ML20072T360
| ML20072T360 | |
| Person / Time | |
|---|---|
| Site: | Seabrook, 05000000 |
| Issue date: | 04/16/1982 |
| From: | Mcgarrigan D UNITED ENGINEERS & CONSTRUCTORS, INC. |
| To: | Parisano J UNITED ENGINEERS & CONSTRUCTORS, INC. |
| Shared Package | |
| ML20071K200 | List: |
| References | |
| FOIA-82-524 NCR-2117, NUDOCS 8304080054 | |
| Download: ML20072T360 (102) | |
Text
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'Vpiyh0"3Me MEMORANDUM
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Orrect: Philadelphia Joe No. 9763.006 DEM.
Reliability & Quality Assurance DATE:. April 16, 1982 P.O. 248-51 NEs: A.M. Ebner - 06UO T;r J. J. Parrisano * - 06U6 D.P. Rhoads - 06UO J.B. Silverwood - 14U6
. Leona Freone:
_n_ F. Mcc rriemn *- 14U6
- R.C. Lesnefsky - 14U6 J.N. Babcock - 14U4 SuaJECT:
J.P. Cannon - 14U3 D.J. Reinert - 14U3 D.C. Lambert - Site
Subject:
Public Service Company of New Hampshire Seabrook Station - Units 1 and 2 Penetration /Piate Welds' Pullman Higgins NCR 2117
~
As per our meetilig of April 15, 1982 I have summarized the background information, technical justification and proposed resolutions for the questions on the containment penetration / plate welds. These questions and the subject NCR required extensive code review and resulted in the following:
1] Code Boundary Between ASME Section III Division 1 and' Division 2.
The Code boundary is defined by the UE&C Drawing 9763-F-805578.
The weld between the penetration sleeve and plate performs a containment At function providing for the process piping to penetrate containment.
the option of the Division 2 designer, this weld was originally designed to be performed to Class 2 Division 1 rules.
However, this Division 1 work is part of containment not part of the piping system.
Pullman-Higgins must complete a separate N-5 Code Data Report for this weld which will be included in the Construction Report for the Containment.
e 2] Subsection NE Or Subsection NC For Penetration / Place and Plate / Pipe Welds.
T1.ase joints can be made under the requirements of either subsection as
- allowed by Division 2.
The present design calls for Class 2 welds to Subsection NC.
This Subsection requires radiography of the joint. Attempts to get meaningful radiography have failed.
Subsection NC does not allow the substitution of ultrasonics or magnetic particle methods for the peneWation/ plate welds. The design will be changed to call out the weld as Class MC, Subsection NE.
Pullman-Higgins does have an MC certification and Subsection NE does allow the use of alternate NDE methods.
3'] Nondestructive Examination of the Plate Material 'and Finished Welds.
Subsection NC requires Magnetic Particle Examination prior to welding of weld edge preps in material joints 2" thick and over.
The change to sub-section NE will require Magnetic Particle Examination of plate materi,1 greater than 1".
This change will affect all the mechanical penetration 5
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8304080054 830304 PDR FOIA KINDER 82-524 PDR
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h plates because they are 3/4",
1", and 2" thick. Eowever, the material
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is SA 516 GR60 supplied with Ultransonc examination.
This Ultrasonic
.wa=4 nation is a more sensitive technique for ex==ination and detection of Lamellar defects.
For this reason, the NCR may be dispositioned
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" Accept-As-Is".
In addition, Subsection NE ' requires that the final welds and all exposed cut edges be Magnetic Particle examined.
This l
will be done. The NDE required for acceptance of the penetration /,
plate weld is Ultrasonics, Magnetic Particle or Liquid Penetrant.
The
(
Magnetic Particle ar==4 nation will cover both material and weld require-seats.
- 4) Impact Testing of Plate Material.
Subsection NC did not require impact testing of the plate.. It was an
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option only required if specified in the Design Specification.
Engineering j,
.did not require impacts as directed by YAEC.
Subsection NE does require impact tests.". Dravo who supplied the material has additional material and impact tests can be performed.
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Proposed Resolution Items 1] UE&C change the penetration / plate and plate / pipe welds to " Class MC Subsection NE.
The penetration / plate weld is a category C weld joint
- and the plate / pipe weld is a category D weld joint.
- 2) Disposition Pullman-Higgins NCR 2117 " Accept-As-Is" foi all penetration plates of Unit 1.
Attach this memo for technical justification.
Have the Authorized Inspector and YAEC concur with this disposition.
Include this NCR and the P-H N-5'. Data Report in the Construction Report.
3] UE&C have Dravo perform Impact Test on the Plate material at the -25*F test temperature required for the containment penetration base metal.
l Impact test should be done in accordance with Subsection NE requirements.
4] Have Pull==n-Higgins perform Matnetic Particle Examination of all l
mechanical penetration plate welds and exposed cut edges.
l 5] Have Pullman-Higgins prepara an N-5 Code Data Report for these welds.
l The Structural Integrity Test will be the Containment Pressure Test at l
1.15 times the design pressure as required by CC-6000 and Specification l
80-1.
l
- 6) UE&C have Unit #2 penetration plate weld joints Magentic Particle e===ined by Dravo or Pullman-Higgins prior to welding.
1 7] Revise Drawing 9763-F-805578, Piping System Design Specification 9763.006-248-43 (Table 2.2-15) and Containment Design Specification to define these welds as Subsection NE, Class MC.
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.aug iTLE DATE Table 2.2-15 of Specification 248-43 and Dwg. F-805575 is inconsistent in specif1ying MT requirements for penetration pipe Trrw
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hj being applicable code to be consistent with Table 2.2-15 of Specification 248-43. Also revise table 2.2-15'as indicated on l
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TABLE 2.2-15 EXAHINATION REQU [REllENTS FOR CONTAIN!!ENT PEhETRATIONS (PIPINC) lluundnries of Applicable t
Hethod of Impact Jurisdiction Codes Items to be Examined Examination Test Penetration Sleeve ASNE Div. 2
. Sleeves (C:ntainment Liner CC-5521 a) Longltudinal Welds RT CC-2612
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Saal Weld to First CC-5521 b) Circumferential Welds RT CC-2512 Circumferential CC-5522 c) Hon-Butt Welds HP or LP CC-2612
\\g Weld Outside CC-5523 d) Attachment Welds HP or LP
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C:ntainment)
CC-5525 e) Leak Chase Leak Test CC-2530 f) Haterial UT CC-2522.1 Flued llead Penetritions (circumferential ASNE Div. 1.
Integral Flued liesde ucid at Sleeve subsection HQ and Piping HP or LP H/A to Wold Attachment NC-2510 m) Haterial UT 9763-006-248-34 tu Process Piping)
NC-2551 b)
Piping Butt Weld UT ASHE Div. I c) Sleeve Butt Weld RT 4
Subsection NE HE-5221 d) Sleeve Butt Weld Fabricated Pen. Piping (Wald of End ASHE Div. 1 Piping Plate to Welds subsection HE.
a) Heterial UT N/A
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NC-2510 HP or LP 9763-006-248-34 50 LP or HP NE-52 2 b) Pipe to End Plate Weld HP or Ll
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Fnbricated Pen. Plates ASHE Div. 1 End Plates See Haterini 9763-006-248-1 (Pipe to Weld to.
Subsection NE a) Heterial 8"' C * *
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NE-2121
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Ytnkte Atomic Electric Co'.
PROJECT:
Seabrook S chrook Station P.0 Box 700 FROM: NUCLEAR INSTALLATION SERVICES COMPANY S xbrook, NH 03874 POST OFFICE BOX 425 NITRO, WV 25143 M ON: Mr. J. Singleton (304) 755-0101 QA Manager NISCO ASME 111 Quality Assurance Manual (Controlled)
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WE ARE TRANSMITTING THE DOCUMENTS LISTED BELOW FOR YOUR G INFORMATION O COMMENTS
'OCUMENT NO.
REVISION TITLE OR DESCRIPTION NISCO ASME lil quality Assurance Manual 32 H
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131 IS REQUESTED. YOUR ANSWER IS NEEDnD BY: ASAP A REPLY O IS NOT REQUESTED.
VERY TRULY YOURS, Mr. Singleton:
AMENTS: Please sign the Transmittal NUCLEAR INSTALLATION SERVICES CO.
letter to indicate your receipt g,g-gy of the controlled QA Manual.
f TITLE Manaaer, Quality Assurance CE COMPLETED BY RECIPIENT (PLEASE RETU' RN)
O ffAVE DESTROYED THE OBSOLETE PAGES AND ADDED THE LATEST REVISIONS TO TH Fl HAVE RECEIVED THE ABOVE REFERENCED DOCUMEN1*S.
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RETURN TO: NUCLEAR INSTALLAT ON SERVICES COMPANY PY J
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POST OFFICE BOX 425 ZlTROe WV 25143.
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QA Manual - ASME Sec.III DOCUMENT 2
3 SECTION Table of Contents
{9' 1 ' OF 1
PAGE REVISION H
DATE 5/28/81 APPROVED & ISSUED BY:
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TABLE OF CONTENTS 1.0 ORGANIZATION 2.0 ENGINEERING 3.0 DOCUMENT CONTROL 4.0 PROCUREMENT CONTROL 5.0; MATERIAL CONTROL 6.0 PROCESS CONTROL 7.0 WELDING 8.0 INSPECTION TESTING AND EXAMINATION 9.0 CALIBRATION 10.0 HEAT TREATING 11.0 CONTROL OF CONSTRUCTION PROCESSES I2.0 DOCUMENTATION l
13.0 AUTHORIZED INSPECTION l
14.0 NONCONFORMITIES 15.0 A_UDIT 16.0 CORRECTIVE ACTION GLOSSARY FORMS e
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8/5/82 aEv:sioN DATE ij ENGINEERING SPECIFICATION TABLE OF CONTENTS WELDING FILLER MATERIAL CONTROL PROCEDURE (SAFETY RELATED) 1.0 Scope 2.0 Purpose 3.0 Responsibilities 4.0 General 4.1 Definitions 4.2 References 4.3 Attachments 5.0 Procedure 5.1 Storage of Welding Filler Materials 5.2 Disbursement of Welding Filler Materials 5.3 Return of Welding Filler Materia,1s 6.0 Quality Assurance / Quality Control l
7.0 Records 1
Attachment #1 (Form 94-1) Entitled " Weld Material Requisition" e
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3 ENGINEERING SPECIFICATION ION A
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1 MAGNETIC PARTICLE EXAMINATION PROCEDURE s,
l 1.0 SCOPE l-I This procedure establishes the equipment, materials, personnel and techniques to be used by NISCO when performing magnetic particle examination with portable equipment, using the non-fluorescent I
dry powder method. It is intended for inspecting welds in structural steel, pipe lines,' and large weldments; or for inspecting relatively large castings, forgings, or other component parts made from ferro-
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2.0 REFERENCES
The parameters described in this procedure comply with the requirements of the following documents:
i ANSI /ASME B & PV Code,Section III, Div.1 - 1980 Edition with A.
Winter 1981 Addenda.
u ANSI /ASME B & PV Code,Section V - 1980 Edition with Winter B.
1981 Addenda.
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,1 ANSI /ASME B & PV Code,Section VIII, Div. 1 - 1980 Edition with h
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t Winter 1981 Addenda.
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ANSI Power Piping Code, B 31.1 1980 Edition with W
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American Welding Society Structural Welding Code, A Edition.
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NISCO ASME Section III QA Manual Rev. H..
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NISCO Written. Practice for NDE, ES 116-1.
3.0 GENERAL 3.1 This procedure defines the manner in which ferromagnetic 1
objects shall be examined using either prods, a yoke device, or a coil to induce the magnetic field.
Examinations shall be performed by the continuous method, with' finely divided ferromagnetic dry particles as the examination medium.
3.2 Each area requiring exarlination shall be magnetized in two directions.
During the second examination, the lines of magnetic flux shall be approximately perpendicular to those used during the first examination.
Both examinations shall be conducted with sufficient overlap to assure 1001, coverage of the test area.
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ENGINEERING SPECIFICATION RE\\ ISION DATE 8/25/82 l
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l INDEX SHEET l
1.0 SCOPE l
2.0 REFERENCES
3.0 PROCEDURE QUALIFICATION / REVISION 4.0 RESPONSIBILITIES l
5.0 PERSONNEL QUALIFICATIONS
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l 6.0 TEST MATERIALS 7.0 GENERAL
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.T 8.0 EXAMINATION TECHNIQUE
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ENGINEERING SPECIFICATION I.0 SCOPE 1.1 This procedure describes the requirements and method of examination which shall be met by NISCO for Liquid Penetrant Examination using solvent removable visible dye penetrant.
1.2 This procedure shall be used for the detection of flaws or discontin-uities existing on or open to the surface of the material being inspected.
1.3 Personnel performing Liquid Penetrant Testing shall be qualified per SNT-TC 1A as specified in NISCO procedure E.S.116-1.
2.0 REFERENCES
2.1 ASME B & PV Code Section III - Div.1,1980 Edition with Addenda thru Winter 1981, Subsections NB, NC, ND, ND and NG.
i 2.2 ASME B & PV Code Section V, 1980 Edition with Addenda thru Winter 1981.
2.3 ASME B & PV Code Section VIII, 1980 Edition with Winter 1981.
2.4 ANSI Power Piping Code B 31.1, 1980 Edition with Addenda thru Winter 1981.
2.5 AWS Structural Welding Code DI.1,1981 Edition 2.6 NISCO QA Manual and Site Addenda 2.7 E.S.116-1, Qualification and Certification of Nondestructive Examination Personnel 3o0-PROCEDURE QUALIFICATION / REVISION 3.1 This procedure shall be qualified in accordance with the applicable l
code on test pieces representative of the material to be examined.
. Qualification Records shall be available at the site.
3.2 Procedure requalification shall be required when:
a.
Any prior processing method is changed which may effect the penetrant examination i.e., processes which may close surface openings or discontinuities or leave interfering deposits.
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19101 DOCUMENT REPID? REQUEST FOR CO.TIENT NISCO CLIENT PSNH PROJECT SEABROOK JOB No.
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(Title)
(FP# 4571A1 PA Giansiracusa WM OA
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(Rev. No.)
JR Mayne
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JC Anzivino (Location)
(Date)
TR Frolo RA Kountz Explanatory R,emarks Attached Yes No y
Safety Related Yes X
No
,l Resolution Comments i
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(Date)
(Responsible Engineer) of Discussed with Commentor
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Yes No Copy of this form sent to
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Cc==entor Yes No
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A 8/20/82 REvlsioN DATE tg ENGINEERING SPECIFICATION INDEX SHEET 1.0 SCOPE 2.0 APPLICABILITY 3.0 GENERAL 4.0 SPECIFIC REQUIREMENTS 5.0 ACCEPTANCE CRITERIA 6.0 REC 0_R.DS 7,0 PROCEDURE QUALIFICATION 8.0 REFERENC,ES MLICIRA A JINLQ JAlULJA55Y6TNLC4EFSA/lcPR COAADAMV
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DATE
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ENGINEERING SPECIFICATION NUCLEAR INSTALLATION SERVICES COMPANY
~. - - -. _. _ _. _.
-- - - _ _ ___ ___...--QUALIFICATION AND CERTIFICATION OF NONDESTRUCTIVE EXAMINATION PERSONNEL INDEX 1.O SCOPE 2.O REFERENCES'~
3.0 DEFINITIONS 4.0 METHODS 5.O LEVELS 6.0 EDUCATION, TRAINING, AND EXPERIENCE 6.2.1 NDE LEVELS I AND II 6.3.1 NDE I.EVEL III 7.0 TRAINING
~
8.0 EXAMINATION 8.5.1 NDE LEVEL I 8.5.2 NDE LEVEL II 8.5.3 NDE LEVEL III 9.0 CERTIFICATION s'..
10.0 TERMINATION 11.0 REFRESHER TRAINING
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REv:SION
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ENGINEERING spec FICATION 9 5. ' D*
NUCLEAR.INSTALLATICN SERVICES CO.
QUALIFICATION AND CERTIFICATION OF INSPECTION PERSONNEL INDEX 1.
Scope 2.
Definitions 3.
Levels of Certification 4.
Education and Experience 5.
Applicable Inspection Activities 6.
Examination Requirements 7.
Documentation of Qualification 8.
Re-certification Requirements 6
h1LICIEAR lhLRTAI 1 ATlf3h1MRVICER CBMPANY
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PAGE' I OF 5 j
3 REVISION C
DATE 9-11-81 ENGINEERING SPECIFICATION PAhtT21 PROCEDURE 1.0 PURPOSE 1.1 This procedura defines NISCO's method of compliance to 10CFR Part 21 which requires the reporting of deviations that are determined, on the basis of a documented evaluation, to be de-facts in basic components or failure to comply with Nuclear Regulatory Commission (NRC) requirements that could result in a substantial safety hazard.
2.0. SCOPE 2.1 This procedure is applicable to " deviations" from the technical requirements of " procurement documents" in " basic components','!'
that could create a " substantial safety hazard," including service of design, inspection, test, or consultation and extends to the entire supply chain.
3.0 DEFINITIONS 3.1 Basic Comoonent - A plant structure, system, component, or part necessary to assure:
3.1.1 Integrity of the reactor coolant pressure boundary.
3.1.2 The capability to shut down the reactor and maintain C.
it in a safe shut-down condition.
9 I
3.1.3 The capability to prevent or mitigate the. consequences of accidents which could result in potential off-s'ite exposures.
3.2 Defects
3.2.1 A deviation in a " basic component" elelivered to a purchaser, where on the basis of an evaluation, the deviation could create a " substantial safety hazard."
, [
3.2.2 The installation, use,or operation of a basic component C
containing a defect as defined above.
3.2.3 A deviation in a portion of a facility subject to the con-struction permit or licensing requirements of 10CFR 50 pro-vided the deviation could, on the basis of an evaluation, create a substantial safetv hazard and the portion of the facility containing the deviation has been offered to the purchaser for acceptance (on-site supplier).
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- ji ENGINEERifJG sPECIFICAT!ON V
Calibration and Control of Measuring and Test Equipment TABLE OF CONTENTS 1.0 Scope 2.0 Purpose 3.0 Responsibilities 4.0 General 4.1 Definitions and /bbreviations 4.2 References 4.3 Attachments 5.0 Procedure 5.1 Calibration 5.2 Calibration Control Program 5.3 Accountability, Storage and Issue of Calibrated Equipment j
6.0 Quality Assurance / Quality Control 7.0 Records i
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NUCLEAR INSTALLATION SERVICES COMPANY I
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E.S No.300
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DATE 6 AW ENGINEERING SPECIFICATION R
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. TABLE OF CONTENTS GENERAL WELDING PROCEDURE Page No.
A Scope 4
B.
References 4
C' Welding Qualifications 4
- 1.. Procedure Qualifications 4
2.
Performance Qualifications 4-5 D'.
Base Metal 5
1.
Base Metal Specification 5
2.
Base Metal Application 5
E. Welding Filler Metals 5
1.
Filler Metal Specifications 5
2.
Consumable Inserts Specification 6
3 Filler Metal Application 6
4.
Filler Metal Storage 6
F.
Weld Joints and Preparation 6
1.
Weld Joint Design 6
2.
Surface Preparation 7
3.
Cleaning 7
4.
Examination of Weld Edge Preparation Surfaces 8
5.. Vurging 8
6_
Alignment Requirements When Components Are Welded From Two Sides 8
7_
Fairing of Offsets 8
i 8.
Alignment Requirements When Inside 8-9 Surfaces are Inaccessiable 9.
Excessive Root Openings 9
10.- Welding End Transitions - Maximum lIj Envelope 9-10 II. Backing Rings and Strips 11
- 12. Socket Welds 11 G. General Heating Procedures and Control 12 i
T. Preheat Temperature 12 Z
Interpass Temperature 12-13 3.
Preheat Maintenance 13 I
4.
Postweld Heat Treatment 13 I
H. Workmanship Requirements 13 I
l '.. Weld Metal Disposition 13-14 2.
Initial and Interpass Cleaning 15 3'.
Backgouging 15 1
4!.
Arc Strikes 5~..
Peening 15-16 16 6.
Weld Distortion Control 7'
Final Weld Surface y
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Final Held Contour 17-l0 j
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Producti Checks I.0 NUCLEAR INSTALLATIOM NN-
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' guaingEsinc SPECIFICATION H=
TABLE OF CONTENTS i,
1 GENERAL WELDING PROCEDURE Page No.
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Tack Welds 18 1.
Definition 18 2.
Tack Weld Procedure 18 K.
Temporary Attachments 19 1.
Definition 19 19 2.
Welding Procedure 3.
Application 19 L.
Repair of Weld Metal Defects 20 1.
Definition 20 2.
Repair Without Welding 20 3.
Repair by Welding 20 4.
Repair Welding Procedures 20-21 5.
Inspection 21 6.
Repair of Base Materials 21
- Table 1 Reinforcement of Welds 22 M.
Reinforcement and In-Service Inspection (ISI) 23 Surface Preparation of Welds 23 1.
Pipe to Pipe Configuration 23 l
2.
Pipe to Component Configuration 23 3.
Component to Component Configuration 23 Figure 1 Limited Accessibility 24 Figure 2 Welding End Transitions 25
~ ~ ~
Maximum Envelope Figure 3 Welding Machine / Welder Surveillance Report
- 26
~
Appendix 1 Weld Joint Configurations 1-41,
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. NUCLEAR INSTALLATION SERVICES COMPANY
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Item #
Title Pages / Sheets 1
Customer Release Form
/
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2 E Certificate of Compliance 3 ' '/
.3 N-2 Form 4
Cross Index to Material & Cable Certs S- /,
(see separats folde for Certs) 5 Finished Module Travelers with Final Electrical
- 7. /M l
Test Data 6
Bulkhead to Ikilkhead Estension Traveler
/3 - M.2.
(includes Pneus:ctic,' Weld', and ND'E results) l 7
Finished Penetration Traveler A 7
,75 8-Repair Traveler (if 'any)
AJ A 9
1 Final-QA Inspection and Release
.:2 6 10 Loose Parts. List J7 l'
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S. UE S C QUALITT ASSURANCE RESERVES THE RIGNT 70 WAIVE ANY V E RIFIC AT3O N.
- 3. 0 STRieufl0N: sf PROJECT 0 RECT 0N NOMENCLATURE: REveEw 0F A CuAL Tv RE0uiREMENT AND iTS STATUS iS DEMOTED eV * ( Al FOR ACCEPT-AeLE, (w) FOR waivEO [SEE Rrhanx5], (C) FOR CONDITION AL (SEE REM ARMS),
(F) FOR Followup (SEE RLMAnx5], OR (NR) FOR NOT REQutRED.
