ML20063P912

SAIC-88/1943, Technical Evaluation Rept,First Interval Inservice Insp Program,Mcguire Nuclear Station Units 1 & 2

ML20063P912
Person / Time
Site:	Mcguire, McGuire
Issue date:	10/31/1989
From:	SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY
To:	NRC
Shared Package
ML20063P913	List: ML20063P912
References
CON-FIN-D-1311, CON-NRC-03-87-029, CON-NRC-3-87-29 SAIC-88-1943, NUDOCS 8911160160
Download: ML20063P912 (73)

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.e TECHNICAL EVALUATION REPORT.

FIRST INTERVAL INSERVICE INSPECTION PROGRAM MCGUIRE NUCLEAR STATION UNITS 1 AND~2 l l

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L-SAIC 88/1943 l- i l

l l- -TECHNICAL EVALUATION REPORT FIRST INTERVAL' INSERVICE INSPECTION PROGRAM MCGUIRE NUCLEAR STATION UNITS 1 AND 2 1

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' Submitted to U.S. Nuclear Regulatory Comission Contract No. 03-87-029 1 1

Submitted by Science Applications International Corporation

. Idaho Falls Idaho 83402 J

L October.1989 L

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l CONTENTS I

1. INTRODUCTION . . . . . . . . . . . . . . . . .:. . . . . . 1 i

2. EVALUATION OF INSERVICE INSPECTION PLAN .......... .

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2.1 Introduction ..................... -3 1

2.2 Documents Evaluated . . . . . . . . . . . . . . . . . .

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2.3 Summary of Requirements . . . .-. . . . . . . . .-. . . 3 2.3.1 Code Requirements . . . . . . . . . . . . . . 4 1

2.3.1.1 Class 1 Requirements ......_..... _4 I 2.3.1.2 Class 2 Requirements ............ 5 l

2.3.1.3 Class 3 Requirements ............. 5 y 2.3.1.4' Component Supports ............. 5 2.3.2 License Conditions ............. 5 2.4 Compliance with Requirements ............. 6 2.4.1 Applicable-Code Edition . . . . . . . . . . . 6 2.4.2- Code Requirements . . . . . . . . . . . . . . 7 2.4.3 Preservice Inspection Commitments . . . . . . 9 h i 2.5 Conclusions and Recommendations . . . . . . . . .'. . .

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3. REQUESTS FOR RELIEF FROM ASME CODE SECTION XI

, EXAMINATION REQUIREMENTS . . . . . . . . . . . . . . . . .-. 12 3.1 Class 1 Components (no relief requests) 3.2 Class 2 Components .................. 13 3.2.1 - Pressure Vessels and Heat Exchangers .... 13  ;

3.2.1.1 Relief Request No. 88-08, Safety Injection Accumulator Tank Shell-to-Lower Head Weld, Category C-A, Item C1.10 . . . . . 13 l

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. 3.2.2 ~ Piping Pressure Boundary (no relief requests) 3.2.3 Pump-.PressureBoundary(noreliefreque:ts)-

3.2.4 Valve Pressure Boundary (no relief requests).

3.3 Class 3 Components (noreliefrequests) :j 3.4 Pressure Tests . . . . . . . . . . . . . . . . . . . . . 15 3.4.1 Hydrostatic-Testtus.of Class 1 Repair-Welds Associated with the Unit I and-Unit 2' Safety injection System,.

IWA 4440- . . . . , , . ... . . .-. . . . . . 15 3.4.2 Hydrostatic Testing of Class.3 Repair. >

Welds in Containment Spray _and Component. '

Cooling Systems, IWA-4440 .'. . . . . . . . . 17 3.4.3 Relief' Request 88-04, Hydrostatic Testing of Class 3 Repair Welds-to the Containment U

Spray-Heat Exchanger 1A,.IWA-4440 . . . . . . 19 ,

4. REFERENCES . . . . . ... . . ... . . . . . . . ... . . . . .

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APPENDIX A: REQUIREMENTS-0F SECTION XI, 1980 EDITION ..

WITH ADDENDA THROUGH WINTER 1980 . . . . . . . . . .- .A-1

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t TECHNIC A EVALUATION REPORT i FIRST INTERVAL \ INSERVICE INSPECTION PROGRAML j MCGUIRE NUCLEAR STATION UNITS 1 AND 2 -i

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1. INTRODUCTION.

Section 50.55a of 10 CFR Part 50 defines the requirements for=the  ;

Inservice. Inspection (ISI) Program for light-water-cooled nuclear power facilities.= Incorporated by-reference in this regulation isSection XI of-the Boiler and Pressure Vessel Code published by the American Society of Mechanical _ Engineers (ASME), which provides the basis for implementing.

inservice inspection.*

Two types of inspections'are required: (1) a preservice inspection conducted before commercial operation to:_ establish a baseline:and.  ;

(2) periodic inservice inspections-conducted during 10-year inspection intervals that normally start from the date of commercial operation. '

Separate plans for completing preservice inspection and each 10-year i inservice inspection must be formulated and submitted.to the:U;S.L Nuclear Regulatory Commission (NRC). The plan ~ for each 10-year interval must be ,

submitted at least six months-before.the start of the interval, i During the initial 10-year interval, inservice inspection examinations must comply with the requirements-in the latest edition and addenda of Section XI facorporated in the regulation on-the date 12 months before the '

date of issuance of the operating license. The program for the first-interval for McGuire Nuclear Station Units I and 2 (MNS-1 &_-2) has-been. i written to the 1980 Edition with Addenda through Winter.1980. 'T_his-is the appropriate Code = edition for MNS 2, based on its operating licer.se dated 1 May 27, 1983. However, this-represents a Code' edition update for MNSil,;

p based on its operating license dated July 8,1981. 'ihe'first ISI interval -t began on December 1, 1981, for MNS-1.and March 1, 1984, for MNS-2.

i Section 2 of this report evaluates the first interval ISI plan-developed by the licensee, Duke Power Company, for MNS-1: and --2 for (a) compliance with this edition of Section XI S (b) compliance with ISI-related commitments identified during the NRC's. review before granting an Operating License, (c) acceptability of examination sample, andL (d) exclusion criteria.-

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• Specific inservice test programs for pumps and valves (IST programs) are being evaluated in other reports.

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Based on the date the construction permit for MNS 1 and 2 was issued 1 (February 23,1973), the plant's Class 1 and 2 components (including sup- '

ports) were to be designed and provided with access to enable performance of inservice examinations and tests and to meet the preservice examination requirements of the 1971 Edition of the Code with Addenda through Winter '

1972 (10 CFR 50.55a(g)(2)). Paragraph 10 CFR 50.5Sa(g) recognizes that some renuirements of the current edition and addenda of Section XI may not be pri.:tical to implement because of limitations of des 1gn, geometry, and materials of construction of components and systems that were designed to  ;

the older Code. The regulation therefore permits exceptions to impractica*, '

examination or testing requirements of the current Code to be requested.

Relief from these requirements may be granted, provided the health and safety of the public are not endangered, giving due consideration to the burden placed on the licensee if the requirements were uposed.

The regulation also provides that ISI programs may meet the requirements of sutsequent Section XI editions and addenda, incorporated by reference in the Rtquiation, subject to approval by the NRC. Portions of such editions ,

or addenda may be used, provided all related requirements of the respective  !

editions or addenda are met. Likewise,Section XI provides that certain components and systems may be exempted from volumetric and surface require-

ments. In some instances, however, these exemptions are not acceptable to the NRC or are acceptable only with restrictions. .

) The Preservice Inspection (PSI) Program for MNS-1 and -2, a 4-loop 1180 MWe Westinghouse pressurized water reactor (PWR), was approved by the staff. References 1 through 8 relate to review and approval of the PSI. The initial ISI program for the first 10 year inspggtion interval (Revision 6) was submitted to the NRC November 7 984,P1 First intery41 1986,00]/ Februar 9 1987,U21 reliefrequestswer(e)ubmittedAugust(q2 April )Octohgg Febru9ty)16,1987,22 Arch 2,1988,D')26,1987,14) Jaggry 19, 1988,UD January 8,1988,L1{)1987, April 27, 1988 09{1 May 4, 1988, cui M i June 2 1 5,1988,(24)ay5,1988,(2ggrch25,1988,9of8,1988 November and November 11, July ()M)988,(I3) October The NRC review d f requests on Ju 1988 (27 1987,(31) March 14,1988,f28Iomeofthesere]L July 12, November 21,1988,(jyge28,1988,]40}11, 1

1988,(34) 1989.

August 3,1988,(32) June 15,1988, 31 and February 23, Relief requests contained in References 10, 21, 22, 23, and 25 are evaluated in this report.

As a result of a preliminary revie additional information on May 7,1986\ y331' pf the Theplan, the staff licensee requested responded to t request for additional information in a letter dated June 20, 1986.(36)heThe staff 1988. (*gyhmitted a second request for additional jggrmation on November 15,

'l The licensee responded March 1, 1989.t > Revision 11 of the ISI plan was included with this response. References 9, 36, and 38 form the primary basis for review of the MNS-1 and -2 ISI program.

References 39 through 49 summarize license conditions, including PSI- and 151-augmented inspectica requirements, related to MNS-1 and -2. References 2 and 6 confirm that there are no unresolved license conditions related to PSI.

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2. EVALUATION OF INSERVICE INSPECTION PLAN d

2.1 IMroductien  !

The approach being taken in this evaluation is to review the applicable program documents to determine the adequacy of their rosponse to CcJe j requirements ed any license conditions pertinent to ISI activities. The l rest of this section describes the submittals reviewed, the basic require- i ments of the effective Code, and the appropriate license conditions. The  ;

results of the review are then described. Finally, conclusions and i recommendations are given.

. 2.2 Documents Evaluated A chronology of documents on MNS-1 and 2 PSI and 151 is given in Section 1 of this report.  :

The key documents that impact the staff's re upt for additional 1 (2) the information,(jD'(1) ic 1 (3) portions of SSER Revisio i

i No's 4 and 6, soJ the PSI program.(bgnp).(4) to a lesser extent, the previous submittals on i

.r 2.3 Summary of Reouirements i The requirements on which this review is focused include the following:

(1) Compliance with Aeolicable Code Editions. The Inservice Inspection Program shall be based on the Code editions defined in 10 CFR and 10 CFR 50.55a b). The licensee for MNS-1 and -2 50.55a(g)(4) has written t he first interval (program to the 1980 Edition with h

addende through Winter If90. This represents a Code edition update for NNS-1 as allowed by 10 CFR 50.55a(g)(4)(iv). These Code requirements are summarized in 2.3.1 below and detailed Code requirements are given in Appendix A. The 1974 Edition, Summer 1975 Ndenda, is to be used for selecting Class 2 welds in sys-tems providing the functions of residual heat removal, emergency core cooling, and containment heat removal. This is a requirement of 10 CFR 50.55a(b)(2)(iv)(A).

I (2) Acceptability if _the Examination Samole. Inservice volumetric, l surface, and visual examinations shall be performed on ASME Code '

Class 1 and 2 components and their supports using sampling- J schedules described in Section XI of the ASME Code and 10 CFR j 50.55a(o). Sample size designations are identified as part of the Code requirements given in Appendix A.

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(3) Exclusion (t iteria. The criteria used to exclude components from examination shall be consistent with IWB 1220, IWC-1220, IWD 1220, and 10 CFR 50.55a(b).  ;

i (4) PSI Commitmenu. The Inservice Inspection Program should address  !

all license conditions, qualified acceptance conditions, or other  !

ISI related commitments described in tie Safety Evaluation Report ,

(SER) and its supplements for the preservice examination.  ;

2.3.1 Code Requirements The following requirements are summarized from the 1980 Edition of i Section XI with addenda through Winter 1980. . Many requirements call for .

the examination of all areas, while other requirements specify more limited.  !

examinations based on criteria such as representative percentage, components examined under other categories, material thickness, location relative to other welds or discontinuities, and component function and cot,struction, i For detailed requirements, see Appendix A of this report or the Code itself.

Er 2.3.1.1 Class 1 Reevirements. The following Class 1 components are to be examined in the first interval in accordance with Table IWB 2500 1:

(1) Pressure-Retaining Welds in Reactor Vessels i (2) Pressure-Retaining Welds in Vessels Other than Reactor Vessels (3) Full Penetratien Welds of Nozzles in Vessels .

(4) Pressure Retaining Partial Penetration Welds in Vessels ,

I (5) Pressure Retair.ing Dissimilar Metal Welds  ;

li (6) Pressure Retaining bolting, Greater than 2 in. Diameter I (7) Pressure-Retaining Bolting, 2 in. and Less in Diameter I (8) Integral Attachments for Vessels (9) Pressure Retaining Welds in Piping (10) Integral Attachments for Piping, Pumps, and Valves i i

(11) Pump Casings and Valve Bodies, including Pressure Retaining Welds (12) Interior of Reactor Vessel, including Integrally Welded Core Support. Structures, Interior Attachments, and Removable Core Support Structures l l

(13) Pressure Retaining Welds in Control Rod Housings l (14) All Pressure Retaining Components - Pressure Tests ~

l (15) Steam Generator Tubing.

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- . 2.3.1.2 Class 2 Reouirements. The following Class 2 components are to be examined in the first interval in accordance with Table IWC 45001:

(1) Pressure Retaining Welds in Pressure Vessels (2) Pressure Retaining Nozzle Welds in Vestsels (3) Integral Attachments for Vessels, Piping, Pumps, and Valves (4) Pressure Retaining Bolting firailer inan 2 in. Diameter (5) Pressure Retaining Welds in Piping (6) Pressure-Retaining Welds in Pumps and Valves (7) All Pressure Retsining Components Pressure Tests.

2.3.1.3 Class 3 Recuirements. The following Class 3 reactor-connected and associated systems are to be examined in the first interval in accor-

, dance with IWD 2500 1:

(1) Systems in Support of Reactor Shutdown Funciion (2) Systems in Support of Emergency Core Cooling,-Containment Heat Removal, Atmosphere Cleanup, and Reactor Residual Heat Removal li (3) Systems in Support of Residual Heat Removal from Spent Fuel -

Storage Pool.

2.3.1.4 Comoonent Sucoorts. The following examination and. inspection of component supp)rts are to be examined in the first interval in accordance with IWF 2500 1:

(1) Plate and Shell Type Supports (2) Linear Type Supports <

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(3) Component Standard Supports.

2.3.2 License Conditions The following is a list of required augmented ISI examinations resulting  !

from license conditions for MNS 1 and -2 (a) Special ultrasonic examination of the accumulator line for pipe i rupture protection. Required by Reference 4, Appendix E.

(b) Auxiliary feedwater nozzle and all piping welds located between the steam generators and the first reducer downstream will be volumetrically examined at a> proximately 31/3 year intervals in accordance with MEB Branc1 Fosition No. 4. Come,itted to in '

Reference 45.

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, (c) One doghause weld per feedwater 13ne will be volumetrically l examined at approximately 31/3' year intervals in accordance '

with MEB Branch Position No. 4. Committed to in Reference 45. )

(d) The following safety injection piping welds will ba ultra-sonically examined at approximately 31/3 year intervals:

'(1) penetration M 334 to pipe- '

(2) penetration M 349 to pipe  !

(3) nitrogen accumulator to pipe  ;

(4) water accumulator to nozzle I (5) water accumulator nozzles to pipe (6) containment sump lines from containment to containment

'.., isolation valve.  :

Committed to in Reference 45. -[

(e) Au mented volumetric and/or surface examination of accessible l we ds in the main steam, feedwater, RHR, and upper head injec-  ;

J tion due to containment penetration inaccessibility. Required l by Reference 4, Appendix B. - '

(f) Augmented u'.trasonic examination at areas where thermal sleeves

have been removed. References 41, 42, and 43 provide a background of the thermal sleeve removal.  :

2.4 Como11ance with Reauirements  ;

i 2.4.1 Applicable Code Edition  !

l: 7 The initial inservice inspection interval examination program must t comply (10 CFR 50.55a(g)(4)(1)) with the requirements of the latest edition ,

and addenda of Section XI incorporated into 10 CFR 50.55a on.the date 12  ;

months before the date of issuance of the operating license. Based on a i i

July 8,1981, operating license for MNS 1, the Code applicable to the first-interval program is the 1977 Edition with addenda through Summer  ;

1979. In accordance with 10 CFR 5 l by letter dated February 28,1989.9M5a(g)(4)(iv),thelicenseerequestedO to update thei MNS 1 to the 1980 Edition with addenda through Winter 1980. Failure to allow the licensee to update to the later Code edition for MNS 1 would place the 1 l additional burden upon the licensee of developing two separate ISI programs t to two different Code editions without a compensating increase in the quality and safety of MNS 1. It is recommended that the licensee be allowed to

update the MNS-1 ISI program to the 1980 Edition, Winter 1980 Addenda. Based l

on a May 27, 1983, operating license for MNS-2, the Code applicable to the first-interval program is the 1980 Edition with addenda through Winter 1980.

The licensee prepared the first interval program to the applicable Code.  ;

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l Section 1.0 of the 151 plan states that examinations of HNS 1 and 2 Class 3 components included in Examination Category D B will be selected in  ;

accordance with Table IWD 25001 of the 1980 Edition through Winter 1982 l addenda. Use of this later Code edition is acceptable, provided all related requirements of the later addenda are met, per 10 CFR 50.55a(g)(4)(iv).

In response to a request for additional information by letter dated March 1, 1989,98 1 the licensee has committed to select all Class 2 piping welds in residual heat removal, emergency core cooling, and containment heat removal systems for examination in accordence with the 1974 Summer 1975 Code, as required by 10 CFR 50.55a(b)(2)(iv)(A). The licensee has additionally chosen to select all other Class 2 piping welds in accordar.;e with the 1974 Summer 1975 Code as allowed by 10 CFR 50.55a(b)(2)(iv)(B).

