ML19261E814

Proposed Repair/Replacement Program for Steam Generator Feedwater Nozzle Safe-End-To-Pipe & Pipe-To-Elbow Welds. Oversize Drawings Encl

ML19261E814
Person / Time
Site:	Millstone
Issue date:	09/28/1979
From:	NORTHEAST UTILITIES
To:
Shared Package
ML19261E813	List: ML19261E812 ML19261E814
References
TAC-11793, NUDOCS 7910040322
Download: ML19261E814 (43)

Text

. ,

DOCKER No. 50-336 MILLS 10NE NUCLEAR POWER STATION, UNIT NO. 2 PROPOSED REPAIR / REPLACEMENT PROGRAM FOR THE STEAM GENERATOR FEEDWATER N0ZZLE SAFE-END-TO-PIPE AND PIPE-TO-ELBOW WELDS 7910040 t 3

SEPTEMBER, 1979 22ia 027

NORTHEAST UTILITIES T = ." = ' = = r -

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1.0 INTRODUCTION

In response to NRC IE Bulletin 70-13, NNECO performed the required volumetric examinations of the steam generator feedwater nozzle to piping welds during the unscheduled plant shutdown commencing on August 9, 1979. Linear indications were detected in both feedwater loops near the : safe end to pipe welds ( AC-G-1, BC-G-1) and the adjacent pipe to elbow welds (AC-G-2, BC-G-2), as shown in attached drawing 25203-20158, Sheet 1, submitted on August 22, 1979 (Docket No.50-33G).

Supplementary UT examinations were performed at the above noted welds to characterize the linear indications in terms of location, length and depth. As a result, a meeting was held with the NRC Staff on August 21, 1979 to discuss the results of the findings and the basis for continued operation of Millstone Unit No. 2.

Based on the analysis of the findings and basis presented at the August 24, 1979 meeting and subsequent supportive documentation sub-mittea on August 22. 1979 and August 24, 1979, the NRC permitted interim operation of LFilstone Unit No. 2 at the licensed power level until October 31, 1979 rubject to commitments specified in NRC letter R. Reid to W. G. Counsil, dated August 25, 1979, Docket No. 50-336.

2.0 PURPOSE The purpose of this submittal is to present a description of the proposed steam generator feedwater nozzle safe end to pipe and pipe to elbow weld repair / replacement program including necessary modifications to the steam generator shield wall as required by Commitment No. 4, Specified in Reference 5.1.

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3.0 DESCRIPTION

OF THE PROPOSED REPAIR / REPLACEMENT PROGRAM The proposed repair / replacement program for the steam generator feedwater nozzle safe end to pipe and pipe to elbow welds will be directed as required to resolve the findings of the NRC Bulletin 79-13 inspections conducted in August 1979. The details of the inspection findings including the linear indication maps were submitted to the NRC on August 22, 1979 and August 24, 1979.

Linear indications were detected in both feedwater loops at the steam generator nozzle safe end to pipe welds (AC-G-1, BC-G-1), and the adjacent pipe to elbow welds (AC-G-2, BC-G-2). The Millstone Unit No. 2 feedwater line configuration, the welds of interest, and the accessibi.11ty to these welds are shown in Figure 1 (uttached).

Access to the safe end to pipe welds is severely restricted by the existing shield wall design.

As a result, several repair options were evaluated including an investigation of possible shield wall removal as required to gain OD access to the nozzle safe end to pipe welds. The two repair methods which are currently considered for the repair / replacement program are as follows:

1. Option A: To remove a portion of the shield wall and to cut / replace feedwater pipe.

2. Option B: To cut pipe outside shield wall and to repair linear indications from ID.

An outline of the repair procedures for Options A and B and the results of the shield wall removal evaluation are presenten herein.

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3.1 Results of Shield Wall Removal Evaluation The feedwater piping penetrations in the upper walls of steam generator compartments 1 and 2 including concrete structural details are shown in attached drawing 25203-11183.

Based on the review of the structural analysis, the following shield wall removal can be instituted consistent with the design bases limitations in the Millstone Unit No. 2 FSAR:

3.1.1 A six foot (G') diameter recess will be removed by drilling and chipping. 'i .e maximum depth of the six foot cutout shall be less than eight inches (8").

3.1.2 After the first layer of vertical (#11) and hori-zontal (#10) rebars are exposed, caution will be exercised not to expose the second layer of rebar.

3.1.3 The rebar around the twenty-four inch (24") sleeve

(#11 x 10'0") and around the steam generator upper anchor (#18 x 12'0") shall remain as is.

