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| {{#Wiki_filter:Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 205.992.5000 SOUTHERN A. COMPANY December 19, 2008 Energy to Serve Your Worid SM Docket No.: 50-321 NL':08-1781 U. S. Nuclear Regulatory Commission ATrN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant -Unit 1 Certified Material Test Report (CMTR) for CRD System Return Nozzle (N-9) Cap Ladies and Gentlemen: | | {{#Wiki_filter:Southern Nuclear Operating Company, Inc. |
| On February 26, 2008 Southern Nuclear Operating Company (SNC) requested an alternative pursuant to 10 CFR 50.55a(a)(3)(i) to perform a dissimilar metal full structural weld overlay on weld 1 C11-1 CRD-3-R-18A. | | 40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 205.992.5000 SOUTHERN COMPANY A. |
| This alternative was subsequently granted. During a related telephone conversation, the NRC requested a copy of the CMTR for CRD system return nozzle (N-9) cap, and it is hereby included in the enclosure to this letter. This letter contains no NRC commitments. | | December 19, 2008 Energy to Serve Your Worid SM Docket No.: 50-321 NL':08-1781 U. S. Nuclear Regulatory Commission ATrN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant - Unit 1 Certified Material Test Report (CMTR) for CRD System Return Nozzle (N-9) Cap Ladies and Gentlemen: |
| If you have any questions, please advise. Sincerely, JYLJ-- M. J. Ajluni Manager, Nuclear Licensing MJAlMNW/daj | | On February 26, 2008 Southern Nuclear Operating Company (SNC) requested an alternative pursuant to 10 CFR 50.55a(a)(3)(i) to perform a dissimilar metal full structural weld overlay on weld 1C11-1 CRD-3-R-18A. This alternative was subsequently granted. |
| | During a related telephone conversation, the NRC requested a copy of the CMTR for CRD system return nozzle (N-9) cap, and it is hereby included in the enclosure to this letter. |
| | This letter contains no NRC commitments. If you have any questions, please advise. |
| | Sincerely, JYLJ-- ~ |
| | M. J. Ajluni |
| | ¥- |
| | Manager, Nuclear Licensing MJAlMNW/daj |
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| ==Enclosure:== | | ==Enclosure:== |
| | Certified Material Test Report (CMTR) for CRD System Return Nozzle (N-9) Cap |
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| Certified Material Test Report (CMTR) for CRD System Return Nozzle (N-9) Cap U. S. Nuclear Regulatory Commission NL-08-1781 Page 2 Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. D. R. Madison, Vice President
| | U. S. Nuclear Regulatory Commission NL-08-1781 Page 2 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. D. R. Madison, Vice President - Hatch Mr. D. H. Jones, Vice President - Engineering RTYPE: CHA02.004 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Hatch Mr. J. A. Hickey, Senior Resident Inspector - Hatch |
| -Hatch Mr. D. H. Jones, Vice President | |
| -Engineering RTYPE: CHA02.004 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. R. E. Martin, NRR Project Manager -Hatch Mr. J. A. Hickey, Senior Resident Inspector | |
| -Hatch Edwin I. Hatch Nuclear Plant -Unit Certified Material Test Report (CMTR) CRD System Return Nozzle (N-9) | |
| .', <CONTENTS Q.A. RECORDS FOR : HATCH 1 EQUIP : FORGINGS MPL NO. 311-AOIH 5/-; AJ403-01-C2 ITEl-t 1 G.E.. P.O. :\0. 205 AJ 403 Rev. 04
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| : COULTEa STEEL & tORGE
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| | Edwin I. Hatch Nuclear Plant - Unit 1 Enclosure Certified Material Test Report (CMTR) for CRD System Return Nozzle (N-9) Cap |
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| CERTIF!CATE | | CONTENTS .', < |
| : 2. I:-=CO 3. | | Q.A. RECORDS FOR : HATCH 1 EQUIP : FORGINGS MPL NO. 311-AOIH 5/-; AJ403-01-C2 ITEl-t 1 G.E.. P.O. :\0. 205 AJ 403 Rev. 04 S~PPLIER : COULTEa STEEL & tORGE COXP~\~ |
| | CO~~7ER ST~E~ & :G~GE COXPA.\~ CERTIF!CATE |
| | : 2. I:-=CO |
| | : 3. COX~~ ~~:AASOX:C :XS?ECTIOS CERTIFICATE |
| | : 4. COX~v. LIQUID PE~E~'7 I~SPECTIO~ CERTIFICATE |
| | : 5. COUL7ER S7EEL & FOaGE CO~A.\~ HEAT TREAT CHARTS |
| | : 6. P.Q.C. ~O. s 903 j;, ,.z |
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| : 4. | | 'GMII'V _ |
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| | 18 |
| | '."r&.~ -ArIMll 101 la.l!<<mm'l k'J!l1iiL |
