L-10-271, Cycle 16 & Refueling Outage 16 Inservice Inspection Summary Report
| ML102720180 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/23/2010 |
| From: | Allen B FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-10-271 | |
| Download: ML102720180 (236) | |
Text
{{#Wiki_filter:FENOC 5501 North State Route 2 FirstEnergyNuclear Operating Company Oak Harbor,Ohio 43449 Barny S. Allen 419-321-7676 Vice President- Nuclear Fax: 419-321-7582 September 23, 2010 L-10-271 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, License No. NPF-3 Davis-Besse Nuclear Power Station Cycle 16 and Refueling Outage 16 Inservice Inspection Summary Report In accordance with the 1995 Edition through the 1996 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI, Article IWA-6000, "Records and Reports,". enclosed is the summary report covering inservice inspection activities performed during operating cycle 16 and refueling outage 16 for the Davis-Besse Nuclear Power Station, Unit No. 1. This report provides a summary of the inservice inspection nondestructive examinations, once through steam generator tubing eddy current examinations, pressure tests, and repairs and replacements performed. There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager - Fleet Licensing, at (330) 761-6071. Sincerely, Bary Sen
Enclosure:
ISI Summary Report cc: NRC Region III Administrator NRR Project Manager NRC Resident Inspector Utility Radiological Safety Board Ohio Department of Industrial Compliance
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ISI
SUMMARY
REPORT CYCLE 16 and REFUELING OUTAGE 16R (16RFO) OUTAGE START DATE: February 28, 2010 OUTAGE COMPLETION DATE: June 29, 2010 REPORTING DATE: September 27, 2010 DAVIS-BESSE NUCLEAR POWER STATION UNIT No. 1 5501 North State Route #2 Oak Harbor Ottawa County, Oh 43449 OWNER: FIRST ENERGY NUCLEAR GENERATION CORPORATION 76 South Main St. Akron, Ohio 44308 NRC DOCKET NUMBER: 50-346 OPERATION LICENSE: NPF-3 COMMERCIAL OPERATION: July 31, 1978
16 RFO Inservice Inspection Summary Page 2 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 Prepared By: S.S. Hofelich lqlr4 4",.._.1:
- Date Reviewed By: D.J. Munson LdLn" Date Approved -By: T. A.I-lenline "ifilho Supervisor ---Programs Signature Date Approved By:
TchncalSer vices Manger- Signalture
16 RFO Inservice Inspection Summary Page 3 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 TABLE OF CONTENTS Section 1 ................................................................................. A bstract Section 2 .................................................................. Steam Generator Eddy Current Section 3 ........................................................................ NDE Manual Examinations Section 4 ........................................................................................ Pressure T ests Section 5 .......................................................................... Repairs and Replacements
16 RFO Inservice Inspection Summary Page 4 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 ABSTRACT This report provides a summary of the Inservice Inspection Nondestructive Examinations, Once Through Steam Generator (OTSG) Tubing Eddy Current Examinations, Pressure Tests, and Repairs/Replacements performed during Cycle 16 and the 1 6 th RefuelingOutage at the Davis-Besse Nuclear Power Station. The Inservice InspectionProgram is in compliance with the requirements of 10 CFR 50.55a, the 1995 Edition through the 1996 Addenda of the ASME Boiler and Pressure Vessel Code Section XI, and the Davis-Besse Unit #1 Technical Specifications. These examinations completed a portion of the examinations required for the second and third periods of the Third Ten Year Inservice Inspection Interval. The second period ended May'20, 2009 while the third period ends September 20, 2012. The Inservice Inspection Program nondestructive examinations, eddy current examinations, and pressure tests were performed by AREVA, FirstEnergy Nuclear Operating Company (FENOC) and Structural Integrity Associates personnel from March 2008 through completion of 16RFO on June 29, 2010. The NDE examinations consisted of Ultrasonic (UT), Liquid Penetrant (PT), Magnetic Particle (MT), Eddy Current (ET), and Visual (VT-1, VT-2, VT-3). Preservice and Inservice Inspection of approximately 180 ASME Class 1 and 2 components were performed. During UT examination of the Reactor Vessel Closure Head (RVCH) nozzles, twelve nozzles were found to have recordable indications. A concurrent Bare Metal Visual examination of the RVCH revealed pressure boundary leakage through Nozzle 4. Supplemental PT & ET examinations of the J-Groove welds were performed and these examinations confirmed an additional twelve nozzles requiring repair. In all, a total of twenty-four nozzles were modified per Relief Request RR-A34. The direct cause was Primary Water Strems Corrosion Cracking. The Root Cause evaluation can be found under Davis-Besse Condition Report 10-73323. Examinations of Class 1 and Class 2 components not related to the RVCH nozzle cracking met the acceptance criteria of ASME Section XI. Approximately 66 ASME Class 1 and 2 system leakage tests were conducted. In addition to the system leakage tests, pressure tests were also conducted following repair/replacement activities. The Bare Metal Visual Examination of the Reactor Vessel Closure Head revealed pressure boundary leakage through Nozzle 4. The remaining Class 1 and Class 2 pressure tests did not reveal any pressure boundary leakage. One hundred (100) percent of the in-service tubing in both Once Through Steam Generators (OTSG) was eddy current examined during the 1 6 th Refueling Outage. Steam Generator Tubes which required removal from service exhibited, similar indications that have been reported in previous eddy current inspections. Similar degradation has also been observed at other B&W design Steam Generators. In the 16th Refueling Outage, 81 tubes in Steam Generator 1-2 and 98 tubes in Steam Generator 1-1 were removed from service. Several Alloy 600 components were mitigated via weld overlays during 16RFO. Full Structural Weld Overlays (FSWOL) were applied to the (2) Core Flood Nozzle Welds, (4) Reactor Coolant Pump Suction Welds, and (3) Reactor Coolant System Cold Leg Drain Welds. Optimized Weld
16 RFO Inservice Inspection Summary Page 5 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 Overlays (OWOL) were applied to the (4) Reactor Coolant Pump Discharge Welds. Pre-service examination of all overlays were performed post-mitigation per NRC approved Relief Requests RR-A32 & RR-A33. All repair/replacements performed at Davis-Besse are controlled via Davis-Besse's Work Order system. Copies of Davis-Besse's Repair/Replacement NIS-2 forms for ASME Class 1 and 2 repairs/replacements are included in this report. All other records including testing and examination records are sent to the FirstEnergy Enterprise Records Management System.