3.1.4 The exposed pipe sleeve and the outer layer of vertical and horizontal rebar may be cut or left in place.

3.2 General Outline of Option A Repair Procedure 3,2.1 Option A: Remove a six foot (G') diameter by eight inches (8") cut-out from shield wall and repair / replace feedwater pipe as outlined below.

3.2.2 Procedural Steps:

(1) Remove concrete shield wall around the feed-water nozzle to a depth less than eight inches and a 77:; 030

-4 diameter of six feet.

(2) Cut feedwater pipe at a specified location on the safe end (i.e., between welds 1 and 2 as shown on Figure 1).

(3) Cut below the second elbow outside the shield wall, upstream of weld 4 as shown in Figure 1.

(4) Remove the pipe and elbow assembly.

(5) Remachine safe end and pipe for new weld prep as specified in the attached fabrication and installation procedure.

(6) Install new replacement section or repaired section in accordance with the initial as-built dimensions and orientation.

(7) Welding of replacement piping to existing piping shall be in accordance with the attached fabrication and installation procedure.

(8) All repair / replacement welds shall be 100%

RT examined in accordance with the applicable codes.

(9) A system pressure test will be performed in accordance with the applicable code.

3.3 General Outline of Option B Repair procedure 3.3.1 Option B: To access the welds from outside the shield wall by removing a section of pipe and repairing from the inside.

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3.3.2 Procedural Steps:

(1) Cut the feedwater pipe outside the shield wall between welds 2 and 3 on Figure 1. Weld 2 is now approximately four feet (4') from outside the shield wall.

(2) Cut below the second elbow beyond weld 4.

(3) Remove the pipe and elbow assembly.

(4) LP inside surface near weld 2 and determine precise location of indications by working from inside the pipe to a method to be determined later.

(5) Grind the inside surface near weld 2 as required to remove indications. The exact method whether manual or automatic is being evaluated.

(6) Measure depth of ground area after all indica-tions have been removed. Perform. LP for verification.

(7) If the grind out depth does not violate the minimum design thickness, blend grind out to a 4:1 taper and a 0.5" radius at the maximum depth of the cavity.

(8) If the grind out depth violates the minimum wall, weld repair from ID in accordance with technique to be determined later.

(9) Grind surface flush and perform LP examination.

Repair as required.

(10) The weld repaired area shall be radiographed.

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(11) Repair indications in the pipe to elbow welds, or pref abricate r, pool piece using replacement eblows/ piping.

(12) Remachine weld preps per attached fabrication and installation procedure.

(13) Fit the pipe and elbow assembly and weld botn joints. Final dimensions shall be in accordance with the as-built dimensions.

(14) perform 100% radiographic examination of closure welds and any new welds; repair as required.

(15) perform system pressure test in accordance with the applicable code requirements.

3.4 Detailed Fabrication and Installation procedure / Design Improvements 3.4.1 The detailed installation and fabrication procedure for the proposed repair / replacement program delineating the specific requirements is Cp-M-4-79, " Fabrication and Installation procedure", dated September 20, 1979.

The referenced procedure is attached for information.

3.4.2 Design Improvements Based on the present understanding of the feedwater line cracking phenomena, the following additional requirements have been instituted or will be instituted at a future date.

(a) All counterbores shall have a minimum 1.0 inch radius at the transitio.. of the taper and a 4:1 slope to minimize stress risers.

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(b) The counterbored area will be ground to a smoothness better than 125 RMS to eliminate machine marks and therefore potential crack initiation sites.

(c) Maximum blending depths without weld repair will be established based on fatigue design considerations rather than a minimum wall thickness considerations for the steam generator feedwater nozzles. Specific Mill-stone Unit No. 2 data from the feedwater line instrumenta-tion will be used as the loading input, Additional efforts are required to reduce tb data fr.r subsequent thermo1 stress analysis.

(d) A minimum preheat of 2000F shall be maintained for carbon steel welds on a continuous basis through post-weld heat treatment to eliminate thermal cycling during fabrication.

(e) The steam generator feedwater nozzle safe end to pipe and the pipe to elbow welds shall be post-weld heat treated following welding repair to minimize residual stresses.

4.0

SUMMARY

AND CONCLUSIONS 4.1 The proposed steam generator feedwater nozzle / pipe repair /

replacement program is being submitted in accordance with Commitment 4 specified in Reference 5.1.

4.2 Two repair options including the possibility of shield wall removal constitute the basis of the repair / replacement program. Additional methods need to be finalized to confirm the feasibility of Option B. However, in view of the limited 77 i 034

accessibility to the safe end to pipe welds, even after the allowable shield wall removal, the additional pursuit of Option B is imperative.