| | .-, CEQ1W, ELlCTIllC COMPANY 652164 NED IHY 175 Cu~tD.~ A.euue SaD Jo**, Callforala 9511' IITS "ISLI 04 SAVANNAH AIRPORT HATCH \. |
| | GEORGIA POWER COMPANY |
| | 'Edwin I'Hatch Nuclear Plant 41.S. Hi9hway 1 GeorQ'ia 31513' D£8CRlPTIOH 1 1 137e'U2 '1 |
| | : 51. AJ40S-01-02 |
| | . . . . . . AND PACUOING MCIl_"8'1S |
| | '~taa ...Dlq ,roc. csr ,: |
| | 009, b. 2(19 JAIl '77) J .0. JH,...oa-Iuye M/e 70' 0, ?'2!''''"' :£ Tid' .'....... |
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| CERTIFICATE
| | ' .,'{,. . '.,"., '."" |
| : 5. COUL7ER S7EEL & FOaGE HEAT TREAT CHARTS 6. P.Q.C. s 903 "-,,,,,,' | | ** h |
| .. ,;;, j;, ,.z , } .. ... ./c .. ... , " ..;. | | :;~~if.*,~&~~~r):~1:.l!f~<~~~"* |
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| :£ Tid' .'....... 18 ....... IHY J .0. JH,...oa-Iuye M/e 70' .,.....,....... 652164 -ArIMll k'J!l1iiL 101 D£8CRlPTIOH 137e'U2 '1 04 la.l!<<mm'l 51. AJ40S-01-02 1 'GMII'V _
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| * i*.. ' .... 1 SAVANNAH AIRPORT HATCH \. GEORGIA POWER COMPANY 'Edwin I'Hatch Nuclear Plant 41.S. Hi9hway 1 GeorQ'ia 31513' ......AND PACUOING MCIl_"8'1S | | !f |
| ...Dlq ,roc. csr ,: 009, b. 2(19 JAIl '77) .-, CEQ1W, ELlCTIllC COMPANY NED 175 A.euue SaD Jo**, Callforala 9511' IITS "ISLI
| | '1"1 "'l: 11 f;' |
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| | * ".~ * . ~~ t 'I .. '., .. ~ ** .., |
| | - ' . ,* HUNTlNOTO LOYS, INC. |
| | I ' ._ K, '. . HUNTINGTON. VlE:ST VInQINIA 25720 .***** _', _ |
| | I *. :, c'.:'( * "0, ~CotA.OI OIlOCJl NO. . ., t"ARIl 0Nll1I NO, '" .. '.''''.''''........ **,..,.;1..* , ,It' 9~' |
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| | ',' ~vJ'" Ltlll tl( I]Nr.l. ,,\LIIIY l.00 11.0000 SlI X r.DM 1101 "'IN Ff<C UIIAL SU r~uuclI la,D |
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| | * Ih'UUL,1.U:l1.--l.60.::uJo-"'o ...... . _. __..... __ |
| | ,r, :1. SAE AMS-:;1065tt A~M[ S~*166 SECTION 2 r'Af'(T If '974 ron 11;:4 ALL U'~" ADDEND" T1mlJUCU SliMMER' Y75 HARK INC WAIVED INCO J2u fi(V [I _." I ..:::. |
| | ., J .rUAL AND DIM~NSIONAL [XAMINATION - OK |
| | (/fARCE |
| | / |
| | ~H~ Off NCR |
| | :T CASTLE I. CO SHIP A H C"STLE I. CO |
| | '900 THIRD Sf '900 HURD Sf SAN FRANCISCO CAL 94107 SAN FRANCISCO CAL9~I07 |
| | ....~. |
| | CHEMICAL ANALYSIS HEAT -141 C HH FE S SI CU NIt,a CR Nxa"8' 0.07 0.21 9.18 .002 G.23 0.36 75.05 '4.90 W;cJ~OIl 0.01 0.'6 8.40 .002 G.'9 0.30 75.60 15.26 |
| | . itEM IHCOT PC LOT pes SHIPPED H>>C8"8'S . . 3 '.1::!,3 F,e40 3 Nxa485 4 ,,2,) FH,4, 3'" |
| | r41(U~Oj) |
| | NXU'OU J |
| | 4 1-' |
| | '1213 It -2,3 fhJ42* |
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| | "'~ur.a-. ftDL. & I'CmG8 CQIIPAlIY DATE 8!'abruUy U77 1494 - 67th street ~~.. 38742 CXlNTRIlCTOA po. 205 AJ403. Rev* ._ 04 Emeryville, caUfornia |
| -', .* 'I-'1"1 11 "'l: f;' *. t 'I .. '., .. ** .., ' . ,
| | ( TEST DATA) |
| * HUNTlNOTO LOYS, INC.! f'._ K, '. . HUNTINGTON.
| | '. "} . IX STRAIGHT IlEAM II ANGLE IlEAM 45 OEGllEES |
| VlE:ST VInQINIA 25720 .***** _', _ *. :, c'.:'( * "0, OIlOCJl NO. . ., t"ARIl 0Nll1I NO, '" .. '.''''.''''..................., **,..,.;1..*, ,It' t r,1JI14] -54544 'lI ' *, , ,****** c', , ... *' "".", Of * -....-...tfl'AI"D _. . ..=:-
| | :1ff.~ TElT ITAlClo\RO ( I'UEIWIIC£ TEST STAICIAIID ) |
| | ASHE B & PV CODE sec. II & III (74) |
| | ~~ B.R. .020* Cl.aa. 1 & Addenda thru Winter 1975 t-l~rM.uYt 7~ PSB (14DB) |
| | DCO 600 60-m & on V 1l1otch INCO 600 SA-388. Para. l'm-2542, Procedure CSF-U'l'-OO7 |
| | * Rev. 0 (23 Feb. 1976). |
| | ~~ |
| | ..,,~.. ~' |
| | ~ ~ |
| | "~ ... (~~ SWlCH UNIT ) |
| | , SlNMAI<£ 24781 AlI 24181 All |
| | ~ .75 .15 QsnU.-NT ) |
| | . IATIRAL NlEll .5 .5- MAKE Sperry couPlANT Water |
| | ~1'IIlEOUENCY 1 MBz 1 MHZ r.tOOEl. OM 721 MEfH()() ImIDeraion MATUIAl SU S13 s" 2229-1 SENSlTMTY 75 , F\A., |
| | IIZEISHAPE 1.0- RD 1.0* RD FR£65i~y 1 MHZ SOlEE" HEIGM ttl. iWbd AtP6ift ~ a"UU9ER INSPfcfOfi .... |
| | . 22497 C-1915 David Lee, Level II ACCEPTED AE.lECTEO 131C5632P1 End cap PorgiDga 1 o Item 1110. 1 5.41- Major 00. 6.22- Major Len9tb S/'S AJ403-01-02 Heat No. JlX8508 surface piDiab: 250 RMS Alloy: Inoooel 600 |
|
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| | , , 1Iio.lClU1H 3'''' ITNIT * * 'fIL8ItOlI: 14'11 ....... |
| ..
