ML20039G451
| ML20039G451 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 09/15/1981 |
| From: | Aswell D LOUISIANA POWER & LIGHT CO. |
| To: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| Shared Package | |
| ML20039G447 | List: |
| References | |
| W3K81-0333, W3K81-333, NUDOCS 8201180252 | |
| Download: ML20039G451 (10) | |
Text
r LOUISIANA P O W E R & LI G H T! P O BOX 600($
24a OetAnONoe sineer
- NEW OnLEANS louts!ANA 70174 * [504) 366-2345 NS$sysM o t aswat Septe:ber 15, 1981 W3K81-0333 Q-3-T33 Mr. K. V. Seyfrit, Director, Region IV U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012 Mr. John Woodward Factory Mutual Engineering 12 Perimeter Center East, Northwest Suite 1200 Atlanta, GA 30346 Mr. J. W. Morvant Louisiana Department of Labor P. O. Box 44063 Baton Rouge, LA 70804
Subject:
Waterford SES Unit #3 Repair Program for the Reactor Containment Vessel Re:
Docke t No. 50-382 Gen tlemen :
Enclosed is the repair program for the Waterford SES Unit #3 Reactor Containment equipment hatch cover md roof cutout. This program also includes the methods of removing miscellanem.s temporary clips, bracket straps and lugs, and the installation of permanent pads and clips as required. These repair programs are submitted for your review as required in para IWA4130 of the ASME Section XI Code.
if there are any questions reg'rding this ongoing activity, please advise.
Very truly yours, D. L. Aswell DLA/RAll/ rd o!$$$$82 0
- bec:
T. F. Gerrets, L. L. Bass, Clyde Hawn, L. V. Maurin, D.
B. Lester, R. K. Stampley, R. A. Hartnett, Central Records l
loE NTIF IC ATION RP R Ev. No.
2 CONT R AC' 71-2 4 2 6 REPAIR PROCEDURE PACE No.
1 or 3-
"C' NUCLEAR CONTAINMENT VESSEL o,7c CORE insp REo rec PREPAREo RDN 12-18-78 o
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ENGA ENGR TEST QA QA QA CLM 12-18-78 CHECKEo s
5 MRS CRS JBT PV RtvisEo PV 5-16-80 E
APB LCW CNS RES 5-16-80 AursORizEo REFERENCE
$TANDARO REV,NO.
1.0 INTRODUCTION
This procedure outlines specific requirements of the Customer and governing Code, as contractually established for additional work on a previously tested and code stamped Class MC Containment Vessel.
2.0 REFERENCES
2.1 Nuclear Quality Assurance Manual for Repairs and Alternations to ASME Code Stamped Components, Issue No. 4.
2.2 Nuclear Quality Assurance Manual (QAM) for ASME Section III Products, Issue No.
6.
2.3 1971 ASME Code,Section III, Division 1, Subsections NA & NE, with Summer 1971 Addenda.
2.4 EBASCO Design Specification No. LOU 1564.717.
2.5 71-2426 0.A. Handbook 2.6 National Board Rules
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s IDENTIFICATION p
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CONTRACT 71-2426 REPAIR PROCEDURE pace No. 2 or 3
pRoovCT NUCLEAR CONTAINMENT VESSEL
3.0 SCOPE
All work to be accomplished in accordance with the reference documents given in Para.
2.0.
3.1 Install 6'E roof cutout and Equipment Hatch Cover.
3.2 Remove miscellaneous temporary clips, bracket straps and lugs.
3.3 Provide permanent pads and clips as reqd' ired by customer.
4.0 PROCEDURE
4.1 Installation of 6'E roof cutouts (See Detailed Field Procedure for Detail C on Contract Dwg. 12).
4.1.1 Clean edges of cutout and opening by brushing or grinding.
4.1.2 Fit cutout in opening, gouge and weld in accordance with WPS-E7018/71-2426 and Special Procedure Instructions on approved contract Drawing 12.
