcpla.ccment items by welding?

2 Form. .

Reply: It is the opinion of the Committee that in lieu

If the previous version of this case W'CI'C used to defer of performing the hydrostatic pressure test required by a Class 2 hydrostatic test. the deferred test may be clim-para. 1WA-4000 for welded repairs or installation of re- inated when the requirements of this revision are met

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649 SUPP. 8 - NC

'VIRGINIA POWER INSERVICE INSPEcnON PROGRAM CHANGE / ISSUE APPROVAL FORM

,JA/2r UHIT HO.: / L nrrERVAL NO. : 2..

STATION:

SUBMITTAL TITLE: -

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Uj_- :3 CHANGE NO. : SECTION HO. : J;.__ REVISION:u'Z-4r (IF AP'PUCAILE)

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DEPARTMENT: .r~.rL_A.I.De SUPERVISOR - ISI/HDE INSPECTION PROGRAMS

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SUPERVISOR - ISI/NDE INSPECTION PROGRAMS (STATION)

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ANII (STATION)

REVIEWED: ~GJ ,%' Lr DATE: <<:/£QJ STATION NUCLEAR SAFETY AND OPERATING COMMITTEE (SNSOC)

REVIEWED AND oA \\s~ \l.9"-t J APPROVED: ~ 4 AFTER APPROVAL, RETURN TO: Joyce A. Lindsay,. :T.N-311£i DATE:

Virginia Power, 5000 Dominion Blvd., Glen Allen, VA 23060 DISTRIBUTION NO.: DISTRIBUTION DATE:

FORN7* 15. WPS

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA. 23261 December 10,*1993 United States Nuclear Regulatory Commission Serial No.93-754 Attention: Document Control Desk NL&P/ETS Washington, D. C. 20555 Docket Nos. 50-280 50-281 50-338 50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 NORTH ANNA POWER STATION UNITS 1 AND 2 INSERVICE INSPECTION PROGRAMS CODE CASE N~24*USAGE APPBQYAL The ASME Code Committee approved Code Case N-524, Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping Section XI, Division 1, August 9, 1993 (attached). We have just recently received our copy of the formal Code Case from ASME. Due to its recent approval, Code Case N-524 has not yet been approved for use in Regulatory Guide 1.147, lnservice_ Inspection Code Case Acceptability ASME Section XI, Division 1. However, provisions stated in footnote 6 to 1o CFR 50.55a provide for use of other Code Cases upon request, if approved by the Director of the Office of Nuclear Reactor Regulation pursuant to 10 CFR 50.55a(a)(3).

Accordingly, we are requesting use of Code Case N-524 at North Anna for the Unit 1 and 2 Second Interval lnservice Inspection Programs, and at Surry for the Unit 1 Second and Third Interval lnservice Inspection Programs, and for the Unit 2 Second Interval lnservice Inspection Program. The basis for our request is provided below.

The ASME Section XI Code (1989 Edition) currently requires one pipe diameter in length, but no more than 12 inches, be examined for Class 1 longitudinal piping welds.

Class 2 longitudinal piping welds are required to be examined for a length of 2.5t, where t is the thickness of the weld. These lengths of weld are measured from the intersection of the circumferential weld and longitudinal weld. Code Case Na524 significantly reduces the required examination volume or surface area. It does this by limiting the examination of the longitudinal weld to the volume or area contained within the examination requirements of the intersecting circumferential weld. This would include the weld and 1/2 inch on both sides of the *weld crown for surface examinations, and 1/4 inch on both sides of the weld crown for volumetric examinatit;ms (lower one third).

VP.

LETIER NO. q3- *Zr;Jf DATE J;;.0Pll3 APPROVED i NRC LEDER NO. 9#-s,z,.. ,ll7/9t1J t~-~~~~~~~~~~-

Code Case N-524 directs the examination effort at the high risk area associated with the weld intersections. It eliminates low risk areas on the longitudinal weld from examination, significantly reducing examination time requirements and exposure to examination personnel. Compliance with the existing ASME Section XI requirements, in lieu of the Code Case, results in unnecessary personnel exposure to complete the required examinations without a compensating increase in the level of quality or safety.

The use of Code Case N-524 has been reviewed by the North Anna and Surry Station Nuclear Safety and Operating Committees.

If there are any questions concerning this matter, please contact us.

Very truly yours, W.L Stewart Attachment e cc: U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, -N~W.

Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station Mr. R. D. McWhorter NRC Senior Resident Inspector North Anna Power Station

-1 Serial No.93-754; SPS/NAPS Use of Code Case N-524 be: Mr. J. "A. Price - SPS page 1 of 1 Mr. J. A. StaJI - NAPS Mr. J. D. Hegner- IN2SE Mr. D. A Sommers - IN2SE Mr. W. R. BenthaJI - SPS Mr. P.A. Kemp- NAPS Mr. E. T. Shaub - IN2SE Mr. A. McNeil! - IN3NW Licensing File (GOV 02-548)

Licensing Information Service Power Records Management (be. original) - ING4 MSRC. Coordinator CONCURRENCE J.P. O'Hanlon/R. F. Sanders E. W. Harrell M. L Bowling E. S. Grecheck D. A. Sommers J. D. Hegner M. R. Kansler

G. E. Kane Action Piao

1. Modify the ISi Programs to incorporate the guidance of Code Case N-524, dated August 9, 1993.

Venfication of Accuracy

1. See attached Code Case N-524 Commitments <Stated or tmpt;edl

1. None Required Changes to the UfSAR or OA Top;ca1 Repon

1. None

CASE N-524 CASES 01-' .UM£ BOILER AND PR&UURE YaSEL CODE Appn,val Data: Aufult ** 1113 SH Nu,,,.rit:al lnd*x fDr crpimion

nd *ny ,..ff;,mation dflfl.

Cue N-524 Alterutift Esamlaation Requirements for Lc,npmdiul Welda in a... 1 ud 2 Pipblc Sedioa XI, Dnuian 1 Inquiry: What alternative requirements may be ap-plied to the surface and wlumetric examination of longitudinal piping welds specified in Table IWB-2500-1, Eumination Categoey B-J, Table IWC-2500-1, Examination Oltegoric:s C-F-1 and C-F-2 (Exam-ination Category C-F prior to Wmter 1983 Adden-da), and Table IWC-2520, Bnmination Category C-G (1974 Edition, Summer 1975 Addenda)?

Reply: It is the opinion of the Committee that the following shall apply:

(a) When only a surface examination is tequired, examination of longitudinal piping welds is not re-quired beyond those portions of the welds within the examination boundaries of intersecting circumfer-ential welds.

(b) When both surface and volumetric_~-

lions arc required, examination of longitudinal piping welds is not required beyond those portions of the welds within the examination boundaries of inter-secting circmufcrential welds provided the following requirements a~et .

(1) Where longitudinal welds arc specified and locations are known, examination requirements shall be met for both transverse and parallel flaws at the intersection of the welds and for that length of lon-gitudinal weld within the circumferential weld ex-amination volume; (2) Where longitudinal welds are specified but locations are unknown, or the existence of longitu-dinal welds is uncenain, the examination require-ments shall be met for both transverse and parallel flaws within the entire examination volume of inter-secting circumferential welds.

903 SUPP. 6 - NC

VIRGINIA. ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 7, 1995 United States Nuclear Regulatory Commission , Serial No. ~5-593 Attention: Document Control Desk NLOS/ETS Washington, D.C. 20555 License Nos. DPR-32 DPR-37 Docket Nos. 50-280 50-281 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 & 2 REQUEST FOR USE OF ASME SECTION XI CODE CASES THIRD INTERVAL INSERVICE INSPECTION PROGRAMS Code Case N-522, "Pressure Testing of Containment Penetration Piping," and Code Case N-535, uAltemative Requirements for lnservice Inspection Intervals," are not currently approved for use by Regulatory Guide 1.147, lnservice Inspection Code Case Acceptability ASME Section XI Division 1. Footnote 6 of 10 CFR 50.55a states that other Code Cases may be authorized upon request pursuant to 10 CFR 50.55a(a)(3). In accordance with these provisions, permission is requested to utilize these Code Cases in Surry's ASME Section XI lnservice Inspection Program.

Code Case N-522 permits the use of Appendix J leakage testing requirements as an alternative to the rules in the Code that govern the pressure testing of certain containment penetrations. Application of this Code Case will reduce the pressure testing requirements for these containment penetrations consistent with the Appendix J performance-based testing requirements for containment penetrations.

Code Case N-535 interprets interval inspection scheduling requirements and allows both interval and period extensions of up to one year to enable an inspection to coincide with a plant outage. Application of this Code Case would provide additional inspection scheduling flexibility in completing period-specific inspections allowing better application of inspection resources during refueling outages.

Currently, Surry Unit 2 is scheduled for a refueling outage in May of 1996 and Surry Unit 1 is scheduled for a refueling outage in February of 1997. It is requested that consideration for approval be completed in time to SU ort the M rage as V.P. LETTER NO. ?S'-.{]'3 @4hs'. I .

. . -~

. J I

NRC LETIEit 1*m '!£-~;::_~/IJ./f? I c.,;. r... ,

both these cases could affect outage inservice inspection requirements and resources .

If you have any questions, please contact us.

Very truly yours,

.~;:?~~

James P. O'Hanlon Sr. Vice President-Nuclear cc: U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch N RC Senior Resident Inspector Surry Power Station Iv. P. LETTER No. 7J-;s9S LJl?d1 DATE /

NRC LETTER NO. ft-;l//z _ _

I

,_____________ DAH

Serial No.95-593 SPS 1 and 2 Code Cases N-522 and 535 be: Dr. 8. L. Shriver - SPS Mr. D. A. Sommers - IN2SE Mr. P. A. Kemp - NAPS Mr. C. G. Lovett - SPS Mr. E.T. Shaub- lN2SE Mr. A. McNeill - lN3NW Ms. J. A. Lindsay - IN3NW GOV02-54B Licensing Information Service Power Records Management (be original) - ING4 CONCURRENCE J. P. O'Hanlon R. F. Saunders M. L. Bowling L. N. Hartz c.Mt <</zy,r Ii"'( ,,11.i-1'1.<

D. A. Sommers ~ **/i.e{q~

D. A. Christian/SPS Commitments (Stated or Implied) and Action Plan

1. No new commitments Action - Incorporate the alternative requirements of Code Case N-522 and N-535 into ISi program after NRC approval.

Verification of Accuracy

1. Code Case N-522, "Pressure Testing of Containment Penetration Piping"

2. Code Case N-535, *Alternative Requirements for lnservice Inspection Intervals"

3. SPS 1 and 2 Outage Schedule 95-03, September 1995 Required Changes to the UFSAR or QA Topical Report 1 None.

IV. P. LETTER. NO. 9S:~TE 1~b1t NRC LETTER N0.9t-d/fv 4fi~

lL________ DATE~

____,~---__j

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... CASE N-522 CASES OF ASME BOILER AND PRESSURE VESSEL CODE

Approval Date: Dec:amber 9. 1993 SH NutMrieal Index for upnlion

.,,o *nY rNfflrmation dares.

Case N-522 Pressure Testinl of Contaillment Pmetntion Piping Section ~ Division 1 Inquiry: What altc:mative ID die rules of Table IWC-2500-1. CateJorY C-H may be med for preume testing piping that penemia

eoalllhanem wmel. when die piping and isolalian valves that me put of the c:omain-ment sy11em arc Class 2 bat die bllanc:e of the -piping system is outside the scope of Section XI?

Reply: his lbe opinion of lbe Committee that 10 CPR SO. Appendix J. may be used as an altcmativc to the rules in Table iWC-2500-1. Category C-H. for pressUR teaing piping d i a l ~ . c:omaimnem vessel. when the piping and isolation valves that arc pan of the con-tainment system arc Class 2 but the balance of the pip-ing syn:m is outside the scope of Section XI?

V.P. LETTER NO. ~S-f3 DATE

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/

NRC LETTER NO. ,96 ,ef/6 DATE 902.1 SUPP. 7 - NC

.... CASE N-535 CASES OF ASME BOILER AND PRESSURE VESSEL CODE Approval Date: December 12, 19!M See Numeric Index for expiration

nd *ny reaffirmation dares.

Case N-535 If an inspection interval is extended, neither the start Alternative Requirements for lmenice Inspection and end-dates nor the inservicc inspection program Intervals for the successive interval need be revised.

Section XI, Division I (b) Examinations may be performed to satisfy the requirements of the extended interval in conjunction IIUJUirl: What alternative to the requirements of with examinations performed to satisfy the requir-IWA-2430(d) may be used for scheduling inservice ments of the successive interval. However, an ex-inspections for components inspected under Program amination performed to satisfy requirements of B? either the extended interval or the successive interval shall not be credited to both intervals.

(c) That ponion of an inspection interval de-Reply: It is the opinion of the Committee that the scribed as an inspection period may be reduced or following requirements may be used in lieu of 1WA- extended by as much as one year to enable an in-2430( d) for scheduling inservicc inspections for com- spection to coincide with a plant outage. This ad-ponents inspected under Inspection Program B: justment shall not alter the requireme~ts for sched-(a) Each inspection interval may be reduced or ex- uling inspection intervals.

tended by as much as one year. Adjustments shall (d) The inspection interval for which an examina-not cause successive intervals to be altered by more tion was performed shall be indentified on exami-than m~e year from the original pattern of intervals. nation records.

V. P. LETTE~ NO. 9~---sfs Idr/r;,/fS DA,E I f\JRC LETTER NO. 7t-d~E #II~

935 -SUPP. 11 - NC

VIRGINIA ELECTRIC AND, POWER COMPANY lbcHM<>ND, V1RGINIA 23261

May 22, 1997 United States Nuclear Regulatory Commission. Serial No.97-264 Attention: Document Control Desk NL&OS/ETS R1 Washington, D.C. 20555 Docket Nos. 50-280, 281 50-338, 339 License Nos. DPR-32, 37 NPF-4, 7 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 NORTH ANNA POWER STATION UNITS 1 AND 2 ASME SECTION XI RELIEF REQUESTS Surry Power Station Units 1 and 2 are presently in the third ten year inservice inspection interval and examinations are conducted to the requirements of the 1989 Edition of ASME Section XI. North Anna Power Station Units 1 and 2 are presently in the second ten year inservice inspection interval and examinations are conducted to the requirements of the 1983 and 1986 Editions of ASME Section XI, respectively.

Pursuant to 10 CFR 50.55a(g), relief is requested from the requirements of the ASME Section XI Code for IWE and IWL repair and replacement activities for both Surry and North Anna from the effective date of Subsection IWE and Subsection_ IWL until September 9, 1997.

By Federal Register Notice 154 (Volume 61 ), dated August 8, 1996, the Nuclear

Regulatory Commission amended its regulations to incorporate by reference the 1992 edition with 1992 addenda of Subsection IWE, and Subsection IWL, with specified modifications and a limitation in 10 CFR 50.55a. The effective date of the amended rule was September 9, 1996. The rule requires an expedited schedule for the completion of examinations, specifying that the first containment inspection (of the first interval) must be completed within five years from the effective date of the rule, that is, September 9, 2001. The rule does not provide time to develop procedures to implement the rules of Subsection IWE and Subsection IWL for repairs and replacements. Therefore, relief is being requested from the repair/replacement

'requirements of the Code until the appropriate implementing procedures can be developed.

Relief requests for Surry Units 1 and 2 and North Anna Units 1 and 2 are provided in Attachments 1 and 2, respectively. These relief requests have been approved by the applicable Station Nuclear Safety and Operating Committee.

No new commitments are made as a result of this letter. If you have any questions concerning this request, please contact us.

Very truly yours, (J(Jd~

R. F. Saunders Vice President - Nuclear Engineering Services Enclosure cc: U. S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 NRG Senior Resident Inspector North Anna Power Station Mr. R. A. Musser NRG Senior Resident Inspector Surry Power Station

ATTACHMENT 1 ASME SECTION XI RELIEF REQUEST NO. IWE.:.1 SURRY POWER STATION UNITS 1 AND 2

Virginia Electric & Power Company Surry Power Station Units 1 and 2 Third 10 Year Interval Relief Request IWE-1

1. IDENT~FICATION OF COMPONENTS All components subject to the rules and requirements for repair and replacement of Class MC pressure retaining compo_nents and their integral attachments, and of metallic shell and penetration liner of Class CC pressure retaining components and their integral attachments in light-water cooled plants as stated in the 1992 edition 1992 addenda of Subsection IWE, "Requirement for Class MC and Metallic Liners of Class CC Components of Light Water Cooled Plants," and IWL, "Requirements for Class CC Concrete Components of Light-Water Cooled Plants", of Section XI, Division 1, of the ASME Boiler and Pressure Vessel Code II. CODE REQUIREMENTS By Federal Register Notice 154 (Volume 61), dated August 8, 1996, the Nuclear Regulatory Commission amended its regulations to incorporate by reference the 1992 edition with 1992 addenda of Subsection IWE, and Subsection IWL, with specified modifications and a limitation in 10 CFR 50.55a. The effective date of the amended rule was September 9, 1996. The rule requires an expedited schedule to complete examinations, specifying that the first containment inspection (of the first interval) must be completed within five years from the effective date of the rule, that is, September 9, 2001. The rule does not provide time to develop procedures to implement the rules of Subsection IWE and Subsection IWL for repairs and replacements.

Ill. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED Relief is requested from the rules of Articles IWE-4000, "Repair Procedures",

and IWE-7000 "Replacements", IWL-4000 "Repair Procedures", IWL-7000 "Replacements", for a period of one year from the effective date of Subsection IWE and Subsection IWL, September 9, 1997.

IV. BASIS FOR RELIEF In order to meet the repair and replacement requirements of Subsection IWE and Subsection IWL, procedures will have to be developed. These new procedures will take time to develop and implement.

e Repair and replacement activities are currently being performed in a controlled process under work orders and maintenance procedures. Materials and work practices are controlled under Virginia Electric and Power Company's Quality

Assurance Program. The work order process specifies post maintenance testing

to assure the component will perform its design function.

V. ALTERNATE PROVISIONS It is proposed that repair and replacement of items within the scope of Subs~ction IWE and Subsection IWL be controlled by maintenance and work order procedures. These procedures will be used until procedures are developed to satisfy the requirements of Subsection IWE and Subsection IWL.

The new procedures will be developed and implemented by September 9, 1997.

The proposed alternative stated above will ensure that the overall level of plant quality and safety will not be compromised.

VI. IMPLEMENTATION SCHEDULE This relief request will be implemented upon receiving NRC approval and will expire on September 9, 1997.

"\

ATTACHMENT 2 ASME SECTION XI RELIEF REQUEST NO. IWE-1 NORTH ANNA POWER STATION UNITS 1 AND 2

Virginia Electric & Power Company

North Anna Power Station Units 1 and 2 Second 10 Year Interval Relief Request IWE-1 I. IDENTIFICATION OF COMPONENTS All components subject to the rules and requirements for repair and replacement of Class MC pressure retaining compo_nents and their integral attachments, and of metallic shell and penetration liner of Class CC pressure retaining components and their integral attachments in light-water cooled plants as stated in the 1992 edition 1992 addenda of Subsection IWE, "Requirement for Class MC and Metallic Liners of Class CC Components of Light Water Cooled Plants," and IWL, "Requirements for Class CC Concrete Components of Light-Water Cooled Plants", of Section XI, Division 1, of the ASME Boiler and Pressure Vessel Code

11. CODE REQUIREMENTS By Federal Register Notice 154 (Volume 61 ), dated August 8, 1996, the Nuclear Regulatory Commission amended its regulations to incorporate by reference the 1992 edition with 1992 addenda of Subsection IWE, and Subsection IWL, with specified modifications and a limitation in 10 CFR 50.55a. The effective date of the amended rule was September 9, 1996. The rule requires for an expedited schedule to complete examinations, specifying that the first containment inspection (of the first interval) must be completed within five years from the effective date of the rule, that is, September 9, 2001. The rule does not provide time to develop procedures to implement the rules of Subsection IWE and Subsection IWL for repairs and replacements.

Ill. CODE REQUIREMENT FROM WHICH RELIEF IS REQUESTED Relief is requested from the rules of Articles IWE-4000, "Repair Procedures",

and IWE-7000 "Replacements", IWL-4000 "Repair Procedures", IWL-7000 "Replacements", for a period of one year from the effective date of Subsection IWE and Subsection IWL, September 9, 1997.

IV. BASIS FOR RELIEF In order to meet the repair and replacement requirements of Subsection IWE and Subsection IWL, procedures will have to be developed. These new procedures will take time to develop and implement.

Repair and replacement activities are currently being performed in a controlled process under work orders and maintenance procedures. Materials and work practices are controlled under Virginia Electric and Power Company's Quality

Assurance Program.* The work order process specifies post maintenance testing to assure the component will perform its design function.

V. ALTERNATE PROVISIONS It is proposed that repair . and replacement of items within the scope of Subsection IWE and Subsection IWL be controlled by maintenance and work order procedures. These procedures will be used until

procedures are developed to satisfy the requirements of Subsection IWE and Subsection IWL.

The new procedures will be developed ~nd implemented by September 9, 1997.

The proposed alternative stated above will ensure that the overall level of plant quality and safety will*not be compromised.

VI. IMPLEMENTATION SCHEDULE This relief request will be implemented upon* receiving NRC approval and will expire on September 9, 1997.

ATTACHMENT 2

SUMMARY

OF CHANGES AND ASME SECTION XI INSERVICE INSPECTION PLAN FORCOMPONENTSANDCOMPONENTSUPPORTS THIRD INSPECTION INTERVAL, REV. 9 SURRY POWER STATION UNIT 2

March 11, 1998 Surry Power Station Unit 2, Interval 3, Period 2 Summary of Changes To Plan Through Revision 9 Sorted By Drawing and Mark Number

Drawing No. MarkNo. Line Number Category Item No. Location Period

Method 11448-FM-132A Special Lift Devices NA NA NA CONT.47 2 MT Comments Added New To Plan With Revision 7: Examine Special Lifting Devices: Reactor Cavity Seal Ring Lift Rig Critical Welds. Reference memorandum from Design Engineering, J.D. MacCrimmon of February 20, 1996, which identifies critical welds. Year examination is due is 1997. The acoustic emission (AE) method may be used in lieu ot; or in addition to surface examination.

ll448-FM-50A Special Lift Devices NA NA AUX BLDG. 2 PT Comments Added New To Plan With Revision 8: Examine Special Lifting Devices: Spent Filter Cask Spreader Beam. Reference memorandum from Design Engineering. J.D. MacCrimmon ofFebruary 5, 1997, which identifies critical welds. Year examination is due is 1997. The acoustic emission (AE) method may be used in lieu ot; or in addition to surface examination. Also see UFSAR Appendix 9B.

ll 548-FM-086B 2-RC-E-2 2-RC-E-2 NA NA CONT.-3 VT-2 Comments Pressurizer Instrument Connections. New with Rev. 7 to plan: Reference memorandum from Spencer Semmes to E.W. Throckmorton dated 1-25-96 and Augmented Inspection Manual Attachment 35.

Examination Method is a modified VT-2, i.e., pressurizer will not be pressurized. Reference VPAP-1103 with special attention paid for the appearance of boric acid crystals and corrosion (rust) on the external surface of the shell of the pressurizer at nozzle locations, which would indicate evidence ofleakage. Nozzle locations are as follows, l Ototal, Reference l l 548-FM-086B, Sheet l: 2-RC-TE-2453-1, 2-RC-TE-2453-2, 2-RC-TE-2454, and at the pressurizer pipe interface (on the pressurizer) at the lines connected to the followwingvalves: 2-RC-126, 2-RC-127, 2-RC-128, 2-RC-129, 2-RC-130; 2-RC-132, and line No. 3/4"-RC-854-1502.

11548-FM-086B 2-RC-E-2 2-RC-E-2 NA NA CONT. -3 2 VT-2 Comments Pressurizer Instrument Connections. New with Rev. 7 to plan: Reference memorandum from Spencer Semmes to E.W. Throckmorton dated 1-25-96 and Augmented Inspection Manual Attachment 35.

Examination Method is a modified VT-2, i.e., pressurizer will not be pressurized. Reference VPAP-1103 with special attention paid for the appearance of boric acid crystals and corrosion (rust) on the external surface ofthe shell of the pressurizer at nozzle locations, which would indicate evidence ofleakage. Nozzle locations are as follows, 10 total, Reference l 1548-FM-086B, Sheet 1: 2-RC-TE-2453-1, 2-RC-TE-2453-2, 2-RC-TE-2454, and at the pressurizer pipe interface (on the pressurizer) at the lines connected to the followwing valves: 2-RC-126, 2-RC-127, 2-RC-128, 2-RC-129, 2-RC-130, 2-RC-132, and line No. 3/4"-RC-854-1502. Examination year is 2000.

