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| | number = ML18101A306 | | | number = ML18101A306 |
| | issue date = 10/19/1994 | | | issue date = 10/19/1994 |
| | title = Requests Approval,Per 10CFR50.55a,Section(a)(3) to Use ASME Section Xi Code Cases N-498-1 & N-524 in Salem & Hope Creek Generating Stations ISI Programs | | | title = Requests Approval,Per 10CFR50.55a,Section(a)(3) to Use ASME Section XI Code Cases N-498-1 & N-524 in Salem & Hope Creek Generating Stations ISI Programs |
| | author name = HAGAN J J | | | author name = Hagan J |
| | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY | | | author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:*** Public Service Electric and Gas Company | | {{#Wiki_filter:*** Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations OCT 1 9 1994 NLR-N94178 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen: |
| * Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President
| | INSERVICE INSPECTION ASME SECTION XI CODE CASE APPLICATION SALEM GENERATING STATION, UNIT NOS. 1 AND 2 HOPE CREEK GENERATING STATION, UNIT NO. 1 DOCKET NOS. 50-272, 50-311, AND 50-354 Public Service Electric & Gas Company (PSE&G) hereby requests approval, per 10CFR50.55a, Section (a) (3) to use ASME Section XI Code Cases N-498-1 and N-524 in the Salem and Hope Creek Generating Stations Inservice Inspection (ISI) Programs. Code Case N-498-1, entitled Alternative Rules for 10-Year System . |
| -Nuclear Operations OCT 1 9 1994 NLR-N94178 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen: | | Hydrostatic Testing for Class l, 2, and 3 Systems was approved by the ASME and published on May 11, 1994. Code Case N-524, entitled Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping was approved by the ASME and published on August 8, 1993. The use of these Code Cases is not presently referenced in NRC Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, Revision 10, dated July, 1993. |
| INSERVICE INSPECTION ASME SECTION XI CODE CASE APPLICATION SALEM GENERATING STATION, UNIT NOS. 1 AND 2 HOPE CREEK GENERATING STATION, UNIT NO. 1 DOCKET NOS. 50-272, 50-311, AND 50-354 Public Service Electric & Gas Company (PSE&G) hereby requests approval, per 10CFR50.55a, Section (a) (3) to use ASME Section XI Code Cases N-498-1 and N-524 in the Salem and Hope Creek Generating Stations Inservice Inspection (ISI) Programs. | | Code Case N-498-1 provides alternative rules for Class 1, 2, and 3 (Table IWB, C, and D-2500-1, Categories B-P, C-H, D-A, D-B, and D-C) ten-year system hydrostatic tests. This Code Case allows a system leakage/system pressure test to be conducted in lieu of a hydrostatic test, subject to the test criteria in the Code Case. |
| Code Case N-498-1, entitled Alternative Rules for 10-Year System . Hydrostatic Testing for Class l, 2, and 3 Systems was approved by the ASME and published on May 11, 1994. Code Case N-524, entitled Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping was approved by the ASME and published on August 8, 1993. The use of these Code Cases is not presently referenced in NRC Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, Revision 10, dated July, 1993. Code Case N-498-1 provides alternative rules for Class 1, 2, and 3 (Table IWB, C, and D-2500-1, Categories B-P, C-H, D-A, D-B, and D-C) ten-year system hydrostatic tests. This Code Case allows a system leakage/system pressure test to be conducted in lieu of a hydrostatic test, subject to the test criteria in the Code Case. Code Case N-524 provides alternative examination requirements for longitudinal welds in Class 1 and 2 piping, Section XI, Division I. PSE&G has reviewed the referenced Code Cases and concurs with the ASME assessment that the use of both Code Cases would provide an acceptable level of quality and safety. | | Code Case N-524 provides alternative examination requirements for longitudinal welds in Class 1 and 2 piping, Section XI, Division I. PSE&G has reviewed the referenced Code Cases and concurs with the ASME assessment that the use of both Code Cases would provide an acceptable level of quality and safety. |
| .... ,., Document Control Desk NLR-N94l78 2 OCT 1 9 1994 Copies of the requested Code Cases have been included as Enclosures 1 and 2. Should there be any questions with regard to this submittal, please do not hesitate to contact us. C Mr. T. T. Martin, Administrator
| | |
