ML18094B277

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Forwards Response to 891117 Request for Addl Info Re Containment Monitor Channels.Channels Capable of Withstanding Containment Design Loading Conditions & Acting as Pressure Boundary.Design Specs Encl
ML18094B277
Person / Time
Site: Salem  PSEG icon.png
Issue date: 01/26/1990
From: Labruna S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18094B278 List:
References
NLR-N90016, NUDOCS 9002090115
Download: ML18094B277 (63)
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  • l Public Service Electric and Gas Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President - Nuclear Operations JAN.2 6 1990 NLR-N90016
u. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION CONTAINMENT MONITOR CHANNELS SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 The attached is in response to your information request of November 17, 1989. In summary, although the Containment Monitor Channels (CMC's) were not originally designed as part of the leaktight containment boundary, they are capable of withstanding the containment design loading conditions. The plugged CMC's are capable of acting as a pressure boundary, as evidenced by their design, installation and testing. Therefore, performance of the containment Integrated Leak Rate Test (ILRT), with plugged CMC's, does not invalidate the test results. Please do not hesitate to contact us if there are any questions regarding this submittal. r-----;;;:~-~~--

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F ~.'.DR A:ooci~.* =!QO 126 -~ r c_i!'.::.000272 I PDC .Jiff Sincerely,

I Document Control Desk NLR-N90016 c Mr. J. c. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector 2 Mr. w. T. Russell, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 JAN 2 6 1990

l NLR-N90016 ATTACHMENT 1 Question 1 Provide supporting analysis and stress calculations for at least one typical monitor channel to show that the containment liner monitor channel system meets the following requirements:

a.

The material strength and qilality of weld attaching the channel to the liner plate should be equal to or better than that of the original liner joints and should meet the applicable requirements of either ASME Boiler and Pressure Vessel Code, Section III, Division 2, Subsections CC-2000, 3000 and 4000 (Code of Concrete Reactor Vessels and Containments, 1983) or whatever comparable code that was used in design and construction.

b.

Since the monitor channels now become part of the containment wall and are therefore considered a structural element, the strength of the channel box and its welds should be able to resist all load combinations involving the tested loads and the loads of a postulated accident, including seismic loads. The design of the monitor channel should meet the applicable requirements of steel containment; i.e., either ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsections NE-2000, 3000 and 4000 for Class MC Components (1983) and American Institute of Steel Construction Specification for the Design, Fabrication and Erection of Structural Steel for Buildings (1978), or whatever comparable code that was used in design and construction.

Response

la. The ASME Boiler and Pressure Vessel Codes used in the design of the containment structure are the 1968 editions of Sections III and VIII. This is evidenced by Specification 68-7123 (Attachment 2). Addendum 2 of Attachment 2 specifies ASME-SA233 - Class E6010 as the weld electrode material used for the test channels. provides sample Record of Welding Procedure Qualification Specification sheets, and Mill Certification of the test channel material (ASTM A-36). Qualified welding procedures, welders and welding operators were used in accordance with Section IX, "Welding Qualifications" of the ASME Boiler and Pressure Vessel Code, 1968 edition. The liner test channels were not designed as part of the leaktight containment boundary. However, they are capable of withstanding the design loads (see response to lb below).

  • lb. Pressure testing (ILRT) of the containment produces a more severe loading on the liner and its attached test channels than the combined Design Basis Earthquake (DBE) and Design Basis Accident (DBA) loading condition.

The test pressure results in a tensile stress in the liner. Seismic loads impose compressive stresses on the liner, which are less limiting than the test pressure tensile stresses. The tensile stresses during the DBA are counteracted by the compressive stresses due to increased temperature (See UFSAR Section 3.8.1.4.1). For this reason PSE&G calculated the stresses induced in the test channels due to the combined loading of the test pressure (47 psig) and the elongation of the liner in both hoop and meridional directions. The calculation is provided in Attachment 4. The tensile liner stresses during ILRT are within the elastic range. Therefore, the resultant liner elongation is used as a loading condition on the monitor channels. The stresses caused by the liner elongation were added to the stress imposed by the test pressure on the closed channel, using the AISC Manual of Steel Construction. This methodology yields conservative results because it imposes the gross liner strains upon the channels and neglects any dimunition of this gross strain by other load resisting paths, such as:

1) the 1/2 inch diameter anchor studs welded on nominal 12 inch by 12 inch centers, which alone can withstand the entire shear force existing between the liner and the concrete containment structure; and 2) the liner to concrete bond.

In the case of the DBA, there would also be a frictional force between the liner and concrete as a result of internal pressure and temperature pressing them together. No credit is taken for the test channels themselves acting as stiffeners to reduce stresses and resultant strains of the liner plate under any loading. Question 2 Complete documentation of installation records, including leak test procedures and results of the liner seam welds and the welds attaching the channel to the liner, should be available on site. Please summarize and provide examples of available records. If no records or only partial records are available, provide whatever additional information/assurance is available regarding procedures, materials, welds, inspection records, etc.

  • Response The extensive testing of both the liner plate welds and the channel to liner plate welds, as specified in Public Service's Specification No. 68-7123, assures the quality and integrity of the welds in question.

Pressure tests were performed at 54 psi (15 minute test) and 47 psi (2 hours) to verify acceptable pressure retention in the area between the test channels and the containment liner. Subsequent leak tests, using both halogen detection and soap bubbles, were performed at 47 psi. consists of:

1) the test channel/liner test procedure; and 2) results of the pressure tests and leak tests. provides examples of field quality control surveillance reports for the above tests and radiography and magnetic particle tests.

In addition to the above, PSE&G has reviewed the actual liner plate principal stresses calculated from the liner plate strain gage rosettes used during the structural integrity test. The average stress and resultant strain is less than that used in our calculations. We attribute this to the likelihood that the strength of the materials used (concrete, rebar, and liner plate) in the construction was greater than that which was specified. Question 3 The staff needs a commitment that you will perform a visual inspection of the accessible interior and exterior surfaces of the containment structure and components prior to any Type A test, including a visual inspection of accessible channel plugs, as required by 10 CFR Part 50, Appendix J.

Response

Per 10CFR50, Appendix J, PSE&G's current procedure for Type A testing requires a general visual inspection of the accessible interior and exterior surfaces of containment structures and components. This inspection is performed to detect signs of structural deterioration. The test procedure does not specifically call for an inspection of the channel plugs. PSE&G will revise the test procedure to emphasize that since the plugged monitor channels serve as a pressure retaining boundary, they should be considered as part of the interior surface of containment for the purposes of the pre-test inspection. The procedure will be revised by March 15, 1990.

NLR-N90016 ATTACHMENT 2

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Mr. A. Nassman Room 1400 60 Park Place Date: June 12, 1973 STNi'IOI;: Salem Nuclear Generating Station -------------- A-267-Camden

~------------~

P.S. SP::'.:C. rm. Alm fdiDLlIDU~-: :: *.: 68-7123 Addendum_.*No. 9 P.S. SP~C. T~T~E: Personnel Locks and Equipment Hatch coritaiiirnen t Liner /. are fo:*

2. si;:ned. cory of t:_:' ~: form.

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I have Return to: above l: en Sponsor Enc;.i.11e:cr Publiq Scrvi~c El Structural Divici So i'c:L:r*l: l-'.lu.ce r-; c 1-; r,. r l~, Ne: w.Jc: r :; e; Tile Enugy re.... '.~.~ t:Loncd QUALITY.11.s~uq f, *rcE spE c i fie 2.. t ion...,aric!/o:c ad cl end. uir> I JJ>Nc*~c5 1973 R. A. A uli'1Jl D \\..: e c t1* i c 8~ 11 ( -l~~ ** <: "'~T) {**J:..' 'f vn CJH i ~.: ~.*i EJM ' A: i

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PUBLIC SERVICE ELECTRIC AND GAS COMPANY l:Ll:CTltlC ENGINEERING DEPARTMENT TRANSMITTAL LETTER OATEe.--~S~e~p~t~e_m~b...;;.._:;e_r_2-'-"l~,---'1~9~7_,__2_~ ~ CONlllTRUCTION *Ufl'l!ltlNTENDENT, U.E.llcC. INC. --- CHIEF CONTROLS ENGINEER --- DIVISION SYP'JRINTENDENT, ELECTRI---------- --- CHIEF CONSTRUCTION ENGINEER --- GENl!RAL llUP'IEltlNTENDl:NT OF DUITRll!lUTION*PROJECTS --- CHIEF COST ENGINEER --- GENERAL l!IUP'IEltlNTl!NDENT OI" DlllTRlllUTION-RELAY --- CHIEI" DEl!llGNING ENGINEER --- GENERAL llUP'l!RINTENDl!NT OP' Gl!Nl!RATION --- CHIEF ELECTRICAL ENGINEER --- GENERATING STATION llUPERINT!tNDENT--------- --- CHIEF MECHANICAL ENGINEER --- LABORATORY IENGINltl:lt --- CHIEF STRUCTURAL ENGINEl!R --- MANAGO OP' CONllTltUCTION ---.~--~Sua"'-"J~e~m111..~Ni1M1~c~J.... eua-...r--'G....,.e~n.....,.ewr"'--a~t~1.....,,n~g.__.asTATION AUTH. ___ u_-_?_6...._.z_... _C,._..a~m-d__..e.... n _________ _

SUBJECT:

WE ATTACH THE NUMllElt 01" COPIEl!l INDICATED ABOVE. OF EACH OF THE FOLLOWING: _l_ P.S.E.llcG. CO'S. --- DRAWINGS --- INSTRUCTION l!IOOKl!I --- SCHEDULEll --- EXPLANATION SHEETS --- L.ETTERS --- SKETCHES --- MANUFACTURER'* -. -- INSTRUCTIONS --- M EMOfllANDA --- SPECIFICATIONS --- TEST REPORTS Addendum No. 8 to Detail Specification No. 68-7123 is approved for co~struction. FOR:

Afl'fl'l!IOVAL

__.X ___ CONSTRUCTION.

COMMl:NTS

INl"OltMATION BY*

TFO:CL F. W. SCHNEIDER MANAGER OF' ENGINEERING ELECTW~ 'ifG:H~PARTMENT

w. A. Mart1_z-FO 0 THE MANAGER OF ENGINEERING. ELECTRIC ENGINEERING DEPARTMENT.