QUALITY REQUIREMENTS t
A-VERIFICATION CHECKLIST
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B-DOCUMENTATION CHECKLIST-A'*
.( AT TIME OF FIN AL VERIFIC ATION )
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- f. FIN Alf VIStJAl.- EX AMIN ATION 1%
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- 1. SUBMITTED DOCUM5NTS
- 2. FINAL-DIMENSION AL A
2.NCR,S CLOSED p p,g47g
- 3. C,0 ATI N G / LININ g,,,g gs As g e
- 4. LUBRICANTS / 0ILS
- 5. CLEA N t' I N ESS 4
~4. VENDOR DRAWING STATUS (REVISION PRESENTED BY gf 8.' ELECTRICAL INSTALLATION A
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- 7. MARKING /IDENTI FICATIO N
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I ji CERTIFICATE OF COMPLIANCE Seabrook Maclear Power Plant 1 & 2 Customer No. 9763-118-1 i
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..,._. The electrical penetratio'ns supplied by Westinghouse El,ect:ic
^*
Corporation, IGTD, Horseheads, NY for'-the above contract are in l
_,, compliance with all referenced specifications, codes, and -
' Procedures to thle bast.of_ cur knowledge and'. belief.
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- I Attest: KEM.As.* 2 N M. W. kasey
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-Quality Assurance Manager'.
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.j DOCUMENT REYlEWED '
3 MAY 211981 1
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n FORM N-2 MANUFAC mRERS DATA REPORT FOR NUCLEAR.,RT AND APPURTENANCES
- i As required by the Provisions of the ASME Code Rules Wes t i nghous e E l ect ri c Co rp.,Wes t inghouse C i rcl e, Ho rseheads,N.Y. i 4845 L (a) Maniactured br (Nasse and address of Manidecturer of past)
Public Service of New Hampshire, Seabrook, NH (b) Manufactured foe (Name and address ~ of NMesse and 1 dress of Manuffeder Yor comp'lucledar urer completed esponefe')ar component) certi cate ho et nuc 2 Identification Manufacturer's Serial No. of Part 8101016 Nac'l Bd. No.
W17285 E-40144 R* L* Korner
! ' - ~ ~~~ (a) Constructed'According to Drawing No.
' Drawing Prepared by Electric Penetration
- 9) Description of Part Inspected winter 1976 July 1974 N/A MC
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M Applicable ASMEcode:SectioeIII,Edicloe dadm Case No.
CI..
h dew ce e en we Med tb de conta kment n d e c # etes de
.L,,,,,,,,
cm,ser d.seri,u
.a s.w s.,. men ee.,.sa
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pressure boundary of the containment vessel at the nozzle. This device has been pneumatically pressure tested in conformance with the design requirements.
We certify thmethe statements made la this report are ccerect and this vessel part a appartensace as defined la the Code coa.
fIseus to the rules of construction of the ASME Code Section III.
(He applicable Design Specification sad Scress Report are noe abe responsibility of the part Manufacturer. An appurtenance Mamelacturer is responsible for furnishias a separme Design Specifiestism and Stress Report if the appartenance is not included is she componeet Design Specificacios and Scress Report.)
Apr'Il 15, 81 3,
3g,gWestinghouse Elect. Corp.,,
W. F. Maney er os et.a m.o i
August 4, 1981 Certifieme of imhorizmien No.
g-eMicae of Authorizmios Empitu_
3 CEREFICARON OF DESIGN FOR APPURTENANCE (when applicable) j Pubile Service of New Hampshire
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Westinghouse Electric Corporation i
sera. analysis report o. nie m l
David H. Rhoads, Jr.
NH 3349 l
l Design specifications certified by Prof. Eng. State Reg.No.
f Seren saalysis report certified br Prof. Eng. Scace Michael Yonko NY g,,,,,, M3 CERURCATE OF SHOP INSPECTION l
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i I, she undersigned, holding a valid commisdom issued by the National Board of Boiler and Pressure Vessel taspectors New York Lumbermen's Mutual Casua1ty Co.
I and/or the Sesse or Province of and employd by i
.g Lona Grove. Illinois have inspected.p1,past of a pressure vessel described i e
- Menefacturer's Partla! Deca Report on Apri1 20 39 and sense that to the but of my knowledge the Manufacturer has constructed this part la accordance with the ASME Code Section s
and belief,ing this certificate, neither the laspector nor his employer makes any wasranty, espre sed
- lied, concers.
By sign l '.ing the part described le this Manufacturer's Parta'al Data Report. Furthermore, neither the aspe%)or
- mployer i
or wiek this laspection. y manner for any personal injury or property damage or a loss of any ki shall be liable la an arisia, i ted
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April 20, 81 1,9gI Dame e
19 o
N8 3605
%jd jA Commissioes t
l 1..ir.eter's ersomt S. A. Thomas n=l==e n.e,d. sta., pr.w.ee med nN eeseptemoment she'elar is>Me(,llege, ehetenee er drawless may be used provided (1) else le SW's 11*',(2) Infesseetten la lassee 3 2 en tMe desm espose Is tssolung
' sheet, ated (3) eesh eheet is numbered and number en sheets le receded la item 3. **Romerke*'.
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FORM N.2 (brek) j Itxas 4-8 Incl. to be completed for single wall vessels. jackets of jacketed vessels, or shells of hese exchangers.
l Material SA333 GR6 60,000 Nominal.406 Corrosion 12 8Pe 7
4 Shell:
T.S.(uta..t R.ng.niqkne s-in. A!!awance_in. Dia it..__.in. Length _ fc.
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Efficiency 5
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No. of Courses A Heads: (a) Material SA240-304 65,000 (b) unterial T.S.
7,3, L
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Ellipts.at Coni I H.mi.ph.rt..I r!.t Side t. Pr..
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If removable, bolis used C A 14't-R7 - 124 000 1/2 (M Read $ibr iastening Nuts SA194-2H
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(b)
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Other fastenies to. est..e.et n enee.mp Drop velshe Charpy Impace fe Ib 8
l 14..Deeias pressere ps! at
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'as temp. o_ f
- F Itessa below se be completed for au vessels where appIIcable.
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Openings: Headhole s, No.
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___ _. May_14, 1981 _
IM)EX TO MATERIAL AM CABLE CERTIFICATIONS SEABROOK CUSTOMER NO. 9763-118-1 Certified Material Test Reports Cert. No.
Heat No.
Pages 1
817686 3
2 190062 3
3 A(A16973) 2 4
A17833 1
5 00201 1
6 00179 1
7 05037 1
8 742417 2
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Cable Cert No.
Type P.O. No.
Pa'ges l
1 10 11540 9
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PROCESS OPERATOR NO.
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SIGN & DATE
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Record header heat and serial number.
M/R-F-70 7
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Record size and 252-1 27 K f(, _s /-g-- [/
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Fil ler Lot No. OC.7R.1 A 7
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/
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2 3
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6 I
8 9
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7 8
9 0
1 2
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5 6
7 8
9 U
1 f
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1 1
1 1
1 1
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2 2
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PROPRIETARY. M21 Tit. ATE BEFORE DISCARDING Mg-h
- PAGE, f ;l DA 3
W STINGHOUSE. LECTRIC CORPORATION N'
2 IND. & GOVT. TUBE DIVISION g
' d.
T
(
SEA 82cox.
=2 3 7- //
252-1-62 TUBE TYPE:
7 S,m e p
,p 3 7 S/N -
gogjja
SUBJECT:
Finished Hodule SUPERSEDED DATS.f fddf -
OPER.
PROCESS OPERATOR NO.
DESCRIPTION SPEC.
REV.
SIGN & DATE
,e /, /.2 -/d -PJ I
Record header heat and serial number.
Z.
Attach external leads.
Recor'd size and 252-i 27 K
~
ru number below.
V$P l-7 $1_
M b-6 l
313 Inspect crimps.
252-1-27 K
W'A J Y-T/
.2f/s /fef /s2*f/
7091 AM /'2#F) 4 Prelimin:frily Dielectric Streng0t and 257-1-3 Q
t l.Y.4) [-f t Insulation Resistance check. Do not record.
p3 nacx weld label to potting shroud /P/W f 2.34 7 213-3-16 M
J Q./ )-(
$ O7 l.J 4*/;c'? A G cf g q$ tog >yj {
Sched. 23 A
e Assemble potting shrouds and Q pot both ends.
252-1-22 C
Record.
Resin Lot No. 6Bli1903 (Proprietary)
Hardener Lot flogD271!c10 M l-/Y-l/
Fiiler Lot Nonn.ya 1a 7
Top off potting.
j f.
Record.
(Proprietary) 252-1-22 C
Resin Lot No.eeu14Al
~
~
Hardener Lot NTE3Zuc10
'"I'# Y~ 8I Filler Lot No.DC.fR_1n Q5 Final Electrical Test.
252-1-3 4 bli.Ml-liff
. ~
were saze gw f..
g AWFs PO No.
.aent / D 18.G' f D Euk NT REVlNED ' l 6
WIT 21 1981 w
I.s.v.
L u t. a c l
ITEM DESCRIPTION HEAT No.
s/N Header 29-40011s A#7PJ I
'//S * * ' "
f.
r
() BTEM NUM8ER FROM DRAWING l
O CPERATION WITNESSED BY Q.C'.
4
' OPERATION PERFORMED BY Q.C.
O AUTHORIZED INSPECTOR hot.D POINT CUSTOMER INSPECTOR WITNESSED CUSTOMER INSPECTOR HOLD PolNT if PRESSURE BOUNDARY
~
i b..
REV.
P c No ORWN CHKD APPR DATE
,g O
OR 9
x
( __
- .=._...
^
-.=:=.:
=D j
(g
.q
\\
ET,25felR2 El.ECTRICAt. TEST DATA conte (c q, (QQb_,
size 5 Sec.
.n. Min MiffklMM.
Record tio j)[_
)
t.e ad Hi Pot KV ins 'Res Cont t/oM
- g. r de //a W
.aM f WM
^"c'"' "* *WN
!I M - / 2 )* /'/Y nod. Type N)
M 27' N I 'IT8' ' Y?
Ser. No.
SW/l2 ~
CY 26.2 197-260 LT~ ~
~ ceNr5r-st.
&s.wner-R GurXer x tras us sws. ecurswuery LEAo x
sus.
courswusty LCAo Mi sus.
'co=r e wu e ry NOTES: 1) Hi Pot and
~
Ins. Res. Is teste, no.
Poi.
ats.
noolrson wo.
Pof.
ats., noo i sox wo.
Poi.
n[s.
noo [r som be tween 't.ead under 101 ;V N
s+
124 V y
N y
165 V, 'V N
'N4 test and all other i
102 t/
V N
125 V if N
166 V
V N
teads grounded to
!' 167 i/
/
N i
Shroud / Canister.
103 i/
V N
126 V V
y I
"l 168, /,
V. w 104 i/ 's/
N 127 V,
V w
105 V i/.
N 1128 'V y IN 169 /
V i,
l 170 /
t/ J DOCUMENT DE 106 V t/-
N f129 V
{/
N t
107 t/.
V N
130i V VN 171
'l V.
J, r
p g U 1881 172 V V
108 i/
V N
l 131 V.
t/
N
.j' 173 t/
V w
109 V
- /
'N 132 i/
i/,
N l1 174 i/.
$7.
N 110 i/.
i/.
s, 133 i/,
U w
175 if i/,
N 111 i/
V,...
N 134,V V,
N 176 V V.
N
.y.
- g 3 4- -
l, 112 /
V, N
y/,
135 i/,
"h*
177 E/
V-
'N i
113 t/
/
N 136 V i
N 9'
178 V J
m 11A i/.
V 137 y, 1/
w t!O 115 i/-
V. ~
138 v. a
~
..'_179 it.
it. ~
.i 180 i/.
J, N
}(' Q,Q_y 116 V,
if N
l 139 if g'
y
..-a 181 i/A V. g.
~
117 V.
iX N
- 1..
140 if g/,
y 1R2 if J
N
=a;w... c llt af V.
N 141 V V
y
$_.d~g 119 V.
i/.
N--
142 V.
i/
9 183 V i/.
w 184 i/
V.
N
- g g 120 V.
i/
N 143 V.
t/.
N
= ' cia.F..:
[F !FQ 185 V t/,
N 121 V i/.
N 144 i/.
y, N
145 14 t/
i 186 i/.
i/,
w 17? t/,
i/,
y
"'4 2 123 V V
N Y
146 V V.
N 187 i/
i/.
N.
4 M
y 147 i/.
V, 188 i/
V.
N 5
189 V i/ -
N
~
14R V i/,
N 190 t/.
i/,
g m
j49 g, v.
y m
5,;;I d
191 17 i/- "N l
150 V.
V" N
.GJ.=EF 192 i/
V.
ggln%lh~~W 151 V^
i/,
N 193 i/
V. w i
152 t/
V.
w l
Il 153 i/
i/
N 194 V f/ N 7-:?%-
- l 154 v.
V' 39.5 s/
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)
N l96
,/.
i/
N l
155 V V'
N i97 i/
V. N
]
156 i/.
i/
N 198 V.
t/. N g
157 if i/
N 1 99 V t/s M n
gg
.!. 1sa,/,
y, m
... -- 200 t/
t/ a V
g-
- il 159 if i/.
N
?
160 i/,
V. N
'E
,,c 161 if, V,
N 162 i/,
1/,
N DE hs 163 V, V
N 55 64 V V
N V
paga of
^/D
r U S.E,,.g i
O* raoraier^av au^'s 55'oa' o'st a o'"c
- DATE, e-h
- PAGE, g og ;
p
.y WESTINGHOUSE E' JCTRIC CORPORATION W
IND, & GOVT. TUBE DIVISION
/
S HORSEHEADS, NEW YORK SPEC. NO. T 252-1~62 SfAB/200X 237-/-2 S/N' g,g jjg TUBE TYPE: p g.f; g,7 3 7 j
SUBJECT:
Finished Hodule SUPERSEDED DATE f_ f., 7p ll PROCESS OPERATOR
.i OP E R.
. DESCRIPTION SPEC.
REV SIGN & DATE NO.
I Record header heat and serial number.
A,4 /d /0-fo
'~ ^~~
2 Attach external leads.
Record size and 252-1-27 K
vu number beIow.
/S,f I-9-fl
& / M/
$s3 inspect ex.i,2ps. _
2s2-1-27 K
jrwm + v-w :D"4 MM-9V s>X M 1.- Ms 4
PrelimHrarily Dielectric Strength 'and 252'T-3 Q'
Insulation Resistance check. Do not record.
OC,I-l.t-P/
l p3 lacx weld label to potting shroud./JffrX/ /Z3t;,fr 213-3-16 M
l 1.* / ') - h
- T, c y
j.A C 8 30fs V fdC.A"/.5'&D y *f Sched. 23 A
t O
Assemble potting shrouds and q pot both ends.
252-1-22 C
Record.'
Resin Lot No.
(., B4 Fa * '/
(Proprietary)
Hardener lot No. e_ o 1pf AJ C./ Q
~
Fiiler Lot No.
g e_. 3 t.
r O
' L9e /.1 $-Y /
7 Top off potting.
j,.
Record.
(Proprietary) 252-1-22 C
Resin Lot No.
6, 3 34.'7 4.s Y Hardener Lot No. c.o h u C i 4 -
FIIler Lot No.
u c - Ot.., a-2.SLe_ p-/S*-R t
2 On Final lilectrical Test.
252-I-3 fl w VHi,#/
,i were size
,c,., g.,,
AWFa PO Ho.
-ss. J b
/l.T ^}0 UnwdT REVIEWED MAT 21 i981 i
.s.y. -
m.
- u. E. a c, ITEM DESCRIPTION HCAT No.
stN Header 29-40014 A/V37
'7/ 7 + ASSEM8W WNy
[
() ITEM NUMBER FROM ORAWING O
OPf RATION WITNESSED 8Y Q.C; 8
OPERATION PERFORMED 8Y Q.C.
& AUTHORIZED INSPECTOR hcl.D POINT CUSTOMER INSPECTOR WITNESSED CUSTOMER INSPECTOR HOLD P0lNT PRESSURE BOUNDARY REV.
e c No ORWN CMXD APPR DATE Q. CHANGIE REVIEWEDBYAUTHORIZijD[
_b O
/
4 Id N
/dd-?#
p p
INSPECTOR h-r9If
'\\A v
jl1
,o )
h p'
s
.)
ET-25!s t R2 ELECTRICAL TEST DATA Conte QCt OO K '
f,A cc.vrA:.; 7f
.e-s?stO Lead Hi Pot KV Ins Res Q$NTt Recorg yo.
p,q stre 5 Sec.
rt Min
- TY, N gNs.dy' I
'y g,g hyj{
2, 'f'
/d & / K y' W 75bt tlb
'l
.ME/
A 25~~ A W Hod. Type b
23.T ifJgVA #7.2 7
2 3' h E &$ *N Sec. No. VW ll0
-~
.23,7 T297.ba n
G #4f.R
^
NOTES: 1) Hi Pot anc LCAO Hi IN$.
CONTINUITY LCAO Hi IN$.
CONTINUITY LCAO HI INS.
CONTINulTY Ins. Res. IS tefte
' NO.
POT.
At$.
MOO lT80I NO. '
POT.
At5.
m00 lT B03 NO.
POT.
AC5.
MOD T B03 between Lead under test and an other 201 ' V, V
N i j
V' N
AW NR 244 t/
V.
N
!AW
.985 i Leads grounded to 202 V
_i/
N P
945 V IA N
286 t/.
t/
N P
Shroud / Canister.
203.i/
i/
N I
246 t/
t/
287 t/,
t/
N l
204 M i/
N l
247
(/,
t/
N 288 t/
t/ 'N l
l l'
205 i/
$/, -
N 248 V,
t/. N 289 1/
V.
N i
i-206 i/
V N
249 V.
i/ N 290 (/.
t/
N
_207 i/.
i/,
N 250 1/.
t/
N 208! t/
i/.
N I: 251 ' g/
(/ NJ 291 i/,
i/
W
~
~~
292 V, i7 W i
209 t/,
1/.
N 252 i/,
if N
293 V M
2531V.
t/. ' N li 294 t/
U.
N 210 t/
i/,
N 211 i/,
1/, N*
254 t/
i/.
N I; 295 i/,
t/.
Terminal Strip 212 (/
i/.
s, 255 d.
i/. N Connection Ref.
296 t/,
\\/
N Ng.E M M 213 i/,
i/
N 256 t/.
i/,
N 297 t/.
g y
214 i/,
i/,
'N 257 t/
i/,
N I
298 t/.
U-N
-O;,
215 il v.
N 258 #
1/. ~
299 ie i/
~
216 i/.
J.- N' 259 Il
\\/r N-300 il 1/
.N -
V i' :
217 if, if,-
N
_260 i/.
- 1). - N
.d j
261 i/.
t/
N N-
- 218 i/,
i/,
N l
219 1/.
i/.
N 262.i/,
i/,
N s "
t220 i/.
j/,
N 263
(/
U, N
F.
221 V U.
N 264 V.
1/,
N sVM' '~ ~ ~ ' '
222 V.
i/
N 265 t/.
/r N
WT'*
Q Q & *'
I
?.AT U M.-i M 223 i/
i/, N 266 t/.
1/.
N 224 i/
U, N 267 g/,
1/,
N b
.5 kW dE%-
.v.
- '~
.~:
C
~225 i/.
i/,
x,
'..M.$$
268 (/.
i/,
N t'
u.
i 1 :
226 i/.
t/.
N I
zb9 t/,
i/,
s, d.S @:Ms*1 227 (/.
T/, N 270 i/,-
t/.
N
'- S
- TC2hb 228 i/r if, %
271 1/
il>
N d *'O 5'E'.'.M 229 t/
i/. N 272 t/"
1/i N.
i E NEi 4. R *.'
230 t/
il, u I
273 17.
1/.
N 231 V.
i/
N 274 i/
t/.
N 232 V U N l
275 t/.
' 1/,
N
)
233 t/.
i/,
N I
276 i/
t/i N
1 234 t/,
i/,
N i
277 t/
V, N
5 235 i/,
s/.
N j.
278 t/
V N
U5 236 t/.
f/
N j
279 t/.
t/.
N I
hG s
237 t/
t /. N 280 t/
t/
N ll
ist:
PROPRIETARY, MUCTE BEFORE DISCAR0 LNG
, y y, gg p I of 2 2
TINGHOUSE ELECTRIC CORPORATION 2
IND & GOVT. TU8E DIVISION HORSEHEADS, NEW YORK SPEC. NO.
T 35-41796 h
Seabrook TUBE TYPE: w y 3 3 3 / f*
S/N y,o, o y SUPERSEDED DATE "E"
Sulkhead Extension Assembly OPER.
PROCESS OPERATOR NO.
DESCRIPTION SPEC.
REV.
SIGN & DATE M Jo W-/0 O1 Stamp heat and serial numbers of bulkhead and g. ny_s o bulkhead extension on respective parts and record below.
paz Authorized inspector Hold Point.
Check flt of bulkhead in bulkhead extension. May be done
/J 4f//-/ M after Operation #3.
i
& J.,f p,y p.fb FA3 Dye check bulkhead weld area.
212-250-2 G
Record.
Cleaner Lot #
77ga#5"'
y Dye Lot #
g& o 82.
Developer - -Lot #
- a C///
/ 8 - 2. P-4 8 4
Assemble bulkhead and extension and make root 213-6-2 E
pass weld.
Record weld filler information:
Sched. I r
TYPE "$ O 9 2.,
Dia._
' SA 2 -
Ht. i d f o ~I ?
-D
/ d2c / 3 9 8
PO #
ef f d se xc
^
FA 5 Dve check and visually.insneer well norned-212-250-2 G
//~y.fd g '-'b{
Cleaner Lot #
79#ad".S~
211-1-46 8
Dye Lot i s'Gof.7_
Develc,i,6r Lot i A'od' //
-ll-T-..FU
/
[
6 Make weld cover pass.
Record weld filler 211-6-2 E
Information:
Sched. 1 F
IYPe T C 7 na,....
,n tr
~ ~ ~ '. " ' "wc"LU e
ot,.
H MI Ht #
Tf tf 2 'l / '7
!/~f d
PO #
96-"d d 9.'3' 9 /
Br -
J SV i-Il L&C 7
Flatten /and -- 8fa= =~-W Tee d 94)
'M Is17en b
~
ofi :'28 AmM u ->
Vo P
ll-1 "ge%. "
si
.3
,vo l
8 TEM DESCRIPTION HEAT NO.
S/N Bulkhead 40-1712
- /74/4
/y
.e-AsSEM8W ML
,n Bulkhead Ext 17-4001c
/pu dI_,
/p/
I) BTEM NUMBER FROM DRAWING 0
OPERATION WITNESSED BY Q.C.