11548-FM-086B 2-RC-E-2 2-RC-E-2 NA NA CONT. -3 2 VT-2 Comments Pressurizer Instrument Co1U1ections. New with Rev. 7 to plan: Reference memorandum from Spencer Semmes to E.W. Throckmorton dated 1-25-96 and Augmented Inspection Manual Attachment 35.

Examination Method is a modified VT-2, i.e., pressurizer will not be pressurized. Reference VPAP-1103 with special attention paid for the appearance of boric acid crystals and corrosion (rust) on the external surface of the shell of the pressurizer at nozzle locations, which would indicate evidence ofleakage. Nozzle locations are as follows, 10 total, Reference l 1548-FM-086B, Sheet 1: 2-RC-TE-2453-1, 2-RC-TE-2453-2, 2-RC-TE-2454, and at the pressurizer pipe interface (on the pressurizer) at the Jines connected to the followwing valves: 2-RC-126, 2-RC-127, 2-RC-128, 2-RC-129, 2-RC-130, 2-RC-132, and line No. 3/4"-RC-854-1502.

ll 548-FM-086B 2-RC-E-2 2-RC-E-2 NA NA CONT. -3 2 VT-2 Comments Pressurizer Instrument Connections. New with Rev. 7 to plan: Reference memorandum from Spencer Semmes to E.W. Throckmorton dated 1-25-96 and Augmented Inspection Manual Attachment 35.

Examination Method is a modified VT-2, i.e., pressurizer will not be pressurized. Reference VPAP-1103 with special attention paid for the appearance of boric acid crystals and corrosion (rust) on the external surface of the shell of the pressurizer at nozzle locations, which would indicate evidence ofleakage. Nozzle locations are as follows, JO total, Reference l 1548-FM-086B, Sheet l: 2-RC-TE-2453-1, 2-RC-TE-2453-2, 2-RC-TE-2454, and at the pressurizer pipe interface (on the pressurizer) at the lines connected to the followwingvalves: 2-RC-126, 2-RC-127, 2-RC-128, 2-RC-129, 2-RC-130, 2-RC-132, and line No. 3/4"-RC-854-1502.

ll 548-FM-086B 2-RC-E-2 2-RC-E-2 NA NA CONT. -3 3 VT-2 Comments Pressurizer Instrument Co1U1ections. New with Rev. 7 to plan: Reference memorandum from Spencer Semmes to E.W. Throckmorton dated 1-25-96 and Augmented Inspection Manual Attachment 35.

Examination Method is a modified VT-2, i.e., pressurizer will not be pressurized. Reference VPAP-1103 with special attention paid for the appearance of boric acid crystals and corrosion (rust) on the external surface of the shell ofthe pressurizer at nozzle locations, which would indicate evidence ofleakage. Nozzle locations are as follows, 10 total, Reference l 1548-FM-086B, Sheet l: 2-RC-TE-2453-1, 2-RC-TE-2453-2, 2-RC-TE-2454, and at the pressurizer pipe interface (on the pressurizer) at the lines connected to the followwing valves: 2-RC-126, 2-RC-127, 2-RC-128, 2-RC-129, 2-RC-130, 2-RC-132, and line No. 3/4"-RC-854-1502.

ll548-FM-086B 2-RC-E-2 2-RC-E-2 NA NA CONT. -3 3 VT-2 Comments Pressurizer Instrument Connections. New with Rev. 7 to plan: Reference memorandum from Spencer Semmes to E.W. Throckmorton dated 1-25-96 and Augmented Inspection Manual Attachment 35.

Examination Method is a modified VT-2, i.e., pressurizer will not be pressutjzed. Reference VPAP-1103 with special attention paid for the appearance of boric acid crystals and corrosion (rust) on the external surface of the shell of the pressurizer at nozzle locations, which would indicate evidence ofleakage. Nozzle locations are as follows, 10 total, Reference I I 548-FM-086B, Sheet I: 2-RC-TE-2453-1, 2-RC-TE-2453-2, 2-RC-TE-2454, and at the pressurizer pipe interface (on the pressurizer) at the lines connected to the followwingvalves: 2-RC-126, 2-RC-127, 2-RC-128, 2-RC-129, 2-RC-130, 2-RC-132, and line No. 3/4"-RC-854-1502. Added with Rev. 7 to the plan, to cover the refueling outage scheduled in year 2003 and in period 3.

Swnmary of Changes Sorted by Drawing and Mark No., SPSU23 Database Page 1 of 46 Print Date: 4121/98

Dra'l\ing No. Mark No. Line Nwnber Category Item No. Location Period

Method 11548-MKS-124A2-4 2-RC-HOOIA 12"-RC-336-602 NA NA CONT. -3 3 VT-3 Comments Support SH. Augmented support program in accordance with QAE 88-60-06. Added to plan with Rev. 6 because an internal review showed that an additional support needed to be added.

11548-SPM-XXXXXX PRESSURE TEST VARIOUS NA NA VARIOUS VT-2 Comments PRESSURE TEST PROGRAM. The site lSl Group will be responsible for tl1e development and implementation of the pressure test plan, which will include all the features required, i.e., categories, items, schedule, etc. The System Pressure Test Plan is issued as Volume 3 to the Inservice Inspection Plan.

11548-SPM-XXXXXX PRESSURE TEST VARIOUS NA NA VARIOUS VT-2 Comments PRESSURE TEST PROGRAlvl. The site ISi Group will be responsible for the development and implementation oftl1e pressure test plan, which will include all tl1e features required, i.e., categories, items, schedule, etc. The System Pressure Test Plan is issued as Volume 3 to the Inservice Inspection Plan.

I 1548-SPM-XXXXXX PRESSURE TEST VARIOUS NA NA VARIOUS VT-2 Comments PRESSURE TEST PROGRAM. The site !SI Group will be responsible for the development and implementation of the pressure test plan, which will include all the features required, i.e., categories, items, schedule, etc. The System Pressure Test Plan is issued as Volume 3 to tlte Inservice Inspection Plan.

I I 548-SPM-XXXXXX PRESSURE TEST VARIOUS NA NA VARIOUS 2 VT-2 Comments PRESSURE TEST PROGRAM. The site ISI Group will be responsible for tl1e development and implementation of the pressure test plan, which will include all tl1e features required, i.e., categories, items, schedule, etc. The System Pressure Test Plan is issued as Volume 3 to the Inservice Inspection Plan.

11548-SPM-XXXXXX PRESSURE TEST VARIOUS NA NA VARIOUS 2 VT-2 Comments PRESSURE TEST PROGRAM. The site ISI Group will be responsible for the development and implementation of the pressure test plan, which will include all the features required, i.e., categories, items, schedule, etc. The System Pressure Test Plan is issued as Volume 3 to the Inservice Inspection Plan.

11548-SPM-XXXXXX PRESSURE TEST VARIOUS NA NA VARIOUS 3 VT-2 Comments PRESSURE TEST PROGRAM. The site ISI Group will be responsible for the development and implementation oftl1e pressure test plan, which will include all the features required, i.e., categories, items, schedule, etc. TI1e System Pressure Test Plan is issued as Volume 3 to the Inservice Inspection Plan.

11548-SPM-XXXXXX PRESSURE TEST VARIOUS NA NA VARIOUS 3 VT-2 Comments PRESSURE TEST PROGRAM. The site ISI Group will be responsible for the development and implementation of the pressure test plan, which will include all the features required, i.e., categories, items, schedule, etc. The System Pressure Test Plan is issued as Volume 3 to the Inservice Inspection Plan.

11548-WMKS-OIOODl H003-1 30"-SHP-101-601 C-C C3.20 CONT.47 Surface Comments PIPING- INTEGRALLY WELDED ATTACHMENT, (H003). Added to plan with Rev. 5 to plan. Added to increase percentage of integral attachments to 10% per NRC SER 95-480 of8-30-95.

11548-WMKS-O 1OOD 1 H003-2 30"-SHP-101-60 I C-C C3.20 CONT.47 Surface Comments PIPING- INTEGRALLY WELDED ATTACHMENT, (H003). Added to plan witl1 Rev. 5 to plan. Added to increase percentage of integral attachments to 10% per NRC SER 95-480 of8-30-95.

Swnmary of Changes Sorted by Drawing and Mark No., SPSU23 Database Page 2of 46 Print Date: 3/11/98

Dra\\ing No. Mark No. Line Number Category Item No, Location Period Method 11548-WMKS-OIOOGI 1-02 14"-WFPD-117-601 C-F-2 C5.51 CONT. 47 UT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Piping replaced by EWR-88-133 and preservice performed by MT/RT. Perform augmented examination each refueling outage. See Augmented Inspection Manual for more information. Replacement Note: Thermal fatigue cracks tend to initiate from geometric discontinuities. The importance of reducing geometric discontinuities during installation should be conveyed to the craft. MT requirement deleted with Rev. 3 to plan.

11548-WMKS-OlOOGI 1-02 14"-WFPD-117-601 C-F-2 C5.51 CONT.47 2 UT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Piping replaced by EWR-88-133 and preservice performed by MT/RT. Perform augmented examination each refueling outage. See Augmented Inspection Manual for more information. Replacement Note: Thermal fatigue cracks tend to initiate from geometric discontinuities. The importance of reducing geometric discontinuities during installation should be conveyed to the craft. Added with Rev. 7 to the plan, to cover the refueling outage scheduled in year 2000 and in period 2.

11548-WMKS-OIOOGI 1-02 14"-WFPD-117-601 C-F-2 C5.51 CONT.47 3 UT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Piping replaced by EWR-88-133 and preservice performed by MT/RT. Perform augmented examination each refueling outage. See Augmented Inspection Manual for more information. Replacement Note: Thermal fatigue cracks tend to initiate from geometric discontinuities. The importance ofreducing geometric discontinuities during installation should be conveyed to the craft. MT requirement deleted with Rev. 3 to plan.

11548-WMKS-OIOOGI 1-02 14"-WFPD-117-601 C-F-2 C5.51 CONT.47 3 UT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Piping replaced by EWR-88-133 and preservice performed by MT/RT. Perform augmented examination each refueling outage. See Augmented Inspection Manual for more information. Replacement Note: Thermal fatigue cracks tend to initiate from geometric discontinuities. The importance of reducing geometric discontinuities during installation should be conveyed to the craft. New with Rev. 5 to plan: Perform RT exam for preservice, if okay, perform UT for preservice (to change from RT to UT) and perform UT and MT examinations for inservice and augmented credit. New with Rev. 7 to the plan: Removed weld from ASME Section XI Plan & changed NOE examinations to UT for augmented examination credit only.

Weld 1-18 on drawing I 1548-WMKS-0102GI will replace this weld for ASME Section XI examination.

11548-WMKS-O I OOG I 1-03 14"-WFPD-117-601 C-F-2 C5.51 2 UT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Piping replaced by EWR-88-133 and preservice performed by MT/RT. Perform augmented examination each refueling outage. See Augmented Inspection Manual for more information. Replacement Note: Thermal fatigue cracks tend to initiate from geometric discontinuities. The importance of reducing geometric discontinuities during installation should be conveyed to the craft. Added with Rev. 7 to the plan, to cover the refueling outage scheduled in year 2000 and in period 2.

11548-WMKS-O 1OOG 1 1-03 14"-WFPD-117-60 I C-F-2 C5.51 CONT.47 3 UT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Piping replaced by EWR-88-133 and preservice perfom1ed by MT/RT. Perform augmented examination each refueling outage. See Augmented Inspection Manual for more information. Replacement Note: Thermal fatigue cracks tend to initiate from geometric discontinuities. The importance of reducing geometric discontinuities during installation should be conveyed to the craft. New with Rev. 5 to plan: Perform RT exam for preservice, if okay, perform UT for preservice (to change from RT to UT) and perform UT and MT examinations for inservice and augmented credit. New with Rev. 7 to the plan: Removed weld from ASME Section XI Plan & changed NOE _examinations to UT for augmented examination credit only. Weld 1-17 on drawing 11548-WMKS-OlOOGI will replace this weld for ASME Section XI examination.

11548-WMKS-O I OOG 1 1-04 14"-WFPD-117-601 C-F-2 C5.51 CONT.47 UT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Piping replaced by EWR-88-133 and preservice performed by MT/RT. Perform augmented examination each refueling outage. See Augmented Inspection Manual for more information. Replacement Note: Thermal fatigue cracks tend to initiate from geometric discontinuities. The importance ofreducing geometric discontinuities during installation should be conveyed to the craft. MT requirement deleted with Rev. 3 to plan.

11548-WMKS-OlOOGI 1-04 14"-WFPD-117-601 C-F-2 C5.51 CONT.47 2 UT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Piping replaced by EWR-88-133 and preservice performed by MT/RT. Perform augmented examination each refueling outage. See Augmented Inspection Manual for more information. Replacement Note: Thermal fatigue cracks tend to initiate from geometric discontinuities. The importance of reducing geometric discontinuities during installation should be conveyed to the craft. Added with Rev. 7 to the plan, to cover the refueling outage scheduled in year 2000 and in period 2.

11548-WMKS-OIOOGI 1-17 14"-WFPD-117-601 C-F-2 C5.51 CONT.47 3 UT/MT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). This weld new to plan with Rev. 7 to the plan. This weld replaces weld 1-03 on drawing 11548-WMKS-O I OOG I.

Sununary of Changes Sorted by Drawing and Mark No., SPSU23 Database Page 3 of 46 Print Date: 3/11198

Drawing No.

Mark No. Line Number Category Item No. Location Period

Method 11548-WMKS-OJOOGJ HOOl-1 14"-WFPD-117-601 C-C C3.20 CONT.47 2 MT Comments Integrally Welded Attachment, (HSS-006). Need thickness in order to update database. Added to plan with Rev. 5 to plan. Added to increase percentage of integral attachments to I 0% per NRC SER 95-480 of8-30-95.

11548-WMKS-OIOOGI HOOl-2 14"-WFPD-117-601 C-C C3.20 CONT.47 2 MT Comments Integrally Welded Attachment, (HSS-006). Need thickness in order to update database. Added to plan with Rev. 5 to plan. Added to increase percentage of integral attachments to l 0% per NRC SER 95-480 of8-30-95.

11548-WMKS-OIOOGI HOOS-I 14"-WFPD-117-601 C-C C3.20 CONT.47 MT Comments PIPING - INTEGRALLY WELDED AITACHMENT, (HOOS). Added to plan with Rev. 5 to plan. Added to increase percentage of integral attaclunents to I 0% per NRC SER 95-480 of 8-30-9 5.

11548-WMKS-O!OOGl H005-2 14"-WFPD-117-601 C-C C3.20 CONT.47 2 MT Comments PIPING- INTEGRALLY WELDED ATTACHMENT, (HOOS). Added to plan with Rev. 5 to plan. Added to increase percentage of integral attachments to 10% per NRC SER 95-480 of8-30-95.

11548-WMKS-O!OlDI 2-SHP-HSS-009 30"-SHP-102-601 TS3.2 TS4.17 CONT.47 0 VT-3 Comments SNUBBER HAHSB. Removed from plan with Rev. 1 to plan, and replaced with 2-HSS-O 13A on drawing l 1548-WMKS-O I 02D I.

11548-WMKS-OIOIGI 1-02 14"-WFPD-113-601 C-F-2 C5.51 CONT.47 2 UT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Piping replaced by EWR-88-133 and preservice performed by MT/RT. Perform augmented examination each refueling outage. See Augmented Inspection Manual for more information. Replacement Note: Thermal fatigue cracks tend to initiate from geometric discontinuities. The importance of reducing geometric discontinuities during installation should be conveyed to the craft. New with Rev. 5 to plan: Perform RT exam for preservice, if okay, perform UT for preservice (to change from RT to UT) and perform UT and MT examinations for inservice and augmented credit. New with Rev. 7 to the plan: Removed weld from ASME Section XI Plan & changed NDE examinations to UT for augmented examination credit only.

Weld 1-11 on drawing l 1548-W:tv!KS-0102Gl will replace this weld for ASME Section XI examination.

11548-WMKS-OlOIGI 1-02 14"-WFPD-113-601 C-F-2 C5.51 2 UT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Piping replaced by EWR-88-133 and preservice performed by MT/RT. Perform augmented examination each refueling outage. See Augmented Inspection Manual for more information. Replacement Note: Thermal fatigue cracks tend to initiate from geometric discontinuities. The importance ofreducing geometric discontinuities during installation should be conveyed to the craft. Added with Rev. 7 to the plan, to cover the refueling outage scheduled in year 2000 and in period 2.

11548-WMKS-OIO!Gl 1-03 14"-WFPD-113-601 C-F-2 C5.51 CONT.47 2 UT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Piping replaced by EWR-88-133 and preservice performed by MT/RT. Perform augmented examination each refueling outage. See Augmented Inspection Manual for more information. Replacement Note: Thermal fatigue cracks tend to initiate from geometric discontinuities. The importance of reducing geometric discontirmities during installation should be conveyed to the craft. New with Rev. 5 to plan: Perform RT exam for preservice, if okay, perform UT for preservice (to change from RT to UT) and perform UT and MT examinations for inservice and augmented credit. New with Rev. 7 to the plan: Removed weld from ASME Section XI Plan & changed NOE examinations to UT for augmented examination credit only.

Weld 1-09 on drawing 11548-WMKS-OIOIGI will replace this weld for ASME Section XI examination.

11548-WMKS-O!OlGl 1-03 14"-WFPD-113-601 C-F-2 C5.51 2 UT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Piping replaced by EWR-88-133 and preservice performed by MT/RT. Perform augmented examination each refueling outage. See Augmented Inspection Manual for more information. Replacement Note: Thermal fatigue cracks tend to initiate from geometric discontinuities. TI1e importance ofreducing geometric discontinuities during installation should be conveyed to the craft. Added with Rev. 7 to the plan, to cover the refueling outage scheduled in year 2000 and in period 2.

11548-WMKS-OlOIGI 1-09 14"-WFPD-113-601 C-F-2 C5.51 CONT.47 2 UT/MT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). This weld new to plan with Rev. 7 to plan. TI1is weld replaces weld 1-03 on drawing 11548-WMKS-O IO 1GI.

11548-WMKS-OlOIGI 1-18 14"-WFPD-113-601 C-F-2 C5.51 CONT.47 2 UT/MT Comments CIRCUl\ffERENTIAL PIPING WELD, (WEPCB). This weld new to plan with Rev. 7 to plan. This weld replaces weld 1-03 on drawing OI 02G I.

Summary of Changes Sorted by Dra\\ing and Mark No., SPSU23 Database Page 4 of 46 Print Date: 3/11/98

Dra'l\ingNo.

Mark No. Line Number Category Item No. Location Period

Method 11548-WMKS-OIOIGI HOOi-i 14"-WFPD-113-601 C-C C3.20 CONT.47 3 Surface Comments PIPING- INTEGRALLY WELDED ATTACHMENT, (HOOIB). Added to plan with Rev. 5 to plan. Added to increase percentage of integral attachments to 10% per NRC SER 95-480 of8-30-95.

11548-WMKS-O IO I GI HOOI-2 14"-WFPD-113-601 C-C C3.20 CONT.47 3 Surface Comments PIPING- INTEGRALLY WELDED ATTACHMENT, (HOOIB). Added to plan with Rev. 5 to plan. Added to increase percentage of integral attachments to 10% per NRC SER 95-480 of8-30-95.

I 1548-WMKS-O 101G 1 HOOl-3 14"-WFPD-113-601 C-C C3.20 CONT. 47 3 Surface Comments PIPING- INTEGRALLY WELDED ATTACHMENT, (HOOIB). Added to plan with Rev. 5 to plan. Added to increase percentage of integral attachments to 10% per NRC SER 95-480 of8-30-95.

11548-WMKS-OIOIGI HOOl-4 14"-WFPD-113-601 C-C C3.20 CONT. 47 3 Surface Comments PIPING- INTEGRALLY WELDED ATTACHMENT, (HOOIB). Added to plan with Rev. 5 to plan. Added to increase percentage of integral attachments to 10% per NRC SER 95-480 of8-30-95.

11548-WMKS-O 102D I 2-SHP-HSS-013A 30"-SHP-103-60 I TS3.2 TS4.17 CONT.47 2 VT-3 Comments SNUBBER HAHSB. Added to plan with Rev. 1 to plan, as a replacement for 2-SHP-HSS-009 on 11548-WMKS-O 10 ID I.

11548-WMKS-O 102D I H002-1 30"-SHP-103-601 C-C C3.20 CONT.47 2 Surface Comments PIPING-INTEGRALLY WELDED ATTACHMENT, (HSS-013A). Added to plan with Rev. I to plan to replace 1-1009-1 on l 1548-WMKS-0122Al.

11548-WMKS-0102Dl H002-2 30"-SHP-103-601 C-C C3.20 CONT.47 2 Surface Comments PIPING - INTEGRALLY WELDED ATTACHMENT, (HSS-013A). Added to plan with Rev. 5 to plan. Added to increase percentage of integral attachments to I 0% per NRC SER 95-480 of 8-30-95.

11548-WMKS-O I 02G I 1-02 14"-WFPD-109-601 C-F-2 C5.5I CONT.47 2 UT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Perform augmented examination each refueling outage. See Augmented Inspection Manual for more information. Replacement Note: TI1crmal fatigue cracks tend to initiate from geometric discontinuities. The importance of reducing geometric discontinuities during installation should be conveyed to the craft. Added with Rev. 7 to the plan, to cover the refueling outage scheduled in year 2000 and in period 2.

11548-WMKS-O I 02G I 1-03 14"-WFPD-109-601 C-F-2 C5.51 CONT.47 UT/MT Conuueuts CIRCUMFERENTIAL PIPING WELD WEPCB. Piping replaced by EWR-88-133 and preservice performed by MT/RT. Perform augmented examination each refueling outage. See Augmented Inspection Manual for more information. Replacement Note: Thermal fatigue cracks tend to initiate from geometric discontinuities. TI1e importance ofreducing geometric discontinuities during installation should be conveyed to the craft.

I 1548-WMKS-O I 02G 1 1-03 14"-WFPD-l 09-601 C-F-2 CS.51 CONT.47 UT Comments CIRCUMFERENTIAL PIPING WELD WEPCB. Piping replaced by EWR-88-133 and preservice performed by MT/RT. Perform augmented examination each refueling outage. See Augmented Inspection Manual for more information. Replacement Note: Thermal fatigue cracks tend to initiate from geometric discontinuities. The importance ofreducing geometric discontinuities during installation should be conveyed to the craft. New with Rev. 5 to plan: Perform RT exam for preservice, if okay, perform UT for preservice (to change from RT to UT) and perfom1 UT and MT examinations for inservice and augmented credit. New with Rev. 7 to the Plan: Removed weld from ASME Section XI Plan and changed NDE examinations to UT for augmented exall)ination credit only. Weld 1-18 on drawing 11548-WMKS-OIO!Gl will replace this weld for ASME Section XI examination.

l 1548-WMKS-0102Gl 1-03 14"-WFPD-109-601 C-F-2 C5.51 2 UT Comments CIRCUMFERENTIAL PIPING WELD WEPCB. Piping replaced by EWR-88-133 and preservice performed by MT/RT. Perform augmented examination each refueling outage. See Augmented Inspection Manual for more information. Replacement Note: Thermal fatigue cracks tend to initiate from geometric discontinuities. TI1e importance ofreducing geometric discontinuities during installation should be conveyed to the craft. Added with Rev. 7 to the plan, to cover the refueling outage scheduled in year 2000 and in period 2.

Summary of Changes Sorted by Dra'l\ing and Mark No., SPSU23 Database Page 5 of 46 Print Date: 3/11198

Draning No.

Mark No. Line Number Category Item No. Location Period

Method I IS48-WMKS-0102Gl 1-04 14"-WFPD-109-601 C-F-2 CS.SI CONT.47 2 UT Comments CIRCUMFERENTIAL PIPING WELD WEPCB. Piping replaced by EWR-88-133 and preservice performed by MT/RT. Perform augmented examination each refueling outage. See Augmented Inspection Manual for more information. Replacement Note: Them1al fatigue cracks tend to initiate from geometric discontinuities. The importance of reducing geometric discontinuities during installation should be conveyed to the craft. Added with Rev. 7 to the plan, to cover the refueling outage scheduled in year 2000 and in period 2.

I I S48-WMKS-O I 02G I 1-11 14"-WFPD-109-601 C-F-2 CS.SI CONT.47 2 UT/MT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). This weld new to plan with Rev. 7 to plan. This weld replaces weld 1-02 on drawing I l S48-WMKS-O IO I GI.