4.3 The detailed fabrication and installation procedure for the proposed repair / replacement program is contained in procedure CP-M-4-79 prepared by Crouse-NES under NUSCO's direction.

4.4 Specific design improvements based on the up-to-date under-standing of the observed feedwater line cracking were incor-porated or will be incorporated into the detailed fabrication and installation procedures. The primary objective of the design improvements is to eliminate or minimize the susceptibility of the feedwater piping to the observed cracking phenomena following the repair / replacement program.

5.0 REFERENCES

5.1 NRC letter from R. Reid to W. G. Counsil, dated August 25, 1979, Docket No. 50-336.

5.2 Crouse-NES Procedure CP-M-4-79 "Feedwater Piping Repair /

Fabrication and Installation Procedure", dated September 20, 1979, including all referenced drawings.

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WELD NUMBERS S/G 2 iM' gg S/G 1 N '. ' 7 'e! @ FW AC G 21 FW BC-G 18

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> I mil _LSTO NE II FEEDWATER LINE CONFIGURATION FIGURE I 22io 036

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CROUSE NUCLEAR ENERGY SERVICES -

NUCLEAR MAINTEN ANCE F ORCES . CONSTRUCTION . TECHNI Le NEEN No sgRVICES UPPER LEWIS RD., LINFlELD. PA. 19468.(215) 248-4340 -

PROJECT TITLE: Feedwater Piping Repair PROJECT LOCATION: Millstone Point Unit II PROJECT NUMBER: G-63659 PROCEDURE NUMBER: CP-M-4-79 Fabrication and Installation Procedure REVISION NUMBER: Rev. No. 0 APPROVALS Crouse N.E.S. [ k< f Engineering Date Crouse N.E.S. '

f 9 .20 79 QC Engineering '() D6te '

Northeast Utilties (PORC) 22iu 037 4a 4c .ou o.oe,cc...N.

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CROUSE NUCLEAR ENERGY SERVICES * /

NUCLEAR M AINTENAN*E FORCES e CO**STRUct TECHNI AL & 1 NLEM NG SERVtCES UPPER LEWIS RD., LINFIELD, PA.19456 c(215) 248- J CP-M-4-79 FABRICATION AND INSTALLATION September 20, 1979 Rev. 3 APPROVED BY: DATE 9 f APPROVED BY:

ev R- DATE f 2.0 79 22;a 038 g . c.oe o.ou, co. N.

Page 1 of 1

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PREFIX - CP-W4-79 Fabrication and Installatton Procedure 1.0 Procedure Changes 1.1 Procedure changes may be implemented as non-intent or intent changes. Non-intent changes are those which do not result in a significant change in scope of the original procedure, nor result in a change to any acceptance criteria. Non-intent changes may be im-plemented with the concurrence of two members of the Millstone Unit II supervisory staff, one of whom holds a Senior Reactor Operator's license. The change must then be reviewed by the Millstone Unit II Plant Opera-tions Revieu CommittSe (PORC) and approved by the Unit Superintendent within 14 days of implementation.

Intent changes may not be implemented without prior review and approval of the Plant Operations Review Committee (PORC) and the Unit Superintendent. Proc-edure revisions, where the entire procedure is reissued, are to be handled as for the original procedure.

2.0 Testing of Operational Equipment 2.1 All procedures requiring the operation of plant equip-ment for testing will be coordinated by Millstone Personnel.

3.0 Safety Tagging 3.1 All safety tagging to prevent improper equipment opera-tion will be controlled and actual isolation / equipment operation performed by Millstone Operations Department personnel.

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Sept. 20, 1979 Rev. O FABRICATION AND INSTALLATION PROCEDURE FOR REPAIR OF FLAWS IN 18 INCH FEEDWATER PIPING TO STEAM GENERATORS 1 AND 2 OF MILLSTONE UNIT 2

1. SCOPE: .

1.1 This procedure describes the steps necessary for -

repair of defective sections of feedwater piping or replacement with new sections. The original configuration of piping shall be retained.

1.2 The location of this work is at elevation 44'-8 5/16" on the 18 Inch Feedwater piping where it penetrates the Steam Generator Enclosure Wall. A modification of the inside wall around the penetra-tion sleeve will be required.

1.3 The summary of procedure section (Section 5) of this document represents an approximate order of steps to be accompliched, however, some of these steps may occur out of the general sequence.

1.4 This procedure may be modified at any time prior to or during the actual work in accordance with any additional requirements deemed necessary by parties or regulatory agencies involved.