Tail Piece 42-4011; A
a OPERATION PERFORMED av e.c.
Code Labe1 43-3371
~
O AUTHORIZED INSPECTOR hcl.D POINT CUSTOMER INSPECTOR WITNESSED CUSTOMER INSPECTOR HOLD PolNT PRESSURE BOUNDARY REV.
P e NO GM emm APPn DATE es CHANGs fb "N
3 A
d
~
N OR
...../
PROPRIETARY. MU( TE BEFORE DISCAROl'NG
{9,1 sisT.
,N,,
WESTINGHOUSE ELECTRIC CORPORATION
/,. g. g PAGE 2
s DATE g
0 IND K. GOVT. TUBE DIVISION
~
g HORSEHEADS. NEW YORK SPEC. NO. T 35-41796 Seabrook
//3 S/N P/4/a %
TUBE TYPE: g g3gfg-
'Bu'1k!.ead Extension Assembiv -
SUPERSEDED DATE
~
OPER.
PROCES3 OPERATOR l
NO.
DESCRIPTION SPEC.
REV.
SIGN & DATE M /,5 212-250-2 G jj,j 7., go da 8 Dye check and visually inspect weld.
l... -
Record:-Cleaner Lot #
7f//o f,5-~
213-3-46 8
., A s t'),",$u Dye Lot #
s f G o 9 2.
W ' ~5' ffGj 11J3/t
Deve1oper Lot i f o d'/ff p1-,, b) i Afdyr ;/,;E A _-f.s* S M A LgAv
.9'g"-9 717 c.
gin 4 //-/(1-d'0 t g st, s
A9 Dimensionally inspect assembly.'
35-41796 DD n-+B 10 Weld tail piece to bulkhead.
Record weld 213-3-16 M
.E
/
filler information:
Sched. 9 8
Type
'3 0 /r
~
Dia.
- /t (,
11-l/7D Mr. e o. x o c y pg y q
g y y, $,
~
11 Leak check tall piece weld.
208-6-22 INI D. pal #*/l*N 1
- al2 Ole. test and visually insoect tail niece wald.
212-250-2 G
J g'. 4, F -
Record Cleaner Lot #
pf#/o_r 213-3-46 8
j z -//-fo Dye Lot.#
fGdt 2-p e/II:"
Deveioper Lot #
,f v g"y//
/7.-tW- @f W /2 6 70 M/N S* b ED I.1 Pneumatic test assembly 60 PSIG for 10 minutes.
252-1-51 8
'~~
D.14 A.I. Hold Po_nt.
1 i
jg,.;p g 15 Weld code label.
Record weld filler infor-211-3-22 E
k mation:
Tvoe '5 C 9 sched. 1 n
Dia.
8/r to Ht. #
o @ *f 9 l~
PC i 9 Y C i 2 'r'.3 9 16 Sand blast bulkhead extension.
252-1-52 INI OfAr/-f-8/
A 17 Inspect. sand blastina.
SSPC-SPIO j,,,g.g I.m pg.g//
18 Paint outside and inside of extension with 35-41796
/-7.-
peoxaluminite.
{
DESCRIPTION HEAT NO.
S/N
-e-. ASSEMBl.Y S/N -
j
(
( ) ITEM NUMBER FROM ORAWING I'
-dg gww-g
, OPERATION WITNESSED BY Q.C.
O A
OPERATION PERFORMED BY Q.C.
~
^^
k
- W N k
O AUTHORIZED INSPECTOR HOLD POINT w'
CUSTOMER INSPECTOR WITNESSED i
.,o
\\m E_.,
//
CUSTOMER INSPECTOR HOLD POINT g --y PRESSURE BOUNDARY REV.
P c NO ORWN CHKD APPR DATE h CHANGE N
/f 3@
NR $g %
- 68
/v
( -
..-)
j i
.e i
Pen. ser.' No.
f/ m a '/
Record' ET-2544-R1 No. gg_-
L'
.r l
f.-
a.
PNOEMATic JEST REPORT e 3'/A~ M dBI* ' ~ ~ '2 ' -
l' Contract Bulkhead Extens' Ion, Part No..9'/- Yd 4 J Y' Serial No.
/M
_ - e.r.t.a_ l_- No.-
X./4 ~~
~
v _.4_= _.
m._. ' -- - BuIkhead Extension.'.Fxt llen.
- A--.
S.
_-:5-..
Test Pressure SO Pstg Nitrogen Test Duration, Time
/4 M./
x
/
.1
}
Bulkhead Extension, Serfal No.
"/Y Passed
.I Failed t
Passed ~ # Failed AM
- - -l--
I Bulkhead EItension, Serial No.. - -..
I '. ~- ~-.' Recc'rd Prepa ed From Travelers Bybte / $A ~ & $ /f-f7
~
7-sg Record Reviewed and' Certified By
//4 W 'koairFM'.T
/2 -/J~- ? O 3
Operator Dets
~~
~
.-. _ _.d'.
.. =..
...._. ~.....- ~~
-W--...,......-...-..-,u,.-.,....--
u.
u.
~. -..
'75kMAS b -NVO
'~L
~.... a =:.
-Q, g
p-
.I Quality Control Observer Dets
.1
- _. ~.
r..
r a
DOCUMENT REVIEWED MAY 211981 c.,
Br -
J S.V L
utsc
'. :-C i
c
. : 7. -..:. _...,. g
.)
-.- - --, 3..
,.. e. -
y.,
.c.
i..........
...,,..p....,.
.e
.-.~.
u:f.w, m+-:.,..
. g;; -
-.. o.
Q.g. y Nne yift;.
~~
. f,.
. %. A ;a,.s g. *
- e.
-....v w{ % y,;.s t Q..y r
- qr.
. := - -
.. i.s.. A **.
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' 5 * ;'y
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s
.4 q. z.4 y?.s s.,4;n,,.',g.
g.
.'..a.*.
.. A
_9; b fS L __2 8 _.
w
.. u ts-8 ~
- 3 i'
o
=-
'- -- ET-2562-R2' o
./
i I
i Project SE'Af@ GOOK _
Contractor Ves tinghouse Electric Corporation
- Penstrition Type WX S 35'/S-Tag No.
// 3 Serial No. 8'/o/04/
Drawing No. ' 9 < J//796 Veld No.
4 si 6 Traveler No.f3S: Ryg.
COMPONENTS
~
~~
~Name 84fd5//M-PfD Naine ~ Sz/4N, Syrl* _ Hame Fi11er Name F11ler Mat I.
8 Part No.dd -3732 Part No.' 37-4 ten 39 _ Type ER 3n9
. Type
- ER 3d9
- JA 24d
. M 373 Ma tff.._ r M ar-po.se Hat'1.
v.g s Diam.
7/s2.
Diam.
. adtr-t
.-. Ne'at No f) 74 f6 Neat No..~}_4sblX
- Neat tio.
O th7 7 Neat No.
'742 f-17
.-... Serl;al No..- /4 -/'
Seria11lo.1
/W 1 ;P.0. No.-
/2 439
= P. 0. No.-
' o 93 ys WaTd bperation Ident: Root Pass per Process Spec.
2/3-4 -2 3
L.
dWRi312dy'
//- 7-J'o_,
wit Operator ident and-Date T
/V//
Leait Check inspector ident and Date
,1 i
M. >P/'tsra hy-s-
/.f
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WESTINGHOUSE ELECTRIC CORPORATION ce IND E. GOVT. TU8E OlVISION N
Seabrook
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HORSEHEADS, NEW YORK SPEC. NO.
T 141-33511, 141-33517, 141-33513
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w x 3 35/5-sin p,,, o 9' (141-3351 % 15, 16, 17, is, 21, 22 TU8E TYPE:
0 3381d FINISHED PENETRATION (LV-3)
SUPERSEDED DATE OPER-V! ' l1 Sb PROCESS OPERATOR NO.
DESCRIPTION SPEC.
REV.
SIGN & DATE j
l Assemble bulkhead assembly, terminal box,
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plumbing and gage valve assembly.
- 4. t-r /
Z Lightly grease red and black "0"
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grooves.
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. Install modules and/or plugs in header.
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Clamp modules and/or plugs using retainers.
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Sniffer leak test.
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Start of Pressure Holding Test.
l Record.
DATE TIME TEMP PRESS 94., e l 7tooAM J V, d %
dd.A Ig Aar f r 7:0s As, I,a 3. d *r 54.9 I
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1 rncismsT REVIEW!D 1
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L asar e1 Sca1 At and of 5 days, temperature corrected as 5.
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pressure drop is not to exceed 10 psig.
do '/-/V-l/
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shipping.
43 C. f'f-E/
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J3 Authorized inspector Review may be accomplished any time before Operation #15.
h M y-tb-f' DESCRIPTION HEAT NO.
S/N s - ASSEM8LY S/N-( ) ITEM NUM8ER FROM ORAWING O, OPERATION WITNESSED BY Q.C.
- A OPERATION PERFORMED 8Y Q.C.
O AUTHORIZED INSPECTOR HOLD POINT CUSTOMER INSPECTOR WITNESSED CUSTOMER INSPECTOR HOLD POINT PRESSURE BOUNDARY
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TINGHOUSE ELECTRIC CORPORATION DATE /Il II-lb FAGE IND. & GOVT. TUBE DIVISION
/w Seabrook HORSEHEADS. NEW YORK SPEC. NO.
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TUBE TYPE:
141-33513 g g3g/g S/N 8/e/oI (141-33514,15,16,17,18,21,22,31 SUBJECI:
l FilllSHED PENETRATION.(LV-3)
SUPERSEDED DATE CPER.
NO.
DESCRIPTION PEC
. REV.
SIGN DATE
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10 Connect leads to terminal strips in box if applicable.
g4 11 Assemble accessories.
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Check accessory package.
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Lol3-Inspect for dimensions and appearance.
141-33518
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-,- ASSEMBLY S/N -
() ITEM NUMBER FROM ORAWING
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,CPERATION WITNESSED BY Q.C.
O CPERATION PERFORMED BY Q.C.
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'_@ F;t0P.RIETARY. MUTILAT E 5EFori! DISC A ADINF, DDE
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S, WESTINGHOUSE ELENRIC CORPORATION E
IND. & GOVT. i jE DIVISION
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Seab rook sf TUBE TYPE:
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S/N f/O/d4/
(141-33514,15,16,17,18,21,22,33815)
FINISHED PENETRATION (Ly-3).
SUPERSEDED DATE / j _, j p g 1
Pareto.
Heat No..
Ser. No.
iqgy.
Part Description o
&/ 7 6 #6
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Bulkhead an-tits 37-4d639-
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Tallpiece 904*//o
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Hea"dE t; ** ~ '. -
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i Position 8 - Module 3 39 75-m 2-J37 y
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50-k0014 A l ?2' 33 7/ S
fo S // 5 75 /weD-237 i.
Posi tion G - Module gg ry g
Heiderm " ' -
44-40014 K/ 76 3.2 7s ?
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8 5/5 X 11 Stud 42-111n 87 h? tsti 2N In 5/8 X 11 Nut 40-3902 o o /79 6-Retainer 42-11og 87 i
6 1/2 X 13 Stud 42-1309 2H 0
1/2 X 13 Nut nI rw,:N 4) l 1:""WRw.7 11 I
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79 H/03 Resin Dye SG4j'A SGo82 Hardener -
to 32uClo Developer s'o p ///
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Size PO No.
Size PO No.
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Type l
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-o - ASSEMBLY 5/N -
(
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( ) BTEM NUMBER FROM ORAWING f
0 OPERATION WITNESSED BY Q.C.
A OPERATION PERFORMED BY Q.C.
O AUTHORIZED INSPECTOR HOLD POINT CUSTOMER INSPECTOR WITNESSED If CUSTOMER INSPECTOR HOLD PolNT PRESSURE BOUNDARY dC.V.
PC NO
,DRWN CH at O APPR OATE Ca CMANGE REVIEVED BY THORIZED y
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l 0157 l
WJESTINGHOUSE ELECTRIC CORPORATION issue cava surestsanan sava IMO. & GOVT. TUBE DIVl5102
'/- Q. Tr I
~ HORSEHEADS. NEW YORK g y., c,
~
FINAL INSPECTION AND RELEASE Enter the Complete a copy of this Inspection checklist for every' unit i l
ld Check the ACC or REJ column as appropriate for visual examin-File completed checB dicate acceptance.
Use the REMARKS column to explain any nonconformance. ~
l
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~
_11st wTt.h the~ test data for the unit.
~
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10.0' _/20 12,0 QCP 4-8 ~
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- 2. 2~
8 - 2'. T te_ 1, Verify _ M ' Visual o._ i ~ ~ -- }.. t ~l.. ~. c-t i % MENT Rt \\ I MAy y E6.. l s .ee - ...e M 3.I General Appearance Assembly.-Noforeign materlaj Labels - present and correct J.2 Pressure /[ PSIG 2'3 Temp C 33 Verify Hfg. and QC Sign offs g 3.4 Check loose items M5PECICPRTNT ISWE ~ 4 J PRESSURE BolN)ARY .h}.= ,( A G a fa w r u n / nave ewseerten ev /ve/ 3 N h M . c oe av22 s / s
-- ar - 1 O 3 Wx No. 33 C/5* ~ Equip. Tag'No. //3 H39 Seabrook L.V. Loose items List . _.. -... _ ~.. - '~~ g- _ ..Disdrip ti66 ' * * ' N6;**
- Required Operator QC Part-Quantity
_ g gg- - ' Sign. Sign. ' ~ ~ ~ ~ ~ j . Jv I. Cable Support A 35-41797 1 V C. p, -- 2 ' Slip On Planga 48.'40063 1 'T --3 Bolts 42v40594 12 g. A '4-notts 42-40432 72 NA NA 5 Washers 42e40347 72 yA NA~ ~ 6 Nuts ~-' 42-40246 72 A/A g,q 7 Washers - 42-40345 24 Jc. 8 Nuts 42-40251 12 jc k A/ A NA 9 Plugs 42-40577 20 i 10 inboard Box A Jf-y/ F// 1 .jc fp O WD MAYN % k \\ e C f = M
r... _ _ y, ,5 ./ Reactor Coo..ht Loop Piping - Welding Procedure Specifications and Quality Assurance Procedures Procedure No.: 55171B Issue Date: 01/01/79 9 SECTION I INSPECTION OBJECTIVES Determine whether welding procedure specifications (WPS) and quality assurance procedures used by licensee / contractors for field welding of reactor coolant loop piping have been established, qualified and controlled in accordance with NRC requirements and SAR commitments, including the licensee's QA program and Code requirements, as applicable. m i 1 l i l I i l I-l l '
r__= TEST HEFO!!! Ti.P e$fHYFf.)@dx x%%lx '3 'a ,i tu/d.8. add /NN.-/ /88.f DATE: 10/20/81 SOLD TO: Abco SHIPPED TO: United Eng. DATE SHIPPED. 10/20/81 ~ 130 Cross Rd. Rt. 1 Site Access Rd. waterford, Conn. 06385
- Seabrook, N.H.
03874 . -[ ~ ~. P.O. NO.:. 5454 P.O. NO.:- 97 011-22458 SPECIFICATION: ASME Sect.III C1 ass 1 Subsection NB-2400 877 Ed wint. '77 Add. Sect.II SFA 5 9 ITEM POUNDS SIZE TYPE IBM XDOf NO. HEAT NO. I-1000 .035 ER308 308X297 55049 2. 3760 .045 ER308 308X298 78156 3. ACTUAL CHEMICAL ANALYSIS OF WIRE Enxmx2xitgxw ITEM C Mn P S l Si Cr Ni Mo l Gu l V i! - l LDtTa-i E .04 1.70 .008 .008 .41 19.89 9.88 .13 .021 l .024 .017 l .063 2. .04 1.68 .009 .009 34 20.07 9 99 .09 .020 .023 .017] .0M 2 3." -t ADDITIONAL TEST RESULTS g G#4!Ti SY5iEM CERT!FICATE MSTS PERFORMED WITH: N/A (W.TER!A!.5) X. RAY: N/A ($C.255 c C'.1,*.St'.GY ',123 STRESS RELIEVED N/A HRS. 6
- F.
AS WELDED STRESS RELIEVED PLATE NO. N/A PLATE NO. N/A YIELD POINT, PSI TENSILE STRENGTH, PSI ELONGATION IN 2". % REDUCTION OF AREA, % PLATE NO. N/A PLATE NO. N/A , pg
- F ft. Ibs.
- F
_ ft. lot
- 1. Ferrite = 9%
j
- 2. Ferrite = 7%
4 ' St:t3 of certify the chemical analysis anci physics or rnecher. cal test resuits reported above are correct as contair.ac. Cih d in the recorca cf the company. Subscribed and sworn to tefore r.e inis_ ccy of 19_ _ .c... Idy,cc:nminion expires -J' g. w
-- m =. = -~~ '=. -. ar ~.~m --n~~.,--. { { l MATERIA') CERTIFICATE ~ 'I q SANDVIK, INC. 5CaANTON WORK 5 P.O. BOX 1220, SCR ANTON, PA.18501 PH: 717. $37 3191 g W PLANT LOCATION. INTERSTATE 31. WAVERLY EXff 59 Cus!0teER PURCHA51 ORC (R N0 5ANovut ORDIR NO jf!M SPECIAL CODE MARES CIRilFICAff DATE 9763.011-20140 - 151574 05 26376 2012.97 3/25/81 soto To: PUBLIC SERVICE C0 0F NH SEABROOK NH SPECIPiCATION ANO MATERIAb ASME SECTION II: SFA5.9; ASME SECTION III: PARA. NB2400 1977 EDITION THRU WINTER ~ 1977 ADD. SANDVIK STAINLESS STEEL WELDING WIRE TYPE ER 308 .045 x 2.5#sp Actual Weld Deposit Analysis, % Heat C Si Mn P S Cr Ni Mo 464872 .059 .38 1.97 .014 .001 20.24 9.29 .02 ~ Cb Ta Ti V Cu N .01 .01 .01 .057 .026 .068 I Delta Ferrite content as determined from above analysis per Fig. NB2433.1-1 WRC Ferrite No. 6 FN . Corresponding ferrite percent 6% This is to certify that the contents of this certificate are correct and accurate, as contained in Sandvik's records, and that all above tested results and operations performed are in compliance with the requirements of the purchase order and the applicable sections of the Code and specifications as designated by the purchase order. ASME Quality System Certificate (materials) No. N-1400. Expiration Date: June 11, 1982. QA/QChTE ~ REVIEWED By A 2 K Ec__ UE & ~C v/ f /r i For Be t H. Berg, Quali Assurance Manager (W-B-SFA-3, REV. 5)ke s _ h,_ m f f
l ~ 'i,, i i t t i i j .J,, st '.a i i i i 4 l 2 i g.,o......, l i i i i i i
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J FIElb PURCHAOE CRDER a F oerv, 4? &S THE ORDER HUMBER MUST APPEAR ACCT.NO. b bbb oN INVotCES. CORRESPONDENCE. IIE V.12 / 76 & Cortstructors unc. SHIPPING PAPERS AND PACKAGES. DATE October 16, 1981 P. O. NO. 9763.011 -24548 Public Service Company Of New Hampshire g c/o United Engineers & Constructors Inc., Agents ,h3,"*,% ',l,*."d.,*] !",34 I,0*ifl'*"*' .50000 UN/. 5/Tr*li..C*"'**"' o P. O. Box 700 i _Seabrook, New Hampshire 03874 Pl/RCHASER O. '8"fl 7c'o"*""" SeaDrook. tvew Ham, shire 03874 Laman-Loesche Supply Company DELIVERIES ACCEPTED 302 Moore Street 7:30 A.M. TO 3:00 P.M. Philadelphia, PA 19101 SELLER MONDAY THRU FRIDAY ONLY. mE3. NoPH42810 SHIP VIA United Parcel CONSIGN TO Public Service Company Of New Hampshire nE3, sY BA
- "IC*
c/o United Engineers & Constructors Inc. DATED 10/5/81 Router No.1 - Site Access Road TvPEn av grp Seabrook, New Hampshire 03874 swEn JEB TERMS: 1L ten days, Net 30 days PRICE D E S CRI PTio N gEu Na FURNfSH F.O.B. Jobsite DE LIVERY:- W/O October 29. 1981 RIS 4 p Fel-Pro-C.}-A,.Antiseize Lubricant copperbased @ $ 5.50 ea. $132.00 24 p(ts 1. 4 15.40 ea. 369.60 2. 24 pts. Fel-Pro h g Nuclear Grade Antiseize Lubricant w _ QUALITY CONTROL REQUIREMENTS (Item 2 only) The following documents are to be submitted with, or prior to, material shipesnt to Mr. R.R. Donald, Q.A. Engineer, Pullman-Higgins, c/o Public O Service Comgeny of New Hampshire, P.O. sex 700, Seabrook, NH 03874, with copies of all transmittal letters to Mr. E.H. Watrous, Supervisor-Purchas-p ing, c/o United Enginee'rs & Constructors Inc., P.O. Box 700, Seabrook, New Hampshire 03874. All documents must include United Engineers & Constructors P.O. Number. Five (5) copies of Certificate of Compliance required, one (1) copy must accUmpany each shipment and each certificate shall be identified with United Engineers & Constructors Inc. Purchase Order Number, and signature must be written in black for reproduction purposes, in accordance with the attached Quality Control Requirements, Item No. 2, dated 10/5/81. 5 I Shir.ents will not be accepted bv Purchaser unless one (1) copy of the .C.c r_.t_i.ficate of Compliance is included with each delivery. PURCHASER WILL NOT ACCEPT OVERSHIP1ENTS l l USE:- Tools & Supplies - All Sys. Valves, Item 2-Nuclear valves Installation only I P. Loesche, Jr. CoNFIP. MING VERSAL oRoER AWARDEo TO ANo ACCEPTED BY 10/14/81 co NoT oUPt ICATE. AN AUTHORITATIVE REPRESENTATIVE oF SELLER oN THE SELLER AGREES To ANo SY ACCEPTING ANo PILLING THIS ORDER oR ANY PART THEREoF. SHALL BE sound BY THE TER*.tS AND CONDITIONS PRINTED oN.THE BACK HEREoP. No CHANGE WI L t. BE PERVITTED IN THIS oRCLR UNL ESS SY WRITTEN AGREEMENT. Public Sa$ ice Company 'Of New Hampshire TOTAL $501.60 [ I I.-.-:e con.e t ew emt ti. s.* ee :, Sei'ee atC tt ward to Un.ted ,JJ,.t.r1 M J g n g:!IC C!S. w o.. :, m. AGENTS CRDCR NO. 9763.011-2'.5!.8 l w.m a c.