I 1548-WMKS-0!02Gl 1-18 14"-WFPD-109-601 C-F-2 CS.SI CONT. 18 3 UT/MT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). This weld new to plan with Rev. 7 to plan. This weld replaces weld 1-02 on drawing 01 OOGI.

I I 548-WMKS-O I 02G I HOOi-i 14"-WFPD-109-601 C-C C3.20 CONT.47 2 Surface Comments Piping - Integrally Welded Attachment, (HOO I A). Need thickness in order to update database. Added to plan with Rev. S to plan. Added to increase percentage of integral attachments to I 0% per NRC SER 95-480 of8-30-95. .

I 1548-WMKS-0!02GI HOOl-2 14"-WFPD-109-601 C-C C3.20 CONT. 47 2 Surface Comments Piping - Integrally Welded Attachment, (HOO 1A). Need thickness in order to update database. Added to plan with Rev. S to plan. Added to increase percentage of integral attachments to 10% per NRC SER 95-480 of8-30-95.

11548-WMKS-O I 02G 1 HOOl-3 14"-WFPD-109-601 C-C C3.20 CONT.47 2 Surface Comments Piping - Integrally Welded Attachment, (HOO I A). Need thickness in order to update database. Added to plan with Rev. 5 to plan. Added to increase percentage of integral attachments to I 0% per NRC SER 95-480 of8-30-95.

I 1548-WMKS-0102GI HOOI-4 14"-WFPD-109-601 C-C C3.20 CONT.47 2 Surface Comments Piping - Integrally Welded Attachment, (HOO l A). Need thickness in order to update database. Added to plan with Rev. S to plan. Added to increase percentage of integral attachments to l 0% per NRC SER 95-480 of8-30-95.

l I 548-WMKS-O l 03 A2- l 1-14 30"-SHP-101-601 C-F-2 CS.Si MSVH 0 UT/MT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Perform augmented examination in accordance with TS 4.15 and Augmented Inspection Manual. Period switched from "l" to "2" with Rev. 3 to plan because this weld was also scheduled in I-2, P-3. Weld l-16BC on the same drawing has been scheduled in period I in this weld's place. Per discussion with Dan Jensen (TAD to Surry for the 1996 refueling outage) this weld does not exist, therefore, it has been removed from the plan effective with Rev. 7 to the plan.

I 1548-WMKS-0103A2-l 1-15 30"-SHP-101-601 C-F-2 CS.SI MSVH 2 UT/MT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). This weld added to plan with Rev. 7 to the plan to replace weld 1-14, for which, it has been determined, does not exist. Perform augmented examination in accordance with TS 4. I 5 and Augmented Inspection Manual.

l 1548-WMKS-0103A2-l l-16BC 30"-SHP-122-601 C-F-2 CS.81 MSVH UT/MT Conunents Pipe Branch Connection > 2 irL NPS, Circumferential Weld. Perform augmented examination in accordance with TS 4. I 5 and Augmented Inspection Manual. Also perform ASME XI examination.

Period switched from "2" to "l" with Rev. 3 to plan, and put weld 1-14 in period 2 to take the place of this weld because weld 1-14 was scheduled in I-2, P-3.

l 1548-WMKS-0103A2-l I-39L 30"-SHP-101-601 C-F-2 CS.52 MSVH 2 UT/MT Comments LONGITUDINAL PIPING WELD, (WEPSEM). New with Rev. 7to the plan: This weld added to the plan to replace weld I-42L on the same line & drawing. Per Relief Request SR-012 & Code Case N-524, the examination area includes only that length of the longitudinal weld (weld l-39L) within the circumferential weld examination volume of welds 1-1 S & 1-30. Exan1ination requirements must be met for both transverse & parallel flaws in the examination area of the longitudinal weld. TS 4.15 added due to weld selection criteria changed to the I 989 Code Summary of Changes Sorted by Drawing and Mark No., SPSU23 Database Page 6 of 46 Print Date: 3/11/98

Drawing No.

MarkNo. Line Number Category Item No. Location Period

Method l 1548-WMKS-0103A2-l l-42L 30"-SHP-101-601 C-F-2 C5.52 MSVH 0 UT/MT Comments LONGITUDINAL PIPING WELD, (WEPSEM). Per Relief Request SR-0 I 2 & Code Case N-524, The examination area includes only that length of the longitudinal weld (Weld l-42L) within the circumferential weld examination volume of welds 1-14 & 1-15. Examination requirements must be met for both transverse & parallel flaws in the examination area of the longitudinal weld. New with Rev. 5 to plan: MT exam performed on 2-13-95 with NRI & 100% coverage. UT examination performed on 2-8-95 with an interval 2 procedure, which does not meet interval 3 requirements.

Therefore, the UT examination must be perfom1ed during the I 996 refueling outage with an interval 3 procedure. New with Rev. 7 to plan: Per discussions with Dan Jensen (TAD to Surry for 1996 refueling outage) this weld and weld 1-14 do not exist, therefore, this weld is removed from the plan & is replaced with weld I-39L on the same line & drawing No.

I 1548-WMKS-0103A2-1 2-02 6"-SHP-145-60 l C-F-2 C5.51 MSVH 3 UT/MT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). New with Rev. 7: TS 4.15 requirement added due to weld selection criteria changed to the 1989 Code.

11548-WMKS-0103A2-2 1-10 30"-SHP-l 02-601 C-F-2 C5.51 MSVH 0 UT/MT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Perform augmented examination in accordance with TS 4. I 5 and Augmented Inspection Manual. New with Rev. 7 to the plan: If this weld (1-10) does not exist as shown on drawing l 1548-WMKS-0103A2-2 then examine weld 1-11 on the same line & drawing as weld 1-10. Per Rev. 5 to drawing, this weld is deleted from the drawing, and deleted from the plan with Rev. 9 to the plan.

11548-WMKS-0103A2-2 1-11 30"-SHP-102-601 C-F-2 C5.51 MSVH 2 UT/MT Conunents CIRCUMFERENTIAL PIPING WELD, (WEPCB). Perform augmented examination in accordance with TS 4.15 and Augmented Inspection Manual. New with Rev. 7 to the plan: This weld (l-11) requires examination only if weld 1-10 is found not to exist as shown on drawing 11548-WMKS-O 103A2-2. That is, it must be determined if weld 1-10 does exist before performing examinations on this weld.

11548-WMKS-0103A2-2 1-26 30"-SHP-102-601 C-F-2 CS.51 MSVH 2 UT/MT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). New with Rev. 7 to the plan: Weld added to TS 4.15 due to weld selection criteria being changed to the 1989 Code.

l 1548-WMKS-0103A2-2 2-02 6"-SHP-146-601 C-F-2 CS.51 MSVH 3 UT/MT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). New with Rev. 7 to plan: TS 4.15 added due to weld selection being changed to the 1989 Code.

l 1548-WMKS-0103A2-2 2-17 6"-SHP-146-60 l NA NA MSVH 2 UT/MT Conunents CIRCUMFERENTIAL PIPING WELD, (WEPCB). Added weld to TS 4.15 with Rev. 7 to the plan because weld selection criteria changed to the 1989 Code.

11548-WMKS-0103A2-3 1-12 30"-SHP-103-601 C-F-2 C5.51 MSVH 0 UT/MT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Perform augmented examination in accordance with TS 4.15 and Augmented Inspection Manual. New with Rev. 7 to the plan: If this weld (1-12) does not exist as shown on drawing I 1548-WMKS-0103A2-3 then examine weld 1-13 on the same line & drawing as weld 1-12. Per Rev. 5 to drawing, this weld is deleted from the drawing, and deleted from the plan with Rev. 9 to the plan.

11548-WMKS-0103A2-3 1-13 30"-SHP-l 03-601 C-F-2 CS.SI MSVH 3 UT/MT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Perform augmented examination in accordance with TS 4.15 and Augmented Inspection Manual. New with Rev. 7 to the plan: This weld (1-13) requires examination only if weld 1-12 is found not to exist as shown on drawing I 1548-WMKS-0103A2-3. That is, it must be determined that weld 1-12 does exist before performing examinations on this weld. Weld 12 determined not to exist and was deleted from the plan with Rev. 9 to the plan. This is done JAW Rev. 5 to the drawing.

l 1548-WMKS-0103A2-3 2-16 6"-SHP-147-601 NA NA MSVH 3 UT/MT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Weld added to TS 4.15 with Rev. 7 to the plan because weld selection criteria changed to 1989 Code.

l 1548-WMKS-0103A2-3 2-17 6"-SHP-147-60 l NA NA MSVH 3 UT/MT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Weld added to TS 4.15 with Rev. 7 to the plan because weld selection criteria changed to 1989 Code.

Summary of Changes Sorted by Drawing and Mark No., SPSU23 Database Page 7of 46 Print Date: 3/11/98

Drawing No.

Mark No. Line Number Category

Item No. Location Period

Method l 1548-WMKS-0112AA1 H032D-1 18"-CC-15-121 D-A Dl.40 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD,(H032D-B). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1548-WMKS-Ol 12AA1 . H032D-2 18"-CC-15-121 D-A Dl.40 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD,(H032D-B). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-Ol 12AA! H032D-3 18"-CC-15-121 D-A Dl.40 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD,(H032D-B). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attaclunents.

11548-WMKS-Ol 12AA! H032D-4 18"-CC-15-121 D-A Dl.40 CONT.-3 0 VT-3 Comments INTEGRALLY ATTACHED WELD,(H03 2D-B). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-Ol 12AA1 H034-I 18"-CC-15-121 D-A Dl.20 CONT. -27 VT-3 Comments INTEGRALLY ATTACHED WELD, (H034). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

I 1548-WMKS-Ol 12AAI H034-2 18"-CC-15-121 D-A Dl.20 CONT. -27 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H034). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

I 1548-WMKS-O! 12ABI H0!8-I !8"-CC-9-121 D-A Dl.40 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO 18). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

I 1548-Wl'v!KS-OI 12AB1 H018-2 18"-CC-9-121 D-A DI.40 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO 18). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1548-WMKS-0112AB1 H018-3 18"-CC-9-121 D-A Dl.40 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO 18). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Conunitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

I 1548-WMKS-0112AB1 H019-1 18"-CC-9-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO 19). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Conunitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1548-WMKS-0112AB! H019-2 18"-CC-9-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO 19). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

I 1548-WMKS-OI 12AB1 H019-3 18"-CC-9-121 D-A Dl.20 CONT. -3 0 VT-3 Conuuents INTEGRALLY ATTACHED WELD, (HO 19). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attaclunents.

Summary of Changes Sorted by Dra~ing and Mark No., SPSU23 Database Page 8of 46 Print Date: 3/11/98

Dra~ing No. Mark No. Line Nmnber Category Item No. Location Period Method 11548-WMKS-0112ABI HOl9-4 18"-CC-9-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO 19). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0112ABI H022-1 18"-CC-9-121 D-A Dl.20 CONT.-3 2 VT-3 Comments INTEGRALLY ATTACHED WELD, (H022). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0112ABI H022-2 18"-CC-9-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H022). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-01 !2ABI H025A-1 18"-CC-9-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H025A). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-\VMKS-O l 12ABI H025A-2 18"-CC-9-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H025 A). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0112ABI H025A-3 18"-CC-9-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H025A). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0112ABI H025A-4 18"-CC-9-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H025A). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0112ABI H025A-5 18"-CC-9-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H025A). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-O l 12AB I H025A-6 18"-CC-9-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H025 A). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0112ABI H025A-7 18"-CC-9-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H025A). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0112ABI H025A-8 18"-CC-9-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H025A). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0112ABI H025C-1 18"-CC-9-121 D-A Dl.40 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H025C). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

T11e corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

Summary of Changes Sorted by Dra~ing and Mark No., SPSU23 Database Page 9of 46 Print Date: 3/11/98

Drawing No. Mark No. LineNwnber Category Item No. Location Period Method 11548-WMKS-01 I 2S 1 H026-l !8"-CC-7-121 D-A Dl.40 CONT.-3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H026). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-Ol 12Sl H026-2 18"-CC-7-121 D-A Dl.40 CONT.-3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H026). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-01 !2S! H026-3 18"-CC-7-121 D-A Dl.40 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H026). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0112Sl H026-4 18"-CC-7-121 D-A Dl.40 CONT.-3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H026). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The ,

corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-01!2Sl H026-5 18"-CC-7-121 D-A Dl.40 CONT.-3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H026). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-O 112S 1 H026-6 18"-CC-7-121 D-A Dl.40 CONT.-3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H026). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0 ll 2S 1 H027-2-l 18"-CC-7-121 D-A Dl.20 CONT. -3 VT-3 Comments INTEGRALLY ATTACHED WELD, (H027-2). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0112S 1 H027-2-2 18"-CC-7-I21 D-A Dl.20 CONT.-3 VT-3 Comments INTEGRALLY ATTACHED WELD, (H027-2). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

l11e corporate database was changed to agree 'With the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-01 !2Sl H029-1 18"-CC-7-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H029). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-Ol 12Sl H029-2 18"-CC-7-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H029). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1548-WMKS-Ol 12Sl H044-l 18"-CC-7-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H044). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-O 112S 1 H044-2 18"-CC-7-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H044). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

Swnmary of Changes Sorted by Dra\\ing and Mark No., SPSU23 Database Page JO of 46 Print Date: 3/11/98

Drawing No. Mark No. Line Number Category Item No. Location Period Method l 1548-WMKS-Ol l2Sl H044-3 18"-CC-7-121 D-A Dl.20 CONT. -3 0 Vf-3 Comments INTEGRALLY ATTACHED WELD, (H044). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1548-WMKS-Ol 12SI H044-4 18"-CC-7-121 D-A Dl.20 CONT. -3 0 Vf-3 Comments INTEGRALLY ATTACHED WELD, (H044). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1548-WMKS-Ol 12SI H044-5 18"-CC-7-121 D-A Dl.20 CONT. -3 0 Vf-3 Comments INTEGRALLY ATTACHED WELD, (H044). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1548-WMKS-Ol 12Sl H044A-1 18"-CC-7-121 D-A Dl.40 CONT. -3 0 Vf-3 Comments INTEGRALLY ATTACHED WELD, (H044A). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

TI1e corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0112SI H044B-1 18"-CC-7-121 D-A Dl.40 CONT. -3 0 Vf-3 Comments INTEGRALLY ATTACHED WELD, (H044B). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0112Sl H044B-2 18"-CC-7-121 D-A Dl.40 CONT. -3 0 Vf-3 Comments INTEGRALLY ATTACHED WELD, (H044B). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1548-WMKS-0112SI H044B-3 18"-CC-7-121 D-A Dl.40 CONT.-3 0 Vf-3 Comments INTEGRALLY ATTACHED WELD, (H044B). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0112Sl H044B-4 !8"-CC-7-121 D-A Dl.40 CONT. -3 0 Vf-3 Comments INTEGRALLY ATTACHED WELD, (H044B). Category verified & Item No. changed with Rev. 7 to Pl~n to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0112S2 HOOIB-1 18"-CC-14-121 D-A Dl.20 CONT. -3 0 Vf-3 Comments INTEGRALLY ATTACHED WELD, (HOO lB). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

! !548-WMKS-0112S2 HOOIB-2 18"-CC-14-121 D-A Dl.20 CONT. -3 0 Vf-3 Comments INTEGRALLY ATTACHED WELD, (HOO I B). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

115 48-WMKS-O l l 2S2 HOOIB-3 18"-CC-14-121 D-A Dl.20 CONT. -3 0 Vf-3 Comments INTEGRALLY ATTACHED WELD, (HOO I B). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0112S2 HOOIB-4 18"-CC-14-121 D-A Dl.20 CONT. -3 0 Vf-3 Comments INTEGRALLY ATTACHED WELD, (HOO lB). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

Summary of Changes Sorted by Dra\\ing and Mark No., SPSU23 Database Page 11 of 46 Print Date: 3111198

Drawing No. Mark No. Line Number Category Item No. Location Period Method l 1548-WMK8-0l 1282 HOOlB-5 18"-CC-14-121 D-A Dl.20 CONT.-3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HOO lB). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l l548-WMKS-Ol l2S2 HOOIB-6 18"-CC-14-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HOO lB). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

I I 548-WMKS-O 11282 HOOIB-7 18"-CC-14-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HOO l B). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1548-WMK8-0l 1282 HOOlB-8 18"-CC-14-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HOO lB). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1548-WMKS-Ol 12S2 HOI0-1 18"-CC-14-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO l 0). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1548-WMKS-011282 HOI0-2 18"-CC-14-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO 10). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l I548-WMK8-0l 12S2 HOl0-3 18"-CC-14-121 D-A Dl.20 CONT.-3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO l 0). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1548-WMKS-Ol 12S2 HOl0-4 18"-CC-14-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO 10). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1548-WMKS-Ol 12S2 HOl0-5 18"-CC-14-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO 10). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1548-WMKS-011282 HOl0-6 18"-CC-14-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO 10). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

I 1548-WMK8-0l 1282 HOl0-7 18"-CC-14-121 D-A Dl.20 CONT.-3 0 VT-3 Comments INTEGRALLY ATT ACHED WELD, (HO 10). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

I 1548-WMK8-0l 1282 HOI0-8 l 8"-CC-14-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HOlO). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attaclunents.

Swnmary of Changes Sorted by Drawing and Mark No., SPSU23 Database Page 12 of 46 Print Date: 3/11/98

Dra"ing No. Mark No. Line Number Category Item No. Location Period Method 11548-WMKS-0112S2 HOI0-9 18"-CC-14-121 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO I 0). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-07 4 applies & the only changes made were to Class 3 integral attachments.

I 1548-WMKS-O I 17B I HOOi-i 10"-RH-l 16-1502 C-C C3.20 CONT. -27 3 PT Comments PIPING- INTEGRALLY WELDED ATTACHMENT, (HOOi). Added to the plan with Rev. l to the plan to replace H007-l on ll548-WMKS-Oll7Bl.

11548-WMKS-OI 17BI HOOl-2 10"-RH-116-1502 C-C C3.20 CONT. -27 3 PT Comments PIPING- INTEGRALLY WELDED ATTACHMENT, (HOOi). Added to the plan with Rev. l to the plan to replace H007-2 on ll548-WMKS-Oll7Bl.

ll548-WMKS-Oll7Bl HOOl-3 10"-RH-l 16-1502 C-C C3.20 CONT.-27 3 PT Conunents PIPING- INTEGRALLY WELDED ATTACHMENT, (HOOi). Added to the plan with Rev. I to the plan to replace H007-3 on I 1548-Wlv[KS-0117Bl.

l 1548-WMKS-Ol l 7Bl H007-l 10"-RH-116-1502 C-C C3.20 CONT. -27 0 PT Comments PIPING- INTEGRALLY WELDED ATTACHMENTS, (HSS-101). Reference memo Woodyard to Rogers of6-13 changed thickness to 0.534". Removed from plan with Rev. I to plan.

1 !548-WMKS-0117Bl H007-2 10"-RH-116-1502 C-C C3.20 CONT. -27 0 PT Conunents PIPING - INTEGRALLY WELDED ATIACHMENTS, (HSS-10 I). Reference memo Woodyard to Rogers of 6-13 changed thickness to 0.534". Removed from plan with Rev. I to plan.

l 1548-WMKS-Ol 17Bl H007-3 10"-RH-116-1502 C-C C3.20 CONT. -27 0 PT Comments PIPING - INTEGRALLY WELDED ATIACHMENTS, (HSS-10 l). Reference memo Woodyard to Rogers of 6-13 changed thickness to 0.534". Removed from plan with Rev. I to plan.

11548-WMKS-0117Bl H009-I 10"-RH-l 17-1502 B-K BI0.20 CONT. -27 2 PT Comments PIPING- INTEGRALLY WELDED ATTACHMENT, (H009B). Added to plan with Rev. 5 to plan. Added to increase percentage of integral attachments to 10% per NRC SER 95-480 of 8-30-95.

l 1548-WMKS-0117Bl H009-2 10"-RH-117-1502 B-K BI0.20 CONT. -27 2 PT Comments PIPING- INTEGRALLY WELDED ATTACHMENT, (H009B). Added to plan with Rev. 5 to plan. Added to increase percentage of integral attachments to 10% per NRC SER 95-480 of8-30-95.

l 1548-WMKS-Ol 18Gl-l HOOl-1 6"-WAPD-102-601 D-B D2.40 MSVH 0 VT-3 Conunents INTEGRALLY ATTACHED WELD, (HOO!). Category & Item No. changed with Rev. 7to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-OI 18Gl-l H002-l 6"-WAPD-102-601 D-B D2.40 MSVH 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H002). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0118Gl-l H003-l 6"-WAPD-104-601 D-B D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H003). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. 111e corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0118GI-I H003-2 6"-WAPD-104-601 D-B D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATIACHED WELD, (H003). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

Sununary of Changes Sorted by Dra\\ing and Mark No., SPSU23 Database Page 13 of 46 Print Date: 3/JJ/98

Draning No. Mark No. Line Number Category Item No. Location Period Method 11548-WMKS-O 11802 HOOi-i 6"-WAPD-101-601 D-B D2.40 MSVH 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HOOi). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-Ol 1802 HOOS-I 6"-WAPD-50-601 D-B D2.20 MSVH VT-3 Comments INTEGRALLY ATTACHED WELD, (HOOS). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0118G2 HOOS-2 6"-WAPD-50-601 D-8 D2.20 lvfSVH VT-3 Comments INTEGRALLY ATTACHED WELD, (HOOS). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0118Ll H004-l 6"-WCMU-108-lSl D-B D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H004). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0118Ll H004-2 6"-WCMU-108-lSI D-B D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H004). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0118Ll H004-3 6"-WCMU-108-IS l D-B D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATT ACHED WELD, (H004). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-O l l 8Ll H004-4 6"-WCMU-108-ISI D-B D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H004). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0! 18LI H004-S 6"-WCMU-108-lSl D-B D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H004). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-O l l 8Ll H004-6 6"-WCMU-108-IS l D-B D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATIACHED WELD, (H004). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

I 1548-WMKS-Ol 18Ll H004-7 6"-WCMU-108-!Sl D-B D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATI ACHED WELD, (H004). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1548-WMKS-Ol 18Ll H004-8 6"-WCMU-108-lS l D-B D2.20 MSVH 0 VT-3 Conunents INTEGRALLY ATI ACHED WELD, (H004). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-Wl\-lKS-O l l 8Ll H006-l 8"-WCMU-lOS-lSl D-B D2.20 MSVH 0 VT-3 Conunents INTEGRALLY ATTACHED WELD, (H006). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

Summary of Changes Sorted by Dra'l\ing and Mark No., SPSU23 Database Page 14 of 46 Print Date: 3/11198

Drawing No. Mark No. Line Number Category Item No. Location Period Method 11548-WMKS-O l l 8Ll I-!006-2 8"-WCMU-105-151 D-8 D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H006). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-O 118Ll I-!012-1 6"-WCMU-107-151 D-8 D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HOI2). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0118Ll I-!012-2 6"-WCMU-107-151 D-8 D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO 12). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96~074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-O ll 8Ll HOl 7-1 6"-WCMU-106-151 D-8 D2.20 MSVH 2 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO 17). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-W.MKS-Ol 18Ll I-!017-2 6"-WCMU-106-151 D-8 D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO 17). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0118Ll I-!033-1 6"-WCMU-106-151 D-8 D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H033). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-O 118Ll HOC22-1 8"-WCMU-105-151 D-8 D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HOC22). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressf.!re test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-O 1 l 8Ll HOC28-l 6"-WCMU-107-151 D-8 D2.20 MSVH 3 VT-3 Comments INTEGRALLY ATTACHED WELD, (HOC28). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-W.MKS-0119Al HOOi-i 24"-WS-126-10 D-B D2.20 CONT.-27 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HOO I). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-Ol 19Al H002-l 24"-WS-126-10 D-8 D2.40 CONT. -27 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H002B). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0119Al I-!002-2 24"-WS-126-10 D-8 D2.40 CONT. -27 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H0028). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0119Al I-!002-3 24"-WS-126-10 D-8 D2.40 CONT. -27 0 VT-3 Conunents INTEGRALLY ATTACHED WELD, (H0028). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

Summary of Changes Sorted by Drm,ing and Mark No., SPSU23 Database Page 15 of 46 Print Date: 3/J 1/98

Dra\\ing No. Mark No. Line Number Category Item No. Location Period Method 11548-WMKS-0119Al H002-4 24"-WS-126-10 D-B D2.40 CONT.-27 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H002B). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0119A2 H002-l 24"-WS-128-10 D-B D2.40 CONT.-27 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H002B). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0119A2 H002-2 24"-WS-128-10 D-B D2.40 CONT.-27 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H002B). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

I I 548-WMKS-O l l 9A2 H002-3 24"-WS-128-10 D-B D2.40 CONT.-27 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H002B). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-Ol 19A2 H002-4 24"-WS-128-10 D-B D2.40 CONT.-27 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H002B). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

1 1548-WMKS-O 119 A3 H002-1 24"-WS-130-10 D-B D2.40 CONT. -27 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H002B). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-O 119A3 H002-2 24"-WS-130-10 D-B D2.40 CONT.-27 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H002B). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-Ol 19A3 H002-3 24"-WS-130-10 D-B D2.40 CONT.-27 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H002B). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-Ol 19A3 H002-4 24"-WS-130-10 D-B D2.40 CONT.-27 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H002B). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0119A4 H002-l 24"-WS-132-10 D-B D2.40 CONT.-27 3 VT-3 Comments INTEGRALLY ATTACHED WELD, (H002B). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0119A4 H002-2 24"-WS-132-10 D-B D2.40 CONT.-27 3 VT-3 Conunents INTEGRALLY ATTACHED WELD, (H002B). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-Ol 19A4 H002-3 24"-\VS-132-10 D-B D2.40 CONT.-27 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H002B). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

Summary of Changes Sorted by Dra\ling and Mark No., SPSU23 Database Page 16 of 46 Prine Date: 3/11/98

Drawing No. Mark No. Line Number Category Item No. Location Period Method 11548-WMKS-0119A4 H002-4 24"-WS-132-10 D-B D2.40 CONT. -27 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H0028). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-0122Al H007-l 12"-SI-247-1502 8-K 810.20 CONT. -27 3 PT Comments PIPING - INTEGRALLY WELDED ATTACHMENT, (H0078). Added to plan with Rev. 5 to plan. Added to increase percentage of integral attachments to l 0% per NRC SER 95-480 of 8-30-95.