16 RFO Inservice Inspection Summary Page 6 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 FORM N18-.1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As roqjuIreci by the Po sn (or UASM5 0000 R1.110 1.0,i lIh~tyNeo OrongOnny76SMsnSAonOo '8______ (Nanio ond Adcdre-ss of Owner) 2,. vi-lu Pwrilon50tN8u 1lonI 2O it'.en }Harbor, Ohio0 434'l9 (NnIow nad AddIress of Plant) 3, Nl'lnt nItn I 4. Owner C01icatno ofAuil loylzallon (Ifrc idretI) N/A S. Cotnn11croioil Sorvko DA10 J113,91 6. Nalltlonn 13ornd unmber f'or Unil NIA iinufhitbroror coinlomcml or Mntndhrhwrr D( Slnlo 0'r __APp!nvlnaonco Immullur NovInvo-Nis, ljonrd i4o, 620-0]14-055-12, 01's(11-1 t31aicudl & Wilcox hanif to2 - WA 1+159 - PTS.O3 I-2 . )ubcock Wilcox 1/nIl /I NA W____ N-158 Now~ 91iPP10ie11AtIshu s III ibanlrist%, s1rulis, of diýIiWJgs u4b ~~I ivk I) Is3%4In.x 11Ilt., (2.)fitfolntntiwt Iafwit lcs I IIIOaL416 Oil tills rq1pomI Isft~iloIocSI oil rwh i;Iecl, Andt (3)e.10sli 6tcN1 Is nikilillW;odt (Itotuu1ntsrt orsfit ces lb reeonitcu nitti top otrIits ronti, I ist 116111(101~9) oa tt SI($~Dp.~ lay.oiln sw Ddtti'e NJ 00 2)(D~*3O
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16 RFO Inservice Inspection Summary Page 7 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
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16 RFO Inservice Inspection Summary Page 8 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 STEAM GENERATOR EXAMINATION RESULTS The ASME Class 1 tubing in the Once-Through Steam Generators (OTSGs) at the Davis-Besse Nuclear Power Station Unit #1 (DBNPS) was examined in March 2010, during the 16 th Refueling Outage (16RFO). The examinations were conducted by Areva to meet the requirements of the DBNPS.Technical Specifications as required by Examination Category B-Q. All examinations met the requirements of techniques qualified in accordance with the PWR Steam Generator Examination Guidelines. No ASME Code Cases are applicable to the examination of Steam Generator Tubing. The 16RFO inspection scope was similar to the inspection completed during 15RFO and included comprehensive inspections for all active and potential degradation mechanisms. The findings of the 16RFO inspection were similar to those predicted in the 15RFO Operational AgSessment. Although the number of indications exceeded the number predicted for some degradation mechanisms, the severity of the degradation was at or below the projected levels for all degradation mechanisms detected. The inspection results are recorded in Condition Report 10-74043. Eddy current examinations were performed utilizing the Bobbin Coil probe and rotating Plus Point probe. The bobbin coil technique was used to perform the standard ASME Code examination for flaw detection. Table 1 summarizes the number and extent of tubes inspected in each OTSG during 16RFO. OTSG 1-B had 46 tubes with lower roll transition or lower tube end Primary Water Stress Corrosion Cracking (PWSCC). Of the 46 tubes, 41 contained single or multiple circumferential indications and five contained axially oriented PWSCC. All of these tubes were plugged because of difficulties in previous outages in obtaining adequate diametric expansion in lower head repair rolls. Cracking of the original roll transition in the upper tubesheet was reported in six tubes that hadn't been rerolled in a previous outage (three in OTSG 2-A and three in OTSG 1-B). A 2 volt leakage criterion for PWSCC is defined in the in situ pressure test screening document. None of these indications exceeded the 2 volt criterion. A 100% Plus Point coil upper roll expansion exam was completed so no inspection expansion was necessary for this damage mechanism. The number of indications was as predicted. Four tubes had indications that could have potentially contributed to leakage during a Large Break Loss Of Coolant Accident (LBLOCA) due to a radius location of greater than 55" and a depth of greater than 60% through wall. The affected tubes were 124-101, 136-1, 142-65, and 151-10, all in OTSG 2-A. All four of these tubes were removed from service to remove them -from the population of LBLOCA leakage contributors. There were no indications in OTSG 1-B that met these criteria for being a LBLOCA leakage contributor. In addition to the four tubes mentioned above, two additional tubes had circumferential indications outside the 55" radius. These tubes, 1-14 and 118-107, both in OTSG 2-A, had depths less than 60%TW. Tube 118-107 also had a groove IGA indication and was, therefore, already scheduled to be plugged. The circumferential indication in Tube 1-14 was initially detected in 14MCO and has grown steadily in both voltage and measured depth since 14RFO. To avoid the potential concern for leakage contribution for the LBLOCA accident conditions, Tube 1-14 was
16 RFO Inservice Inspection Summary Page 9 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 also removed from service by plugging. Davis Besse is licensed for repair roll joint slippage during accidents, but plugging these tubes that could exceed the 60%TW threshold at the next inspection makes the evaluation for LBLOCA leakage more easily managed in future outages. Again, there were no such indications in OTSG 1-B. A 100% Plus Point coil examination of repair roll expansions was completed so no inspection escalation was necessary for this damage mechanism. Tube end cracking was also detected at the tube end weld heat affected zone where PWSCC of 96 upper tube ends in OTSG 2-A and 51 upper tube ends in OTSG 1-B was observed. These counts only include tubes that hadn't been repair rolled in a previous outage. Most of these indications were axial, however one circumferential indication was observed in the upper tubesheet tube end of Tube 136-1 in OTSG 2-A. This damage mechanism only contributes slightly to leakage since only those indications over 2 volts by Plus Point probe are assumed to leak. There were 31 upper tube end cracks that exceeded 2 volts by Plus Point and thus were assumed to leak. However, these tubes pose no threat to steam generator integrity since the leakage must pass the mechanical roll in the tubesheet. A 100% Plus Point coil exam of upper tubesheet tube ends was complete so no inspection escalation was necessary for this damage mechanism. The number of indications was less than predicted. A total of 29 tubes had degradation reported in an upper tubesheet repair roll expansion (24 in OTSG 2-A and 