| | lAM - 67th stnet EmexyviU., cal oj fornia |
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| | ( i&'ECfiON UEtHOO ) |
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| | o IoUoGNETlC PARTICLE o EcoY CUAAENT ASMB B & PV' CODB sec. II & IIX (74) |
| "., i 14 'L,it.):.>>
| | C1as8 1 & Addenda thru Winter 1975 C T_ES_T_D_A_TA_ _) Para. NB-2546. Procedure LP:t-4l00l, Rev. 18 (20 February 1976). |
| PSi',UiY"'1'4 i.t,:.ucp:
| | ( PENETRANT MATERIALS) 1"II'l! Tracer-Tech P133 water Acetone 0-310 Lot 10398 |
| * tt': .:- ...:.:.:,: | | ' . . =... . .tOt |
| 'Wed* ;t:-.:.::.:
| | * 0.006% .lPPM |
| ..... 1 ',' Ltlll tl( I]Nr.l. ,,\LIIIY l.00 1101 "'IN Ff<C UIIAL SU 11.0000 SlI X r.DM :
| | .~ 0.009% *!PPM |
| * Ih'UUL,1.U:l1.--l.60.::uJo-"'o
| | ** IM5iCl "ROOM NUilOiilA 1 |
| ...... . _. __..... ,r, :1. SAE AMS-:;1065tt SECTION 2 r'Af'(T If '974 ron 11;:4 ADDEND" T1mlJUCU SliMMER' Y75 HARK INC WAIVED INCO J2u fi(V [I ..:::. ., J .rUAL AND
| | 22497 137C5632Pl End cap Forging. |
| [XAMINATION
| | Iba Do. 1. |
| -OK (/fARCE Off NCR :T CASTLE I. CO A H C"STLE I. CO '900 THIRD Sf '900 HURD Sf SAN FRANCISCO CAL 94107 SAN FRANCISCO
| | JOd~9ER C-1934 iliSPEcfCiA David Lee, Level II 1 0 |
| ....CHEMICAL HEAT -141 C HH FE S SI CU NIt,a Nxa"8' 0.07 0.21 9.18 .002 G.23 0.36 75.05 0.01 0.'6 8.40 .002 G.'9 0.30 75.60 . itEM IHCOT PC LOT pes H>>C8"8'S . . 3 '.1::!,3 F,e40 Nxa485 4 ,,2,) FH,4, ;'
| | -:.,' 5.41. - Major 00, 6.22- Major LeDqth s/5 AJ403-01-o2 Beat Ilb. 1JX8508 surface Finiah: 250 RMS A.1.1oy: Inconel 600 |
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| | ~~ti '.,., ... |
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| | ,:'f')' . . ~Jf.~ /\ |
| * DATE 8!'abruUy U77 .. 38742 CXlNTRIlCTOA 04 po. 205 AJ403. Rev*._ " '...
| | ~, ~~ ~'\. |
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| | l:,,":~~,=~=-::-:=~=-:::::':":':"=- ~_::_~.:..\: / |
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| | ":.." ,ee:M* FOR fLECTl(lH OR AEIiWlKS |
| DCO 600
| | . " ~ ". |
| .. ... , SlNMAI<£ 24781 AlI . IATIRAL NlEll 1 MBz MATUIAl SU IIZEISHAPE 1.0-RD ( I'UEIWIIC£ TEST STAICIAIID ) ASHE B & PV CODE sec. II & III (74).020* Cl.aa. 1 & Addenda thru Winter 1975 60-m & on V 1l1otch SA-388. Para. l'm-2542, Procedure INCO 600 CSF-U'l'-OO7
| | ea- :,", Iaz'U 'Mr. in.spected and evaluated in ~c:cordance with LPI-41001, Rev. 18. |
| * Rev. 0 (23 Feb. 1976). SWlCH UNIT ) 24181 All QsnU.-NT ).5-MAKE Sperry couPlANT Water 1 MHZ r.tOOEl. OM 721 MEfH()() ImIDeraion S13 s" 2229-1 SENSlTMTY 75 , F\A., 1.0* RD 1 MHZ SOlEE" iWbd AtP6ift a"UU9ER INSPfcfOfi
| | rejectab1e indicationa were foWld* |
| ....ttl.22497 C-1915 David Lee, Level II. ACCEPTED AE.lECTEO End cap PorgiDga 1 o Item 1110. 1 5.41-Major 00. 6.22-Major Len9tb S/'S AJ403-01-02 Heat No. JlX8508 surface piDiab: 250 RMS Alloy: Inoooel 600 .... 131C5632P1
| | It |
| .,
| |
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| |
| 14'11 .......* ASMB B & PV' CODB sec. II & IIX (74) C1as8 1 & Addenda thru Winter 1975 *, , 1Iio.lClU1H 3''''ITNIT o IoUoGNETlC PARTICLE o EcoY CUAAENT lAM -67th stnet EmexyviU., cal oj fornia ( i&'ECfiON UEtHOO ) C T_ES_T_D_A_TA
| |
| __Para. NB-2546. Procedure LP:t-4l00l, Rev. 18 (20 February 1976). ( PENETRANT MATERIALS) 1"II'l! Tracer-Tech P133 water ..tOt
| |
| * 0-310 Lot '... =... 0.006% .lPPM . 0.009% *!PPM ... Beat Ilb. 1JX8508 surface Finiah: 250 RMS A.1.1oy: Inconel 600 ** 1 137C5632Pl IM5iCl"ROOM NUilOiilA iliSPEcfCiA 22497 C-1934 David Lee, Level II End cap Forging. 1 0 Iba Do. 1. 5.41.-Major 00, 6.22-Major LeDqth-:.,' 's/5 AJ403-01-o2 '. ,., ... ,:'f')' ..