11548-WMKS-0122Al H007-2 12"-Sl-247-1502 B-K 810.20 CONT. -27 3 PT Conunents PIPING - INTEGRALLY WELDED ATTACHMENT, (H0078). Added to plan with Rev. 5 to plan. Added to increase percentage of integral attachments to I 0% per NRC SER.95-480 of 8-30-95.

l 1548-WMKS-0!22Al H009-l 12"-Sl-247-1502 C-C C3.20 CONT. -27 0 PT Comments PIPING- INTEGRALLY WELDED ATTACHMENT, (H009). Reference memo Woodyard to Rogers of6-13 changed thickness to 0.378". Removed from plan with Rev. I to plan. H002-l on drawing 11548-WMKS-O I 02D I added to plan as a replacement.

11548-WMKS-0!22Dl H006-l 12"-Sl-246-1502 8-K 810.20 CONT. -27 2 PT Comments PIPING - INTEGRALLY WELDED ATTACHMENT (H0068). Added to plan with Rev. 5 to plan to replace integrally welded attachment H007 on drawing 11548-WMKS-O l 22Ll.

11548-WMKS-0122Dl H006-2 12"-Sl-246-1502 8-K. BI0.20 CONT. -27 2 PT Conunents PIPING - INTEGRALLY WELDED ATTACHMENT (H0068). Added to plan with Rev. 5 to plan to replace integrally welded attachment H007 on drawing 11548-WMKS-O 122Ll.

l 1548-WMKS-0122Dl H006-3 12"-SI-246-1502 B-K Bl0.20 CONT.-27 2 PT Comments PIPING - INTEGRALLY WELDED ATTACHMENT (H006B). Added to plan with Rev. 5 to plan to replace integrally welded attachment H007 on drawing 11548-WMKS-O l 22Ll.

l 1548-WMKS-0122Dl H006-4 12"-SI-246-1502 B-K Bl0.20 CONT.-27 2 PT Comments PIPING - INTEGRALLY WELDED ATTACHMENT (H006B). Added to plan with Rev. 5 to plan to replace integrally welded attachment H007 on drawing 11548-WMKS-O 122Ll.

l 1548-WMKS-0122Jl 2-09 6"-SI-250-1502 C-F-1 C5.ll CONT. -27 3 UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPC8). TS Item 2.1.2. Examine a minimum of2.5% of the welds every refueling outage with all complete by the end of the interval. Year changed to 2003 with Rev. 8 to the plan to ensure that 2.5% of the welds are examined every refueling outage.

l 1548-WMKS-0122Kl-l 2-20 6"-Sl-248-1502 C-F-1 CS.II CONT. -27 3 UT/PT Comments Circumferential Piping Weld, (WEPC8). TS Item 2.1.2. Examine a minimum of2.5% of the welds every refueling outage with all complete by the end of the interval. Year changed to 2003 with Rev.

8 to the plan to ensure that 2.5% of the welds are examined every refueling outage.

l 1548-WMKS-0!22Ll 1-05 l 2"-RC-322-1502 B-J B9.ll ALOOP UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Terminal End. PT exam completed on 2-15-95 with 100% coverage & NRI. Perform UT examination during the 1996 refueling outage in order to complete the period requirements.

11548-Wl\IKS-0122Ll H007-l 12"-Sl-245-1502 8-K Bl0.20 CONT. -27 0 PT Comments PIPING - INTEGRALLY WELDED ATTACHMENT, (H007). Removed from plan because attachment is partially inaccessible. Replaced with attachment H006 on drawing 11548-WMKS-O 122D l.

Reference memo Dalton to McNeill of3-15-95 (FAX date).

11548-WMKS-0122Ll H007-2 l 2"-Sl-245-1502 B-K Bl0.20 CONT.-27 0 PT Comments PIPING - INTEGRALLY WELDED ATTACHMENT, (H007). Removed from plan because attachment is partially inaccessible. Replaced with attachment H006 on drawing 11548-WMKS-O l 22D I.

Reference memo Dalton to McNeil! of3-15-95 (FAX date).

Sununary of Changes Sorted by Dral\ing and Mark No., SPSU23 Database Page 17 of 46 Print Date: 3111198

Drawing No. Mark No. Line Number Category Item No. Location Period Method l 1548-WMKS-0123C2 2-32 8"-CS-134-153 NA NA CONT. -3 3 UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). TS Item 2.1.2. Examine a minimum of 2.5% of the welds every refueling outage with all complete by the end of the interval. Year changed to 2003 with Rev. 8 to the plan to ensure that 2.5% of the welds are examined every refueling outage.

l 1548-WMKS-0123Kl 2-CS-H002 8"-CS-133-153 F-A Fl.40 SAFEGUARDS VT-3 Comments SUPPORT HAVARI. This support placed in period l with Rev. 3 to plan. Support 11548-WMKS-RC-IOZl RC-H002 placed in period 2 to take the place of this support.

l 1548-WMKS-0123Ll 0-02 12"-CS-102-153 C-F-1 CS.II SAFEGUARDS UT/PT Conunents CIRCUMFERENTIAL PIPING WELD, (WEPCB). ADDED TO PLAN 1N REV. 5 TO REPLACE WELD 0-04 ON l 1548-WMKS-OI23Ml DUE TO PARTIAL EXAM ON WELD 0-04 DURING THE 1995 REFUELING OUTAGE.

11548-WMKS-0123LZI 0-02 12"-CS-102-153 C-F-1 C5.ll YARD UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). WELD ADDED TO PLAN WITH REV. 5 TO PLAN TO REPLACE WELD 0-05 ON 11548-WMKS-O 123M!. WELD 0-05 WAS A PARTIAL EXAMINATION IN 1995. ANEW WELD WAS SUBSTITUTED IN LIEU OF ASKING RELIEF.

l 1548-WMKS-0123Ml 0-01 12"-CS-101-153 C-F-1 C5.l 1 SAFEGUARDS 2 UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Period changed from "l" to "2" with Rev. 3 to plan, because weld was also scheduled in I-2, P-3. Weld 0-04 on same line & drawing No. is replacement for this weld.

l 1548-WMKS-0123Ml 0-02 12"-CS-101-153 C-F-1 C5.ll SAFEGUARDS 2 UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Period changed from" l" to "2" with Rev. 3 to plan, because weld was also scheduled in 1-2, P-3. Weld 0-05 on same line & drawing No. is replacement for this weld.

l 1548-WMKS-0123Ml 0-03 12"-CS-101-153 C-F-1 C5.ll SAFEGUARDS UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Weld was ultrasonically examined ori 6-17-94 with 100% of the required volume examined. Perform the surface examination.

11548-WMKS-0123Ml 0-04 12"-CS-101-153 C-F-1 C5.ll SAFEGUARDS 0 UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Period changed from "2" to "1" with Rev. 3 to plan. Replaces weld 0-01 on the same line & drawing No. that was scheduled in P-1. PERIOD CHANGED FROM "l" TO "O" IN REV. 5. NEW WELD SUBSTITUTED DUE TOPARTIAL. DID NOT WANT TO SUBMIT A RELIEF. This weld replaced with weld 0-02 on drawing l 1548-WMKS-0123Ll.

l 1548-WMKS-0123Ml 0-05 12"-CS-101-153 C-F-1 C5.ll SAFEGUARDS 0 UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Period changed from "2" to "l" with Rev. 3 to plan. Replaces weld 0-02 on the same line & drawing No. that was scheduled in P-1. PERIOD CHANGED FROM "1" TO "O" WITH REV. 5 TO PLAN. EXAM PERFORMED RESULTED IN A PARTIAL. NEW WELD SUBSTITUTED IN LIEU OF SUBMITTING RELIEF. WELD 0-02 ON l 1548-WMKS-0123LZ1 SUBSTITUTED.

l 1548-WMKS-0123Ml 0-13L 12"-CS-101-153 C-F-1 C5.l2 SAFEGUARDS UT/PT Comments LONGITUDINAL PIPING WELD, (WEPSEM). Per Relief Request SR-012 & Code Case N-524, The examination area includes only that length of the longitudinal weld (Weld 0-13L) within the circumferential weld examination volume of welds 0-02 & 0-03. Examination requirements must be met for both transverse & parallel flaws in the examination area of the longitudinal weld. The weld was ultrasically examined on 6-17-94 with I 00% of the required volume examined. Perfonn the surface examination.

l 1548-WMKS-0124Al 1-0lDM 6"-RC-338-1502 B-F B5.40 CONT.47 UT/PT Comments PRESSURIZER- NOZZLE TO SAFE END BUTT WELD, (WEPNSB). Year changed from "00" to "96", (with Rev. 3 to plan) because the same weld is scheduled in I-2, P-3 for re-examination ofa partial examination performed in 1986 and the same weld cannot be examined twice in the same refueling outage.

11548-WMKS-0124Al 2-RC-SV-255 IA 6"-RC-339-1502 B-M-2 Bl2.50 CONT.47 0 VT-3 Conunenh VALVE BODY GREATER THAN 4 IN. NOMINAL PIPE SIZE. Perform a VT-3 examination if valve is opened for any reason. Perform the VT-3 examination to the extent practicable. New with Rev. 9 to plan: Examination removed from the plan because the valve body (Valve 2-RC-SV-255 lA) was examined during the 1997 refueling outage.

Summary of Changes Sorted by Drawing and Mark No., SPSU23 Database Page 18 of 46 Print Date: 3/11/98

Drawing No. MarkNo. Line Number Category Item No. Location Period Method I 1548-WMKS-0!24Al 2-RC-SV-25518 6"-RC-338-1502 B-M-2 812.50 CONT.47 0 VT-3 Comments VALVE BODY GREATER THAN 4 IN. NOMINAL PIPE SIZE. Perform a VT-3 examination if valve is opened for any reason. Perform the VT-3 examination to the extent practicable. New with Rev. 9 to the plan: Removed from the plan because the valve body (Valve 2-RC-SV-255 IA) was examined during the 1997 refueling outage.

I 1548-WMKS-O l 24AI 2-RC-SV-255 IC 6"-RC-337-1502 B-M-2 812.50 CONT.47 0 VT-3 Comments VALVE BODY GREATER THAN 4 IN. NOMINAL PIPE SIZE. Perform a VT-3 examination if valve is opened for any reason. Perform the VT-3 examination to the extent practicable. New with Rev. 9 to the plan: Examination removed from the plan because the valve body (Valve 2-RC-SV-2551 A) was examined during the 1997 refueling outage.

I 1548-WMKS-0124Al 4-IIBC 3"-RC-335-1502 8-J 89.32 CONT.47 PT Comments CIRCUMFERENTIAL PIPING WELD BRANCH CONNECTION, (WEPBC). Reference memo Dalton to McNeill of3-15-95 (FAX date): This weld is covered by a strong-back and is, therefore, inaccessible. A relief request will be required since all branch connections must be examined. The weld is not being removed from the plan at this time to ensure that it remains visible until a relief request is submitted & approved. 5-22-96: Received PT report of saddle weld, but relief request has not been submitted. Will store report in Misc. section of 1996 outage binder until relief is approved.

Update: 6-20 Reliefrequests status: Pending- Virginia Power Ltr.96-606 dated 1-2-97.

11548-WMKS-0!25Al 1-06 4"-RC-3 I 4-1502 B-J B9.11 ALOOP 2 UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Terminal End. TS Item 2.1.1. Examine a minimum of 5% of the welds every refueling outage with all complete by the end of the interval. Year changed to 2000 with Rev. 8 to the plan to ensure that 5% of the welds are examined every refueling outage.

l 1548-WMKS-0125Al 1-09 4"-RC-314-1502 B-J 89.11 CONT.-27 2 UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). TS Item 2.1. l. Examine a minimum of 5% of the welds every refueling outage with all complete by the end of the interval. Examination changed from 1997 outage to 1999 due to the elimination of SI welds from TS 2.1.1. Change effective with Rev. 5 to plan.

11548-WMKS-0125Al 1-11 4"-RC-314-1502 B-J 89.11 CONT.-27 3 UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). TS Item 2.1.1. Examine a minimum of 5% of the welds every refueling outage with all complete by the end of the interval. Year changed to 2003 with Rev. 8 to the plan to ensure that 5% of the welds are examined every refueling outage.

11548-WMKS-0125Al 1-12 4"-RC-314-1502 B-J B9.ll CONT.-27 3 UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). TS Item 2.1. I. Examine a minimum of 5% of the welds every refueling outage with all complete by the end of the interval. Year changed to 2003 with Rev. 8 to the plan to ensure that 5% of the welds are examined every refueling outage.

I 1548-WMKS-0125Al 1-13 4"-RC-314-1502 B-J B9.ll CONT.-27 3 UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). TS Item 2.1. l. Examine a minimum of 5% of the welds every refueling outage with all complete by the end of the interval. Year changed to 2003 with Rev. 8 to the plan to ensure that 5% of the welds are examined every refueling outage.

I 1548-WMKS-0125Al 2-05 4"-RC-315-1502 B-J B9.ll CLOOP 3 UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). TS Item 2.1.1. Examine a minimum of 5% of the welds every refueling outage with all complete by the end of the interval. Year changed to 2002 with Rev. 8 to the plan to ensure that 5% of the welds are examined every refueling outage.

11548-WMKS-O 125Al 2-30 4"-RC-315-1502 B-J B9.l I CONT.18 UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). TS Item 2.1.1. Examine a minimum of5% of the welds every refueling outage with all complete by the end of the interval. THIS WELD WAS EXAMINED IN THE 1995 REFUELING OUTAGE, HOWEVER CREDIT WAS NOT TAKEN DUE TO COVERAGE ANOMALIES BETWEEN THE SURFACE AND VOLUMETRIC EXAMINATION SHEETS. WHIP RESTRAINTS ARE ASSOCIATED WITH THIS WELD WHICH APPARENTLY REDUCES THE EXAMINATION COVERAGE OF THE SURFACE EXAMINATION. THIS COVERAGE WAS REPORTED AS 100%0NTHE 5 SIDE BASE METAL, 25.89%0N THE WELD METAL AND 18.75%0N THE2 SIDE BASE METAL. THIS COVERAGE DID NOT APPEAR TO CORRELATE WITH THE VOLUMETRIC EXAMINATION REPORT WHICH HAD 100% COVERAGE IN THE 7&8 DIRECTIONS. THIS EXAM WAS DISCUSSED WITH MR. SPOONER WHO RECO!v!MENDED THAT THE EXAM BE REPEATED IN THE 1996 REFUELING OUT AGE. 1.4 WELDS ARE REQUIRED TO MEET Tl IE 5%

CRITERIA OF TECHNICAL SPECIFICATIONS. 2 OTHER WELDS WERE COMPLETED, THEREFORE THIS EXA!vI CAN BE REPEATED IN THE 1996 REFUELING OUTAGE AND NOT VIOLATE TECHNICAL SPECIFICATIONS.

Summary of Changes Sorted by Drawing and Mark No., SPSU23 Database Page 19of 46 Print Date: 3// //98

Draning No. Mark No. Line Number Category Item No. Location Period Method I 1548-WMKS-O I 25AI 2-RC-H006 4"-RC-315-1502 F-A Fl.10 CONT.18 2 VT-3 Comments SUPPORT HAANC. Reexamination of 1995, Period I failure, loose nuts on the intermediate connecting bolts. Added to plan with Rev. 5 to plan.

11548-WMKS-0127Cl 1-23 8"-SI-292-153 C-F-1 CS.II SAFEGUARDS 2 UT/PT Conunents CIRCUMFERENTIAL PIPING WELD, (WEPCB). TS Item 2.1.2. Examine a minimum of2.5% of the welds every refueling outage with all complete by the end of the interval. Year changed to 2000 with Rev. 8 to the plan to ensure that 2.5% of the welds are examined every refueling outage.

11548-WMKS-0127GI 2-CH-H013 6"-CH-318-152 F-A Fl.20 AUX. BLDG. VT-3 Comments SUPPORT HAVAR Examined on 5-4-94, which was before the start of the 3rd Interval, therefore the examination has been rescheduled for the 1996 refueling outage.

11548-WMKS-0127GI 2-CH-H013 6"-CH-318-152 F-A Fl.20 AUX.BLDG. VT-3 Conunents SUPPORT HAVAR. Examined on 5-4-94. Examination was performed before start of 3rd Interval and therefore, must be repeated.

11548-WMKS-012713 1-11 2"-SI-275-1502 B-J 89.40 CONT. 18 PT Comments SOCKET WELD, (WEPSOK). This weld added to plan with Rev. 3 to plan, and replaces weld 1-13 on the same line No. & drawing No.

11548-WMKS-012713 1-13 2"-SI-275-1502 B-J 89.40 CONT. 18 0 PT Comments SOCKET WELD, (WEPSOK). This weld removed from plan with Rev. 3 to plan per verbal request from J. Dalton on 9-1-94. Replaced with weld 1-11 on same line No. & drawing No.

l 1548-WMKS-0127J3Z 2-SI-H002 2"-SI-275-1502 F-A Fl.20 CONT.-27 3 VT-3 Comments SUPPORT HARES. Added to database with Rev. 2 to drawing. Added to plan with Rev. 5 to plan. This support was added to the plan because additional supports were added to the database, and this is needed in order to ensure 15% of the supports are examined.

l 1548-WMKS-0127J3Z 2-SI-H003 2"-SI-275-1502 F-A Fl.20 CONT.-27

3 VT-3 Comments SUPPORT HARES. Added to database with Rev. 2 to drawing. Added to plan with Rev. 5 to plan. 1bis support was added to the plan because additional supports were added to the database, and this is needed in order to ensure 15% of the supports are examined.

11548-WMKS-0127J3Z 2-SI-H016 2"-SI-275-1502 F-A Fl.20 CONT.-27 2 VT-3 Comments SUPPORT HARES. Added to database with Rev. 2 to drawing. Added to plan with Rev. 5 to plan. This support was added to the plan because additional supports were added to the database, and this is needed in order to ensure 15% of the supports are examined.

l 1548-WMKS-2018A5 1-26 14"-WFPD-117-601 NA NA MSVH 0 UT/MT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Perform augmented examination in accordance with TS 4.15 and Augmented Inspection Manual. Removed from plan with Rev. 7 to plan due to weld selection for TS 4.15 being changed to the 1989 Code.

l 1548-WMKS-2018A5 2-WFPD-H022 18"-WFPD-l 06-90 l NA NA TURBINE 3 VT-3 Comments SUPPORT HAANC. Augmented support program in accordance with QAE 88-60-06. Re-examination of failed support after repair ofloose bolt, cracks in grouting and concrete, Period 2, outage SU29710.

l 1548-WMKS-2018A5 2-WFPD-H023 18"-WFPD-106-901 NA NA MSVH 2 VT-3 Conunents SUPPORT HARES. New with Rev. 9: Scheduled for examination as an additional examination, i.e., an expansion due to failure of support 2-WFPD-H022 on the same drawing and line number as this support.

l 1548-WMKS-2022A2Z HOO!-! 6"-CC-165-151 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HOO 1). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

Summary of Changes Sorted by Drawing and Mark No., SPSU23 Database Page 20of 46 Print Date: 3/11/98

Drawing No. Mark No. Line Number Category Item No. Location Period Method 11548-WMKS-2022A2Z H002-1 6"-CC-165-151 D-A Dl.40 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H002). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-2022A3 HOOi-i 6"-CC-181-151 D-A Dl.20 CONT.-3 3 VT-3 Comments INTEGRALLY ATTACHED WELD, (HOO!). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

1 I548-WMKS-2022A3Z HOl 1-1 6"-CC-181-151 D-A Dl.20 CONT.-3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO! I). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes m'ade were to Class 3 integral attachments.

l 1548-WMKS-2022A3Z H012-1 6"-CC-181-151 D-A Dl.40 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO 12). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-2022A4 2-CC-H008 6"-CC-173-151 F-A Fl.30 CONT.-3 3 VT-3 Comments SUPPORT HAANC. Added to plan with Rev. 2 to plan. Supports are newly identified as of8-23-94.

l 1548-WMKS-2022A4 H006-1 6"-CC-173-151 D-A Dl.20 CONT.-27 0 VT-3 Comments INTEGRALLY WELDED ATTACHMENT, (H006). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1548-WMKS-2022A4 H008-1 6"-CC-173-151 D-A Dl.20 CONT.-3 3 VT-3 Comments INTEGRALLY WELDED ATTACHMENT, (H008). Added to plan with Rev. 2 to plan. Supports are newly identified as of 8-23-94. Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. l11e corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

I 1548-WMKS-2022A4 H009-1 6"-CC-173-151 D-A Dl.40 CONT.-3 0 VT-3 Comments INTEGRALLY WELDED ATTACHMENT, (H009). Supports are newly identified as of8-23-94. Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-2022Bl H019-1 6"-CC-160-151 D-A Dl.20 CONT.-3 3 VT-3 Comments INTEGRALLY ATTACHED WELD, (H019). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-2022BIZ H021-l 6"-CC-160-151 D-A Dl.40 CONT.-3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H021 ). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

! 1548-WMKS-2022B2 HOOi-i 6"-CC-156-151 D-A Dl.20 CONT.-3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HOOi). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l l548-WMKS-2022B2Z HOll-1 6"-CC-156-151 D-A Dl.40 CONT. -27 0 VT-3 Comments INTEGRALLY ATT ACHED WELD, (HO 11 ). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

Summary of Changes Sorted by Dra"ing and Mark No., SPSU23 Database Page 21 of 46 Print Date: 3// 1/98

Dra\\ing No. Mark No. Line Number Category Item No. Location Period Method l 1548-WMKS-2022B3 HOOi-i 6"-CC-159-151 D-A Dl.20 CONT. 18 3 VT-3

)

Comments INTEGRALLY ATTACHED WELD, (HOO I). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-2022B3Z H006-1 6"-CC-159-151 D-A Dl.40 CONT. -27 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H006). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-CC-28Z HOil-! 6"-CC-177-151 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO 11 ). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the.site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-CC-282 H012-1 6"-CC-177-151 D-A Dl.40 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO I 2). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-CC-362 H016-1 6"-CC-161-151 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO 16). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1548-WMKS-CC-36Z H017-l 6"-CC-161-151 D-A Dl.40 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO I 7). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1548-WMKS-CC-37Z HOOi-i 6"-CC-153-151 D-A Dl.40 CONT. -3 2 VT-3 Comments INTEGRALLY ATTACHED WELD, (HOO I). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

I 1548-WMKS-CC-39 H006A-1 6"-CC-155-151 D-A Dl.20 CONT. -3 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H006A). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match.