5 in OTSG 1-B). Most of these indications were axial PWSCC in the heel transition of previously installed repair rolls. This degradation was first reported during 15RFO. During 16RFO, there were also 4 tubes with circumferential PWSCC, 2 tubes with volumetric indications, and 2 tubes with SCC in the toe transition of repair rolls. One tube also had both circumferential and volumetric degradation associated with a repair roll. None of these indications were large enough to result in predicted accident leakage. These tubes were plugged to remove them from service. At the time of this inspection there were 131 repair rolls in service in OTSG 2-A and 31 in service in OTSG 1-B. The overall number of indications in rolled regions in the upper tubesheet was in line with expectations. The number of axial PWSCC was slightly underpredicted, but the number of circumferential PWSCC indications was slightly overpredicted. Since a 100% exam had been performed for this damage mechanism, no inspection scope expansion was required. Freespan volumetric degradation was observed during 16RFO in Tube 17-82 in OTSG 1-B. This indication was located just below the 15th TSP. This indication was small and not a challenge to tube integrity. During the 15RFO inspection, there were 18 similar indications reported. Therefore, the one indication reported during 16RFO inspection was less than the predicted number of indications. The volumetric IGA is likely due to the presence of sludge deposits building below the drilled region of the 15th TSP. This tube was plugged: Since a 100% bobbin exam was performed, no inspection expansion was required. The number of wear indications continues to.increase in each steam generator. This is because wear is a progressive damage mechanism, and also there is more consistent reporting of wear that is located at the top and bottom of a TSP as two separate wear indications, rather than one wear call for the two indications. During 16RFO, there were 786 wear indications reported by bobbin in OTSG 2-A and 423 wear indications reported by bobbin in OTSG 1-B. There was one location with a Plus Point wear call that had no corresponding bobbin wear call (Tube 65-2 in OTSG 1-B at 15S). This location was inspected with rotating Plus Point due to a bobbin Non-Quantifiable Indication (NQI) call and was confirmed as an 11 %TW wear indication with Plus Point. This,
16 RFO Inservice Inspection Summary Page 10 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1.,5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 therefore, brings the total number of unique wear indications to 424 in OTSG 1-B. All of the wear indications measured less than 40% TW. The deepest wear indication in OTSG 2-A was 27% TW and the deepest wear indication in OTSG 1-B was 23% TW. There were no cracks observed in any of the wear indications that were examined with the Plus Point coil. There were no Possible Loose Part (PLP) indications, or indications of foreign object wear detected by either the bobbin or special interest exams. The Plus Point examination of the tubesheet crevice regions did not identify any indications of degradation. Therefore, no scope expansions were required. The most limiting observed degradation is considered to be Axial Freespan ODSCC / IGA, (Groove IGA) which was first discovered during 13RFO. This damage typically forms in the upper regions of the periphery of the tube bundle in axial scratches on the tube surfaces that occurred while inserting tubes in the OTSGs during manufacturing. There were 37 of these indications in 25 tubes in OTSG 2-A and 65 indications in 36 tubes in OTSG 1-B detected. Although the particular flaws (102 total) identified during 16RFO were fairly small, industry experience shows that the behavior of this damage can be a dominant factor in determining the remaining life of the OTSGs and can limit the cycle length of a plant where this degradation is severely'developed. The number of indications predicted for this mechanism for the limiting steam generator in the previous Operational Assessment evaluation was 39. Although the number detected was higher than the prediction, the severity of the indications was in line with expectations. The largest groove IGA indication measured 0.55 volts by Plus Point coil and had a measured length of 2.76 inches. None of the observed indications were large enough to challenge tube integrity. Therefore, no in situ pressure testing was required for this degradation mechanism. A 100% bobbin exam was completed so no inspection escalation was necessary. It should be noted that prior to 15RFO this mechanism was limited to above the- 14th TSP. However during both 15RFO and 16RFO, groove IGA was observed as low as the 10th TSP in OTSG 1-B, while still limited to above the 14th TSP in OTSG 2-A. The mechanism continues to occur predominately in the periphery of the OTSGs. Another significant item of interest is that no cracks in dents were detected during 16RFO. Dents can act as initiation sites for SCC and can also mask true degradation. Due to prior experience at other OTSG plants, this issue is taken very seriously at Davis Besse as demonstrated by the aggressive inspection scope on identifying and inspecting dents. A visual exam (VT-1) was performed of all installed welded plugs due to indications of slight primary-to-secondary leakage. Theinspection identified one potentially leaking plug in the lower tubesheet of OTSG 1-B in tube 73-117. The plug was one of the original Mk 500 welded plugs installed prior to placing the OTSGs in service. This plug was successfully removed and replaced, with a rolled plug. The 16RFO repairs bring the cumulative plugging to 706 (4.6%) tubes plugged in OTSG 2-A and 377 (2.4%) tubes plugged in OTSG 1-B. Since the installed sleeves also affect the flow, an equivalent plugging value can be assigned for the installed sleeves. The sleeves installed at DBNPS have been evaluated at a plugging equivalency factor of 1 / 6.7 for installed sleeves. Thus the 199 installed sleeves in OTSG 2-A are equivalent to 30 plugged tubes, and the 212