2.

REFERENCES:

2.1 ASME Section III, 1971 with addenda to Summer 1975 2.2 ASME Section IX, 1971 with addenda to Summer 1975 2.3 ASME Section XI, 1974 with addenda to Summer 1975 2.4 Feedwater system piping repair methodologies for Northeast Utilities Service Company, Millstone Unit II - prepared by Combusion Engineering, Inc.

September.1979.

2.5 NUSCO Quality Assurance, CAT. I 401-C 2.6 Bechtel Specification 7604-C-21 Concrete (Information only) 2.7 Bechtel Specification 7604-C-62 Steel (Information only) 2.8 Bechtel Specification 7604-A-17 Coating (Information only) 2.9 Bechtel Specification 7604-M-200 (Field Fab. Piping)

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September 20, 1979 Rev. 0 2.10 Attachment to above Piping Spec. 7604-MS-2 (Weld Prep.)

2.11 Bechtel Speciff7ation 7604-M-292 Piping (Information

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only) 2.12 Bechtel Specification 7604-M-215 Insulation (Information only) 2.13 Bechtel Letter, Hughes to Hart dated 20 August 79.

2.14 NUSCO Procedure for plugging and providing cover and cleanliness for components opened for repair 2.15 NUSCO Procedure for operational leak testing of feedwater system 2.16 Attachment 1, Weld History Report 2.17 Attachment 2, Weld Maps 2.18 Attachment 3, Defect Maps 2.19 Attachment 4, Western Stress Procedure (later) 2.20 (DELETED) 2.21 Drawing Number and Revision Drawing Number Revision 25203-20158 SH.1 ISO A 7604-M-200-514-3 ISO 514 As Built 7604-M-200-515-3 ISO 515 As Built 2626-5106 Spool Drawing As Built 2626-5112 Spool Drawing As Built E-233-604-7 Nozzle Detail 7 25203-CS-1 Civil Standards As Built 25203-11183 Concrete As Built E-233-651 SG No 1 Dimensions As Built E-233-655 SG No 2 Dimensions As Built 2.22 Tool Lis't

3. DISCUSSION:

It will be necessary to chip out a portion of inte~rior Steam Generator Enclosure Wall and remove a portion of 24 inch sleeve to gain access to flaw area of 18 Inch Feedwater Pipe. The removed portion of concrete and 22io 041

p .

September 20, 1979 Rev. O sleeve will not be replaced, however, the rough chipped concrete surface and exposed cut rebar shall be repaired and coated.

All areas where personnel are anticipated to work shall be HP surveyed. All personnel shall be HP and respirator trained; and every effort shall be made to keep the radia-tion exposure as low as possible to comply wi".h the concept of the ALARA Program.

Radiography shall be performed on all pipe replacement welds (Other base line NDE requirements may be necessary). Crouse will perform film interpretations; final acceptance will be by the Owner. The Containment shall be clear of personnel as required during radiography.

4. PRE-REOUISITES:

4.1 Tag out system 4.2 Drain and flush lines 4.3 Complete HP surveys 4.4 Clean up all concrete chips, grindings and dust prior to beginning work on pipe.

4.5 Supply fire watch for all welding

5.

SUMMARY

OF PROCEDURE SECTIONS

1. Removal of insulation

2. Layout of concrete volume to be removed

3. Chipping of concrete

4. Cutting pipe sleeve

5. Cleanliness ecsurance

6. Removing flaw areas of piping

7. New weld preps

8. Fit up and erection of new piping

9. Stress relieving of weld to Safe End Nozzle

10. Leak testing

11. Repairing of concrete

12. Coating of concrete

13. Replacing of insulation 22!o 042

September 20, 1979 Rev. 0

6. PROCEDURE:

6.1 Removal of Insulation:

6.1.1 Provide equipment necessary to protect workers from hazards of asbestos insulation as required by state and federal laws.

6.1.2 Provide area for temporary storage of insula-tion panels and small parts such as screws, clamps, etc. So they will not become misplaced.

6.1.3 Tag and remove individual panels for reinstal-lation later.

6.2 Layout of concrete volume to be removed:

6.2.1 Consult concrete Drawing 25203-11183 Sections A and B.

6.2.2 Layout a 3-foot radius circle, extending 2 faet beyond circumference of penetration sleeve.

6.2.3 Mark the inside of sleeve to a depth of no greater than 8 inches.

6.2.4 QC to verify layout of cutout.

No. 1 S.C. Compartment _

QC Signature Da te No. 2 S.G. Compartment QC Signature Date 6.3 Chipping of Concrete:

6.3.1 Provide sealed shelf or platform under area to be removed to keep contamination of lower portion of S.G. Compartment to a minimum.