The licensee has indicated his intention in Section 1.2.2 of the 151 plan to apply Code Case N 356 to the first ISI interval at MNS..' and -2, 1 This Code Case extends the recertification period of Level III NCE personnel 1 from 3 to 5 years, and is not approved for use in Regulatory Guide 1.147, l Revision 6.

Reports datedNRC January Region !! revit30,1985,beql and November use of14,this 1985 Code Case

' ; use (gg)IE Inspction J of this Code Case .t MNS therefore represents a Code update. The licensee formally  ;

- 6 in a letter dated February 28, l requeg 1989. permission By letter to apply dated Code Case 16, 1989, May the NRC 5 granted approval to use ,

Code Case N 356 in Duke'sSection XI ISI Program. In the NRC's approval '

letter, they noted that Code Case N-356 has been incorporated in the 1983 Edition, Winter 1983 Addenda, and that they had approved its use in the 151 programs of several other nuclear power plants.

. 2.4.2 Code Requirements .

The first 1 the ISI program.91grval Wol The ISI program submitted ISI program of record was is contained reviewedin(exclusive Revisionof11 of p

pump and valve testing) and the following observations were noted:

The Inservice Inspection Program for MNS-1 and -2 identifies appropriate Code classes for each component of the power plant.

The design of the Code Class I components of the reactor coolant pressure boundary in MNS 1 and -2 incorporates provisions for access for inservice examination in accordance with Section XI of the ASME Code.

Examination instructions and procedures, including diagrams or system drawings identifying the extent of areas of components subject to examina.

tion, have been prepared. They are listed in the ISI program component tables, cross-referenced to weld and hanger isometrics and component identification drawings, and marked on pipe and instrument drawings (P&lDs).

A complete set of piping isometric drawings has not been provided. However, a review of those provided indicates a weld selection program that complies with Code requirements.

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Examinations and tests are to be performed and evaluated and the results recorded providing a basis for evaluation and comparison with the results of subsequent examinations as required by Code.

Visual, surface, and volumetric examinations are defined as specified by Code.

Exemptions from examination meet Code specifications IWB 1220, IWC-1220, and IWD 1220. Replacements are performed to IWA 7000.

Examination requirements, methods, acceptance standards, inspecticn intervals, deferrals, the selection of items to be examined. .the number of items to be examined, and the examination. fraction of each weld inspected meet the requirements of Tables IWB 2500-1, IWC-2500-1, IWD 2500-1, and IWF 2500 2, except as indicated below.

There are numerous examinations at both units for which the scheduling requirements of. Tables IWB 2412-1 and IWC-24121 are not met. The examination categories that are not in Code compliance are listed below.

Unit 1

1. Category B-B, pressure-retaining welds in vessels other than reactor vessels, less than the minimum allowable number of examinations performed in the first examination period (9%).

2. Category B F, pressure-retaining dissimilar metal welds, less than the minimum allowable number of examinations performed in the first period (5%).

3. Category B-G 2, pressure-retaining bolting 2 in and less in diameter, ,

less than the minimum allowable number of examinations performed in the 3 first period (13%).

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4. Category C-B, pressure-retaining nozzle welds in vessels, more than the maximum allowable number of examinations completed in the second exami- >

nation period (75%). ,

5. Category C-C, integral attachments for vessels, piping, pumps, and valves, less than the minimum allowable number of examinations performed in the first examination period (7%).

6. Category C-H, all pressure retaining components, system pressure test; no examinations performed in the first examination period.

Unit 2

1. Category B G 2, pressure retaining bolting 2-in. and less in diameter, more than the maximum allowable number of examinations performed in the first (39%) and second (80%) examination periods.

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2. Category B.J. pressure retaining welds in piping, more than the maximum  ;

allowable number of examinations performed in the first (40%) and second i (77%) examination periods.

3. Category C A, pressure retaining welds in pressure vessels, more than '

the maximum allowable number of examinations performed in the first (44%) examination period.

! 4. Category C B, pressure retaining welds in vessels, more than the maximum allowable number of examinations completed in-the first period (73%). No examinations are scheduled for the second period, but the '

total completed in the first period is still_ over the allowable maximum for the first and second period.  ;

The first and second inspection periods are over at MNS 1 and the first period is over at MNS 2. In cases where the number of examinations performed exceeds that allowed by Code, it is recommended that those examinations per-formed beyond the maximum number allowed not be credited for the period in ,

which they were performed, and that they be reexamined later in the ten year-  :

interval so that scheduling requirements are met. It is recommended that the licensee closely review examination schedules at MNS 1 and -2 and submit p relief requests for all examinations that do not meet Code requirements, per 10CFR50.55a(g)(5)(iii). ,

2.4.3 Preservice Inspection Commitments The first interval ISI program was reviewed for compliance with pre-service inspection commitments and the following observations were noted:

(a) The licensee demonstrated by analysis in Reference 13 that welds in both ends of the first elbow off reactor coolant loops A, C, ,

and D in the 10 in, accumulator lines are in accordance with I criteria for pipe break protection. The licensee proposed special ultrasonic and surface inspection procedures for detecting inter-granular stress corrosion cracking (IGSCC) on these welds, and stated that the examination would be performed while the system is pressurized to aid in the detection of small cracks. An ,

acoustic emission leak detection system wps The NRC concluded in Appendix E of SSER No.that 4M)also sinceproposed.

criteria for pipe break protection were being met, no augmented ISI was necesssary. The NRC goes on to state, however, that the proposed .

augmented ISI will provide added assurance of continuing struc-

, tural integrity and that it is therefore acceptable.

In a subsequent transmittal dated Novenber 5,1984,(7)the licensee found that performing the examination with the systems pressurized is impractical because to satisfy the pressure-temperature limits of the reactor coolant system,-to which the accumulator line is directly connectec, the fluid temperature would need to be at least 1800F. The licensee states that at this this temperature in a confined area, the heat stress on inspection 9

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l personnel would render the inspection inherently less, rather than l more, reliable. The licensee also contends that the higher . i temperatures would mean that more time would be required for the inspection, and radiation exposures.wpuld increase. The proposed alternative examination is to perform the inspection with the '

system depressurized and at ambient temperature using modern  ;

inspection techniques developed in recent years for the detection  :

of IGSCC. Based on the licensee's demonstration in Reference 13  !

that a break in the accumulator line is less severe than the I limiting LOCANo.

sis in SSER in the)FSAR, and the inspection 4,0 the proposed NRC's acceptance of this analy-with the-system i depressurized is acceptable provided the licensee uses inspection  ;

methods that have been' demonstrated for detecting IGSCC and the. (

acoustic emission leak detection system is monitored for leakage.  !

To address this issue, the ISI program examination listing  !

contains an augmented examination titled " Pipe Rupture Protection" .

that is performed on eight welds in each unit. The examinations- l are spread out over the ten year interval. l (b) In the FSAR, the licensee committed to an augmented examination  ;

that consists of the auxiliary feedwater nozzle and all welds '

8 located between the steam generators and the first reducer down-

• stream and one doghouse weld per feedwater line, at 3-1/3 year intervals. Reference 47. indicates that piping to the Units 1 and 2 steam generator nozzles was removed and replaced to facilitate

• installation of a flow distribution manifold. Reference 49 i indicates that an additional modification was performed on the Units 1 and 2 feedwater system in order to provide heatup capabilities of this same system to protect against thermal shock on the steam generator nozzle area. l The ISI program examination listing states that the ultrasonic [

examination will be "best effort UT due to configuration."

i No explanation of this examination has been provided.- A visual '

examination is also included in the augmented inspection. In  ;

addition, the ISI program shows that 11 welds are inspected in the '

first outage at Unit I and seven welds are inspected-in the first  :

outage at Unit 2. The scheduled examinations are not performed at i 31/3 year intervals as committed to in the FSAR.. ,

(c) An augmented examination of the safety injection system modifi-cations at 31/3 year intervals was committed to in the FSAR.- i Reference 49 indicates that Unit I safety injection system piping  ;

was modified in order to prevent the primary and secondary check 1 valves to the reactor coolant system from fluttering. The Unit 1 1 ISI program examination listing contains an augmented ultrasonic I examination titled " Safety Injection System Modifications" that is performed on 11 welds, i The ISI program examination listing states that the ultrasonic examination will be "best effort UT due to configuration." No' explanation of this examination has been provided. In addition, 1 I

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the ISI program'shows that the ex6mination is only performed once in the first ten year interval (first outage), not at 31/3 year intervals as committed to in the FSAR.

(d) In SSER No. 4, Appendix B (4) the NRC staff required an augmented

> examination of accessible welds in the main steam, feedwater, RHR, and upper head injection piping due to containment penetration inaccessibility. This augmented examination is not addressed in the 151 program.

(e) The Unit 1 151 program examination listing contains an augmented ultrasonic examination titled

• Thermal sleeves Removal" that is performed on 14 areas in the first outage. The ISI program examination listing states that the ultrasonic examination will be "best effort UT due to configuration."

2.5 Conclusions and Recommendations

. Based on the preceding evaluation, it is concluded that the McGuire Nuclear Station Units 1 and 2 ISI program meets the requirements of (1) the Code and (2) NRC regulations, with the exceptions detailed below, li A review of the examination listings and drawings provided with the 151 plan indicates that some Code requirements are not being met. Speci-fically, scheduling requirements are not met for the various examination categories listed in Section 2.4.2 of this report. The-licensee should be aware that compliance with ASME Section XI is required unless relief has been granted by the NRC staff. It is recommended that the licensee review those  ;

examinations pointed out in Section 2.4.2 of this report and submit relief requests for any and all examination requirements that cannot be met in the first ten year interval.

It is unclear that all au I (Section 2.4.3 of this report)gmented .

inspection are Some inspections requirements indicated asare being met a *best-effort UT due to configuration,' and some inspections are not spread over the interval as required. The ISI plan does not' address the augmented inspection of welds in main steam, feedwater, RH piping as required by SSER No. 4, Appendix B.(4)R, Concerns andregarding upper headthe injection licensee's augmented ISI program detailed in Section 2.4.3 above, should be reviewed by the NRC staff.

The following additional conclusions are made concerning the- first interval 151 plan.

The licensee requested in a letter dated February 28,1989,(51)to update the MNS-1 151 plan from the 1977 Summer 1979 Code to the same Code edition as MNS 2, the 1980 Winter 1980 Code. Such an update would result in a higher degree of consistency between plans and increase the overall-reliability of ISI examinations, as well as decreasing the burden upon the licensee and NRC staff of developing and reviewing an 151 plan to separate 11

Code editions. It is therefore recommended that permission to update the MNS-1 151 plan to the 1980 Edition, Winter 1980 Addenda, be granted, per 10 CFR 50.55a(g)(4)(iv).

Category D B examinations will be performed according to the 1980 Edition, Winter 1982 Addenda. Use of this later Code edition is acceptable, provided all related requirements of the later addenda are met, per 10 CFR 50.55a(g)(4)(iv). .

In a second letter dated February 28,1989,(53) the licensee requested permission to apply Code Case N 356 to the 151 plan for MNS 1 and 2. N 356 ,

is not approved for use in Regulatory Guide 1.147. Revision 6, but is incor-porated in Section XI in the Winter 1983 Addenda and later editions. It is recommended that the licensee be allowed to update the portion of the 151 plan covering the recertification period for Level 111 NDE personnel to the Winter 1983Addendaper10CFR50.55a(g)(4)(iv). As required in 10 CFR 50.55a(g)(4)(iv), all related requirements under IWA 2300 of the later edition must also be mit (i.e., specific examination requirements).

3 .' RE0 VESTS FCw RELIEF FROM ASME CODE SECTION XI I

EXAMINATION REQUIREMENTS ,

Fourfihj-)intervalrelief(

B8, June 27, 1988, uestssubmittedg$

July 1,1988,(2 and gustNovember 27,1986,(10) 8, May5(2pihavebeenidentifiedthatrequirereview.

1988, The following sections evaluate these pending relief requests. The relief request submitted in Reference transmitted 21 (88 04) to Duke was Company Power subsequently evaluated on February 23,by the hg)andRelief 1989.L with the SSER Request 88 04 is evaluated herein and is basically a paraphrase of the SSER.

Where relief is recommended in the following report section, it is done so on the assumption that the proposed alternative examination ar.d all i applicable Code examinations for which relief has not been requested will be performed on the subject component. Where additional examinations beyond proposed alternatives and Code requirements are deemed necessary, these are included as conditions for recommending relief.

The material included in the paragraphs titled Code Relief Recuett,,

Etocosed Alternative Examination, and Licensee's Basis for Recuestina Relief is quoted directly from the relief request except for minor editorial changes such as removing references to figures and tables not included in this report.

i 12

i i

3.1 Class 1 Components (no relief requests)

. \

3.2 Class 2 Components l 1

1 3.2.1 Pressure Vessel and Heat Exchangers ,

3.2.1.1 Relief Recuest No. 88 08. Safety In.iection Aceiimulator Tank Shell-to Lower Head Weld. Cateaory C A. Item C1.10 I

ode Recuirement i

.. Essentially 100% of the circumferential head to shell welds in ]

each vessel or heat exchanger shall be volumetrically examined in t accordance with Figure IWC-2520-1 during each inspection interval.

For multiple vessels with similar design,-size, and service (such i as steam generators and heat exchangers), the required examinations may be limited to one vessel or distributed among the vessels (i.e.,

l, the upper head-to shell weld could be performed on one vessel and the lower head to shell weld could be performed on a separate, but -

similar, vessel).

_ Code Relief Reauest Relief is requested from ultrasonic examination of the shell-to lower head weld on one accumulator tank at each unii..

b ProDosed Alternative Examination The licensee proposes to perform ultrasonic examination of an additional accumulator tank shell-to-upper head weld at each unit.

Licensee's Basis for Reauestina Relief -

The Unit I and 2 Safety Injection Accumulator Tanks are designed such that the shell-to lower head welds are inaccessible to 1repare the surface for ultrasonic examination. T5e weld on erch tan ( is located a) proximately 1 inch from where the support skirt is welded to the t.n(. This situation exists for all Unit 1 and 2 accumulator tanks. The Safety Injection Accumulator Tank shell-to-upper head welds have the same geometric design and thickness as the shell-to lower head welds. The shell-to upper head weld and shell- ,

to lower head welds are identical in size, material, and type of weld.

13 -

, ~. . . -

Evaluation The shell-to lower head weld is enclosed within the accumulator tank support skirt and it appears from drawings that very little clearance exists between the support skirt and the weld. It is agreed that an ultrasonic examination is impractical on this configuration. A surface examination also appears impractical.

As an alternative, the licensee' has proposed to examine an additional accumulator tank upper head to shell. weld at each unit.

Assuming materials, configuration, weld procedures, and quality assurance are the same for all accumulator shell to head welds, the proposed alternative examination would give an indication of-structural reliability similar to that required by Code.

Conclusions and Recommendations

- Based on the above evaluation, it is concluded that for the shell-to-lower head welds discussed above, the Code requirements are l g,'

impractical. It is further concluded that the proposed alternative examination L.11 provide adequate assurance of structural reli-

• ability. Therefore, relief is recommended as requested. ,

References References 23 and 25. )

l M 3.2.2 Piping Pressure Boundary (no relief requests) l 3.2.3 Pump Pressure Boundary (no relief requests) 3.2.4 Valve Pressure Boundary (no relief requests) ,

I

\

l 14

-i

- ._,e . . _ . . _ . . _ ,. . . - _, -- .

3.3 Class 3 Components (noreliefrequests) 3.4 Pressure Tests r

3.4.1 Hydrostatic Testino of Class 1 Reoair Welds Associated with the Unit 1 Jnd Unit 2 Safety Iniection System. IWA 4441 ydeRecuirement l IWA 4440 states that after repairs by welding on the pressure-retaining boundary, a system hydrostatic test shall be performed in accordance with IWA 5000. IWA 5214(b) requires that the test pressure and temperature for a system hydrostatic test subt.rquent to the component repair or replacement shall comply with the system test pressure and temperature specified in IWB 5222 IWC-5222,'and IWD- '

$223, as applicable to the system which contains the repaired or replaced component.  ;

1 l:

Code Relief Recuest  ;

Relief is requested from hydrostatic testing of repair welds associated with the Unit I and 2 Safety Injection System.

Prooosed Alternative Examination ,

t A 100% radiographic examination plus 100% PT examination are

li required upon completion of all pressure boundary welds. An additional PT examination of all root pass welds will also be performed, ,

Also, a hy&ostatic test will be performed at the 10 year inspection interval per Section XI of the ASME Code. An inservice leak test cannot be performed on this system because if the check valves hold, the system will not see system pressure. In addition, a UT examination will be pert'ormed on the welds for Preservice Baseline Inspection per ASME Section XI. .

Licensee's Basis for Recuestina Relief There are no isolation valves downstream of these primary and  !'

secondary check valves to the NC system; therefore it is impossible to isolate these portions of systems. However,=there are several L

approaches to partially pressurizing the system.

l 15 l  :

{ .: .- - - , -. - . -- - -- .. ..

7 l

The first approach would be to pressurize the Reactor Coolant f System (NC) to 2235 pounds, and then use the Safety injection (NI)  !

pumps to pressurize the NI systems against one of the check valves, t However, this pump pressure is'only 1600 pounds, which falls far short of the required test pressure. j The second approach would be to remove the internals from the primary check valves, which go to the NC system, and then pressurize  :

the NC system to 1.02 of 2236 sounds at 5000F temperature. However,  !

this method would.still not ac11 eve the desired test pressure per the i Code because this would be a dead leg pipe with no flow, and the convective and conductive effect of heat transfer possibly would not  :

reach the 5000F temperature minimum, as this portion of the system is  !

uninsulated. This would also require draining the system in order to replace the internals into the check valve, a very timely and costly procedure.