WIE HAVIE NO COMMIENT9

OUR'COMMl:NTS AltE ATTACHED

COMMENT* ON Rl:VER*E 81Dlt Ho04M SOM 1&0 71

Put;::c Ser. :ce Elcctr:::: 2;:.j Gas Comp:iny 80 P<::.:f. Place Ne\\*:urk, N.J. 07101 Phone 201.'622-7000 STATION: AUTHORIZATION: u -267. P.S. SPEC. NO. AND ADDENDUM NO.: P.s. sPEc. TITLE: CJtir;f0 inrne.il+ f..ioe.'1-Enclosed are Z:, copies of the specification and/ or addendu~ listed above. These copies are hereby approved and are for use in connection with the above mentioned project. Please acknowledge receipt of this documentation by returning a signed copy of this form. W. A. Martin Chief Structural Engineer Electric Eng:ne~~i{f Department By: "~ the above mentioned or Engineer K. fl.. A-u /J Public Service Electric and Gas Company Structural Division 80 Park Place Newark, New Jersey 07101 The Energy People addendum ll*,.....,..

rr*** PUDLIC SERVICE ELECTRIC AND GAS cnXPANY ELECTRIC E3GINEZRING DEPARTMENT ADDENDUM NO. 9

  • DETAIL SPECIFICATION N0.68-7123 CONTAINMENT LINER PERSONNEL LOCKS AND EQUIPMENT HATCH SALEM.NUCLEAR GEXERATING STATION UNITS N~. l A~D 2 ARTIFICIAL ISLAND LOWER.ALLOWAYS CREZK TOW~SHIP
  • SALZX'COUNTY, NEW'JERS2Y PREPARED BY:

RZVIE't!ED BY: QA APPROVAL: PROJECT APPROVAL1 I. . r REV. 0 thru REV. 9 I. I *; ~... /.' I,.. DATZ 5-30-73 fj]C /7-! I

~\\ \\*lELDI>;G:. Aoo;~:.*mu:: ;;o. 9 DETi"\\IL SP:CCif'IC\\'1.'IO:~ :JO. GS-7123 co:..;T.i1.Il;: ~=::~I' LL:;-:::? PERSO:;:.;;::r_, LOC1~S lC:W EQ'0~ * *: :~::-:;.' !L"l':!:'C;: Sl~Ls:.i i'JUCI.2.:~:.~~ G!:?;:~..:-*.'l,I:.:~ s*~*.:-~ 1r:o~*J UNI TS i.:O. l ?-.~:D 2 PUBLIC.SERVICE EL::.::C'=:'RIC

-.~*::-: Cl'.S cm::::i,::,.~.:Y AR'.i'IFICli->L rsr,.:*i,: i)

LO\\';ER' f,LLO~*.*:.,:.i'S c~i:;:;:::;( '.lC<::SHII' s1~LEM cou:\\TY, i.~:E:\\*; J£::>.:::r.=Y Add to Paraqraph (20)~e), Page 5, tho ~cllowing sentence: Rij'). 7' * ~.'?'...., ... ~... - I.~ 5-30-73 Weld r~inforcer::'2nt. 1:10.y l;e -:* srcund fl_ush in local areas to per~it ra~iographing. l

PUBLIC SERVIC~ ELECT~IC AND GAS cnM?A~Y ~~ECTRIC ENGINEERING DE?ARTXE~T ADDENDUM NO. 8 DETAIL SPECIFICATION NO. 68-7123 CONTAINMENT LINER PERSONNEL LOCKS AND EQUIPMENT HATCH SALEM.NUCLEAR GENERATING STATION UNITS N~. l A~D 2 ARTIFICIAL ISLAND LOWER.ALtOWAYS CRE~K TO~NSHIP

  • SALZM~COUNTY, ~EW'JERSZY PREPARED BY:

REV I EW ED BY : REV~ 0 thru REV. No. 8 STRUCTURAL APPROVAL: l. QA APPROVAL: PROJECT A?PROVALi I. ~! . i ~.. I.*.

ADD~NDUi*i NO. 8 DETAIL SPECIFICATICN NO. 63-7123 c ON'l'f\\ nr;.:E E'r L IH:C R PERSOHHEL LOCi\\:S.l:.ED EQ,UI?i-'.:!~~TT HATC~: SALEM NUCLEAR GERERATIHG S~hTION UNITS NO. 1 AND 2 PUBLIC SERVICE ELEC'I'l\\IC fl.Im C:/.S CCl-'.PAI~Y ARTIFICIAL ISLAITD LOWER ALLOW!dS C~EEK TO'f*!iTSIIIP SALEM COUNTY, NEW JERSEY Paragraph 22 (f), page (7) shall read as stated in Addendum No. 2. The addition to this paragraph in Addendum No. 6 is deleted. RAA:BAB 9-13-72 Sheet 1 of 1.

PUBLIC SERVICE ELSCTR:c AND GAS CnXPA~Y ELECTRIC E~GI~ZERING DEPAR~MENT ADDENDUM NO. 7

  • DETAIL SPECIFICATION NO. 6'8-7123 CONTAINMENT LINER PERSONNEL LOCKS AND EQUIPMENT HATCH SALZM. NUCLEAR GE::1rn.ATING STATION UNITS No*. l AND 2 ARTIFICIAL ISLAND LOWER.ALLQ' *..'AYS CRE:*:K TOWNSHIP*

SALZX' COUNTY, ~EW.JERSZY PREP AR ZD BY : REVIE'..JED BY: REV. 0 thru REV. No. 7 STRUCTURAL APPROVAL: I\\_:..:;~ QA APPROVAL: PROJECT APPROVAL& . I - . *.f. -. I 1.* DATZ . 4-28-72

~-=----- *-* PUBLIC SERVICE ELECTRIC AND GAS cnMPANY ELECTRIC ENGINEERING DEPARTMENT ADDENDUM NO. 5 ADDENDUM NO. 6 DETAIL SPECIFICATION NO. 68-7123 C ONTAINME~rT LINER PERSO~NEt LOCKS AND EQUIPME?IT HATCH SALEM.NUCLEAR GENERATING STATION UNITS NO. l AND 2 ARTIFICIAL ISLAND LOWER.ALLOWAYS CREZK TOWNSHIP SALEM COUNTY, NEW.JERSEY REV. 0 thru DATE REV. 5 & 6 PREPARED BY: RZV I EWED BY: . STRUCTURAL APPROVAL: QA APPROVAL: PROJECT APPROVAL1 I. i

      • ~.

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DETAIL SPECIFICATICN NO. 68-7123 CONTAINMENT LINER PERSONNEL LOCKS AND EQUIPMENT HATCH SALEM NUCLEAR GENERATING STATION UNITS NO. 1 AND 2 PUBLIC SERVICE ELECTRIC AND GAS COMPANY ARTIFICIAL ISLAND LOWER ALLOWAYS CREEK TOWNSHIP s~LEM COUNTY, NEW JERSEY R. A. AULD/NJR May 8, 1968 Addendum No. 1 Addendum No. 2 (. Addendum No. 3 Addendum No. 4 Addendum No. 5 Addendum No. 6 Addendum No. 7

ADDENDUM NO. 7 DETAIL SPECIFICATION NO. 68-7123 CONTAINMENT LINER PERSONNEL LOCKS AND EQUIPMENT HATCH SALEM NUCLEAR GENERATING STATION UNITS NO. 1 AND 2 PUBLIC SERVICE ELECTRIC AND GAS COMPANY ARTIFICIAL ISLAND LOWER ALLOWAYS CREEK TOWNSHIP SALEM COUNTY, NEW JERSEY Paragraph (13), Page 4, shall be changed to read as follows: (13) The liner of the completed structure shall be substantially round. The difference between the maximum and minimum inside diameters at any cross section shall not exceed 0.25% of the nominal diameter at the cross section under consideration up to elevation 130 1-0 11

  • Above this elevation, the tolerance shall not exceed 0.50% of the nominal diameter at the cross section under consideration.

RAA:BAB 4-28-72 Sheet 1 of 1.