16 RFO Inservice Inspection Summary Page 11 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 installed sleeves in OTSG 1-B are equivalent to 32 plugged tubes. The plugging equivalency for OTSG 2-A is then 736 tubes (4.8%) and for OTSG 1-B is 409 tubes (2.6%). Prior to 16RFO, there were 131 repair rolls in service in OTSG 2-A and 31 repair rolls in service in OTSG 1-B. Due to various reasons including cracking in the heel transition (upper roll transition) of the repair roll, 28 tubes with existing repair rolls in OTSG 2-A and 7 tubes in OTSG 1-B were removed from service. This left 103 existing repair rolls in OTSG 2-A and 24 in OTSG 1-B. During 16RFO, repair rolls were installed in 65 tubes of OTSG 2-A and in 45 tubes of OTSG I-B. The final count was 168 repair rolls in OTSG 2-A and 69 repair rolls in OTSG 1-B remaining in service. Table 1: Summary of Steam Generator Inspection Scope uring 16RFO OTSG 2-A OTSG 1-B Inspection of all newly installed repair rolls 65 45 Periphery AFW Header to tube gap exam 366 396 Full length bobbin exam of all in-service non-sleeved tubing (100%) 14832 15178 Full length bobbin exam of sleeves (100%) 199 212 Plus Point exam of the sleeve at the point of entry (USE) and parent tube 199 212 pressure boundary portion extending approximately 6 inches past the sleeve end (LSE) of the sleeves (the parent tube between the bottom of the upper most sleeve roll and the top of the middle sleeve roll may be excluded from inspection since it is not a pressure boundary) (100%) Plus Point exam of non-sleeved in-service upper tube roll expansions 14633 14966 including non stress relieved upper repair roll expansions and factory re-rolls (100%) Plus Point exam of the non-sleeved in-servide tubes in the upper tube sheet 7317 8442 region from tube end including tube end, upper roll expansion and crevice to upper tube sheet exit (50%) Plus Point exam of in-service stress relieved lower tube roll expansions and 3126 15178 tube ends Plus Point exam of the tubes bordering the sleeve region 89 80 Plus Point exam of all of the flaw-like indications (I codes, TWD, and new 114 708 dents) reported from bobbin Plus Point exam of all Non Quantifiable Signal (NQS) and Manufacturing 111 110 Burnish Mark (MBM) indications above 1OS-2" Plus Point exam of all dent indications below 14S (100% sample of all 90 112 previously reported and new dents using a >2.5 volt bobbin threshold) Plus Point exam of all dent indications greater than or equal to 1 volt above 208 298 14S in the non-periphery region Plus Point exam of all dent indications greater than or equal to 0.5 volts 18 11 above 14S in the periphery region Plus point exam sample of the defined lower tubesheet sludge pile region 1447 1709 tubes (50%) Sleeve bobbin and Plus Point exam of all previously identified geometric 0 40 distortions Plus Point exam of all previously identified and new magnetic stain (MAG) 0 23 indications Plus Point exam of the Hot Leg rolled Plugs (20%) 121 54 Visual Welded Plug Exam (VT-I) (100%) 33 19 Visual Plug exams of all Plugs in Upper and Lower (100%) 1250 558 Total Exams 45218 58351
16 RFO Inservice Inspection Summary Page 12 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978' VORM NIS~.1 OWNER'S RE~POR~T FOR INSEiRVICIE WSPE-0TION53 ALs roqlufroc by (fie Provlsfon., of tho ASM1E Gode Mil~os I. Owiler l1 i:UW~qrgX Nno!nr Ov~ornfling Conponiy, 76 8. 4il S, A1ron, oilo '14303 (Nftno nnd Addrosý of 0%mer) 2.,nC1lnlion )ws1os ~ln 'wl SI N. Sla~eh, 2,0k ~Iflnihor, Ohio 113(119 5~ Coiircnl MIDnl l~~T7 6, 1Nniiooo1 liowu'd Noiflflivrfor /
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16 RFO Inservice Inspection Summary Page 13 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 F'ORM NIS.1 (Bueck) 8, 1ntoinfllnta) DaMs March 200R to 11n12010 9, bnprotioo l'vdod ldonttficalon:
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.13tle cr[g11yof,LvnLr~vrltic i.q2co. BY.sW A &
C('IVJVATI 01? INSui\C'lICT IOPPIlCTION I, itianodersIg¢ied, hioldhing n VAIlid colmtissifol Islited by thi Nallolatl Doerih of holloir iiiii Ps'ssluo V'ssi'lnspeolors amil (hla State or Provnceo of 01h[o tald e1ni*la)yed by' llatfonW stwain h0oller.o.. hinslptonl of
& liisuran,.o hln fr0Fdl CQonIeetlcit btmv, Inspected 111o colponeollnts dosudlbhed Inl Jils Owinr's Reporl dtodnig ilia Ierlod HIdIih9.(008 - It Joue2010 alilitto1 athdto ll* best ofnIly knowteilgeI aiid bti Adl'o Owellrl Ilas pci*eioliled exilllitlominills mitd tests Rod InlSi corCOtCll' measures dlscrlbd II (hils Owner's Report In accontoanco wilh bow Inspllo;Plat )'afa Pd as rctolurd by Iho ASMB CoiltlSectoi XI. d at' Im~plied, conceomningl
*By slgnttng this :etll~lcawt neoitlhr the Inspector nor his eniploycranko cay, warntaily, e:oprs.'l)o l11o oxililditiloll,:, tesls, nod corrveIvo'i)tasireos d*scribcd hIithis Ownler's Ivlolt. Piilhirim*tiro, oeilltor Iho IlisljvitQr 1101 Ills oeplo'yor slhall lie liafbl Ilnalny mlanlnet for fally per-'sonal hdiny or li.operly dnllage, or it loss oftily kiLd aling 11-01i1or VL ancled wlltV lnit l "hin lelolle-. E. 21 his~lror';,*81gimt!. *{~tllll ll, 'o~lOnld fi I-Hiltiwols.ll*~'
16 RFO Inservice Inspection Summary Page 14 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 NONDESTRUCTIVE EXAMINATIONS Nondestructive Examinations were completed by AREVA, FENOC, and Structural Integrity Associates personnel from the end of 15RFO through the completion of 16RFO (June 2 9 th, 2010) at the Davis-Besse Nuclear Power Station. These examinations completed a portion of the examinations required for the second and third periods of the Third Ten Year Inservice Inspection Interval. The second period ended May 20, 2009 while the third period ends September 20, 2012. Inspections were performed to meet the requirements of ASME Section XI 1995 Edition through 1996 Addenda. The number and percentage of ASME Class 1 and 2 and Containment examinations completed are outlined below.
16 RFO Inservice Inspection Summary Page 15 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31. 1978 Davis-B3SSess.NceajPn
- Completionn Code Com -pliance Summary - 3rd Interval - 3rd Period ISI - Code Edition - 1995 Edition/1996 Addenda Period 3 Total Total Total [ % Comp. to Cat. Item No. Description Required Sched Comp Sched Comp. Cumin % Date B-A 81,11 Reactor Vessel Circumferential Shell Welds 3 3 0 3 0 0% 0%