Therefore, due to orientation of_ the valves within the system, it is not possible to.hydrostatically test-the system. However, the i proposed alternate examinations are equal to or better than the  !

required testing per the Code, l.

Evaluation [

The licensee has explored several' options for partially pressurizing the piping containing the repair welds and found all '

to be impractical. An inservice leak test is also impractical. As an alternative, the repair weld areas will be 100% radiographically and 100% dye-penetrant examined, with an additional dye penetrant examination of the root pass welds.

I The proposed alternative examination,

along with the Code-required hydrostatic test as partiof the 10 year ISI plan, will '

provide necessary assurance of structural reliability. .

l Conclusions and Recommendations 1

Based on the above evaluation, it is concluded that for the hydrostatic tests discussed above, the Code requirements are .!

impractical. It is further concluded that the proposed alte; native

[- examination will provide necessary assurance of structur'ai reli- <

ability. -Therefore, relief is recommended as requested. I l

References Reference 10.

l l

16 .

\

,e - - ,,- - - - , , - --. - - . _ _ _ - - , - . . . - - + - , ,-. , .- ,,

l 3.4.2 Hydrostatic Testino of Class 't Reoair Welds in Containment Sorav and I l Comoonent Coolina Systems. IWA 4440 i

Code Reauirement i ,

IWA 4440 states that after repairs by welding on the pressure-retaining boundary. a system hydrostatic test shall be performed in accordance with IWA 5000. IWA 5214(b) requires that the test pressure i and temperature for a system hydrostatic test subsequent to the  !

component repair or replacement shall comply with the system test ,

pressure and temperature specified in IWB 5222. IWC 5222, and i IWD 5223, as applicable to the system which contains the repaired i or replaced component.  !

. Code Relief Recuest Relief is requested from hydrostatic testing of repair welds associated with the below listed valves in the Containment Spray and i Component Cooling Systems: i l 1RN 134A 2RN 134A IRN 235B 2RN 235B . l' IRN-86A 2RN 86A IRN 1878 '2RN-187B i

Prooosed Alternative Examination All welds will be subjected to a PT or MT examination on root pass and also final welding pass. An inservice leak test at system pressure and temperature will also be performed for all welds i li involved.

Licensee's Basis for Reauestino Relief The modifications listed in this request will be performed during refueling outages. During each refueling outage there are certain periods of time each train of the RN system can be drained. The RN system provides cooling for the Residual Heat Removal (ND) system and  ;

the Spent Fuel Cooling (KF) system, both of which are needed for the majority of the outage. Based on a typical outage, the RN Supply and Discharge Header for either A or B Train can be drained and available for work for approximately 6 days on Unit I and 10 days on Unit 2.

Unit 1 is more restricted due to the fact that the Control Room Ventilation / Chilled Water (VC/YC) system Chillers discharge to the Unit 1 RN Discharge Header only; therefore, when the Unit 1 RN <

Discharge Header is drained, VC/YC is inoperable, which places Unit 2 in a 7-day Technical Specification operability constraint per Technical Specification 3.7.6. These short time periods allow barely 17

_, + _ , , . . ...._,,.__,.-__r...._s .

, , .r, , _

p enough time to perforin the actual modifications to the RN system.

' Attempting a hydrostatic test on the large portions of the RN system involved with the subject welds would involve significant, manpower,andequipment,(highcapacity,highheadpump). planning, A hydro-static test on this.large a section of RN piping would add days to the outage schedule even if the hydro pump was staged ahead of time.

Most of the time needed would be comprised of valve alignments to fill and sent the system. Since isolation valves on the system are 36" butterfly valves, the valves would most likely leak by at hydro-static test pressure. Even with a high capacity pump, hydrostatic test pressure may not be obtained.due to this' leakage. Also, the leakage past these valves could potentially overpressurize other vital equipment such as critical instrumentation. To repair the 36" butterfly valves would involve a major undertaking and agair, present similar hydro problems due to the.36" valves being weld end valves which would also require hydrostatic testing following replacement.

Therefore, the licensee believes the additional manpower, planning, execution expense, and burden of time placed on Duke to perform the required hydrostatic testing does not provide a commen-surate increase in operational quality. Additionally, the licensee b

believes that the alternative testing.that is lanned is more than adequate to ensure safe and consistent reliabi ity of the system. ,

Evaluation It is agreed that the required hydrostatic test may not be possible due to probable leakage of isolation valves. As an alter-native, the repair weld areas will be dye penetrant or magnetic particle examined on the weld root pass and final weld surface.

An inservice leak test at system pressure and temperature will be -

performed on the repair weld areas prior to plant startup.

I The proposed alternative examination, along with the Code-required hydrostatic test as part of the 10 year 151 plan, will provide necessary assurance of structural reliability. Therefore, relief is recommended.

Conclusions and Recommendations Based on the above evaluation, it is concluded that for the hydrostatic test discussed above, the Code requirements are im-practical. It-is further concluded that the proposed alternative examination will provide necessary assurance of structural reliability. Therefore, relief is recommended as requested.

Beferences Reference 22.

e 18 f

a '

]

1 3.4.3 Relief Recuest 88 04. Hydrostatic Testino of Class 3'Renair Welds to  !

the Containment Sorav Heat Exchancer 1A. 1WA 4440  !

Code Reouirement IWA-4440 sta;es that after repairs by welding on the pressure-retaining boundary, a system hydrostatic test shall be performed in  !

accordance with IWA 5000. IWA 5214(b) requires that the test pressure i

and temperature for a system hydrostatic test _ subsequent to the component repair or replacement shall comply with the system test  ;

pressure and temperature specified in IWB 5222, IWC 5222, and IWD 5223, as applicable to the system which contains the repaired or replaced component. i Code Relief Recuest Relief is requested from hydrostatic testing of a modification I which adds a 6-in inspection port on the side of Containment Spray i Heat Exchanger IA.

prooosed Alternative Examination A. A pneumatic test will be performed on the subject welds, prior to drilling a hole in the vessel, at 110% of 200 psig, or 220 psig  ;

to assure weld integrity. ,

B. An inservice inspection at system pressure will be performed  ;

following the return of the vessel to service.  ;

t I

I licensee's Basis for Recuestino Relief Hydrostatic testing of welds referenced in this request would be +

impractical based on the following reason:

The inlet and outlet isolation valves are 18' valves and are a +

butterfly ty>e design. Historically, these butterfly valves have not

• held design iydro pressures without significant leakage. It is believed that additional hydro pump capacity would-not result in the desired pressure due to leakage past these valves. The installation ,

of blind flanges upstream and downstream of the outlet isolation valves would require complete drain-down of the RN Supply and Return Header. This task could not be accomplished within the 72-hour  :

Technical Specification limit. The RN system is a low pressure, lowtemperature(135psig.950F) system,whiletheheatexchanger vessel is designed for 200 psig. Therefore, the hydrostatic pressure >

would be limited to 1.1 times 135 psig or 149 psig, due to limiting ,

RN system design parameters. ,

i 19 ,

- - , - . , . . , , . , - - - r- , --. - -w-- . , . - . . - - - - , _ . - , . + ...r. , ,- =4.w.aw-i -- --+y.,----

1 t . ,

Evaluation The NS Heat Exchanger is of the shell and tube tylse for which ECCS water from either the Refueling Water Storage Tant or the containment sump circulates through the tubes while Nuclear Service Water (RN) circulates through the shell side. The NS system is an engineered safety feature w1ich, in the event of a 1.0CA, removes thermal energy from the Containment Building, transferring it through the NS heat exchanger to the Ultimate Heat Sink by way of the RN system. .The RN system is designed as a low pressure (135 psig),

low temperature (950F) system, while the NS heat exchanger vessel is designed for 200 psig.

10 CFR 50.55a(g) requires each licensee to develop and implement a program for ISI and testing of systems and components classified as ASME Code Class 1, Class 2, and Class 3. Consistent with the guidance in Regulatory Guide 1.26, the tube side of the heat exchanger is classified as ASME Section til Class 3 and the shell side is classi-fied as-ASME Section VIl!. Thus, in a literal reading of 10 CFR 50.55a(g)(4), the shell side of the heat exchanger would not fall within the scope of the McGuire 151 program. However, 10 CFR I,

50.55a(g)(6)(ii) states "The Commission may require the licensee to follow an augmented inspection program for systems and components for which the Commission deems that added assurance of structural reli-ability is necessary." Consistent with 10 CFR 50.55a(g)(6)(ii), the .!

NS and RN systems are safety related systems, and the heat exchar.gers i are appropriately included in McGuire's 151 program.  !

In its submittal. Duke Power Company performedtobean" alteration"rathertha(DPC)'considersthe.

na repair,* and towork involve the ' National Board Inspection Code Book." The NRC does not ,

recognize such a document, and takes no position on its relevance or appropriateness. Because the subject component is included in the l' McGuire ISI program, our evaluation is based upon Section XI (1980 EditionwithWinter1980 Addenda).

Section XI of the ASME Code does not directly address " alter-ations or moaifications." However, the rules of Articles IWA-4000 Repair Procedures, and IWA 7000 Replacements, are relevant. Section XI does not provide ex)1icit rules for design or installation of new or replacement parts, sut generally defers to the

• Original Code for Construction," in this case Section VIII, Division I.Section VIII Division 1, as compared'to Section Ill, has simplified rules for design and construction of pressure vessels. In recognition of this fact, Section Vill requires hydrostatic testing of the pressure boundary at 150% of design pressure.

Thus, the pressure test on the ' alteration" should have been conducted et 150% of design pressure or 300 psig, not 220 psig. By testing only to the lower pressure, DPC has, in effect, derated the heat exchanger (shell-side) from 200 psig to two-thirds of 220 psig, or 147 psig. Because the test was complated and the shell penetrated l

l 20

( l l.

4 prior to submittal of the request for relief, ratesting at the higher' test pressure is no longer practical. Thus DPC's relief request is viewed as a request for NRC acceptance of the derated heat exchanger.

In this respect, it is noted that the derated pressure (147 psig) still exceds the RN system design pressure of 135 psig and provides a reasonable level of structural integrity. Replacing the heat exchanger or reworking the alteration to achieve a proper test pressure would cause considerable hardship without a compensating increase in the-level of quality and safety.

Conclusions and Recommendations Based on the above evaluation, it is concluded that for the hydrostatic test discussed, the Code requirements are impractical.

It is further concluded that the proposed alternative examination will provide adequate assurance of structural reliability, therefore, relief is recommended.

References

] Reference 21 and 54.

l l

21 l

4. REFERENCES

1. W. O. Parker, Jr. (Duke) to H. R. Denton (NRC). February 1, 1979; Unit 1 preservice inspection relief request and preliminary inservice inspection relief request.

2. W. O. Parker (Duke) to H. R. Denton (NRC). December 15, 1980; revised PSI relief requests.

3. B. J. Youngblood (NRC) to W. O. Parker (Duke), February 17, 1981;-

review of December 15, 1980 revised relief requests.

i

4. Safety Evaluation Report, Unit 1 151/ PSI Anoroval of Unit 1, NUREG 0422, Supp. 4, January 1981.

5. Letter. H. B. Tucker (Duke) to H. R. Denton (NRC), December 22, 1982; preliminary inservice inspection and preservice inspection relief requests Units 1 and 2.

.{,

6. . Letter, H. B. Tucker (Duke) to H. R. Denton (NRC), January 11, 1983; y Unit 2 hydro testing relief request.

7. Letter, H. B. Tucker (Duke) to H. R. Denton (NRC), January 19, 1983; l Unit 2 preservice inspection relief request. '

8. Safety Evaluation Report, Unit 2 IST - PSI Anoroval of Unit 2, NUREG-0422, Supp. 6, February 1983.  ;

9. H. B. Tucker (Duke) to H. R. Denton and E. G. Adensam (NRC),

November 7,1984; submittal of Inservice Inspection Plan: Vols.1. II, ,

III (Revision 6).

10. H. B. Tucker (Duke) to B. J. Youngblood (NRC), August 27,1986; N

request for relief from hydrostatic testing following repairs. l

11. H. B. Tucker (Duke) to NRC, February 9, 1987; request for relief from hydrostatic testing following repairs. t

12. H.B. Tucker (Duke)toNRC, February 16, 1987; request for relief from hydrostatic testing following repairs.

13. H. B. Tucker (Duke) to NRC, April 7, 1987; request for relief from hydrostatic testing following repairs. ]

14. H. B. Tucker (Duke) to NRC, October 26, 1987; request for relief from '

hydrostatic testing following repairs.

15. H.B. Tucker (Duke)toNRC, January 19. 1988; response to request for additional information concerning October 26, 1987 relief request.

16. H. B. Tucker (Duke) to NRC, January 28, 1988; request for relief from hydrostatic testing following repairs.

l

^

22

i

17. H. B. Tucker (Duke) to NRC, March 2, 1988; Code Case applicability for ISI.  !

18. H. B. Tucker (Duke) to NRC, March 25, 1988; additional information on February 9,1987 relief request.

. 19. H. B. Tucker (Duke) to NRC, April 27, 1988; request for relief from  !

hydrostatic testing following repairs.

20. to NRC, May 4,1988; additional information on H. B. Tucker October (Duke) 26, 1987 re lief request.

21. H. B. Tucker.(Duke) to NRC, May 5,1988; request for relief from hydrostatic testing following repairs.

22. H. B. Tucker (Duke) to NRC, June 27, 1988; request for relief.from hydrostatic testing following repairs.

23. H. B. Tucker (Duke) to NRC, July 1,1988; request for relief from i examination of Unit 2 Safety Injection Accumulator Tank.

24. H. B. Tucker (Duke) to NRC, Detober 5,1988; repeat of modification 1 8

for which relief was requested February 9, 1987, and granted July.12, *

• j 1988.

H. B. Tucker (Duke) to NRC, November 8,1988; revision of July 1,1988 l 25.

relief request.

26. H. B. Tucker (Duke) to NRC, November ll,1988; request for relief from hydrostatic testing following repairs.

27. B. J. Youngblood (NRC) to H. B. Tucker (Duke), July 31, 1987; Safety Evaluation of relief request submitted April 7,1987.

• I 28. D. Hood (NRC) to H. B. Tucker (Duke), March 14, 1988; Safety -

Evaluation of relief request submitted January 28, 1988. .

! 29. D. B. Matthews (NRC) to H. B. Tucker (Duke), June 15, 1988; Safety Evaluation of relief request submitted April 27, 1988.

30. NRC internal memo, C. Y. Cheng to H. Pastis, D. Hood, and K. Jabbour, June 28, 1988; review of Code Case use for ISI.

31. D. B. Matthews (NRC) to H. B. Tucker (Duke), July 12, 1988; Safety Evaluation of a relief request submitted February 9,1987, February 16, 1987, and March 25, 1988. +

32. D. B. Matthews (NRC) to H. B. Tucker (Duke), August 3, 1988; Safety Evaluation of relief requests submitted October 26, 1987, January 19, 1988, and May 4, 1988.

33. D.B.Matthews(NRC)toH.B. Tucker (Duke), November 21, 1988; Safety Evaluation of relief request submitted November 11, 1988.

l l 23  :

l l- -

34 D. B. Matthews (NRC) to H. B. Tucker (Duke), February 23, 1989; l safety evaluation of Relief Request 88 04.  !

35. D. Hood (NRC) to H. B. Tucker (Duke), May 7, 1986; request for additional information. ,

36. H. B. Tucker'.(Duke) to H. R. Denton (NRC), June 20, 1986; response to request for additional information.

l

37. D. S. Hood (NRC) to H. B. Tucker (Duke), November 15, 1988; request i for additional information regarding ISI program. 1

38. H. B. Tucker (Duke) to NRC, March 1. 1989; response to November 15, 1988, request for additional information, including Rev. 11 of ISI 1 Plan. )

39. Letter, R. S. Boyd (NRC) to W. O. Parker, Jr. (Duke), February 9, 1979; augmented inservice inspection for pipe rupture protection.

40. Letter, W. O. Parker, Jr. (Duke) to H. R. Denton (NRC), March 22, 1979; augmented inservice inspection for pipe rupture protection, l

41. W. O. Parker, Jr. (Duke) to H. R. Denton (NRC), July 13, 1982;  !

submittal of thermal sleeve evaluation-report. ,

1

42. NRC Memo, R. Bosnak (NRC) to E. G. Adensam (NRC), December 27, 1982; McGuire 1 and 2 thermal sleeves. i

43. NRC Memo. E. G. Adensam (NRC McGuire 1 and 2 thermal sleev)es,to R. Bosnak (NRC), January ll, 1983; 1

44. Letter, H. B. Tucker (Duke) to H. R. Denton (NRC), November 5 -1984; augmented inservice inspection for accumulator injection line welds.

45. McGuire FSAR Q-121-7 to Q 121-13; submittal of preservice inspection

b and inservice inspection questions and responses.

l 46. H.B. Tucker (Duke)toH.R.Denton(NRC), September 14, 1982; relief l

request from hydrostatic testing of feedwater and safety injection l piping modifications.

47. H. B. Tucker (Duke) to H. R. Denton (NRC), October 19, 1982; revision of September 14, 1982, hydrostatic testing relief request.

48. T. M. Novak (NRC) to H. B. Tucker (Duke). December 29,;1982; review of September 14,'1982, and October 19, 1982, relief requests.

49. H. B. Tucker (Duke) to H. R. Denton (NRC), March 11, 1983; relief request from hydrostatic testing of feedwater piping modifications.

50. H. B. Tucker (Duke) to NRC, February 28, 1989; request to update MNS 1  ;

to the 1980 Winter 1980 Code Edition for ISI.