| -Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. N. Olshan, Licensing Project Manager -Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. D. Moran, Licensing Project Manager -Hope Creek U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. C. Marschall | | Document Control Desk 2 OCT 1 9 1994 NLR-N94l78 Copies of the requested Code Cases have been included as Enclosures 1 and 2. Should there be any questions with regard to this submittal, please do not hesitate to contact us. |
| -Salem (S09) USNRC Senior Resident Inspector Mr. R. Summers -Hope Creek (S09) USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 95-4933 r.* .., * .. , **Dclc:..,,,,, .. .s. """-a/ .... ,,,, 2 I IDfrr md Mr ,..,. .. doll .... | | C Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. N. Olshan, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. D. Moran, Licensing Project Manager - Hope Creek U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. C. Marschall - Salem (S09) |
| Alumadft RD111for10.Ymr S,... Tutlq far C.. 1 1 J &ad 3 s,.t.mll Sa:doll Dimloll 1 /lfl/UllY: | | USNRC Senior Resident Inspector Mr. R. Summers - Hope Creek (S09) |
| Wlw lla:madn rulOI may be U..S ID lieu of thole requirad by Soctiaa XI. Dm.Jcm 1, T&bla IWB-2500.1, Ca.tqory B-P, Table IWC2S00-1, Cat* egozy CH, and Table IWD.-2500-1, Catqmics 0-A. D-B. 'and D-C. al applicable, far the 10-fgr system hydrostatic test? Rl/19: (o) It is the opinion of th& CammittlMI that u an alcrmariYIS rem. 10-)'ear system lrjdrulbitfc teSt qutred by Tablo Caiepy B-P. the fol* lawinl rules shall be uaed. (lJ A l)'ltem 1eakap iac (IWB-52%1) shall b9 ccnducied ai or ncar tba end of eadl impcaioa terY&L prier to reaccor surmp. (2) Tho bounduy subject m mt pnmurizadoll du.rinf th* l)'ltem leabp tolC shall mead co all 0ua 1 pteame rctainina CDmponalfl within the tcm boundary.
| | USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 95-4933 |
| fJ) Prior m pcrtormiJll
| | |
| : w. vr-2 vDuaJ e:ami* nation. the system wll ba to nomiAal operatin1 preaura far at lcar 4 hours for imulated systems and 10 minura far nozdmulaled J?SWmt. Tho system shall be mfilminsd u namtut opcradq presaure during perfarmmce of rhe VT-2 visual=* auUnacica. ( 4) Test ccmperaaues and pra.suns shall iun exceed limitin& eondieicma fm ma bydrmladc test curve as conramecl m dw plant TICbnieaJ tianL (5) The vr_z vilual llftMfrqtim
| | r.* .., |
| &hall lDdudc all . widam me bounduy idcmfaed in (a}(2) above. (6J Tesr imamuntadan 1"C4macmena:
| | .., **Dclc:..,,,,,.. |
| of .. 5260 UI n0t aPPlfclble. | | .s. """-a/ .... ,,,, 2 IDfrr I |
| "?bnt limeoptiUoa of th* Committc&
| | md Mr ,..,.. .doll . . . . |
| thal. al an alternative to the 10.,Ur system hydrostatic quired by Table IWCZS00-1.
| | CueN~l . (2) n. bcnmduy labjecl ta .c pc asmtutiau Alumadft RD111for10.Ymr S,... ~ durfq the l)'lieDl prmma te1e DU aiad to all Tutlq far C.. 11 J &ad 3 s,.t.mll 0111 2 I I ciponatl inctucled In. thole pucibd ot.,.. |
| Catepy CH. the fol* lowinl rules smll be used. (1) A system prasure tat shall be condw:ted at or near the end of each inspoctiaa or dmtn1 th* same inspection period of Heh lnspcdion inter* val of Inspcc:don Propm B. . (2) n. bcnmduy labjecl ta .c pc asmtutiau durfq the l)'lieDl prmma te1e DU aiad to all 0111 2 I I ciponatl inctucled In. thole pucibd ot.,.. tema r.qu:lncl tu opwatll or auppoft me ..,_,. ljlt.c:m frmaina llp tD ad includia&
| | Sa:doll ~ Dimloll 1 tema r.qu:lncl tu opwatll or auppoft me ..,_,. ljlt.c:m frmaina llp tD ad includia& die fim DOml&Uy dOICd |
| die fim DOml&Uy dOICd vaM, indadlq a Afety ar reUcf 'Yllw. or Ya1Ye pable of amamauc dosmt when the aDty fmlction ii required.
| | /lfl/UllY: Wlw lla:madn rulOI may be U..S ID lieu vaM, indadlq a Afety ar reUcf 'Yllw. or Ya1Ye ca-of thole requirad by Soctiaa XI. Dm.Jcm 1, T&bla pable of amamauc dosmt when the aDty fmlction IWB-2500.1, Ca.tqory B-P, Table IWC2S00-1, Cat* ii required. |
| r1J Prior io perfmmfq m. vr.2 visual nadon. the &yStem shall b* pressurized to nmninal operaciq pieaun far
| | egozy CH, and Table IWD.-2500-1, Catqmics 0-A. r1J Prior io perfmmfq m. vr.2 visual enmi-D-B. 'and D-C. al applicable, far the 10-fgr system nadon. the &yStem shall b* pressurized to nmninal hydrostatic test? operaciq pieaun far |
| * mtnfnmm of 4 houn for in* su1ated .,.ram md 10 mtnura for ncminsoJaccd 1)'1-tcnu. lhaD .,. mamtl!Ded at nominal aatfq duriq pcrfDmwM:c of the VT*l visual cnminlfioa.