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.-._bnited1.nt,incbs&CcastructorsInc. s () q i Quality Control Requirements e L
- -L0ESCHE SUPPLY COMPANY PH42810 10/5/81 9763.011-24548 10/16)81 I
SELLER REQUISITION NUMBER,- DATE ' PURCHASE ORDER NUMBER - O i 1. Material Certification Seller shall furnish four copies of Mill Test Reports for the material purchased showing the re'sults of all analyses and tests that are performed by the producer / manufacturer, including those required by the material specification and/or in accordance with the Purchase Order. The reports must also include the name and location of the producing facility, UE&C Purchase Order number, the heat number of each item covered, item descriptions and quan- ~ ities, and have an original signature affixed 'by,a person authorized t to de so. Any non-destructive testing results shall include the procedure and acceptance standard employed. Certificate of _ Compliank:e_ ' 2.; Seller shall furnish five copies of a Certificate of Compliance that Q the materials furnished hereunder are new, have been manufactured, shop assembled and tested to U.S. standards (unless prior written 7 approval to the contrary is obtained from UE&C) in accordance with the mahufacturer's normal processes and inspections. to assure an acceptable level of quality consistent with the requirements of-- the specifications and Purchase Order. - 3. Work::anship & Wonconformances_ r ~ Seller shall comply with all codes, regulations arid standards' applicable to. the work. If the Seller observes that specifigations (- or drawings 'are at variance therewith, he will inform UE&C, in j writing, requesting appropriate modification. Should the ScIIer perform eny work knowing it to be contrary to these requirements. 2 l and without such " notice to UE&C he will bear all costs arising l therefor =. Defective material shall not be repaired and used in the construc-l tion of the equipment without prior approval of UE&C. For defects in canufacture, including castings, the method of repair shall be mutually agreed upon by both Seller and UE&C. 4. Special Requirements .O . I l-
- QA/QC Engine'er
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l - - -. - ~ j Y ( ~ yf. :.... .M.. ; A DETAILS J ,. 2 1. Persons Contacted ankeeAtomicEle$tricCompany(YAEC) ~
- 0. L. Covill, Lead Civil QA Engineer J. H. Herrin, Site Manager (PSNH)
- G. F. Mcdonald Jr., QA Manager (Framingham)
- W. T. Middleton, QA Engineer
- J. A. Philbrock, Senior Project Engineer (Framingham)
- J. W. Singleton, Field QA Manager
- R. K. Tucker, Lead Mechanical Engineer (Framingham)
United Engineers and Constructors (UE&C) R. G. Blair, Construction Superintendent / Civil Superintendent
- J. A. Grusetskie, Site Engineer
- 0. C. Lambert, Field Supervisor - QA l
K. M. Kalawadia, Structural Engineer (Philadelphia) l
- 0. McClellan, Civil Structural Site Engineer R. D. Tancibok, QA Engineer W. Tinlan, Construction Superintendent 4
J. Todd, Construction Engineer 9 U. S. NRC
- A. Carne, Senior Resident Inspector 1
l Perini Power Constructors (PPC) R. Rudala, Structural Steel Weld Supervisor L. Granpre, Concrete Coastruction Superintendent R. Hammer, QC Inspector Structural Welding R. Hart, Site QA Manager R. Narva, Supervising QA Engineer - Concrete J. Pattison, Supervising QA Eingineer - Welding R. Vachon, QC Inspector - Concrete R. Collins, QC Inspector - Concrete Pullman - Higgins (P-H) M. Daniels, Non-destructive Examiner - Structural Steel Welds
- indicates attendees at exit interview August 27, 1982 f
The inspector conferred with other if censee, construction manager and l contractor personnel during the course of the inspection. I i );Qit ~DnA 5 ^ ,1 14 i
l F;lis Ns.19 6 55.,r pp,~~ '} MIN-CESCHE SUPPLY C] INC. CONTRACTOR,-IllDUSTRIAL SUPPLIES & EQUIPMENT Inv. No. WAREHOUSE: N s \\ CFF CE: 302 MOORE STREET inv. Date 1820 L MOYAMEN5tNG AVE. y tilL AC ELPHI A, P A.19148 .da,,.n .L ci. ~..- C in M. = u / Y ) t. <a E :,,1~.4 A6in' E .\\ - G 7t.. 7. r.s/. hi. - /.0 </~fn /> fp//St oeseaeavio u,.,1 l ...e. i. ou, vorai. .< -.. = s i "r,' a"t.',,, 6 l l l 7_ _N 7 NT I / r-l l / x10 C GTD / I ( / V I n l.-~^//..A/}/stt. u..,t u ?'. f n,. l e .x { l j, N \\!I I I-I e W ). o i-
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a e .q 3 e I NSPECTION AND MAINTENANCE PROC ~ Paragraph 5.1 SECTION 5 I ( SECTION 5 INSPECTION AND MAINTENANCE PROCEDURES
5.1 INTRODUCTION
- 4. A step'by-step procedure delineating the pans to be removed from the vessel and the tool or tools necess-This section covers the procedures for periodic inspec-ary to remove them.
Lions, tests, a4ustments and repairs to maintain the availability or performance of the steam generator.
- 5. Provision of any necessary mockups to qualify the Because the steam generator is part of the reactor coolant procedure, tools and personnel.
system, servicing of the unit (particularly on the primary side) will most probably result in exposure of servicing
- 6. Precautions taken to insure that no tools, personal personnel to radiation. Therefore, it is important for the items, or loose internal parts are accidentally dropped utility to prepare detailed servicing procedures and train into th6 steam generator or the primary coolant pip-the personnel thoroughly in all aspects of any service ing, for example:
procedure. It is recommended that the utility consult with the Westinghouse Nuclear Service Division in plan-
- a. Lanyards tied to all tools.
ning their maintenance activities.
- b. No coveralls with outside pockets.
WARNING
- c. Clean tarpaulin or heavy cloth which may be used ALL MAINTENANCE PROCEDURES to close the cavity between the shell and the tube MUST BE CLOSELY CONTROLLED TO bundle wrapper.
COMPLY WITH APPLICABLE FEDERAL, NATIONAL (FOR EXAMPLE U.S. CODE
- d. Inventory Checklist of tools, temporary seals, OF FEDERAL REGULATIONS. TITLE 10, covers, maintenance items and personal items CHAPTER 20), STATE OR LOCAL RE-(glasses, watches, rings, pens, etc.). Non. essential p
QUIREMENTS. WHENEVER POSSIBLE, loose items should not be carried inside the steam THE MAINTENANCE WORK SHOULD BE generator. REHEARSED IN A " DRY RUN" TO KYEP l ACTUAL MAINTENANCE TIME AND
- e. Properly fabricated and installed covers over the R ADI ATION EXPOSURE TO A channel head primary coolant inlet and outlet MINIMUM.
nozzles. i 5.1.1 Preparation for Maintenance
- 7. Allotment of a specific clean area adjacent to the steam generator to conform to and maintain cleanti.
i Prior to disassembly of any openings and especially ness requirements and to provide for temporary where bodily entry into the steam generator is to occur, storege, cleaning, and inspection of pans removed. j appropriate procedures are to be prepared delineating the i requirements involved for the specific operations. The
- 8. Record of all locked parts and the manner in which I
following considerations should, as a minimum, be they were locked prior to disassembly. f acknowledged in development ofinspection and mainte-i nance procedures.
- 9. Disposition of pans removed; e.g., replaced with new parts, or condition of old parts reinstalled.
- l. Purpose of operation to be performed.
i e 5.2 SECONDARY SIDE IJPPER INTERNALS INSPECTION AND {
- 2. Any precautionary air (oxygen level) and radiation MAINTENANCE 2
measurements which must be taken. WARNING =
- 3. Instruction of personnel who will actually do the work:
what to examine, how it comes apan, how it goes IT IS AESOLUTELY NECESSARY TO j together, and precautions to be observed. PROVIDE ADEQUATE VENTILATION TO SO 0P 51 v. s 1 lYSS - -. ~...
Persynd 5.2.1 SECTION 5 - INSPECTION AND NIAINTENANCE PROCEDURE 8 i contain a wire thread insert for proper engage. bolts. Protect the bolts to prevent thread
- s.,
ment between the bolt and the tapped hole, damage, which may cause the bolts to be unfit Refer to the As-Built Drawing, Figures 15A to for reuse. 1 5D for specified use, if any, of such inserts. It is unlikely a wire thread insert will disengage from the manway pad bolt holes during closure 5.2.2 Inspection and Removal of Secondary Side Upper disassembly. However, examine each bolt and laternals (Secondary Moisture Separator Vanes) hole and notify Westinghouse for further instructions should r.ny wire thread inserts The following steps comprise the disassembly procedure i become unscrewed. .to be used.for removal of the secondary moisture sepe. retor vanes. Sep 2. Remove the handhole cover and discard the gasket. Detail "B," Figure 11. It may be NOTE t necessary to gently pry or " work" the gasket free from the recess. Inspection and removal of separator vanes is accomplished from the inside of the separator CAUTION housing qBer entry through Bank "E," (see Figure 1 3), which is the only bank that must be TAKE CARE TO NOT NICK, GOUGE OR SCRATCH, opened from the outside of the separator. ESPECIALLY IN THE RADIAL DIRECTION, THE GASKET RECESS. IF THE GASKET RECESS IS NOTE NICKED, G0UGED, SCRATCHED OR OTHERWISE DAMAGED, THE OWNER 15 ADVISED TO CONTACT Consult Figure 13 for Steps 1 through 7 WESTINGHOUSE FOR FURTHER INSTRUCTIONS below. BEFORE ATTEMPTING TO COMPLETE THE CLOSURE. Step 1. Remove the perforated plate (108), which is the i Sep J. Cover all bolt holes on the manway cover "'"*[.
- E "
E'**** # "I
- ""' II "8
- mounting pad with corrosion-resistant tape (see Section 6.3, Item 3). It is recommended that a
."I' temporary cover of wood or polyethylene be r a ' Removal of this plate will expose a small section taped over the manway opening to block entry i of foreign material and contaminants whenever the nsanway is not being used. Step 2. Remove the Bank "E" Top Vane Cover (11) and Bank "E" Bottom Vane Cover (12) shown CAUTION in View "E." The top (or bottom) cover is secured to the moisture separator housing by I DUltlNG MANWAY D15ASSEMKY OR REASSEMBLY .12 in. [3 mm] fillet welds on the sides and a OPERATIONS, EXERCISE CARE TO AVOID DAMAG-small bevel weld on the top (or bottom) edge of ING THE GASKET SEATING SURFACES. PROTECT the cover. FLANGE FACES ON THE COVER AND PAD BY COVERING THEM WITH CORROSION RESISTANT Step J. Grind off the locking welds on Bank "E" Jack-TAPE (SEE SECTION 6.3, ITEM 3) OR. AS AM i ing bolts (1), (four bolts total) and loosen; j ALTERNATIVE. LEAVE THE OLD GASKET TEM-remove bolts and locking plates (5), which will i 2 P0RARILY TAPED IN PLACE AS A PROTECTIVE release the compression load on the vanes. O COVERING. DO NOT REUSE THE OLD GASKET. IT 3 MUST BE DISCARDED. 3 l Step 4. Remove the standard vane assemblies (3) and Jacking vane assembly (4) through the " slots" Sep 4. After removal of the bolts and manway cover. created in the opening by removal of the top and take care to properly store both the cover and bottom vane covers per Step 2 above. [ l l l l 53 l
g o 9 0 Peregraph 5.2.3 SECTION 5 - INSPECTION AND MAINTENANCE PROCEDURES .e approximately 126 standard vanes in each bot. channel, filling the bank to the opening created k tom bank. Although the majority of the vanes by the perforated plate (10-B) removal. can be installed by simply tilting them to fit into the housing racks, as the bank fills up with Step 7. Perform a final cleanliness check of the sec-vanes, it will become necessary to install the,last ondary moisture separator interior. Remov,e all. few vanes through the corner cutout. Install tools, and then continue to install the standard vanes per Detail "B," being careful to note that vanes from outside the separator housing until the " hook" or " pocket" points toward the the bank is filled. The vane installed at the jack-interior of the assembly and the straight or trail-ing bolt end must be a jacking vane (4). Ing edge of each vane points toward the exterior or shell of the generator. Step K. Install the bolts (1) and locking plate (5). Tighten the bolts (1) so the vanes are not free to Ster J. Tighten bolts (1) so the vanes are not free to move, but still retain the dimension of 1.5 in. move, but still retain the dimension of 1.5 in. 138.1 mmi or less between the jacking vane and (38.1 mm) or less between thejacking vane and the housing. See Detail"B." If the distance be-the housing. See Detail "B." If the distance bet-Iween the jacking vane and the housing is. ween thejacking vane and the housing is greater greater than 1.5 in. [38.1 mm), then add one or than 1.5 in. [38.1 mm), then add one or more more additional standard vanes to achieve the additional standard vanes to achieve the specific specific dimension. Gage all vanes to 0.20 to dimension. Gage all vanes to 0.20 to 0.50 in. _ 0.50 in. [$.08 to 10.16 mm) per Detail "B." If [5.08 to 10.16 mmi per Detail "B." If new vane new venejacking bolts and additional or replace-Jacking bolts, additional vanes, or replacement ment vanes are needed, see Section 6, " Spare vanes are needed, see Section 6, " Spare Parts, Parts, Consumable Items and Tools," for order-Consumable items and Tools," for ordering ing information. Information. ~ Step 9. Weld the bolts (1) to the locking plate (5) per Step 4. Weld bolts (1) to locking plate (5) per Detail Detail "B." Welding parameters for Specifica-
- B." See Section 6.2. Item 12, if new locking tion NIT 32 are in the Appendix, Section 7.
plates are reiluired. Step 10. Install and weld the vane cover, top Bank "E" Siep 5. Install and weld the lower Vane Cover Assem-(11) and vane cover, bottom Bank "E" (12). ~ bly (6) and the Vane Cover (13), as well as the See Section 6 if new vane covers are needed for "L" shaped Cover Plate (7) over each Vane Bank "E." Cover Assembly (6) as shown in Section "C-C" and Detail "D." as each bank is completed. See Step ll. Install the small perforated plate (10B) and weld Section 6.2, item 12, if new vane cover and in place as shown in View "E" and the detail for cover plates are needed. Bank "E." Welding parameters for NIT 38 are in Appendix, Section 7.3. MW Because removal of the perforated plate (108) 5.2.4 Secondary Side Manway Closure Reassembly l and the top and bottom vane covers (11 and 12) creates a " slot" on the exterior of the moisture Before proceeding to reassemble a secondary side man-( separator housing in Bank "E " there is no nced way closure, the threaded holes on the manway pad, to remove and then reinstall the vane cover as* bolts, the gasket recess on the manway pad and the cover g sembly (6), top vane cover (13), and L-shaped must be cleaned using the procedure described below. O cover plate (7) on Bank "E." After cleaning, the bolts and threaded holes on the man-2 way pad are to be lubricated per instructions given below. l~ Step 6. This step and all others to follow apply only to Bank "E." Starting from inside the moisture separator housing. install a starting vane and 5.2.4.1 Manway Closure Pre. Assembly Cleaning and then sufficient standard vanes in the Bank "E" Lubrication i e ? 55 .. ~
~ ~ ~ --*"-------------------------y-- r 0 3 Paragraph 5.2.4.1 ~ SECTION 5 - INSPECTION AND MAINTENANCE PROCEDURE 8 WARNING NOTE METHYL ALCOHOL IS FLAMMABLE, Normally, secondary side manway covers are TOXIC TO THE SKIN, IS POISONOUS IF interchangeable and do not have match marks. INGESTED, AND THE VAPORS ARE However, it is good practice to reinstall each HARMFUL TO BREATHE. CONSULT THE cover on the same manway opening from which MANUFACTURER'S SAFETY RECOM. it was mmond. MENDATIONS FOR PROPER USE. Step J. Hand tighten all bolts against the cover and ,, then proceed to tighten the bolts, following the S.2.4.2 Manway Closwa ' ", Procedwo tightening sequence and instructions sivan on Figure 51. First tighten all the bolts to the The following steps cover the reassembly and bolt Intermediate Torque values shown in Table 5-2. tightening procedures to be used on the secondary side manway closures after cleaning and lubrication of closure parts per Section 5.2.4.1. CAUTION 1 AT THE COMPLETION OF STEP 3, IF A_NY NEW CAUTION BOLTS ARE BEING USED IN THE CLOSURE, THE SPECIAL INSTRUCTIONS IN SECTION 5.4 MUST BE IF_ANY,, OF THE BOLTS TO BE INSTALLED ARE Jg FOLLOWED TO "8REAK IN" THE NEW BOLTS. AFTER BOLTS, THE SPECIAL TIGHTENING PROCEDURE COMPLETING AL_L. INSTRUCTIONS IN SECTION 5.4, DISCUSSED IN SECTION 5.4 SHOULD 8E CON. PROCEED DIRECTLY TO STEP 5 BELOW, SKIPPING SULTED BEFORE ANY BOLTS ARE INSTALLED. THl3 STEP 4. IF USING ONLY OLD BOLTS IN THE CLOSURE, DO NOT SKIP STEPS 4 AND 5 BELOW. SPECIAL PROCEDURE WILL BE REQUIRED TO PROCEED DIRECTLY TO STEP 4 AFTER COMPLET-BREAK.lN THE NEW BOLTS. i ING STEP 3. Star L Remove the temporary cover, ifinstalled, from Step 4. Again following the tightening sequence shown the manway opening, and remove the plugs [ in Figure 5-1, tighten all bolts to the final torque I from the manway pad bolt holes. Install a new value of Table 5 2. Continue the tightening flexitallic gasket (refer to Section 6.2, Item 4 for sequence until all bolts are at the final Iorque proper gasket) in the cleaned gasket recess per ,yg,- Detail "B" of Figure 1 1. Step 5. Following the sequence in Figure 5-1, with all Step 2. Position the manway cover, using a lifting "'"*U * *
- I '9"' ** * * " " "
device, and loosely secure the cover in place - ne bolt, relubricate thoroughly the bolt threads I using the pre-lubricated bolts. I and the undersurface of the bolt head and then retignten the bolt to the final torque value. Con-l l CAUTION tinue for each bolt,in the Figure 51 sequence, ~ until the entire bolt circle has been tightened to EXAMINE THE COVER AND MANWAY PAD FCR the final torque value of Table 5 2. MATCH MARKS OR PLACARDS INDICATING THE USE OF A CUSTOMlZED COVER AND REQUIRING A NOTE PARTICULAR ORIENTATION OF THE COVER. AUGN This multi. step tightening procedure is des.igned MATCH MARKS ON THE COVER AND MANWAY I Prevent cocking of the cover causing incor. E PADS IF MATCH MARKS ARE PRESENT. (SEE SEC. N TION 6.4 FOR SPECIAL COVERS,IF ANY.) THE SEC- ".ct I ading f the gasket and a closure which
- '" I'*
l-* ONDARY MANWAY COVER WEIGHS APPROX. IMATELY 330 L85 [150 kgl. TAKE CARE WHEN HANDLING THIS COVER TO AVOID INJURY TO PER. Step 6. Check the torque value of all bolts, using the SONNEL sequence of Figure 51. or alternately a clock-l l l 57 ,,_,,,-_n
n 9 8ECTION 5 - INSPECTION ANO IRAINTENANCE PROCEDURES Paragreps5.2 PERSONNEL ENTERING AND WOREING WARNING INSIDE THE SECONDARY SIDE UPPER r INTERNALS TO AVOID SUFFOCATION TO AVOID POSSIBLE SERIOUS INJURY OR EXHAUSTION WHILE INSIDE THE TO PERSONNEL. THE UNIT MUST BE UNIT. BOTH SECONDARY SIDE MAN. COMPLETELY DEPRESSURIZED, WAYS SHOULD BE OPEN PRIORTO AND DRAINED AND VENTED BEFORE DURING ANY UPPER INTERNALS STARTING CLOSURE DISASSEMBLY. MAINTENANCE AND FORCED AIR YEN-TILATION ESTABLISHED THROUGH Step 1. Insert an eyebolt (18UNC 2A) into the THE UNIT UPPER INTERNALS VIA THE threaded holein the side of the secondary man. MANWAYS AND/OR INDIVIDUAL mv cover, Figure 1 1, and attach the cover to a RESPIRATORY EQUIPMENT PROVIDED suitable lifting / handling device using slings TU PERSONNEL ENTERING THE UNIT through the eyebolt. Folicwing the sequence SECONDARY SIDE UPPER INTERNALS. and instructions on Figure 5 1, begin to remove the 20 bolts (1.25-8UN 2A) securing the cover. The purpose of Inspection of the secondary side upper First, loosen in sequence allbolts only 1/12 o/a internals is to examine the condition of the primary and twn. or approximately 30*, and then repeat the secondary moisture separation equipment and to deter-sequence, this time loosening all bolts an addi-mine if any parts need service. The moisture separator tional 1/6 of a twa or approximately 60*. Nier housings, piping, and drains normally do not require ser-completion of these two sequences in the cover vicing. However, delicate items, such as the vanes in the loosening process, the bolts may be completely secondary separator, may need repair or replacement. As unthreaded and removed. It is recommended a precautionary measure, all internal surfaces should be that at least four bolts, equally spaced on the examined for corrosion, erosion or mechanical damage bolt circle, be left in place until the weight of the and any unusual conditions noted on suitable forms for manway is completely supported by the lifting future compilation of troubleshooting charts. If signifi-device. cant damage from corrosion is observed, the secondary i l side water chemistry should be carefully checked, (Refer WARNING to Section 4.6) and Westinghouse notified (see Front Matter, page li). THE WEIGHT OF THE SECONDARY MANWAY COVER IS APPROXIMATELY CAUTION 330 POUNDS 1I50 ks]. EXERCISE CARE AVOID DROPPING TOOLS OR PARTS INTO THE WHEN REMOVING THE COVER, TO LOWER PORTIONS OF THE STEAM GENERATOR AVOID INJURY TO PERSONNEL. WHEN ASSEMOLING OR DISASSEM8 LING SEC. l ONDARY SIDE INTERNALS. SEAL 0FF ALL PRIMARY CAUTION l SEPARATOR EXIT OPENINGS OR ORIFICE RINGS l (SEE FIGURES 12, AND 21) ON THE MO. DECK BEFORE REMOVAL, CAREFULLY EXAMINE COVER ( l AND THE DOWNCOMER ANNULUS BETWEEN THE AND VESSEL MOUNTING PAD TO DETERMINE IF WRAPPER AND THE SHELL TO PREVENT FOREIGN ANY MATCH MARKS OR PLACARDS EXIST INDICAT. i' OBJECTS AND TOOLS FROM STRIKING THE TU8ES ING THE COVER 15 CUSTOMIZED FOR THE LOCA. OR BECOMING LOST IN THE LOWER SECTION. IF TION AND MUST BE REINSTALLED IN THE SAME WELDING MUST BE PERFORMED DURING A RE. LOCATION AND SAME ORIENTATION (MATCH PLACEMENT OR REPAIR. EXERCISE EXTREME CARE MARKS LINED UP) ON REASSEMBLY OF THE TO AVOID STRIKING ARCS ON THE STEAM DRUM CLOSURE. REFER TO SECTION 6.4 FOR A LISTING SHELL OF SPECIAL OR CUSTOMlZED PARTS AND THEIR N LOCATION. k 5.2.1 Secondary Side Manway CIcsure Disassenbly NOTE The following steps comprise the procedure for dis-assembly of the secondary side manway closures. One or more manway pad threaded holes may [ s l k 52: l l - + - - -