24

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4 4

51. V. L. Brownlee (NRC) to H. B. Tucker (Duke), January 30, 1985; IE Inspection Report Nos. 50 369/84-41 and 50 370/84 38.

52. V. L. Brownlee (NRC) to H. B. Tucker (Duke), November 14,1985; IE Inspection Report Nos. 50 369/85 37 and 50 370/85 38.

53. H. B. Tucker (Duke) to NRC, February 28, 1989; Use of Code Case N 356,

54. D. B. Matthews (NRC) to H. B. Tucker (Duke), May 16, 1989; approval of use of Code Case N 356. ,

1 i

O h

e 6

d' A

+

c 25

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..w ,

- ~- - -- - +

. . _ < _ . . . . _ . . . . . ...m ..._..s,m...m m... _ _ . _ _ . . . . _ . _ , . _ , . . _ . _ . . ~ . . - . _ _ _ . _ , _ . . m__m. s _ . . . . . .. . . m_._

. . j

! i APPENDIX A

. Requirements of Section XI of the. American Society of Mechanical i Engineers Boiler and Pressure Code,  !

1983 Edition with Addenda through Winter 1980 ,

A.1 CLASS 1 REQUIRD4ENTS l t

A.1.1 CATECORY B-A, PRESSLRE-RETAINING WELDS IN REACTOR VESSEL l

A.1.1.1 le11 Welds, Item B1.10 l A.1.1.1.1 C1rcumferential and Longitudinal WelJs, Items B1.11 and 81.12 i All pressure-retaining circumferential and longitudinal shell welds in i the reactor vessel shall be volumetrically examined in accordance with .

Figures IWB-2500-1 and -2 over essentially 100% of their lengths during the  :

I first inspection interval. Examinations may be performed at or near the i end of the interval. - !

A.1.1. 2 Head Welds , Item Bl .20 }

i A.1.1. 2.1 Circumferential and Meridional Head Welds, Items 81.21 and 81.22 l All pressure-retaining circumferential and meridional head welds in the reactor vessel head shall be volumetrically examined in accordance with  !

Figure IWB-2500-3 over the accessible portion up to 100% of the weld length

, a, during the first inspection _ interval. . The bottom head welds may be i examined at or near the end of the interval.

i A.1.1. 3 Shell-to-Flance Weld, Item Bl .30 l Essentially 100% of the length of the shell-to-flange weld shall be volumetrically examined in accordance with Figure IWB-2500-4 during the ,

first inspection interval. ~ If partial examinations are conducted from the  :

flange face, the remaining examination required to be conducted from the i vessel wall may be performed at or near the end of each inspection i interval. The examination of the shell-to-flange weld may. be performed ,

during the first and third inspection periods in conjunction with the  !

nozzle examinations of Examination Category B-D (Program B). At least 50% l of shell-to-flange weld shall be examined by the end of the first l inspection period, and the remainder by the end of the third inspection i period.

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A.'1.1. 4 Head-to Flange wid, Item 81.40 i Essentially 100% of the lengtn of the head-to-flange weld shall be volu-

! metricully and surface examined in accordance with Figure IWS-2500 5 during the first inspection interval. If partie) examinations are conducted from the flany face, the remaining examination required to be conducted from the vessel wcM may be performed at or near the end of each inspection interval.

i A.1.1.5 Repair Welds, Jtem B1.50 A .1.1.5 .1 Repair Welds in the Beltline Region, Item B1.51 All base metal weld repair areas in the beltline region where repair depth exceeds 10% nominal of the vessel wall shall be volumetrically examined in accordance with figures IWB-2500-1 and -2 during the first inspection interval. Examinations may be performed at or near the end of the interval. The beltline region extends for the length of the vessel thermal shield, or in the absence of a thermal shield, the effective length of reactor fuel elements. If the location of the repair is not positively and accurately known, then the individual shell plate, forging, or shell course containing the repair saall be included.

A .1. 2 CATEGORY B-8. PRESSURE-RETAINING WELDS IN VESSELS OTHER THAN REACTOR VESSELS A.1.2.1 Shell-to-Head Welds in the Pressurizer, Item B2.10 A.1. 2.1.1 Circumferential Shell-to-Head Welds. Item B2.11 All circunferential shell-to-head welds in the pressurizer shall be volumetrically examined in accordance with Figure IWB-2500-1 over I essentially 100% of their length during the first inspection interval.

A.1. 2.1. 2 Longitudinal Shell Weld, Item 82.12 One foot of the selected longitudinal shell weld in the pressurizer intersecting the examined circumferential shell-to-head weld shall be volumetrically examined in accordance with Figure IWB-2500-2 during the first inspection interval.

A.1.2.2 Head Welds in Pressurizer Vessels, Item B2.20 A.1.2.2.1 Circumferential and Meridional Head Welds, Items 82.21 and 82.22 All circumferential and meridional head welds in the pressurizer shall i be volumetrically examined in accordance with Figure IWB-2500-3 over essen-l tially 100% of their lengths during the first inspection interval.

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1_______________-_________ ._- _.

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p A.1. 2. 3 Head Welds in the Primary Side of the Steam Generators. Item B2.30 A.1. 2. 3.1 Circumferential and Meric"onal Head Welds. Items 82.31 and R2.32 All circumferential and meridional head welds in the primary side of the steam generators shall be volumetrically examined in accordance with Figure IWB-2500-3 over essentially 100% of their length during the first inspection interval .

A.1. 2. 4 Tubesheet-to-Head Weld. Item B2.40 The tubesheet-to-head weld in the primary side of the steam generators shall be volumetrically examined in accordance with Figure !WB-2500-6 over essentially 100% of its length during the first inspection interval.

A.1. 2. 5 Shell (or Head) Welds in the Primary Side of the Heat Exchangers.

Item B2.50 1:

A.1. 2. 5.1 Circumferential Welds, Item B2.51 -

All circumferential shell (or head) welds in the primary side of the heat exchangers shall be volumetrically examined in accordance with Figures IWB-2500-1 and -3 over essentially 100% of their length during the first inspection interval .

A.1.2.5.2 Longitudinal (or Meridional) Welds, Item B2.52 i

All longitudinal (or meridional) welds in the primary side of the heat 4' exchangers shall be volumetrically examined in accordance with Figures IWB-2500-2 and -3 over essentially 100% of their length during the first inspection interval .

A.1. 2. 6 Tubesheet-to-Shell (or Head) Welds. Item B2.60 The tubesheet-to-shell (or head) welds shall be volumetrically examined in aecordance with Fipure IWB-2500-6 over essentially 100% of its length during the first interval.

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A.I.3 CATEGORY 8-D, FULL PENETRATION WELDS OF N0ZILES IN VESSELS (INSPECTION PROGRAM B)

A.I.3.1 Reactor Vessel Nozzle-to-Vessel Welds, Items B3.90 and 83.100 All nozzle-to-vessel welds and inside radius sections in the reactor vessel snall be volumetrically examined in accordance with Figures IWB-2500-7(a) through (d) during the first interval of operation. The nozzle-to-vessel weld and adjacent. areas of the nozzle and vessel are included. At least 251 but not more than 50% (credited) of the nozzles shall be examined by the end of the first inspection period and the remainder by the end of the inspection interval. If examinations are conducted from inside the component.and the nozzle weld is examined by

. straight beam ultrasonic method from the nozzle bore, the remaining examinations required to be conducted from the shell may be performed at or near the end of each inspection interval.

l' A.I.3.2 Pressurizer Nozzle-to-Vessel Welds. Items B3.110 and B3.120 All nozzle-to-vessel welds and inside radius sections in the pressurizer shall be volumetrically examined in accordance with Figures IWB-2500-7(a) through (d) during the first interval of operation. The nozzle-to-vessel weld and adjacent areas of the nozzle and vessel are included. At least 25% but not more than 50 (credited) of the nozzles shall be examined by the end of the first inspection period and the re-mainder by the end of the inspection interval.

II A.I.3.3 Steam Generator Nozzle-to-Vessel Welds. Items 83.130 and B3.140 All nozzle-to-vessel welds and inside radius sections in the primary side of the steam generator shall be volumetrically examined in accordance with Figures IW8-2500-7(a) through-(d) during the first interval of operation. The nozzle-to-vessel weld and adjacent areas of the nozzle and vssel are included. At least 25% but not more than 50% (credited) of the nozzles shall be examined by the end of the first inspection period and the remainder by the end of the inspection 4nterval.

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, . i A.1. 3. 4 Heat Exchanger Nozzle-to-Vessel Welds Items B3.150 and B3.160 l

All nozzle-to-vessel welds and inside radius sections in the primary i

' side of the heat exchanger shall be volumetrically examined in accordance  :

with Figures IWB-2500-7(a) through (d) during the first interval of  ;

operation. The nozzle-to-vessel weld and adjacent arest of the nozzle and  !

vessel are included. At least 255 but not more than 505 (credited) of the ,

nozzles shall be examined by the end of the first inspection period and the  ;

remainder by the end of the inspection interval. l l

i CATEGORY B-E, PRES $URE-RETAINING PARTIAL PENETRATION WELDS IN  ;

A.1. 4 YES#ILS l t

A.1. 4.1 Reactor Yessel Partial Penetration Welds, Item B4.10  !

A.1. 4.1.1 Vessel bzzles. Item B4.11 }

.I The external surfaces of partial penetration welds on 25% of reactor  ;

vessel nozzles shall be visually examined (VT-2) during the first inspec- -

tion interval. The examinations shall cumulatively cover the specified '

percentage among each group of penetrations of comparable size and function.  :

i A.1. 4.1. 2 Control Rod Drive Nozzles, Item B4.12 l The external surfaces of partial penetration welds on 255 of the ,

control rod drive nozzles shall be visually examined (VT-2) during the  ;

first inspection interval. The examinations shall cumulatively cover the '

specified percentage among each group of penetrations of comparable size b and function.

A.1. 4.1. 3 Instrumentation bzzles, Itew B4.13 The external surfaces of partial penetration welds on 25% of the instrumentation nozzles shall be visually examined (YT-2) during the first ,

inspection interval. The examinations shall cumulatively cover the  !

specified percentage among each group of penetrations of comparable size and function.  ;

' A.1. 4. 2 Heater Penetration Welds on the Pressurizer, Item B4.20 The external surfaces of 25% of the heater eenetration welds on the '

pressurizer shall be visually examined (VT-2) during the first inspection i in terval . The examinations shall curalatively cover the specified per- l centage among each group of penetradons of com;, arable size and function. -

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i A.1. 5 CATEGDRY B-F, PRESSURE-RETAINING DIS $1MILAR METAL WELDS A.1. 5.1 Reactor Vessel bzzle-to-Safe End Butt Welds, Item B5.10 1 All nozzle-to-safe end butt welds in nominal pipe size greater than 4 in. in the reactor vessel shall be surface and volumetrically examined in .

accordance with Figure IWB-2500-8 during the first inspection interval. L.

The examinations may be performed coincident with the vessel nozzle i examinations required by Examination Category B:'). Dissimilar netal welds i between combinations of (a) carbon or low alloy steels to high alloy -

steels, (b) carbon or low alloy steels to high nickel. alloys, and (c) high I' alloy steel to high nickel alloys are included.

- A.1.5 . Reactor Vessel Nozzle-to-Safe End Butt Welds, Item B5.11 The surfaces of all nozzle-to-safe end butt welds in nominal pipe size

. less than 4 in. in the reactor vessel shall be examined in accordance with Figure IWB-2500-8 during the first inspection-interval. The examinations may be performed coincident with the vessel nozzle examinations required by

& Examination Category B-D. Dissimilar metal welds between combinations.of-(a) carbon or lw alloy steels to high alloy steels (b) carbon or icw -

alloy steels to high nickel alloys, and (c) high alloy steel to high nickel-alloys are included. <

i A.1.5.3 Reactor Vessel Ezzle-to-Safe- End Socket Welds, Item B5.12 The surfaces of all nozzle-to-safe end socket welds in the reactor vessel shall be examined in accordance with Figure IWB-2500 8 during the first inspection interval. The examinations may be performed coincident with the vessel nozzle examinations required by< Examination Category B-D.  !

8 Dissimilar metal welds-between combinations of (a) carbon or low alloy -

steels to high alloy steels, (b) carbon or low alloy steels to high nickel  :

alloys, and (c) high alloy steel to high nickel alloys are included. 3 A.1.5.4 Pressurizer bzzle-to-Safe End Butt Welds, -Item 85.20 -

All nozzle-to-safe. end butt welds in nominal pipe size greater than 4 in in the pressurizer shall be surface and volumetrically examined in accordance with Figure IWB-2500-8 during the first inspection interval.- -

Dissimilar metal welds between combinations of (a) carbon or low alloy j steels to high alloy steel, (b) carbon or low' alloy steel to high niekel alloys, and -(c) high alloy steel' to high nickel alloys are included, i A.1.5.5 Pressurizer Nozzle-to-Safe End Butt Welds, Item B5.21 -

The surfaces of all nozzle-to-safe end butt welds-in nominal pipe size less than 4 in. in the pressurizer shall be examined in accordance with - '

rigure IWB-2500-8 during the first inspection interval. Dissimilar metal

.A-6 o . ~ .

l welds between combin6tions of (a) carbon or lw alloy steels to high alloy steel, (b) carbon or Iw alloy steel to high niekel alloys, end (c) high alloy steel to high nickel. alloys are included.

A.1.5.6 Pressurizer %zzle-to-Safe End Socket Welds, Item B5.22 The surfaces of all nozzle-to-safe end socket welds in the pressurizer

( shall be examined in accordance with Figure IWB-2500-8 during the first inspection interval. Dissimilar metal' welds between combinations of (a) l carbon or low alloy steels to high alloy steel, (b) carbon or lw alloy steel to high niekel alloys, and (c) high alloy steel to high niekel alloys are included. j i

o A.1.5.7 Steam Generator Nozzle-to-Safe End Butt Welds, Item B5.30-All nozzle-to-safe end butt welds in nominal pipe size greater than 4 in. in the steam generator shall be surface and volumetrically examined.

in accordance with Figure IWB-2500-8 during the first inspection interval.

Dissimilar metal welds between conbinations- of (a) carbon or low alloy U steels to high alloy steel, (b) carbon or low alloy steel to high nickel alloys, and (c) high alloy steel to high nickel alloys are included. .

A.1'.5.8 Steam Generator Nozzle-to-Safe End Butt Welds, Item B5.31 The surfaces of all nozzle-to-safe end butt welds in-nominal pipe size less than 4 in. in the steam generator shall be examined in accordance with -

Figure IWB-2500-8 during the first inspection interval. Dissimilar metal welds between conbinations of (a) carbon or. low alloy steels to high alloy steel, (b) carbon or low alloy steel to high nickel alloys, and (c) high alloy steel to high nickel alloys are included. j i  :

c 1.5.9 _ Steam Generator Nozzle-to-Safe End Socket Welds, Item B5.32 The surfaces of all nozzle-to-safe end socket welds in the steam .

. generator shall be examined in accordance-with Figure IWB-2500-8 during the- ,

firs, inspection interval . . Dissimilar metal welds between combinations of '

(a) cerbon or low alloy steels to high alloy steel, (b) carbon or low alloy steel to high nickel alloys, and (c) high alloy steel to high' nickel alloys  !

are italuded.

A.1.5.10 Heat Exchanoer Nozzle-to-Safe End Butt Welds, Item B5.40 All nozzle-to-safe end butt welds in nominal pipe size greater than j

, 4 in. in the heat exchangers shall be surface and volumetrically examined 1

in accordance with Figure IWB-2500-8 during the first inspection interval. I i Dissimilar metal welds between combinations of (a) carbon or low alloy

, steels to high alloy steel, (b) carbon or low alloy steel to high nickel alloys, and (c) high alloy steel to high niekel alloys are included, j

, 1 1

A-7

i A.1.5.11 Heat Exchanger Nozzle-to-Safe End Butt Welds, Item B5.41  !

All nozzle-to-safe end butt welds in nominal pipe size less than 4 in.

in the heat exchangers shall be surface and volumetrically examined in ac-cordance with Figure IWB-2500-8 during the first inspection interval. Di s- .

similar mc Lt1 welds between combinations of (a) carbon or low alloy steels i to high alloy steel, (b) carbon or low alloy steel to high nickel alloys, j end (c) high alloy steel to high nickel alloys are included.

l A.1.5.i? liegt Exchanoer Nozzle-to-Safe End Socket Welds, Item B5.42  !

All nozzle-to-safe end socket welds in the heat exchangers shall be surface and volunetrically examined in accordance with Figure IWB-2500-8 during the first inspection interval. Dissimilar metal welds between conbinations of (a) carbon or low alloy steels to high alloy steel, (b) i carbon or low alloy steel to high nickel alloys, and (c) high alloy steel '

to high nickel alloys are included.

U A.1.5.13 Piping Safe End Butt Welds. Item B5.50 All dissimilar metal safe end butt welds in piping greater than 4 in.

shall be surface and volumetrically examined in accordance with Figure IWB-2500-8 during the first inspection interval. Dissimilar metal welds between conbinations of (a) carbon or low alloy steels to high alloy steel, (b) carbon or low alloy steel to high nickel alloys, and (c) high alloy ,

steel to high nickel alloys are included, t A.1.5.14 Piping Safe End Butt Welds, Item B5.51 I All dissimilar metal safe end butt welds in piping less than 4 in, shall be surface and volunetrically examined in accordance with Figure IWB-2500-8 during the first inspection interval. Dissimilar metal welds between conbinations of (a) carbon or lov -alloy steels to high alloy steel, (b) carbon or low alloy steel to high nickel alloys, and (c) high alloy steel to high nickel alloys are included.