ADDENDUM NO. 6 DETAIL SPECIFICATIO~ NO. 68-7123 CONTADIHEWI' LINER PERSON~IEL LOCKS AiTD EQUIPKSNT HATCH SALEM NUCLEAR GEi'IERATIUG STATION UNITS NO. 1 AND 2 PUBLIC SERVICE ELECTRIC AND GAS COMPANY ARTI?ICIAL ISLMrD LOWER ALLOWAYS CREEK TOWNSHIP SALEM COUNTY, NEW JERSEY INSPECTION AND TESTING: Add the following sentence to Paragraph 23 (a) (2) Page 7 - Vacuum Box Test: - When impractical to vacuum box test, a liquid penetrant (fuel oil) shall be used. WELDING: Add an additional sentence to Paragraph 22 (f) Page 7 as follows:* A liquid penetrant inspection shall also be performed on the welded seams. Add to Paragraph 22 (d) the following: If a weld repair is required on the vertical seam at the junction or a v~rtical seam and a horizontal seam, one "spot" adjacent to the defect on the vertical seam shall be radiographed. RAA:BAB 3-8-71 Sheet 1 or 1.

ERECTION: ADDENDUM NO. 5 _ DETrtIL SPECIFICATION NO. 68-7123 CCNTAINMENT LINER PERSONNEL LOCKS AND EQUIPMENT HATCH SALEM NUCLEAR GENERATING STATION UNITS NO. 1 AND 2 PUBLIC SERVICE ELECTRIC AND GAS CCMP~NY ARTIFICIAL ISLAND LCWER ALLOWAYS CREEK TOWNSHIP SALEM CCUNTY, NEW JERSEY Paragraph (14), Page 4, shall be changed to read as follows: (14) The liner shall be erected with an out of plumb allowance not to exceed 1/500 of the height. RAA:ST 7-21-70 Sheet 1.

~ MATERIAL: ADDENDUM NO. 4 DETaIL SPECIFICATICN NO. 68-7123 CCNTaINMENT LIN~R PERSONNEL LOCKS aND EQUIPMENT HAfCH SALEM NUCLEaR GE~ERAfIKG STATION UNITS NO. 1 AND 2 PUBLIC SERVICE ELECTRIC AND GAS CCMPANY ARTIFICIAL ISLAND LO~ER ALLOWAYS CREEK TOWNSHIP SALEM COUNTY, NEW JERSEY Paragraph (6) (d), Page (3) shall be changed to read as follows: The equipment and personnel access hatch material shall be as follows: Equipment Hatch Sleeve ASTM-A300 Cl. 1 and Flanges A-516 Gr. 60 Equipment Hatch Heads ASTM-A300 Cl. 1 A-516 Gr. 60 Personnel Locks ASTM-A300 Cl. 1 A-516 Gr. 60 The equipment hatch and personnel locks shall be A516 Gr. 60 steel normalized by heating to l,?00°F (+ 50°) and cooling in still air and vee notch tested to a minimum of-15-ft. lb. at -40°F, in accordance with ASTM Specification A370-65. Cn the interior bulk-head which is not subjected to low temperatures, the material shall pass a charpy vee notch test of 15-ft. lbs. at +20°F, in accordance with ASTM Specification AJ?0-65. WAS:MAS 12-10-69 Sheet 1. (

, ~* ':I. MATmIAL: ADDENDUM NO. 3 DETAIL SPF.CIFICATION NO. 68-712.3 CONTAINMENT UNm PERSONNEL LOCKS AND ~UIPMENT HATCH SAI.FM NUCLEAR GENERATING STATION UNITS NO. 1 AND 2 PUBLIC SERVICE ELECTRIC AND GAS COMPANY ARTIFICIAL ISLAND LOWER ALLOWAYS CREEK TOWNSHIP SALEM COUNTY, NEW JERSEY Paragraph (6) (d), Page (3) shall be changed to read as follows: The equipment and personnel access hatch material shall be as follows: Equipment Hatch Sleeve and Flanges Equipment Hatch Heads Personnel Locks AS'l'H-A.300 Cl. 1 A-516 Gr. 60 AS'IM-A.300 Cl. 1 A-516 Gr. 60 ASTM-A.300 Cl. 1 A-516 Gr. 60 The equipnent hatch and personnel locks shall be A516 Gr. 60 steel normalized by heating to 1,?000F (!,500) and cooling in still air and vee notch tested to a minimum of 15-ft. lb. at -40°F, in accordance with ASTM Specification A.370-65. FS:NJR 7-18-69 Sheet 1 of 1

MATERIAL: ADDENDUM NO. 2 DETAIL SPECIFICATION NO. 68-7123 CONTAINMENT LINER PERSONNEL LOCKS AND EQUIPMENT HATCH SALEM NUCLEAR GENERATING STATION UNITS NO. l AND 2 PUBLIC SERVICE ELECTRIC AND GAS COMPANY ARTIFICIAL ISLAND LOWER ALLOWAYS CREEK TOWNSHIP SALEM COUNTY, NEW JERSEY Paragraph (6) (d), Page (3) shall be changed to read as follows: The equipment and personnel access hatch material shall be as follow~: Equipment Hatch Sleeve and Flanges Equ~pment Hatch Heads Personnel Locks ASTM-A300 Cl.I A-516 Gr. 60 ASTM-A300 Cl.I A-516 Gr. 60 ASTM-A300 Cl.I A-516 Gr. 60 The equipment hatch and personnel shall be A516 Gr. 60 steel normalized by heating to 1700°F (! 50°) and cooling in still air and vee notch tested to a minimum of 15-ft. lb. at -50°F, in accordance with ASTM Specification A370-65. (h) Welding Electrodes Material Joined Plate-Carbon steel to carbon steel (manual) Plate-Carbon steel to carbon steel (automatic) Test Channels Stainless steel to stainless steel Carbon steel to stainless steel Page (3) Specification ASME-SA233 Class E7018-* (' - _)I Linde #29 with grade 50 Flux ASME-SA233 - Class E6010 ASME-SA298 Class E-308 Inconel 182 or E-309 Sheet 1 of 3

Revise Paragraph (8) Page (J) to read as follows: In general cylinder, dome and bottom plates shall be single vee beveled for welding unless noted otherwise on the drawings. Revise Paragraph 22 (a) Page (6) to read as follows: All double butt welded shell and dome joints shall be spot radiographed with the exception of the first 10-ft. made by each welder or operator which shall be 100% radiographed. Every 50-ft. thereafter a minimum of one spot radiograph (12-in. of welded joint) or two spot radiographs (6-in. of welded joint each) shall be taken. The radiograph films shall be made available to the Owners quality control representative at the job site for review during construction and on completion of the work shall be given to the Owner for his records. Revise Paragraph (f) Page (7) to read as follows: In locations where radiography is not possible, such as floor plates where back-up plates are used, the liner fabricator shall perform magnetic particle inspection of the welded seams. Revise Paragraph (23),(2) and (3) Page (7) and (8) to read as follows:

2)

Vacuum Box Test All liner bottom plates, welds shall be first tested for leak tightness using a vacuum box test. The box shall be evacuated to at least a 5 psi pressure differential with the atmospheric pressure.

3)

Strength and Leak Tests All welds shall be covered by channels as indicated on the drawings. After completion of the predetermined zone of channel covered welds, a strength test shall be performed by applying 54 psig air pressure to the channels in the zone for a period of 15 minutes and the exposed welded joints given a soap test for leaks. Any bubbles indicating a leak will require that the leak be rewelded and retested. It is intended that the leak tests to be made during liner-erection shall indicate no evidence of leakage at liner plate welds and at liner plate and weld joint channel welds. Sheet 2 of.3

3) Strength and Leak Tests (continued)

The zone of channel covered welds shall be pPessurized to 47 psig with a 20% by weight of Freon-air mixture. The entire run of the channel to plate welds shall then be traversed with a halogen leak detector. The sensitivity of the leak detector shall be 1 x l0-5 standard CC per second. The sniffer should be held approximately 1/2-inch from the weld anq traversed at a rate of about 1/2-inch/ second. The detection of any amount of halogen shall indicate a leak requiring weld repairs and retesting. In addition, the zone of channels shall be held at the 47 psig air pressure for a period of at least two hours. After correction for temperature change the indicated pressure change shall not exceed 0.5 psi. Where leaks occur, welds shall be repaired by grinding, chipping and/or machining and rewelding. Add to Specification: (47) Contractor shall furnish typical mill test reports for welding electrodes with the exception of electrode No. E6010. RAA :MAB 4-10-69 Sheet 3 of 3

MATERIAL: ADDENDUM NO. 1 DETAIL SPECIFICATION NO. 68-7123 CONTAINMENT LINER PERSONNEL LOCKS AND EQUIPMENT HATCH SALEM NUCLEAR GENERATING STATION UNITS 1 & 2 PUBLIC SERVICE ELECTRIC AND GAS COMPANY ARTIFICIAL ISLAND LOWER ALLOWAYS CREEK TOWNSHIP SALEM COUNTY, NEW JERSEY Paragraph (6) under Material shall be changed to read as follows: (6) All material shall be new and be of domestic manufacture. "'f

  • ~

.\\ ~ (a) Liner The liner plates for the cylinder, dome, bottom and pits shall be low carbon/high manganese steel with fine grain structure meeting ASTM Specifi-cation A-442-66 Grade 60. The plates shall be impact tested in accordance with ASME Boiler Code Section III, Paragraph N331.2, at a temperature 6o°F below the minimum service* temperature of 8QOF. The same impact test shall apply to the ASTM-Al06 Grade B steel and ASTM-Al55 KC70 used for pipe sleeves furnished by Public Service Electric and Gas Company. (b) Piping Penetrations Pipe penetration sleeves, 12" diameter and under Penetration reinforcing plates Pipe penetration sleeves over 12" diameter Anchor Rings and Bars Rolled shapes (c) Electrical Penetrations ASTM-A-106 Gr. B ASTM-A-442, Gr. 60 ASTM-A-155 KC70 ASTM-A-442, Gr. 60 ASTM-A-36 Penetrations sleeves to accommodate the electrical penetrations assembly cartridges will be Schedule 80 Carbon Steel, except where otherwise noted. Sheet 1 of 2