O 9 SECTION 0 - INSPECfl0N AND MAINTENANCE PROCEDURES Persyspb 5.L2 NOTE NOTE All vanes should be marked or identified as to There are approximately 151 standard vanes location and orientation prior to extraction (3),in each upper bank,(banks "A,""B,""C" through the manway. and "D") and 126 standard vanes (3), in each lower bank (banks "E," "F," "G" and "H"). Sg J. After sufficient Bank "E" vanes have been Each bank has one starting vane and onejacInns removed, the interior of the separator housing vane. may be entered for examination and removal, if 4 required, of any other vanes from the remaining - NOTE i banks in the moisture separator assembly. See steps below. Normany service is not'necessary below the i mid-deck plate (See Figures 12 and 21). If S g 6. The removal of starting, standard and jacking access is necessary, there are ladders and vane assemblies (2,3,4 respectively) from the hatches with welded-on covers in the mid-deck remaining banks can be accomplished by first plate and hatches with welded-on covers in the grinding the bead weld connecting the "L"- lower deck plate. Open hatches and ladders are shaped Cover Plates (7), located in the lower on the intermediate deck plate. Most internals corner of each bank at the Jacking bolt end. are welded in place and are not normally con-Removal of the vane cover plate exposes the siderod removable. Check au wr*=ible parts for i Vane Cover Assembly (6), which may then be security and erosion. See Figures 1 2 and 2 1 for removed by cutting out the 1/8 inch fillet welds location ofladders and aa:ess openings. j joining the Vane Cover Assembly to the bank racks. Removal of the Vane Cover Assembly 5.2.3 Secondary Side Upper internals Reassembly (6) and the smaller Top Vane Cover (13), (m Separator Vanos) located at the top of each bank, creates a " slot" through which the vanes may be extracted from NOTE the bank. See Section "C-C " Detail "D" and s Front View Sectional of Figure 1-3. Censult Figure 13 througheet the followlas Sg 7. Grind away the weld holding the jacking bolts (1) to the Locking Plate (5), (Note: Two sets of The following steps comprise the procedure for reinstall-bolts and locking plates). Release the com-ing the second stage moisture separator vanes. Prior to pressive forces on the vanes by unscrewing the replacement of the vanes, the interior decks of the sec-bolts and removing the bolts and locking plates. + The vanes may now be removed through the ondary moisture separator housing and the vane support channels must be checked to insure cleanliness. Steps I slot opening in the bank. through 5 apply to all banks excepr Bank "E " Steps 6 to 11 apply only to Bank "E." CAUTION Step I. Complete one bank at a time. Bank "E" must be EXERCISE CARE TO CAREFULLY MARK ANO STORE completed last. Install the bolts (1), through the THE "L" $NAPEO COVER PLATES (7), ANO THE TOP locking plate (5) into the vane bank housing. (13) AND BOTTOM (4) VANE COVERS. ALSO USE Install both top and bottom sets of bolts and CARE TO Pfl0PERLY STORE JACKING 80LTS AND locking plates in each housing. Thread each bolt ' LOCKING PLATES FOR REUSE. PROTECT JACKING until its threaded end is flush with the inner wall l BOLT THREADS ANO VANE COVER PIECES. of the housing. Refer to Detail "B." h i CAREFULLY REMOVE AND MARK OR IDENTIFY 8 EACH VANE AS T0 ITS LOCATION, ORIENTATION, Step 2. Install one starting vane (2) and one jacking c. ETC. BEFORE IT 15 REMOVED THROUGH THE MAN. vane (4), per bank. Assemble standard vanes WAY HATCH. AV010 OEN0 LNG OR OTHERWISE (3) to fill intermediate space. 'there are approx-OAMAGING THE VANES OURING REMOVAL imately 151 standard vanes in each top bank and i 5-4
o 9 SECTION 5 - INSPECTION AND MAINTENANCE PROCEDURES Paragraph 5.2.4J .Swp 1. Remove all tools and parts from the steam AND THE VAPORS ARE HARMFUL TO generator secondary side. BREATHE. CONSULT THE MANUFAC- / TURER'S SAFETY RECOMMENDATIONS Step 1. Remove protective tape and old gasket if used FOR PROPER USE. to protect gasket recess. Step 6. Clean all bolts to remove rust, burrs, old lubri- ~ CAUTION cants and any foreign materials. Hand brushing with a stainless steel wire brush may be neces. DO NOT ATTEMPT TO REUSE 0LD GASKET. lT MUST ary. Examine bolt threads for nicks, burrs, and IE DISCARDED. deformed threads'. Redress threads with a flat stone or a fine file to correct the condition or, if Say J. Clean the gasket recess to remove any residue not correctable, replace the bolts. (See Section remaining from the previous gasket or protec-6.2. Item 7 for replacement bolts.) Wipe each tive tape. Use a flat brass scraper, followed by bolt with lint-free cloth soaked in petroleum dis- ~ fine grade emery cloth if necessary. The gasket tillate PDS 55812CJ (See Section 6.3, item 6) recess and cover must be clean and smooth followed by a clean, dry, lint-free cloth. Repeat prior to installation of a new gasket. procedure as required on each bolt until clean. ing cloths are free of rust and all foreign CAUTION materials. ME CARE TO M NBCK, ME M SCWCH, Sep 7. Thoroughly lubricate the threads on each bolt . ESPECIALLY IN THE RADIAL DIRECTION, THE and the under surface of each bolt head. Also GASKET RECESS. IF THE GASKET RECESS 15 lubricate the int:rnal threads in the manway pad NICKED, G0UGED, SCRATCHED OR OTHERWISE bolt holes using a bristle brush smaH enough to DAMAGED, THE OWNER IS ADVISED TO CONTACT insert in the tapped hole. Remove any excess , WESTINGHOUSE FOR FURTHER INSTRUCTIONS Iubricant from the manway pad with petroleum BEFORE ATTEMPTING TO COMPLETE THE distillate PDS-55812CJ (see Section 6.3, Jtem I MSWE. 6). Avoid applying excess lubricant on the pad ace near e gas et recem area.The prescribed Smp 4. Remove protective tape from the bolt holes I" around the manway opening. The internal threads on the bolt holes should be blown clean in the cleaned and lubricated bolt holes. t CAUTIM CAUTION THE MANWAY OPENING SHOULD BE COVERED TO THE USE OF ANY LUBRICANT OTHER THAN POS-PREVENT ENTRY OF CONTAMINANTS WHEN BOLT 55812CJ 15 PR0HIBITED (8ECAUSE OVERLOADING HOLES ARE BEING BLOWN M CLMED. OF THE THREADED FASTENERS MAY RESULT) Sep 5. Wipe each bolt hole with a clean lint-free cloth WITHOUT THE PRIOR APPROVAL OF AN AUTH0- ~ soaked in petroleum distillate pleaning solvent ERM M WEMESE REN C AM PDS-55812CJ (See Section 6.3, Item 6). Then wipe with a clean, dry lint free cloth. Repeat procedure until cleaning cloths are free of rust Step 8. Final clean the manway opening and gasket or previous lubricants and foreign materials. recess with methyl alcohol, PDS M 51100AJ (see Section 6.3, item 5), and dry with a clean, f7 WARNING lint-free cloth. To avoid entry of contaminants, o install a temporary cover of wood or PETROLEUM DISTILLATE SOLVENT polyethylene taped in place over the cleaned PDS-55812CJ IS FLAMMABLE, TOXIC TO manway opening, if the manway closure is not THE SKIN, IS HARMFUL IF INGESTED to be completed immediately. (~ 58 Is
N n) q i SECTI0li 5 - IN8PECil0N Allt ilAINTENANCE PROCEDURES Pmenph 5.2.4.2 wise rotational serence, until each bolt meets ing device. Following the sequence and instruc-the final torque value of Table 5-2. tions on Figure 3-1, first loosen in sequence all bolts (18UNC 2A) only 1/12 of a mm or Sary 7. Clean the clo'sure cover and bolt heads with approximately 30" and then repeat the sequence petroleum distillate PDS-55812CJ (See Section this time loosening all bolts an additional 1/6 ef 6.3. Item 6) and wipe dry to remove any excess e rwnor approximately 60*. Aftercompletion of lubricant and foreign material. this two-sequence cover loosening process, the bolts may be completely unthreaded and WARNING removed. PETROLEUM DISTILLATE SOLVENT NOTE PDS-55812CJ IS FLAMMABLE, TOXIC TO THE SKIN,15 POISONOUS IF INGESTED One or more handhole pad threaded holes may l AND THE VAPORS ARE HARMFUL TO contain a wire thread insert for proper engage-l BREATHE CONSULT THE MANUFAC-ment between the bolt and the tapped hole. TURER'S SAFETY RECOMMENDATIONS Refer to the As. Built Drawing, Figure 510A l FOR PROPER USE. through 5-10D for specified use, if any, of such inserts. It is unlikelf a wire thread insert will dis-Sary S. Perform the Secondary Side Leak Test as dis-engage from the handhole pad bolt holes during cussed in Section 4.10.4. closure disassembly. However, examine each bolt and hole and notify Westinghouse for 5.3 INSPECTION AND MAINTENANCE OF SECONDARY $10E further instructions should any wire thread LOWER INTERNALS inserts become unscrewed. Access for inspection and cleaning of the secondary side lower internals and the tube bundle is available through WARNING the six (6) handholes located on the lower shell as shown in Fisare 1-1. (Also refer to Section 1.4.11.2) These THE WEIGHT OF THE HANDHOLE COV-handholes permit limited access for examining the condi. ER IS APPROXIMATELY $0 LBS 122.7 kgl. tion of the tube bundle, tubeplate secondary side face, EXERCISE CARE WHEN REMOVING THE support pistes, flow baffle and blowdown pipes. The COVER TO AVOID INJURY TO PERSON. l' handholes are also used for introducing and mounting NEL. equipment for cleaning the secondary side, such as the sludge lancing apparatus. CAUTION 5.3.1 Disassembly of Handhole Closures BEFORE REMOVAL, CAREFULLY EXAMINE THE COV. ER AND VESSEL MOUNTING PAD TO DETERMINE IF The following steps comprise the procedure required to ANY MATCH MARKS OR PLACARDS EXIST, -t remove the handhole covers and gain access to the sec. IN0lCATING THE COVER 15 CUSTOMlZED FOR THE ondary side through any of the six handhole openings. LOCATION AND MUST BE RE. INSTALLED IN THE ~' SAME LOCATION AND SAME ORIENTATION (MATCH ^ WARNING MARKS UNED.UP AT THE TIME OF REASSEMBLY OF THE CLOSURE.) REFER TO SECTION 6.4 FOR A LIST. TO AVOID POSSIBLE SERIOUS INJURY ING 0F SPECIAL OR CUSTOMlZED PARTS, IF ANY. TO PERSONNEL THE UNIT MUST BE AND THEIR LOCATION. COMPLETELY DEPRESSURIZED, y DRAINED AND VENTED BEFORE NOTE g STARTING CLOSURE DISASSEMBLY. G One or more handhole pad threaded holes may E 3ep L Install a 0.513 UNC 2B eyebolt in the threaded contain a wire thread insert for proper engage. hole located on the side of the handhole cover, ment between the bolt and the tapped hole, and attach the eyebolt to a davit or suitable lift. Refer to the As. Built Drawing, Figures 15A l l 5-8 ~ ^- M
l i !,,,. v + l D ) .s Peregraph 5.7.2 8ECil0N 5 - INSPECTION ANO MAINTENANCE PROCEDURES penetrant. (See Section 5.8 for dye penetrant in welds made during the welded tube plugging pro-h examination details.) cedure or during the manway seal weld when the welded i i diaphragm (altemate closure) method is used. (See Sec. Step 16. Remove all equipment, checking against the tion 5.10.3.) The presence of hidden surface weld defects Inventory !ist, and prepare to test the welded is made visible as red stains against the white developer. joint. WARNING Ssep 17. Pressurize the secondary side as specified in i Section 4.10.5, Tube Leak Test. SOLUTIONS USED TO INSPECT FOR SURFACE FLAWS ARE SKIN IRRITANTS, Step 18. Visually check the tubeplate for any water AND REPEATED OR PROLONGED CON-leakage through the welded tube plugs. TACT WITH THE SKIN SHOULD BE AVOIDED. WASH HANDS THOROUGH-Step 19. Should a leak be found in the tube plus weld, LY AFTER U$iNG. USE HIGHLY VOLA. + depressurize the generator, grind the weld to a TILE SOLVENTS AND CLEANING SOLU. i i maximum depth of.100 in. [2.5 mm), and TIONS CAUTIOUSLY. l repair in accordance with the weld procedure in Steps 14 and 15 above. The Dye Penetrant examination is to be done in accord. j ance with the ASME Boiler and Pressure Vessel Code, ~ Samp 10. Retest the secondary side as specified in Section Section IIL The following material is presented for infor-4.10.5. Tube Leak Test, and inspect all welded mation and use by the Owner as reference material. 4 tubes for leaks. Siep 11. If no leaks are detected, depressurize the sec. 5.8.1 Examination ondary side of the steam genetat,or. The examination must be conducted on clean surfaces. It Ssep 11. Clean all internal surfaces on the outlet side of is important that the areas being tested and these areas 1 the primary chamber with methyl alcohol PDS immediately atacent be free from any dirt, grease, scale, M.51100AJ (See Section 6.3, item 5), rinse salts, or other matter which would clog the surface open. l with domineralized water, dry with clean lint-ings, absorb the penetrant, or react with the penetrant. l free cloth, and remove protective covers from All such contamination must be removed immediately the outlet nozzle. prior to the start of the test. Following the mechanical l removal of all injurious matter, the test surfaces shall WARNING receive a final cleaning by swabbing with a clean cloth saturated with methyl alcohol PDS M-51100AJ (See Sec-METHYL ALCOHOL IS FLAMMABLE,. tion 6.3 Item 5), until assured that the surface is free l TOXIC TO THE SKIN, IS POISONOUS IF INGESTED AND THE VAPORS ARE from all contamination. Allow the surface to dry at least 5 mmutes before proceeding. HARMFUL TO BREATHE. CONSULT THE MANUFACTURER'S SAFETY RECOM-If necessary, rough surfaces, such as weld beads, should MENDATIONS FOR PROPER USE. be ground before using the penetrant, to prevent false indications. Siep 13. Repeat Step 22 on the inlet side of the chamber. Step 14. Reassemble the primary manway closure ir, 5.0.2 Equipment accordance with Section 5.10. 1 N No special equipment is necessary for dye penetrant l~ 5.8 DYE PENETRANT EXAMINATION inspection other than that used for the application of the ~ liquids. The dye penetrant and the developer are to be l The dye penetrant process is used to detect surface applied in sufficient quantity to thoroughly cover all parts cracks, porosity, and other indications which may appear to be inspected. !o 9 5 21 t ~~ -,.J'~' r.-..r~:~~~ ~~
.q 3 ShCTION 5 -INSPECTION AND MAINT NANCE PROCEDURES Paragnph 5.8.3 5.8.3 Application of Penetrant may be used as s guideline for determining relevant I *. indications. The indications revealed by this testing as Apply penetraat to the surface, with the temperature bet-determined by ASME Section Ill criteria should be cor-ween 60*F and 125*F [16*C and Sl*Cl, by spraying or brushing, so that the area is completely covered. Allow rected and reinspected for any relevant indications. Dye the dye to remain on the area to be tested for a minimum penetrant testing should be continued after repairs until of 15 minutes. Do not permit the penetrant to dry. Add no relevant indications are present. more penetrant during the 15-minute soaking period to prevent the dye from drying. 5.9 TUBE PLUGGING RECORD CAUTION Figures 510A through 510D, Tube Layout Charts (to be provided later) will record for each unit those tube N EXERCISE CARE THAT THE INSPECTION MATER-locations plugged during manufacture. (A sample is pro-IALS 00 NOT ENTER INACCES$1BLE PLACEI, WCH vided in the initialissue of this technical manual) AS BOLTED JOINTS, WHERE THEY CAhNOT BE RE-MOVED; AND THAT THEY DO NOT CONTACT AREAS This record must be updated to document any tubes OTHER THAN THOSE BEING TESTED. plugged after the unit is put into service. The tube layout chart may be used to pictorially indicate plugged tube } locations. 5.8.4 Removal of Excets Penetrant : 4 The dye penetrant is, water soluble, eM all excess 5.10 PRIMARY MANWAY CLOSURE REASSEM8LY l penetrant can be removed by a water wash or wet cloth. It is necessary to re'mcve all of the penetrant from the sur-There are two methods of closure for the primary man-j face, because the residual dye will decrease the senritivity ways: (1) the normal, or gasketed closure and (2) the of the test. Excessive washing is not recommended, seal-welded diaphragm type closure. Both of these however, because the dye trapped in the surface indica-tions ma'y be leached out. After removalfof the ' Before proceeding with the manway closure, remove all - penetrant, dry the surface with paper towels or dry rass. tools and parts from the steam generator. When leaving the primary chamber, wipe the inside surface clean, using 5.8.5 Developing a lint-free cloth wetted with methyl alcohol PDS M-51100AJ (See Section 6.3, item 5). Within 10 minutes after the surface is thoroughly dry, apply a thin even coating of developer. A single coating is WARNING sufficient and should be applied by spraying to' the full test area at one time. A!!ow the developer to dry for at THIS ALCOHOL IS FLAMMABLE, TOXIC least 7 minutes, but not more than 30 minutes, to permit TO THE SKIN, IS POISONOUS IF IN-absorption of the dye remaining in the surface indica-GESTED AND THE VAPORS ARE HAILM-l l tions which may be present. FUL TO BREATHE. CONSULT THE MAN-UFACTURER'S SAFETY RECOMMENDA-l 5.8.6 Indication Identification ~ TIONS FOR PROPER USE. Indications will show up as red stains against the white developer. Scattered red dots indicate porosity, while 5.10.1 Manway Closure Pre-Assembly Cleaning and l l solid red lines result from cracks or cold shuts. A line of Lubrication 7 dots may represent a very tight crack, cold shut, or par-tially welded lap. Before reassembly of the primary side manway closure g can begin, the threaded holes on the manway pad, bolts, g 5.8.7 Final Examination gasket recess on the manway pad and the insert disc must g i be cleaned using the procedure described below. After Upon conclusion of the dye penetrant inspection, all rele-cleaning, the bolts and threaded holes on the manway vant indications should 6s recorded. ASME Section Ill pad are to be lubricated per instructions given below. O m l $=E l r = = . = :- ~:-
- - = ~ ]. O E / Paragraph 5.10.1 SECTION 5 - INSPECTION AND MAINTENANCE PROCEDURES Step 1. Remove all tools and check that the primary HARMEUL TO BREATHE. CONSULT THE O~ chamber has been properly cleaned. See Steps MANUFACTURER'S SAFETY RECOM-10 and 11 of Section 5.7.1 for proper cleaning. MENDATIONS FOR PROPER USE. Remove protective tape and old gasket if they have been used to protect the gasket recess. Step 4. Remove the protective tape from the bolt holes around the manway opening. The internal CAUTION threads on the bolt holes should be blown clean with compressed air. DO NOT ATTEMPT TO REUSE THE OLD GASKET. IT MUST BE DISCARDED. Step J. Wipe each bolt hole with a clean lint-free cloth soaked in petroleum distillate cleaning solvent l ~ Step 2. Clean the gasket recess on both the manway PDS-55812CJ (See Section 6.3, item 6). Then opening and insert disc to remove any residue wipe with a clean, dry lint-f]ee cloth. Repeat pro-remaining from the previous gasket or protec-cedure until cleaning cloths are free of rust or tive tape. Use a flat brass scraper followed by previous lubricants and foreign materials. fine grade emery cloth if necessary. The gasket 3 recess and insert disc must be clean and smooth prior to installation of a new gasket. Take care WARNING not to souge the gasket recess on either the manway opening or the insert disc. Replace the PETROLEUM DISTILLATE SOLVENT insert disc if the recess cannot be cleaned or is PDS-558I2CJ (SEE SECTION 6.3 ITEM 6) soused (See Section 6.2, Items 2 and 3). IS FLAMMABLE, TOXIC TO THE SKIN AND THE VAPORS ARE HARMFUL TO BREATHE. CONSULT THE MANUFAC. CAUTION TURER'S SAFETY RECOMMENDATIONS FOR PROPER USE. TAKE CARE TO NOT NICK, G0UGE OR SCRATCH, ESPECIALLY IN THE RADIAL DIRECTION THE MAN-l WAY OPENING GASKET RECESS. IF THE GASKET Sica 6. Clean all bolts to remove rust, burrs, old lubri-l RECESS IS NICKED, G0UGED, SCRATCHED OR cants and any foreign materials. Hand brushing l OTHERWISE DAMAGED, THE OWNER ls ADVISED TO with a stainless steel wire brush may be neces. CONTACT WESTINGHOUSE FOR FURTHER INSTRUC-sary. Examine bolt threads for nicks, burrs, and TIONS BEFORE ATTEMPTING TO COMPLETE THE deformed threads. Redress threads with a flat. CLOSURE. stone or a clean, fine file to correct condition or, if not correctable, replace the bolts. (See Section CAUTION 6.2, item 6 for replacement bolts.) Wipe each boh with lint-free cloth soaked in petroleum dis-DO NOT ALLOW SCRAFINGS AND FOREIGN tillate PDS-55812CJ (See Section 6.3, item 6) MATERIAL TO ENTER INTO THE MANWAY DURING and then dry with a clean, lint-free cloth. Repeat CLEANING. COVER OR BLOCK MANWAY OPENING. procedure as required on each bolt until clean-ing cloths are free of rust and a'l foreign Step 3. Wipe the gasket recess and insert disc with materials. methyl alcohol, PDS M-51100AJ (See Section 6.3 Item 5). Also remove all deposits on the Step 7 Thoroughly lubricate the threads on each bolt insert disc face. and the under surface of each bolt head. Also e( ~ lubricate the internal threads in the manway pad I WARNING bolt holes using a bristle brush small enough to insert in the tapped holes. Remove any excess METHYL ALCOHOL IS FLAMMABLE, lubricant from the manway pad with petroleum TOXIC TO THE SKIN, IS POISONOUS IF distillate PDS-55812CJ (See Section 6.3, Item INGESTED AND THE VAPORS ARE 6). Avoid applying excess lubricant on the pad O 5 23 -s ~ 2..., ~ + =
o-i 9 SEdTI0lt 5 - INSPECTION AND MAINTENANCE PROCEDURES Pmenph 5.10.1 face near the gasket recess area. The prescribed way pad as shown in Detail "C " Figure 11. h lubricant for both bolts and holes is PDS-After the insert disc is installed, check that the 5370lNJ (See Section 6.3, Item 1). flathead screws are tightly installed and that the top ofeach)1athead screw is recessed a minimum of CAUTION .060 in. [LS mm) below the top of the insert disc. ~ THE USE OF ANY LUBRICANT OTHER THAN PDS. Step J. Remove the plugs from the cleaned and lubri-53701NJ IS PROHIBITED (BECAUSE OVERLOADING cated manway pad bolt holes. Position the man-OF THE THREADED FASTENERS MAY RESULT) way cover, using a lifting device, and loosely WITHOUT THE PRIOR APPROVAL OF AN AUTHO-secure the cover in place, using the pre-lubri-RIZED EMPLOYE OF THE WESTINGHOUSE ELECTRIC cated bolts. CORPORATION. CAUTION Sig 8 Clean the manway opening and gasket recess with methyl alcohol PDS M-51100AJ (See Sec-EXAMINE COVER AND MANWAY PAD FOR MATCH tion 6.3, Item 5) and dry with a clean, lint-free MARKS OR PLACARDS INDICATING THE USE OF A cloth. To avoid entry of contaminants, install a CUSTOM! ZED COVER AND REQUIRING A PARTICU-temporary cover of wood or polyethylene taped LAR ORIENTATION OF THE COVER. ALIGN MATCH in place over the cleaned manway opening, if MARKS ON THE COVER AND MANWAY PADS, IF l the manway closure is not to be completed MATCH MARKS ARE PRESENT. (SEE SECTION 6.4 immediately. FOR SPECIAL COVERS, IF. ANY.) WARNING l Normally, the primary side manway covers are METHYL ALCOHOL IS FLAMMABLE, interchangeable and do not have match marks. TOXIC TO THE SKIN, IS POISONOUS IF However, it is good practice to reinstall each l INGESTED AND THE VAPORS ARE cover on the same manway opening from which HARMFUL TO BREATHE. CONSULT THE it was removed. MANUFACTURER'S SAFETY RECOM-MENDATIONS FOR PROPER USE. CAUTION 5.10.2 Primary Manway Closure Reassembly-Standard AT THE COMPLETION OF STEP 3, IF ANY NEW Closure (Gasketed) and Bolt Tightening Procedure BOLTS ARE BEING USED IN THE CLOSURE, THE SPECIAL INSTRUCTIONS IN SECTION 5.10.4 MUST l The following steps cover the reassembly and bolt BE FOLLOWED, AFTER COMPLETING ALL INSTRUC-tightening procedures to be used on the primary side TIONS IN SECTION 5.10.4, PROCEED DIRECTLY TO manway closures after cleaning and lubrication of closure STEP 6 BELOW, SKIPPING STEPS 4 AND 5. IF ONLY parts per Section 5.10.1. If any of the bolts to be installed OLD BOLTS ARE USED IN THE CLOSURE, DO NOT i are new bolts, the special installation and tightening pro-SKIP STEPS 4 AND 5 BELOW. PROCEED DIRECTLY cedure discussed in Section 5.10.4 will be required to TO STEP 4 AFTER STEP 3. break-in the new bolts. Step 4. Handtighten all bolts against the cover and then Stg L Remove the temporary cover, if installed, from proceed to tighten the bolts following the i the manway opening. Install a new fl,exitallic tightening sequence and instructions given on gasket (refer to Section 6.2, Item 1) in the Figure 51. First tighten the belts to the Inter-g cleaned gasket recess per Detail "C" of Figure mediate Torque values shown in Table 5 2. y 1 1. O CAUTION E Ste 2. Install the primary manway insert with the gasket, using the three 0.25-20 UNC-2A THE PRIMARY MANWAY BOLTS ARE SIZED SUCH flathead screws to secure the insert to the man __ THAT THEY MUST BE REPLACED AT THE LESSER O' , 5 Z4
- W-N.