A.1.5.15 Piping Safe End Socket Welds, Item B5.52 l

All dissimilar metal safe end socket welds in piping shall be surface'  !

and voluretrically examined in accordance with Figure IWB-2500-8 during the first inspection interval. Dissimilar metal welds between combinations of (a) carbon or low alloy steels to high alloy steel,. (b) carbon or low alloy steel to high nickel alloys, and (c) high alloy steel to high nickel alloys are included.

A-8

. i A.1.6 CATEGORY B-G-1, PRESSURE-RETAINING BOLTING LARER:THAN.2 INCHES - -

IN DIAMETER A.1. 6.1 Reactor Closure Head Ests. Item B6.10 The surfaces of all reactor closure head nuts larger than 2. in, in '

diameter shall be examined during:the first inspection interval. Bol ting i may be examined (a) in place under tension, (b) when the connection is i disassembled,- or (c) when the bolting is removed. Examinations may be performed at.or near.the end of the inspection interval. <

A.1.6. 2 Reactor Closure Studs, in Place, -Items B6.20 and B6.30 All. closure studs in the. reactor vessel larger than 2 in. in diameter shall be volumetrically examined in-accordance with Figure IWB-2500-12 during the-first inspection interval. A surface examination is' also' required when the studs'are removed. Examinations may be performed att i or.near. the end of the inspection interval. l A.1. 6. 3 Threads in the Flange in the Reactor Vessel Item 86.40 -

All threads in the flange in the reactor vessel shall be volumetrically examined in accordance with IWB-2500-12 during the first inspection interval. . Examination includes threads in base metal and is required only' t when the connection is disassembled. Examinations may be performed at or '

near the end of the inspection interval.

A.1. 6. 4 Reactor Closure Washers and Bushings, Item B6.g U The surfaces of 411 closure washers and bushings on bolting larger than 2 in. in diameter in the reactor vessel shall:be visually examined (VT-1)'

during the first inspection interval. Burhings in base material, of flanges  :

are required to be examined only when the connections are disassembled; bushings _may be examined in place. The examinations may be performed at or i near the end of the inspection interval.

A.1.6.5 Pressurizer Bolts, Studs, and Flange Surfaces, Items B6.60 and B6.70 ,

All bolts and studs larger than 2'in. in diameter in the pressurizer shall be volumetrically examined in accordance with IWB-2500-12 during- the first inspection interval .. Bolting may be examined (a) in- place under ten-

-sion, (b) when the . connection-is disassenbled, or (c) when the bolting is ,

removed. The-flange surfaces shall also be visually examined (VT-1) when.

the connection -is disassembled. The examination includes 1-in, of the annular surface surrounding each stud. Examinations may be performed at or near the end of the inspection-interval.

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A.1.6.6 Pressurizer Nuts, Bushings, and Washers, Item B6.80

, The surfaces of al' uts, bushings, and washers on bolting larger than 2 in. in diameter shall se visually examined (VT-1) during the first in-spection interval . Bushings in the base material of flanges are required to be examined only when the connections are disassembled; bushings say be ,

inspected in place. Bolting may be examined (a) in place under tension, (b) when the connection is disasse21ed, or (c) when the bolting is removed.

Examinations may be performed at or near the end of the inspection interval.

A.1.6.7 Bolts, Studs, and F1anoe Surfaces in Steam Generators, Items B6.90 and B6.100 All bolts and studs larger than 2 in..in diameter in steam generators shall be volumetrically examined in accordance with IWB-2500-12 during the first inspection interval. Bolting may bc examined (a) in place under.

tension, (b) when the connection is disassembled, or (c) when the bolting is removed. The flange surfaces shall also be visually examined (VT-1) when the connection is disasse21ed. The examination includes l' in. of the 4

annular surface surrounding each stud. Examinations may be performed at or I near the end of the inspection interval.

A.1 6.8 Nuts, Bushings, and Washers in Steam Generators Item B6.110 i The surfaces of all nuts, bushings, and washers on bolting larger than j 2 in. in diameter in steam generators shall be visually examined (VT-1) .

, during the first inspection interval. Bushings in the base material of -

flanges are required to be examined.only when the connections are dis-I assembled; bushings may be inspected in place. Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed. Examinations may be-performed at or near l' the end of the inspection interval.

A.1.6.9 Bolts. Studs, and Flance Surfaces in Heat Exchanoers, Items ETTE6 and B6.130 All bolts and studs larger than 2 in. in diameter in hea.t exchangers shall be volunetrically examined in accordance with IWB-2500-12 during : the first inspection interval. Bolting may be examined (a) in place under tension, (b) when the connection is disassesled..or (c) when the bolting-is removed. The flange surfaces shall also be visually examined (VT-1) when the connection is disasse21ed. The examination includes 1 -in of' the annular surface surrounding each stud. Examinations may be performed at or near the end of the inspection interval. Examinations are limited to bolts and studs on components selected for examination under Examination '

i Categories B-B, B-J, B-L-1, and B-M-1, as applicable. l l

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A.1.6.10 Nuts, Bushings, and Washers in Heat Exchangers, Item B6.140 The surfaces of all nuts, bushings, and washers on bolting larger than 2 in, in diameter in heat exchangers shall be visually examined (VT-1) during the first inspection interval. Bushings' in the base material of flanges are required to be examined only when the connections are dis-assembled; bushings may be inspected in place. Bolting may be examined (a). in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed. Examinations may be performed at or near the end of the inspection interval. Examinations are limited to bolts ant ,

studs on components selected for examination under Examination Categories B-B, B-J, B-L-1, and B-N-1, as applicable. ,

l A.1.6.11 Bolts , Studs , and Flange - Surfaces in. Piping, Items' B6.150 and B 6.160 All bolts and stu'ds larptr than 2 in. in diameter in piping shall be volumetrically examined in accordance with IWB-2500-12 during the first inspection interval.- Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is re-l moved. The flange surfaces shall also be visually examined (VT-1) when the-connection is disassembled. The examination includes 1 in, of the annular .

surface surrounding each stud. Examinations may be performed at or near the end of the inspection interval.

A.1.6.12 Nuts, Bushingt, and Washers in Piping, Item B6.170 The surfaces of all nuts, bushings, and washers on bolting larger than 2 in. in diameter in piping shall be visually examined (VT-1) during the first inspection interval. Bushings in-the base material of flanges are required to be examined only when the connections are disassenbled; y bushings may be inspected in place. Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when '.he bolting is removed. Examinations may be performed at or near the and of the inspection interval.

A.1.6.13 Bolts, Studs, and Flange Surfaces in Pumos, Items B6.180 and B6.190 All bolts and studs larger than- 2 in. in diameter in pumps shall be volumetrically examined in accordance with IWB-2500-12 during the first inspection interval . Bolting may be examined (a) in place under tension, (b) when the connection is disassenbled, or (c) when the bolting is re-wv ed. - The flange surfaces shall also be visually examined (VT-1) when the cocnection is disassembled. The examination includes 1.in, of the annular surface surrounding each stud. Examinations may be performed at or near the end of the inspection interval. Examinations are limited to bolts and studs on components selected for examination under Examination Categories B-B, B-J, B-L-1, and B-M-1, as applicable.

A-11

l 0 4 A.1.6.14 Nuts , Bushings , and- Washers in Pumps, Item B6.200-l The surfaces of all nuts, bushings, and washers in bolting larger than '

l 2 in, in diameter in pumps shall be visually examined (VT-1) during the first inspection interval . Bushings in the base material of flanges are l~

required to be examined only when the connections are disasseeled; r bushings may be inspected in place. Bolting may be examined (a) in place under tension, (b) when the connection is disassesled, or (c) when the i bolting is removed.- Examinations may be performed at or near. the end of the inspection interval. Examinations are limited to bolts and studs on i components selected for examination under Examination Categories B-B, B-J, B-L-1, and B N-1, as applicable.

l t

l A.1.6.15 Bolts , Studs, and F1anoe Surfaces in Valves, Items B6.210 and '

l B6.220 All bolts and studs larger than 2 in, in diameter in valves shall be-  ;

volumetrically examined in accordance with IWB-2500-12 during the first '

inspection interval. Bolting may be examined (a) in place under tension, 1 (b) when the connection is disassembled, or (c) when the bolting is re-moved. The flange surfaces shall also be visually examined (VT-1) when the .

connection is disassesled. The examination includes 1 in, of the annular surface surrounding each stud. Examinations may be' performed at or near the end of the inspection interval. . Examinations are limited to bolts and studs on components selected for examination under Examination Categories B-B, B-J, B-L-1, and B N-1, as applicable.

! A.1.6.16 Nuts, Bushings, and Washers in Valves Item B6.230

.L h The surfaces of all nuts, bushings, and washers on bolting larger than >

2 in. in diameter in valves shall be visually examined (YT-1) during the-first inspection interval. Bushings in the base material of flanges-are required to be examined only when the connections are disassesled, but' bushings may be inspected in place. Bolting may be examined (a)~ in place under tension, (b) when the connection is disasse21ed, or (c) when the bolting is removed. Examinations may be performed at or near-the end of the inspection interval. Examinations are limited to bolts and studs on  ;

components selected for examination under Examination Categories B-B, B-J, B-L-1, and B-M-1, as applicable.

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. A.1.7 ~ CATEGORY B-G-2, PRESSURE-RETAINING BOLTING 2 INCHES AND SMALLER ,

IN DIAMETER L

A.1. 7 .1 Bolts Studs, and Wts in Reactor Vessel Item B7.10 The surfaces.of all'. bolts, studs,.and nuts 2 in, or less in diameter in the reactor vessel shall be visually examined (VT-1) during:the first ,

inspection interval . Bolting may be examined (a) in place under tension, (b) when the connection is disasseeled, or (c) when the bolting is. removed.

A.1.7 . 2 Bolts, Studs ,' and Wts in Pressurizer, Item B7.20 The surfaces of all bolts, studs, and nuts 2.in. or.less in-diameter in-the pressurizer shall. be visually examined (VT-1) during the first '

inspection interval. Bolting may be examined (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed. i A.1.7. 3 Bolts, Studs, and %ts-in Steam Generators- Item B7.30

< . The surfaces of all bolts, studs, and nuts 2 in. or less in diameter in -

. the steam generators shall be. visually examined (YT-1) during the' first i inspection interval. ~ Bolting may. be examined-(a) in place under tension, i (b) when the connection is disassembled,'or (c) when the bolting is removed.

1 A.1.7.4 Bolts , Studs , and Wts in Heat Exchangers, Item B7.40' The surfaces of all bolts, studs, and-nuts 2 in. or less in diameter in i the heat exchangers: shall be. visually examined (VT-1) during the first inspection interval. Bolting may be examined (a) in place under tension, Li

,b (b) when the connection is disasseeled, or (c) when the bolting is removed.

! A.1. 7 . 5 Bolts, Studs, and Wts in Piping, Item B7.50 i

The sur' aces of all bolts, studs, an'd nuts 2 in, or less in diameter 1r-piping shall be visually examined (VT-1) during the first inspection 4

in terval . Bolting may be examined.(a) in place under tension,. (b) when i the connection is disassembled, or (c) when the bolting is. removed, y i

A.1.7.6 Bolts, Studs, and Wts in Pumps, Item B7.60 4

The surfaces of all bolts, studs, and nuts 2 in. or less in diameter in:  :

pumps shall be visually er,amined (VT-1) during the first inspection ~f

, in terval . Bolting may be examined (a) in place under tension, (b) when-the connection is disassembled, or (c) when- the bolting is removed.

A-13 I ,

i

i .,

l,

- A.1.7.7 Bolts Studs, and Wts in Valves, Item B7.70 The surfaces of all bolts, studs, and nuts 2 in. or less in diameter in .

valves shall be visually examined (VT-1) during the first inspection inter- l

! val. Bolting may be examined (a) in place under tension, (b) when the j

connection is disassenbled, or (c) when the bolting is removed.

V l

A.1.7.8 Bolts, Studs, and Wts in Control Rod Drive Housings. Ittm B7.80 The surfaces of all bolts, studs, and nuts 2 in, or less in diameter in control rod drive housings shall be visually examined (VT-1) during the first inspection interval when disassembled.

A.1. 8 CATEGORY B-H, VESSEL SWPORTS I A.1.8.1 Inteorally Welded Attachments in Reactor Vessel , Item B8.10 .

The attachment weld joining the. reactor vessel support to the pressure-

. retaining membrane of the reactor vessel where the support base material design thickness is 5/8 in or greater shall be surface or volumetrically examined, as applicable, in accordance with Figures IWB-2500-13. -14, and

-15 during the first inspection interval. Weld buildups on nozzles that serve as supports are excluded. The examination includes essentially 100%

of the length of the weld to the reactor' vessel and the integral attachment weld to a cast or forged integral attachment to the reactor vessel, as applicable. One hundred percent of the welding of each lug on the vessel g

is included in the examination.

A.1.8.2 ' Integrally Welded Attachments in Pressurizer, Item B8.20 The attachment weld joining the pressurizer vessel support to the -

pressure-retaining membrane of the reactor vessel where the support base material design thickness is 5/8 in, or greater shall be surface or volu-metrica11y examined, as applicable, in accordance with Figures IWB-2500-13,

-14, and -15 during the first inspection interval. Weld butidups on nozzles that serve as supports are excluded. The examination includes essentially 100% of the length of the weld to the pressurizer and the integral attachment weld to a cast or forged integral attachment to the pressurizer, as applicable. One hundred percent of the welding of each lug on the vessel is included in the examination.

A-14 L -_ . .. . _ _ _ ..~. - _ _ _ _ _ _ _ ..

A.1.8.3- Inteorally Welded Attachments in Steam Generators, Item B8.30 l The attachment weld joining the steam generator support to the

-pressure-retaining membrane of the generator where the support base material design thickness is 5/8 in, or greater shall be surface or volumetrically examined, as applicable, in accordance with Tigures IWB-2500-13, -14, and -15 during the first inspection interval. Weld buildups on nozzles that serve as supports are excluded. The examination includes essentially 100% of the length of the weld to the steam generator and the integral attachment weld to a cast or forged integral attachment to the steam generator, as applicable. One hundred percent of the welding _of each lug on the vessel is included in the examination. The examination is I limited to the attachment weld on one steam generator.

'. A.1.8.4 Integrally Welded Attachments in Heat Exchangers. Item B8.40 l The attachment weld [oining the heat exchanger support to the pressure- 1 retaining membrane of the heat exchanger where the support base material design thickness is 5/8 in, or. greater shall be surface or volumetrically examined, as applicable, in accordance with Figures IWB-2500-13. -14, and ll -15 during the first inspection interval . Weld buildups on nozzles that serve as supports are excluded. The examination includes essentially 100% ,

of the length of the weld to the heat exchanger and the integral attachment weld to a cast or forged integral attachment to the heat exchanger, as applicable. One hundred percent of the welding of each lug on the heat exchanger is included in the examination. The examination is limited to the attachment weld on one heat exchanger.

t l

A.1. 9 CATEGORY B-J, PRESSURE-RETAINING WEl.DS IN PIPING ll A.1. 9.1 kminal Pipe Size 4 In. and Greater, Item B9.10 l

A.1.9.1.1 Circumferential Welds, Item B9.11 For circumferential welds in pipe of nominal pipe size 4 in and I

greater, surface plus volumetric examinations shall be performed in ac-cordance with Figure IWB-2500-8 over essentially 100% of the weld length during each inspection interval. The examination shall include the following:

la) All terminal ends in each pipe or branch run connected to vessels.

(b) All terminal ends and joints in each pipe or branch run connected to other components where the stress levels exceed the following limits under loads associated with specific seismic events and operational conditions. l A-15

,. e .- o e r l

. l L .

^

- (1 ) primary plus secondary stress intensity of 2.4Sm.for ferritic steel and austenitic steel, and I

(2)l cumulative usage factor U of 0.4..

(c) ' All dissimilar metal welds between conbinations of la) carbon or low alld steels to high alloy steels; i l-(b) carbon or low alloy steels to high nickel alloys;.and l

(c) high alloy steels to high nickel alloys..  ;

L (d) Additional piping welds so that the total number of circumferential i' butt welds selected for examination equals 25% of the circumfer- -

l ential- buttLwelds in the reactor coolant piping system. This total does not inelude welds exc1uded by IWB-1220. These addi- :

.. tions1 welds mny be located-in one loop (one loop is currently-defined for both PWR and BWR plants in tha 1980 Edition).-  !

For welds in carbon or low alloy steels, only those welds showing  ;

reportable preservice transverse indications need be examined for transverse reflectors, i j '

A.1.9.1.2 Longitudinal Welds Item B9.12 For longitudinal welds in pipe of nominal- pipe size 4 in, and greater.  !

l surface plus volumetric examinations shall be performed in accordance with

! Figure IWB-2500-8 for at least a pipe-diameter length, but not more than 12 '

in, of each longitudinal weld intersecting the circumferential welds re--

quired to be examined by Examination Categories B-F and B-J. For welds in -

carbon or icw alloy steels, only those welds: showing reportable preservice :

transverse indications need be examined for transverse reflectors. .

l A.1.9.2 Nominal Pipe Size less Than 4 In., Item 89.20 ~

i A'.1. 9. 2.1 Circumferential Welds, Item B9~ 21 .

'For circumferential welds in pipe of nominal pipe size less than 4 in.,-

surface examinations shall be performed int accordance with-Figure IWB-2500-8 over essentially 100% of the weld length during each inspection: 1 interval . The examination'shall include'the following:.

(a) All terminal ends in each pipe'or branch run connected to vessels. ,

(b) All. terminal ends and-joints int each pipe:or< branch run connected to other components where the stress levels exceed the following (

limits under loads- associated with specific seismic events and' operational conditions.