The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-CC-392 H011-1 6"-CC-155-151 D-A Dl.40 CONT. -27 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO 11 ). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-CC-4!2 H012-1 6"-CC-154-151 D-A Dl.40 CONT. -27 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HO 12). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-Wl\'1KS-CC-48Z H003-l 6"-CC-169-151 D-A Dl.20 CONT. -3 0 VT-3 Conunents INTEGRALLY ATTACHED WELD, (H003). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-CC-48Z H004-1 6"-CC-169-151 D-A Dl.40 CONT. -3 0 VT-3 Comments INTEGRALLY ATT ACHED WELD, (H004). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

Summary of Changes Sorted by Drawing and Mark No., SPSU23 Database Page 22 of 46 Print Date: 3/J J/98

Dra,,ing No. Mark No. Line Number Category Item No. Location Period Method 11548-WMKS-CH-1 I 1-01 3"-CH-303-1503 C-F-1 C5.21 AUX.BLDG. 0 UT/PT Comments Circumferential Piping Weld, (WEPCB). This weld removed from the plan with Rev. 5 to plan & removed from the drawing with Rev. 5 to the drawing.

11548-WMKS-CH-1 l 1-02 3"-CH-303-1503 C-F-1 C5.21 AUX.BLDG. 0 UT/PT Comments Circumferential Piping Weld, (WEPCB). This weld removed from the plan with Rev. 5 to the plan & removed from the drawing with Rev. 5 to the drawing.

11548-WMKS-CH-11 1-03 3"-CH-303-1503 C-F-1 C5.21 AUX. BLDG. UT/PT Comments Circumferential Piping Weld, (WEPCB). TS Item 2.1.2. Examine a minimum of2.5% of the welds every refueling outage with all complete by the end of the interval. Added to plan with Rev. 5 to plan to replace weld deleted from drawing I 1548-WMKS-CH-11 with Rev. 5 to the drawing.

11548-WMKS-CH-1 I 1-10 3"-CH-303-1503 C-F-1 C5.21 AUX.BLDG. 2 UT/PT Comments Circumferential Piping Weld, (WEPCB). New with Rev. 9 to the plan: TI1is weld added into the plan. to take the place of weld 1-11 on the same drawing and line number as weld 1-10. Weld 1-1 I is covered by a support.

11548-WMKS-CH-l 1 1-11 3"-CH-303-1503 C-F-1 C5.21 AUX. BLDG. 0 UT/PT Comments Circumferential Piping Weld, (WEPCB). New with Rev. 9 to the plan: This weld removed from plan because it is covered by a support. Weld 1-10 on the same drawing and line was added into the plan to take the place of weld 1-11.

11548-WMKS-CH-l l 1-12 3"-CH-303-1503 C-F-1 C5.2! AUX.BLDG. 2 UT/PT Comments Circumferential Piping Weld, (WEPCB). TS Item 2.1.2. Examine a minimum of2.5% of the welds every refueling outage with all complete by the end of the interval. Year changed to 2000 with Rev.

8 to the plan to ensure that 2.5% of the welds are examined every refueling outage.

11548-WMKS-CH-ll 2-01 3"-CH-302-1503 C-F-1 C5.21 AUX. BLDG. 0 UT/PT Conunents Circumferential Piping Weld, (WEPCB). This weld removed from the plan with Rev. 5 to the plan & removed from the drawing with Rev. 5 to the drawing.

11548-WMKS-CH-l l 2-02 3"-CH-302-1503 C-F-1 C5.21 AUX.BLDG. 0 UT/PT Comments Circumferential Piping Weld, (WEPCB). This weld removed from the plan with Rev. 5 to the plan & removed from the drawing with Rev. 5 to the drawing.

11548-WMKS-CH-l 1 2-03 3"-CH-302-1503 C-F-1 C5.21 AUX.BLDG. UT/PT Comments Circumferential Piping Weld, (WEPCB). Added to plan with Rev. 5 to plan to replace weld deleted from drawing 11548-WMKS-CH-11 with Rev. 5 to the drawing.

11548-WMKS-CH-11 2-04 3"-CH-302-1503 C-F-1 C5.21 AUX.BLDG. 0 UT/PT Comments Circumferential Piping Weld, (WEPCB). Reference memo (Naughton to file) dated 6-19-9 5: Due to inconsistencies between the 1995 refueling outage NDE report and the drawing it is believed that this weld was called 2-05 on the examination report. Therefore, this weld is scheduled for examination during the 1996 refueling, and is effective with Rev. 5 to the plan. Removed from plan with Rev. 7 to the plan. Removed because of a partial examination. Weld 0-08 on drawing 11548-WMKS-CH-18 placed in plan to replace this weld.

11548-WMKS-CH-l 1 2-05 3"-CH-302-1503 C-F-1 C5.21 AUX.BLDG. UT/PT Comments Circumferential Piping Weld, (WEPCB). Reference memo (Naughton to file) dated 6-19-95: Due to inconsistencies between the 1995 refueling outage NDE report and the drawing it is believed that this weld was called 2-04 on the examination report. TI1erefore, this weld is scheduled for examination during the 1996 refueling, and is effective with Rev. 5 to the plan.

11548-WMKS-CH-l 1 2-CH-H004 3"-CH-302-1503 F-A Fl.20 AUX.BLDG. VT-3 Comments SUPPORT HARES. Examined on 5-4-94, which was before the start of the 3rd Interval, therefore the examination has been rescheduled for the 1996 refueling outage.

I 1548-WMKS-CH-1 I 2-CH-H004 3"-CH-302-1503 F-A Fl.20 AUX.BLDG. VT-3 Comments SUPPORT HARES. Examined 5-4-94. Examination was performed before start of 3rd Interval and therefore, must be repeated.

Sununary of Changes Sorted by Dra~ing and Mark No., SPSU23 Database Page 23 of 46 Print Date: 3/11/98

Drawing No. Mark No. Line Number Category Item No. Location Period Method 11548-WMKS-CH-11 2-CH-H004A 3 "-CH-302-1503 F-A Fl.20 AUX.BLDG. VT-3 Comments SUPPORT HARES. Examined on 5-4-94, which was before the start of the 3rd Interval, therefore the examination has been rescheduled for the 1996 refueling outage.

11548-WMKS-CH-11 2-CH-H004A 3 "-CH-302-1503 F-A Fl.20 AUX.BLDG. VT-3 Comments SUPPORT HARES. Examined on 5-4-94. Examination was perormed before start of 3rd Interval and therefore, must be repeated.

11548-WMKS-CH-1 l 3-01 3"-CH-381-1503 C-F-1 C5.21 AUX.BLDG. 0 UT/PT Comments Circumferential Piping Weld, (WEPCB). This weld removed from the plan with Rev. 5 to the plan & removed from the drawing with Rev. 5 to the drawing.

11548-WMKS-CH- l 1 3-02 3 "-CH-381-1503 C-F-1 C5.21 AUX.BLDG. 0

UT/PT Conunents Circumferential Piping Weld, (WEPCB). This weld removed from the plan with Rev. 5 to the plan & removed from the drawing with Rev. 5 to the drawing.

11548-WMKS-CH-l l 3-03 3"-CH-381-1503 C-F-1 C5.21 AUX.BLDG. 3 UT/PT Comments Circumferential Piping Weld, (WEPCB). Added to plan with Rev. 5 to plan to replace weld deleted from drawing 11548-WMKS-CH-11 with Rev. 5 to the drawing.

11548-WMKS-CH-l l A-01 3"-CH-381-1503 C-F-1 C5.41 AUX.BLDG. 3 PT Comments Circumferential Piping Weld, (WEPCB). TS Item 2.1.2. Examine a minimum of2.5% of the welds every refueling outage with all complete by the end of the interval. Added to plan with Rev. 5 to plan to replace weld deleted from drawing 11548-WMKS-CH-11 with Rev. 5 to the drawing.

11548-WMKS-CH-1 l B-01 3"-CH-302-1503 C-F-1 C5.41 AUX.BLDG. PT Comments Circumferential Piping Weld, (WEPCB). Added to plan with Rev. 5 to plan to replace weld deleted from drawing 11548-WMKS-CH-11 with Rev. 5 to the drawing.

11548-WMKS-CH-l l C-01 3"-CH-303-1503 C-F-1 C5.41 AUX.BLDG. PT Comments Circumferential Piping Weld, (WEPCB). Added to plan with Rev. 5 to plan to replace weld deleted from dr;wing 11548-WMKS-CH-l l with Rev. 5 to the drawing. Line No. and Item No. changed with Rev. 5 to drawing.

11548-WMKS-CH-18 0-08 3"-CH-371-1503 C-F-1 C5.21 AUX.BLDG. 2 UT/PT Comments Circumferential Piping Weld, (WEPCB). Added to plan with Rev. 7 to plan to replace weld 2-04 on drawing 11548-WMKS-CH-1 l.

11548-WMKS-CH-8 1-41 3"-CH-301-1502 B-J B9.21 CONT. -27 0 PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Removed from plan with Rev. 7 to the plan. This weld replaced with weld 1-59 on Dwg. CH-9.

11548-WMKS-CH-8 1-54 3"-CH-301-1502 B-J B9.21 CONT. -3 2 PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Terminal End. New with Rev. 7 to plan: Rescheduled from period I to period 2 because the examination was not performed.

11548-WMKS-CH-8 2-CH-H008A 3"-CH-301-1502 F-A Fl.JO CONT. -27 2 VT-3 Comments SUPPORT HARES. Reexamination of 1995, Period 1, failure, excessive gap between the baseplate and wall. Acceptable gap after repair and evaluation is 1/16" to 1/8". See DCP 93-048, Rev. 12 and I 1548-PSSK-CH-8.8A for additional information, if needed. Added to plan with Rev. 5 to plan.

11548-WMKS-CH-9 1-59 3"-CH-379-1503 B-J B9.21 CONT. -3 2 PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Terminal End. Radiation levels reported to be 50 Ron 5-3-91 by site Sr. NDE Technician. Recommend flushing prior to examination. Added with Rev. 7 to plan because weld is a terminal end.

Summary of Changes Sorted by Drawing and Mark No., SPSU23 Database Page 24 of 46 Print Date: 3/J //98

Drawing No. Mark No. Line Number Category Item No. Location Period Method l lS48-WMKS-CH-E-2 2-CH-HOOS 2-CH-E-2 F-A Fl.40 AUX.BLDG. 0 VT-3 Conunents SUPPORT HAANC. Removed from the database with Rev. 9 to the plan. Based on Rev. 3 to the drawing. This support was scheduled for examination in Period 2.

l lS48-WMKS-CH-E-2 H003-l 2-CH-E-2 D-A Dl.20 AUX.BLDG. 2 VT-3 Comments INTEGRALLY WELDED ATTACHMENT, (H003 ). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database

match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l 1S48-WMKS-CH-E-2 H004-l 2-CH-E-2 D-A Dl.20 AUX. BLDG. 2 VT-3 Comments INTEGRALLY WELDED ATTACHMENT, (H004). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Conunitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l lS48-WMKS-CH-E-2 HOOS-I 2-CH-E-2 D-A Dl.20 AUX.BLDG. 0 VT-3 Comments INTEGRALLY WELDED ATTACHMENT, (HOOS). Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Conunitment No 96-074 applies & the only changes made were to Class 3 integral attachments. Removed from the database with Rev. 9 to the plan. Based on Rev. 3 to the drawing. This integral attachment was scheduled for examination in Period 2.

l 1S48-WMKS-CH-E-3 1-06 2-CH-E-3 B-D B3.1SO CONT. -3 2 PT Comments HEAT EXCHANGER - NOZZLE TO VESSEL WELD. Per relief request SR-010 perfonn a liquid penetrant (PT) examination in lieu of an ultrasonic examination. New with Rev. 7 to plan:

Rescheduled from period 1 to period 2 because the examination was not performed in period I.

l !S48-WMKS-CH-E-3 1-08 2-CH-E-3 B-D B3.1SO CONT. -3 2 PT Comments HEAT EXCHANGER - NOZZLE TO VESSEL WELD. Per reliefrequest SR-0 IO perform a liquid penetrant (PT) examination in lieu of an ultrasonic examination. New with Rev. 7 to plan:

Rescheduled from period l to period 2 because the examination was not performed in period l.

l 1S48-WMKS-CH-E-4 HOOi-i 2-CH-E-4 D-A Dl.20 CONT. -3 VT-3 Comments INTEGRALLY ATTACHED WELD, (HOO I) Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Conunitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

l lS48-WMKS-CH-E-4 H002-1 2-CH-E-4 D-A Dl.20 CONT. -3 VT-3 Comments INTEGRALLY ATTACHED WELD, (H002) Category verified & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to a*gree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

I 1S48-WMKS-RC-IO-l 1-08 3 l "-RC-308-2SO IR B-J B9.ll CLOOP 0 Uf/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Removed from plan with Rev. 7 to plan & replaced with weld 1-09 on drawing 11 S48-WMKS-RC-l l-l. Weld removed due to partial examination.

l 1S48-WMKS-RC-10-l 1-18 3 I "-RC-308-2SO IR B-J B9.12 CLOOP 0 Uf/PT Comments LONGITUDINAL PIPING WELD, (WEPSEM). Per Relief Request SR-012 & Code Case N-S24, The examination area includes only that length of the longitudinal weld (Weld 1-18) within the circumferential weld examination volume of weld 1-08. Examination requirements must be met for both transverse & parallel flaws in the examination area of the longitudinal weld. Removed from the plan with Rev. 7 to the plan because weld 1-08 (circ. weld) was a partial exam. Weld will be replaced with weld 1-18 on drawing RC-11-1.

I IS48-WMKS-RC-10-l 1-19 3 l "-RC-308-2SO IR B-J B9.12 CLOOP 0 Uf/PT Conunents LONGITUDINAL PIPING WELD, (WEPSEM). Per Relief Request SR-012 & Code Case N-S24, The examination area includes only that length of the longitudinal weld (Weld 1-19) within the circumferential weld examination volume of weld 1-08. Examination requirements must be met for both transverse & parallel flaws in the examination area of the longitudinal weld. Weld removed from plan with Rev. 7to the plan because weld 1-08 (circ. weld) was a partial exam. Weld will be replaced with weld 1-19 on drawing RC-11-1.

l l S48-WMKS-RC-l 0-1 MOV-2S94 29"-RC-307-2SO IR NA NA CCUBICLE 2 UT-CGWT Comments Examine every refueling. Loop Stop Valve Stems (hot leg). Added with Rev. 7 to the plan, to cover the refueling outage scheduled in year 2000 and in period 2.

Summary of Changes Sorted by Dra"ing and Mark No., SPSU23 Database Page 25 of 46 Print Date: 311 //98

Dra\\ing No. Mark No. Line Number Category Item No. Location Period Method 11548-WMKS-RC-!O-l MOV-2595 27 "-RC-309-250!R NA NA CCUBICLE 2 UT-CGWT Conunents Examine every other refueling. Loop Stop Valve Stems (cold leg). Added with Rev. 7 to the plan, to cover the refueling outage scheduled in year 2000 and in period 2.

11548-WMKS-RC-IOZI 2-RC-H002 2"-RC-359-1502 F-A Fl.40 CLOOP 2 VT-3 Comments SUPPORT HAVARI. This support placed in period 2 with Rev. 3 to plan and replaces support 11548-WMKS-0123Kl CS-H002, which was moved to period I to replace this support.

11548-WMKS-RC-IOZ4 1-01 2"-CH-393-1502 B-J 89.40 CLOOP 2 PT Comments SOCKET WELD, (WEPSOK). New to plan with Rev. 2 to plan. Replaces weld 1-10 on same line No. & drawing No. Designated weld as terminal end due to licensing concerns (Jolm Lewis). See memo Paul to Lewis of 8-16-94. New with Rev. 7 to plan: This weld removed from plan & replaced with weld 1-04 on the same line & drawing No. as weld 1-0 I. Reason for change: weld 1-0 I is inaccessible unless RCP main flange is disassembled. See relief request SR-018. New with Rev. 9 to plan: This weld added back into the plan in period 2 to ensure that if the RCP main flange is disassembled that this weld will get examined. See reliefrequest SR-018.

11548-WMKS-RC-IOZ4 1-01 2"-CH-393-1502 B-J 89.40 CLOOP 3 PT Comments SOCKET WELD, (WEPSOK). New to plan with Rev. 9 to plan: This weld is inaccessible unless the main RCP flange is disassembled. This weld added back into plan in period 3 to ensure that if the RCP main flange is disssambled that weld 1-01 will be examined. See relief request SR-018.

l !548-WMKS-RC-JOZ4 1-04 2"-CH-393-1502 B-J 89.40 CLOOP PT Comments SOCKET WELD, (WEPSOK). New with Rev. 7 to plan: This weld added to plan to replace weld 1-01 on the same line & drawing No. as this weld, (l-04).

l 1548-WMKS-RC-IOZ4 1-10 2"-CH-393-1502 B-J 89.40 CLOOP 0 PT Comments SOCKET WELD, (WEPSOK). Removed from plan with Rev. 2 to plan. Replaced with weld 1-01 on same line No. & drawing No.

11548-WMKS-RC-J J-J 1-09 3 J "-RC-305-250 IR B-J 89.11 BLOOP 2 UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Added to plan with Rev. 7 to the plan to replace weld 1-08 on drawing 11548-WMKS-RC-!O-l.

11548-WMKS-RC-11-1 1-18 31 "-RC-305-250 IR B-J 89.12 BLOOP 2 UT/PT Comments LONGITUDINAL PIPING WELD, (WEPSEM). Per Relief Request SR-012 & Code Case N-524, the examination area includes only that length of the longitudinal weld (weld 1-18) within the circumferential weld examination volume of weld 1-09. Examination requirements must be met for both transverse & parallel flaws in the examination area of the longitudinal weld. Weld added to the plan with Rev. 7 to the plan to replace weld 1-18 on drawing 11548-WMKS-RC-10-l.

11548-WMKS-RC-l l-l 1-19 31"-RC-305-2501R B-J 89.12 BLOOP 2 UT/PT Comments LONGITUDINAL PIPING WELD, (WEPSEM). Per Relief Request SR-012 & Code Case N-524, the examination area includes only that length of the longitudinal weld (weld 1-19) within the circumferential weld examination volume of weld 1-09. Examination requirements must be met for both transverse & parallel flaws in the examination area of the longitudinal weld. Weld added to the plan with Rev. 7to the plan to replace weld 1-19 on drawing 11548-WMKS-RC-IO-l.

11548-WMKS-RC-11-l MOV-2592 29"-RC-304-2501R NA NA BCUBICLE 2 UT-CGWT Comments Examine every refueling. Loop Stop Valve Stems (hot leg). Added with Rev. 7 to the plan, to cover the refueling outage scheduled in year 2000 and in period 2.

11548-WMKS-RC-J J-l MOV-2593 27 "-RC-306-250JR NA NA BCUBICLE 2 UT-CGWT Comments Examine every other refueling. Loop Stop Valve Stems (cold leg). Added with Rev. 7 to the plan, to cover the refueling outage scheduled in year 2000 and in period 2.

11548-WMKS-RC-J JZ3 1-01 2"-CH-395-1502 B-J 89.40 BLOOP 2 PT Conunents SOCKET WELD, (WEPSOK). New to plan with Rev. 9 to plan. This weld entered into plan in period 2 to ensure that weld 1-01 is examined if the RCP main flange is disassembled. This weld is inaccessible unless the RCP main flange is disassembled. See relief request SR-018.

Summary of01anges Sorted by Dra\\ing and Mark No., SPSU23 Database Page 26of 46 Print Date: 3/11/98

Drawing No. Mark No. Line Nmnber Category Item No. Location Period Method 11548-WMKS-RC-I JZ3 1-01 2"-CH-395-1502 B-J B9.40 BLOOP 3 PT Comments SOCKET WELD, (WEPSOK). New to plan with Rev. 2 to plan. Designated weld as terminal end due to licensing concerns (John Lewis). See memo Paul to Lewis of8-16-94. Replaces weld 1-20 on l 1548-WMKS-RC-12Z5.

11548-WMKS-RC-12Z5 1-01 I 'h "-CH-397-1502 B-J B9.40 ALOOP 2 PT Comments SOCKET WELD, (WEPSOK). Designated as terminal end with Rev. 2 to plan. New with Rev. 9 to plan: TI1is weld is inaccessible unless the RCP main flange is disassembled. Perfonn the required examination if the main RCP flange is disassembled. See relief request SR-018.

l 1548-WMKS-RC-12Z5 1-01 1Y,"-CH-397-1502 B-J 89.40 ALOOP 3 PT Comments SOCKET WELD, (WEPSOK). Designated as terminal end with Rev. 2 to plan. New with Rev. 9 to the plan: This weld is inaccessible unless the RCP main flange is disassembled. Perform the required examination if the main RCP flange is disassembled. See relief request SR-018.

l 1548-WMKS-RC-12Z5 1-04 IV, "-CH-397-1502 B-J B9.40 ALOOP 2 PT Comments SOCKET WELD, (WEPSOK). New with Rev. 9 to plan: TI1is weld is added to the plan to replace weld 1-01 on the same drawing and line number. This weld is an additional weld and is scheduled for examination to ensure that 25% of examination category B-J welds are examined in the event that weld 1-0 I is not examined. Weld 1-0 I is inaccessible unless the RCP main flange is disassembled. See reliefrequest SR-018.

11548-WMKS-RC-12Z5 1-20 2"-CH-397-1502 B-J B9.40 ALOOP 0 PT Comments SOCKET WELD, (WEPSOK). Removed from plan with Rev. 2 to plan. Replaced with weld 1-01 on l 1548-WMKS-RC-1 IZ3.

l 1548-WMKS-RC-12Z5 2-CH-HOOJ 2"-CH-397-1502 F-A Fl.JO ALOOP VT-3 Conunents SUPPORT HAVAR. Reexamination of 1995 (Interval 2 - Period 3) failure. Repaired under RR# 95-066, for more information also see Engineering Transmittal S-95-0550. Added to plan with Rev. 5 to plan.

11548-WMKS-RC-6 2-RC-MOV-2585 8"-RC-3 l l-250JR A CUBICLE 0 Comments VALVES- BOLTS, STUDS AND NUTS. Bolting may be examined in place, under tension, or when removed. 4 Studs & Nuts. New with Rev. 6 to plan: Reference Engineering Transmittal May to Throckmorton of I 0-18-95: Bolting on this valve does not function as a pressure retaining part of the valve. Therefore, exempt from examination, and removed from plan, Period 3.

11548-WMKS-RC-E-IA2 2-09 2-RC-E-lA C-B C2.21 CONT. 47 0 UT/MT Comments VESSEL - NOZZLE TO SHELL WELD, FEEDWATER NOZZLE, (WECNTV). Changed examination requirement from 2-RC-E-l A to 2-RC-E-IB - in order to schedule examinations as they were scheduled in interval 2 - Ref. Table IWC-2500-1, Cat. C-B, Note. 3.

l 1548-WMKS-RC-E-IA2 2-10 2-RC-E-IA C-B C2.21 CONT. 47 0 UT/MT Comments VESSEL - NOZZLE TO HEAD WELD, MAIN STEAM NOZZLE, (WECNTV). Requirement to examine 0-33" moved to 02-RC-E-1 B with Rev. 4 to plan.

11548-WMKS-RC-E-IB.2 2-09 2-RC-E-IB C-B C2.21 CONT.47 UT/MT Comments VESSEL - NOZZLE TO SHELL WELD, FEEDWATER NOZZLE, (WECNH). Examine from O" to 16", clockwise, (0 Ref: top centerline offeedwater nozzle). Changed with Rev. 4 to plan: Changed examination requirement from 2-RC-E-lA to 2-RC-E-lB - in order to schedule examinations as they were scheduled in interval 2 - Ref. Table IWC-2500-1, Cat. C-B, Note. 3.

11548-WMKS-RC-E-IB.2 2-10 2-RC-E-IB C-B C2.21 CONT.47 UT/MT Comments VESSEL- NOZZLE TO HEAD WELD, !vIAIN STEAM NOZZLE, (WECNH). Examine from O" to 33", clockwise, (0 Ref.: top centerline offeedwater nozzle). Changed with Rev. 4 to plan: Changed examination requirement from 2-RC-E-IA to 2-RC-E-l B - in order to schedule examinations as they were scheduled in interval 2 - Ref. Table IWC-2500-1, Cat. C-B, Note 3.

11548-WMKS-RC-E-IC.2 2-09 2-RC-E-JC C-B C2.21 CONT. 47 2 UT/MT Comments NOZZLE TO SHELL WELD. Examine from 16" to 33", clockwise, (0 Ref. top centerline offeedwater nozzle). Changed with Rev. 4 to plan: Changed examination from 2-RC-E-lB to 2-RC-E-lC - in order to schedule examinations as they were scheduled in interval 2 - Ref. Table IWC-2500-1, Cat., C-B, Note 3.