B-A B1,21 Reactor Vessel Circumferential Head Welds I 0 1 0 0% 0% B-A B1.30 Reactor Vessel Shell-to-Flange Weld 1 I 0 1 a 0% 0% B-A B1.40 Reactor Vessel Head-to-Flange Weld I 0 1 0 0% 0% B-A Pressure Retaining Welds in Reactor Total: Vessel 6 6 0 6 0 0% 0% Pressurizer Shell-to-Head Welds B-B B2,11 Circumferential 2 1 1 1 0 50% 50% Pressurizer Shell-to-Head Welds B-8 B2.12 Longitudinal 2 1 1 0 50% 50% Steam Generators (Primary Side) Head 8-B B2.31 Welds Circumferential 1 0 1 0 0 100% 100% Steam Generators (Primary Side) Tubesheet-8-B B2.40 to-Head Weld 2 0 2 0 1 100% 100% B-B Pressure Retaining Welds in Vossels Total: Other than Reactor Vessels 7 2 5 2 1 72% 72% Reactor Vessel Nozzle Inside Radius B-D B3.100 Section 8 8 -0 8 0 0% 0% 2 3 2 0 50% 1 50% B-D 13.110 Pressurizer Nozzle-to-Vessel Welds 6 B-D B3.120 Pressurizer Nozzle Inside Radius Section 6 2 3 2 1 50% 1 50% Steam Generators (Primary Side) Nozzle-to-B-D B3.130 Vessel Welds 6 5 I 84% 1 84% Steam Generators (Primary Side) Nozzle B-D 83.140 Inside Radius Section 6 5 84% 1 84% B-D B3.go Reactor Vessel Nozzle-to-Vessel Welds 8 8 0 8 0 0% 0% B-D Full Penetration Welded Nozzles In Total: Vessels 40 22 16 22 3 40% 1 40% Head with N06600 Nozzles and UNS N06082 or UNS W86182 Partial Penetration. B-E 84.10 Welds 1 1 100% 1 100% UNS N06600 Nozzles and UNS N06082 or UNS W86182 Parlial-Penetration Welds In 1 1 B-E B4.20 Head 1 1 100% 1 100% B-E 2 2 2" 2 100% 1 100% Total: Class I PWR Reactor Vessel Upper Head 2 Reactor Vessel NPS 4 or Larger Nozzle-to-B-F B5.10 Safe End Butt Welds 2 2 0 2 0 0% 0% B-F Pressure Retaining Dissimilar Metal Total: Welds In Vessel Nozzles 2 2 0 2 0 0% 1 .0% B-G-1 B6.10 Reactor Vessel Closure Head Nuts 60 12 48 12 12 80% 80% B-G-1 B6.180 Pumps Bolts and Studs 16 0 16 0 8 100% 100% B-G-1 B6.190 Pumps Flange Surface 0 0 1 0 0 0% 0% B-G-1 B6.200 Pumps Nuls. Bushings, and Washers 16 2 14 2 6 88% 88%
16 RFO Inservice Inspection Summary Page 16 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 Davis-Besse Nuclear Plant Completion Code Compliance Summary-- 3rd Interval - 3rd Period ISI - Code Edition - 1995 Edition/1996 Addenda Period 3 Total Total Total % Comp, to' Cat. Item No, Description Required Schad Comp Sched Comp. Cumin %I Date Reactor Vessel Closure Studs, When Reactor Vessel Closure Studs, When B-G-1 B6.30 Removed 60 12 48 12 12 80% 80% B-G-1 B6.40 Reactor Vessel Threads in Flange 1 0 1 0 1 100% 100% B-G-1 B6.50 Reactor Vessel Closure Washers, Bushings 62 12 50 12 12 81% 81% B-G-1 B6.60 Pressurizer Bolts and Studs 12 4 8 4 0 67% 67% B-G-1 B6.70 Pressurizer Flange Surface 0 0 0 0 0 0% 0% B-G-1 B6.80 Pressurizer Nuts, Bushings, and Washers 12 4 8 4 0 67% 67% B-G-1 Pressure Retaining Bolting, Greater than Total: 2 in In Diameter 239 46 194 46 51 82% 82% B-G-2 B7.20 Pressurizer Bolts, Studs, and Nuts 3 0 1 0 0 34% 34% B-G-2 B7.30 Steam Generator Bolts, Sluds, and Nuts 4 1 3 1 0 75% 75% B-G-2 B7.50 Piping Bolts, Studs, and Nuts 10 2 0 0 20% 20% 13 1 1 0 8% 8% B-G-2 B7.70 Valves Bolts, Studs, and Nuts B-G-2 Pressure Retaining Bolting, 2 in. and Total: Less In Diameter 30 2 7 2 1' 24% 24% Piping NPS 4 or Larger Circumferential 34 20 18 20 4 53% 53% B-J 89.11 Welds Piping Less than NPS 4 Circumferential B-J B9.21 Welds 43 11 32 11 8 75% Piping Branch Connection Welds NPS 4 or B-J B9.31 Larger 1 0 2 0 0 200% 200% Piping Branch Connection Welds Less Than B-J B9.32 NPS 4 3 1 5 1 1 167% 167% B-J 89.40 Piping Socket Welds 10 2 9 2 2 90% 90% B-J B9.50 Full Structural Weld Overlays 5 14 14 20% 20% 1 0 0 0 0 0% 0% B-J B9.60 Optimized Weld Overlays B.J Total: Pressure Retaining Welds in Piping 97 48 67 48 16 70% 70% 2 1 50% 50% 13-K B10.10 Pressure Vessels Welded Attachments 1 2 3 1 0 150% 150% B-K B10.20 Piping Welded Atiachments B-K Welded Attachments For Vessels, Piping, Pumps, and Valves 4 2 4 2 1 100% 100% Total: B-L-1 B12.10 Pumps Casing Welds 4 4 0 4 0 0% 0% B-L-1 Pressure Retaining Welds in Pump Total: Casings 4 4 0 4 0 0% 0% B-L-2 B12.20 Pump Casing 0 0 1 0 0- 0% 0% B-L-2 Total: Pump Casings 0 0 1 0 0 0% 0% B-M-2 B12.50 Valve Body. Exceeding NPS 4 0 0 3 0 0 0% 0% B-M-2 Total: Valve Body, Exceeding NPS 4 0 0 3 0 0 0% 0% B-N-1 B13.10 Reactor Vessel, Vessel-Interior 1 0 1 0. 0% 0% B-N-1 Total; Interior of Reactor Vessel 1 .1 0 1 0 0% 0% Reactor Vessel (PWR) Interior Attachments B-N-2 B13.60 Beyond Beltline Region 12 12 0 12 0 0% 0% B-N-2 Welded Core Support Structures and Total: Interior Attachments to Reactor Vessel 12 12 0 12 0 0% 0%
16 RFO Inservice Inspection Summary Page 17 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
- i Davis-Besse Nuclear Plant Completion Code Compliance Summary - 3rd Interval - 3rd Period ISl - Code Edition - 1995 Edition/1 996 Addenda Period 3 Total Total Total % Comp. to Cat, Item No. Description Required Sched Comp Sched Comp. Cumin % Date Reactor Vessel (PWR) Core Support B-N-3 B13.70 Structure 1 1 0 1 0 0% 0%
B-N-3 Total: Removable Core Support Structures 1 1 0 1 0 0% 0% B-0 B14.10 Reactor Vessel Welds In CRD Housing 13 1 16 1 10 116% 116% B-O Pressure Retaining Welds in Control Rod Total: Housings 13 15 1 10 116% 1 116% Pressure Vessels Shell Circumferential C-A C1.10 Welds 2 3 2 2 43% 1 43% Pressure Vessels Head Circurnferetlai C-A C1.20 Welds I 0 0 100% 1 100% C-A C1.30 Pressure Vessels Tubesheet-to-Shell Welds 2 2 0 100% 1 100% C-A Pressure Retaining Welds in Pressure Total: Vessels 10 6 2 " 3 60% 1 60% Nozzles Withoul Reinforcing Plate in Vessels > 1/2in. Nominal Thickness - Nozzle C-B C2.21 to Shell Weld 6 3 0 50% 1 50% Nozzles Without Reinforcing Plate in Vessels > 1/2in. Nominal Thickness Nozzle C-B C2.22 Inside Radius Section 3 I 0 34% 1 34% Nozzles With Reinforcing Plate in Vessels > 1/2in. Nominal Thickness Reinforcing Plate C-B C2.31 Welds to Nozzle and Vessel 3 75% 1 75% Nozzles With Reinforcing Plate in Vessels > 1/21n. Nominal Thickness Nozzle-to-Shell (or Head) Welds When Inside of Vessel is C-B C2.33 Inaccessible 2 2 0 2 0 0% 1 0% C-B Pressure Retaining Nozzle Welds in Total: Vessels 15 5 7 5 47% I 47% Pressure Vessels Integrally Welded C-C C3.10 Attachments 2 0 1 0 0 50% 50% C-C C3.20 Piping Welded Attachments 26 6 22 6 6 85% 85% C-C C3.30 Pumps Integrally Welded Attachments 3 0 3 0 1 100% 100% C-C Welded Attachments For Vessels, Piping, Total: Pumps, and Valves 31 6 26 6 7 84% 84% C-D C4.30 Pumps. Bolts, and Studs 20 8 4 8 0 20% 20% C-D Pressure Retaining Bolting, Greater than Total: 2 in In Diameter 20 8 4 8 0 20% 1 20% Piping Welds >/= 3/tin. Nominal Wall Thickness for Piping > NPS 4 C-F-1 C5.11 Circumferential Welds 4 1 3 1 75% 1 75% Piping Welds < 3/Sin. & > 1/5in. Nominal Wall Thickness for Piping > NPS 4 C-F-1 C5.11A Circumferential Welds 28 6 22 6 6 79% 79% Piping Welds <= 1/5in. Nominal Wall C-F-1 C5.1 1B Thickness for Piping > NPS 4 14 2 11 2 3 79% 79% Piping Welds> 1/5in. Nominal Wall Thickness for Piping >1= NPS 2 and <4= NPS C-F-I C5.21 4 Circumferetial Welds 23 4 19 .4 7 83% 1 83% Piping Welds < 1/5in. Nominal Wall Thickness for Piping >/= NPS 2 and <1= NPS C-F-1 C5.21A 4 Circumferential Welds 13 2 11 ,2 3 85% 1 85%