| | * mtnfnmm of 4 houn for in* |
| r-1> n. vr.2 Vllual 'f!nmin*iicm aball indade all compuunts within the boundaiy idcntiOed in (b)(2) above. (SJ Teat lmcrumantatlan rcqairmnena of IW A-5260 IR nm applioabJ& (c) It ism. apiDlon of m. Commiaa that. as an altomaiive to m. 1o.,ar symm hyc1mltad.c test quind bJ Table IWI).2500-1 Cateptes D-A. D-B. or 0-C (D-B for the 1989 Ediliou with tha 1991 and subsequent Addenda)..
| | su1ated .,.ram md 10 mtnura for ncminsoJaccd 1)'1-tcnu. no~ lhaD .,. mamtl!Ded at nominal op-aatfq praiaxp~ duriq pcrfDmwM:c of the VT*l Rl/19: visual cnminlfioa. |
| u applicable.
| | (o) It is the opinion of th& CammittlMI that u an r-1> n. vr.2 Vllual 'f!nmin*iicm aball indade alcrmariYIS rem. 10-)'ear system lrjdrulbitfc teSt re- all compuunts within the boundaiy idcntiOed in qutred by Tablo IWB-~1. Caiepy B-P. the fol* (b)(2) above. |
| th* followin1 rulu shall be UMd. (I) A aymm pnman tat aha1l be conducted at ar near the dd of uda impec:ticla tntaiwl or durin1 the same inlp9CtioD pcrlod of e8Ch impcc:don incer-. val of InspecDon Prasrmza B. (2) The bonnday mbjecc to ten prmurinticm durina w system prean* wi sball a=d ta all aa113 e. "'l""""'Nlll included m them portians of.,,. tema required to opeiate m auppart tho saf;ty system fimctiml up Ea and indudlng the first normally dosed valve, indudia1 a safmty or relief valY8 or valw Q* pabl* of amomatic clolura when cha safety tunction ii requin:d. (JJ Prior to petbm.lq tt. VT-2 visual C'Dmi* nation. the System shall be to nominal operadns praaun far ai leui .4 hours for imulated systems and 10 minura for Nmin1Pl1ted synrms. The system sball be mainWncd a' nominal apcnrln1 pressure dur1Dg performance of tho vr-2 visual CX* aminar:ion. | | lawinl rules shall be uaed. (SJ Teat lmcrumantatlan rcqairmnena of IWA-(lJ A l)'ltem 1eakap iac (IWB-52%1) shall b9 5260 IR nm applioabJ& |
| (4) Th* VT*2 visual ennrinaticm lh.all lnclude all componcma within the bounduy idCntiftad in (c)(2) above. (S) Test instnment:atian requirements of lWA-5260 ue not applicable.
| | ccnducied ai or ncar tba end of eadl impcaioa in- (c) It ism. apiDlon of m. Commiaa that. as an terY&L prier to reaccor surmp. altomaiive to m. 1o.,ar symm hyc1mltad.c test rc-(2) Tho bounduy subject m mt pnmurizadoll quind bJ Table IWI).2500-1 Cateptes D-A. D-B. |
| SUPP, I -NC
| | du.rinf th* l)'ltem leabp tolC shall mead co all or 0-C (D-B for the 1989 Ediliou with tha 1991 and 0ua 1 pteame rctainina CDmponalfl within the syl- subsequent Addenda).. u applicable. th* followin1 tcm boundary. rulu shall be UMd. |
| .. . ..
| | fJ) Prior m pcrtormiJll w. vr-2 vDuaJ e:ami* (I) A aymm pnman tat aha1l be conducted at nation. the system wll ba ~ to nomiAal ar near the dd of uda impec:ticla tntaiwl or durin1 operatin1 preaura far at lcar 4 hours for imulated the same inlp9CtioD pcrlod of e8Ch impcc:don incer-. |
| * CASES OF ASME BOILER AND PRESSURE VESSEL CODE Approval Date: August 9, 1993 See Numerical Index for expiration and any reaffirmation dates. Case N-524 Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping Section XI, Division 1 Inquiry: What alternative requirements may be plied to the surface and volumetric examination of longitudinal piping welds specified in Table IWB-2500-1, Examination Category B-J, Table IWC-2500-1, Examination Categories C-F-1 and C-F-2 ination Category C-F prior to Winter 1983 da), and Table IWC-2520, Examination Category G (1974 Edition, Summer 1975 Addenda)?