MATERIAL (Continued): (d) Access Penetrations The equipment and personnel access hatch material shall be as follows: Equipment Hatch Sleeve ASTM-A300, Cl. I and Flanges A516 Gr. 60 Equipment Hatch Heads ASTM-AJOO, Cl. I A516 Gr. 60 Personnel Locks ASTM-A300, Cl. I A516 Gr. 60 The equipment hatch and personnel locks shall be A516 Gr. 60 steel normalized by heating to l,?OOOF arid cooling in still air and V-notch charpy tested to a minimum of 15 ft. lbs. at -5C° F, in accordance with ASTM Specification A370-65. Paragraphs (e)* through (h) unchanged. RAA:VAS 9-18-68 Sheet 2 of 2

-_I DETAIL SPECIFICATION NO. 68-7123 CONTAINMENT LINER PERSONNEL LOCKS AND EQUIPMENT HATCH SALEM NUCLEAR GENERATING STATION UNITS NO. 1 AND 2 PUBLIC SERVICE ELECTRIC AND GAS COMPANY ARTIFICIAL ISLAND LOWER ALLOWAYS CREEK TOWNSHIP SALEM COUNTY, NEW JERSEY INSTRUCTIONS TO BIDDERS SUBMITTING OF BIDS: (1) All bids shall be submitted, in triplicate, in sealed envelopes to: Public Service Electric and Gas Company 80 Park Place Newark, New Jersey 07101 Attention of Mr. R. W. Lockwood, Manager of Purchases FORM OF PROPOSAL: (2) State a lump sum price for furnishing and installing the containment liners with appurtances for Units No. 1 and 2 at Salem Nuclear Generating Station in accordance with Detail Specification No. 68-7123. ADDITIONAL INFORMATION REQUIRED: (3) In addition to lump sum price, quotati.on should contain the following information: (a) Terms of payment. (b) The Contractor shall submit with his proposal a detailed de-scription of his fabrication and erection procedure including any temporary bracing or supports he plans to use. (c) The Contractor shall state a unit price for any additional Nelson studs that may be required by the Owner. (d) Two types of electrical penetration sleeves are shown on drawing 201177-A-8710. Please state the price differential if any, between types "A" & "B". (e) State price per pound for furnishing and installing miscellaneous items such as pipe support brackets, crane conductor brackets, space heater brackets, etc. which are not shown on the drawings, but will be required. (f) State type and size of major erection equipment to be used. (g) State capability to erect two liners concurrently. GENERAL INFORMATION: (4) The site will be accessible both by water and by road, but there will be no railroad access. Sheet 1 of 2

GENERAL INFORMATION (Continued): (5) The bidders shall visit the site and acquaint themselves with the field condition& which would affect the erection of the liners. (6) The tentative erection schedule for the liners is as follows: Reactor Pit Liner and Drain Pit Elevator & Sump Pit Liners Knuckle Plate & Containment Floors Cylinder Walls Up to El. 120 Cylinder Wall Above El. 120 & Dome RAA:VAS 5-8-68 No. 1 Unit Dec. 1968 - Jan. 1969 Jan. 1969 - Feb. 1969 March 1969 - May 1969 May 1969 - July 1969 March 1970 - July 1970 Sheet 2 of 2 No. 2 Unit Feb. 1969 - March 1969 March 1969 - May 1969 June 1969 - July 1969 July 1969 - Oct. 1969 Aug. 1970 - Nov. 1970

DETAIL SPECIFICATION NO. 68-7123 CONTAINMENT LINER PERSONNEL LOCKS AND EQUIPMENT HATCH SALEM NUCLEAR GENERATING STATION UNITS NO. 1 AND 2 PUBLIC SERVICE ELECTRIC AND GAS COMPANY ARTIFICIAL ISLAND LOWER ALLOWAYS CREEK TOWNSHIP SALEM COUNTY, NEW JERSEY SCOPE OF WORK: (1) This specification covers the furnishing of all tools, equipment, ma-terial, labor and supervision to detail, fabricate, deliver, unload and erect the steel liners with all appurtenances for the Containment Structures, Units No. 1 and 2 at Salem Nuclear Generating Station of Public Service Electric and Gas Company, located on the south end of Artificial Island in Lower Alloways Creek Township.in Salem County, New Jersey. (2) The general clauses governing the work herein specified are given in General Specification No. 66-5002, which is attached hereto and forms a part hereof. DRAWINGS: (3) shown on In general, the work to be done and the material to be furnished is the fgilowing drawings: 2011SS-A-8710 - Equipment and Personnel Hatches 201175-A-8710 Containment - Bottom Ljner 201176-A-8710 Liner - Reactor Pit and Sump and Elevator Pits 201177-A-8710 Liner - Side Elevation Quadrant "A" 201178-A-8710 Liner - Side Elevation Quadrant "B" 201179-A-8710 Liner - Side Elevation Quadrant "C" 201180-A-8710 Liner - Side Elevation Quadrant "D" io1181-A-8710 Dome Liner and Details 201182-A-8710 Sump Valve Room Liners INFORMATION ONLY 201001-A-8703 Excavation Plan 204802-A-8752 Plan Generating Facilities WORK INCLUDED: (4) The work shall include but not be limited, to the following: (a) (b) (c) (d) (e) (f) (g) Liner plates for containment including pits in mat. Pipe penetration sleeves (unless stated otherwise on the draw-ings or in this specification.) Instrument and electrical penetration sleeves. Ventilation penetration sleeves. Fuel transfer penetration sleeve

  • Equipment hatch penetration sleeves and heads.

Personnel hatches complete with controls, lighting system, conduits, wiring, fittings for air supply, gaskets, intercommunication, equalizing system and electrical connectors and air exhausts. Operating and maintenance manuals, including parts lists are to be furnished.

1.

WORK INCLUDED (Continued): (h) Channels and plates for pressurized test of welds. (i).Reinforcement at openings as required. (j) Reinforcing of dome. (k) Nelson studs and other anchors. (1) Pickling or sandblasting of plates and channels. (m) Shop painting. (n) Heat treatment and stress relieving as required. (o) Radiographic examination and other non-destructive testing. (p) Sectional pressure testing. (q) All instruments, equipment, connections and interconnecting piping required for zone testing during construction. WORK NOT INCLUDED: (5) (a) Concrete, forms and reinforcing steel. (b) Field painting. MATERIAL: (c) Miscellaneous steel and anchors set in concrete mat. (d) Leveling tees, for bottom liner plates and grouting and screening between these tees. (e) Insulation. (f) Inte.rnals for fuel transfer sleeve. (g) Furnishing, installing and testing penetration internals. (h) Permanent piping and instrumentation required for the liner seam channels and penetration test pressurizing system * (i) Post construction leak test. (6) All material shall be new and be of domestic manufacture. (a) (b) Liner The liner plates for the cylinder, dome, bottom and pits shall be low carbon/high manganese steel with fine grain structure meeting ASTM Specification A-442-66 Grade 60. Tile plates shall be impact tested in accordance with ASME Boiler Code 0 Section III, Paragraph N331.l and N331.2, at a temperature 30 F below the minimum service temperature of S0°F. Piping Penetrations Pipe penetration sleeves, 12" diameter and under Penetration reinforcing plates Piping penetration sleeves over 12" (Rolled to piping tolerances and 100% radiographed). Anchoring Rings and Bars Rolled Shapes fJ /l.-" ASTM-A-333, Gr. ASTM-A-442, Gr. AS'IM-A-300 Cl. Firebox A516, ASTM-A-442, Gr. AS'IM-A-131, Gr. 1 60 I Gr. 60 60 c Spec. No. 68~~123

2.

\\.

MATERIAL (Continued): (c) Electrical Penetrations (d) Penetration sleeves to accommodate the electrical penetration assembly cartridges will be Schedule 80 Carbon Steel, except where otherwise noted. Access Penetrations The equipment and personnel follows: Equipment Hatch Sleeve and Flanges Equipment Hatch Heads Personnel Locks access hatch material shall be as ASTM-A300, Cl. I, Firebox -A516 Gr. 60 ASTM-A300, <t*U 1, Firebox A-516 Gr. 60 ASTM-A300, Cl. I, Firebox -A516 Gr. 60 The equipment hatch and personnel lock&'~ shall be firebox steel normalized by heating to l,700°F and cooling in still air and charpy tested to a minimum of 15-ft.-lb. at -50°F, in accordance with ASTM Specification E-208-63T. (e) Dome Stiffeners (f) (g) (h) FABRICATION: The stiffeners for the dome shall be of ASTM A-36 material. Mill Tests Mill test reports both physical and chemical, for all shapes and plates used in this work shall be furnished to the purchaser. Certified reports of impact tests shall also be furnished to the purchaser. Miscellaneous Items Anchors shall be Nelson studs or approved equal. Gaskets shall be silicone or approved equal. Welding Electrodes Material Joined Carbon steel to carbon steel Stainless steel to stainless steel Carbon steel to stainless steel Specification ASME-SA233 Class E7016 or E7018 ASME-SA298 Class E-308 ASME-SB295 Class E.. Ni Cr Fe -3 (7) All fabrication shall be done in accordance with the best shop practice. All edges to be welded shall be properly prepared and aligned to assure good welds. Thermal stress-relieving shall be applied to fabricated items as required to insure the dimensional stability of fabricated items. Penetration sleeves to which attachments are to be made shall have edge p~a~aration for welding as indicated on the drawings, All joints shall be full penetration welds. (8) All cylinder and dome plates shall be double vee beveled for weld unless noted 'otherwise on the drawings. Bottom plates shall be single vee beveled as shown on the drawings. Spec. No. 68-7123

3.