| |
| /\
| |
| / ":.." , ee:M* FOR fLECTl(lH OR AEIiWlKS ." ". :,", Iaz'U 'Mr. in.spected and evaluated in with LPI-41001, Rev. 18.ea-rejectab1e indicationa were foWld* It .'< | |
| 1/28/77 General Electric COMpany P.O.' 205 AJ 40) P.ev. 04 CSF No. 38742 1n1;:0::e1 600 HT TRT LOT
| |
| * 38798A HT* KX 8508 HT: Anneal 1625°F !25°F, 1 Hr ., AC.. furnace No. 7 Operator:
| |
| Kevln/Don Shift: Days
| |
|
| |
|
| ... I:' ."" ..*
| | 1/28/77 General Electric COMpany P.O.' 205 AJ 40) P.ev. 04 CSF ~ot No. 38742 |
| .... ... | | ~ldterial: 1n1;:0::e1 600 HT TRT LOT |
| * J';' 'J**.* PQC NO. S | | * 38798A HT |
| :..;..,.'.."-'<. ,,'IERAl. | | * KX 8508 HT: Anneal 1625°F !25°F, 1 Hr furnace No. 7 |
| ELECTRIC .c..**
| | ., A..C Operator: Kevln/Don Shift: Days |
| ENERGY REMARKS/EOUIPMENT SERIAL NUMBERS; QUANTITY 1 ORGA"IIATION: | | |
| Coulter Steel & Forge Co. DATE
| | -"~"'; ... !(.~( I : ' ."" ..*~.,..~.... |
| __/'_"--.:.t?L.:...?.L7
| | . . |
| _
| | * tl.~ .to(.~ J';' 'J**.* |
| _ DATE:
| | '~~)3~ |
| __
| | if:~' : ..; . . , . '.. "- '<. |
| __ FORCINC ....v PUIllCMA$1[
| | ,,'IERAl. ELECTRIC PQC NO. S |
| OlilOElit ITe,..!S. | | .c..** |
| NO. 4 1 SUPPLIER'S CERTIFICATION 4 | | tI~UCLEAR ENERGY DIVISION CT UAUTY CERTIFICATI FORCINC |
| TITLE: Quality Control 51'S AJ403-01-02 THIS IS TO CERTifY THA":' THE PRODUCTS IDENTIFIED HE.REIN HAVe BEEN MANUFACTURED UNDER A CONTROLLED QUALITY ASSURANCE PROGRAM AND ARE IN CONFORMANCE WITH THE CUo\LITV REOUIREMENTS INCLUDING APPLICABLE CODes, AROS AND SPECIFtCATlO-"S AS IDENTIFIEO IN THE ABOVE-REFERENCED OOCUME.P<oITS; UNLESS NOTED BELOW. ANY SUPPORTING BE FORWARDED OR RETAINED IN ACCORDANce WITH PU'lCHASE OROERPEOUIREMENTS.
| | ....v PUIllCMA$1[ OlilOElit ITe,..!S. NO. QUANTITY 205 AJ403 4 1 1 SUPPLIER'S CERTIFICATION THIS IS TO CERTifY THA":' THE PRODUCTS IDENTIFIED HE.REIN HAVe BEEN MANUFACTURED UNDER A CONTROLLED QUALITY ASSURANCE PROGRAM AND ARE IN CONFORMANCE WITH THE PROCURE\~ENT CUo\LITV REOUIREMENTS INCLUDING APPLICABLE CODes, STAND AROS AND SPECIFtCATlO-"S AS IDENTIFIEO IN THE ABOVE-REFERENCED OOCUME.P<oITS; UNLESS NOTED BELOW. ANY SUPPORTING DOCU~eNTATtDNWILL BE FORWARDED OR RETAINED IN ACCORDANce WITH PU'lCHASE OROERPEOUIREMENTS. |
| GE QUALITY ASSURANCE CERTIFICATION NONCONFORMANCES FROM PROCUREMENTOUALITV REQUIREMENTS. | | SIGNEO;~ 4 ?"~-<: DATE: _-..I-C1"",II~Y_ _/"-C'~-.L/...::'_Z,-L.Z __ |
| THIS IS TO CERTIFY THA'l' eVIDENCE SUPPORTING T"'E ABove SUPPLle'l'S CERTIFICATION STATEME"lT HAS SEEN REvle..';EO AND PRODUCT NONCQMFOR\4ANCeS FqOM PROCURE* MENT QUALITY RECUIRE\1E!'lTS HAVE BEEN FOUND UNLESS P<oIOTED BELOW, TITlE: G QA REPReSENTATIVE This PQC changed because of clerical error, original equipment shipped 3/18117. 205 AJ403 CT UAUTY CERTIFICATI}} | | TITLE: Quality Control ~.ana8er ORGA"IIATION: Coulter Steel & Forge Co. |
| | GE QUALITY ASSURANCE CERTIFICATION THIS IS TO CERTIFY THA'l' eVIDENCE SUPPORTING T"'E ABove SUPPLle'l'S CERTIFICATION STATEME"lT HAS SEEN REvle..';EO AND ~O PRODUCT NONCQMFOR\4ANCeS FqOM PROCURE* |
| | MENT QUALITY RECUIRE\1E!'lTS HAVE BEEN FOUND UNLESS P<oIOTED BELOW, SIG.,o,~j DATE :_",2&':':"~~;:J. _ _/'_"--.:.t?L.:...?.L7 _ |
| | TITlE: G QA REPReSENTATIVE O~GANIZATION:_..;B\IRP==D _ |
| | NONCONFORMANCES FROM PROCUREMENTOUALITV REQUIREMENTS. |
| | REMARKS/EOUIPMENT SERIAL NUMBERS; 51'S AJ403-01-02 This PQC changed because of clerical error, original equipment shipped 3/18117.}} |
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MONTHYEARNL-24-0014, Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical.2024-01-30030 January 2024 Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical. NL-23-0889, Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems2023-12-0606 December 2023 Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems NL-23-0879, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0841, Update to Notice of Intent to Pursue Subsequent License Renewal2023-11-20020 November 2023 Update to Notice of Intent to Pursue Subsequent License Renewal NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0422, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R272023-05-30030 May 2023 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R27 NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-23-0179, National Pollutant Discharge Elimination System (NPDES) Permit Renewal2023-03-13013 March 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal NL-23-0101, Cycle 28 Core Operating Limits Report Version 12023-02-23023 February 2023 Cycle 28 Core Operating Limits Report Version 1 NL-23-0003, Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 12023-01-20020 January 2023 Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1 NL-23-0069, Correction of Technical Specification Omission and Typographical Error2023-01-20020 January 2023 Correction of Technical Specification Omission and Typographical Error NL-22-0316, Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable2022-11-30030 November 2022 Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable NL-22-0850, Supplement to License Amendment Request to Revise the NFPA 805 Fire Protection Program2022-11-18018 November 2022 Supplement to License Amendment Request to Revise the NFPA 805 Fire Protection Program NL-22-0832, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF .2022-10-27027 October 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF . NL-22-0800, Supplement to Authorized Relief Request HNP-ISI-RR-05-022022-10-27027 October 2022 Supplement to Authorized Relief Request HNP-ISI-RR-05-02 NL-22-0801, Response to Request for Additional Information Regarding: Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of .2022-10-14014 October 2022 Response to Request for Additional Information Regarding: Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of . NL-22-0757, Units 1 & 2, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-09-30030 September 2022 Units 1 & 2, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NL-22-0687, Notice of Intent to Pursue Subsequent License Renewal for Hatch Units 1 & 22022-08-31031 August 2022 Notice of Intent to Pursue Subsequent License Renewal for Hatch Units 1 & 2 NL-22-0406, Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes2022-08-19019 August 2022 Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes NL-22-0650, Units 1 and 2 - Response to Request for Confirmation of Information Regarding License Amendment Request to Revise the NFPA 805 Fire Protection Program2022-08-19019 August 2022 Units 1 and 2 - Response to Request for Confirmation of Information Regarding License Amendment Request to Revise the NFPA 805 Fire Protection Program NL-22-0590, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Exten2022-08-18018 August 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Exten NL-22-0672, Registration of Spent Fuel Cask Use2022-08-17017 August 2022 Registration of Spent Fuel Cask Use NL-22-0564, and Vogtle Electric Generating Plant, Registration of Spent Fuel Cask Use2022-07-21021 July 2022 and Vogtle Electric Generating Plant, Registration of Spent Fuel Cask Use NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 NL-22-0499, Registration of Spent Fuel Cask Use2022-06-27027 June 2022 Registration of Spent Fuel Cask Use NL-22-0362, Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update2022-06-0101 June 2022 Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update NL-22-0365, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1R302022-05-31031 May 2022 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1R30 NL-22-0335, Supplement to Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 And.2022-05-17017 May 2022 Supplement to Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 And. NL-22-0344, Annual Radiological Environmental Operating Reports for 20212022-05-10010 May 2022 Annual Radiological Environmental Operating Reports for 2021 NL-22-0315, Technical Specification 5.6.6 Post Accident Monitoring Instrumentation Report for Drywell Temperature Indicator Inoperable for Greater than 30 Days2022-05-0404 May 2022 Technical Specification 5.6.6 Post Accident Monitoring Instrumentation Report for Drywell Temperature Indicator Inoperable for Greater than 30 Days NL-22-0325, Withdrawal of Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable2022-05-0303 May 2022 Withdrawal of Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable NL-22-0283, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf.2022-04-29029 April 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. NL-22-0271, Changes to the Physical Security Plan2022-04-19019 April 2022 Changes to the Physical Security Plan NL-22-0240, SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations2022-03-31031 March 2022 SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations NL-21-0918, License Amendment Request to Revise the NFPA 805 Fire Protection Program. with Attachments 3 to 52022-03-31031 March 2022 License Amendment Request to Revise the NFPA 805 Fire Protection Program. with Attachments 3 to 5 NL-22-0220, Units 1 and 2 - Nuclear Property Insurance Coverage as of April 1, 20222022-03-28028 March 2022 Units 1 and 2 - Nuclear Property Insurance Coverage as of April 1, 2022 NL-22-0221, Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2022-03-28028 March 2022 Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) 2024-01-30
[Table view] Category:Report
MONTHYEARML24005A1142024-01-0505 January 2024 Recommendation for 2023-301 Cr/Sim 3 (Emergency Depress the Reactor Using Main Steam Line Drains) NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 A000412, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2021-12-0202 December 2021 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-20-1295, 10 CFR 71.95 Report on Non-Compliance Involving Radwaste Cask 3-60B2020-12-14014 December 2020 10 CFR 71.95 Report on Non-Compliance Involving Radwaste Cask 3-60B ML20303A1782020-09-29029 September 2020 Submittal of Revision 38 to Updated Final Safety Analysis Report NL-19-0674, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-09-30030 September 2019 Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 NL-18-0863, CFR 50.55a Request for Alternative HNP-ISI-ALT-05-04 Implementation of BWRVIP Documents in Lieu of Certain 8-N-1 and 8-N-2 Examinations2018-06-21021 June 2018 CFR 50.55a Request for Alternative HNP-ISI-ALT-05-04 Implementation of BWRVIP Documents in Lieu of Certain 8-N-1 and 8-N-2 Examinations NL-18-0506, Failure to Observe the Certificate of Compliance Condition of the 8-120B Cask Pre-Shipment Leak Test2018-04-16016 April 2018 Failure to Observe the Certificate of Compliance Condition of the 8-120B Cask Pre-Shipment Leak Test NL-17-1713, Proposed Alternative GEN-ISI-ALT-2017-03, and HNP-ISI-ALT-05-07, Version 1.0 Service Water Evaluation for Code Case N-513-4 for Moderate Pressure, and for Higher Pressure2018-04-0606 April 2018 Proposed Alternative GEN-ISI-ALT-2017-03, and HNP-ISI-ALT-05-07, Version 1.0 Service Water Evaluation for Code Case N-513-4 for Moderate Pressure, and for Higher Pressure NL-18-0282, Enclosure 1: NFPA 805 LAR Transition Report for Edwin I. Hatch2018-04-0404 April 2018 Enclosure 1: NFPA 805 LAR Transition Report for Edwin I. Hatch NL-17-1916, Pressure and Temperature Limits Report2017-11-27027 November 2017 Pressure and Temperature Limits Report ML18012A0582017-10-31031 October 2017 NEDO-33884, Revision 0, Gnf Fecrai ATF Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-18-0026, NEDO-33884, Revision 0, Gnf Fecrai Atf Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1.2017-10-31031 October 2017 NEDO-33884, Revision 0, Gnf Fecrai Atf Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-18-0026, NEDO-33884, Revision 0, Gnf Fecrai ATF Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1.2017-10-31031 October 2017 NEDO-33884, Revision 