| | systems and 10 minura far nozdmulaled J?SWmt. val of InspecDon Prasrmza B. |
| Reply: It is the opinion of the Committee that the following shall apply: (a) When only a surface examination is required, examination of longitudinal piping welds is not quired beyond those portions of the welds within the examination boundaries of intersecting ential welds. (b) When both surface and volumetric tions are required, examination of longitudinal piping welds is not required beyond those portions of the welds within the examination boundaries of secting circumferential welds provided the following requirements are met. (1) Where longitudinal welds are specified and locations are known, examination requirements shall be met for both transverse and parallel flaws at the intersection of the welds and for that length of gitudinal weld within the circumferential weld amination volume; (2) Where longitudinal welds are specified but locations are unknown, or the existence of dinal welds is uncertain, the examination ments shall be met for both transverse and parallel flaws within the entire examination volume of secting circumferential welds. 903 CASE N-524 SUPP. 6 -NC}}
| | Tho system shall be mfilminsd u namtut opcradq (2) The bonnday mbjecc to ten prmurinticm presaure during perfarmmce of rhe VT-2 visual=* durina w system prean* wi sball a=d ta all auUnacica. m aa113 e. "'l""""'Nlll included them portians of.,,. |
| | ( 4) Test ccmperaaues and pra.suns shall iun tema required to opeiate m auppart tho saf;ty system exceed limitin& eondieicma fm ma bydrmladc test fimctiml up Ea and indudlng the first normally dosed m |
| | curve as conramecl dw plant TICbnieaJ Specitlca- valve, indudia1 a safmty or relief valY8 or valw Q |
| | * tianL pabl* of amomatic clolura when cha safety tunction (5) The vr_z vilual llftMfrqtim &hall lDdudc ii requin:d. |
| | all .~ar widam me bounduy idcmfaed in (JJ Prior to petbm.lq tt. VT-2 visual C'Dmi* |
| | (a}(2) above. nation. the System shall be ~ to nominal (6J Tesr imamuntadan 1"C4macmena: of J.WA- operadns praaun far ai leui .4 hours for imulated |
| | .. 5260 UI n0t aPPlfclble. systems and 10 minura for Nmin1Pl1ted synrms. |
| | "?bnt limeoptiUoa of th* Committc& thal. al an The system sball be mainWncd a' nominal apcnrln1 alternative to the 10.,Ur system hydrostatic ~ re- pressure dur1Dg performance of tho vr-2 visual CX* |
| | quired by Table IWCZS00-1. Catepy CH. the fol* aminar:ion. |
| | lowinl rules smll be used. (4) Th* VT*2 visual ennrinaticm lh.all lnclude (1) A system prasure tat shall be condw:ted at all componcma within the bounduy idCntiftad in or near the end of each inspoctiaa in~ or dmtn1 (c)(2) above. |
| | th* same inspection period of Heh lnspcdion inter* (S) Test instnment:atian requirements of lWA-val of Inspcc:don Propm B. 5260 ue not applicable. |
| | SUPP, I - NC |
| | * CASES OF ASME BOILER AND PRESSURE VESSEL CODE CASE N-524 Approval Date: August 9, 1993 See Numerical Index for expiration and any reaffirmation dates. |
| | Case N-524 Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping Section XI, Division 1 Inquiry: What alternative requirements may be ap-plied to the surface and volumetric examination of longitudinal piping welds specified in Table IWB-2500-1, Examination Category B-J, Table IWC-2500-1, Examination Categories C-F-1 and C-F-2 (Exam-ination Category C-F prior to Winter 1983 Adden-da), and Table IWC-2520, Examination Category C-G (1974 Edition, Summer 1975 Addenda)? |
| | Reply: It is the opinion of the Committee that the following shall apply: |
| | (a) When only a surface examination is required, examination of longitudinal piping welds is not re-quired beyond those portions of the welds within the examination boundaries of intersecting circumfer-ential welds. |
| | (b) When both surface and volumetric examina-tions are required, examination of longitudinal piping welds is not required beyond those portions of the welds within the examination boundaries of inter-secting circumferential welds provided the following requirements are met. |
| | (1) Where longitudinal welds are specified and locations are known, examination requirements shall be met for both transverse and parallel flaws at the intersection of the welds and for that length of lon-gitudinal weld within the circumferential weld ex-amination volume; (2) Where longitudinal welds are specified but locations are unknown, or the existence of longitu-dinal welds is uncertain, the examination require-ments shall be met for both transverse and parallel flaws within the entire examination volume of inter-secting circumferential welds. |
| | 903 SUPP. 6 - NC}} |
|
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M7571999-10-22022 October 1999
Advises That Attachment 1 to ,Marked as Proprietary,Re Safety Limit MCPR & Fuel Vendor Change Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5)
ML20217M2101999-10-19019 October 1999
Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates
ML20217H8471999-10-18018 October 1999
Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs
ML18107A5601999-10-18018 October 1999
Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses
ML20217K8441999-10-15015 October 1999
Submits Revised Commitment to NRC Bulletin 90-01,Suppl 1 for Hope Creek Generating Station
ML20217H9771999-10-13013 October 1999
Forwards SRO & RO Initial Exam Rept 50-354/98-302,suppl Rept on 990125-29,mtg Meeting on 990322,990429-30 & 0617-18 in-office Review & 990720 Telcon on Appeal Results.Overall, 11 of 16 Applicants Received NRC Licenses
ML18107A5531999-10-0808 October 1999
Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1
ML18107A5561999-10-0707 October 1999
Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests
ML20217C4391999-10-0606 October 1999
Informs That Util Authorized to Administer Initial NRC Retake Written Exam to Applicant Listed,During Week of 991011
ML18107A5501999-10-0505 October 1999
Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station
ML18107A5521999-10-0505 October 1999
Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys
ML18107A5591999-10-0505 October 1999
Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2
ML20217A9601999-10-0404 October 1999
Forwards Errata Redressing Deficiencies & Correcting Two Typos to Ufsar,Rev 10.Incorporate Attached Pages/Figures Into Controlled Copies of UFSAR
ML20217A6861999-10-0101 October 1999
Forwards Insp Rept 50-354/99-05 on 990711-0829.Four Violations Occurred Re Areas of Fire Protection,Operation at Reduced Feedwater Inlet Temp & safety-related Battery Charging Operation & Being Treated as NCVs
LR-N990430, Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review1999-09-28028 September 1999
Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review
IR 05000272/19990071999-09-28028 September 1999
Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified
ML18107A5341999-09-22022 September 1999
Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999)
ML18107A5421999-09-22022 September 1999
Forwards Discharge Monitoring Rept for Salem Generating Station for Aug 1999.Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection
05000354/LER-1999-009, Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl1999-09-20020 September 1999
Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl
ML20217K7781999-09-16016 September 1999
Forwards Discharge Monitoring Rept for Hope Creek Generating Station for Month of Aug 1999. Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection
ML20212B3631999-09-14014 September 1999
Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld
ML20212B4021999-09-13013 September 1999
Submits Supplemental Info Related to Hope Creek License Change Request (LCR) H98-08,submitted to NRC on 981230, Re Flood Protection TS Changes
ML18107A5321999-09-13013 September 1999
Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources.
ML18107A5331999-09-13013 September 1999
Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2
ML18107A5351999-09-13013 September 1999
Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments
ML18107A5221999-09-0808 September 1999
Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations
ML18107A5231999-09-0808 September 1999
Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999
ML20211N5421999-09-0808 September 1999
Forwards Amend 121 to License NPF-57 & Safety Evaluation. Amend Revises TSs by Relocating Procedural Details of RETS to Offsite Dose Calculation Manual
LR-N990395, Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also1999-09-0101 September 1999
Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also
ML18107A4981999-08-26026 August 1999
Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues
ML18107A5061999-08-26026 August 1999
Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151
ML18107A5181999-08-26026 August 1999
Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided
ML18107A5051999-08-24024 August 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves
ML18107A4921999-08-23023 August 1999
Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02
ML18107A4911999-08-20020 August 1999
Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars
ML20211B5341999-08-20020 August 1999
Forwards RAI Re 2nd 10-yr ISI Interval Relief Requests Re Plant.Info Requested to Be Provided within 60 Days of Receipt of Ltr
ML18107A4861999-08-19019 August 1999
Forwards NPDES Discharge Monitoring Rept, for Salem Generating Station for Month of Jul 1999.Rept Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection
ML18107A4831999-08-18018 August 1999
Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1
ML18107A4801999-08-13013 August 1999
Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed
ML20210R4911999-08-11011 August 1999
Forwards Insp Rept 50-354/99-04 on 990530-0711.No Violations Noted.Inspectors Reviewed Performance Indicators Submitted as Part of Pilot Program for New Regulatory Oversight Process & Verified Data
ML18107A4751999-08-0505 August 1999
Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630
ML20210M7571999-08-0404 August 1999
Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response
ML20210H9241999-07-26026 July 1999
Informs That State of Nj Dept of Environ Protection Has No Comments on Licensee 990517 Request for Amend to TS by Adding TS 3.3.10, Instrumentation of OPRM Sys
ML20210F3271999-07-22022 July 1999
Forwards SE Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3 Re First 10-year Interval for ISI Program at Hope Creek
ML18107A4531999-07-20020 July 1999
Forwards Discharge Monitoring Rept for Salem Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection
ML20210D3971999-07-16016 July 1999
Forwards Discharge Monitoring Rept for Hope Creek Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection
05000354/LER-1999-007, Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl1999-07-14014 July 1999
Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl
ML20209G2831999-07-14014 July 1999
Disclosure Closure of TAC MA1194 Re Licensee Response to RAI to GL 92-01,Rev 1,Suppl 1, Rc Structural Integrity, for Plant
LR-N990250, Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds1999-07-0909 July 1999
Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds
ML18107A4431999-07-0606 July 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments
1999-09-08
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML18107A5601999-10-18018 October 1999
Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses
ML20217K8441999-10-15015 October 1999
Submits Revised Commitment to NRC Bulletin 90-01,Suppl 1 for Hope Creek Generating Station
ML18107A5531999-10-0808 October 1999
Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1
ML18107A5561999-10-0707 October 1999
Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests
ML18107A5591999-10-0505 October 1999
Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2
ML18107A5521999-10-0505 October 1999
Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys
ML18107A5501999-10-0505 October 1999
Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station
ML20217A9601999-10-0404 October 1999
Forwards Errata Redressing Deficiencies & Correcting Two Typos to Ufsar,Rev 10.Incorporate Attached Pages/Figures Into Controlled Copies of UFSAR