PAINTING: (9) All liner plates shall be cleaned and the liner surface of the cylin-der and dome pl~tes shall be given a prime coat as follows: All material shall be cleaned by pickling or by sandblasting to a white finish to remove all mill scale and rust. These methods of surface prepa-ration shall be performed in accordance with the Steel Structures Painting Council Surface Preparation Specifications dated October 1, 1963, or the latest revision. Procedure 3.1.2.2 or 3.1.2.3, as described in Specifi-cation No. 8, shall be strictly followed for cleaning by acid pickling. Blasting procedures shall conform to Specification No. 5 for white blast cleaning and the finished surface shall have an appearance equal to that as defined in Section 2.2. The cleaned surface shall be primed with Keeler and Long epoxy-acite white primer No. 7107 to give a dry film thickness of two mils. If any visible rust forms prior to priming, it shall be removed by hand or mechanical cleaning methods. Plates shall be painted to within 2" of edges prepared for welding, Th~ edges prepared for welding shall be coated with Deoxaluminite for protection. ERECTION: (10) The Contractor shall be responsible for the proper and safe handling and erection of the complete containment liners as covered by this specifi-cation. The Contractor forces on the site shall receive, unload and properly stockpile and protect the materials against damage during storage and handling. Adequate temporary bracing, struts, shores and similar items shall be provided by the Contractor to position and hold the containment plating and appurtenances during erection. Wind *bracing required to hold and support the liner shall be provided and erected by the Contractor. All fabrications and erection shall conform to the requirements of the ASME Boiler Code Section VIII. (11) The Contractor shall submit details of his erection procedure and bracing to-the Owner for his review. Approval of the system by the purchaser does not relieve the Contractor of full responsibility for the safety and stability of the liner assemblies throughout the erection of the liner. (12) The use of a guyed derrick for erection will not be permitted as the guys interfere with other construction operations. (13) The liner of the completed structure shall be substantially round. The difference between the minimum and maximum inside diameters at any cross section shall not exceed 0.25% of the nominal diameter at the cross section under consideration. Maximum diameter 140'-2", minimum diameter 139'-10". (14) The liner shall be erected with an out of plumb allowance not to exceed 1/500 of the height to the cross section under consideration. (15) Care shall be taken in matching edges of cylindrical and hemi-spherical sections to insure that all joints are property aligned. (16) All penetration sleeves, equipment hatches and personnel locks shall be installed by the Contractor. (17) Any lugs attached to the liner plates, for erection purposes shall be removed and any projecting metal shall be ground smooth. The plates shall not be gouged or damaged in the process of removing the lugs. Attachment of !~8S shall be made with a qualified welding procedure. Spec. No. 68-7123

4.

ERECTION (Continued): (lS) Erection operations of the Contractor shall be performed in ac-cordance with the Purchaser's CPM schedule. WELDING: (19) General (a) All welding shall be done only by qualified welding operators. Qualification of welding procedures, welders, and welding operators shall be in accordance with Section IX "Welding Qualifications" of the ASME Boiler and Pressure Vessel Code. (b) The Contractor shall make available to the Owner reports of the results of tests required to qualify the welding pro-cedures, the welding operators, and the welders. (c) Welding shall not be performed when the surfaces of the parts to be welded are wet from snow, rain or ice; when rain or snow. is falling on such surfaces; during high winds, unless work and welder are properly shielded; nor when the base metal temperature is less than0 70°F. ljhen base metal temper-ature is within the range of20 F to 7,Q F inclusive, the base metal within 3" of the place where welding is to be started shall be heated to a temperature warm to the hand to remove - moisture. (20) Weld Quality (a) All welds shall'-be sound throughout full penetration of plate thickness. If necessary, back gouge and reweld. There shall be no crack or zone of incomplete penetration or lack of fusion in any weld or weld pass. The weld may be considered sound if it contains small amounts of slag and porosity which is well dispersed and is within the limits ~ecessary to meet all of the requirements of the porosity standards of the ASME Code. (b) Butt welds shall have full penetration, be slightly convex, and of uniform width and height. (c) Fillet welds shall be of specified size with full throat and legs of uniform width. When not specified on the drawings, the fillet weld size shall be at least equal to the thickness of the thinner attachment. (d) All welds shall be free from undercut and overlap. (e) Weld reinforeement shall be not less than 1/16" or more than 1/8". Reinforcement shall merge into the base material without shoulder or undercut. Spec. No. 68-7123

5.

WELDING (Continued); (f) All slag or flux remaining on any bead or layer or welding, _s,llall be removed before applying the nex~ layer. (g) Cleaning of each bead or layer may be performed by a pneu-matic hammer. All beads or layers shall be thoroughly wire brushed and visually inspected before applying the succeeding bead or layer. All defects or irregularities disclosed by inspection which would prevent proper disposition of succeeding bead, shall be removed. (h) The cover pass of each weld shall be free of coarse ripples, irregular surface, non-uniform bead pattern, high crown, and deep ridges or val~eys between beads. (21) Repair of Welds (a) Visible defects, such as cracks, pinholes, and incomplete fusion, and defects detected by the tests and examinations prescribed in Inspection and Tests of Welds shall be com-pletely removed and the welds repaired by rewelding. (b) Ilefective work shall be repaired by the Contractor for his account. (c) Repair welds shall be subject to the same welding and inspection requirements as the original welds. (d) Repair, chipping, grinding, or gouging of welds shall be done in such a manner as not to gouge, groove, or reduce the base metal thickness. (22) Inspection & Testing of Welds (a) For the liner complete radiograph shall be made of the first 10 feet of full penetration weld made by each welder or weld-ing -operator and a, _minimum of "spot" radiograph on a 12" film every 50 feet thereafter of weld on side walls and dome, except where back-up plates are used. The radiograph films shall be given to the Owner for his review and records. (b) For the locks the location of the "spot" rad-iographs shall be subject to the approval of the Owner's inspector. (c) All locks shall be 100~ radi&graphed for the first S' of full penetration weld.made by each welder or welding operator and a minimum "spot" radiograph on 12" film every 20 feet there-after. The radiograph films shall be given to the Owner for his review and records

  • Spec. No. 68-7123
6.

WELDING (Continued): (d) When a "spot" radiograph shows defects that require repair, _t~o adjacent "spots" shall be radiographed. If defects re-quiring repair are shown in either of these, all of the weld-ing performed by the responsible welder or welding operator shall be 100% radiographed to determine end of defect in ac-cordance with ASME Code. (e) Tile Contractor shall give the Owner notice in ample time so the inspector can be present when welds will be tested both for shop work and field work. (f) In locations where radiography is not possible, such as floor plates~ and lower courses of shell plates where back-up plates are used, the liner fabricator shall perform ultrasonic tests using an acceptance limit of 5% sensitivity determined by a reference specimen. (g) All defects or irregularities disclosed by radiograph or ultra-sonic examination shall be removed and repaired by the Con-tractor for his account. (h) All additional non-destructive testing shall be for the Con-tractor's account. INSPECTION AND TESTING: (23) It is intended that the Containment Buil~ing Liner, its surrounding reinforced concrete structure, and all penetrations through* the building be fabricated, erected, and tested in such a manner that the completed building can successfully pass strength and leak rate test by others. Field inspection and testing will take place during erection of the Containment Liner and be performed by the Contractor. (a) Construction Tests (1) During erec~ion of the liner, the Contractor shall perform the following inspection and tests: Spec. No. 68-7123 a) Liner Plates

1)

Ultrasonic Testing - See Section 22 (f) of this specification.

2)

Vacuum Box Test All liner plate welds shall be first tested for leak tightness using a vacuum box test. The box shall ~e evacuated to at least a 5 psi pressure differential with the atomospheric pressure.

7.

INSPECTION AND TESTING (Continued):

3)

Strength and Leak Tests After completion of a successful vacuum box test, the welds shall be covered by channels as indicated on the drawings. After completion of the predetermined zone of channel covered welds, a strength test shall be performed by applying 54 psig air pressure to the channels in the zone for a period of 15 minutes and the exposed welded joints given a soap test for leaks. Any bubbles indicating a leak will require that the leak be rewelded and retested. It is intended that the leak tests to be made during liner erection shall indicate no evidence of leakage at liner plate welds and at liner plate and weld joint channel welds. The zone of channel covered welds shall be pressurized ao 47 psig with a 20% by weight of Freon-air mixture. The entire run of the channel to plate welds shall then be traversed with a halogen leak detector. The se~~itivity of the leak detector shall be 1 x 10 standard CC per second. The sniffer should be held approximately 1/2 inch from the weld and traversed at a rate of about 1/2 inch/ second. The detection of any amount of halogen shall indicate a leak requiring weld repairs and retesting. In addition, the zone of channels shall be held at the 47 psig air pressure for a period of at least two hours with no indication of drop in pressure. Compen-sation for change in ambient air temperature shall be made if necessary. Where leaks occur, welds shall be repaired by grinding, chipping and/or machining and rewelding. (b) Penetrations (1) Strength and leak tests of individual penetration internals and closures will be performed by Others. Leak tests of the penetration sleeve weld channels shall be by this Contractor. (c) Personnel Locks (1) The Contractor shall perform leak tests on the lock, gaskets and all channels as follows: Spec._- No. 68-7123

8.