16 RFO Inservice Inspection Summary Page 18 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 Davis-Besse Nuc earl a Completion Code Compliance Summary - 3rd Interval - 3rd Period IS - Code Edition - 1995 Edition/1 996 Addenda Period 3 Total Total Total % Comp. to Cat. Item No. Description Required Sched Comp Sched Comp. Cumin % Date C-F-1 C5.30 Socket Welds 8 2 6 2 2 75% 75% Pipe Branch Connections of Branch Piping C-F-1 C5.41 >1= NPS 2 Circumferential Weld 2 1 1 1 0 50% 50% C-F-1 Pressure Retaining Welds in Austenltic Total: Stainless Steel or High Alloy Piping 92 18 73 18 22 80% 80% Piping Welds >/= 3/8in. Nominal Wall Thickness for Piping > NPS 4 C-F-2 C5.51 Circumferential Welds(l) 19 3 17 3 90% Piping Welds < 3/8in. Nominal Wall Thickness for Piping > NPS 4 C-F-2 C5.51A Circumferential Welds 10 2 8 2 2 80% 80% Pipe Branch Connections of Branch Piping C-F-2 C5.81 >/= NPS 2 Circumferential Weld 2 0 2 0 1 100% 100% C-F-2 Pressure Retaining Welds In Carbon or Total: Low Alloy Steel Piping 31 5 27 5 8 88% 88% C-G C6.10 Pump Casing Welds 3 1 2 0 67% 67% C-G C6.20 Valve Body Welds 4 0 4 0 2 100% 100% C-G Pressure Retaining Welds In Pumps and Total: Valves 7 1 6 2 86% 86% E-A E1.11 Accessible Surface Areas 1 0 1 1 0 100% 100% E-A E1.12 Accessible Surface Areas 1 0 0 0% 0% E-A Total: Containment Surfaces 2 1 1 1 0 50% 50% Required Augmented Examination, Surface Area Grid, Minimum Wall Thickness E-C E4.12 Location 0 0 1 0 0% 0% E-C Containment Surfaces Requiring Total: Augmented Examination 0 1 0 1 0 0% 0% E-D E5.30 Moisture Barriers 2 2 0 2 0 0% 0% E-D Total: Seats, Gaskets, and Moisture Barriers 2 2 0 2 0 0% 0% E-G EB80 Bolted Connections 57 16 41 16 9 72% 72% E-G Total: Pressure Retaining Bolting 57 16 41 16 9 72% 722% F-A F1.10 Class 1 Piping Supports 25 7 20 7 5 80% 80% F-A F1.20 Class 2 Piping Supports 79 18 64 18 15 82% 82% Supports other than Piping Supports (Class F-A F1.40 1, 2, and MC) 23 6 15 6 4 66% 1 66% F-A Total: Supports 219 51 173 51 43 79% 1 79% Grand Totak 944 267 678 267 180 19% 172%
16 RFO Inservice Inspection Summary Page 19 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 ASME Class 1 and 2 Examinations: The specific Class 1 and 2 examinations completed during Cycle 16 and the 1 6th Refueling Outage are identified on the attached table. Conditions requiring evaluation are noted in the referenced Condition Reports.
DAVIS-BESSE NUCLEAR POWER STATION UNIT #1 Class 1, Class 2, and Containment Examinations 16th Refueling Outage Wri Sumhmary No Component ID.. . . . Examination Exam:Date Conditionr Fin~al Status:;o 1 ntC S .ope
. Report No .Reprt i. .. =_
Number 'iL Examination Category B-B, 'Pressure Retaining Welds in; Vessels Other, Than Reactor Vessel I rZZ ISI B02.040,215000 RC-SG-1-1-WG-58-2 16-UT-058 4/1/2010 Accept r< CD Ex*amination Category 8-0, FullPenetration WeldedNozzlles in Vessels *,,,*, I I I SI. 3.. 03.120.01400 RC-PZR-WP-33-Z/W-IR . 16-UT-023 318/2010 Accept i1;1 B030 .130.21 5200 RC-SG-1-1-WG-50z-ZZ/Y 16-UT-020 313/2010 Accept Reflef'R'u.., a fo C limtedexrrinatonobverage', : SI B03.140.215600 RC-SG-1-1-WG-50-ZJY-IR 16-VT-117 318/2010 Accept ExaminationiCategory B:E, Class...R ectr* Vesel ppe#ea........ " .. :..,..!
. . y".' . I. ii : . ':
[SI 804,020.098300 RC-RVCH-CRDM-NOZZLES 16-VENDOR-016 5/26/2010 10-73323 Eval CR 10-73323 Root Cause describes 0 0 evaluation I repair. Acceptable 5 9 preservice examinations performed after repair per RR-A34 0 . AUG 0 A8400.9 RCRCH-CRDM-NOZZLES. 16-P-04 /2-010 '10-746340 Reject " F1' b'ýf,ýj6~ltas:l'SW6CS'
. . .ev=luati6 " Acceptable'
- 'prsrv; exmntin eo~ after :
reaprRA34' RR :,x AUG B04.020.098300 RC-RVCH-CRDM-NOZZLES 16-PT-050 3/30/2010 10-74640 Eval CR 10-73323 Root Cause describes evaluation / repair. Acceptable preservice examinations petformed after repair per RR-A34 AUG Bd4m.:020.098300b RCIkRVCH-.CRDM-NOZZ ES .- ,:6-PT-051 3/2012010 1C-76401&4Reject C173Rt
.,S Ca Ue'cri6 es
.evaluatiýn:/ repair. AcýIeP~table, 0
;.es~vc 'eaiaos pefo ýý after. ~
AUG B04.020.098300 RC-RVCH-CRDM-NOZZLES 1:6-PT-052 3/3012010 10-74640 Eval CR 10-73323 Root Cause describes evaluation I repair. Acceptable preservice examinations performed after C) repair per RR-A34 .. .0 0t RV CH-CR DM-NOZZ LES 6
- RC 0 .5 - 3./3 0/20Y0 .7 1 Acce0 ... . . .. ..
A U GM 0 AUG B04.020.098300 RC-RVCH-CRDM-NOZZLES 16-PT-054 3/30/2010 10-74640 Eval CR 10-73323 Root Cause describes evaluation / repair. Acceptable preservice examinations performed after repair per RR-A34 AUG. "0f4.02009830 RC-RVCH-CRDM-NOZZLES 16-'PT-055 /302010 I N174640 Reject ICR 10-72 ;oi36*tFo'o'dd'is'- ' I , ,~ eva uation Ji'rE pair,4iqbpt~le, '0 Iipes~~;iatiio s'performediafter 1 AUG 804. 020.098300 RC-RVCH-CRDM-NOZZLES . 6-PT-056 .3/30/200 AcceApt Accept repair01 ,', 'K '
DAVIS-BESSE NUCLEAR POWE R STATION UNIT #1 Class 1, Class 2, and Containn ient Examinations 16th Refueling Or.atage AUG B4.020.098300 RC-RVCH-CRDM-NOZZLES 16-PT-057 u3/0/20i0i: 10-74640' Rejec it*1 R'7 10,k
-73323 Root Cause'describes' 1'
... .. /.repair. Acceptable F
/evaIuation F 11FF ;presevceeexaminations F jperformed'afte*j 0 I i FF w Ft FFreparr per RR-A34 FFF CD AUG 804.020.098300 RC-RVCH-CRDM-NOZZLES 16-PT-058 3/30/2010 Accept AUG B04.020-09,8300 RCRvcH-CRDMk-*NOZZLES 1.6-PT-059 3/3012010 10G-74640 Eval F CýR 10'73323RootCaVse describe'sFF' C)
F evaluiationF/ repair. Acceptable', F p.rapreservice
- Iexaminations 5erfornrie':after "F, 00 0
'F epair per RR-A34 F' Z
AUG B04.020.098300 RC-RVCH-CRDM-NOZZLES 16-PT-075 5/6/2010 Accept AUG* B04020.0198300 RC-RVCH-CRDM-NOZZLES'. 16-PT-076. 6/11/2010 Accept C/F AUG p!i";iSi 804.020.098300 30!iii~~4.020.098300; RC-RVCH-CRDM-NOZZLES RC-RVCJH-CROM-NiflSi*;i]'- .7,, 16-VENDOR4:011 1~ 6-VEN#IDOR-OlD,:!I*r F;! 4/1 /2010 Accept 00 a
;5/28/2.010 F FAccept -Prebservice examns after ealý Examination CategoryB-F, PressureRetaining DissimilarMetal Welds In Vessel Nozzles AUG.' BO5.01Q0.052700 , Rc-ýRPy-WR-3Wj ,y ' 16-VENDO R-"'w*l Accept Fi: Pre7milnatgon UT AUG B05.010.053000 RC-RPV-WR-53-Y 16-VENDOR-018 3/9/2010 Accept Pre-mriigation UT t dohn Car~tegory 'B1 Pressur Redtaining Boltng, Greater.Ta 21nIn'Damter IS! 806.010.095800 RC-RPV-NUT-037 16-VT-120 3/16/2010 Cn
':.~. ii'si 60:6i. 95900 I:;RC-RPV7-N UT;038; " .."~~.'