LR-N990430, Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review1999-09-28028 September 1999
Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review
ML18107A5341999-09-22022 September 1999
Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999)
05000354/LER-1999-009, Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl1999-09-20020 September 1999
Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl
ML20212B3631999-09-14014 September 1999
Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld
ML20212B4021999-09-13013 September 1999
Submits Supplemental Info Related to Hope Creek License Change Request (LCR) H98-08,submitted to NRC on 981230, Re Flood Protection TS Changes
ML18107A5321999-09-13013 September 1999
Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources.
ML18107A5351999-09-13013 September 1999
Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments
ML18107A5331999-09-13013 September 1999
Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2
ML18107A5231999-09-0808 September 1999
Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999
ML18107A5221999-09-0808 September 1999
Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations
LR-N990395, Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also1999-09-0101 September 1999
Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also
ML18107A4981999-08-26026 August 1999
Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues
ML18107A5181999-08-26026 August 1999
Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided
ML18107A5061999-08-26026 August 1999
Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151
ML18107A5051999-08-24024 August 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves
ML18107A4921999-08-23023 August 1999
Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02
ML18107A4911999-08-20020 August 1999
Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars
ML18107A4831999-08-18018 August 1999
Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1
ML18107A4801999-08-13013 August 1999
Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed
ML18107A4751999-08-0505 August 1999
Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630
ML20210M7571999-08-0404 August 1999
Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response
ML20210H9241999-07-26026 July 1999
Informs That State of Nj Dept of Environ Protection Has No Comments on Licensee 990517 Request for Amend to TS by Adding TS 3.3.10, Instrumentation of OPRM Sys
05000354/LER-1999-007, Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl1999-07-14014 July 1999
Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl
LR-N990250, Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds1999-07-0909 July 1999
Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds
ML18107A4431999-07-0606 July 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments
ML18107A4181999-06-30030 June 1999
Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl
LR-N990316, Responds to NRC Request for Info Re Y2K Readiness at Npps, Per GL 98-01,suppl 1.Disclosure Encl1999-06-30030 June 1999
Responds to NRC Request for Info Re Y2K Readiness at Npps, Per GL 98-01,suppl 1.Disclosure Encl
ML18107A4131999-06-25025 June 1999
Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC
ML18107A4061999-06-21021 June 1999
Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed
ML20196E6471999-06-21021 June 1999
Forwards Revised marked-up TS Page for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively. Revised Pages Do Not Alter Conclusions Reached in 10CFR50.92 No Significant Hazards Analysis Previously Submitted
ML20209B6441999-06-21021 June 1999
Offers No Comments on Licensee 990529 Request for Revs to Plant Radiological Effluent Ts,Per GL 89-01
ML20196E9631999-06-17017 June 1999
Informs That Util Has Made Change to Commitment Stated in NRC Ser,Suppl 5.Commitment That Has Been Changed Is Item Number 1 of First Paragraph on Page 9-3 of Ser,Suppl 5
LR-N990295, Submits Change 1 to Relief Request RR-A4,which Clarifies Requirements Re Snubber Visual Insps.Request Was Submitted as Part of Plant Second Interval ISI Program on 9905111999-06-16016 June 1999
Submits Change 1 to Relief Request RR-A4,which Clarifies Requirements Re Snubber Visual Insps.Request Was Submitted as Part of Plant Second Interval ISI Program on 990511
05000354/LER-1999-006, Forwards LER 99-006-00 Re Esfa B Channel Primary Containment Isolation Signal Actuation.Attachment a Lists Commitments Util Making to NRC Re LER1999-06-15015 June 1999
Forwards LER 99-006-00 Re Esfa B Channel Primary Containment Isolation Signal Actuation.Attachment a Lists Commitments Util Making to NRC Re LER
ML18107A3691999-06-11011 June 1999
Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours)
ML18107A3641999-06-0404 June 1999
Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1
ML18107A3561999-06-0303 June 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments
ML18107A3611999-05-27027 May 1999
Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05
ML18107A3301999-05-24024 May 1999
Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves
ML18107A3291999-05-20020 May 1999
Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6)
ML18107A3031999-05-18018 May 1999
Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments
ML18107A2891999-05-13013 May 1999
Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness
1999-09-08
[Table view] |
Text
- Public Service Electric and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 Vice President - Nuclear Operations OCT 1 9 1994 NLR-N94178 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
INSERVICE INSPECTION ASME SECTION XI CODE CASE APPLICATION SALEM GENERATING STATION, UNIT NOS. 1 AND 2 HOPE CREEK GENERATING STATION, UNIT NO. 1 DOCKET NOS. 50-272, 50-311, AND 50-354 Public Service Electric & Gas Company (PSE&G) hereby requests approval, per 10CFR50.55a, Section (a) (3) to use ASME Section XI Code Cases N-498-1 and N-524 in the Salem and Hope Creek Generating Stations Inservice Inspection (ISI) Programs. Code Case N-498-1, entitled Alternative Rules for 10-Year System .