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l l I n t i Pangnph 5.10.2 SECTION 5 - INSPECTION AND MAINTENANCE PROCEDURES N l Table 5 2 Bolt Torque Values for Primary Manway, Secondary Manway and Ha'ndhole Covers I i Intermediate Final Torque ? Torque Values Values i Primary Manway 400 15 ft-lbf 1600 15 ft-Ibf ( [543 20 N-ml [2770 20 N-ml l Secondary Manway 125 15 ft-lbf 500 215 ft-lbf (170 m20 N-ml [678 20 N ml i l Handhole 65 15 ft-lbf 250 15 ft-lbf [88 20 N ml [339 20 N ml i I q f INTERVAL OF: A) EACH 9000 CYCLES OF MORE Step 8. Clean the closure cover and bolt heads with THAN 10% OF FULL POWER LOAD CHANGE, OR B) petroleum distillate PDS-55812CJ (See Section I I EACH 10 YEARS NORMAL OPERATION. 6.3, item 6) and wipe dry to remove any excess lubricant and foreign material. Step 5. Again following the tightening sequence shown WARNING in Figure 5-1, tighten all bolts to the Final Tor-que Value of Table 5-2. Continue the tightening PETROLEUM DISTILLATE SOLVENT sequence until all bolts are at the final torque ppS.55812CJ IS FLAMMABLE, TOXIC TO we value. THE SKIN,IS POISONOUS IF INGESTFD AND THE VAPORS ARE HARMFUL TO l ~ ~ ~ BREATHE. CONSULT THE MANUFAC-I j NOTE TURER'S SAFETY RECOMMENDATIONS [ This multi-step tightening procedure is designed FOR PROPER USE. to prevent cocking of the cover, causing incor-rect loading of the gasket and a closure which gg,p 9. Perform the Primary Side Leak Test as dis-will leak. cussed in Section 4.10.3. Step 6. Following the sequence in Figure 5-1, with all CAUTION bolts already at the final torque value, remove one bolt, relubricate thoroughly the bolt threads AS NOTED IN SECTION 3, PRIMARY MANWAY and the undersurface of the bolt head with PDS-COVERS ON THE LOWER SHELL ASSEMBLY ARE 6 53701NJ (see Section 6.3, Item 1) and then _ SHIPPED WITH 400 FT.LB [543 N-ml BOLT TORQUE retighten the bolt to the final torque value. Con. AND MUST BE TIGHTENED TO THE FINAL TORQUE tinue for each bolt in the Figure 5-1 sequence, VALUE GIVEN IN TABLE 5 2 BEFORE PUTTING THE l until the entire bolt circle has been tightened to UNIT IN SERVICE. SECONDARY SIDE MANWAY AND e { the Final Torque Value of Table 5-2. HANDHOLE COVERS ARE SHIPPED WITH THEIR I FINAL BOLT TORQUE PER TABLE 5 2. HOWEVER, y Step 7. Check the torque value of all bolts using the AL_1. COVER BOLTS SHOULD BE !NSPECTED ON A c sequence of Figure 5-1, or alternately a clock-MANWAYS AND HAN0 HOLES TO ASSURE THAT THE wise rotational sequence, until each bolt meets CORRECT FINAL TORQUE VALUES ARE ACHIEVED, the Final Torque Value of Table 5-2. BEFORE PUTTING THE UNIT INTO SERVICE. D 5-25 l pc - _m
Q } SECTION 5 - INSPECTION AND MAINTENANCE PROCEDURES Paragraph 5.10.2 CAUDON CAUDON @l THE TORQUE VALUES LISTED IN TABLE 5 2 ARE WHEN WELDING IN A CONFINED AREA, USE A BASED ON THE USE OF THE SPECIFIC LUBRICANT FORCED AIR BLOWER TO EXHAUST WELDING P05-5370lNJ (SEE SECTION 6.3, ITEM 1). THE FUMES. USE OF ANY SUBSTITUTE IS PROHIBITED (BE- . CAUSE 0VERLOADING OF THE THREADED FASTEN. 5.10.3.3 Seal Weld Procedure for Primary Manway ERS MAY RESULT) WITHOUT THE PRIOR APPROVAL Diaphragms OF AN AUTHORIZED EMPLOYE OF THE WESTING-NOUSE ELECTRIC CORPORATION. Step 1. Inspect the diaphragm recess for imperfections j which might interfere with the rewelding of the diaphragm. The manway cladding is stainless j 5.10.3 Primary Manway Closure Reassembly-Optional steel, and the diaphragm material is Inconel (Seal Weided Diaphragm) Method (ASME-SB-168). This method requires the use of an Inconel seal-welding Step 2. The edges or surface of the parts to be joined diaphragm. See Detail "D," Figure 1-1. This diaphragm should be smoothed by machining, chipping, or is obtainable from Westinghouse. See Section 6.2, Item grinding. Rubber or resin-bonded aluminum 1 2 9. oxide or silicon carbide grinding wheels should be used. New stainless steel wire brushes may Two welding methods may be used in this proc'edure. also be used for final dressing. The welding parameters for each method are given in Sections 5.10.3.1 and 5.10.3.2. The actual welding pro-NOTE cedure is given in Section 5.10.3.3. Take care that the manway opening is blocked by a temporary cover (see Step 8, Section 5.10.3.1 Tungsten inert Gas Method Welding Parameters 5.10.1) during any grinding, smoothing and dressing operations to prevent entry of contami-Gas Tungsten Arc Welding (GTAW) wire shall be.0625 nants r f reign materialinto the manway open-l in [1.6 mm] diameter and shall meet ASME Specification '"8- 'SFA 5.14 (ER NiCr-3).The 2 percent thoriated tungsten electrode diameter may be.0625 in [1.6 mm) or.094 in. [2.5 mm] and shall meet AWS Specification 5.12. Argon Step 3. Clean the pans to be welded using lint-free cloth gas shall be 99.8 percent minimum purity. Base material and petroleum distillate cleaning solvent, PDS-(diaphragm) shall be Inconel, (ASME-SB-168). The pri-55812CJ (See Section 6.3. Item 6), followed by mary manway closure seat material is ASME-SA-240 a final cleaning with methyl alcohol, PDS M. l use direct current, straight polarity, voltage 9 to 14, $1100AJ (See Section 6.3. Item 5). Type 308L weld deposited cladding. For all weld pass.s l amperage 50 to 90, argon flow 13 to 21 cfh [.102 to.165 WARNING 1/s], cup size 4. METHYL ALCOHOL AND PETROLEUM DISTILLATE ARE FLAMMABLE, TOXIC 5.10.3.2 Shielded Metal Arc Method Welding Parameters TO THE SKIN, POISONOUS IF INGEST-ED AND THE VAPORS ARE HARMFUL l Shielded Metal Arc Welding (SM AW) material shall be TO BREATHE. CONSULT THE MANU- .125 in. [3.15 mm) or.094 in. [2.5 mml diameter wire to FACTURER'S SAFETY RECOMMENDA. -l ASME SFA 5.11 (ENiCrFe-3). Base material shall be the TIONS FOR PROPER USE. I same as for the Gas Tungsten Arc method. For all passes O use direct current, reverse polarity (electrode positive), Step 4. Insert the new diaphragm into the recess on top 3: voltage 22V to 24V, maintain a short arc, amperage 90 to of the manway insert. Check for solid seating by 130 for.125 in. [3.15 mm) wire or 50 to 80 for.094 in. lightly tapping the diaphragm with a wooden [2.5 mm) wire. mallet. I 5 Z56 +.... -. ---_e.--..w.. = =. .e. me
r s SECTION 6 - REPLACEMENT PARTS. CONSUMABLE ITEMS AND TOOLS Paragraph 6.3 d 6.3 CONSUMABLE ITEMS AND TOOLS O ltem Name Order From 1 Hi-Temperature Cmpd PDS-53701 NJ Felt Products Mfg. Co. (Order as: Fel-Pro CS-A Hi-Temp 7480 N. McCormick Blvd. Thread Compound) Skokie, IL 60076 2 _ _ Graphite Lubricant PDS 53701 AJ Huron Industries, Inc. (Order as: Neolube No. 2 Dry Conductive P.O. Box 104 i Lubricant for Nuclear Applications) Port Huron, MI.48060 l i 3 "Scotchrap" Brand Tape 2 in. wide. 3M Company l No. 51 heavy duty 20 mils 2501 Hudson Road l St. Paul, MN 55119 4 Paint, black Carboline No. 4674 Carboline Company 328 Hanley Industrial Court St. Louis, MO 63144 1 5 Methyl Alcohol PDS M-51100AJ, Rev. A U.S. Chemicals Company 99 Park Ave. New York, NY 10016 l 6 Petroleum Distillate Solvent PDS $5812CJ Westinghouse Electric Corporation Benolite Division l Manor, PA 15665 or Gulf Oil Corporation 3802 Gulf Building 'Pittsburgh, PA 15219 or Shell Oil Company 900 United Bank Building West 25th St. Cleveland. OH 44101 or Sun Oil Company l 16th and Walnut St. Philadelphia, PA 19103 P 7 Jet-line Package 3-200 Thomas Industries i P.O. Box 666 2 Matthews, NC 28105 4 l 6.4 SPARE PARTS-SPECIAL (No entries at present) h a c 5 g [ i t 0t l i 's.e J i m
Paragraph 6.1 SECTION 6 - REPLACEMENT PARTS. CONSUMABLE ITEMS AND TOOLS SECTION 6 ) REPLACEMENT PARTS, CONSUMABLE ITEMS AND TOOLS 6.1 GENERAL This section lists the recommended quantities of spare parts for four steam generators. The consumable items are listed here for reference and are specified on an "as-required" basis. Certain spare parts items may be of special or customized design to accommodate acceptable deviations and allowable tolerances or non-standard conditions arising during manufacture. Any such spare parts items are identified in Section 6.4 as to the particular unit, location on the unit, and special part drawing number for record and reordering purposes. 6.2 SPARE PARTS-STANDARD Westinghouse Recommended item Name ofPart Mfg. Westinghouse on-Hand Drawing item Nc Quantity 1 Primary Manway Gasket 390A029 1 16 2 Primary Manway Insert 651B171 1 2 3 Primary Manway Insert Set Screw 70001 DA 4BT 24 4 Secondary Manway Gasket 390A029 3 16 5 Handhole Opening Gasket 390A029 2 80 6 Primary Manway Closure Bolt 651B293 1 6 7 Secondary Manway Closure Bolt 651B293 3 6 8 Handhole Opening Closure Bolt 651B293 5 12 9 Primary Manway Diaphragm 389A200 1 1 10 Tube Plugs (Welded) 394A702 16 48 p// U 11 Tube Plegs (Explosive) 2647A18 1 48 12 Secondary Moisture Separator Parts
- a. Starting Vane 3459C20 A01 None
- b. Standard Vane 3459C21 A01 None
- c. Jacking Vane 3459C22 A01 None
- d. Vane Jacking Bolt 397A135 3
None
- e. Jacking Bolt Locking Plate 652B541 5
None f; Standard Bank Vane Cover Assembly 2506B51 A01 None
- g. "L"-Shaped Cover Plate 2502B85 1
None
- h. Bank "E" Vane Cover (top) 2502B93 A02 None
- i. Bank "E" Vane Cover (bottom) 2502B93 A03 None
- j. Standard Bank Vane Cover (top) 2503B08 1
Nonc 13 Handhole Wrapper Closure Inner Plate Assembly 3462C49 A01 1 14 Handhole Wrapper Closure Outer Plate Assembly 3462C50 A01 1 15 Handhole Wrapper Closure Special Locking Washer 3462C48 1 80 l i C, 2 V.' l 1 O l 61
_s. 3 J U PUBLIC SERVICE m ano m m m rnsin.e ins ome.: i Company of New Hampshre 1671 Worcester Road Framingham, Mossochusetts 01701 (617) - 872 - 8100 [ i15{TL 5 March 17, 1982 SB-12991 T.F. P2.4.1 No Response Required Nuclear Energy Services, Inc. Shelter Rock Road Danbury, CT 06810 Attention: Mr. James A. Munson, Project Manager
Dear Mr. Munson:
Seabrook Station Preservice Inspection Services l Transmitted herewith are the Notes of Meeting of our February 26, 1982 meeting. If they are not in accordance with your understanding, please advise. This letter shall also serve as formal notice for NES to proceed with the work to be performed under Contract No. SBY-2. Notice *was given verbally at the above meeting and shall be effective as of that date. l Very truly yours, [ R. P. Pizzuti Construction Manager RPP/CDM/jmm Transmittal ec: B. B. Beckley J. DeVincentis J. H. Herrin D. G. McLain W. B. Sturgeon, Jr. G. S. Thomas bec: J. J. Lance R. McCormack N #qp4D P. Oikle narron
1 NOTES OF MEETING l Yankee Atomic Electric Company, Framingham Office PLACE: DATE: Friday, February 26, 1982
SUBJECT:
Preservice Inspection Services ATTENDANCE: P. Nason - PSNH - Manchester G. Papami - NSD - Start-Up NSD - Start-Up C. Molis NSD - Framingham J. Lance NSD - Framingham R. Romer NSD - Framingham C. Melin S. Sodosky - NSD - Seabrook Nuclear Energy Services (NES) J. Munson L. Sage - Nuclear Energy Services (NES) f This meeting was held to discuss the adequacy of drawings PURPOSE: transmitted to NES and to identify additional information required by NES to prepare the PSI Program Plans, to finalize NES's Contract schedule and to resolve comments on NES's QA Manual and QAPP. i DISCUSSION: NES received from United Engineers on February 17, 1982 a drawing Although these package of inservice inspection piping isometrics. drawings are sufficient to start work on the PSI Program Plans, NES presented a list of additional drawings and data that will be This list included but is not limited to the l required soon. fo11owing: I FSAR Sections Piping Specifications Foreign Prints Weld Id. System I Weld List NSD will expedite transmittal of the listed documents through UESC to NES by March 31, 1982. NES distributed a revised project schedule reflecting changes as Start of work on the ' discussed in our meeting of January 6,1982. is indicated on March 1,1982. Based on l program plan development no pending contractual concerns and the resolution of QA concerns this meeting, it was agreed to direct NES to proceed with the NES cautioned that receipt of the requested drawings contract work. and data must be by the above March 31, 1982 to support this start. l l l
O O The contract option of RVP As-Built Verification was discussed. NSD will recommend to PSNH that the option be exercised. It would-be advantageous to complete this verification prior to May 1982, since work on the vessel expected at that time will require removal i of the existing access scaffolding. NES will confirm their man-power availability and respond to NSD. The scheduling of Steam Generator eddy current exams was discussed. These exams will follow hydro testing by Westinghouse (May 1983). NSD's comments on the NES QA manual and Project Plan (QAPP) presented in NSD letter No. SB-12838 were addressed. All items were resolved. l NES will issue to NSD one controlled copy of their QA manual including Implementing Procedures, formally respond to NSD's comments with resolution as agreed and reissue their QAPP with revisions as required. 9 Establishing regularly scheduled progress meeting with NES was briefly discussed. NES indicated their contract budget includes limited travel expenses although the importance of progress meetings is realized. It was agreed that meetings will remain on an as needed basis and that same future meetings will be held in Danbury. Notes Prepared by, C. D. Melin Construction Department 4 l s i e
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i I j-.... ....-._.-.,.. _ ~ _.. e.-- ( Page 1 REACTOR COOLANT LOOP PIPING INSTALLATION AND INSPECTION FIELD INSTRUCTION 132 1.0 SCOPE 1.1 This instruction shall provide all pertinent information, and make specific reference to additional documents where necessary, in order to achieve acceptable installation and inspection criteria for the primary reactor coolant piping. 2.0 REFERENCE 2.1 P0f NSS-140 FPf DESCRIPTION PH ISOMETRIC 54060 LPI-HL RC-1-01 ~ 54061 LPI-ECI RC-2-01 54062 LPI-EC2 RC-2-01 54063 LPI-CL RC-3-01 54064 LP2-HL RC-4-01 54065 .LP2-ECI RC-5-d1 54065 LP2-EC2 RC-5-01 54067:. LP2-CL RC-6-01 54068 LP3-HL RC-7-01 54069 LP3-ECI RC-8-01 54070 LP3-EC2 RC-8-01 54071 -LP3-CL RC-9-01 54072 1.P4-HL htC-10-01 54073 LP4-EC1 RC-11-01 54074 LP4-EC2 RC-11-01 54075 LP4-CL RC-12-01 m. s _.-.