Summary of Changes Sorted by Drawing and Mark No., SPSU23 Database Page 27 of 46 Print Date: 3111/98

Dra\\ing No. Mark No. Line Number Category Item No. Location Period Method 11548-WMKS-RC-E-lC.2 2-10 2-RC-E-IC C-B C2.21 CONT.47 2 UT/MT Comments NOZZLE TO HEAD WELD. Examine 33" to 67", clockwise, (0 Ref.: top centerline offeedwater nozzle). Changed with Rev. 4 to plan: Changed examination requirement from 2-RC-E-IB to 2-RC-E-IC - in order to schedule examinations as they were scheduled in interval 2 - Ref. Table IWC-2500-1, Cat. C-B, Note 3.

I 1548-WMKS-RC-E-2 1-08 2-RC-E-2 B-K BIO.IO CONT. 18 2 UT Comments PRESSURIZER - INTEGRALLY WELDED ATIACHMENT. (0 Ref.: Centerline of manway). New with Rev. 8 to plan: Examine O" to 193" clockwise & changed method to UT. New with Rev. 7 to plan: Changed examination method to MT or UT from surface, and the following: Verify that the weld configuration is, or is not as shown in ASME Section XI, 1989 Edition, Figure IWB-2500-14. If the configuration is as shovm in ASME Section XI, 1989 Edition, Figure IWB-2500-14 perform a UT examination on the OD of the weld from O" fo 193", clockwise, or perform a MT examination on the back side of the weld from O" to 193", clockwise and a MT examination on the OD from 96" to 193", clockwise. If the configuration is not as shovm in ASME Section XI, 1989 Edition, Figure IWB-2500-14 perform a MT examination on the back side of the weld from O" to 193", clockwise, and a MT examination on the OD from 96" to 193", clockwise, (0 Ref.: Centerline ofmanway). !fit is determined that the weld cannot be UT examined and MT examination from the back side must be performed, but the back side of the weld is inaccessible or radiation levels are such that examination cannot be performed from the back side, submit information needed to prepare a relief request to Corporate ISi for subsequent preparation of a reliefrequest.

11548-WMKS-RC-E-2 1-08 2-RC-E-2 B-K BIO.IO CONT.18 3 UT Comments PRESSURIZER- INTEGRALLY WELDED ATIACHMENT. (0 Ref.: Centerline ofmanway). New with Rev. 8 to plan: Changed examination method to UT: Examine from 193" to O" (290.250)",

clockwise. IfMT examination is performed, both sides of the weld must be examined per ASME Section XI, 1989 Edition, Figures IWB-2500-13, -14, or -15, as applicable. UT examination may be performed ifthe weld configuration is as shown in ASME Section XI, 1989 Edition, Figure IWB-2500-14. (0 Ref.: Centerline ofmanway).

l 1548-WMKS-RC-MOV2590 2-RC-MOV-2590 29"-RC-301-2501 R B-M-2 Bl2.50 A CUBICLE 0 VT-3 Comments VALVE BODY GREATER THAN 4 IN. NOMINAL PIPE SIZE, (DARLING 95-11778). Perform a VT-3 examination if valve is opened for any reason. Perform the VT-3 examination to the extent practicable. Removed from Period I of the plan with Rev. 7 to the plan. Valve body internals examination performed on MOV-2592 during the 1996 refueling outage.

l 1548-WMKS-RC-MOV2590 2-RC-MOV-2590 29"-RC-30 l-2501R B-M-2 Bl2.50 A CUBICLE 0 VT-3 Comments VALVE BODY GREATER THAN 4 IN. NOMINAL PIPE SIZE, (DARLING 95-11778). Perform a VT-3 examination if valve is opened for any reason. Perform the VT-3 examination to the extent practicable. Removed from Period 2 of the plan with Rev. 7 to the plan. Valve body internals examination performed on MOV-2592 during the 1996 refueling outage.

l 1548-WMKS-RC-MOV2590 2-RC-MOV-2590 29"-RC-301-2501R B-M-2 Bl2.50 A CUBICLE 0 VT-3 Comments VALVE BODY GREATER THAN 4 IN. NOMINAL PIPE SIZE, (DARLING 95-11778). Perform a VT-3 examination if valve is opened for any reason. Perform the VT-3 examination to the extent practicable. Removed from Period 3 ofthe plan with Rev. 7 to the plan. Valve body internals examination performed on MOV-2592 during the 1996 refueling outage.

l 1548-WMKS-RC-MOV2590 FLANGE 29"-RC-301-2501R B-G-1 B6.220 A CUBICLE 0 VT-I Comments LOOP STOP VALVE - FLANGE SURFACE. Examine l" annular surface surrounding each stud, (if connection is disassembled).

Removed from Period l of the plan with Rev. 7 to the plan. Valve flange surface examination performed on MOV-2592 during the 1996 refueling outage.

l 1548-WMKS-RC-MOV2590 FLANGE 29"-RC-301-250 l R B-G-1 B6.220 A CUBICLE 0 VT-I Conuuents LOOP STOP VALVE - FLANGE SURFACE. Examine l" annular surface surrounding each stud, (if connection is disassembled).

Removed from Period 2 of the plan with Rev. 7 to the plan. Valve flange surface examination performed on MOV-2592 during the I 996 refueling outage.

I 1548-WMKS-RC-MOV2590 FLANGE 29"-RC-301-250 JR B-G-1 B6.220 A CUBICLE 0 VT-I Comments LOOP STOP VALVE - FLANGE SURFACE. Examine I" annular surface surrounding each stud, (if cmmection is disassembled).

Removed from Period 3 of the plan with Rev. 7 to the plan. Valve flange surface examination performed on MOV-2592 during the 1996 refueling outage.

l 1548-WMKS-RC-MOV259! 2-RC-MOV-2591 27 "-RC-303-2501R B-M-2 Bl2.50 A CUBICLE 0 VT-3 Conunents VALVE BODY GREATER THAN 4 IN. NOMINAL PIPE SIZE, (DARLING 95-1 I 778). Perform a VT-3 examination if valve is opened for any reason. Perform the VT-3 examination to the extent practicable. Removed from Period 2 of the plan with Rev. 7 to the plan. Valve body internals examination performed on MOV-2592 during the 1996 refueling outage.

! l 548-WMKS-RC-MOV259 I 2-RC-MOV-259 I 27 "-RC-303-250 IR B-M-2 Bl2.50 A CUBICLE 0 VT-3 Comments VALVE BODY GREATER THAN 4 IN. NOMINAL PIPE SIZE, (DARLING 95-1 I 778). Perform a VT-3 examination if valve is opened for any reason. Perfonn the VT-3 examination to the extent practicable. Removed from Period 3 of the plan with Rev. 7 to the plan. Valve body internals examination perfonued on lv!OV-2592 during the I 996 refueling outage.

Summary of Changes Sorted by Dra\\mg and Mark No., SPSU23 Database Page 28of 46 Print Date: 3111198

Drawing No. Mark No. Line Number Category Item No. Location Period Method I 1548-WMKS-RC-MOV2591 2-RC-MOV-259 I 27 "-RC-303-250IR B-M-2 Bl2.50 A CUBICLE 0 VT-3 Comments VALVE BODY GREATER THAN 4 IN. NOMINAL PIPE SIZE, (DARLING 95-11778). Perform a VT-3 examination if valve is opened for any reason. Perform the VT-3 examination to the extent practicable. Removed from Period I of the plan with Rev. 7 to the plan. Valve body internals examination performed on MOV-2592 during the 1996 refueling outage.

l l 548-WMKS-RC-MOV259 l FLANGE 27 "-RC-303-250IR B-G-1 B6.220 A CUBICLE 0 VT-I Comments LOOP STOP VALVE - FLANGE SURFACE. Examine l" annular surface surrounding each stud, (if connection is disassembled).

Removed from Period 3 of the plan with Rev. 7 to the plan. Valve flange surface examination performed on MOV-2592 during the 1996 refueling outage.

1 l 548-WMKS-RC-MOV2591 FLANGE 27 "-RC-303-2501R B-G-1 B6.220 A CUBICLE 0 VT-I Comments LOOP STOP VALVE - FLANGE SURFACE. Examine I" annular surface surrounding each stud, (if connection is disassembled).

Removed from Period 2 of the plan with Rev. 7 to the plan. Valve flange surface examination performed on MOV-2592 during the 1996 refueling outage.

l l 548-WMKS-RC-MOV2591 FLANGE 27 "-RC-303-250IR B-G-1 B6.220 A CUBICLE 0 VT-I Comments LOOP STOP VAL VE - FLANGE SURFACE. Examine l" annular surface surrounding each stud, (if connection is disassembled).

Removed from Period 1 of the plan with Rev. 7 to the plan. Valve flange surface examination performed on MOV-2592 during the 1996 refueling outage.

I 1548-WMKS-RC-MOV2592 2-RC-MOV-2592 29"-RC-304-250 IR B-M-2 B12.50 BCUBICLE 0 VT-3 Comments VALVE BODY GREATER THAN 4 IN. NOMINAL PIPE SIZE, (DARLING 95-11778). Perform a VT-3 examination if valve is opened for any reason. Perform the VT-3 examination to the extent practicable. Removed from Period 3 of the plan with Rev. 7 to the plan. Valve body internals examination performed on MOV-2592 during the 1996 refueling outage.

l 1548-WMKS-RC-MOV2592 2-RC-MOV-2592 29"-RC-304-250 lR B-M-2 B12.50 BCUBICLE 0 VT-3 Comments VALVE BODY GREATER THAN 4 IN. NOMINAL PIPE SIZE, (DARLING 95-11778). Perform a VT-3 examination if valve is opened for any reason. Perform the VT-3 examination to the extent practicable. Removed from Period 2 ofthe plan with Rev. 7 to the plan. Valve body internals examination performed on MOV-2592 during the 1996 refueling outage.

l l 548-WMKS-RC-MOV2592 FLANGE 29"-RC-304-250 IR B-G-1 B6.220 BCUBICLE 0 VT-I Comments LOOP STOP VALVE - FLANGE SURFACE. Examine l" annular surface surrounding each stud, (if connection is disassembled).

Removed from Period 2 of the plan with Rev. 7 to the plan. Valve Flange Surface examination performed on MOV-2592 during the 1996 refueling outage.

l l 548-WMKS-RC-MOV2592 FLANGE 29"-RC-304-2501R B-G-1 B6.220 BCUBICLE 0 VT-I Comments LOOP STOP VALVE - FLANGE SURF ACE. Examine 1" annular surface surrounding each stud, (if connection is disassembled).

Removed from Period 3 of the plan with Rev. 7 to the plan. Valve Flange Surface examination performed on MOV-2592 during the 1996 refueling outage.

11548-WMKS-RC-MOV2593 2-RC-MOV-2593 27 "-RC-306-2501R B-M-2 B12.50 BCUBICLE 0 VT-3 Comments VALVE BODY GREATER THAN 4 IN. NOMINAL PIPE SIZE, (DARLING 95-11779). Perform a VT-3 examination if valve is opened for any reason. Perform the VT-3 examination to the extent practicable. Removed from Period 1 of the plan with Rev. 7 to the plan. Valve body internals examination performed on MOV-2592 during the 1996 refueling outage.

1 l 548-WMKS-RC-MOV2593 2-RC-MOV-2593 27 "-RC-306-2501R B-M-2 B12.50 BCUBICLE 0 VT-3 Comments VALVE BODY GREATER THAN 4 IN. NOMINAL PIPE SIZE, (DARLING 95-11779). Perform a VT-3 examination if valve is opened for any reason. Perform the VT-3 examination to the extent practicable. Removed from Period 2 of the plan with Rev. 7 to the plan. Valve body internals examination performed on MOV-2592 during the 1996 refueling outage.

1 l 548-WMKS-RC-MOV2593 2-RC-MOV-2593 27 "-RC-306-2501R B-M-2 B12.50 BCUBICLE 0 VT-3 Comments VALVE BODY GREATER THAN 4 IN. NOMINAL PIPE SIZE, (DARLING 95-11779). Perform a VT-3 examination if valve is opened for any reason. Perform the VT-3 examination to the extent practicable. Removed from Period 3 of the plan with Rev. 7 to the plan. Valve body internals examination performed on MOV-2592 during the 1996 refueling outage.

11548-WMKS-RC-MOV2593 FLANGE 27 "-RC-306-2501R B-G-1 B6.220 BCUBICLE 0 VT-I Conunents LOOP STOP VALVE - FLANGE SURFACE. Examine I" annular surface surrounding each stud, (if cormection is disassembled).

Removed from Period I of the plan with Rev. 7 to the plan. Valve flange surface examination perfonned on lv!OV-2592 during the 1996 refueling outage.

Sununary of Changes Sorted by Drawing and Mark No., SPSU23 Database Page 29of 46 Print Date: 3/J J/98

Drawing No. Mark No. Line Number Category Item No. Location Period Method I 1548-WMKS-RC-MOV2593 FLANGE 27 "-RC-306-2501R B-G-1 B6.220 BCUBlCLE 0 VT-!

Comments LOOP STOP VAL VE - FLANGE SURFACE. Examine l" annular surface surrounding each stud, (if connection is disassembled).

Removed from Period 2 of the plan with Rev. 7 to the plan. Valve flange surface examination performed on MOV-2592 during the 1996 refueling outage.

I I 548-WMKS-RC-MOV2593 FLANGE 27 "-RC-306-2501R B-G-1 B6.220 BCUBlCLE 0 VT-!

Comments LOOP STOP VALVE - FLANGE SURF ACE. Examine l" annular surface surrounding each stud, (if connection is disassembled).

Removed from Period 3 of the plan with Rev. 7 to the plan. Valve flange surface examination performed on MOV-2592 during the 1996 refueling outage.

l I 548-WMKS-RC-MOV2594 2-RC-MOV-2594 29"-RC-307-2501R B-M-2 Bl2.50 CCUBlCLE 0 VT-3 Comments VALVE BODY GREATER THAN 4 IN. NOMINAL PIPE SIZE, (DARLING 95-11778). Perform a VT-3 examination if valve is opened for any reason. Perform the VT-3 examination to the extent practicable. Removed from Period I of the plan with Rev. 7 to the plan. Valve body internals examination performed on MOV-2592 during the 1996 refueling outage.

l 1548-WMKS-RC-MOV2594 2-RC-MOV-2594 29"-RC-307-250IR B-M-2 B12.50 CCUBlCLE 0 VT-3 Comments VALVE BODY GREATER THAN 4 IN. NOMINAL PIPE SIZE, (DARLING 95-11778). Perform a VT-3 examination ifvalve is opened for any reason. Perform the VT-3 examination to the extent practicable. Removed from Period 2 of the plan with Rev. 7 to the plan. Valve body internals examination performed on MQV-2592 during the 1996 refueling outage.

l 1548-WMKS-RC-MOV2594 2-RC-MOV-2594 29"-RC-307-250 IR B-M-2 BI2.50 CCUBICLE 0 VT-3 Comments VALVE BODY GREATER THAN 4 IN. NOMINAL PIPE SIZE, (DARLING 95-1 I 778). Perform a VT-3 examination if valve is opened for any reason. Perform the VT-3 examination to the extent practicable. Removed from Period 3 of the plan with Rev. 7 to the plan. Valve body internals examination performed on MOV-2592 during the 1996 refueling outage.

l 1548-WMKS-RC-MOV2594 FLANGE 29"-RC-307-250 IR B-G-1 B6.220 CCUBICLE 0 VT-!

Comments LOOP STOP VALVE - FLANGE SURFACE. Examine I" annular surface surrounding each stud, (if connection is disassembled).

Removed from Period I of the plan with Rev. 7 to the plan. Valve flange surface examination performed on MOV-2592 during the 1996 refueling outage.

l I 548-WMKS-RC-MOV2594 FLANGE 29"-RC-307-250 lR B-G-1 B6.220 CCUBICLE 0 VT-I Comments LOOP STOP VALVE - FLANGE SURFACE. Examine I" annular surface surrounding each stud, (if connection is disassembled).

Removed from Period 2 of the plan with Rev. 7 to the plan. Valve flange surface examination performed on MOV-2592 during the 1996 refueling outage.

11548-WMKS-RC-MOV2594 FLANGE 29"-RC-307-2501R B-G-1 B6.220 CCUBlCLE 0 VT-!

Comments LOOP STOP VALVE - FLANGE SURFACE. Examine l" annular surface surrounding each stud, (if connection is disassembled).

Removed from Period 3 of the plan with Rev. 7 to the plan. Valve flange surface examination performed on MOV-2592 during the 1996 refueling outage.

11548-WMKS-RC-MOV2595 2-RC-MOV-2595 27 "-RC-309-2501R B-M-2 Bl2.50 CCUBlCLE 0 VT-3 Comments VALVE BODY GREATER THAN 4" NOMINAL PIPE SIZE, (DARLING 95-11779). Perform a VT-3 examination if valve is opened foe any reason. Perform the VT-3 examination to the extent practicable. Removed from Period l of the plan with Rev. 7 to the plan. Valve body internals examination performed on MOV-2592 during the 1996 refueling outage.

l 1548-WMKS-RC-MOV2595 2-RC-MOV-2595 27 "-RC-309-2501R B-M-2 Bl2.50 CCUBlCLE 0 VT-3 Comments VALVE BODY GREATER THAN 4" NOMINAL PIPE SIZE, (DARLING 95-11779). Perform a VT-3 examination if valve is opened foe any reason. Perform the VT-3 examination to the extent practicable. Removed from Period 3 of the plan with Rev. 7 to the plan. Valve body internals examination performed on MOV-2592 during the 1996 refueling outage.

11548-WMKS-RC-MOV2595 2-RC-MOV-2595 27 "-RC-309-250IR B-M-2 B12.50 CCUBICLE 0 VT-3 Comments VALVE BODY GREATER THAN 4" NOMINAL PIPE SIZE, (DARLING 95-11779). Perform a VT-3 examination ifvalve is opened foe any reason. Perform the VT-3 examination to the extent practicable. Removed from Period 2 of the plan with Rev. 7 to the plan. Valve body internals examination performed on MOV-2592 during the 1996 refueling outage.

11548-WMKS-RC-MOV2595 FLANGE 27 "-RC-309-250IR B-G-1 B6.220 CCUBlCLE 0 VT-I Comments LOOP STOP VAL VE - FLANGE SURFACE. Examine I" annular surface surrounding each stud, (if connection is disassembled).

Removed from Period I of the plan with Rev. 7 to the plan. Valve flange surface examination performed on MOV-2592 during the 1996 refueling outage.

Smnmary of Changes Sorted by Drawing and Mark No., SPSU23 Database Page 30of 46 Print Date: 3/11/98

Drawing No. MarkNo. Line Number Category Item No. Location Period Method 11548-WMKS-RC-MOV2595 FLANGE 27 "-RC-309-2501R 8-G-I 86.220 CCU8ICLE 0 VT-I Conunents LOOP STOP VALVE - FLANGE SURFACE. Examine 1" annular surface surrounding each stud, (if connection is disassembled).

Removed from Period 2 of the plan with Rev. 7 to the plan. Valve flange surface examination performed on MOV-2592 during the 1996 refueling outage.

11548-WMKS-RC-MOV2595 FLANGE 27 "-RC-309-2501R 8-G-1 86.220 CCU8ICLE 0 VT-I Comments LOOP STOP VALVE - FLANGE SURF ACE. Examine I" annular surface surrounding each stud, (if connection is disassembled).

Removed from Period 3 of the plan with Rev. 7 to the plan. Valve flange surface examination performed on MOV-2592 during the 1996 refueling outage.

11548-WMKS-RC-MOV2595 NUTS-1-13 27 "-RC-309-250 IR B-G-1 B6.230 CCU8ICLE 2 VT-I Comments LOOP STOP VALVE NUTS. Examine nuts I through 13. Examination may be performed in place, under tension, or when removed. New with Rev. 4 to plan: Nuts changed from 1-26 to 1-13.

l l548-WMKS-RC-MOV2595 NUTS-14-26 27 "-RC-309-2501R 8-G-1 B6.230 CCUBICLE 3 VT-I Comments LOOP STOP VALVE NUTS. Examine nuts 14 through 26. Examination may be performed in place, under tension, or when removed. New with Rev. 4 to plan: Nuts 14-26 changed from period 2 to period 3.

11548-WMKS-RC-MOV2595 STUDS-1-13 27 "-RC-309-2501R B-G-1 B6.210 CCUBICLE 2 UT Comments LOOP STOP VALVE STUDS. Examine studs I through 13. Examination may be performed in place, under tension, or when removed. New with Rev. 4 to plan: Studs changed from 1-26 to 1-13.

l 1548-WMKS-RC-MOV2595 STUDS-14-26 27 "-RC-309-2501R B-G-1 B6.210 CCUBICLE 3 UT Comments LOOP STOP VALVE STUDS. Examine studs 14 through 26. Examination may be performed in place, under tension, or when removed. New with Rev. 4 to plan: Studs 14-26 changed from period 2 to period 3.

11548-WMKS-RC-P-!Al 2-RC-P-!A 2-RC-P-IA B-L-2 B12.20 A CUBICLE 0 VT-3 Conunents PUMP CASING. Perform a VT-3 examination (to the extent practicable) of internal surfaces if the pump is disassembled. New with Rev. 9: Removed from the plan at the completion of period I because the examination was not performed during the period.

11548-WMKS-RC-P-IAI 2-RC-P-lA 2-RC-P-lA B-L-2 B12.20 A CUBICLE 0 VT-3 Comments PUMP CASING. Perform a VT-3 examination (to the extent practicable) of internal surfaces if the pump is disassembled. Removed from the plan because pump casing 2-RC-P-l C was examined during the 1997 refueling outage and per Table IWB-2500-1 (B-L-2) examination is required only on one pump casing, (note 1).

11548-WMKS-RC-P-IAI 2-RC-P-lA 2-RC-P-lA B-L-2 B12.20 A CUBICLE 0 VT-3 Comments PUMP CASING. Perform a VT-3 examination (to the extent practicable) of internal surfaces if the pump is disassembled. New with Rev. 9 to the plan: Removed from the plan because pump casing 2-RC-P-IC was examined during the 1997 refueling outage and per Table IWB-2500-1 (B-L-2) examination is required only on one pump casing, (note 1).

11548-WMKS-RC-P-IA2 FLANGE 2-RC-P-lA B-G-1 B6.190 A CUBICLE 0 VT-I Conunents REACTOR COOLANT PUMP - MAIN FLANGE SURF ACE. Examine I" annular surface surrounding each bolt, (if connection is disassembled). New with Rev. 9: Removed from the plan at the completion of period I because the examination was not performed during the period.

11548-WMKS-RC-P-!B.1 2-RC-P-IB 2-RC-P-IB B-L-2 B12.20 BCUBICLE 0 VT-3 Comments PUMP CASING. Perform a VT-3 examination (to the extent practicable) of internal surfaces if pump is disassembled. New with Rev. 9: Removed from the plan at the completion of period I because the examination was not performed during the period.

11548-WMKS-RC-P-IB.l 2-RC-P-IB 2-RC-P-IB B-L-2 B12.20 BCUBICLE 0 VT-3 Conunents PUMP CASING. Perform a VT-3 examination (to the extent practicable) of internal surfaces if pump is disassembled. Removed from the plan because pump casing 2-RC-P-IC was examined during the 1997 refueling outage and per Table IWB-2500-1 (B-L-2) examination is required only on one pump casing, (note I).

Summary of Oianges Sorted by Dra\\ing and Mark No., SPSU23 Database Page 31 of 46 Print Date: 3/11/98

Drawing No. Mark No. Line Number Category Item No. Location Period Method 11548-WMKS-RC-P-IB. l 2-RC-P-IB 2-RC-P-IB B-L-2 Bl2.20 BCUBICLE 0 VT-3 Comments PUMP CASING. Perform a VT-3 examination (to the extent practicable) of internal surfaces if pump is disassembled. Removed from the plan because pump casing 2-RC-P-l C was examined during the 1997 refueling outage and per Table IWB-2500-1 (B-L-2) examination is required only on one pump casing, (note I).

I I 548-WMKS-RC-P-l B.2 FLANGE 2-RC-P-IB 8-G-l 86.190 BCUBICLE 0 VT-I Comments REACTOR COOLANT PUMP - MAIN FLANGE SURFACE. Examine l" annular surface surrounding each bolt, (if connection is disassembled). New with Rev. 9: Removed from the plan at the completion of period 1 because the examination was not performed during the period.

11548-WMKS-RC-P-lC.l 2-RC-P-IC 2-RC-P-IC B-L-2 812.20 CCUBICLE 0 VT-3 Comments PUMP CASING. Perform a VT-3 examination (to the extent practicable) of the internal surfaces if the pump is disassembled. New with Rev. 9: Removed from the plan at the completion of period 1 because the examination was not performed during the period.