Hydrostatic Testing for Class l, 2, and 3 Systems was approved by the ASME and published on May 11, 1994. Code Case N-524, entitled Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping was approved by the ASME and published on August 8, 1993. The use of these Code Cases is not presently referenced in NRC Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, Revision 10, dated July, 1993.
Code Case N-498-1 provides alternative rules for Class 1, 2, and 3 (Table IWB, C, and D-2500-1, Categories B-P, C-H, D-A, D-B, and D-C) ten-year system hydrostatic tests. This Code Case allows a system leakage/system pressure test to be conducted in lieu of a hydrostatic test, subject to the test criteria in the Code Case.
Code Case N-524 provides alternative examination requirements for longitudinal welds in Class 1 and 2 piping,Section XI, Division I. PSE&G has reviewed the referenced Code Cases and concurs with the ASME assessment that the use of both Code Cases would provide an acceptable level of quality and safety.
Document Control Desk 2 OCT 1 9 1994 NLR-N94l78 Copies of the requested Code Cases have been included as Enclosures 1 and 2. Should there be any questions with regard to this submittal, please do not hesitate to contact us.
C Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. N. Olshan, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. D. Moran, Licensing Project Manager - Hope Creek U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. C. Marschall - Salem (S09)
USNRC Senior Resident Inspector Mr. R. Summers - Hope Creek (S09)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 95-4933
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.s. """-a/ .... ,,,, 2 IDfrr I
md Mr ,..,.. .doll . . . .
CueN~l . (2) n. bcnmduy labjecl ta .c pc asmtutiau Alumadft RD111for10.Ymr S,... ~ durfq the l)'lieDl prmma te1e DU aiad to all Tutlq far C.. 11 J &ad 3 s,.t.mll 0111 2 I I ciponatl inctucled In. thole pucibd ot.,..
Sa:doll ~ Dimloll 1 tema r.qu:lncl tu opwatll or auppoft me ..,_,. ljlt.c:m frmaina llp tD ad includia& die fim DOml&Uy dOICd
/lfl/UllY: Wlw lla:madn rulOI may be U..S ID lieu vaM, indadlq a Afety ar reUcf 'Yllw. or Ya1Ye ca-of thole requirad by Soctiaa XI. Dm.Jcm 1, T&bla pable of amamauc dosmt when the aDty fmlction IWB-2500.1, Ca.tqory B-P, Table IWC2S00-1, Cat* ii required.
egozy CH, and Table IWD.-2500-1, Catqmics 0-A. r1J Prior io perfmmfq m. vr.2 visual enmi-D-B. 'and D-C. al applicable, far the 10-fgr system nadon. the &yStem shall b* pressurized to nmninal hydrostatic test? operaciq pieaun far
- mtnfnmm of 4 houn for in*
su1ated .,.ram md 10 mtnura for ncminsoJaccd 1)'1-tcnu. no~ lhaD .,. mamtl!Ded at nominal op-aatfq praiaxp~ duriq pcrfDmwM:c of the VT*l Rl/19: visual cnminlfioa.