(See GWPS-SMA for correction of wide gaps.)
4.1.3 100% radiograph the weld in accordance with RTP-71-2426-9B and approved contract drawings.
4.2 Installation of Equipment Hatch Cover.
(See Detailed Field Procedure for Joint G on Contract Dwg. 26.)
i 4.2.1 Clean edges of Cover and Barrel by brushing or grinding.
4.2.2 Fit Cover to Barrel, gouge and weld in accordance with WPS-E7018/71-2426 and Field Procedure Instruc-tions on approved contract drawing 26.
4.2.3 100% radiograph the weld in accordance with RTP-71-2426-9B and approved contract drawings.
4.3 Removal of miscellaneous clips, bracket straps, and lugs.
4.3.1 Gouge and remove.
4.3.2 Grind remaining weld relatively smooth.
- Go 148 A REV J AN 77
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IDENTIFICATION RP REV.NO.
2 CONTRACT 71-2426 REPAIR PROCEDURE ance No. 3 or 3 NUCLEAR CONTAINMENT VESSEL 4.3 Removal of Miscellaneous clips, bracket straps, and lugs (cont.)
4.3.3 Visually inspect per VEP-1B.
4.3.4 If questionable indications are found by visual examination, MT indications in accordance with MTP-(71-2426)-13B.
4.3.5 Unacceptable indications may be repaired by grinding (not to exceed.01 inches below thickness shown on contract drawings) or by welding.
4.3.6 After repairing by grinding or welding, MT examine the completed repair in accordance with MTP-(71-2426)-13B 4.4 Provide permanent pads and clips as required by customer.
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4.4.1 Fabricate and install the pads and clips in accordance with approved contract drawings, the appropriate cus-tomer approved welding procedure (WPS-E7018/71-2426, WPS-E308L/71-2426 and/or WPS-E309A/71-2426), and the QA Manual.
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4.4.2 MT or PT all welds in accordance with MTP-(71-2426)-13B, or PTP-12B as specified on contract drawings.
5.0 CLARIFICATION OF QAM REQUIREMENTS:
Authorized Inspection for the shop and field shall be provided by CBI.
(Refer to Paragraph 4.1 of the Repair and Alteration Q.A. Manual).
6.0 DOCUMENTATION
6.1 Document the work in accordance with the QAM for the contract.
6.2 The " Manufacturer's Report of Welded Repairs" (Page 4 of Repairs and Alterations Q.A. Manual) shall be provided in lieu of any ASME Data Reports described in QAM.'
6.3 A " Manufacturer's Report of Welded Repairs" may be provided to cover all repair work or several
" Manufacturer's Report's of Welded Repairs" may be provided to document individual or groups of repair work covered by this procedure.
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NUCLEAR
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QUALITY ASSURANCE MANUAL
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FOR REPAIRS AND ALTERATIONS TO ASME CODE STAMPED COMPONENTS
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,L ISSUE NO. 4 This manual has been reviewed by management. They concur with and endorse this manual and the impi me ation.of the-Quality Assurance Program which it describes.
h./-). 77 Director, C6rporate Nuclear Quality Assurance Data h
Authority and Responsibility provisions of the Nuclear Quality Assurance Manual for ASME Section ill Products" are applicable to this manual.
13 77, [
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e<a 4-/S-77 Senior Vi() President Date
~ Senior Vice Presidpg't Date Manager of Operations Manager of Engine @in A
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mt.c NUCLEAR QUALITY ASSURANCE MANUAL FOR REPAIRS AND ALTERATIONS TO ASME CODE noe no.
1 or 4
STAMPED COMPONENTS Issue No. 4 ev RHS one 6-6-77
1.0 SCOPE
This manual describes the Quality Assuritnce Program for control
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of rcpairs and alterations to ASME Code (Section III) stamped compom its.
2.0 BASIS OF PROGRAM The program is based on utilization of the " Nuclear Quality Assurance Manual for ASME Section III Products," current issue together with this manual.