4,.;.. l 54072 'Lp4-HL RC-10b1 { 'E D.4. 7.I"pf 54073 LP4-EC1 RC-11-01 l 54074 LP4-EC2 RC-11-01 1a 54075 LP4-CL RC-12-01 g,..a l 'QA APPROVED. e((s -j-DATE ka1} o BY-- 6-L8i y ' s...k' W9
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y< K. tr ti... - likiI ) l k D R[ llyyny h;i REF. DWGS.5EE AB0\\E,5RT.gi{ J Vil y[M NO. 7035 h ./. 19/22't.A FIELD SYSTEM Pk UE & C ISO.i-08/ I'L41 A DR AVO ISO P.P.P. "A" SH E ET Q' O7-R E V. h O.5W_E i I 0F I4 I h' DRAWN l CHK'D APPR'D 4 . LATE BY E QA DESCRIPTibN ~ SEABROOK STATION ig Pullman Power Products $'i.f' ' pal DW es _t A D B E B S BT S. L'Z,13.,i4 ' ~ ~ ~ ' " ~ ~ ' " " " ' " " L'4S: PUBLIC SERVICE Of MI 44s(w 624Bn NEW HAMPSHIRE ISOMETRIC DRAWING g,q ,.==- = =. i"399s%?r94$si%5MsMA& MAT is N i e %m y. p%p;;}bihN5NkN[d5EdNNMIM#5%%#7tTWSM# 9 4 :1 w p :1 n,yi r,,.9yQe gn%. gu%g.g&En\\ v.g.yg&w+ M;mc;;k: c.u n ..g g,m - y y, m
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FIELD INSTRUCTION 132 4.7 All operations and processes performed during the in-sta11ation of the primary reactor coolant loop piping which encompasses handling, rigging, fitting, welding inspection, etc. shall be done per Pullman Power Products Quality Assurance Program. UE&C RCE shall submit applicable Pullman welding procedures to Westinghouse for review. Westing-house shall have access to all records. 4.8 Each we'ld shall be preliminarily' fit-up in such a manner i that will facilitate the establishment of a Base Material Acceptable Discontinuities Profile through Radiographic examination. The intent is to orient end preparation with respect to each other as close to final fit-up conditions as practical, preferable without consumeables. The ID and OD of parts to be joined shall be marked forpanoramdcr base line R.T. The base line R.T. results shall be u' sed as a comparison to subsequent informational and final RTs using ID and OD marks for consistency of source and film placement. This operation will preclude the unnecessary removal of acceptable base metal discontinuities which would otherwise be undiscernable as to location with respect to the weld deposited. E.G TRAM MARK PLACING AND WELD SHRINKAGE HISTORY 5.1 Just prior to welding, but after final fit-up, shallow tram punch marks shall be applied to the components utilizing a dual low stress center punch tool. Refer to Attachment B for tool sketch. Placement of the marks shall be as follows: 5.1.1 Place punch tool parallel to the axis of the pipe and perpendicular to the weld joint. Center tram so that the resultant punch marks will be approxi-mately equidistance from the weld edge preps (centered i l across weld.) The tram tool when centered, should .i-result in punch marks approximately (1) one inch .g '? from the edges of weld preps. -l-w... 5.l.2 For all 5G-position welds, (pipe axis horizontal) weld i shrinkage measurement tram punchtmarks shall be placed at 12:00 top center, 3:00, 6:00 and 9:00. From 12:00 l to 3:00 shall be established by facing toward the nearest vessel the pfpe is being. connected to and rotating clockwise 90 from 12:00 to 3:00. 5.1.3 For all other welding positions, weld shrinkage measurementtrampunchmarkssgallbeplaceddue North, South, East and West 90 apart. 5.1.4 Punch marks, once applied, shall be precisely meas.ured from center to center across the weld joint after the joint is final fit-up and prior to welding and recorded on " weld shrinkage history record" Attachment C. Measurements shall be repeated and recorded as follows: 5.1.4.1 hfter re'moval of blocks (when used per'6.0-)- 'and comoletion of hot passi L DATLIN3&NW EM bkl.1...
l 7 I e p.,gg, M L 0-~ER D FREPARAl lON t' INSTRUCTION tr % 10* t 2 -30, FW NO. F010\\ [ IS O NO'. RC-lO -Ol 'li t 'M NPS 29" ISI , y', / g ,/ 20**2X W 51 r NOM THK 2.W__ M1N TH K j {19 MIN (tn.) (tm) ' /a .j %.01t.015 C DIM 29 20 - / Tatar, YIN i J2nc'7 (AS A PPLICABL.E) o 6 d PREP BY~ _DATE th-GREATER TRM i INSEKr/ BR O A PPR BY -bhTE COUNTERBORE AND MINIMUM WALL VERIFICATION MIN WALL C-B ORE MIN WALL A H A- . A-E H 8 B' B-F B B .l/ C-G C ( ( G __ 9 G 9 D-H u E E_ . i, .)F P 'F F D G D G E E H g SIDE OF WELD SID E OF W E LD NT USED: ' INSTRUMENT USED' {NSTRUMENT USED' INSTRUMENT USEC w n __SE R* TYPE SER TYPE SER TYPE-SER C,TICI.N VERIFICATION msmw care QC.lNSPECTION VERIFEADON mstrcTOR o3ri ontGTam'Totthnc.c l.COVNTERBORE WITHIN tot.CRAuCE t - .1. z
l-l Use of Automatic Welding Machines Dimetrics FI-126 Based on the schedule of FWS# submitted to engineering from scheduling, select location & have UE&C install electrical outlet for Dimetric-Gold track II(480 volts.) 3 phase,60HZ) Move power pack into location and connect argon into power pack. I Have scaffolding or staging installed if required, and move equirment into place. Equipment: A. TIG (one-hander) torch with accessories. B. Weld head C. Programmer (note: remote programmer must be visible to operator) D. Track with legs E. Electrical cables A. When I.O. is inaccessible, check high-low using 1/8" thick spacer,to allow use of high-low gauge,take into consideration that the insert will be 1/16" thick. After proper fit up has been obtained, QA Inspector will verify marked up pipe as shown. SCR15E WITH TUN 65Te.N sc2iSEF. SELECT DN* 2 sEtccnow mi i 0 _f" O 7-p ( ) yn +y E ' 8" '6" SELECT 1ous4 GELECTio M *3 me,. 2. pg,, 1. Using the most visible location of the selections given in (fig.2) have fitter scribe measurements a,b,c,d at two locations, j 2. After insert or backing ring has been tacked into place, have QA Inspector check alignment using scribed marks. l B. When I.D. is accessible, verify high-low by physical measurement from the I.D. l Track installation shall begin after space requirements (fig.3) and the process sheet have been checked to see if stripheaters and thermocouples are required. l A. The surface of the pipe where the track feet meet the pipe must be free of paint, l rust,millscale,or other coatings that may impair electrical connection between the pipe and track. B. Separate the split annular track ring by unscrewing the two captive locking screws. l Retract the three mounting feet by unscrewing the locking screws of each foot located on the track surface. l .C. Set one-half of the track on top of the pipe to be welded. Line up bottom half of the track with the top half, screw the two pieces together.
The distance that g tungsten elcctrode ext'end'fFo[tlin gas cup Tif5h6uld be" B. approximately inc .o 3/4 inch. The tungsten sho',) be tight in the torch and no. wobble or loosenes,s present. j Vill. Using ll$e (fig.8) e'stdblish the frbul shd UI Weld hWd slUp Up. Align tungsten to center of insert and trial run. Adjust track to center of insert. IX. The welding supervisor will review welding parameters with the welding operator of each machine. X. The remote programmer will be set up. Theweldwillbestenciledbythewelding operator or operators as described in Pullman-Higgins Procedure (X-9). ~ ~ The welding operator is defined as the person or persons that have been qualified, --- who watch and interpret weld puddle. XL Using a weld r0d requisit10n (fig,6) obtain wire spo01s from site r94 rooms, Check to see that the spool of wire is scribed with the size, type, and heat of material. ReturntorodroomasspecifiedinP-HJS-VIII-3(latestRev.) XII Before weld out is begun, adjust front end head alignment of machine. (Ref.VIoftheFI) Orig. Code W@ sEABROOK STATION 41.R.11005 PULLMAN POWER PRODUCTS Rec. Type WELD R0D STORES REQUISITION Lu.s. index RECORD COPY JOB 7035 Gys. Uno No. 180. / Dwg. No. Wnl:1 No. Date l CO /frI oua F0101 5-7-Fl Weld Procedure Weld Type: Hanger O I 50 M-l-6M Butt Vsocuei o Otner et I 6" &y~ %' E-70 s-3 insert or Backing Ring Heaj,No. I MO,\\D insert or sacking Ring a n% M x ROo TYPE q $',j'2 ^ b"2 3/16 N at g y h kfEl /8 eturned E-70s-3 oss 2.x AM % i.P f i aM'A%V / E-7o s.3.ouspX A WO / Vu B. / 4 j 4-Welder ymnos issued By Time Pr Foreman, 0.A. Approval Heat No. Verified O.A. i Fig.6 P. P. P. Q. A. APPROVID BY j DATE 6.N. 1 .... J O% ~ .m w.~
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m n. support or l sKt. f m 5-VE. Weld head set-up should be done carefully. Do not pick up head by torch cable or manpnWerOphle, A. Loosen cam follower tension screws on weld haad and swing cam follower arms out away from head carriage channel. After making sure arc voltage contral mechanism is at the top of its' travel range, pick up weld head by the front & rear. B. Mount head on track by pointing torch towards weld joint and setting carriage channel onto track. Swing cam follower arms under track lips and screw down cam follower tension screws hand tight. Jog head forward and reverse several times and check tightness of cam follower tension screws,again adjust hand tight. C" To7cFifiiiuld be' positioned over weld joint and be precision aligned by the os- ~~ cillator vernier slide located on top of weld head. Make sure oscillator vernier slide is located in center of travel. D. In the SG positionthe tungsten should be positioned at right angles to the radial tangent of the pipe. VII. The tungsten electrode is used to transfer the welding current from the weld head to the work surface, A. The shape of the tungsten electrode tip is a very important factor in automated welding. ref. (fig.4) i N loEAt. S table ^'* ander~'\\ 'W ___.3 3-4G ~ !D.,4 6 m F1at ----- p.:' d (Thediameter l - -.G a t
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5 Point m Governs arnperage Appa q e r - whg - "iwan 0 .;T e,. & " g*f O i (Radial ht DAD Sill.Tl h*# 1 Grooves m gg FIG. 4 PAGE 2 0F 4 ,. - ~ 7vf 4 REF.DWGS. OTHER UE & C PLAN g i i i UE & C ISO ELD _ Mf! E
q ) SB 1 & 2 FSAR 5.2 INTECRITY OF REACTOR COOLANT PRESSURE BOUNDARY This section discusses the measures employed to provide and maintain the integrity of the reactor coolant pressure boundary (RCPB) for the plant's design lifetime. The RCPB is as defined in Section 50.2 of 10 CFR 50. In that definition, the RCPB extends to the outermost containment isolation valve in the system piping which penetrates the containment and is connected to the reactor coolant system (RCS). Since other sections describe the com-ponents of these auxiliary fluid systems, this section will be limited to the components of the RCS as defined in Section 5.1, unless otherwise noted. The reactor coolant pressure boundary is designed to accommodate the system pressures and temperatures attained under all expected niodes of* plint operation, including all anticipated transients, and to maintain the stresses within applicable stress limits. The system is protected from overpressure by means of pressure-relieving devices, as required by applicable codes. Materials of construction are specified to minimize corrosion and erosion and to provide a structural system boundary throughout the life of the plant. Fracture prevention measures are taken,to prevent brittle fracture. Inspec-tion is in accordance with applicable codes, and provisions are made for surveillance of critical areas to enable periodic assessment of the boundary integrity, as described in Section 5.2.4. For additional information on the RCS, and for components which are part of the RCPB but are not described in this section, refer to the following sec-tions: Section 6.3 - for the RCPB components which are part of the emergency a. core cooling system. b. Section 9.3.4 - for the RCPB components which are part of the chemical and volume control system. Section 3.9(N).1 - for the design loadings, stress limits, and c. analyses applied to the RCS and ASME Code Class I components, d. Section 3.9(N).3 - for the design loadings, stress limits and analyses applied to ASME Code Class 2 and 3 components. 5.2.1 Compliance With Codes and code cases 5.2.1.1 Compliance With 10 CFR Section 50.55a RCS components are designed and fabricated in accordance with 10 CFR 50, Section 50.55a, " Codes and Standards". The addenda of the ASME Code applied in the design of each component is listed in Table 5.2-1. 1 i .A,
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j ] ~] I ~ SB 1 & 2 FSAR O The above procedpres, which will be followed for normal operations with a steam bubble, transitional operations where the reactor coolant system is potentially water-solid, and during specific testing operations, will provide in-depth cold overpressure prevention or reduction, thereby augmenting the installed overpressure relief system. i 5.2.3 Reactor Coolant Pressure Boundary Materials i 5.2.3.1 Material Specifications Material specifications used for the principal pressure retaining applications I in each component of the RCPB are listed in Table 5.2-2 for ASME Class 1 primary components and Table 5.2-3 for ASME Class 1 and 2 auxiliary components. i Tables 5.2-2 and 5.2-3 also include the unstabilized austenitic stainless l steel material specifications used for components in systems required for reactor shutdown and for emergency core cooling. The unstat'lized austenitic stainless steel materials for the reactor vessel internals, Qich are required.for emergency core cooling for any mode of normal operation or under postulated accident conditions and for core struc-I tural load bearing members, are listed in Table 5.2-4.. In some cases, the tables may not be totally inclusive of the material speci-fications used in the lis'ted applications. However, the listed specifications are representative of those materials utilized. The materials utilized conform with the requirements of the ASME Code, I Section III, plus applicable addenda and Code cases. ~ The welding materials used for joining the ferritic base materials of the RCPB conform to, or are equivalent to, ASME Material Specifications SFA 5.1, 5.2, 5.5, 5.17, 5.18 and 5.20. They are qualified to the requirements of the ASME Code, Section III. The welding materials used for joining austenitic stainless steel base materials of the RCPB conform to ASME Material Specifications SFA 5.4 and 5.9. They are qualified to the requirements of the ASME Code, Section III. The welding materials used for joining nickel-chromium-iron alloy in similar base material combination and in dissimilar ferritic or austenitic base material combination conform to ASME Material Specifications SFA 5.11 and 5.14. They are qualified to the requirements of the ASME Code, Section III. 5.2.3.2 Compatibility With Reactor Coolant a. Chemistry of Reactor Coolant The reactor coolant system (RCS) chemistry specifications are given in Table 5.2-5. 5.2-9
i O ] SB 1 & 2 FSAR O The RCS vater chemistry is selected to minimize corrosion. A routinely scheduled analysis of the coolant chemical composition is performed to verify' that the reactor coolant chemistry meets the specifications. The chemical and volume control system provides a means for adding chemicals to the RCS which control the pH of the coolant during pre-startup and subsequent operation, scavenge oxygen from the I coolant during heatup, and-control radiolysis reactions involving hydrogen, oxygen and nitrogen during all power operations subsequent to startup. The limits specified for chemical additives and reactor coolant impurities for power operation are shown in Table 5.2-5. f The pH control chemical employed ~is lithium hydroxide monohydrate, enriched in 7Li isotope to 99.97.. This chemical is chosen for its compatibility with the materials and water chemistry of borated water / stainless steel / zirconium /Inconel systems. In addition, 7 i L is produced in solution from the neutron irradiation of the dissolved boron in the coolant. The lithium-7 hydroxide is introduced into the RCS via the charging flow. The solution is prepared in the ( laboratory and transferred to the chemical additive tank. Reactor makeup water is then used to flush the solution to the suction header of the charging' pumps. The concentration of lithium-7 hydroxide in the RCS is maintained in the range specified for pH control. If the concentration exceeds this range, the cation bed demineralizer is employed in the letdown line in series operation with the mixed bed demineralizer. During reactor startup from the cold condition, hydrazine is.added to the coolant as an oxygen scavenging agent. The hydrazine addi-tion is stopped at 1800F because of the rapid decomposition at this temperature. While hydrazine is being added, all the demin-eralizers are valved out of service to prevent their rapid depletion by ammonia (NH ) which could lead to a flow of impurities into the 3 coolant system. The reactor coolant is treated with dissolved hydrogen to control the products formed by the decomposition of water by radiolysis. The hydrogen reacts with the oxygen to form water and prevent the oxygen from reacting with the nitrogen and forming nitric acid (HNO ). The hydrogen overpressure is accomplishedrby a 3 l self-contained pressure control valve in the vapor space of the volume control tank. This valve can be adjusted to maintain the correct equilibrium hydrogen concentration. l Boron, in the chemical form of boric acid, is added to the RCS to accomplish long term reactivity control of the core. The mechanism for the process involves the absorption of neutrons by the 10B l isotope of naturally occurring boron. O 5.2-10 --,v
l een ~- ~ e.- a. SB 1 & 2 FSAR i Suspended solids (corrosion product particulates) and other impurity concentrations are maintained below specified limits by controlling l the chemical quality of makeup water and chemical additives and by purification of the reactor coolant through the CVCS mixed bed demineralizer. i b. Compatibility of Construction Materials With Reactor Coolant All of the ferritic low alloy and carbon steels which are used in principal pressure-retaining applications are provided with corro-sion resistant cladding on all surfaces that are exposed to the reactor coolant. The corrosion resistance of this cladding material is at least equivalent to the corrosion resistance of Types 304 and 316 austenitic stainless steel alloys or nicke1 chromium-iron, martensitic stainless steel and precipitation-hardened stainless steel. The cladding on ferritic type base materials receives a post-weld heat treatment, as required by the ASNE Code. 1 Ferritic low alloy and carbon steel nozzles are safe-ended with either stainless steel wrought materials, stainless steel weld metal analysis A-7 (designated A-8 in the 1974 Edition of the ASME Code), or nickel-chromium-iron alloy weld metal F-Number 43. The latter buttering material requires further safe-ending, with austen-itic stainless steel base material after completion of the post-weld O heat treatment, when the nozzle is larger than a 4 inch. nominal inside diameter and/or the wall thickness is greater than 0.531 inches. All of the austenitic stainless steel and nickel-chromium-iron alloy base materials with' primary pressure-retaining applications are used in the, solution-anneal heat treat condition. These heat treatments are as required by the material specifications. During subsequent fabrication, these materials are not heated above 8000F, other than locally by welding operations. The solution-annealed surge line material is subsequently formed by hot bending, followed by a re-solution annealing heat treatment. Components with stainless steel, sensitized in the manner expected during component fabrication and installation, will operate satis-factorily under normal plant chemistry conditions in pressurized water reactor systems because chlorides, fluorides and oxygen are controlled to very low levels. c. Compatibility With External Insulation and Environmental Atmosphere i In general, all of the mat.erials listed in Tables 5.2-2 and 5.2-3 which are used in principal pressure-retaining applications and which are subject to elevated temperature during system operation 5.2-11 1
,g ] SB 1 & 2 FSAR l O j are in contact with thermal insulation that covers their outer l surfaces. The thermal insulation used on the RCPB is either reflective stain-less steel type or made of compounded materials which yield low leachable chloride and/or fluoride concentrations. The compounded materials in the form of blocks, boards, cloths, tapes, adhesives, l cements, etc., are silicated to provide protection of austenitic I stainless steels against stress corrosion which may result from accidental wetting of the insulation by spillage, minor leakage or other co'ntamination from the environmental atmosphere. Section 1.8 includes a discussion which indicates the degree of conformance .[ with Regulatory Guide 1.36, " Nonmetallic Thermal Insulation for Austenitic Stainless Steel". In the event of coolant leakage, the ferritic materials will show increased general corrosion rates. Where minor leakage is anticipated from service experience, such as valve packing, pump seals, etc., only materials which are compatible with the coolant are used. These are as shown in Tables 5.2-2 and 5.2-3. Ferritic materials exposed to coolant leakage can be readily observed as part of the in-service visual and/or nondestructive inspection program to assure the integrity of the component for subsequent service. S.2.3.3 Fabrication and Processing of Ferritic Materials a. Fracture Toughness The fracture toughness properties of the primary components meet the requirements of the ASME Code, Section III, paragraph NB-2300. l The fracture toughness
- properties of the reactor vessel materials I
are discussed in Section 5.3. \\ l l Limiting steam generator and pressurizer RTNDT temperatures are guaranteed at 600F for the base materials and the weldments. These j materials will meet the 60 ft-lbs absorbed energy and 35 mils lateral expansion requirements of the ASME Code Section III at 1200F. The i actual results of these tests are provided in the ASME material data reports which are supplied for each component and submitted co Public Service Co. of New Hampshire at the time of shipment of l the component. Calibration of temperature and charpy impact test machines are performed to meet the requirements of the ASME Code, Section III, paragraph NB-2360. Westinghouse has conducted a test program to determine the fracture toughness of low alloy ferritic materials with specified minimum yield strengths greater than 50,000 pounds per square inch (psi), 5.2-12
9' 9 SB 1 & 2 FSAR to demonstrate compliance with Appendix G of the ASME Code, Section III. In this program, fracture toughness properties were determined.and shown to be adequate for base metal plates and forgings, weld metal and heat-affected zone metal for higher strength ferritic materials used for components of the RCPB. The results of the program are documented in Reference 4. l b. Control of Welding All welding is conducted utilizing procedures qualified according to the rules of Sections III and IX of the ASME Code. Control of welding variables, as well as examination and testing during procedure qualification and production welding, is performed in accordance with ASME Code requirements. Section 1.8 includes discussions which indicate the degree of con-formance of the ferritic materials components of the RCPB with l Regulatory Guides 1.34, " Control of Electroslag Properties"; 1.43, " Control of Stainless Steel Weld Cladding of Low Alloy Steel Compo-i nents"; 1.50, " Control of Preheat Temperature for Welding of Low-Alloy Steel"; and 1.71, " Welder Qualification for Areas of Limited. Accessibility". 5.2.3.4 Fabrication and Processing of Austenitic Stainless Steel D ~ l Subsections 5.2.3.4.a to 5.2.3.4.e address Regulatory Guide 1.44, " Control of the Use of Sensitized Stainless Steel", and present the methods and controls utilized by Westinghouse to avoid sensitization and to prevent intergranular 7 l ; attack of austenitic stainless steel components. The subject of austenitic stainless steel for use in ESF applications, is addressed by UE&C in Subsection 6.1(B).1, Metallic Materials. Also, Section 1.8 includes a discussion which indicates the degree of conformance with Regulatory Guide 1.44. a. Cleaning and Contamination Protection Procedures It is required that all austenitic stainless steel materials used in fabrication, installation, and testing of nuclear steam supply components and systems be handled, protected, stored, and cleaned according to recognized and accepted methods which are designed to minimize contamination which could lead to stre'ss corrosion cracking. The rules covering these controls are stipulated in Westinghouse process specifications. As applicable, these process specifications supplement the equipment specifications and purchase order requirements for austenitic stainless steel com'onents or systems which Westinghouse p procures for the Seabrook NSSS, regardless of the ASME Code class-ification. 'Ihey are also given to United Engineers & Constructors and to Public Service Co. of New Hampshire for their information. O 5 5.2-13 ,-+-.---v ~~.. -[