6.3.2 Provide " Clean Room" enclosure over work area, utilizing portable ventilating and filtering equipment.

6.3.3 Provide vacuum cleaning equipment to keep airborn contamination to a minimum, and respir-ators for personnel.

6.3.4 Provide protective material for Steam Generator, Nozzle and Safe End to preclude damage from

_4_ 221m 043

September 20, 1979 Rev. O chipping tools, weld spatter and are strikes.

6.3.5 Begin removal of concrete inside layout area to a depth just inside outer layers of rebar.

Outer layers of rebar are authorized to be cut using pneumatic cutoff wheel.

6.3.6 QC shall monitor removal operation at various intervals and insure that a minimum cover of 3/4 inch exists for No. 11 sleeve rebar and minimum of 1 1/2 inch cover exists for No. 18 upper anchor rebar. This QA Procedure may limit the depth of the 6 foot cutout to less then 8 inches. Location and depth of rebar may be determined by rebar finder and 1/4 inch masonry pilot drill.

Rebar cover not less than 3/4 inch, No. 11 rebar S.G. No. 1 QC Signature Date Rebar cover not less than 1 1/2 inch,, No. 18 rebar S.G. No. 1 QC Signature Date Rebar cover not less than 3/4 inch, No. 11 rebar S.G. No. 2 QC Signature Date Rebar cover not less than 1 1/2 inch, No. 18 rebar S.G. No.2 QC Signature Date 6.4 CUTTING OF PIPE SLEEVE 6.5.1 Cut away premarked section of pipe sleeve by using cut-off wheel.

6.5.2 Clean up all chips, dust and grindings before proceeding.

22io 044 September 20, 1079 Rev. 0 6.5 CLEANLINESS ASSURANCE 6.5.1 Remove all tools and equipment not necessary for further work and establish tool inventory and tool accountability per reference 2.14.

6.5.2 Clean up all concrete chips, dust grindings,~etc.

to comply with cleanliness criteria of reference 2.14.

6.5.3 QC to verify tool accountability and cleanliness criteria complied with.

S.G. No. 1 Compartment QC Signature Date S.G. No. 2 Compartment QC Signature Da te 6.6 REMOVING FLAW AREAS OF PIPING 6.6.1 Removal of fla's areas of piping may be accomplished by either method A or D of reference 2.4 Concrete will be removed regardless of which method is used.

6.6.2 Field dimensions of pipe shall be checked for agree-ment with reference as built drawings and record on problems.

6.6.3 Mark position where cuts are to be made. Flaw areas shall not be cut into, on either Elbow or Transition Safe-End. (Consult Defect Map) 6.6.4 NUSCO shall have final authority for establishing position of cuts.

6.6.5 QC shall verify final position of cuts.

Layout verified :

S.G. No 1 NUSCO Signature QC Signature Date S.G. No 2 NUSCO Signature QC Signature Date 6.6.6 Piping upstream of section to be removed shall be temporarily supported by rigid means. Section to be removed shall be temporarily supported such that it can be carefully removed without damage to itself or surrounding piping.

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September 20, 1979 Rev. 0 6.6.7 Cuts shall be made using pneumatic cut-off wheel.

Grind to blue line condition and break off.

6.6.8 QC shall verify proper cut off made.

Cut off verified S.G. No. 1 Safe End or other cut (Ident ) QC Signature Date Cut off verified S.G. Ho. 1 Elbow QC Signature Date Cut off verified S.G. No. 2 Safe End other cut (Ident ) QC Signature Date Cut off verified S.G. No. 2 Elbow QC Signature Date 6.6.9 Warning signs shall be posted by all exposed open-ings concerning hazards of breathing atmosphera inside these openings.

6.6.10 All openings shall be cleaned and plugged per Ref. 2.14 to such a depth which will allow counter boring and beveling operations.

6.6.11 QC verification, openings cleaned and plugged.

Verified S.G. No.1 Safe End QC Signature Date Verified S'.G. No.1 Elbow QC Signature Date Verified S.G. No.2 Safe End QC Signature Date Verified S.G. No. 2 QC Signature Date 6.7 NEW WELD PREPS 6.7.1. All spools and fittings shall be erected in the field; all weld preparation shall be as follows:

6.7.2 All weld preps on straight run pipe and fittings shall be in accordance with Crouse WPS-GTA-SMA-l.1-106 221o 046 Sept. 20,1979 6.7.3 Weld prep on Steam G'enerator Nozzle Safe Rev. O Ends shall be in accordance with Crouse WPS-GTA-SMA-1.1-10 6 6.7.4 All counter bores shall have minimum of 1 inch radius at the inboard transition to the inside diameter of the pipe to eliminate possibility of stress risers. The machine finish shall be smoother than 125 R.M.S. to eliminate detrimental machine marks.