INSPECTION AND TESTING (Continued): a) The channels and gaskets shall be strength tested by a 54 psig air pressure to the channels and between the gaskets and hold for 15 minutes. b) The lock shall be strength tested by pressurizing to 54 psig air pressure and holding for 15 minutes with hold down bars on inner doors. c) The channels shall be leak tested by pressurization to 47 psig with a 20% by weight of Freon-air mixture. The entire run of plate weld and the channel to plate welds shall then be traversed with a halogen leak detector. The sniffer should be held approxi-mately 1/2 inch from the weld and traversed at a rate of about 1/2 inch/second. In addition the zone of channels shall be held at the 47 psig air pressure for a period of at least two hours with no indicated drop in pressure. Compensation for change in ambient air temperature shall be made if necessary. Where leaks occur, welds shall be repaired by grinding, chipping and/or machining and rewelding. d) The gaskets and seals on lock penetrations shall be leak tested by pressurizing the space between the gaskets and seals to 47 psig with a 20% by weight of Freon-air mixture and testing the inside and outside of each door and -;eal the same as (b) above. (d) Eguip!llftt Hatch (1) The equipment hatch cover shall have a double gasket and shall be tested as described under Personnel Locks. (24) The Contractor shall notify the OWner prior ta any tests in sufficient time so that all tests shall be made when the OwRer's inspector and liner fabricator's inspector are present. (25) Approval of shop leak tests do not relieve:*tthe Contractor of his responsibility of furnishing leak tight locks that will be subject to the Post Construction Tests performed by Others. Should leaks appear in any of the Contractor's work, when the Others are making the Post Construction Tests, they shall be repaired and backcharged to the CSO-Dtractor's account. (e) Post Construction Tests (1) After the Containment Building is complete with liner, reinforced concrete structure, and all electrical and piping penetrations, equipment hatch and personnel locks in place, the post construction leak test will be performed by Others. Spec. No. 68-7123

9.

DESIGN CONDITIONS FOR PERSONNEL LOCKS: (26) The design pressure for the locks on the Containment side shall be 0 54 psig with coincident temperature of 270 F. Stresses and welding shall be in accordance.with ASME Unfired Pressure Vessel Code Section VIII. (27) The locks shall also be designed for 54 psig internal pressure and the door on the containment side shall be provided with the necessary hold down bolts. (28) The seals and equipment to be furnished shall be designed and selected so8as to be capable of withstanding an integrated total rgdiation dosage of 1 x 10 R. The design temperature for the seals shall be 300 F. (29) The minimum plate thickness shall be 3/8" for stressed sections. (30) The locks shall have doors on both ends, each of which shall be de-signed to withstand the design pressure from the Containment side. Each door shall be fitted with two (2) seals. The seals will be located so that air will be applied between each seal and pressurized to 54 psig. The door shall be mechanically interlocked in such a manner that only one door can be opened at a time. The interlocks shall also control the pressure between the seals. (31) The doo~ shall be made to operate mechanically. Visual indicators shall be provided at the exterior face of each door showing status of the opposite door with switch for remo~e indication in control room * (32) The locks shall be furnished with a pressure eqialization system that will equalize the pressure inside the lock to the pressure on the opposite side of the door being opened. (33) Equipment openi~~cover must have two (2) seals with air applied between each seal and test pressurized to 54 psig similar to doors. (34) Pressure gauges shall be installed outside the Containment, in the lock and inside the Containment, indicating the lock and containment pressures. (35) Channels shall be provided over welded joints on the inside of the lock sleeve which will not be accessible from both sides after the concrete cylinder wall is poured. (36) Each lock shall have the following minimum requirements and provision for extra connections, included values: (a) (b) (c) (d) (e) (f) (g) (h) Fittings for emergency air supply. Fittings for interior lighting. Fittings for intercommunication connection. Fittings for air supply and exhaust. Fittings for pressure equalization, including check valves and gauges. Raised floor, designed for 100 psf live load. Full length, shoulder high hand bar. Fittings for special apparatus - indicating signal. Spec. No. 68-7123

10.

DESIGN CONDITIONS FOR EQUIPMENT HATCH: (37) The design of the inner cover of the equipment opening shall be 54 0 psi with a co~n~ident temperature of 270 F. Stresses and welding shall be in accordance with ASME Unfired Pressure Vessel Code Section VIII. (38) The* design of the outer aover of the equipment opening shall be for an external pressure of 1000 lbs. per sq. ft. The plating shall have a mini-mum thickness of 1 inch and shall be well stiffened and cover equipped-with* a lifting eye. (39) The inner cover shall be filled with two seals. The seals shall be located so that air can be applied between the seals at 54 psi. The seals and equipment shall be designed and selected so as8to be capable of withstanding an integrated total radiation dosage of 1 x 10 R. The design temperature shall be 270°F. (40) The outer cover shall be provided with a single seal. /* ERECTION SEQUENCE: (41) The liner floor, shell and dome plates shall be erected in the following sequence for each unit: (a) Reactor *~cavity floor and walls.and drain pit. (b) Containment sump and elevator pit liners. (c) Floor plates and pressure channels. (d) Penetration sleeves, pressure channels and cylindrical steel plates up to elevation 120"-0". After elevation 120 i: is reached, work will be suspended until all iuternal concrete work is com-plete and major components (reactor and steam generators) are set. (e) Complete cylinder plating and channels up to spring line. (f) Dome plates and stiffners, pressure channels and ventilation opening. (g) Pipe brackets, space heater supports, crane conductor brackets and miscellaneous items. (42) After all equipment has been installed in each containment, the Con-tractor shall return to install the equipment hatch doors, adjust personnel doors and make any required repairs or corrections. (43) Items (a), (b) and (c) shall be furnished as early items to meet the construction schedule. (44) As there are~two units involved, we contemplate that the second unit will follow this first closely enough so that items (a) through (d) can be erected alternately between the units. Spec. No. 68-7123

11.

MISCELLANEOUS: (45) Nelson studs shall be welded to the plating as shown on the drawings. Each welder, at_ tjle beginning of each work day, will attach at least one test stud which will be tested by bending the stud approximately 45 degrees toward the plate to demonstrate the integrity of the weld. If failure occurs in the weld, the welding procedure or technique will be corrected, and two successive studs successfully welded and tested before further studs are attached to the liner plate. These test studs will be allowed to remain in place but will not be considered as a part of the regular stud pattern required by the design. All studs on which a full 360 degree weld is not obtained will be removed and replaced by a new stud. Before welding a new stud where a defective one has been removed, the area will be ground flush and smooth. (46) Penetrations shall conform to the applicable sections of ASA N6.2-1965, "Safety Standard for the Design Fabrication and Maintenance of Steel Containment Structures for Stationary Nuclear Power Reactors." All personnel locks and aµy portion of the equipment access door extending beyond the concrete shell will conform in all respects to the requirements of ASME Section III Nuclear Vessels Code. The"liner will be reinforced about all openings in accordance with the philosophy of ASME Section VIII Pressure Vessels Code (i.e., by replacing cutout area of liner plate). Liner reinforcement will be designed to support penetra-tions in the appropriate portion of liner plate during field erection. RAA:VAS 5-8-68.* Spec. No. 68-7123

12.

i I

NLR-N90016 ATTACHMENT 3

CONTRACT CHICAGO BRIDGE AHO IRON COMPANY RECORD.OF WELDING PROCEDURE QUALIFICATION SPECIFICATION TO A.S.M.E. SECTION IX LATEST EDITIOH PART II ESSENTIAL VARIABLES SPECIFICATION NO. ___ _.9~-~H..._ _________ _ ~.ING PROCESS _ _...,:S=-=.:h;..:;:i:...::e:...::l=-d.;;..:.e~d;._;:_M:...::e.;;..:.t.;;..:.a;;.._l_A_r_c ___ ~IAL SPECIF I CA llON __ A...._.2=--0=1.... B __ TO _._A_2_0_l_B __ ASME P-NO. _ __....__ ___ TO ASME P-NO. ---~--- 3/.4 II THICKNESS (IF PIPE, DIA. AND WALL THICK.) _ _._..... _ __.._ ____ THICKNESS RANGE THIS TEST QUALIFIES 3/16 11 to 1 1/2 11 ~RMETALGROUPNO.F ______________ _ y,.__u METAL ANALYSIS NO. A ____ l ________ _ ASTM SPECIFICATION N0. _____ -.::2;..;:3""'3..__ _____ DATE Dec MANUAL OR MACHINE __ M_a_n..:_.u_a_l ___ FLUX OR ATMOSPHERE FLUX TRADE NAME OR COMPOSITION----- INERT GAS COMPOSITION --------- TRADE NAME ______ FLOW RATE __ IS BACKING STRIP USED? _ _....,N._,,o'------- PREHEAT TEMPERATURE RANGE None POSTHEAT TREATMENT ____ _.N~o ... n~e..__ __ WELDING PROCEDURE SINGLE OR MULTIPLE PASS Multiple SINGLE OR MULTIPLE ARC Single POSITION OF GROOVE _1 WELDING TECHNIQUE (FOR INFORMATION ONLY) ELECTROOE ___ ___.E~6~0.1~0;__ _________ TYPE OF BACKING ----iN~oy,.jn~e;:_,_ __________ _ FILLER WIRE DIAMETER WELDING CURRENT 5/32 "p & 3/16; DC Reverse Po; CONSULT PART 111 HON.ESSENTIAL VARIABLES FOR JOINT DIMENSIONS AND WELDING CURRENT SET"'!"INGS. TEST RESULTS REDUCED SECTION TENSILE RESULTS DIMENSIONS ULTIMATE ULTIMATE UNIT CHARAC SPECIMEN NO. AREA TOTAL WIDTH THICKNESS LOAD, LB. STRESS, PSI ANO 9-H-l 1.388 .432 .600 39,600 66,000 Ducti. q-H-? 1.430 .425 .607

40. 000 66,000 Ducti GUIDED BEND TEST TYPE RESULT TYPE RESULT Free Root OK All O.K.