O O SB 1 & 2 FSAR l r i The process specifications which define these requirements and which follow the guidance of ANSI N-45 committee specifications are as follows: 82560HM Requirements for Pressure Sensitive Tapes for Use on Austenitic Stainless Steel. 83336KA Requirements for Thermal Insulation Used on Austenitic Stainless Steel Piping and Equipment, t 83860LA Requirements for Mirking of Reactor Plant Components and Piping. 84350HA Site Receiving Inspection an'd Storage Requirements for Systems, Material and Equipment. 84351NL Determination of Surface Chloride and Fluoride on Austenitic Stainless Steel Materials. 85310QA Packaging and Preparing Nuclear Components for Shipment and Storage. 292722 Cleaning and Packaging Requirements of Equipment for Use in the NSSS. g 597756 Pressurized Water Reactor Auxiliary Tanks Cleaning Procedures. 597760 Cleanliness Requirements During Storage Construction, Erection and Start-Up Activities of Nuclear ' Power System. Section 1.8 includes a discussion which indicates the degree of conformance of the austenitic stainless steel components of the RCPB with Regulatory Cdide 1.37, " Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants". l b. Solution Heat Treatment Requirements The austenitic stainless steels listed in Tables 5.2-2, 5.2-3 and I 5.2-4 are utilized in the final heat treated condition required by I the respective ASME Code Section II materials specification. Material Inspection Program c. The Westinghouse practice is that austenitic stainless steel materials of product forms with simple shapes need not be corrosion tested provided that the solution heat treatment is followed by water quenching. Simple shapes are defined as all plates, sheets, bars, pipe and tubes, as well as forgings, fittings, and other shaped 5.2-14
331&2 FSAR 0 products.which do not have inaccessible cavities or chambers that would preclude rapid cooling when water quenched. When testing is required, the tests are performed in accordance with ASTM A 262, Practice A or E, as amended by Westinghouse Process Specification 84201 MW. d. Prevention of Intergranular Attack of Unstabilized Austenitic Stainless Stasis Unstabilised austenitic stainless s.teels are subject to intergranular I attack (ICA), provided that three conditions are present simultaneously. l Thesecates 1. An? aggressive environment, e.g., an acidic aqueous medium containing chlorides or oxygen. 2. A sensitized steel. I 3. A'high temperature. I If any one of the three conditions described above is not present, i, intergranular attack will not occur. Since high temperatures cannot 1 be avoided in all components in the NSSS, Westinghouse relies on ( the elimination of conditions 1 and 2 to prevent intergranular O, attack on wrought stainless steel components. The water chemistry in the RCS of a Westinghouse pressurized water reactor is rigorously controlled to prevent the intrusion of aggressive species. In particular, the maximum permissible oxygen and chloride concentrations are 0.005 ppe and 0.15 ppe, respectively. Reference 5 describes' the precautions taken to prevent the intrusion of chlorides into the system during fabrication, shipping, and storage. The use of hydrogen over pressure precludes the presence of oxygen ~ during operation. The effectiveness of these controls has been i demonstrated by both laboratory tests and operating experience. i/s The long time exposure of severly sensitited stainless steel in early plants to PWR coolant environments has not resulted in any sign of intergranular attack. Reference 5 describes the laboratory experimental findings and the Westinghouse operating experience. The additional years of operations since the issuing of Reference 5 have provided furthee confirmation of the earlier conclusions. Severly sensitized stainless steels do not undergo any intergranular attack in Westinghouse pressurized water reactor coolant environments. In spite of the fact there never has been any evidence that PWR coolant water attacks sensitized stainless steels, Westinghouse f considers it good metallurgical practice to avoid the use of sensi-tized stainless steels in the NSSS components. Accordingly, measures are taken to prohibit the purchase of sensitized stainless steels and to prevent sensitization during component fabrication. Wrought r. 5.2-15 O h adhi 7
~ SB 1 & 2 FSAR austenitic stainless steel stock used for' components that are part of 1) the RCPB, 2) systems required for reactor shutdown, 3) systems required for emergency core cooling, and 4) reactor vessel internals (relied upon to permit adequate core cooling for normal operation i or under postulated accident conditions) is utilized in one of the i following conditions: 1. Solution-annealed and watet quenched, or 2. Solution-annealed and cooled through the sensitization temper-ature range within less than approximately five minutes. It is generally accepted that these practices will prevent sensiti-zation. Westinghouse has verified this by performing corrosion tests on as-received wrought material. Westinghouse recognizes that tBe heat-affected zones of welded components must, of necessity, be heated into the sensitization temperature range, 800 to 15000F. However, severe sensitization, i.e., continuous grain boundary precipitates of chromium carbide, with adjacent chromium depletion, can still be avoided by control of welding parameters and welding processes. The heat inputa and associated cooling rate through the carbide precipitation range are of primary importance. Westinghouse has demonstrated this by corrosion testing a number of weldments.' Of 25 production and. qualification weldments tested, representing all major welding processes and a variety of components, and incorporating base metal thicknesses from 0.10 to 4.0 inches, only portions of two were severly sensitized. Of these, one involved a heat input of 120,000. joules, and the other involved a heavy socket veld in relatively thin-walled mate cial. In both cases,' sensitization was caused.by high heat inputs relative to the section thickness. However, in only the socket weld did the sensitized condition exist at the surface, where the material is exposed to the environment; a material change has been made to eliminate this condition. a Heat input is calculated according to the formula: H = (E)(I)(60) S Where: H = joules /L E = volts I = amperes S = travel speed (in/ min) 5.2-16 l
_ - =. --__= - Q ~. SB 1 & 2 FSAR Westinghouse controls the heat input in all austenitic pressure boundary weldsents by: 1. Prohibiting the use of block welding. i 2. Limiting the maximum interpass temperature to 3500F. 3. Exercising approval rights on all welding procedures. i To further assure that these controls are effective in preventing i sensitization, Westinghouse will, if necessary, conduct additional intergranular corrosion tests of qualification mock-ups of primary pressure boundary and core internal component welds, including the following: 1. Reactor Vessel Safe Ends 2. Pressure Safe Ends 1 3. Surge Line and Reactor Coolant Pump Nozzles 4 I [ 4. Control Rod Drive Mechanisms Head Adaptors 5. Control Rod Drive Mechanisms Seal Welds 6. Control Rod Extensions 7. Lower Instrumentation Penetration Tubes 4 To summarize, Westinghouse has a four point program designed to prevent intergranular attack of austenitic stainless steel components. 1. Control of primary water chemistry to ensure a benign environment. 2. Utilization of materials in the final heat-treated condition, and the prohibition of subsequent heat treatments in the 800 to 15000F temperature range. 3. Control of welding processes and procedures'to avoid heat-affected zone (HAZ) sensitization. 4. Confirmation that the welding procedure used for the manufacture l of components in the primary pressure boundary and of reactor l internals do not. result in the sensitization of heat-affected zones. Both operating experience and laboratory experiments in primary water have conclusively demonstrated that this program is 100 percent effective in preventing intergranular attack in Westinghouse NSSS's } utilizing unstabilized austenitic stainless steel. l 5.2-17 . ~ -
g ~ SB 1 & 2 FSAR O e. Retesting Unstabilized Austenitic Stainless Steels Exposed to Sensitization Temperatures It is not normal Westinghouse practice to expose unstabilized austenitic stainless steels to the sensitization range of 800 to 15000F during fabrication into components. If, during the course of fabrication, the steel is inadventently exposed to the sensiti-zation temperature range, 800 to 15000F, the material may be tested in accordance with ASTM A262, Practice A or E, as amended by Westinghouse Process Specification 84201 MW, to verify that it is not susceptible to intergranular attack, except that testing is not required for: 1. Cast metal or weld metal with a ferrite content of five percent or more, i 2. Material with carbon content of 0.03 percent or less that is subjected to temperatures in the range of 800 to 15000F for less than one hour, 3. Material exposed to special processing, provided the processing - is properly controlled to develop a uniform product and provided that adequate documentation exists of service exp'erience and/or test data, to demonstrate that the processing will not result in increased susceptibility to intergranular stress corrosion. If it is not verified that such material is not susceptible to intergranular attack, the material will be re-solution annealed and water quenched or rejected. l f. Control of Welding The following paragraphs address Regulatory Guide 1.31, " Control of Stainless Steel Welding", and present the methods used, and the verification of these methods, for austenitic stainless steel welding. The welding of austenitic stainless steel is controlled to mitigate the occurrence of microfissuring or hot cracking in the weld. Although published. data and experience have not confirmed that fissuring is detrimental to the quality of the weld, it is recognized that such fissuring is undesirable in a general sense. Also, it has been well documented in the technical literature that the presence of delta ferrite is one of the mechanisms for reducing the susceptibility of stainless steel welds to hot cracking. However, there is insuffi-cient data to specify a minimum delta ferrite level below which the material will be prone to hot cracking. It is assumed that such a minimum lies somewhere between 0 and 3 percent delta ferrite. The scope of these controls discussed herein encompasses welding processes used to join stainless steel parts in components designed, 5.2-18 i
~ ~ l_ ~ ~ ~ ~ n 9 a SB 1 & 2 FSAR
- O fabricated or stamped in accordance with ASME Code, Section III, Class 1 and 2, and*cor's support components. Delta ferrite control is appropriate'for the above welding requirements, except where no filler metal is used or for other reasons such control is not j
applicable. These exceptions include electron beam welding, auto-genous gas-shielded tungsten are welding, explosive welding, and welding using fully austenitic welding materials. The fabrication and installation specifications require welding procedure and welder qualification in accordance with the ASME Code, Section III, and include the delta ferrite determinations 3 for the austenitic stainless steel welding materials that are used for welding qualification testing and for production processing. Specifically, the undiluted weld deposits of the " starting" welding t materials are required to contain a minimum of 5 percent delta i ferriteb, as determined by chemical analysis and calculation using i the appropriate weld metal constitution diagrams. When new welding procedure qualification tests are evaluated for these applications, including repair welding of raw materials, they are performed in 1 accordance with the requirements of Section III and Section II of the ASME Code. The results of 511,the destructive and non-destructive tasts are 3 reported in the procedure qualification record, in addition to the information required by ASME Code, Section III. The " starting" welding materials used for fabrication and install-ation welds of austenitic stainless steel materials and components t meet the requirements of ASME Code, Section III. The austenitic stainless steel welding material conforms to ASME weld metal analysis A-7, (designated A-8 in the 1974 Edition of the ASME Code), Type 308 or 308L for all applications. Bare weld filler metal, including consumable inserts, used in inert gas welding processes conform to ASME SFA-5.9, and are procured to contain not less than 5 percent delta ferrite according to ASME Code, Section III. Weld filler metal materials used in flux shielded welding processes conform to ASME SFA-5.4 or SFA-5.9, and are procured in a wire-flux combination to be capable of providing not less than 5 percent delta ferrite in the deposit according to the ASME Code, Section III. Welding materials are tested using the welding energy inputs to be employed in production welding. Combinations of approved heat and lots of " starting" welding materials are used for all welding processes. The welding quality assurance program includes identification ard control of welding l l b The equivalent ferrite number may be substituted for percent delta ferrite. I 5.2-19 l
t ~~ .] SB 1 & 2 FSAR O material by lots and heats, as appropriate. /311 of the weld proces-sing is monitored according to approved inspection programs which include review of " starting" materials, qualification records, and ~ welding parameters. Welding systems are also subject to quality assurance audit including calibration of gages and instruments, identification of " starting" and completed materials, welder and procedure qualifications, availability and use of approved welding and heat treating procedures, and documentary evidence of compliance with materials, welding parameters and inspection requirements. Fabrication and installation welds are inspected using non-destructive examination methods according to the ASME Code, Section III, rules. To assure the reliability of these controls, Westinghouse has com-pleted a delta ferrite verification program, described i which has been approved as a valid approach to verify the Westing-house hypothesis and is considered an acceptable--alternative for ~,.. e - -- e_ T2e Regulatory Staff's acceptance letter and topical report evalu- " ~ were -r *~ ~ -M
- " " ~M[bh The program results, which do support the hypothesis presented in Reference 6, are sum-marized in Reference 7.
1 Section 1.8 includes discussions which indicate the degree of con-l formance of the austenitic stainless steel components of the RCPB with Regulatory Guides 1.34, " Control of Electroslag Properties", and 1.71, " Welder Qualification for Areas of Limited Accessibility". 5.2.4 Inservice Inspection and Testing of Reactor Coolant Pressure j Boundary All components of the reactor coolant pressure boundary are designed, fabri-l cated and erected in such a way as to comply fully with the requirements of Section XI of the ASME Boiler and Pressure Vessel Code. 5.2.4.1 System Boundary Subject to Inspecticn The system boundary (ASME Section III Class I components) subject to inservice inspection includes the following: a. Reactor pressure vessel; including shell, heads, cladding, nozzles, penetrations and supports. b. Steam generators, primary side; including heads, flanges, nozzles and supports, c. Reactor coolant-pumps; including pump bodies, nozzles and supports, d. Pressurizer vessel; including heads, body shell, nozzles and shirt. O 5.2-20
l f SB 1 & 2 i FSAR. I D Reactor coolant piping; including the loop piping, pressurizer e. (See surge line, pressurizer spray line, valves and supports. Table 5.2-6 for'the list of lines and Tables 5.2-7 for the list of valves which form the reactor coolant pressure boundary, along with items a through d above). t 5.2.4.2 Accessibility All components have been arranged to provide the maximum possible clearances for access for inservice inspection, consistent with the design and function of the plant, and in accordance with the requirements of IWA-1500 of Section XI of the Code. Inservice inspection of the reactor vessel is described in Subsections 5.3.'1.6 and 5.3.3.7. Inservice inspection of the steam generator is described in subsection 5.4.2.5 and for the pressurizer in Subsection 5.4.10.4. Piping systems requiring volumetric (ultrasonic) inservice inspection are designed to provide access for inspection, and pipe welds are smoothed and concoured to permit effective use of the inspection equipment (See Figure 5.2-1). I Access for inservice inspection of' major NSSS equipment, other than the reactor j pressure vessel, has been facilitated as follows: Manways have been provided in the steam generator channel head to a. O. permit internal inspection of the steam generator. b. A manway has been provided in the pressurizer top head to allow access for internal inspection of.the pressurizer. The insulation covering all inspectable equipment and piping welds [ c. is designed for easy removal and replacement to facilitate weld' inspection and repsir, if necessary, and to provide adequate access i for surface and volumetric examination. d. The floor above the reactor coolant pumps has been provided with removable plugs to pe'rmit removal and installation of the pump motor, and to allow internal inspection of the pumps. The reactor coolant loop compartments have been designed to permit a. personnel access during refueling outages, to pennit direct inspec-tion of the external sections of the piping and components. f. Platforms and ladders have been strategically located to provide access to valves and other components for convenience in operation and maintenance. These platforms and ladders will facilitate inservice inspection. O 5.2-21
A ) SB 1 & 2 FSAR G i 5.2.4.3 Examination Techniques and Procedures In general, except for the reactor pressure vessel, inservice inspection is performed using manual techniques wherever possible. In those few cases where plant configuration and radiation level make manual inspection undesirable, automated techniques are used. The baseline inspection uses the same procedures and type of equipment as is used for inservice inspection to verify the adequacy of procedures and equipment. The reactor pressure vessel shell is inspected using an automated inspection device, as are the shell-to-nozzle welds and the inner surface of the nozzles. The bottom head welds and the nozzle safe-end welds are examined using manual techniques. For details of reactor pressure vessel inspection, refer to Subsection 5.3.3.7 and Chapter 16. The remote inspection equipment is tested and proven adequate prior to its use for baseline inspection. For details of inspection of the steam generators, refer to Subsection 5.4.2.5. Laydown areas are provided for storage of removed components and racks, and stands are provided to facilitate examination of removed components. Hoists and other handling equipment are provided in strategic locations for use during inservice inspection. The visual examination employed as a basis for the report on the general condition of the parts, components or surfaces includes such conditions as ll scratches, wear, cracks, corrosion or erosion of surfaces, misalignment, deformation or leakage. 5.2.4.4 Inspection Intervals Inspection intervals are ten years, and are in accordance with IWA-2400 of l Section XI of the ASME Code, Plan B. See Chapter 16 for details of the inser-l vice inspection plan. All inspections required by IWA-2500 will be completed by the end of each 10 year interval. It is planned that the required inservice inspection will be accomplished during ncrual plant maintenance and refueling shutdown periods. During the first 1/3 of the inspection intervals, at least 16% of the required inspections, and not more than 34%, will be completed. By the end of the cecond 1/3 of the interval, at least 50% and not more than 67% of the required inspections will be completed. The remaining inspections will be completed by the end of the 10 year interval. 5.2.4.5 Examination Categories and Requirements Inservice inspection categories and requirements are defined in Section XI l of the Code for specific code classes. A detailed description of the means used to meet these requirements is given in Chapter 16. In general, Seabrook categories are identical with IWB-2500 of the Code, and requirements are the came as IWB-2000 of the Code. o 5.2-22
. -~A11 olcetrical squipment ic Closo IE, cnd cquipment within tha containm:nt ctmo:phara io envircnment=4 y qualificd to insura cpsrcbil'$y in tha hostile cnviro,nment resulting fre )n cccids;nt. ./ 8 All piping and components downstream of the flow restricting orifice are Safety Class 2, and seismic Category I. All other piping and components downstream of the motor-operated valve are classified Non-Nuclear Safety. 5.2.6.4 Instrumentation Requirements Vent valve position indication is provided on the main control board. Inadvertent opening of the vent valves is detected by means of temperature detectors in the downstream piping, with alarm indication at the main control board. 5.2,7 References 1. WCAP-9292, " Dynamic Fracture Toughness of ASME SA508 Class 2a and ASME SA533 Grade A Class 2 Base and Heat Affected Zone Material and Applicable Weld Metal, March 1978. 2.
- Cooper, L., Miselis, V. and Starek, R.M., " Overpressure Protection for Westinghouse Pressurized Water Reactors", WCAP-7769, Revision 1, June 1972 (also 1,ettgr NS-CE-622, dated April 16, 1975, C.
Eiche1dinger (Westinghouse) to D.B. Vassallo (NRC), additional information on WCAP-7769, Revision 1). 3. Burnett, T.W.T., et al, "LOFTRAN Code Description", WCAP-7907, October 1972. 4. Letter NB-E-1730, dated March 17, 1978, C. Eiche1dinger (Westinghouse) to J.F. Stolz (NRC). O SB 1 & 2 FSAR 5. Colik, M.A., " Sensitized Stainless Steel in Westinghouse PWR Nuclear Steam Supply Systems", WCAP-7735, August 1971. 6. Enrietto, J.F., " Control of Delta Ferrite in Austenitic Stainless Steel Weldments", WCAP-8324-A, June 1975. \\
- Enrietto, J.F., " Delta Ferrite in Production Austenitic Stainless
{SteelWeldments",WCAP-8693, January 1976. l l 1
^ ~ ~ ~ ~ ~ ~ ~ ~ ~ ' ' ' ~ ~ ~. ~ ~ ~* - - - - - ~. - - ~ - - T SANOVIK, INC. SCRANTON WoeKS P 0. SCX 1220. SCRANTON. PA.18501 PM: 717 587 5193 PLANT LOCATION: INTERSTATE 31, WAVERLY EXff 59 CU5f008ER PURCM51 CROER N0 SANOVIA ORCER N0 sitm SPECIAL CODE mAnts CERiticAtt DATE 9763.011-20140 - 151574 05 26376 2012.9# 3/25/81 soto To: PUBLIC SERVICE C0 OF NH SEABROOK NH SPECINCATION AND MATERIAL: ASME SECTION II: SFA5.9; ASME SECTION III: PARA. NB2400 1977 EDITION THRU WINTER 1977 ADO. SANDVIK STAINLESS STEEL WELDING WIRE TYPE ER 308 045 x 2.5#sp Actual Weld Deposit Analysis, % Heat C Si Mn P S Cr Ni Mo 464872 .059 .38 1.97 .014 .001 20.24 9.29 .02 Cb Ta Ti V Cu N .01 .01 .01 .057 .026 .068 0 s r. N. Ch' Delta Ferrite content as determined from above analysis per Fig. NB2433.1-1 WRC Ferrite No. 6 FN Corresponding ferrite percent 6% This is to certify that the contents of this certificate are correct and accurate, as contained in Sandvik's records, and that all above tested results and operations performed are in compliance with the requirements of the purchase order and the l applicable sections of the Code and specifications as designated by the purchase order. ASME Quality System Certificate (materials) No. N-1400. Expiration Date: June 11, 1982. QA/QC SITE REVIEWED l By J P h Jd-UE & ~C v/i/r i l (date) i For Be t H. Berg, Quali Assurance Manager / rc -##, - b (W-B-SFA-3, REV. 5)ke m f f m aan ,, CUSTOMER ORIGINAL ee==. e.e-*w ea p-.waso m e, ,+ e==+...-em*e.~.=amor-m - - ee ew
- --en--
-= ---=.,=%-=+ e -= * *-
y3 QUAus y Ant tzt.,xc3 o(V[tA <-x TEST REFORT ".P nMEhaXM j 3 DI/ision wraIrd. WMr'wr.n.- /.O0O DATE: 10/20/81 O i SOLD TO: Abco SHIPPED TO: United Eng. DATE SHIPPED. 10/20/81 e 130 Cross Rd. Rt. 1 Site Access Rd. Waterford, Conn. 06385
- Seabrook, N.H.
03874 P.O. NO.:. 5454 P.O. NO.:. 97.011-22458 l SPECIFICATION: ASME Sect.Ill Class 1 Subsection NB-2400 '77 Ed Wint. '77 Add. Sect.ll SFA 5 9 ITEM POUNDS SIZE TYPE !BM XDOF NO. HEAT NO. L 1000 .035 ER308 308X297 55049 2-3760 .045 ER308 308X298 78156 t 1 ACTUAL CHEMICAL ANALYSIS OF WIRE CnX CEXX2X1tfrsi S l Sa Cr Ni Mo ~ Lu l V 4: ytTa~ ITEM C Mn P + l l g L .04 1 70 .008 .008 .41 19.89 9.88 .13 .021 I .024 .017 {.063 2 .04 1.68 .009 .009 34 20.07 9.99 .09 .020 .023 .017j .05: 1 i r _ 1a l i w ~ t ADDITIONAL TEST RESULTS A.ut.E. QW!.!Tf STEM CERTIFICATE .1 idsis PERFORMED WITH: N/A (PJ.TERIA!.5) .'i - X-RAY: N/A (3C.3sg , g STRESS RELIEVED N/A HRS. 6
- F.
EXP. W.n ', la43 hv i AS WELDED STRESS RELIEVED PLATE NO. N/A PLATE NO. N/A YlELD POINT. PSI TENSILE STRENGTH. PSI El.ONGATION IN 2". N REDUCTION OF AREA, % PLATE NO. N/A PLATE NO. N/A_, PACTS 6 'r-ft. lbs. 'F _ ft. Ic 1
- 1. Ferrite = 9%
- 2. Ferrite = 7%
~ State of ' certify the chemical analysis anc' ch'fsical or mecher Cih of cal test results reported above are correct as contairac. In the record cf the company. , Subscribed and sworn to t:efore :: t inis-ccy of 19_ ~ [ [f uC4 /.,h4__ ,ftary Pwohr fay'ccmmission expires ( a, 2.ss. m sw.:sar w4. A w 44 -e e g_e=+Nei.pewei d**.-
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