0, Gnf Fecrai ATF Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-18-0026, NEDO-33883, Revision 0, Gnf Armor Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1.2017-09-30030 September 2017 NEDO-33883, Revision 0, Gnf Armor Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-17-1255, Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope High Frequency Confirmation Evaluation2017-08-22022 August 2017 Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope High Frequency Confirmation Evaluation NL-17-0955, Alternatives HNP-ISI-ALT-05-05 and HNP-ISI-ALT-05-062017-06-0505 June 2017 Alternatives HNP-ISI-ALT-05-05 and HNP-ISI-ALT-05-06 ML17069A2402017-04-13013 April 2017 Mitigating Strategies Assessment (CAC Nos. MF7932 and MF7933) - Redacted ML16356A0172016-12-16016 December 2016 Information Report for Lead Use Assemblies NL-16-2466, Fukushima Near-Term Task Force Recommendation 2.1 Expedited Seismic Evaluation Process Report Completion2016-12-15015 December 2016 Fukushima Near-Term Task Force Recommendation 2.1 Expedited Seismic Evaluation Process Report Completion NL-16-1136, Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope Low Frequency Evaluation2016-08-10010 August 2016 Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope Low Frequency Evaluation NL-16-0463, Submittal of 10 CFR 50.46 ECCS Evaluation Model, Annual Report for 2015 and Significant Change/Error Report2016-04-0101 April 2016 Submittal of 10 CFR 50.46 ECCS Evaluation Model, Annual Report for 2015 and Significant Change/Error Report NL-15-2010, E.I. Hatch - Submits 10 CFR 71.95 Report on Non-Conformance Involving Radwaste Cask 8-120B2015-11-0202 November 2015 E.I. Hatch - Submits 10 CFR 71.95 Report on Non-Conformance Involving Radwaste Cask 8-120B NL-15-1461, Submittal of 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B2015-08-21021 August 2015 Submittal of 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B ML15097A4242015-04-27027 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations Relating to Recommendation 2.1 of the NTTF Review ML15106A3102015-04-17017 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Draft Minimum Shift Staffing Analysis ML14335A1372015-03-25025 March 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) NL-14-1989, Expedited Seismic Evaluation Process Report - Fukushima Near-Term Task Force Recommendation 2.12014-12-30030 December 2014 Expedited Seismic Evaluation Process Report - Fukushima Near-Term Task Force Recommendation 2.1 NL-14-1876, Proposed Lnservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0, Conceptual Design Information Package2014-11-24024 November 2014 Proposed Lnservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0, Conceptual Design Information Package NL-14-1245, 10 CFR 26.719(c) Report: False Negative Results for a Blind Performance Test Sample2014-08-22022 August 2014 10 CFR 26.719(c) Report: False Negative Results for a Blind Performance Test Sample ML14223A7942014-07-31031 July 2014 Enclosure 2 - Non-Proprietary Gnf Report GNF-001N6296-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Hatch 2 Cycle 24 ML14155A4052014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident (TAC MF0234-35) ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14155A3612014-06-0606 June 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident NL-14-0343, Seismic Hazard and Screening Report for CEUS Sites2014-03-31031 March 2014 Seismic Hazard and Screening Report for CEUS Sites NL-14-0326, Units 1 and 2, Recommendation 2.1 Flood Hazard Reevaluation Report, Requested by NRC Letter Dated March 12, 20122014-03-0606 March 2014 Units 1 and 2, Recommendation 2.1 Flood Hazard Reevaluation Report, Requested by NRC Letter Dated March 12, 2012 ML13364A2022014-02-27027 February 2014 Interim Staff Evaluation Related to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14045A1472014-02-12012 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Edwin I. Hatch Nuclear Plant, Units 1 and 2, TAC Nos.: MF0712 and MF0713 NL-13-1898, 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B2013-08-30030 August 2013 10 CFR 71.95 Report on Potential Issues Involving Radwaste Cask 8-120B ML13193A3662013-08-0707 August 2013 Request for Concurrence on the Effects of the Edwin I. Hatch Nuclear Plant, Units 1 and 2 on the Federally-Listed Endangered Species Altamaha Spinymussel NL-13-0172, Southern Nuclear Operating Company'S Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (EA-12-051)2013-02-27027 February 2013 Southern Nuclear Operating Company'S Overall Integrated Plan in Response to 3/12/2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (EA-12-051) NL-13-0214, Southern Nuclear Operating Company'S Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events..2013-02-27027 February 2013 Southern Nuclear Operating Company'S Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events.. ML13115A4732013-01-31031 January 2013 GNF-0000-0079-7396NP, Rev. 6, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction Into the Hatch Nuclear Plant, March 2008 NL-13-0402, GNF-0000-0079-7396NP, Rev. 6, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction Into the Hatch Nuclear Plant, March 20082013-01-31031 January 2013 GNF-0000-0079-7396NP, Rev. 6, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction Into the Hatch Nuclear Plant, March 2008 ML12355A6332012-11-26026 November 2012 SNCH082-RPT-02, Ver. 1.0, Edwin I. Hatch, Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 3 of 11 ML12355A6312012-11-26026 November 2012 SNCH082-RPT-02, Ver. 1.0, Edwin I. Hatch, Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 2 of 11 ML12355A0592012-11-26026 November 2012 SNCH082-RPT-01, Ver. 1.0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 11 of 11 ML12355A0562012-11-26026 November 2012 SNCH082-RPT-01, Ver. 1.0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 8 of 11 ML12355A0552012-11-26026 November 2012 SNCH082-RPT-01, Ver. 1.0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 7 of 11 ML12355A0542012-11-26026 November 2012 SNCH082-RPT-01, Ver. 1.0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 6 of 11 2024-01-05