A-16 t

4

_u___.____. . . . . . _ _ - _ . . . . . . . _ . . _ , ,_ .- . _ . , _ , _ . . . .

13 o.

• 0 I (1) primary plus secondary stress intensity of 2.4Sm.for ferritic steel and austenitic steel, and.

. (2) cumulative usage factor U cf 0.4.

(c) All dissimilar metal welds between conbinations of:

(a) carbon or low alloy steels to high alloy steels;-

(b) . ci rbon or low alloy steels: to high. nickel alloys;.and (c) hi ,h alloys steels to.high nickel alloys.

(d) Additici il piping welds so that the total nunber of circumfer .

ential b .tt welds selected for examination equals 25% of the circumic ential butt welds in the reactor cociant piping system.

This total does not include welds; excluded by-IWB-1220.. These-additional welds any be located in one loop (one loop is currently-defined for both PWR and. BWR plants in the 1980 Edition).

A.1 9.2.2 - Longitudinal Welds, Item B9.22 p For longitudinal welds in pipe of nominal pipe size less than 4 in.,

- surface examinations shall be performed in accordance with Figure IWB- ,

2500-8 for at least a pipe-diameter length, but not more than 12 in. of -

each longitudinal weld intersecting the circumferential welds required to

- be examined by Examination Categories B-F and 8-J.

A.1.9. 3 Branch Pipe Connection Welds, Item B9.30 '

A.1.9. 3.1 kminal Pipe Size 4 Inches and Greater, Item B9.31 g For welds-in branch connections 4'in, and. greater, surface plus-

. volumetric examinations shall be performed in accordance with Figures IWB-2500-9, -10 and -11 over essentially 100% of the weld length during each ' inspection interval. The examinations shall include the!following:.

(a) All terminal ends in(each pipe or branch run connected to vessels.

(b) All terminal ends and joints in each pipe or branch run-connected to other components. where the stress-levels exceed the1following limits under loads associated with specific seismic events and.

operational conditions.

(1 ) primary plus secondary stress intensity of 2.'4Sm for ferritic steel and austenitie steel', and (2) cumulative usage factor U of 0.4.

i A-17

, e- .- 5I (c)- All ' dissimilar metal welds between combinations of:- ,

(a)' carbon orjlow alloy: steels:to high alloy steels; i L(b)-- carbon or low' alloy steels to high nickel alloys; and- H

'(c ) high alloy steels to high nickel alloys.-

(d) ~~ Additional' piping welds so' that the total number of circumfer-

.ential butt welds selected for examination equals 25% of the .

circumferential butt ~ welds in the reactor coolant piping system.

This total does not include welds excluded by IWB-1220. These additional welds may be located in one loop (one loop .is ~ currently ^

defined for both.PWR andiBWR plants inLthe 1980 Edition).

For welds in carbon. or low alloy steels, only those welds showing.

reportable preservice transverse indications need be examined for1

. transverse reflectors. .

=s A.1.9.3.2 Nominal- Pipe Size i.ess Than 4 Inches, Item B9.32 '

For welds in branch pipe' connections less than 4 in.,- surface ,

.i examinations'shal1 ~ be performed in accordance with Figures IWB-2500-9, i

-10, and -11 over essentia11y' 100% of the weld-length during each -

inspection interval. The examinations shall include the following:.

(a) All terminal, ends in each pipe or branch run connected to vessels..

(b) All terminal ends and joints in each pipe or branch run conneeted-to other components where the stress levels exceed the following.

limits-under loads associated with specific seismic events and i operational conditions.

4 (1 ) primary plus secondary stress intensity of 2.4Sm for ferritice i steel and austenitic steel, and: 3 (2) cumulative usage factor U of 0.4.

(c)- All dissimilar metal: welds ~ between conbinations of: J (a) carbon or low alloy steels to high' alloy steels; .

(b): carbon or low alloy steels to high nickel alloys; and i (c) high alloy steels to high1 nickel alloys..

(d) Additional piping welds so that the total number of circumfer-ential butt welds selected fortexamination ' equals 25% of the circumferential butt welds in the reactor coolant piping system.:

This total does not include welds excluded by IWB-1220. These additional welds may be located in one loop (one'1oop is currently

l. defined for both PWR and BWR plants in the 1980' Edition).

A-18

-l

• --------_-----.______a+ -

__________-_a__------

-- - - +- _c- , a w-,--.- -wwwewe w w e- we sw we--we e --+,:re v- + e- -,aW s--

1

l. c .

A.1.9.4 Socket Wel ds ,' Item B9.40 i L Socket welds shall be surface examined in accordance with Figure l

IW3-2500-8 over essentially 100% of the weld length during each inspection interval.- 'The examinations shall include the following:

(a) All terminal ends 'in each pipe = or branch run connected to vessels.

(b) ' All terminal ends and joints in each pipe or branch run connected

! to other components where the stress levels exceed the following i limits under loads associated with specific seismic events and l- operational conditions,

! (1 ) primary plus ' secondary stress intensity of 2.4Sm for ferritic i steel and austenitic steel, and

- ( 2) cumulative usage factor U of 0.4.

(c) All dissimilar metal welds between cotinations'of:

(a) carbon or low alloy steels to high alloy steels;

-(b) carbon or low alloy steels to high nickel alloys; and

'b. (c) high alloy steels to high nickel alloys. ,

(d) Additional piping welds so that the total nuser of circumfer-ential butt welds selected for examination-equals 25% of the circumferential butt welds in the reactor coolant piping system.

This total does not include welds excluded by IWB-1220 -These additional welds nay be located in one loop (one loop is currently defined for both PWR and BWR plants in the 1980 Edition).

I CATEGORY B-K-1, INTEGtAL ATTACFNENTS FOR PIPING, PIMPS, AIO VALVES A.1.10 f' A.1.10.1 Integrally Welded Attachments on Piping, Item 810.10 i-Volumetric or surface examinations, as applicable, per Figures IWB-2500-13 -14, and -15 of essentially 100% of the weld length are required for all integrally welded support attachments of piping. Incl udes -

the welded attachments of piping required to be examined by Examination ,

Category B-1 and the weld attachments of associated pumps and valves in-tegral to such piping. Includes those attachments whose base material

, design thickness is'5/8 in, or- greater.

A.1.10.2 Integrally Welded. Attachments on Pumps, Item B10.20 Volumetric or surface examinations, as applicable, per Figures IWB-2500-13, -14, and -15 of essentially 100% of the weld len9th are j required for all integrally welded support attachments of pumps. Includes the welded attachments of piping required to be examined by Examination j

A-19

I Category B-J and the weld attachments of associated pumps and valves in-tegral to such piping. Includes those attachments whose base ~ material design thickness.is 5/8 in, or greater..

A.1.10.3 Integrally Welded Attachments on Valves,' Item 810.30 Volunetric'or surface examinations, as applicable, per Figures IWB-2500-13, -14, and -15 of essentially 100% of the weld length are required for all integrally welded support attachments of valves. Includes the welded attachments of piping required by Examination Category B-J and the weld attachments of associated pumps and valves integral to such piping.

Includes those attachments whose base material design thickness is 5/8 in, or greater.

O A.1.11 CATEG^61ES B-t-1 AND B-M-1, . PRESSURE-RETAINING WELDS IN PUMP CASINGS AND VALVE E0 DIES, AND B-L-2 AND B-M-2, PUMP CASINGS AND VALVE BODIES

'p. A.1.11.1 Pump Casing Welds, Item B12.10 Essentially 100% of the pressure-retaining welds in at least one pump in each group of pumps performing similar functions in the system (e.g.,

recirculating coolant pues) shall be volumetrically examined in accordance with Figure IWB-2500-16 during each inspection interval. The examinations may be performed at or near the end of the inspection interval.

A.1.11.2 Pump Casings, Item 812.20 The internal surfaces of at least one pu@ in each group of pugs per-

) forming similar functions in the system (e.g., recirculating coolant punps)-

shall be visually examined (VT-3) during each inspection interval. The examination may be performed on the same pump selected for volumetric examination of welds. - The examinations may be performed at or near the end of the inspection' interval.

A.1.11.3 Valve Body Welds Nominal Pipe Size Less than 4 in.,- Item B12.30 The surfaces of essentially-100% of the body welds (nominal. pipe size less than 4 in.) in at least one valve. in each group'of valves with- the same construction design (e.g., globe, gate, or check valve) and manufacturing .

method that perform similar functions in the system (e.g., containment iso-lation and system overpressure protection) shall. be examined in accordance with Figure IWB-2500-17 during. each inspection interval. The examinations may be performed at or near. the end of the inspection interval.

A-20

4 .

k.1.11.3.1 Valve Body Welds , Eminal Pipe Size 4 In. and Greater, _ _

Item B12. 31 Essentially 100% of the body welds (nominal pipe size' 4 in, and greater) in at least one valve in each group of valves with the same con-struction design (e.g., globe, gate, or check valve) and manufacturing method that perform similar functions in the system (e.g., containment isolation and system over-pressure protection) shall be volumetrically examined in accordance with Figure IWB-2500-17 during each inspection in terval . A supplementary surface examination may be performed as required in IWB-3518.1(d).- The examinations may be performed at or near the end of the inspection = interval .

A.1.11.4 Valve Body Exceeding 4 In. %minal Pipe Size, Item B12.40 i

~

The internal surfaces of at least one valve in each group of valves l with the same construction design (e.g., globe, gate, or check valve) and manufacturing method that perform similar functions that exceed 4-inch diameter in the system (e.g., containment isolation and system overpressure protection) shall be visually examined (VT-3) during each inspection

-l interval . The examination nay be performed on the same valve selected for volumetric examination of welds. The examinations may be performed at or '

s near the end of.the inspection interval.

A.1.12 CATEGORIES B-N-1, INTERIOR OF REACTOR VESSEL; B-N-2, INTEGRALLY WELDED CORE SUPPORT STRUCTURES A2 INTERIOR ATTACH 4ENTS TO REACTOR VESSELS; and B-N-3, RD40VABLE CORE SUPPORT STRUCTURES A.1.12.1 Reactor Vessel Interior, Item B13.10 ui The accessible areas of the reactor vessel interior, including the .

spaces above and below the reactor core that are made accessible by  !

removing components during normal refueling outages, shall be visually examined (VT-3) during the first refueling outage and subsequent refueling outages at approximately 3-year intervals.

A.1.12.2 Boiling Water Reactor Vessel Interior Attachments, Item B13.20 The accessible welds in the reactor vessel interior attachments 'shall be visually examined (VT-1) during each inspection interval. The examina- i tions may be performed at or near the end of the inspection interval.

A.1.12.2.1 Boiling Water Reactor Core Support Structure, Item B13.21 The accessible surfaces of the core support structure shall be visually I examined (VT-1) during each inspection interval. The examinations ney be performed at or near the end of the inspection interval.

A-21

o 1

I 5.1.12.3 Core Support Structure for Pressurized Water Reactor Vessels.

Item B13. 30 The accessible welds and surfaces of the core support structure shall be visually examined ( YT-3) each inspection interval. The structure shall be removed from the reactor vessel for examination. The examinations may be perforned at or near the endof the inspection interval.

4 A.1.13 CATEGDRY B-0, PRESSURE-RETAINING WELDS IN CONTROL ROD HOUSINGS A.1.13.1 Welds in Control Rod Drive Housings, Item B14.10 The welds in 10% of the peripheral control rod drive housings shall be surface or volumetrically examined in accordance with Figure IWB-2500-18 during each inspection interval. The examinations may be performed.at or near the end of the inspection interval.

1 A.1.14 CATEGORY B-P, ALL PRESSURE-RETAINING CG!PONENTS ~

A.1.14.1 Reactor Vessel Pressure-Retaining Boundary, Item -

B15.10

(:

The reactor vessel pressure-retaining boundary shall be visually examined ( VT-2) during the system leakage test performed in accordance with IWB-5221 during each refueling outage. System pressure tests of the l

reactor coolant system shall be conducted in accordance with IWA-5000.

System pressure tests for repaired, replaced, or altered components shall l be governed by IWA-5214(c). The pressure-retaining boundary during the lg system leakage test shall correspond to the reactor coolant system boundary with all valves in- the normal position which is required for normal reactor operation startup. The VT-2 examination shall, however, extend to and .

include the second closed valve at the boundary extremity. A system hydro-static test (IWB-5222) and the accompanying VT-2 examination are acceptable I in lieu of the system leakage test (IWB-5221) and VT-2 examination.

A.1.14.1.1 Reactor Vessel Pressure-Retaining Boundary, Item B15.11 The reactor vessel pressure-retaining boundary shall be visually.

examined (VT-2) during the system hydrostatic test performed in accor-dance with IWB-5222 once per inspection = interval. The pressure-retaining boundary during the test shall include all Class 1 components within the system boundary. The examinations nay be performed at or near the end~of the inspection interval. . System pressure tests of the reactor coolant system shall be conducted .in accordance with IWA-5000. System pressure i tests for repaired, replaced, or altered components shall be governed by IWA-5214(c ).

l l

l A-22

7 k.1.14.2 P ressurizer Pressure-Retaining Boundary, Item B15.20 The pressurizer pressure-retaining boundary shall be visually examined

( VT-2) during the system leakage test perforned in accordance with IWB-5221 during each refueling outage. System pressure tests for the reactor coolant system shall be conducted in accordance with IWA-5000. System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c). The pressure-retaining boundary during the system leakage test shall correspond to the reactor coolant system boundary with all valves in the nornal position which is required for normal reactor operation startup. The VT-2 examination shall, however, extend to and include the second closed valve at the boundary extremity. A system hydrostatic test (IWB-5222) and the accompanying VT-2 examination are acceptable in lieu of the system leakage test (IWB-5221) and VT-2 examination.

A.1.14.2.1 Pressurizer Pressure-Retaining Boundary, Item B15.21 The pressurizer pressure-retaining boundary shall be visually examined (VT-2) during the system hydrostatic test performed in accordance with IWB-5222 once per inspection interval. The pressure-retaining boundary during I the test shall include all Class 1 components within the system boundary.

• The examinations may be performed at or near the end of the inspection in terval . System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000. System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c).

A.1.14.3 Steam Generator Pressure-Retaining Boundary, Item B15.30 The steam generator pressure-retaining boundary shall be visually g

examined (VT-2) during the system leakage test performed in accordance with IWB-5221 during each refueling outage. System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000.

System pressure tests for repaired, replaced or altered components shall be governed by IWA-5214(c). The pressure-retaining boundary during the system leakage test shall correspond to the reactor coolant system boundary with all valves in the nornal position which is required for normal reactor operation startup. The VT-2 examination shall, however, extend to and include the second closed valve at the boundary extremity. A system hydrostatic test (IWB-5222) and the accompanying YT-2 examination are-acceptable in lieu of the system leakage test (IWB-5221) and VT-2 examination.

A.1.14.3.1 Steam Generator Pressure-Retaining Boundary, Item B15.31 The steam generator pressure-retaining boundary shall be visually examined (VT-2) during the system hydrostatic test performed in accordance with IWB-5222 during each refueling outage. The examinations nay be A-23

performed at or near the end of the inspection interval. The pressure-retaining boundary during the test shall include all Class I components within the system boundary. System pressure tests of the reactor coolant

- system shall be cor. ducted in accordance with IWA-5000. System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c ).

A l.14.4 Heat Exchanoer Pressure-Retaining Boundary, Item B15.40 The heat exchanger pressure-retaining boundary shall be visually examined (VT-2) during the system leakage test performed in accordance with IWB-5221 during each refueling outage. System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000.

System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c). The pressure-retaining boundary during the system leakage test shall correspond to the reactor coolant system boundary with all valves in the normal position which is required for normal reactor operation startup. The VT-2 examination shall, hwever, extend to and include the second closed valve at the boundary extremity. A system hydro-

[;

static test (IWB-5222) and the accompanying VT-2 examination are acceptable in lieu of the system leakage test (IWB-5221) and VT-2 examination. , l A.1.14.4.1 Heat Exchanger Pressure-Retaining Boundary, Item B15.41 The heat exchanger pressure-retaining boundary shall be visually examined (VT-2) during the system hydrostatic test performed in accordance with IWB-5222 once per inspection interval. The pressure-retaining boundary during the test shall include all Class 1. components within the system boundary. The examinations nny be performed at or near the end of the inspection interval. System pressure tests of the reactor coolant 1 j: system shall be conducted in accordance with IWA-5000. System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c ).

A.1.14.5 Piping Pressure-Retaining Boundary, Item B15.50 The piping pressure-retaining boundary shall be visually examined (VT-2) during the system leakage test performed in accordance with IWB-5221-  ;

during each refueling outage. System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000. System pressure tests-for repaired, replaced, or altered components shall be governed by IWA-5214(c ). The pressure-retaining boundary during the system leakage test shall correspond to-the reactor coolant system boundary with all valves in the normal position which is required for normal reactor operation startup. The VT-2 examination shall, hwever, extend to and include the second closed valve at the boundary extremity. A system hydro-static test (IWB-5222) and the accompanying VT-2 examination are acceptable in lieu of the system leakage test (IWB-5221) and VT-2 examination.

A-24

,aa :

i A.1.14.5.1 Piping Pressure-Retaining Boundary, Item B15.51 The piping pressure-retaining boundary shall be visually examined l

(VT-2) during the system hydrostatic test performed in accordance with IWB-5222 once per inspection interval. The pressure-retaining boundary during the test shall include all Class 1 components within the systam boundary. The examinations say be perforned at or near the end of the inspection interval. System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000. System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c).

A.1.14.6 Pumo Pressure-Retaining Boundary, Item B15.60 l

The pump pressure-retaining boundary shall be visually examined (VT-2) l' during the system leakage test performed in accordance with IWB-5221 during each refueling outage. System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000. System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c).