6.7.5 QC shall verify all weld preps are in accord-ance with prescribed documents (consult weld map as required).

S.G. No.1 Safe End AC-G-21 QC Signature Date S.G. No.2 Safe End BC-G-18 QC Signature Date S.G. No.1 Spool Weld Preps: AC-G-1 Ident. QC Signature Date AC-G-2 Ident. OC Signature Date AC-G-3 Ident. QC Signature Date AC-G-4 Ident. QC Signature Date S.G. No. 2 Spool Preps: BC-G-1 Ident. OC Signature Date BC-G-2

. Ident. QC Signature Date BC-G-3 Ident. QC Signature Date BC-G-4 _

Ident. QC Signature Date Vertical Spool Weld Prep. on existing pipe to S.G. Nc , 2 -

BC-G-3 Ident. OC Signature Date

(

September 20, 1979 Rev. 0 6.7.6 QC shall verify Min. Wall Thickness inspection by UT or Micrometer on both S.G. nozzles Safe End and pipe where required.

S.G. No. 1 nozzle QC Signature Date S.G. No. 2 nozzle QC Signature Date Ident QC Signature Date Ident QC Signature Date Iden t QC Signature Date Ident QC Signature Date Ident QC Signature Date Ident QC Signature Date 6.8 FIT-UP AND ERECTION OF NEW PIPE 6.8.1 Protection shall be provided for end preps which may pass through wall sleeves in crder to prevent damage to such. Care should be taken not to damage any portion of existing pipe, fittings, or portions which are being replaced. If damage should occur the defective area shall be corrected in accordance with approved procedures.

6.8.2 Fit-up will be in accordance with Crouse WPS -

. GTA-SMA-1.1-106.

6.8.3 QC shall verify new field dimensions are in accord-ance with As Built dimensions 6.6.2 S.G.No.1 As Built QC Signature Date S.G.No.2 As Built QC Signature Date

September 20, 1979 Rev. 0 6.8.4 On horizontal spool piece if required fit-up shall be as follows:

1. Spool shall be cut slightly long and preped on one end.

2. Spool shall be erected and fit-up tempor-arily to Safe End nozzle.

3. Unpreped end shall then be marked to exact.

length necessary for fit-up.

4. Remove spool and prep other end.

5. QC to LP all end preps.

S.G. No 1 LP Exam Prep. Ident.

OC Signature Date Prep. Ident.

OC Signature Date Prep. Ident.

QC Signature Date S.G. No 2 LP Exam Prep. Ident.

QC Signature Date Prep. Ident.

QC Signature Date Prep. Ident.

QC Signature Date 6.8.5 Clean up all new sections of pipe, fittings, and existing pipe and nozzle ends.

6.8.6 QC to verity cleanliness in accordance with NUSCO Cleanliness Inspection Plan Ref. 2.14.

S.G. No 1 Cleanliness QC Signature Date S.G. No 2 Cleanliness QC Signature Date 6.8.7 QC to verify removal of all temporary plugs before final fit-up and erection of pipe" dL J 049

September 20, 1979 All Plugs Removed Rev. O S.G. No 1 QC Signature Date S.G. No 2 QC Signature Date 6.8.8 Perform final fit-up and tack weld all spools and fittings in place.

6.8.9 QC to verify fit-up in accordance with Crouse WPS -

GTA - SMA - 1.1 - 106 S.G. No 1 Fit-up QC Signature Date S.G. No 2 Fit-up QC Signature Date 6.8.10 QC to perform visual and RT inspection on root passes.

S.G. No 1 QC Signature Date S.G. No 2 QC Signature Date 6.8.11 Welding to S.G. Nozzle shall be in accordance with Crouse WPS # later, all other weld joints shall be to Crouse WPS-GTA-SMA-1.1-106. Grinding of outer weld contour surfaces to smoother than 125 RMS finish for UT Examination will be required.

QC Signature Date 6.8.12 QC will verify parameters required by weld history record and sign form.