[Table view] Category:Technical
MONTHYEARNL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 A000412, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2021-12-0202 December 2021 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-20-1295, 10 CFR 71.95 Report on Non-Compliance Involving Radwaste Cask 3-60B2020-12-14014 December 2020 10 CFR 71.95 Report on Non-Compliance Involving Radwaste Cask 3-60B ML20303A1782020-09-29029 September 2020 Submittal of Revision 38 to Updated Final Safety Analysis Report NL-19-0674, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-09-30030 September 2019 Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 NL-18-0282, Enclosure 1: NFPA 805 LAR Transition Report for Edwin I. Hatch2018-04-0404 April 2018 Enclosure 1: NFPA 805 LAR Transition Report for Edwin I. Hatch NL-17-1916, Pressure and Temperature Limits Report2017-11-27027 November 2017 Pressure and Temperature Limits Report ML18012A0582017-10-31031 October 2017 NEDO-33884, Revision 0, Gnf Fecrai ATF Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-18-0026, NEDO-33884, Revision 0, Gnf Fecrai ATF Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1.2017-10-31031 October 2017 NEDO-33884, Revision 0, Gnf Fecrai ATF Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-18-0026, NEDO-33884, Revision 0, Gnf Fecrai Atf Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1.2017-10-31031 October 2017 NEDO-33884, Revision 0, Gnf Fecrai Atf Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-18-0026, NEDO-33883, Revision 0, Gnf Armor Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1.2017-09-30030 September 2017 NEDO-33883, Revision 0, Gnf Armor Lead Test Assembly for Edwin I. Hatch Nuclear Plant, Unit 1. NL-17-1255, Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope High Frequency Confirmation Evaluation2017-08-22022 August 2017 Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope High Frequency Confirmation Evaluation NL-16-2466, Fukushima Near-Term Task Force Recommendation 2.1 Expedited Seismic Evaluation Process Report Completion2016-12-15015 December 2016 Fukushima Near-Term Task Force Recommendation 2.1 Expedited Seismic Evaluation Process Report Completion NL-16-1136, Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope Low Frequency Evaluation2016-08-10010 August 2016 Fukushima Near-Term Task Force Recommendation 2.1 Seismic Limited-Scope Low Frequency Evaluation NL-15-2010, E.I. Hatch - Submits 10 CFR 71.95 Report on Non-Conformance Involving Radwaste Cask 8-120B2015-11-0202 November 2015 E.I. Hatch - Submits 10 CFR 71.95 Report on Non-Conformance Involving Radwaste Cask 8-120B NL-14-1876, Proposed Lnservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0, Conceptual Design Information Package2014-11-24024 November 2014 Proposed Lnservice Inspection Alternative HNP-ISI-ALT-HDPE-01, Version 2.0, Conceptual Design Information Package ML14223A7942014-07-31031 July 2014 Enclosure 2 - Non-Proprietary Gnf Report GNF-001N6296-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Hatch 2 Cycle 24 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 NL-14-0343, Seismic Hazard and Screening Report for CEUS Sites2014-03-31031 March 2014 Seismic Hazard and Screening Report for CEUS Sites ML13364A2022014-02-27027 February 2014 Interim Staff Evaluation Related to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14045A1472014-02-12012 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Edwin I. Hatch Nuclear Plant, Units 1 and 2, TAC Nos.: MF0712 and MF0713 NL-13-0402, GNF-0000-0079-7396NP, Rev. 6, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction Into the Hatch Nuclear Plant, March 20082013-01-31031 January 2013 GNF-0000-0079-7396NP, Rev. 6, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction Into the Hatch Nuclear Plant, March 2008 ML13115A4732013-01-31031 January 2013 GNF-0000-0079-7396NP, Rev. 6, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction Into the Hatch Nuclear Plant, March 2008 NL-11-1081, Reactor Pressure Vessel 2N2G Recirculation Inlet Nozzle-To-Safe End Weld Full Structural Weld Overlay, Crack Growth Calculations and Stress Analysis - Spring 2011 Outage (2R21)2011-07-0707 July 2011 Reactor Pressure Vessel 2N2G Recirculation Inlet Nozzle-To-Safe End Weld Full Structural Weld Overlay, Crack Growth Calculations and Stress Analysis - Spring 2011 Outage (2R21) NL-11-1131, Unit 2, GNF-Ziron Lead Test Assemblies2011-06-16016 June 2011 Unit 2, GNF-Ziron Lead Test Assemblies NL-10-0824, Hatch, Unit 2, GNF-0000-0101-6839NP, GNF-Ziron Basic Characteristics and Properties.2010-03-31031 March 2010 Hatch, Unit 2, GNF-0000-0101-6839NP, GNF-Ziron Basic Characteristics and Properties. NL-10-0824, Hatch, Unit 2, GNF-0000-0114-0175NP, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction.2010-03-31031 March 2010 Hatch, Unit 2, GNF-0000-0114-0175NP, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction. NL-10-0824, GNF-0000-0113-8604NP, GNF-Ziron Performance Benefits and Licensing Requirements Assessment.2010-03-31031 March 2010 GNF-0000-0113-8604NP, GNF-Ziron Performance Benefits and Licensing Requirements Assessment. ML1013407402010-03-31031 March 2010 GNF-0000-0114-0175NP, Technical Basis Supporting GNF-Ziron Lead Test Assembly Introduction. ML1013407382010-03-31031 March 2010 GNF-0000-0101-6839NP, GNF-Ziron Basic Characteristics and Properties. NL-09-0503, Response to Preliminary White Finding on 1B EDG Coupling Failure2009-04-15015 April 2009 Response to Preliminary White Finding on 1B EDG Coupling Failure ML0916006722009-03-31031 March 2009 GE-NE-0000-0080-0259-NP-R4, Shroud Repair Replacement of Upper Support Stress Analysis Report, Public