---".:R'S NAME* w.H ft Cave SOCIAL SECURITY NO. 3 5 3-05-9832wELDER'S SYMBOL WHO BY VIRTUE OF THESE TESTS MEETS WELDER PERFORMANCE REQUIREMENTS. WE CERTIFY THAT THE STATEMENTS IN THIS RECORD ARE CORRECT AND ":"HAT THE TEST WELDS WERE PREPARED, WELDED ACCORDANCE WITH THE REQUIREMENTS OF SECTION IX OF THE ASME CODE. SIGNED CHICAGO BRIDGE & IRON COMPANY DATE_...._..___. ttORATORY-TESTNO. ~--L9_-~H--~-~~-- _______ _t:.!:_:_~ 1 ,L:..J.2'.,J....~bl:ll!!~"4--~~A~N£!...s_ REMARKS: Char hole S

PAGE CONTRACT CHICAGO SRIDG E AND IROH COMPANY RECORD OF WELDING PROCEDURE QUALIFICATION SPECIFICATION TO A.S.M.E. SECTION IX LATEST EDITIOH t 19'* PART II ESSENTIAL VARIABLES SPECIFICATION NO. ______ 9""---V.¥.--------- WELDING PROCESS ____ S,,;i.*.1.1h'""'j,,s;e._lwd"""ew..wd_..Mu.e.._.t_.a....... l_...A...,r....,c..___ .~IAL SPECIFICATION__.,A..,..2c..=..0_1-.B __ TO A201B ASt'Xt.P*NO. ------TO ASME P*NO. ------- 3/4 11 THICKNESS (IF PIPE, DIA. AND WALL THICK.) __ -.z._J...-~--- THICKNESS RANGE THIS TEST QUALIFIES J /16" to 1 1/2 11 FJ'-"-\\~METALGROUPNO.F ___ ~--------- Yf,_.~*METAL ANALYSIS NO. A-----'---------- ASTM SPECfflCA TION NO *..;.*----..J.;..J...~-------- DATE Dec MANUAL OR MACHINE -""-=a::.:n.=..u=a-=l'------ FLUX OR ATMOSPHERE FLUX TRADE NAME OR COMPOSITION-----

  • INE'RT GAS COMPOSITION--------

TRADE NAME ______ FLOW RATE IS BACKING STRIP USED? _ PREHEAT TEMPERATURE RANGE ______ o.... n~e~ POSTHEAT TREATMENT ______ ~'""'""- WELOIHG PROCEDURE SINGLE OR MULTIPLE PASS Multiple SINGLE OR MULTIPLE ARC _ _.S"'-=i=nc,;;lgi.:::l...:::e:;.__POSITION OF GROOVE WELDING TECHNIQUE (FOR INFORMATION ONLY)

1 ELECTROOE _____

...,ELli6~0""'1-.:0::::.....--------- '.! :i TYPE OF BACKING None WELDING CURRENT

=DC~J...-.:..R:..;:e:;..v:;..e=r=s-=e;.......:

! "SULT PART 111 NOH.ESSBfTIAL VARIABLES FOR JOINT DIMENSIONS AND WELDING CURRENT SETTINGS.

11 1

1

-~-. TEST RESULTS ii .f i l I I REDUCED SECTION TENSILE RESULTS ./ DIMENSIONS ULTIMATE ULTIMATE UNIT CHARAC SPECIMEN HO. AREA TOTAL WIDTH THICKNESS LOAD, LB. STRESS, PSI AN 9-V-l 1.434 .435 .625 42,000 67,200 Duct' 9-V-2 1.388 .437. .605 39,000 64, 800 Duct' I GUIDED BEND TEST TYPE RESULT TYPE -RESULT 4 Side Bends All OK Free Root OK ..,/-.,R'S NAME

w. H. Cave SOCIAL SECURITY No? 53 9832 WELDER'S SYMBOL

~VIRTUE OF THESE TESTS MEETS WELDER PERFORMANCE REQUIREMENTS. WE CERTIFY THAT THE STATEMENTS IN THIS RECORD ARE CORRECT AND iHAT THE TEST WELDS WERE PREPARED, WELDED ACCORDANCE WITH THE REQUIREMENTS OF SECTION IX OF THE ASME CODE. SIGNED CHICAGO BRIDGE & IRON COMPANY DATE Dec .LABORATORY. TEST NO. __ _.9;._-.....;V.._ ____ _ REMARK~~~~-~-~~.ui.~1¥-~~UJ..lu...c~~=-..i-UJL.t:;..LJ.."'"1..--'-~~_.._~~u...s;:;.u.___g_.J..._-=-J..J.L..:...c..~~-- .,. ' ( ~ '*.

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PRODUCTION DEPARTMENT - METALLURGICAL CLAIRTON STEEL S -~ R_dfc_o_6 *. FILE HO.

  • ~ELS

~---------~S~E~PT.l..!-.~2~7 ___ 19 ___ 6~8;....__

>ecification BOP STEEL ASTM A-36-67 BRIDGE AND IRON CO GREENVILLE PA Load Tally or Shipping Notice------~~0>.~..--------- SIZE Heal ~ No. c Mn ORDERED J 311 C-10 / A6J81~6

4. 1 H

.23 .51 II II / '\\r>>n7;~ r 0.JU II .22

  • l.6 II II

-~ SYL Vl\\!IL\\ l SS GHE!~Y rn to before me this ~p., 19 68 ¥otary Public I ires* L wARD.. Notary p ublic ar um er C N b ,p ~. S~ c~t-: ANALYSIS

  • 1 Test Piece Yield Point St re~

lbs. per Cut From lbs. pe"h p s sq. in/ sq. in/ / ~ I .008.027 .180 11 CH 4l*L*70 66330 II 45100 67760

  • /

/

  • 01 2.022

.170 11 *c;-i 4L*780 66770 II 45400 67L*10 1:8UI I~ I DO SL Et be in dul rdi sworn ac t I 9 Y CO ng 0 law, deposes and says that the figures set forth above are . correct, as contained in the records of the company. u E~ In 8 ' 10 / / 25.6 23.n 25.0 25.6 Red. of Bend Area /st J ml - OK OK OK ) 'I L*...,,f /( /J-,.~<~ ~ Frtd C. Hart, ChJef Metallara_ln v'-c" I 7 B7 1//rj/< 7

02.000.0572 " (t 1 I A* *A *-- A.__._. """"A '-A '°-'I~~ I I~** PRODUC

  • H DEPARTMENT - METALLURGICAL

.ENO. __ _ ~I~R~TO~N~ST~E~E~L~_WORKS Test Report of __ C_li!\\_r*_IN_E_L_S _____________ . S FPT. Product Description/Specification BOP STEEL ASTf1 A-36-67

  • Load Tally or Shippi~g Notice

~ '~c Charged to __ c_H_rc_A_G_o_!3_R_r_o_G_E_A_1_m_r_R_ON_c_o __ G_RE_E_l*l_v_r_LL_E_._P_A _________ _ Shipped to

  • Customerr's Order No.

an~ Date 68-32Lr6U-7 9/10/60 SAME Mill Order No. LF-91945 Heat No. A6JCL*6 II

\\6387/.*

II STATE OF P ENNSYLV/\\IH1\\ COUNTY. OF ALLEGHENY SIZE ~ ORDERED 311 C-10

4. lH II II II I SS.
  • Subscribed an sworn to bef~re me this AJ]V) /_ ~y* 09PT. *,., 19 68

>£K._ .-~/,12,~tary Public >' Commi ion expires.*_------ 31 "'""'" u!AQD lIDlarv Public c Mn i / .23 .51 .22

  • l1-6 Car Number s<"'P

~v~. ~-1. ~ Test Piece Yield Point St re~ lbs. per Cut. From sq. in;* lbs~-~"!} sq. 1n. ANALYSIS p s }' ./ I .008.027

  • H30 11 CH 4l*L*70 66330 II 45100 67760*

o 1 70 II CH 4L*]80 66770 / / .012.022 . II lt-5400 67L*10 PAUi

  • r<. DOSLEY

, being duly sworn according. to law, deposes and says that the figures setforth above are. correct, as contained-in the records of the company~ ") /-;~.f /( &.*:>,; ...,re I 7 v E~ In 8 I<~/ ,I 25.6 23.3 25.0 25.6

.. --- --.,..-... ~-.ic--*~---*<:~-*~---... --- - - - -.-- M -----~,/jl:----- ~---**-- ;;;--;--- ~ - ;: -- ~. 0 -*~

  • ~ '.