6.8.13 0c visual and LP Final Weld S.G. No.1

. Id ent . AC-G-1 ,

QC Signature Date Weld Ident. AC-G-2 QC Signature Date

September 20, 1979 Rev. O Ident. AC-G-3 QC Signature Date Ident. AC-G-4 QC Signature Date Ident. AC-G-21 QC Signature Date S.G. No.2 Ident. BC-G-1 QC Signature Date Ident. BC-G-2 QC Signature Date Ident. BC-G-3 QC Signature Date Ident. BC-G 4 QC Signature Date Ident. BC-G-18 QC Signature Date 6.8.12 Radiograph all welds and verify acceptance.

6.8.13 Continuous monitoring of all 60*F preheat and stress relieving on nozzle transition welds shall receive careful consideration.

6.9 STRESS RELIEVING TRANSITION WELD TO SAFE END NOZZLE 6.9.1 Crouse will subcontract the stress relieving if re-quired and perform surveillance.QC will verify calibrated equipment and acceptable heat charts are generated in accordance with Western Stress's Stress Relieving Procedure.

6.10 LEAK TESTING 6.10.1 System shall undergo leak testing by NUSCO procedure for operational testing Ref. 2.15.

6.11 PREPARING OF CONCRETE 6.11.1 The rough surface created by removal of sections of concrete shall be smoothed by use of epoxy grout according to Mfg. Instructions. ^11 cut-o'ff ends of rebar shall be at least f?ush with concrete surface.

22;c 051 September 20, 1979 Rev. 0 6.12 COATING OF CONCRETE 6.12.1 All surfaces shall be coated with one coat Keeler and Long No 7107 epoxy white primer to 3 mils DFT and one coat of Keeler and Long epoxy enamel to 2.5 mils DFT. Safety precautions associated with use of these coatings shall be complied with.

Coatings are allowed to overlap the very small ex-posed edge of steel sleeve. Coatings shall be applied according to Mfg. instructions.

6.12.2. QC shall verify coating.

S.G. No 1 Coating QC Signature Date S.G. No 2 Coating QC Signature Date 6.13 REPLACEMENT OF INSULATION 6.13.1 Provide equipment necessary for protection of workers from hazards of asbestos insulation as required by federal and state laws.

6.13.2 Replace all insulation panels.

6.13.3 QC verify replacement of insulation panels S.G. No 1 Insulation Replaced QC Signature Date S.G. No 2 Coating Insulation Replaced QC Signature Date 2'l' : 052

Attachment l' September 20, 19h9 i

' Rev. O i

WEID HISTORY REDRD

, CROUSE NUCLEAR ENERGY SERVICES, INC.

Part I FABr.ICATION TRAVELER / PROCESS SHEET Weld Nap No.

Class 1,2,3, Cther Size Schedule (Circle One) Weld No.

To

,se Metal No. Type or Grade Base Metal No. Type or Grade Type Filler Metal Heat No. Consumable Type & Heat Other Weld Spec.

Insert Number & Rev. No.

Frs [ red By Date Engr. Spec. & Rev. No.

Part. II To Base Metal Heat No. Base Metal Hea t No.

Requirements Inspector Date A U A N_A PROD DaTE10C lDATE' WELDERS NO. CODE INS.

Verification of Materials toca cm

' Joint Prep, Preclean, Fit-Up cat m CD Preheat *F coca cm Root Fass, RT,MP,LP,UT,VT coca cm i Max. Interpass Temp 'F caca cm Intermediate, RT MP.LP.UT.VT ED CD CD Stress Relieve *F ca ca cm l Final Pass RT,MP,LP,UT,VT c m c--) c m . I Radiographic Stages Weld Repairs 0( ) 1( ) 2( ) 3( )

Remarks:

WELD REPAIR HISTORY RECORD Prepared By Date Welder Ident.

Type Filler Met. Heat No. Consumable Ins. Type & Heat No. Other i.epair Pro,

~

Radiograph Petrarks: A 0A NA Joint Prep Preclean Fitup O O Preheat *F OOO Root Pasp RT,MP,LP,UT,VT C Remarks: Max. Interpass Temp *F O Stress Relieve *F O.'O O Prod Date Final Pass kT,MP,LP,UT,VT OOO QC Date ,

I Verify That This Record And The Final Radiographic Reports Have Been Reviewed By He And Found Acceptable With Code Requirements; QC Engineer Date Authorized Code Insp. Date J-221, 053 .

. I

% FIGURE 1 .