NL-08-1781, Certified Material Test Report (CMTR) for CRD System Return Nozzle (N-9) Cap2008-12-19019 December 2008 Certified Material Test Report (CMTR) for CRD System Return Nozzle (N-9) Cap NL-08-1448, Submittal of Additional Information to Support Proposed Exemption to 10 CFR 50.448 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding2008-09-22022 September 2008 Submittal of Additional Information to Support Proposed Exemption to 10 CFR 50.448 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0822500372008-07-31031 July 2008 GNF-0000-0088-6047NP, Enclosure 4, Impact of GNF-Ziron Cladding on Thermal-Mechanical Licensing Limits, July 2008 NL-08-1250, GNF-0000-0088-6043NP, Enclosure 6, Properties of GNF-Ziron, July 20082008-07-31031 July 2008 GNF-0000-0088-6043NP, Enclosure 6, Properties of GNF-Ziron, July 2008 NL-08-1250, GNF-0000-0088-6047NP, Enclosure 4, Impact of GNF-Ziron Cladding on Thermal-Mechanical Licensing Limits, July 20082008-07-31031 July 2008 GNF-0000-0088-6047NP, Enclosure 4, Impact of GNF-Ziron Cladding on Thermal-Mechanical Licensing Limits, July 2008 NL-08-1301, GE-NE-0000-0080-0259-R2, Hatch 2 Nuclear Plant, Shroud Repair Replacement of Upper Support Stress Analysis Report.2008-06-30030 June 2008 GE-NE-0000-0080-0259-R2, Hatch 2 Nuclear Plant, Shroud Repair Replacement of Upper Support Stress Analysis Report. NL-08-0634, Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Radiological Consequences Analyses2008-05-0505 May 2008 Request to Implement an Alternative Source Term Response to Request for Additional Information Regarding the Radiological Consequences Analyses NL-08-0590, Revised Proposed Exemption to 10 CFR 50.46 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding2008-05-0202 May 2008 Revised Proposed Exemption to 10 CFR 50.46 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding NL-08-0380, Proposed Exemption to 10 CFR 50.46 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding2008-03-21021 March 2008 Proposed Exemption to 10 CFR 50.46 and 10 CFR 50 Appendix K to Allow Ziron Fuel Cladding ML0624902422006-08-29029 August 2006 Enclosure 1, E. I. Hatch Request to Implement an Alternative Source Term - AST Safety Assessment ML0624904922006-07-28028 July 2006 Enclosure 8, E. I. Hatch, Request to Implement an Alternative Source Term - Unit 1 Main Steam Isolation Valve Alternate Leakage Path Seismic Evaluation ML0624904982006-07-28028 July 2006 Enclosure 9, E. I. Hatch, Request to Implement Alternative Source Term - Unit 1 Seismic Verification of Potential Secondary Containment Bypass Leakage Paths Terminating at Main Condenser ML0434304752004-10-20020 October 2004 SIR-04-120, Rev. 0, Elastic-Plastic Fracture Mechanics Evaluation of the Plant Hatch Unit 1, Core Shroud V5 and V6 Welds. ML0802902312004-02-12012 February 2004 Westinghouse Technical Bulletin: Information Regarding Recent Crossflow Ultrasonic Flow Measurement System Performance Observations, TB-04-4 ML0624902592003-04-30030 April 2003 Enclosure 13, E. I. Hatch Request to Implement an Alternative Source Term - EPRI Technical Report 1007896, Seismic Evaluation Guidelines for HVAC Duct and Damper Systems. ML0311800572003-04-25025 April 2003 Results of the Edwin I. Hatch Generating Station Units 1 and 2 SDP Phase 2 Notebook Benchmarking Visit ML0310502642002-12-19019 December 2002 Request for License Amendment Measurement Uncertainty Recapture Power Uprate, Enclosures 1 - 6 2022-07-14
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Text
Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201-1295 Tel 205.992.5000 SOUTHERN COMPANY A.
December 19, 2008 Energy to Serve Your Worid SM Docket No.: 50-321 NL':08-1781 U. S. Nuclear Regulatory Commission ATrN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant - Unit 1 Certified Material Test Report (CMTR) for CRD System Return Nozzle (N-9) Cap Ladies and Gentlemen:
On February 26, 2008 Southern Nuclear Operating Company (SNC) requested an alternative pursuant to 10 CFR 50.55a(a)(3)(i) to perform a dissimilar metal full structural weld overlay on weld 1C11-1 CRD-3-R-18A. This alternative was subsequently granted.
During a related telephone conversation, the NRC requested a copy of the CMTR for CRD system return nozzle (N-9) cap, and it is hereby included in the enclosure to this letter.
This letter contains no NRC commitments. If you have any questions, please advise.
Sincerely, JYLJ-- ~
M. J. Ajluni
¥-
Manager, Nuclear Licensing MJAlMNW/daj
Enclosure:
Certified Material Test Report (CMTR) for CRD System Return Nozzle (N-9) Cap
U. S. Nuclear Regulatory Commission NL-08-1781 Page 2 cc: Southern Nuclear Operating Company Mr. J. T. Gasser, Executive Vice President Mr. D. R. Madison, Vice President - Hatch Mr. D. H. Jones, Vice President - Engineering RTYPE: CHA02.004 U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Hatch Mr. J. A. Hickey, Senior Resident Inspector - Hatch
Edwin I. Hatch Nuclear Plant - Unit 1 Enclosure Certified Material Test Report (CMTR) for CRD System Return Nozzle (N-9) Cap
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Q.A. RECORDS FOR : HATCH 1 EQUIP : FORGINGS MPL NO. 311-AOIH 5/-; AJ403-01-C2 ITEl-t 1 G.E.. P.O. :\0. 205 AJ 403 Rev. 04 S~PPLIER : COULTEa STEEL & tORGE COXP~\~
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SIGNEO;~ 4 ?"~-<: DATE: _-..I-C1"",II~Y_ _/"-C'~-.L/...::'_Z,-L.Z __
TITLE: Quality Control ~.ana8er ORGA"IIATION: Coulter Steel & Forge Co.
GE QUALITY ASSURANCE CERTIFICATION THIS IS TO CERTIFY THA'l' eVIDENCE SUPPORTING T"'E ABove SUPPLle'l'S CERTIFICATION STATEME"lT HAS SEEN REvle..';EO AND ~O PRODUCT NONCQMFOR\4ANCeS FqOM PROCURE*
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TITlE: G QA REPReSENTATIVE O~GANIZATION:_..;B\IRP==D _
NONCONFORMANCES FROM PROCUREMENTOUALITV REQUIREMENTS.
REMARKS/EOUIPMENT SERIAL NUMBERS; 51'S AJ403-01-02 This PQC changed because of clerical error, original equipment shipped 3/18117.