REPORT OF MECHANICAL AND CHEMICAL TESTS t?ll<J 2 :Sr

  • . ~ BfriiLEHEM STEEL CORPORATION r--..

r ~ METALLU,RGICAL DEPARTMENT r ~MU"S OllDfll HO, 7-98U-16 013-2686 CH[CAGO BRIDGE & IRON CO BOX 610 GREENVILLE PA 16125 ASTH A36-69 10520 2 SWORN TEST REPORTS HEAT HO. 171C723,... 171C752-C751,,,,. J.' !C723..- 1 :r'1C.is2-j 181C751-HO. PIKES c 35 C3X4.l 20 C3X4* l 15 C3X4.l s .zo .60.014.025.05 .21 .59.011.021.05 .191... 59.. 013.01qll.osi Fut 40 40 40 Cu LENGTH Ni 104-35647-3/3 BETHLEHEM CHICAGO BRIDGE & IRON CO GREENVILLE PA YIRD W~IGHT POL"-.Y fr:t

  • 11480 44783 44704 45415 I\\'.

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,.* -"\\ 2IU'4i.g'.';:J~ CHICAGO BRIDGE & IRON COMPANY PURCHASE ORDER HO. MUST APPEAR OH~LI/~.~ lt'fVOICES, PACKAGES AND SHIPPING P~P,l!~~Stlt

  • ~v PU RCH-AS e-ORDER MERCER COUNTY GREENVILLE, PENNSYLVANIA 1612!5*

PURCHASE ORDER NO. 3T OF __ JIMm Steel Corporation Jateway Center >Urgh, Pennsylvania -15222 _J TIONS: Ship to above address unless noted below: Routing: Our ~ruck. COLLECT PREPAID MILL: NO. SHIPPING NOTICES: 0 NO. TEST REPORTS: NO. MONEY INVOICES: NO. BILLS OF LADING: VENDOR ORDER NO.: INSPECTION BY ,-S-T_R_U_C_T-IO_N_S_;----------------i Ml LL UNLESS PENN:.TAX;<~f" EXEMPT-.* OTHERWISE NOTED S01EDULED ROLLING: SHIPPING PROMISE: CONFIRMING LENGTH OESCRIPTIO"N FEET EACH Channels - 3" ft 4.l.I 0 1'7.* 6 8o do 32 0 131.2 do 0 ll.ll.8 20 do 8 113~4 .8 do 33 0 l:-'15 n 4o do 0 Boll August Production - Beth1ehem

NLR-N90016 ATTACHMENT 4

~ OE-AP.ZZ-00021 PSE 8! G ~ fi(Aq ft,JFORf\\JO /1 Tu CXJfD-.W'I' ,,iv r~ j ON ON~ y ~~ 6 b, 0 PS~G ~ 2:.: µ, ~*: J . -,.",1'*.:~ """'".. aun NudMr Oeoutment m a*ma anaacm . caLCUL&!'%Oll CO'ID *-~ (('.::::, 0 - olf-1 7 i OJ' L CALCULATION REVISION 0 CP NUMBER REVISION HISTORY SEE SHEET 2 (INTERIM or FINAL) INTERIM

  • Proposed Plant FOR REVISION Chane;*

FINAL

  • Support* Instal-HISTORY led Condition FU'1'UR! CCNJ'IJUIATION REQUIU:D:

.NO --=--- ORIGINATOR (Initial ' Data) SEE SHEET 2 REVIEWER (Inii;ial ' Dat*) SEE SHEET 2 Public servic* SUPERVISOR APPROVAL <t--~ ~ V \\a\\ \\"i\\ i °\\ (Initial ' D*te) COVER SHUT 2 (Number Pac;**) CALCUI.ATIONS (Number P&CJU) J 0 (Excludinq Attac:bMnU) ATTACHMDTS I /:Z (Numbe~/Total Paqu) TOTAL PAGES I 4-- IMPORTAN'l' TO SA1'E'l'Y. C[] YU D NO It Y**, da*iqn veritic:a~ion requirad per DE-AP.ZZ*OOlO(Q) (Oasiqn V*ritication, Ref. 8.3) Paqa 1 Of 2 Rev. o I I I

TITLE IDNO * . 1:7 -f--i **-.. :_..-- cO s 0-*~**+/r;' SHEET . 0 PS~G 1'::Jr.r"*55l< (" e (*~It./ :..,vu' r ',-f-~ *f r: ; *,. ' ; REFERENCE .....,.,~.

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20F2 ORIGINATOR -JQ L L L OATI CALCULATION PD / CONTINUATION SHEET UVIEW!I. ./ DATE RF.ftHKES FACILITY' CODE: RE -1 CATEmRY CODE: z~ I SAFETY CIA5S : (iQ. I SYSTEM CODE: RC04: IEUV= IDRAWI~: aIBER: SALEM*ORIGINAL CAf..J::.. B<Xl< oo. I PAGE 005. CALCULATION FILE: TITLE/DESCRIPTION: .1:f _;:;_-;_;;..*. '." r,,..-y! ~::-,".""_:_ {:. -

-~-:

REVISIC>>i HIS'ltmY (continued) RE.V. DESCRIPI'ION. 0 REVISION ONLY ADDS CALCULATION NUMBERS AND SHEET NUMBERS TO EXISTING CALCULATION PER DE-AP.ZZ-0002(Q) AND AP.PRO PR IA TE CALCULATION CROSS-REFERENCING. REVISION DOES NOT ADDRESS CALC. ADEQUACY OR PERFORM DESIGN VERIFICATION.

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5)-J, 3 6S0-04 J 7 Were the test acceptance criteria to equal or exceed the stresses com-puted under the factored loadings, then destruction of some elements would result.

It is not necess~ry to test up to design stresses to verify the struc-tural integrity of the containment. Prediction and verification of deformation patterns, using the same design and analysis procedures for both design and test conditions, will serve to verify the design. It has been described in Section 5.2.4 and in Table 5.2-9 that the tensile stresses in the liner plate during the structural acceptance test will be greater than those which would occur under the accident condition. The reason for this is that there is no temperature rise associated with the test condition. Compressive stresses are created by the high temperatures associated with an accident condition, which overcome the tension in the liner. The stresses in the reinforcing bars will be lower during the test condition than the values calculated for the accident condition. With regard to the liner, the largest number and length of seams occurs in the cylinder and dome and, therefore, the greatest potential for leak.age. The test condition yields tensile stresses in the dome and most of the cylinder that are higher than those of the design condition. The exception is the lower cylinder wall, where design condition ten-sile stresses are higher. With the exception of this area, the test will place a greater stress condition on the potential leakage paths than any of the design conditions; The acceptance criteria requires demonstration that the overall struc-ture exhibits elastic behavior throughout the test range. Inelastic behavior at localized stress concentrations will be considered accep-table. Greatest agreement between the computed strains and those actually observed is anticipated in the shell of the containment. {/ Greater disparity between observed and calculated strains is contemplated SNGS-FSAR Units 1&2 Amendment 22

PUBLIC SERVICE ELECTRIC ANO GAS COMPANY SH,+ REFER TO ~Ei~f~9'_ arJJtr t ~ f/;. J

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00001 Additional Information Requested April 9, 1968 h-Z\\d) AT TAC tt 5S0*0117 QUESTION 11. 2 (d) With respect to the design of penetrations, describe:

d.

Criteria for concrete thennal protection at penetrations; include the temperature rise permitted to exist in the concrete under operating con-ditions and the,(time dependent) effect that loss of thermal protection would have on the containment's structural and leak-tightness characteristics. ANSWER We are placing two coolers in each penetration, (see Figure 5.l-19a of Section 5) with individual connections to each of two (2) independent supply and two (2) return headers in accordance with United States Navy Bureau of Ships General Sp~cification (for combat vessels). The containment penetration sleeve will be designed for 150 F maximum at full load operation. Under accident conditions a maximum of 250 F is con-sidered with the concrete at 120 F. Axial growth of the containment sleeve at 250 F between anchor and liner attachments is O. 0155 inches as shown by the formula from Rourk- "Formulas for Stress and Strain," Page 194, Case 20, 2nd Edition 1943 where: W = 2,238 lbs S = 2,672 psi For complete loss of coolant and assuming a long time at maximum main steam temperature of 550 F the axial growth of the containment sleeve would be 0.056 inches where W = 8,114 lbs S = 9,686 psi AMENDMENT 6

Additional Information Requested_April 9, 1968 ll.2(d) ~ In this case the concrete irrunediately surrounding the containment sleeve may reach a maximl..ll!l temperature of 300 F without any detrimental effect on the concrete. Therefore the deflection will not reach the maximum 3hown at 550 F which is based on a 120 F concrete temperature. Under accident conditions where the containment may reach an internal pressure of 47 psig the forces of pressure and thermal stresses are in opposition and will produce a net reduced total force. AMENDMENT 6 Atmlt f 00002 sso ~0411 )

NLR-N90016 ATTACHMENT 5}}

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