.. 'f6-vt-121. Accept,. .
Is, B06.010.096000 RC-RPV-NUT-039 16-VT-122 ý3/17/*2 0 I0 ... ... . .Ac ce pt . . . .. ... .. .. . ... . 31171201,0, " Accept I 1..l 806b010.096100 ýC-.A PV*-UTp04*0 '. . . .. , 16Vf-123 - - 3/17/2010 00 [Sl 806.010.096200 RC-RPV.NUT-041 16-VT-124
.I:: '..806.010-096300 RC-RPNUT-04.... . F ,16-V.-1 25 3/17/2010 Accept ISl B06.010.096400 RC-RPV-NUT-043 16-VT-126 3/*:17/2.0 10 SC) i.1.;i,#06.019050' RC-RPFV:NUT ..:.**.F.i.16-VT-,1?7 F. 3/16/2010 Accept 4t-ISl B06.010.096600 RC-RPV-NUT-045 16-VT-128 3/16/2010 w .
Si1, 8 , RCIRPV-NuT-46 ,..,. . 'F. '
'I6-. 9F 2;B06.010.0967,00 .3/16/2010 .
Is) B06.010.096800 RC-RPV-NUT-047 16-VT-130 3/16/2010 Accept is 806.010.0969000 RC- RPWLNUT04 . 6-VT-1 31 3/16/2010 ISl B06.030.087500 RC-RPV-STUD-037 16-UT-045 3/16/2010 Accept isi *s06.030*s7io0 RC-.RPV 7StU'D-:38 , , :. .16-UT-04 . ISI B06.030.087900 RC-RPV-STUD-039 16-UT-053 Accept 3/16/2010 ,FFF([! FAF
- 151 . BI* .03088100 ,RCýRPV-ttSTU 7 .i ,.
- 040. 16-UT-054
. -. 3/17/2010 i Accept*'FFF!ii!;'!l]i;l;i
F !2,.i!!i F ii~i!i i;!::;;iilt =}::F;: {~ii'~iii;ii F f ii SI B06.030.088300 RC-RPV-STUD-041 16-UT-055 3/1712010 I:I,,,.,,,B0,61030.088500 RC-RPV-STUO-064: , . F. , i 16-UT-0. 6 F Accept IS[ B06.030.088700 RC-RPV-STUD-043 16-UT-047 3/17/2010 isI p:,60*6.030.8890 ,C*-RcPV-tuT 0 44 .. 16-UT-0481 ,Accept ISI 1806.030.089100 RC-RPV-STUD-045 16-UT-049 3/16/2010 Accept!
isi.. BO&030.0830,C-g-TD04,.,, 16-UT 7050 3/16/2010, 3/186/2010 Accept ISI 806.030.089500 RC-RPV-STU D-047 16-UT-051 3/116/2010. Si.: .! 6030089i700 RC-RPV-rTUD.048. .. 16-UT-052 3/16/2010( Accept 0 ISI 806.040.923500 RC-RPV-F'LNG-THRD 16-UT-032 i-., ISI , 06 050 285000 RCRPV-WASHIER-*037 16-.-i 32 3/10/2010 Li,, iSI 806.050.285100 RC-RPV-WASHERS-038 16-VT-133 4 3/16/12010 500 028 00 ... .....RC 15.:.ii!:.:.!S[:}i. .PV:.WASI
..... ER6039'.
..6...
.. 3..7/0.0.....I..
DAVIS-BESSE NUCLEAR POWER STATION UNr Class 1, Class 2, and Containment Examinatio 16th Refueling Outage ISI 806.050.285300 RC-RPV-WASHERS-040 16-VT-135 3/1712010 Accept
- S! 6q§02854 -0.: R* RCV-VWASHERS-041' . 16-VT-136 ;3417/2010b Accept ISI 806.050.285500 RC-RPV-WASHERS-064 16-VT-137 3/17/2010 Accept C IS[ 806:050.285600 ' 16-VT-138 73/16/2010
.RC-RPV-WAsHERS-043 Accept ! ,, 9,1 I CID- 51 IS[ B06.050.285700 RC-RPV-WASHERS-044 16-VT-139 3!16/2010 Accept
.S06...05 O1 10. 28518.0 .. R.RFPV-WASHERS-04s 16-vT-40. 3,I/16/2 01lO 0 IS! 806.050.285900 RC-RPV-WASHERS-046 16-VT-141 3/16/2010 Accept CD1 15' 06.050.286000 RC-RPýV-WAHR-4 16-vT-142 , /621 Accept Accept
[SI B06.050.286100 RC-RPV-WASHERS-048 16-VT-143 3/16/2010 0'Q Cn 151 06.180.,22.ý3400 RC-RCP-tt'býSTUDý9 16UT-0214 3/9/12010 '
- ccept ' 1',hIC![,:bFuF ,
is[ B0.180.223500 RC-RCP-1-1-1-STUD-10 16-UT-025 3/9/2010 Accept c -0 [SI!