11548-WMKS-RC-P-lC.l 2-RC-P-IC 2-RC-P-lC B-L-2 812.20 CCUBICLE 0 VT-3 Comments PUMP CASING. Perform a VT-3 examination (to the extent practicable) of the internal surfaces if the pump is disassembled. New with Rev. 9 to the plan: Removed from the plan because this pump casing was examined during the 1997 refueling outage and per Table IWB-2500-1 (B-L-2) examination is required only once during the interval.

11548-WMKS-RC-P-l C.2 8-09 2-RC-P-IC B-G-1 B6.180 CCUBICLE 2 UT Comments REACTOR COOLANT PUMP - MAIN FLANGE BOLT. Bolt may be examined in place, under tension, or when removed. Period changed from 1 to 2 with Rev. 4 to plan.

11548-WMKS-RC-P-l C.2 8-10 2-RC-P-lC B-G-1 B6.180 CCUBICLE 2 UT Comments REACTOR COOLANT PUMP - MAIN FLANGE BOLT. Bolt may be examined in place, under tension, or when removed. Period changed from I to 2 with Rev. 4 to plan.

11548-WMKS-RC-P-IC.2 8-11 2-RC-P-IC B-G-1 B6.180 CCUBICLE 2 UT Comments REACTOR COOLANT PUMP - MAIN FLANGE BOLT. Bolt may be examined in place, under tension, or when removed. Period changed from I to 2 with Rev. 4 to plan.

11548-WMKS-RC-P-1 C.2 8-12 2-RC-P-IC B-G-1 86.180 CCUBICLE 2 UT Conunents REACTOR COOLANT PUMP - MAIN FLANGE BOLT. Bolt may be examined in place, under tension, or when remove?. Period changed from 1 to 2 with Rev. 4 to plan.

11548-WMKS-RC-P-1 C.2 8-13 2-RC-P-IC B-G-1 86.180 CCUBICLE 2 UT Comments REACTOR COOLANT PUMP - MAIN FLANGE BOLT. Bolt may be examined in place, under tension, or when removed. Period changed from I to 2 with Rev. 4 to plan.

11548-WMKS-RC-P-1 C.2 8-14 2-RC-P-lC B-G-1 86.180 CCUBICLE 2 UT Comments REACTOR COOLANT PUMP - MAIN FLANGE BOLT. Bolt may be examined in place, under tension, or when removed. Period changed from I to 2 with Rev. 4 to plan.

11548-WMKS-RC-P-l C.2 8-15 2-RC-P-IC B-G-1 86.180 CCUBICLE 2 UT Comments REACTOR COOLANT PUMP - MAIN FLANGE BOLT. Bolt may be examined in place, under tension, or when removed. Period changed from 1 to 2 with Rev. 4 to plan.

11548-WMKS-RC-P-l C.2 8-16 2-RC-P-lC 8-G-l 86.180 CCUBICLE 2 UT Comments REACTOR COOLANT PUMP - MAIN FLANGE BOLT. Bolt may be examined in place, under tension, or when removed. Period changed from I to 2 with Rev. 4 to plan.

11548-WMKS-RC-P-IC.2 8-17 2-RC-P-lC B-G-1 B6.180 CCUBICLE 2 UT Comments REACTOR COOLANT PUMP- lvIAIN FLANGE BOLT. Bolt may be examined in place, under tension, or when removed. Period changed from I to 2 with Rev. 4 to plan.

Summary of Changes Sorted by Drawing and Mark No., SPSU23 Database Page 32 of 46 Print Dal~: 3/1 J/98

Drauing No. Mark No. Line Number Category Item No. Location Period Method 11548-WMKS-RC-P-l C.2 B-18 2-RC-P-IC B-G-1 B6.180 C CUBICLE 2 UT Comments REACTOR COOLANT PUMP - MAIN FLANGE BOLT. Bolt may be examined in place, under tension, or when removed. Period changed from 1 to 2 with Rev. 4 to plan.

11548-WMKS-RC-P-lC.2 B-19 2-RC-P-IC B-G-1 B6.180 CCUBICLE 2 UT Comments REACTOR COOLANT PUMP - MAIN FLANGE BOLT. Bolt may be examined in place, under tension, or when removed. Period changed from 1 to 2 with Rev. 4 to plan.

11548-WMKS-RC-P-lC.2 B-20 2-RC-P-IC B-G-1 B6.180 CCUBICLE 2 UT Comments REACTOR COOLANT PUMP - MAIN FLANGE BOLT. Bolt may be examined in place, under tension, or when removed. Period changed from 1 to 2 with Rev. 4 to plan.

11548-WMKS-RC-P-l C.2 B-21 2-RC-P-IC B-G-1 B6.180 CCUBICLE 2 UT Comments REACTOR COOLANT PUMP - MAIN FLANGE BOLT. Bolt may be examined in place, under tension, or when removed. Period changed from 1 to 2 with Rev. 4 to plan.

11548-WMKS-RC-P-l C.2 B-22 2-RC-P-IC B-G-1 B6.180 CCUBICLE 2 UT Comments REACTOR COOLANT PUMP - MAIN FLANGE BOLT. Bolt may be examined in place, under tension, or when removed. Period changed from 1 to 2 with Rev. 4 to plan.

11548-WMKS-RC-P-l C.2 B-23 2-RC-P-IC B-G-1 B6.180 CCUBICLE 2 UT Comments REACTOR COOLANT PUMP - MAIN FLANGE BOLT. Bolt may be examined in place, under tension, or when removed. Period changed from 1 to 2 with Rev. 4 to plan.

11548-WMKS-RC-P-lC.2 B-24 2-RC-P-IC B-G-1 B6.180 CCUBICLE 2 UT Comments REACTOR COOLANT PUMP - MAIN FLANGE BOLT. Bolt may be examined in place, under tension, or when removed. Period changed from 1 to 2 with Rev. 4 to plan.

11548-WMKS-RC-P-l C.2 LSHB 2-RC-P-IC B-G-2 B7.60 CCUBICLE VT-I Comments REACTOR COOLANT PUMP - LOWER SEAL HOUSING BOLTS. Examine bolts 1 through 4. Bolts may be examined in place, under tension, or when removed. Number of bolts changed with Rev.

6 to plan from 8 bolts to 4 bolts. This change was required when USHB was determined to be non-class & removed from the plan & database, in order to keep examination percentages within Code.

11548-WMKS-RC-P-!C.2 LSHB 2-RC-P-IC B-G-2 B7.60 CCUBICLE 2 VT-!

Comments REACTOR COOLANT PUMP - LOWER SEAL HOUSING BOLTS. Examine bolts 5 through 8. Bolts may be examined in place, under tension, or when removed. Added to plan with Rev. 6 to plan.

This change was required when USHB was determined to be non-class & removed from the plan & database, in order to keep examination percentages within Code.

11548-WMKS-RC-P-IC.2 LSHB 2-RC-P-IC B-G-2 B7.60 CCUBICLE 3 VT-I Comments REACTOR COOLANT PUMP - LOWER SEAL HOUSING BOLTS. Examine bolts 9 through 12. Bolts may be examined in place, under tension, or when removed. Period changed from 2 to 3 with Rev. 6 to plan. This change was required when USHB was determined to be non-class & removed from the plan & database, in order to keep examination percentages within Code.

11548-WMKS-RC-P-!C.2 USHB 2-RC-P-IC CCUBICLE 0 Comments REACTOR COOLANT PUMP - UPPER SEAL HOUSING BOLTS. Examine bolts 1 through 4. Bolts may be examined in place, under tension, or when removed. Removed from the Period 2 of the plan with Rev. 6 to the plan. It has been determined that bolting is non-class. See Rev. 4 to drawing.

11548-WMKS-RC-P-lC.2 USHB 2-RC-P-!C CCUBICLE 0 Comments REACTOR COOLANT PUMP - UPPER SEAL HOUSING BOLTS. Examine bolts 5 through 12. Bolts may be examined in place, under tension, or when removed. Removed from the Period 3 of the plan with Rev. 6 to the plan. It has been determined that bolting is non-class. See Rev. 4 to drawing.

11548-W.MKS-RC-R-l.2 2-RC-R-1 2-RC-R-1 NA NA CONT. -27 2 VT-2 Comments Reactor Vessel Head, Examination Method is a modified VT-2, i.e., RV will not be pressurized. Reference VPAP-1103 with special attention paid for the appearance of boric acid deposits on the external surface of the reactor vessel head at penetrations, which would indicate evidence ofleakage.

Summary of Changes S0rte1I by Dra1'ing and Mark No., SPSU23 Database Page 33 of 46 Print Date: 3// 1198

Dra\\ing No. Mark No. Line Number Category Item No. Location Period Method 11548-WMKS-RC-R-l .2 2-RC-R-I 2-RC-R-I NA NA CONT.-27 2 VT-2 Comments Reactor Vessel Head, Examination Method is a modified VT-2, i.e., RV will not be pressurized. Reference VP AP-I I 03 with special attention paid for the appearance of boric acid deposits on the external surface of the reactor vessel head at penetrations, which would indicate evidence of leakage.

11548-WMKS-RC-R-l.2 2-RC-R-l 2-RC-R-l NA NA CONT.-27 2 VT-2 Comments Reactor Vessel Head, Examination Method is a modified VT-2, i.e., RV will not be pressurized. Reference VP AP-I I 03 with special attention paid for the appearance of boric acid deposits on the external surface of the reactor vessel head at penetrations, which would indicate evidence ofleakage.

11548-WMKS-RC-R-1.2 2-RC-R-l 2-RC-R-1 NA NA CONT.-27 3 VT-2 Comments Reactor Vessel Head, Examination Method is a modified VT-2, i.e., RV will not be pressurized. Reference VP AP-I I 03 with special attention paid for the appearance of boric acid deposits on the external surface of the reactor vessel head at penetrations, which would indicate evidence ofleakage.

11548-WMKS-RC-R-l .2 2-RC-R-l 2-RC-R-l NA NA CONT.-27 3 VT-2 Comments Reactor Vessel Head, Examination Method is a modified VT-2, i.e., RV will not be pressurized. Reference VP AP-I I 03 with special attention paid for the appearance of boric acid deposits on the external surface of the reactor vessel head at penetrations, which would indicate evidence ofleakage.

11548-WMKS-RC-R-l.4 CCW-21 2-RC-R-I B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from I to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-1.4 CCW-22 2-RC-R-I B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from I to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CCW-23 2-RC-R-I B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from I to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-1.4 CCW-24 2-RC-R-1 B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from I to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CCW-25 2-RC-R-I B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from I to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CCW-26 2-RC-R-l B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from I to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CCW-27 2-RC-R-I B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from I to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l .4 CCW-28 2-RC-R-I B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from I to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CCW-29 2-RC-R-I B-G-1 B6.50 CONT.47 2 VT-I Conunents REACTOR VESSEL CLOSURE WAS HERS. Period changed from I to 2 with Rev. 4 to plan.

Sununary of Changes Sorted by Dra\\ing and Mark No., SPSU23 Database Page 34 of 46 Print Dare: 3/1 J/98

Drawing No. Mark No. Line Number Category Item No. Location Period Method 11548-WMKS-RC-R-1.4 CCW-41 2-RC-R-1 B-G-1 B6.50 CONT.47 3 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 2 to 3 with Rev. 4 to plan.

1 I548-WMKS-RC-R-l.4 CCW-42 2-RC-R-I B-G-1 B6.50 CONT.47 3 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 2 to 3 with Rev. 4 to plan.

I I548-WMKS-RC-R-l.4 CCW-43 2-RC-R-I B-G-1 B6.50 CONT. 47 3 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 2 to 3 with Rev. 4 to plan.

I I548-WMKS-RC-R-l.4 CCW-44 2-RC-R-I B-G-I B6.50 CONT.47 3 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 2 to 3 with Rev. 4 to plan.

I I548-WMKS-RC-R-l.4 CCW-45 2-RC-R-I B-G-I B6.50 CONT.47 3 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 2 to 3 with Rev. 4 to plan.

I I548-WMKS-RC-R-l.4 CCW-46 2-RC-R-I B-G-I B6.50 CONT.47 3 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 2 to 3 with Rev. 4 to plan.

I I548-WMKS-RC-R-l.4 CCW-47 2-RC-R-I B-G-I B6.50 CONT.47 3 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 2 to 3 with Rev. 4 to plan.

I I548-WMKS-RC-R-l.4 CCW-48 2-RC-R-I B-G-I B6.50 CONT.47 3 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 2 to 3 with Rev. 4 to plan.

I I548-WMKS-RC-R-l.4 CCW-49 2-RC-R-l B-G-I B6.50 CONT.47 3 VT-1 Comments REACTOR VESSEL CLOSURE WASHERS. Period changed from 2 to 3 with Rev. 4 to plan.

I I548-WMKS-RC-R-l.4 CCW-50 2-RC-R-l B-G-1 B6.50 CONT.47 3 VT-I Conunents REACTOR VESSEL CLOSURE WAS HERS. Period changed from 2 to 3 with Rev. 4 to plan.

I I548-WMKS-RC-R-I.4 CCW-5I 2-RC-R-l B-G-1 B6.50 CONT.47 3 VT-I Conunents REACTOR VESSEL CLOSURE WAS HERS. Period changed from 2 to 3 with Rev. 4 to plan.

I 1548-WMKS-RC-R-l.4 CCW-52 2-RC-R-1 B-G-I B6.50 CONT.47 3 VT-I Conunents REACTOR VESSEL CLOSURE WAS HERS. Period changed from 2 to 3 with Rev. 4 to plan.

1 I548-WMKS-RC-R-l.4 CCW-53 2-RC-R-l B-G-I B6.50 CONT.47 3 VT-I Conunents REACTOR VESSEL CLOSURE WAS HERS. Period changed from 2 to 3 with Rev. 4 to plan.

I 1548-WMKS-RC-R-l.4 CCW-54 2-RC-R-I B-G-I B6.50 CONT. 47 3 VT-I Conunents REACTOR VESSEL CLOSURE WASHERS. Period changed from 2 to 3 with Rev. 4 to plan.

Sununary of Changes Sorted by Dra'l'ing and Mark No., SPSU23 Database Page 35 of 46 Print Date: 3/11198

Drawing No. Mark No. Line Nwnber Category Item No. Location Pe1iod Method 11548-WMKS-RC-R-1.4 CCW-55 2-RC-R-1 B-G-1 B6.50 CONT. 47 3 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 2 to 3 with Rev. 4 to plan.

1J 548-WMKS-RC-R-1.4 CCW-56 2-RC-R-1 B-G-1 B6.50 CONT. 47 3 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 2 to 3 with Rev. 4 to plan.

11548-WMKS-RC-R-1.4 CCW-57 2-RC-R-l B-G-1 B6.50 CONT. 47 3 VT-I Conunents REACTOR VESSEL CLOSURE WASHERS. Period changed from 2 to 3 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CCW-58 2-RC-R-1 B-G-1 B6.50 CONT. 47 3 VT-I Conunents REACTOR VESSEL CLOSURE WAS HERS. Period changed from 2 to 3 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-01 2-RC-R-I B-G-1 B6.50 CONT. 47 VT-I Comments REACTOR VESSEL CLOSURE WASHERS. Period changed from 2 to 1 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-02 2-RC-R-1 B-G-1 B6.50 CONT. 47 VT-I Conunents REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to I with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-03 2-RC-R-1 B-G-1 B6.50 CONT.47 VT-I Comments REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to I with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-04 2-RC-R-1 B-G-1 B6.50 CONT. 47 VT-I Comments REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to 1 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-05 2-RC-R-1 B-G-1 B6.50 CONT. 47 VT-I Comments REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to I with Rev. 4 to plan.

11548-WMKS-RC-R-1.4 CVW-06 2-RC-R-1 B-G-1

B6.50 CONT. 47 VT-I Conmwnts REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to 1 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-07 2-RC-R-1 B-G-1 B6.50 CONT. 47 VT-I Co nunen ts REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to 1 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CV\V-08 2-RC-R-1 B-G-1 B6.50 CONT. 47 VT-I Conm1ents REACTOR VESSEL CLOSURE WAS HERS. Period changed from 3 to I with Rev. 4 to plan.

11548-WMKS-RC-R-1.4 CVW-09 2-RC-R-l B-G-1 B6.50 CONT. 47 VT-I Conm1ents REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to I with Rev. 4 to plan.

11548-\VMKS-RC-R-1.4 CV\V-10 2-RC-R-l B-G-1 B6.50 CONT. 47 VT-I Conm1ents REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to I with Rev. 4 to plan.

Summary of 01anges Sorted by Dra\\ing and Mark No., SPSU23 Database Page 36 of 46 Print Date: 3/11198

Drawing No. MarkNo. Line Number Category Item No. Location Period Method 11548-WMKS-RC-R-1.4 CVW-11 2-RC-R-I B-G-1 B6.50 CONT.47 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 3 to I with Rev. 4 to plan.

11548-WMKS-RC-R-1.4 CVW-12 2-RC-R-I B-G-1 B6.50 CONT.47 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 3 to I with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-13 2-RC-R-1 B-G-1 B6.50 CONT. 47 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 3 to I with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-14 2-RC-R-l B-G-1 B6.50 CONT.47 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 3 to I with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-15 2-RC-R-I B-G-1 B6.50 CONT.47 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 3 to I with Rev. 4 to plan.

11548-WMKS-RC-R-1.4 CVW-16 2-RC-R-l B-G-1 B6.50 CONT.47 VT-I Comments REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to I with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-17 2-RC-R-l B-G-1 B6.50 CONT.47 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 3 to l with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-18 2-RC-R-l B-G-1 B6.50 CONT.47 VT-1 Comments REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to i with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-19 2-RC-R-l B-G-1 B6.50 CONT.47 VT-I Comments REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to 1 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-20 2-RC-R-l B-G-1 B6.50 CONT. 47 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 3 to 1 with Rev. 4 to plan.

11548-WMKS-RC-R-1.4 CVW-21 2-RC-R-l B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-1.4 CVW-22 2-RC-R-l B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-23 2-RC-R-l B-G-1 B6.50 CONT. 47 2 VT-I Conunents REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-24 2-RC-R-l B-G-1 B6.50 CONT. 47 2 VT-I Comments REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to 2 with Rev. 4 to plan.

Summary of Changes Sorted by Dra""ing and Mark No., SPSU23 Database Page 37 of 46 Print Date: 3111/98

Drawing No. MarkNo. Line Number Category Item No. Location Period Method 11548-WMKS-RC-R-l .4 CVW-25 2-RC-R-l B-G-1 B6.50 CONT.47 2 VT-1 Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 3 to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-26 2-RC-R-l B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 3 to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-27 2-RC-R-l B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-28 2-RC-R-l B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 3 to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-29 2-RC-R-l B-G-1 B6.50 CONT.47 2 VT-1 Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 3 to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l .4 CVW-30 2-RC-R-l B-G-1 B6.50 CONT.47 2 VT-1 Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 3 to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-31 2-RC-R-l B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 3 to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-32 2-RC-R-1 B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from _3 to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-33 2-RC-R-1 B-G-1 B6.50 CONT.47 2 VT-1 Comments REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-1.4 CVW-34 2-RC-R-l B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 3 to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-35 2-RC-R-1 B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 3 to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-36 2-RC-R-1 B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-37 2-RC-R-1 B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 3 to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 CVW-38 2-RC-R-1 B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WAS HERS. Period changed from 3 to 2 with Rev. 4 to plan.

Sununary of Changes Sorted by Draning and Mark No., SPSU23 Database Page 38of 46 Print Date: 3111198

Dra'l'ling No. Mark No. Line Number Category Item No. Location Period Method 11548-WMKS-RC-R-l.4 CVW-39 2-RC-R-1 B-G-1 B6.50 CONT.47 2 VT-I Conunents REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-1.4 CVW-40 2-RC-R-1 B-G-1 B6.50 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE WASHERS. Period changed from 3 to 2 with Rev. 4 to plan.

11548-WMKS-RC-R-l.4 NUT-21 2-RC-R-1 B-G-1 B6.IO CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-22 2-RC-R-l B-G-1 B6.IO CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUL New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-23 2-RC-R-1 B-G-1 B6.10 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-24 2-RC-R-1 B-G-1 B6.IO CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-25 2-RC-R-1 B-G-1 B6.IO CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-1.4 NUT-26 2-RC-R-1 B-G-1 B6.IO CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-27 2-RC-R-l B-G-1 B6.10 CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-1.4 NUT-28 2-RC-R-1 B-G-1 B6.IO CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-29 2-RC-R-1 B-G-1 B6.IO CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-30 2-RC-R-1 B-G-1 B6.IO CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-31 2-RC-R-1 B-G-1 B6.10 CONT. 47 2 VT-I Conunents REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-W:MKS-RC-R-l.4 NUT-32 2-RC-R-I B-G-1 B6.IO CONT.47 2 VT-I Conunents REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

Summary of Changes Sorted by Dra'l'ling and Mark No., SPSU23 Database Page 39of 46 Print Date: 3/11198

Drawing No. Mark No. Line Number Category Item No. Location Period Method 11548-WMKS-RC-R-l.4 NUT-33 2-RC-R-l B-G-1 B6.IO CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-34 2-RC-R-l B-G-1 B6.10 CONT.47 2 VT-1 Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-1 per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-35 2-RC-R-l B-G-1 B6.IO CONT.47 2 VT-1 Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-1 per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-36 2-RC-R-l B-G-1 B6.IO CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-37 2-RC-R-I B-G-1 B6.IO CONT.47 2 VT-1 Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-1 per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-38 2-RC-R-l B-G-1 B6.10 CONT.47 2 VT-1 Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-39 2-RC-R-I B-G-1 B6.IO CONT.47 2 VT-1 Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-1 per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-40 2-RC-R-l B-G-1 B6.IO CONT.47 2 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-41 2-RC-R-I B-G-1 B6.IO CONT.47 3 VT-1 Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-42 2-RC-R-I B-G-1 B6.IO CONT.47 3 VT-1 Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-1 per Relief Request SR-025.

11548-WMKS-RC-R-1.4 NUT-43 2-RC-R-1 B-G-1 B6.IO CONT. 47 3 VT-1 Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-1 per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-44 2-RC-R-I B-G-1 B6.IO CONT.47 3 VT-1 Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: M_ethod changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-45 2-RC-R-l B-G-1 B6.IO CONT.47 3 VT-1 Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-46 2-RC-R-1 B-G-1 B6.IO CONT. 47 3 VT-I Conunents REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

Summary of Changes Sor1ed by Dral\ing and Mark No., SPSU23 Database Page 40of 46 Print Date: 3/J 1198

Drawing No. Mark No. Line Number Category Item No. Location Period Method 11548-WMKS-RC-R-l.4 NUT-47 2-RC-R-I B-G-1 B6.IO CONT.47 3 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-48 2-RC-R-1 B-G-1 B6.IO CONT. 47 3 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-49 2-RC-R-I B-G-1 B6.IO CONT. 47 3 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-50 2-RC-R-1 B-G-1 B6.10 CONT.47 3 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT- I per Relief Request SR-025.

11548~\VMKS-RC-R-l .4 NUT-51 2-RC-R-l B-G-1 B6.10 CONT. 47 3 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-52 2-RC-R-1 B-G-1 B6.IO CONT.47 3 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-1 per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-53 2-RC-R-1 B-G-1 B6.IO CONT.47 3 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-1 per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-54 2-RC-R-1 B-G-1 B6.IO CONT. 47 3 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-1 per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-55 2-RC-R-1 B-G-1 B6.10 CONT.47 3 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l .4 NUT-56 2-RC-R-I B-G-1 B6.10 CONT. 47 3 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-1.4 NUT-57 2-RC-R-I B-G-1 B6.IO CONT.47 3 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RC-R-l.4 NUT-58 2-RC-R-1 B-G-1 B6.10 CONT. 47 3 VT-I Comments REACTOR VESSEL CLOSURE HEAD NUT. New with Rev. 9 to plan: Method changed from MT to VT-I per Relief Request SR-025.

11548-WMKS-RS-P-2A 2-01 2-RS-P-2A C-G C6.10 SAFEGUARDS 0 VT-I Comments RECIRC SPRAY PUMP- CASING WELD, (WECCAS). Weld is inaccessible (buried in concrete). Per relief request (SR-004) perform a remote visual examination of the accessible portions of the l.D.

of the pump casing welds, if the pump is disassembled, and the pump shaft is removed. New with Rev. 9: Removed from the plan at the completion of period I because the examination was not perfonned during the period.