En 1

ofg AC- G 8 a

AC-G 7-+ i

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AC-G-9 ,

AC<rl8 AC-G-4 gg x , - 4a [C-G 14 BC-G 9 AC-G -21 M-G-1 SWEEPOt.ET 4 AC-G-19 4 STEAM g (< '99,, GENERATOR N i AC- G -20 ,

(g GENERATOR '"2 g( '

0: BC- G-18 ,o- a k6 LCONT ON 25203-20158 s

sg, A G-6 g. p. -BC-G-lO SH.2 BC-G-1 \<~BC-G-il NOTES B C- G- gfp ./ '

BC G-2 BC- G-12 I

BC-G -16

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2. HANGER DWG NOS. FOLLOWED BY t ARE WELDEO TO PIPING PRESSURE

1. ' BC- G-4

-G 3 BC-G-IS

\ WQCONT 20158ON BC-G-17 252OJ-SH.2 BOUNDARY 3 EXEMPT WEl.DS (PIPE-TO-P!PE)

NOT SHOWN.

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BC- G-13

'8-18"X 6" SWEEPOI.E T BC-G -14 C

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• Attachment 3 TABLE 1 1 Of 4 MILLSTONE UNIT NO. 2 STEAM GENERATOR #1 WELD # AC-G-1 (SAFE-END-TO-PIPE WELD)

Circumferential location

• Indication Distance From Component (RT Film) Length Centerline of Weld Safe-End 57 .8 cm 1.2 cm Safe-End 0-2 3.7 cm 1.0 cm Safe-End 12 - 14 Intermittent 1.2 and 1.4 cm Pipe 13 .9 cm 1.5 cm Pipe 13 - 14 1.4 cm 1.5 cm Pipe 9 .7 cm 1.3 cm Safe-End 13 - 18 8.0 cm 1.3 cm Safe-End 16-1/2 - 18 4.0 cm 1.0 cm Pipe 14 - 16 5.7 cm 1.4 cm Fipe 12-1/2 . 9 cm 1.4 cm Pipe 14 1.5 cm 1. 0 cm Safe-End 45 - 48 Intermittent 1.3 cm Pipe 45 1/2 3.4 cm 1.4 cm Safe-End 45 - 47 4.4 cm 1. 2 cm Pipe 44 - 45 1. 2 cm 1.3 cm Pipe 45 - 46 .8 cm 1.3 cm Pipe 46 - 47 2.6 cm 1. 2 cm Safe-End 46 - 49 Intermittent 1.3 cm Safe-End 49 - 50 1.8 cm .7 cm 22'o 055

o .

Attachment 3 TABLE 1 (Continued) 2 of 4 MILLSTONE UNIT No. 2 STEAM GENERATOR #2 WELD # BC-G-1 (SAFE-END-?O-!'IPE WELD)

Circumferential Location

• Indicacion Distr.nce From Componaat. _

(RT Film) Length _ _ Centerline of Weld Safe-End 57 - 3 12 cm 1 cm Pipe 57 - 0 2 cm 13 mm Pipe 1 1 cm 13 mm Pipe 1-2 2 cm 11 mm Pipe 11 ~ 13 3 cm 2 cm Safe-End 7-1/ 2 - 8 c 5 ;, 2.5 cm Safe-End 12 - 14 3.5 cm 14 mm Safe-End 45 - 48 8 cm 1 cm Pipe 43 - 46 8 cm 1.3 cm Pipe 46-1/2 1/2 3 cm 1.2 cm Safe-End 56-1/2 - 2 9 cm 1. 0 cm Safe-End 55 - 56 3 cm 1. 2 cm Pipe 57 - 0 1.5 cm 1.0 cm Sa f f.-End 47 - 49 4.5 cm 1.3 cm Pipe 48 - 49 2.5 cm 1. 2 cm Pipe 57 - 2 Intermittent . 9 cm Safe-End 46 - 51 Intermittent 1.2 cm

• X-ray film location marker, at two-inch increments spanning 360 degrees.

22;o 056

Attachment 3 Table 1 Continued 3 of 4 MILLSTONE UNIT NO. 2 STEAM GENERATOR #1 WELD # AC-C-2 (PIPE-TO-ELBOW WELD) i Indications detected as follows:

Marker Locations:

6 - 18 40 - 48 1:00 - 4:00 o' clock 8:00 - 10:00 o' clock 221v 057

Attachment 3 Table 1 Continued 4 of 4 MILLSTONE UNIT NO. 2 STEAM GENERATOR #2 WELD # BC-G-2 (PIPE-TO-ELBOW WELD)

Indications detected as follows:

Marker Locations:

0-2 12 - 18 40 - 48 2-4 12 - 16 41 - 47 46 - 52 12:00 o' clock 3:00 o' clock 9:00 o' clock 22i., 058