(o) It is the opinion of th& CammittlMI that u an r-1> n. vr.2 Vllual 'f!nmin*iicm aball indade alcrmariYIS rem. 10-)'ear system lrjdrulbitfc teSt re- all compuunts within the boundaiy idcntiOed in qutred by Tablo IWB-~1. Caiepy B-P. the fol* (b)(2) above.
lawinl rules shall be uaed. (SJ Teat lmcrumantatlan rcqairmnena of IWA-(lJ A l)'ltem 1eakap iac (IWB-52%1) shall b9 5260 IR nm applioabJ&
ccnducied ai or ncar tba end of eadl impcaioa in- (c) It ism. apiDlon of m. Commiaa that. as an terY&L prier to reaccor surmp. altomaiive to m. 1o.,ar symm hyc1mltad.c test rc-(2) Tho bounduy subject m mt pnmurizadoll quind bJ Table IWI).2500-1 Cateptes D-A. D-B.
du.rinf th* l)'ltem leabp tolC shall mead co all or 0-C (D-B for the 1989 Ediliou with tha 1991 and 0ua 1 pteame rctainina CDmponalfl within the syl- subsequent Addenda).. u applicable. th* followin1 tcm boundary. rulu shall be UMd.
fJ) Prior m pcrtormiJll w. vr-2 vDuaJ e:ami* (I) A aymm pnman tat aha1l be conducted at nation. the system wll ba ~ to nomiAal ar near the dd of uda impec:ticla tntaiwl or durin1 operatin1 preaura far at lcar 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for imulated the same inlp9CtioD pcrlod of e8Ch impcc:don incer-.
systems and 10 minura far nozdmulaled J?SWmt. val of InspecDon Prasrmza B.
Tho system shall be mfilminsd u namtut opcradq (2) The bonnday mbjecc to ten prmurinticm presaure during perfarmmce of rhe VT-2 visual=* durina w system prean* wi sball a=d ta all auUnacica. m aa113 e. "'l""""'Nlll included them portians of.,,.
( 4) Test ccmperaaues and pra.suns shall iun tema required to opeiate m auppart tho saf;ty system exceed limitin& eondieicma fm ma bydrmladc test fimctiml up Ea and indudlng the first normally dosed m
curve as conramecl dw plant TICbnieaJ Specitlca- valve, indudia1 a safmty or relief valY8 or valw Q
- tianL pabl* of amomatic clolura when cha safety tunction (5) The vr_z vilual llftMfrqtim &hall lDdudc ii requin:d.
all .~ar widam me bounduy idcmfaed in (JJ Prior to petbm.lq tt. VT-2 visual C'Dmi*
(a}(2) above. nation. the System shall be ~ to nominal (6J Tesr imamuntadan 1"C4macmena: of J.WA- operadns praaun far ai leui .4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for imulated
.. 5260 UI n0t aPPlfclble. systems and 10 minura for Nmin1Pl1ted synrms.
"?bnt limeoptiUoa of th* Committc& thal. al an The system sball be mainWncd a' nominal apcnrln1 alternative to the 10.,Ur system hydrostatic ~ re- pressure dur1Dg performance of tho vr-2 visual CX*
quired by Table IWCZS00-1. Catepy CH. the fol* aminar:ion.
lowinl rules smll be used. (4) Th* VT*2 visual ennrinaticm lh.all lnclude (1) A system prasure tat shall be condw:ted at all componcma within the bounduy idCntiftad in or near the end of each inspoctiaa in~ or dmtn1 (c)(2) above.
th* same inspection period of Heh lnspcdion inter* (S) Test instnment:atian requirements of lWA-val of Inspcc:don Propm B. 5260 ue not applicable.
SUPP, I - NC
- CASES OF ASME BOILER AND PRESSURE VESSEL CODE CASE N-524 Approval Date: August 9, 1993 See Numerical Index for expiration and any reaffirmation dates.
Case N-524 Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping Section XI, Division 1 Inquiry: What alternative requirements may be ap-plied to the surface and volumetric examination of longitudinal piping welds specified in Table IWB-2500-1, Examination Category B-J, Table IWC-2500-1, Examination Categories C-F-1 and C-F-2 (Exam-ination Category C-F prior to Winter 1983 Adden-da), and Table IWC-2520, Examination Category C-G (1974 Edition, Summer 1975 Addenda)?
Reply: It is the opinion of the Committee that the following shall apply:
(a) When only a surface examination is required, examination of longitudinal piping welds is not re-quired beyond those portions of the welds within the examination boundaries of intersecting circumfer-ential welds.
(b) When both surface and volumetric examina-tions are required, examination of longitudinal piping welds is not required beyond those portions of the welds within the examination boundaries of inter-secting circumferential welds provided the following requirements are met.
(1) Where longitudinal welds are specified and locations are known, examination requirements shall be met for both transverse and parallel flaws at the intersection of the welds and for that length of lon-gitudinal weld within the circumferential weld ex-amination volume; (2) Where longitudinal welds are specified but locations are unknown, or the existence of longitu-dinal welds is uncertain, the examination require-ments shall be met for both transverse and parallel flaws within the entire examination volume of inter-secting circumferential welds.
903 SUPP. 6 - NC