Summary of Changes Sorted by Dra"ing and Mark No., SPSU23 Database Page 41 of 46 Print Date: 3/11/98

Dra'l\ing No. Mark No. Line Number Category Item No. Location Period Method l 1548-WMKS-RS-P-2A 2-02 2-RS-P-2A C-G C6.IO SAFEGUARDS 0 VT-!

Comments RECIRC SPRAY PUMP- CASING WELD, (WECCAS). Weld is inaccessible (buried in concrete). Per relief request (SR-004) perform a remote visual examination of the accessible portions of the l.D.

of the pump casing welds, if the pump is disassembled, and the pump shaft is removed. New with Rev. 9: Removed from the plan at the completion of period I because the examination was not perfonned during the period.

I I548-WMKS-RS-P-2A 2-03 2-RS-P-2A C-G C6.I0 SAFEGUARDS 0 VT-I Comments RECIRC SPRAY PUMP- CASING WELD, (WECCAS). Weld is inaccessible (buried in concrete). Per reliefrequest (SR-004) perform a remote visual examination ofthe accessible portions ofthe l.D.

of the pump casing welds, if the pump is disassembled, and the pump shaft is removed. New with Rev. 9: Removed from the plan at the completion of period l because the examination was not pcrfom1ed during the period.

l 1548-WMKS-RS-P-2A 2-04 2-RS-P-2A C-G C6.I0 SAFEGUARDS 0 VT-!

Comments RECIRC SPRAY PUMP - CASING WELD, (WECCAS). Weld is inaccessible (buried in concrete). Per re!iefrequest (SR-004) perfonn a remote visual examination of the accessible portions of the l.D.

of the pump casing welds, if the pump is disassembled, and the pump shaft is removed. New with Rev. 9: Removed from the plan at the completion of period l because the examination was not performed during the period.

l !548-WMKS-RS-P-2B 2-01 2-RS-P-2B C-G C6.I0 SAFEGUARDS 0 VT-!

Comments RECIRC SPRAY PUMP- CASING WELD, (WECCAS). Weld is inaccessible (buried in concrete). Per Relief Request (SR-004) perform a remote visual examination of the accessible portions of the l.D. of the pump casing welds, if the pump is disassembled, and the pump shaft is removed. New with Rev. 9: Removed from the plan at the completion of period I because the examination was not performed during the period.

l 1548-WMKS-RS-P-2B 2-02 2-RS-P-2B C-G C6.I0 SAFEGUARDS 0 VT-I Comments RECIRC SPRAY PUMP - CASING WELD, (WECCAS). Weld is inaccessible (buried in concrete). Per Relief Request (SR-004) perform a remote visual examination of the accessible portions of the l.D. of the pump casing welds, if the pump is disassembled, and the pump shaft is removed. New with Rev. 9: Removed from the plan at the completion of period I because the examination was not performed during the period.

I I 548-WMKS-RS-P-2B 2-03 2-RS-P-2B C-G C6.IO SAFEGUARDS 0 VT-I Comments RECIRC SPRAY PUMP- CASING WELD, (WECCAS). Weld is inaccessible (buried in concrete). Per Relief Request (SR-004) perform a remote visual examination of the accessible portions of the I.D. of the pump casing welds, if the pump is disassembled, and the pump shaft is removed. New with Rev. 9: Removed from the plan at the completion of period I because the examination was not performed during the period.

I I548-WMKS-RS-P-2B 2-04 2-RS-P-2B C-G C6.IO SAFEGUARDS 0 VT-I Comments RECIRC SPRAY PUMP- CASING WELD, (WECCAS). Weld is inaccessible (buried in concrete). Per Relief Request (SR-004) perform a remote visual examination of the accessible portions of the l.D. of the pump casing welds, if the pump is disassembled, and the pump shaft is removed. New with Rev. 9: Removed from the plan at the completion of period I because the exan1ination was not performed during the period.

I I548-WMKS-SI-l 0-04 !2"-SI-201-153 C-F-1 CS.II SAFEGUARDS 0 lIT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). This weld removed from plan with Rev. 3 to plan. This weld replaced with weld 0-05 on the same line No. & drawing No. This weld was removed from the plan because J. Dalton stated that it could not be examined by UT due to configuration.

l I548-WMKS-SI-l 0-05 12"-SI-201-153 C-F-1 CS.II SAFEGUARDS UT/PT Cornments CIRCUMFERENTIAL PIPING WELD, (WEPCB). This weld added to plan with Rev. 3 to plan & replaces weld 0-04 on the same line No. & drawing No.

l I548-Wl\IKS-SI-l 0-14 I 2"-SI-202-153 C-F-1 CS.II SAFEGUARDS 0 UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). This weld removed from plan with Rev. 3 to plan. TI1is weld replaced with weld 0-16 on the same line No. & drawing No. TI1is weld was removed from the plan because J. Dalton stated that it could not be examind by UT due to configuration.

11548-WMKS-SI-I 0-16 12"-SI-202-I53 C-F-1 C5.ll SAFEGUARDS UT/PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). TI1is weld added to plan with Rev. 3 to plan & replaces weld 0-14 on the same line No. & drawing No.

Sununary of Changes Sorted by Drm\ing and Mark No., SPSU23 Database Page 42 of 46 Print Date: 3/11198

Drawing No. Mark No. Line Nwnber Category Item No. Location Period Method 11548-WMKS-SI-IO 0-09 3"-SI-270-1503 C-F-1 C5.21 AUX.BLDG. 0 UT/PT Comments Circumferential Piping Weld, (WEPCB). This weld removed from plan with Rev. 7 to the plan. This weld replaced with weld 0-11 on the same line No. & drawing No.

11548-WMKS-SI-10 0-10 3"-SI-270-1503 C-F-1 C5.21 AUX.BLDG. 0 UT/PT Comments Circumferential Piping Weld, (WEPCB). This weld removed from plan with Rev. 7 to the plan. This weld replaced with weld 0-12 on the same line No. & drawing No.

11548-WMKS-SI-10 0-11 3 "-SI-270-1503 C-F-1 C5.21 AUX.BLDG. UT/PT Comments Circumferential Piping Weld, (WEPCB). This weld added to the plan with Rev. 7 to the plan. This weld replaces with weld 0-09 on the same line No. & drawing No.

11548-WMKS-SI-10 0-12 3 "-SI-270-1503 C-F-1 C5.21 AUX.BLDG. UT/PT Comments Circumferential Piping Weld, (WEPCB). TI1is weld added to the plan with Rev. 7 to the plan. This weld replaces with weld 0-10 on the same line No. & drawing No.

11548-WMKS-SI-12A 2-05 3"-Sl-272-1503 C-F-1 C5.21 AUX.BLDG. 2 UT/PT Comments Circumferential Piping Weld, (WEPCB). New with Rev. 9 to plan: This weld (2-05) added to the plan to replace weld 2-07 on the same line and drawing number because weld :i-07 is covered by a support and is inaccessible for examination.

11548-WMKS-SI-12A 2-07 3"-Sl-272-1503 C-F-1 C5.21 AUX.BLDG. 0 UT/PT Comments Circumferential Piping Weld, (WEPCB). New with Rev. 9 to plan: This weld removed from the plan and replaced with weld 2-05 on the same line anidrawing number because weld 2-07 is covered by a support and is inaccessible for examination.

11548-WMKS-SI-2 1-12 3"-SI-270-1503 C-F-1 C5.21 CONT. -3 UT/PT Comments Circumferential Piping Weld, (WEPCB). PT exam completed on 2-28-95 with I 00% coverage & NRI. UT examination needs to be performed during the 1996 refueling outage in order to complete the period requirements.

11548-WMKS-Sl-2 2-33 2"-Sl-276-1503 C-F-1 C5.30 CONT. -27 PT Comments SOCKET Weld, (WEPSOK). Per change 6 to Rev. 7 to the plan: this weld added to replace weld 2-35 on the same line & drawing No.

11548-WMKS-SI-2 2-35 2"-SI-276-1503 C-F-1 C5.30 CONT. -27 0 PT Comments SOCKET Weld, (WEPSOK). Per change 6 to Rev.7 of the plan: This weld removed from the plan & replaced with weld 2-33 on the same line & drawing No.

11548-WMKS-SI-3 1-17 3"-Sl-272-1503 B-J 89.21 CONT. -27 PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Removed from TS Item 2.1.1 with Rev. 3 to drawing, which eliminated sensitized piping piece 17. Change effective with Rev. 5 to plan.

11548-WMKS-SI-3 1-19 3 "-SI-272-1503 B-J 89.21 CONT. -27 2 PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Removed from TS Item 2.1. l with Rev. 3 to drawing, which eliminated sensitized piping piece 17. Change effective with Rev. 5 to plan ..

11548-WMKS-SI-3 1-20 3 "-SI-272-1503 B-J B9.21 CONT. -27 2 PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Removed from TS Item 2.1. l with Rev. 3 to drawing, which eliminated sensitized piping piece 17. Change effective with Rev. 5 to plan ..

11548-WMKS-SI-3 1-22 3"-Sl-272-1503 B-J 89.21 CONT. -27 0 PT Comments CIRCUMFERENTIAL PIPING WELD, (WEPCB). Removed from TS Item 2.1. l with Rev. 3 to drawing, which eliminated sensitized piping piece 17. Change effective with Rev. 5 to plan.

11548-WMKS-SI-3 1-23 3"-Sl-272-1503 B-J 89.21 CONT. -27 3 PT Comments CIRCUi\ffERENTIAL PIPING WELD, (WEPCB). Removed from TS Item 2.1.1 with Rev. 3 to drawing, which eliminated sensitized piping piece 17. Change effective with Rev. 5 to plan.

Summary of Changes Sorted by Drawing and Mark No., SPSU23 Database Page 43 of 46 Print Date: 3/11198

Dmwing No. Mark No. Line Number Category Item No. Location Period Method 11548-WMKS-SI-36 1-41 2"-SI-277-1503 8-J 89.40 CONT. -27 0 PT Conunents SOCKET WELD, (WEPSOK). Removed from TS Item 2.1.1 with Rev. 3 to drawing, which eliminated ssensitized piping piece 95. Change effective with Rev. 5 to plan.

11548-WMKS-SI-36 1-42 2"-SI-277-1503 B-J B9.40 CONT. -27 PT Comments SOCKET WELD, (WEPSOK). Removed from TS Item 2.1.1 with Rev. 3 to drawing, which eliminated sensitized piping piece 95. Change effective with Rev. 5 to plan.

11548-WMKS-SI-P-lA 2-01 2-SI-P-IA C-G C6.10 SAFEGUARDS 0 VT-!

Conunents LOW HEAD SAFETY INJECTION PUMP - CASING WELD, (WECCAS). Weld is inaccessible, (buried in concrete). Per Relief Request (SR-004) perform a remote visual examination of the accessible portions of the I.D. of the pump casing welds, if the pump is disassembled, and the pump shaft is removed. New with Rev. 9: Removed from the plan at the completion of period I because the examination was not performed during the period.

11548-WMKS-SI-P-IA 2-02 2-SI-P-IA C-G C6.I0 SAFEGUARDS 0 VT-1 Comments LOW HEAD SAFETY INJECTION PUMP-CASING WELD, (WECCAS). Weld is inaccessible, (buried in concrete). Per Relief Request (SR-004) perform a remote visual examination of the accessible portions of the I.D. of the pump casing welds, if the pump is disassembled, and the pump shaft is removed. New with Rev. 9: Removed from the plan at the completion of period 1 because the examination was not performed during the period 11548-WMKS-SI-P-lA 2-03 2-SI-P-lA C-G C6.10 SAFEGUARDS 0 VT-1 Comments LOW HEAD SAFETY INJECTION PUMP - CASING WELD, (WECCAS). Weld is inaccessible, (buried in concrete). Per Relief Request (SR-004) perform a remote visual examination of the accessible portions of the I.D. of the pump casing welds, if the pump is disassembled, and the pump shaft is removed. New with Rev. 9: Removed from the plan at the completion of period 1 because the examination was not performed during the period.

11548-WMKS-Sl-P-IA 2-04 2-SI-P-!A C-G C6.10 SAFEGUARDS 0 VT-1 Comments LOW HEAD SAFETY INJECTION PUMP - CASING WELD, (WECCAS). Weld is inaccessible, (buried in concrete). Per Relief Request (SR-004) perform a remote visual examination of the accessible portions of the I.D. of the pump casing welds, if the pump is disassembled, and the pump shaft is removed. New with Rev. 9: Removed from the plan at the completion of period 1 because the examination was not performed during the period.

11548-WMKS-WAPD-2 HOOl-1 6"-WAPD-150-601 D-B D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (HOO 1). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-WAPD-2 H003-1 6"-WAPD-152-601 D-8 D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATT ACHED WELD, (H003 ). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Conunitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

I 1548-WMKS-WAPD-2 H003-2 6"-WAPD-152-601 D-B D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H003). Category & Item No. changed with Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-WAPD-2 H003-3 6"-WAPD-152-601 D-B D2.20 MSVH 0 VT-3 Comments INTEGRALLY ATTACHED WELD, (H003). Category & Item No. changed with Rev. 7 to Plan to ensure that tl1e site pressure test database and the corporate component database match. 111e corporate database was changed tci agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

11548-WMKS-WAPD-2 H003-4 6"-WAPD-152-601 D-B D2.20 MSVH 0 VT-3 Conunents INTEGRALLY ATTACHED WELD, (H003). Category & Item No. changed witl1 Rev. 7 to Plan to ensure that the site pressure test database and the corporate component database match. The corporate database was changed to agree with the site database. Commitment No 96-074 applies & the only changes made were to Class 3 integral attachments.

Incore Del Tinn Tubes 2-RC-R-l NA NA CONT. 47 2 ET Comments Perform 100% ET of all thimble tubes. Reactor Vessel Incore Detector 111imble Tubes. Added with Rev. 7 to the plan, to cover tl1e refueling outage scheduled in year 2000 and in period 2.

Summary of Changes Sorted by Dm\\ing and Mark No., SPSU23 Database Page 44 of 46 Print Date: 3/l //98

Drawing No. Mark No. Line Nwnber Category Item No. Location Period Method LP Turbine Disc LP Turbine Rotor I Rotor No. TD-50654 NA NA TURBINE 2 UT Conunents UT Examine Low Pressure Turbine Disc Bore and Keyway Area. 5 year exam. Last examination performed during 1993 refueling outage. Unit start up date was 5-6-93 per Ltr.93-318. In order to sch.

UT of discs with surface exams, request an extension from Westinghouse on the UT exams until the 1999 outage. New with Rev. 7 to the plan: Per Tel-Con with John Patrick on 1-15-97, he plans to install the recently refurbished spare rotors into Unit 2 during tl1e 1997 refueling outage. New with Rev. 9 to the Plan: Changed year to 1999 because Westinghouse has allowed an extension of up to 72 months for the UT examination. Ref. Field Action Request (FAR) 7-SU-3 294-069.

LP Turbine Disc LP Turbine Rotor 2 Rotor No. TD-50655 NA NA TURBINE 2 UT Comments UT Examine Low Pressure Turbine Disc Bore and Keyway Area. 5 year exam. Last examination perfom1ed during 1993 refueling outage. Unit start up date was 5-6-93 per Ltr.93-318. In order to sch.

UT of discs witl1 surface exams, request an extension from Westinghouse on the UT exams until the 1999 outage. New with Rev. 7to the plan: Per Tel-Con with John Patrick on 1-15-97, he plans to install the recently refurbished spare rotors into Unit 2 during the 1997 refueling outage. New wiili Rev. 9 lo the Plan: Changed year to 1999 because Westinghouse has allowed an extension of up to 72 months for the UT examination. Ref. Field Action Request (FAR) 7-SU-3294-069.

LP Turbine Rotor LP Turbine Rotor I Rotor No. TD-50654 NA NA TURBINE 2 VT/MT/PT Comments VT/MT or VT/PT I 00% of Low Pressure Turbine Rotor Blades. 6 operating year exam. Last exam. performed during 1993 refueling outage. Unit start up date is 5-6-93 per Ltr.93-318. In order to schedule UT of discs with surface exams, request an extension from Westinghouse on the UT exams until tl1e 1999 refueling outage. New wiili Rev. 7 to the plan: Per Tel-Con wiili John Patrick on 1 97, he plans to install the recently refurbished spare rotors into Unit 2 during tile 1997 refueling outage. New with Rev. 9 to the Plan: Changed year to 1999 because Westinghouse has allowed an extension ofup to 72 months for the UT examination. Ref. Field Action Request (FAR) 7-SU-3294-069.

LP Turbine Rotor LP Turbine Rotor 2 Rotor No. TD-50655 NA NA TURBINE 2 VT/MT/PT Comments VT/MT or VT/PT I 00% of Low Pressure Turbine Rotor Blades. 6 operating year exam. Last exam. performed during 1993 refueling outage. Unit start up date is 5-6-93 per Ltr.93-318. In order to schedule UT of discs witl1 surface exams, request an extension from Westinghouse on the UT exams until the 1999 refueling outage. New with Rev. 7 to tl1e plan: Per Tel-Con with John Patrick on 1 97, he plans to install the recently refurbished spare rotors into Unit 2 during the 1997 refueling outage. New with Rev. 9 to the Plan: Changed year to 1999 because Westinghouse has allowed an extension ofup to 72 months for the UT examination. Ref. Field Action Request (FAR) 7-SU-3294-069.

Special Lift Devices Special Lift Devices NA NA CONT. 47 Surface Comments Added New To Plan With Revision 6, Change No. 3 to complete Interval 2 requirements: Examine Special Lifting Devices: Reactor Coolant Pump Motor Lift Sling Welds. Reference WCAP-10228 dated January 1983, Table A-5 on page A-11 and Figure A-3 on page A-12. This change will be printed in the next revision to the plan and will show as Revision 7 to the plan.

Special Lift Devices Special Lift Devices NA NA FB 2 MT Comments Added New To Plan With Revision 8: Examine Special Lifting Devices: Spent Fuel Pool Transfer Canal Gate Alternate Lift Rig. Reference memorandum from Design Engineering, J.D. MacCrimmon of February 5, 1997, which identifies critical welds. Year examination is due is 1997. The acoustic emission (AE) method may be used in lieu of, or in addition to surface examination. Also see UFSAR Appendix 9B.

Special Lift Devices Special Lift Devices NA NA CONT.47 3 AE Comments Examine Special Lifting Devices By End oflnterval. Added wiili Rev. 7 to plan: Special lifting devices are defined as the: Reactor Vessel Head Lift Rig, Reactor Vessel Internals Lift Rig and Reactor Coolant Pump Motor Lift Rig. These lift rigs and their critical parts and welds are listed in WCAP-10228 (January-1983) in Tables A-1 through A-5, and shown in figures A-I through A-3.

VIR-l-5100B 02-RC-P-IA Serial No. 1S-D012 NA NA A CUBICLE 2 UT/PT Conunents PT bore & complete UT volumetric examination. Flywheel must be re-moved. 10 year examination. Added with Rev. 6 to plan due to this flyv,heel being installed into the "C" location during the 1995 forced outage: Last examination performed at Cheswick, PA as baseline examination. The flywheel was installed new into Unit I "C" during the 1990 outage, therefore the l O year examination is due in tl1e year 2000. New with Rev. 7 to the plan: The flywheel was installed into Unit 2 "A" location during the 1996 refueling outage.

VIR-l-5100B 02-RC-P-IA Serial No. 1S-DOl2 NA NA A CUBICLE 2 UT Comments UT bore & keyway. Flywheel may be removed, or in-place. 3 year examination. New with Rev. 9 to plan: Last examination performed on I 0-12-97. TI1e flywheel was installed into the Unit 2 "C" location during the 11-95 forced outage. Prior to that, it was the spare. The flywheel was installed into the "A" pump location during the 1996 refueling outage.

VIR-l-5100B 02-RC-P-IA Serial No. 1S-D012 NA NA ACUBICLE 2 UT Comments UT bore & keyway. Flywheel may be removed, or in-place. 3 year examination. New with Rev. 6 to plan. Last examination performed on 2-3-94. TI1e flywheel was installed into the Unit 2 "C" location during the 11-95 forced outage. Prior to that, it was the spare. New with Rev. 7 to the plan: The flywheel was installed into the "A" pump location during the 1996 refueling outage.

Sununary of Changes Sorted by Dra"l\ing and Mark No., SPSU23 Database Page 45 of 46 Print Date: 3111/98

Drawing No. Mark No. Line Number Category Item No. Location Period Method VIR-1-5 IOOB 02-RC-P-IB Serial No. l S-76P049 NA NA BCUBICLE 2 UT/PT Comments UT bore & keyway. Flywheel may be removed, or in-place. 3 year examination. Came out ofU-1 "B" during the 1994 outage & designated as "spare" until installed in the "B" location during the 1995 refueling outage. The 3 & 10 year examinations were completed on 8-24-94 at the station. However, the unit did not return to service until 3-21-95 (per operations logs), therefore, examinations will be tracked from the unit run time start date of3-2 J-95. New with Rev. 9 to plan: Last three year examination performed on 10-12-97 during the 1997 refueling outage.

VIR-1-5 lOOB 02-RC-P-IB Serial No. l S-76P049 NA NA B CUBICLE 2 UT Comments UT bore & keyway. Flywheel may be removed, or in-place. 3 year examination. Came out ofU-1 "B" during the 1994 outage & designated as "spare" until installed in the "B" location during the 1995 refueling outage. The 3 & 10 year examinations were completed on 8-24-94 at the station. However, the unit did not return to service until 3-21-9 5 (per operations logs), therefore, examinations will be tracked from the unit run time start date of3-21-95. The three year exam is scheduled in 1997 because there is presently no outage scheduled in 1998 and if scheduled in 1999 the examination would have to be extended by a year, which would require a TS change.

VIR-1-5100B 02-RC-P-lC Serial No. 2S-77P314 NA NA CCUBICLE UT Comments UT bore & keyway. Flywheel may be re-moved, or in-place. 3 year examination. Last examined at Cheswick., PA on 3-7-91. Unit did not return to service until 6-7-91, therefore, exam. is tracked from run time start date of6-7-9l. New with Rev. 5: FLYWHEEL MOVED FROM "A" PUMP TO "C" PUMP IN FEB. 1995 REFUELING.

VIR-1-5100B 02-RC-P-!C Serial No. 3S-76P049 NA NA CCUBlCLE 2 UT Comments New with Rev. 9: UT bore & keyway. Flywheel may be re-moved, or in-place. 3 year examination. Last examination perforn1ed on 6-19-97 when this flywheel was the spare prior to the Unit 2 1997 refueling outage. Installed in the "C" pump location during the 1997 refueling outage.

VIR-l-5100B None Serial No. 3S-76P049 NA NA SPARE 2 UT Comments UT bore & keyway. Flywheel may be removed, or in-place. 3 year examination. New with Rev. 8 to plan: Removed from the Unit I "A" location during the 1997 refueling outage & became the spare, the three year examination (UT in place) must be performed prior to reinstalling into the planl VIR-l-5100B None Serial No. 3S-76P049 NA NA SPARE 2 UT/PT Comments PT bore & complete UT volumetric examination. Flywheel must be removed. IO year examination. New with Rev. 8 to plan: Removed from the Unit I "A" location during the 1997 refueling outage &

became the spare.

VIR-1-5100B None Serial No. 2S-77P314 NA NA SPARE 2 UT Conunents New with rev. 7 to the plan: UT bore & keyway. Flywheel may be re-moved, or in-place. 3 year examination. Last 3 year examination was performed on 2-12-95. Unit did not return to service until 3 95, therefore, exam. is tracked from run time start date of3-21-95. FLYWHEEL MOVED FROM "A" PUMP TO "C" PUMP IN FEB. 1995 REFUELING. The flywheel was removed from Unit 2 "C" during the 1995 forced outage & became the spare. The flywheel was installed into the Unit 2 "C" location during the 1996 refueling outage. New with Rev. 9 to the plan: Removed from the Unit 2 "C" location during the 1997 refueling outage & became the spare, the three year examination (UT) must be performed prior to reinstalling into the plant.

VIR-1-5 !00B None Serial No. 2S-77P3 l4 NA NA SPARE 3 UT/PT Comments New with Rev. 7 to the plan: PT bore & complete UT volumetric examination. Flywheel must be removed. 10 year examination. The last 10 year examinations was completed on 3-7-91 at Cheswick.,

PA. However, the unit did not return to service until 6-7-91, therefore, examinations will be tracked from tl1e unit run time start date of 6-7-91. New with Rev. 9 to the plan: Removed from the Unit 2 "C" location during the 1997 refueling outage & became the spare.

Record Count: 554 Sununary of Changes Sorted by Dra~ing and Mark No., SPSU23 Database Page 46 of 46 Print Dote: 311 J/98

ML18151A245

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1.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

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