System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000. System pressure tests for repaired, replaced, 3

or altered components shall be governed by IWA-5214(c). The pressure- '

retaining boundary during the system leakage test shall correspond to the reactor coolant system boundary with all valves in the nornal position which is required for nornal reactor' operation startup. The VT-2 exami-nation shall, however, extend to and include the second closed valve at

', the boundary extremity. A system hydrostatic test (IWB-5222) and the accompanying YT-2 examination are acceptable in lieu of the system leakage test (IWB-5221) and VT-2 examination, i

A.1.14.6.1 Pump Pressure-Retaining Boundary, Item B15.61 The pump pressure-retaining boundary shall be visually examined (VT-2) l during the system hydrostatic test performed in accordance with IWB-5222 once per inspection interval. The pressure-retaining boundary during the test shall include all Class 1 components within the system boundary. The i examinations nay be performed at or near the end of the inspection inter-val . System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000. System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c).

I i

A.1.14.7 Valve Pressure-Retaining Boundary, Item B15.70 The valve pressure-retaining boundary shall be visually examined ( VT-2) during the system leakage test performed in accordance with IWB-5221 during each refueling outage. System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000. System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c).

The pressure-retaining boundary during the system leakage test shall A-25 6

- - - - _ _ - - _ _ _ . - - - - - - - - - - - - - _ - - - - - - - - - .-,-~--r---,

-o .

0 a

correspond to the reactor coolant system boundary with all valves in the nornel position which is required for nornel reactor operation startup.

The VT-2 examination shall, however, extend to and include the second closed valve at the boundary extremity. A system hydrostatic test (IWB-5222) and the accompanying YT-2 examination are acceptable in Iteu of the system leakage test (IWB-5221) and YT-2 examination.

A.1.14.7.1 Valve P ressure-Retaining Boundary, B15.71 The valve pressure-retaining boundary shall be visually examined (VT-2) during the system hydrostatic test performed in accordance with IWB-5222 once per inspecticn interval. The pressure-retaining boundary during the test shall include all Class 1- components within the system boundary. .The examinations nay be performed at or near the end of the inspection interval.

System pressure tests of the reactor coolant system shall be conducted in accordance with IWA-5000. System pressure tests for repaired, replaced, or altered components shall be governed by IWA-5214(c).

U .

A.l .15 CATEGORY B-Q, STEAM GENERATOR TUBING ,

A.1.15.1 Steam Generator Tubing, Straight Tube Design, Item B16.10 The entire length of the steam generator tubing shall be volumetrically examined in 3% of the heating surface in each generator during the first inspection interval. The heat transfer surface is specified in terms of

• the number of tubes to be examined.

l' A.1.15.2 Steam Generator Tubing, U-Tube Design, Item B16.20 Steam generator tubing (hot leg side), U-bend portion, and cold leg ,

~

side (optional) shall be volumetrically examined in 3% of the heating surface in each generator during the first inspection interval.

i A-26 ,

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

t A.2. CLASS 2 REQUIREMENTS A. 2.1 - CATEGORY C-A, PRESSURE-RETAINING WELDS IN PRESSURE VESSELS r

A. 2.1.1 Shell Circumferential Welds, Item C1.10:

E:sentia11y 100% of the shell circumferential welds at gross structural discontinuities shall be' volumetrically-examined in accordance with Figure IWC-2520-1 during each inspection interval. A gross structural-discon-tinuity is defined in NB-3213.2. Examples are. junctions between shells of different thicknesses, cylindrical shell-to-conical shell junctions, and shell (or head)-to-flange welds and head-to-she11' welds. For multi pl e -

vessels with similar design, size, and service. (such as steam generators

', and heat exchangers), the required examinations may be-limited to one vessel or distributed among the vessels..

' A. 2.1. 2 Head Circumferential Weld, Item C1.20 1 Essentially 100% of the circumferential head-to-shell weld shall be volumetrically examined in accordance with. Figure IWC-2520-1 during each -

inspection interval. For multiple vessels with similar: design, size, and service (such as steam generators and heat-exchangers), the required -

examinations may be limited to one vessel or distributed among the vessels.

l '

A. 2.1. 3 Tubesheet-to-Shell Weld Item C1.30

! Essentially 100% of the tubeshee't-to-shell weld shall be volumetrically -

examined in accordance with Figure IWC-2520-2 during each. inspection inter- i val . For mul tiple vessels with similar design, size, and servire-(such as li . steam generators and heat exchangers), the required examinations say be limited to one vessel or distributed among the vessels.

1 A.2.2 CATEGORY C-B, PRESSURE-RETAINING N0ZZLE WELDS IN VESSELS

- A. 2. 2.1 Nozzles in Vessels 1/2 In. or Less in ibmina1LThickness',~ Item C2.10 i All nozzles in vessels 1/2 in, or .less :in nominal _ thickness at terminal ends of piping runs.shall be surface examined in accordance with~ Figure IWC-2520-3 during each . inspection interval. Terminal ends include nozzles welded to or integrally cast in vessels that connect to piping runs (man-ways and handholes are excluded). Only those piping runs . selected for exrmination under-Examination Category C-F are included..  :

A-27 I 1

m. _ __ .,. _ _ . , _ _ _ ~ . . . _ _ _ . ___ _ _ _ _

A.2.2.2 Nozzles in Vessels Over 1/2 In. in Nominal Thickness, Item C2.20 l

A. 2. 2. 2.1 Nozzle-to-Shell (or Head) Weld, Item C2.~21 l

' l l The nozzle-to-shell. (or head) welds of all nozzles in vessels over 1/2 in. in nominal. thickness at terminal ends of piping runs shall be -

(

surface and volumetrically examined in acenrdance with Figure IWC-2520-4 during each-inspection interval. Terminal ends include nozzles welded to ,

i or integrally castLin vessels that connect to piping runs (manways and handholes are excluded). Only those piping runs selected for examination under Examination Category C-F are included, t

A.2.2.2.2 Nozzle Inside Radius Section, Item C2.22 The inside radius sections of all nozzles in vessels over 1/2 in, in nominal thickness at terminal ends of piping runs shall be volumetrically examined in accordance with Figure IWC-2520-4 during each inspection interval. Terminal ends include nozzles welded to or integrally cast in

• vessels that connect to piping runs (manways and handholes are excluded). >

Only those piping runs selected for examination. under Examination Category I C-F are included.

2 A.2.3 CATEGORY C-C, SUPPORT MEMBERS A.2.3.1 Integrally Welded Support Attachments' in Pressure Vessels, item C3.10 t The . surfaces of 100% of each integrally welded attachment in pressure vessels shall be surface examined in accordance with Figure IWC-2500 .N during each inspection interval. Examination is' limited to integrally  :

welded attachments whose base material design thickness is 3/4 in. or greater. For 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 supporting elements, the examination of the support elements may.be distributed among the vessels.

B A.2.3.2 Integrally Welded Attachments in Piping, Item C3.40

,t The surfaces of 100% of each-integrally welded attachment in piping shall be surface examined in-accordance with Figure IWC-2500-5. Exami-nation is limited to integrally welded attachments whose base' material design. thickness is 3/4 in. or greater. In addition, examinations are-limited to attachments of those components required to be examined under Examination Categories C-F and.C-G.

i A-28

l i

A.2.3.3 Inteorally Welded Pump Attachments, Item C3.70 The surfaces of 100% of each integrally welded attachment in pumps '

i shall be examined in accordance with Figure IWC-250D-5. Examination is limited to integrally welded attachments whose base material design thickness is 3/4 in, or greater. Examinations are limited to attachments of those components required to be examined under Examination Categories C-F and C-G.

A.2.3.4 Integrally Welded Valve Support Attachments, Item C3.100 The surfaces of 100% of each integrally welded valve attachment shall be examined in accordance with Figure IWC-2500-5 during each inspection in terval . Examination is limited to integrally welded attachments whose base material design thickness 1s 3/4 in. or greater. Examinations are limited to attachments of those components required to be examined under Examination Categories C-F and C-G.

1 1

l' A.2.4 CATEGORY C-D, PRESSURE-RETAINING BOLTING GREATER THAN 2 INCHES IN DIAMETER A. 2. 4.1 Bolts and Studs in Pressure Vassels, Item C4.10 For bolts and studs in pressu < vessels,100% of the bolts and studs at each bolted connection of components required to be inspected shall be volumetrically examined in accordance with Figure IWC-2520-6 during each inspection interval.- Bolting may be examined on one vessel in each system p required to be examined that is similar in design, size, function, and l s ervice. In addition, where the vessel contains a group of bolted connec-tions of similar design and size (such as flange connections and manway c covers), only one bolted connection among the group need be examined.  ;

Bolting may be examined in place under load or upon disassembly of the connection. .

I A.2.4.2 Bolts and Studs in Piping, Item C4.20 f One hundred percent of the bolts and studs at each bolted piping connection shall be volumetrically examined in accordance with Figure IWC-2520-6. The examination of flange bolting in piping systems required to .

be examined nay be limited to the flange connections in pipe runs selected for examination under Examination Category C-F. Bolting may be examined in place under load or upon disassembly of the connection.

t i

1 1 A-29

, - - - - , , - w ,- a e w ,m-, , . -

I A.2.4.3 Bolts and Studs in Pumps, Item C4.30 For pumps,100% of the bolts and studs at each bolted connection of pumps shall be volumetrically examined in accordance with Figure IWC-2520-6. Bolting on only one pump among a group of pumps in each system 4 required to- be examined that have similar designs, sizes, functions, and service is required to be examined. In addition, where one pump contains a group of bolted connections of similar design and size (such as flange connections and manway covers), the examination may be conducted on one bolted connection among the group. Bolting ney be examined in place under load and upon disassembly of the connection.

A.2.4.4 Bolts and Studs in Valves, Item C4.40 For valves,100% of the bolts. and studs at each bolted connection of valves shall be volumetrically examined in accordance with Figure IWC-2520-6. Bolting on only one valve among a group of valves in each system required to be examined that have similar designs, sizes, functions, and service is required to be examined. In addition, where one valve contains a group of bolted connections of similar design and size (such as flange i- connections and manway covers), the examination may be conducted on one bolted connection among the group. Bolting may be examined in place under -  !

load and upon disassembly of the connection.

A.2.5 CATEGORY C-F, PRESSURE-RETAINING WELDS IN PIPING A.2.5.1 Piping Welds 1/2 In. or Less Eminal Wall Thickness, Item C5.10 l A. 2. 5.1.1 Circumferential Welds 6 Item C5.11 The surfaces of 100% of each circumferential weld 1/2 in. or less nomi-nal wall thickness shall be examined in accordance with Figure IWC-2520-7 J'uring eact) inspection interval. The welds selected for examination shall include

a. all welds at locations where the stresses under the-loadings resulting from Normal and Upset plant conditions as calculated by the sum of Equations 9 and 10 in NC-3652 exceed the specified value;

b. all welds at terminal ends (see (e) below) of piping or branch runs;

c. all dissimilar metal welds;

d. additional welds, at structural discontinuities (see (f) below) such that the total number of welds selected for examination in-cludes the following percentages of circumferential piping welds; A-30

, . q. - 4

.,j

' For boiling water reactors:

1. none of the welds exempted by IWC-1220;-

2. - none of the welds in residual heat removal and emergency core cooling systems (see (g) below);'

3. 50% of the main steam system welds;

4. 25% of the welds in all- other. systems. j -

For pressurized water reactors:

_l

1. none of the welds exempted by IWC-1220; . I

2. none of the welds'in residual heat removal and emergency. core i cooling systems; . .

3. 10% of the main steam system welds 8 in, nominal pipe size  ;

and smaller; l

4. ' 25% of the welds in all other systems.: 1

,l

e. terminal ends:are the extremities of piping runs that connect to structures, components (such as- vessels, pumps, and valves) or pipe anchors, each of which act as rigid restraints or provide at

'least two degrees of restraint to piping thermal expansion; I f. structura? discontinuities >1nclude pipe weld: joints to vessel '

nozzles, valve _ bodies, pump casings,' pipe fittings-(such as, '

elbows, tees, reducers, and. flanges conforming to ANSI Standard- "

B16.9). and nine branch connections and fittings;

g. examination requirements are under.. development..

For welds in carbon or low alloy steels, only those welds showing  :

reportable preservice transverse indications need to be examined for -  !

transverse reflectors.  !

b A. 2.5.1. 2 Longitudinal Welds. Item C5.12-  !

Longitudinal welds 1/2 )n. or less nominal wall' thickness shall be

- surface examined in accordance with IWC-2520-7 (2.5 t at the intersecting' I circumferential weld) during each inspection interval. j 1

A.2.5.2 Piping Welds Over 1/2 In. 2minal Wall Thickness, item C5.20- q A. 2.5. 2.1 Circumferential Welds. Item C5.21 One hundred percent of each circumferential weld over 1/2'in.' nominal wall thickness shall be surface and volumetrically examined in accordance with Figure IWC-2520-7 during each in:;pection interval.. The welds selected for examination shall include a

1 A-31 J

-. , I a.. .all welds- at locations-where the stresses under the loadings __

resulting from Normal and Upset plant conditions as calculated by i the sum of Equations 9 and 10 in: NC-3652 exceed the specified f

value; s

_l

b. all welds at-terminal ends (see (e) below) of p% or branch runs;

c. all dissimilar-metal welds;

d. additional welds, at structural discontinuities (r.re (f) belw)'

such that the total number of welds selected Nr cd11 nation in-cludes the following percentages of circumferential piping welds; . ,

For boiling water reactors::

C

1. none of the welds exempted by IWC-1220; . .

2. none of the welds in residual. heat removal and emergency core

. cooling systems..(see (g)= below); ]

- 3. 50% of the main steam system welds,

4. - 25% of the welds in all other . systems, f For pressurized water-reactors:- - '

1. none 'of the-welds' exempted by IWC-1220;.

2.- none of the welds in residual heat removal and emergency core cooling systems;

3. 10% of the main steam system welds 8 in, nomina 1L pipe. size.

and smaller; 4 25% of the welds in all other systems.

e. terminal ends are'the extremities of. piping runs that' connect to.

d structures , components (such as . vessels, . pumps,'and valves). or

.I pipe anchors, each of which act as rigid: restraints or provide-at i least two degrees of restraint'to piping thermal:exmnsion; '

l f.- structural discontinuities include pipe we'd joints. to vessel '

nozzles, valve bodies, pump easings, pi;eifittings ~(sucq as, elbows, tees, reducers, and flanp5 conformingito ANSI itandard ,

B16.9),'and nine oranch connections.and fittings;-

g. examination requirements- are .under development.

For welds in carbon or low alloy steels,-only- those welds showin' g reportable preservice transverse indications need to be examined for trans- ,

verse reflectors. -

j A.2.5.2.2 Longitudinal Velds, Item C5.22 Longitudinal welds over 1/2 in, nominal wall thickness shall be' surface and volumetrically examined in accordance with Figure :IWC-2520-7 (2.5 t at the intersecting circumferential weld) during each inspection interval..

A-32

A.2.5.3 Pipe Branch Connections. Item C5.30 A. 2. 5. 3.1 Circumferential Welds, Item C5.31 The surfaces of 100% of each circumferential weld in pipc branch i connections'shall be examined in accordance with Figure IWC-2520-9 during l each inspection interval. The welds selected for examination shall include

a. all welds at locations where the stnsses under the loadings resulting from Normal and Upset plant conditions as calculated by the sum of Equations 9 and 10 in NC-3652 exceed the specified value;

b. all welds at terminal ends (see (e) below) of piping or branch runs;

~

c. all dissimilar metal welds; d.- additional welds, at structural discontinuities (see (f) below) )

such that the total nunber of welds. selected for examination in-cludes the following percentages of circumferehtial piping welds; 1

For boiling water reactors:  !

1. none of the welds exempted by IWC-1220; I

2. none of the weids. in residual heat removal and emergency core cooling systems (see (g) below);

3. 50% of the main steam system welds 8 in;

4. 25% of the welds in all other systems.

For pressurized water reactors:

6

.. none of the welds exempted by IWC-1220; g 2. none of the welds in residual heat removal; and emergency core cooling systems; 3.- 10% of the nain steam system welds 8 in. nominal . pipe size and smaller; I

4. 25% of the welds in all other systems.

e. terminal ends are the extremities of piping runs- that connect to

. structures, emponents (such as, vessels, pumps, and valves) or pipe anchors, each of which act as rigid restraints or provide at least two degrees-of restraint to piping thermal expansion; 1 f. -structural discontinuities include pipe weld joints to vessel )

nozzles, valve bodies, pump casings, pipe. fittings (such as, I elbows, tees, reducers, and flanges conforming to ANSI Standard B16.9), and nine branch connections and-fittings; 9 examination requirements are under development.

i For welds in carbon or *ow alloy steels, only those welds showing

! reportable preservice transverse indications need to be examined for trans-verse reflectors.

Ie A-33

- , . - . . . . . .., . , . . _ , . . . .. -, l

I l

k.2.5.3.2 Longitudinal Welds, Item C5.32 l Longitudinal welds in pipe branch connections shall be surface examined in accordance with Figure IWC 2520-7 (2.5 t at the intersecting circumfer-ential weld) during each inspection interval.

l A.2.6 CATEGORY C-G, PRESSURE-RETAINING WELDS IN PUMPS AE) VALVES

! A. 2. 6.1 Pump Casing Welds. Item C6.10 >

One hundred percent of all pump casing welds in each pipir.g run ,

examined under Examination Category C-F shall be surface exerrined in accordance with Figure IWC-2520-8 during each inspection Piurval. For multiple pumps of similar design, size, function, and seryfce in a system, only one pump among each group of multiple pumps is required to be examined. The exa;nination may be performed from either the inside or outside surface. ,

i p

A. 2. 6. 2 Valve Body Welds. Item C6.20 One hundred percent of all valve body welds in each piping run examined under Examination Category C-F shall be surface examined in accordance with Figure IWC-2520-8 during each inspection interval. For multiple valves of similar design, size, function, and service in a system, only one valve among each group of multiple valves is required to be examined. The examination may be performed from either the inside or outside surface.