However, it may be contractually established to use an earlier Nuclear QA Manual if the original construction was by CBI in accordance with that Manual.. The aaplicable QA Manual (herein referred to as QAM) together with f
tais Manual shall be issued to a Contract *QA Handbook covering
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the repair or alteration work.
QAM requirements shall be followed with the applicable modifications and additional requirements of paragraphs 4.0, 5.0 and 6.0 below.
3.0 APPLICABLE CODES
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Rules governing repair and alteration after stampi.ng are contained in ASME Code,Section XI, which is mandatory for ASME Class 1, 2 and 3 pressure-retaining components and.their supports.
For other' classes of work, application of other rules must be contractually established.
This manual complies with ASME Code Section XI,1974 Edition with Addenda h through W. inter 1976.
4.0 GENERAL (APPLICABLE TO ALL WORK UNDER THIS MANUAL) 4.1 Authorized Inspection AuthoriiedInspectionforshopworkshallnormallybepbvidedbyCBI, unless the customer insists on providing it. ~ Authorized In.spection for x
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field work shall be provided by the customer, unless the customer in-i sists'on CBI arranging for it.
CBI's contract with the Hartford Steam Boiler Inspection and Insurance Company includes inspection services for repair 'nd alteration.
Prior to their agreeing to provide this a
inspection for CBI, a request must be sent to the applicable Hartford Regional Office.
The request shall
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whether it will be handled as a repair or alteration include a clear definition of the work to be performed.
and whether a State' jurisdiction is involved.
The de-finition of work must include all work to be performed
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M wrte NUCLEAR QUALITY ASSURANCE MANUAL FOR REPAIRS AND ALTERATIONS TO ASME CODE
- ace so. 2 or 4
STAMPED COMPONENTS Issue No. 4 45 av RHS cart 6-6-77 by CBI and clearly outline the scope of the Inspector's work and the documentation required.
4.2 Repair or. Alteration Procedure (s
A procedure shall be written covering specific requirements of the customer and govarning Code.
It shall be handled as a repair procedure in accordance with the procedure p control system of QAM. It shall contain:
A.
Scope of work on the component B.
Operations necessary to accomplish the work C.
For Section XI work, any special electrode storage and baking requirements (5.2) gif
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'D.
Any special documentation requirements
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E.
Clarification of QAM requirements,'as necessary.
4.3 Acceptance of QA Program Prior to starting work, the Project Manager'shall obtain the customer's and AI's acceptance of the QA Program (comprising this manual, QAM, any-addenda
'and/or supplements and the Repair or Alteration Procedure).
4.4 Delete all referer.ces in QAM to ASME Surveys and Certi-(
ficates of Authorization.
q 5.0 WORK GOVERNED BY ASME CODE SECTION XI 5.1 Welders and welding procedures shal1 be qualified to
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NB-4300 (ASME Section III) and any special requirements (er
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of IWB-4400.
5.2 Special requirements for baking and storing covered electrodes are given in IWB-4420.
When these are applicable and exceed those of'QAM, they shall be specified in the Repair or Alter.ation Procedure 4
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4 w.e NUCLEAR QUALITY ASSURANCE MANUAL FOR REPAIRS AND ALTERATIONS TO ASME CODE exce no.
3 or 4 STAMPED COMPONENTS Issue No. 4 av RHS oavt 6-6-7'7 5.3: Controi of other special Section XI requirements exceeding QAM shall also be specif.ied in the Repair or Alteration Procedure.
N 5.4 'This work shall be documented on it report form agreeable to the owner.
6.' O WORK NOT GOVERNED BY ASME CODE SECTION XI l
In addition to ar.y other contract requirements (3.0), this work shall be documented on " Manufacturer's Report of Welded Repairs or Alterations " form GE 304 (see page 4).
lm If there is no welding involved, the form may be marked-up to so indicate.
This form shall be subject to controls specified for N-1 Data Reports in QAM, including the required CNQA release prior to signing.
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