3 A. 2. 7 CATEGORY C-H ALL PRESSURE-RETAINING COMPONENTS l A. 2.7.1 Pressure Vessels. Item C7.10 1

Pressure .essel pressure-retaining boundaries (other than open-ended j

portions of systems) shall be visually examined (YT-2) dering the system leakage test performed in accordance with IWC-5221 during each inspec-

'. tion. % components within the pressure retaining boundary are exempt or l excluded from the examination requirements, except as specified in IWA-5214(c) for repairs and replacements. Where portions of a system are subject to system peassure tests associated with two different system '

functions, the Vf-2 examination need only be performed during the test conducted at the higher of the test pressures of the respective system function. The pressure retaining boundary includes only those portions of the system required to operate or support the safety system function l

up to and including the first normally closed valve (including a safety or relief va',ve) or valve capable of automatic closure when the safety function is +equired. A system hydrostatic test (IWC-5222) and accompany-ing YT-2 exanination are acceptable in lieu of the system pressure test '

(IWC-5221) ant; YT-2 examination.

A-34

,,w..-_..

l

! A.2.7.1.1 Pressure Vessels, Item C7.11 Pressure vessel pressure-retaining boundaries (other than open-ended portions of systems) shall be visually examined (YT-2) during the system hydrostatic test performed in accordance with IWC-5222 during each inspec-tion period. 2 components within the pressure retaining boundary (as defined by Ete (7)) are exempt or excluded from the examination require-4 ments, except as specified in IWA-5214(c) for repairs and replacements.

The system hydrostatic test (IWC-5222) shall be conducted at or near the end of each inspection interval or during the same inspection period of each inspection inteNa1 of Inspection Program B. The pressure retaining

boundary includes only those portions of the system required to operate or 1 support the safety system function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of 4

automatic closure when the safety function is required.

A. 2.7. 2 Piping, Item C7.20 Pipin systems)shall g pressure-retaining boundaries (other than open-ended leakage test portions of be visually examined (YT-2) during the system  ;

performed in accordance with IWC-5221 & ring each inspection period. 2

) components within the pressure-retaining boundary are exempt or excluded ,

from the examination requirements, except as specified in IWA-5214(c) for ,

i repairs and replacements. Where portions of a system are sub, ject to system '

pressure tests associated with two different system functions, the VT-2 examination need only be performed during the test conducted at the higher of the test pressures of the respective system function. The pressure

> retaining boundary includes only those portions of the system required to l operate or support the safety system function up to and including the first I normally closed valve (including a safety or relief valve) or valve capable l of automatic closure when the safety function is required. A system hydro-static test (!WC-5222) and accompanying YT-2 examination are acceptable in l p

lieu of the system pressure test (IWC-5221) and VT-2 examination.

A. 2.7. 2.1 Piping, Item C7.21 Piping pressure-retaining boundaries (other than open-ended portions of systems) shall be visually examined (VT-2) during the system hydrostatic test performed in accordance with IWC-5222 during each inspection period.

W components within the pressure-retaining boundary [as defined by 2te (7)) are exempt or excluded from the examination requirements, except as specified in IWA-5214(c) for repairs and replacements. The system hydro-static test (IWC-5222) shall be conducted at or near the end of each inspection interval or during the same inspection period of each inspection interval of Inspection Program B. The pressure-retaining boundary includes only those portions of the system required to operate or support the safety system (including function a safety up or to relief and including)the valve or valve first normally capable of closed automatic valve closure when the safety function is required.

I A-35

--..-- .,. --- _ .~- , -a- - . . , -

. - - - . ~ . , , - , . .- - --

- ,. , . - . , - .--.,c ... , , . ,

J, .

A. 2.7.3 Pumps , item C7. 30 i

Pump pressure-retaining boundaries (other than open-ended portions of systems) shall be visually examined (YT-2) during the system leakage test performed in accordance with IWC-5221 Wring each inspection period. %

components within the pressure retaining boundary are exempt or excluded ,

from the examination requirements, except as specified in !WA-5214(c) for t repairs and replacements. Where portions of a system are subject to system pressure tests associated with two different system functions, the VT-2 '

examination need only be performed during the test conducted at the higher of the test pressures of the respective system function. The pressure-retaining boundary includes only those portions of the system required to >

operate or support the safety system function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required. A system hydro-hydrostatic test (IWC-5222) and accompanying YT-2 examination are acceptable in lieu of the system pressure test (IWC-5221) and VT-2 examination, t

A. 2.7. 3.1 Pumps, Item C7.31 i Pump pressure-retaining boundaries (other than open-ended portions of

, systems) shall be visually examined (VT-2) during the system hydrostatic -

test performed in accordance with IWC-5222 & ring each inspection period.

2 components within the pressure retaining boundary [as defined by bte (7)) are exempt or excluded from the examination requirements, except as specified in IWA-5214(c) for repairs and replacements. The syttem hydrostatic test (IWC-5222) shall be conducted at or near the end of each inspection interval or during the same inspection period of each inspection interval of Inspection Program B. The pressure-retaining boundary includes only those portions of the system required to operate or support the safety system (including function a safety uportorelief and including)the valve or valvefirst capable normally closed valve of automatic closure l' when the safety function is required.

A. 2.7. 4 Valves, Item C7.40 Valve pressure-retaining boundaries other than open-ended portions of systems) shall be visually examined (VT-2) during the system leakage test in accordance with IWC-5221 cbring each inspection period. % components within the pressure-retaining boundary are exempt or excluded from the examination requirements, except as specified in IWA-5214(c) for repairs and replacements. Where portions of a syst m are subject to system pressure tests associated with two differera system functions, the VT-2 examination need only be performed during the test conducted at the higher of the test pressures of the respective system function. The pressure-retaining boundary includes only those portions of the system required to operate or support the safety system function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required. A system l

i A-36

hydrostatic test (!WC-5222) and accompanying YT-2 examination are l acceptable in lieu of the system pressure test (!WC-5221) and VT-2 i i examination, t 4

A. 2. 7. 4.1 Valves, Item C7.41  ;

Valve pressure-retaining boundaries (other than open-ended portions of systems) shall be visually examined (VT-2) during the system hydrostatic test per formed in accordance with IWC-5222 during each inspection period.  ;

b components eithin the pressure-retaining boundary [as defined by l

%te (7)1 are exempt or excluded from the examination requirements, except as sp6cified in IWA-5214(c) for repairs and replacements. The system hydrostatic test (!WC-5222) shall be conducted at or near the end of each '

, inst sion interval or during the same inspection period of each inspection

, in' J1 of Inspection Program B. The pressure-retaining boundary includes ,

or. . . those portions of the system required to operate or support the safety.  !

system function up to end. including the first normally closed valve (in- l ciuding a safety or relief valve) or valve capable of autonatic closure i when the safety function is required, t I

i i

11 l

l I

i f

i f

l l

i A-37 i t

l 1 . .- - . _ _ - . . . - , . . - _ . - . . _. . , - _ -, _

I j'. .* . j i

A3 CLASS 3 REQUIRD4ENTS ,

j l

i  :

CATEGORY D-A, SYSTEMS IN SUPPORT OF R$ ACTOR SHUTDOWN FUNCTION l

A.3.1 A. 3.1.1 Pressure-Retaining Components. Item 01.10 ,

The pressure-retaining components in the pressure-retaining boundary shall be visually examined (VT-2) during the system pressure test IWA-5000/

IWD 5221 each inspection period. A system hydrostatic test (IWD-5223) and )

accompanying VT-2 examination are acceptable in lieu of the system pressure  !

test and VT-2 examination. The system hydrostatic test shall be conducted at or near the end of each inspection interval or~ during the same inspec-tion period of each inspection interval for Inspection Program B. The

,,- system boundary extends up to and including the first normally closed valve ,

or valve capable of automatic closure as required to perform the safety- j related system function. There are no exemptions'or exclusions from these i requirements except as specified in !WA-5214(c).  ;

I l l' A. 3.1. 2 Integral Attachment--Component Supports and Restraints. Item D1.20 i

Component supports and restraints shall be visually examined (VT-3) in accordance with IWD-25041 during each inspection interval. For multiple components within a system of similar design, function, and service, the i integral attachment of only one of the multiple components shall be exam- ,

ined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b). ,

A. 3.1. 3 Integral Attachment--Mechanical and %draulie Sntbbers. .

Item Dl .30 i

Mechanical and hydraulic snubbers shall be visually examined (VT-3) in accordance with IWD-2500-1 during each inspection interval. For mul ti ple i components within a system of similar design, function, and service, the

-f integral attachment of only one of the multiple components shall be exam-ined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).  !

A. 3.1. 4 Integral Attachment--Spring Type Supports. Item 01.40  ;

Spring type supports shall be visually examined (VT-3) in accordance  :

with IWD-2500-l' during each inspection interval. . For multiple components 1 within a system of similar design, function, and service, the integral l attachment of only one of the multiple components shall be examined. The integral attachments selected for examination shall correspond to those ,

component supports selected by IWF-2510(b). l l

)

i A-38  ;

1 l

A.3.1.5 Integral Attachment--Constant Load Type Supports. Item 01.50 l Constant load type supports shall be visually examined (VT-3) in i accordance with IWD 2500-1 during each inspection interval. For multiple l components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be  ;

examined. The integral attachments selected for examination shall cor-respond to those component supports selected by IWF-2510(b).

A.3.1.6 Integral Attachment--Shock Absorbers. Item D1.60 l Shock absorbers shall be visually examined (VT-3) in accordance with r IWD-2500-1 during each inspection interval. For multiple components within J

,. a system of similar design, function, and service, the integral attachment ,

of only one of the multiple components shall be examined. The integral i attachments selected for examination shall correspond to those component .

supportsselectedbyIWF-2510(b).

I A.3.2 CATEGORY D-B, SYSTEMS IN SUPPORT OF EMERGENCY CORE COOLING, CONTAINMENT HEAT REMOVAL, ATMOSPHERIC CLEANUP, AND REACTOR RESIDUAL HEAT REMOVAL A.3.2.1 Pressure-Retaining Components. Item 02.10 The pressure-retaining components in the pressure-retaining boundary shall be visually examined (VT-2) during the system pressure test IWA-5000/

IWD-5221 each inspection period. A system hydrostatic test (IWD-5223) and li accompanying VT-2 examination are acceptable in lieu of the system pressure ,

test and VT-2 examination. The system hydrostatic test shall be conducted at or near the end of each inspection interval or during the same inspection '

i period of each inspection interval for Inspection Program Bi The system boundary extends up to and including the first normally closed valve or valve capable of automatic closure as required to perform the safety-related '

system function. There are no exemptions or exclusions from these require-ments except as specified in IWA-5214(c).

A.3.2.2 Integral Attachment--Component Supports and Restrai m item 02.20 Component supports and restraints shall be visually examined (VT-3) in accordance with IWD-2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).

l A-39

_ _ _ _ _ _ _ _ _ _ _ ~

r A.3.2.3 Integral Attachment- Mechanical and Hydraulic Snubbers. Item D2.30 Mechanical and hydraulic snubbers shall be visually examined (VT-3) in accordance with IWD-2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be exam-ined. The integral attachments selected for examination shall correspond

, to those' component supports selected by IWF-2510(b).

A.3.2.4 Integral Attachment--Spring Type Supports Item D2.40  ;

Spring type supports shall be visually examined (VT-3) in accordance with IWD-2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral

.- attachment of only one of the multiple components shall be examined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).

A.3.2.5 Integral Attachment--Constant Load Tyoe Supports, Item D2.50 a

Constant inad type supports shall be visually examined (VT-3) in accor- .

dance with IWD-2000-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be exam-  :

ined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).

A.3.2.6 Integral Attachment--Shock Absorbers, Item D2.60 Shock absorbers shall be visually examined (VT-3) in accordance with

> IWD-2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined. The integral L attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).

A.3.3 CATEGORY D-C, SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL FROM SPENT FUEL STORAGE POOL A 3.3.1 Pressure-Retaining Components, Item D3.10 The pressure-retaining components in the pressure-retaining boundary shall be visually examined (VT-2) during the system pressure test IWA-5000/

IWD-5221 each inspection period. A system hydrostatic test (IWD-5223) and accompanying VT-2 examination are acceptable in lieu of the system pressure test and VT-2 examination. The system hydrostatic test shall be conducted at or near the end of each inspection interval or during the same inspection A-40

period of each inspection interval for Inspection Program B. The system boundary extends up to and including the first normally closed valve or valve capable of automatic closure as required to perform the safety related system function. There are no exemptions or exclusions from these require-ments except as specified in IWA-5214(c).

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r A.3.3.2 Integral Attachment--Component Supports fnd Restraints, item D3.20 i s

i Component supports and restraints shall be visually examined (VT-3) in accordance with IWD-2500-1 during each inspection interval. For multiple ,

components within a system of similar design, function, and service, the e integral attachment of only one of the multiple components shall be exam-ined. The integral attachments selected for examination shall correspond  ;

to those component supports selected by IWF-2510(b).

I A 3.3.3 Integral Attachment--Mechanical _ _and, Hydraulic Snubbers, l Item D3.30 .

y Mechanical and hydraulic snubbers shall be visually examined (VT-3) in i accordance with IWD-2500-1 during each inspection interval. For multiple  ;

components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be exam-ined. The integral attachments selected for examination shall correspond to those component supports selected by,1WF-2510(b).

l 3 A.3.3.4 Integral Attachment--Spring Type Supports, Item 03.40 y Spring type supports shall be visually examined (VT-3) in accordance i with IWD-2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined. The

integral attachments selected for examination shall correspond to those ,

component supports selected by IWF-2510(b).

A.3.3.5- Integral Attachment--Constant Load Type Sv3 orts, Item 03.50 Constantloadtypesupportsshallbevisuallyexamined(VT-3)in accordance with IWD-2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be exam-ined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).

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i A.3.3.6 integral Attachment--Shock Absorbers, Item D3.60 Shock absorbers shall be visually examined (VT-3) in accordance with IWD 2500-1 during each inspection interval. For multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined. The integral

. attachments selected for examination shall correspond to those component supportsselectedbyIWF-2510(b).

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A.4 COMPONENT SUPPORTS .!

A.4.1 CATEGORY F-A, PLATE AND SHELL TYPE SUPPORTS, ITEMS F-1, F-2, i AND F-3 All supports within the examination boundaries of IWF-1300 having. .

components and piping required to be examined during the first inspection j interval by IWB-2500, IWC-2500, and IWD-2500 shall be visually examined -

(VT-3) each inspection interval. The areas subject to examination are 1 mechanical connections to the pressure-retaining component; weld and

• mechanical connections to the building structure; and weld and mechanical connections at intermediate joints in a multiconnected integral and non-  ;

integral support.  ;

A.4.2 CATEGORY F-8, LINEAR TYPE SUPPORTS, ~ ITEMS F-1, F-2, AND F-3 4

All supports within the examination boundaries of IWF-1300 having.

components and piping required to be examined during the first inspection t

' l. interval by IWB-2500, IWC-2500, and IWD-2500 shall be. visually examined (VT-3)eachinspectioninterval. The areas subject to examination are .

mechanical connections to the pressure-retaining component; weld and mechanical connections to the building structure; and weld and mechanical connections at intermediate joints in a multiconnected integral and non-integral support.

A.4.3 CATEGORY F-C, COMPONENT STANDARD SUPPORTS, ITEMS F-1, F-2, F-3,  ;

AND F-4 I .All supports within the examination boundaries of IWF-1300 having l components and piping required to be examined during the first inspection interval by IWB-2500,- IWC-2500, and IWD-2500 shall be visually examined (VT-4)eachinspectioninterval. The areas subject to examination are mechanical connections to the pressure-retaining component; weld and mechanical connections to the building structure; weld and mechanical connections at intermediate joints in multiconnected integral and non-l integral support; and spring-type supports, constant load-type supports, snubbers, and shock absorbers.

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~ Enclosure 3 TABLE 1

SUMMARY

OF RELIEF REQUESTS Relief Date Date Recuest of of NRC Number Request Approval Sub.iect None 08/27/86 22/29/86 NI system discharge  ;

check valve repair  !

welds  !

None 04/07/87 07/31/87 Hydro testing for removal of Upper Head Injection system

' None 02/09/87, 07/12/88 Hydro testing of 02/16/87, (See also Nuclear Service 1

03/25/88 Duke letter Water (RN) system of10/05/88) welds None 10/26/87, 08/03/88 RN and Ground Water 01/19/88, Monitoring system welds 05/04/88 88-01(Unit 1)01/28/88 03/14/88 Hydro testing of RN system repair welas <

None 03/02/88 12/01/88 Code Cases N-401, N-416,  !

N-426, and N-427.

88-02 (Unit 2) 04/27/88 06/15/88 Valves 2M134 and 2RN135 ,

88-04 05/05/88 02/23/89 Containtent Spray Heat i Exchanger s 88-05 and 06/27/88, 06/29/89 RN modification 89-0206 02/16/89 04/04/90 01/22/90 88-08(super- 11/08/88 Herein SafetyInjection(NI) l l

sedes88-06) Tank  :

88-09(Unit 1)11/11/88 11/21/88 k' elds- from RTD system modification d9e to NI  !

-line interference i i

88-10 (Unit 1) 12/19/88, 12/22/88 Check Valve 1NI-160 l 12/20/88 replacement None 02/28/89 05/16/89 Ccde Case N 356 -i 4

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