- 80680.23600 *Ri*p-1*i-$-Tup* ;:<i:,! 1 -¢023 " 319/2010:,. Accept ,
IS B06.180.223700 RC-RCP-1-1-1-STUD-12 16-UT-027 3/912010 Accept [SI 806.18012238W0 RýC-RCP- 1.1Ji-ST UD -1,3,, , 16UT-028 I - .3/912010 Is] 806.180.223900 RC-RCP-1-1-1-STUD-14 16-UT-O29 3/9/2010 Accept -i - B*o6.is0'.22to6o RC-4'CP-i11SUD1 ' 16-UT-03039200 Accept *., I F ' ' IS1 806.180.224100 RC-RCP-1-i-1-STUD-16 16-UT-031 3/9/2010 Accept is[! , E06.2060.821400 10~ RPýC 8P~1.9dUSWASNERs-p.> 16-VT-073 //01 I' Accept ISl 806.200.821500 RC-RCP-1-1-1-NUTS/WASHERS-10 16-VT-074 3/9/2010 Accept 1i1 . 806.200.821i '0 , '-**-tNUTSWASKERS-t1 16-,VT-075 3/9/2010 Accept CoC IS[ B06.200.821700 RC-RCP-1-1-1-NUTS/WASHERS-12 16-VT-076 3/9/2010 Accept . c4-P CD 181 B06.00j81o0b RCCRt71-i-!1-jNUJT'SWASHERS-13 . 16-VT-077 ,.,//P0 Accept A' t l 000 IS] 806.200.821900 RC-RCP-1-1-1-N UTS/WASHERS-14 16-VT-078 3/9/2010 Accept
-Is . B06.200.822000.' RC;RC,,P-1-11NUTS/WASHtERS.15.' 16-NVT749, , .3/9/2010 Accept 4- -
[SI B06.200.822100 RC-RCP-1 i -NUTS/ASHERS-i 16 16-VT-080 3/9/2010 Accept - o inan C0e30. 2,1PressurMe-etainnLg ol-ing,i.AdLe Inb 1iameter5 I[I 807.030.215700 RC-SG-1-1-UPM-BLTG .16-VT-I 1 3,16/12010 Eva! Acceptable follow-up exam per-formed after thread conditioninqg (I16-VT-i 55) 1SI 807.030.215700 R SGi PWLTG 16-VT-155ý 3/18/2010 F PSI B07.030.216100 RC-SG-1-I-UP[O-SLTG 16-VENDOR-012 3/19/'201 0 Accept e t !!i~~!'i!:: F ;;i i*!% !iiiii:~ i*!l!!!!~i; I, iii'F'I! !!ii~~;'::!iii~~i PSI 6 07.,050..474900, RQýHEAD VENT-FLANGE BOLTING-5 '16-VENDOR-OlS" 3/17/2010 PSI B07.070.274300 CF-CF30-BLTG 16-v\)-195 :3/11,12010' F' Accept PS 1:,,. 07.070.27460: CF-CF31i-BLTG '-,V , i6-IL 19 A~cept. PSI B07.070.281300 MU-MU2B-BLTG 16-VT-173 5/10/2010 ExainaionCatgor 'Bi, te~sur Reainng eldsin'Piping Accept Accept SIl 809.011.006600 CF-33B-CCA-6-2-FW31 16-UT-034 3/11/2010 Accept di SI 89s.01.O1060, DH34-Cb42SWlo,' 16-UT-013 3/4/20 10 Accept -o CD iS! B09.011.042000 RC-MK-A-24-2-FW139B 16-UT-012 3/4/2010 cc CD
,ISI 80.-1J..4210b *RC-M1K-k---W3 i: Accept IN) i'F',!iii epti i:!;', :: !
cci*
*1-~
3/5j'201 0 ii!i r ,F i* i i!}IJIi~!i I ![,:';[F~i!IF*: ib :,!! ['a AUG 909.011.032200 RC-MK-A-67-1-FW105A 16-VENDOR-019 3/5/2010 Accept Pre-mitigation UT 0
-n
ýAUG" 809.011.033300 ,R-K-5t 7 1SW69A., 16¶VENDOR-020. N)
F,') AUG B09.011.036100 RC-MK-A-67-2-FW1 34A 16-VENDOR-021 3/6/2010 Accept Pre-mitigation UT (-I' . .:: AU0G 0*901 01.*0**700 R- 5 Wý-*VENDOR-On2 3/5/2010
;. lt. ::A~ceP~t
'i.
Accept ' ,* Pr re-mitiga P ie-mitigatio'n tion UT -, AUG B09.011.043300 RC-MK-A-67-3-FW1 05B 16-VENDOR-023 Accept , .'Pre-mifigalloii UT,,i AUG:" _809.011.0b4'4200Q R'bRCNK.-B444SWV69B !'-16-,VENDOR-024_ 3/,112/2.010 I
DAVIS-BESSE NUCLEAR POWER STATION UNIT #1 Class 1, Class 2, and Containment Examinations 16th Refueling Outage AUG B09.011.047000 RC-MK-5-67-1-FW1348 16-VENDOR-025 3/6/2010 Accept Pre-mitigation UT r) I:: AUG' .. 1047800, RC-MK-...'-S.4 iB0019 A16-VENDORJ626 ' 3/12010.o . ....
......; .. UT..'..
AUG B09.021.005900 RC-MK-B-56-1-FW10B 16-VT-150 3/19/2010 Accept 0 16-PT-0II33N'.4120'1 0 c"e ptt,'1Ac
.I II, :.
- St5I.':.'iBQ9.021 .006300..HP-33C-CCAý2-A.W34 C,)
AUG B09.021.006300 HP-330-CCA-2-45A-FW34 16-UT-021 3/5/2010 Accept (it
-I
- 0 9!.*w021.00600 RC.ýMK-p-4:4*-1-**J*2: 16-PT-027.3420 C)
AUG B09.021.006400 RC-MK-8-44-1-WJ-68-2 16-UT-022 3/5/2010 AceptC Accept i (it isi. 8.0'9:.021.*015900 :MUJ-31: C CA WB 16-PT-0 ~ _1/112010 1' EL cn C,) ISI 509.021.024700 RC-MK-A-135-SW22 16-PT-031 3/8/2010 Accept '0 (it ISI RC-M1343-W4. Rc-<5700 00i ý09.W02:0
- 16-PT-036J3921 C)
ISI 809.021.027300 RC-MK-A-93-SW42 16-PT-032 3/8/2010 Accept
<00 16-PT-034, - 3/8,2010' Accept,'
ISI B09.021.812900 MU-31-CCA-18-4-FW19E 16-PT-038 3/11/2010 Accept AUG: .B01:.20.. :!Mu! qcý6ýS:21IUE.31-.CA..84FyV19E 16-PT-074 : 20*:..41212 10 2 Uft ' 2 AUG 809.021.812900 MU-31-CCA-18-4-FW1SE 16-VT-083 3/11/2010 10- 73293 Eval Arc stnkes removed and acceptable PT 0) exam performed (1 6-PT-074) PSI"' 809.032.037000.RcMK--56:1: ' 16PT0*0. 3/25/2010 ' '" I" '. . ISI B09.032.045000 RC-MK-B-44-1-1N2 16-MT-003 3/5/2010 Accept k.:"9.040;01210 0. R.FSK-M-tCAJ.1.F. ~. . 6P0 '. . ' '3/9/2010 ':', A; ': '. ' - ISI B09.040.014800 RC-FSK-M-CCA-7-1-FW44 16-PT-035 3/9/2010 Accept
- ,SI 809.050.010242 kRC-40-CCA-I8*I-FW2 OVERLY . 1,6-VENDOR-004:
8V,. ' 3/9/20100 AccPtwH ' 1:YHJbI - ' >. AUG 809.050.010249 RC-MK-A-82-FW54 OVERLAY 16-VENDOR-005 3/25/2010 Accept Post-mitigation -00 Psi B09.050,010255 RC-MKA67--F.wi05AOv"ERA*Y . 16-yENIDORO033- " ',4/3/2010 t:.JmitMiýaton i PSI B09.050.010257 RC-MK-A-67-2-FW134A OVERLAY 16-VENDOR-036 3/31/2010 Accept Post-mitigation
<PSI *809
, .. 6.05:1 025.9 ,RG-MKI-A-6^7-.3.-FW I105R V ,ERt..4Y .16-VENDOR-039, 4/15/2010..... Accpt Po~ig...o.
PSI B09.050.010261 RC-MK-B-67-1-FW134B OVERLAY 16-VENDOR-040 4/15/2010 Accept Post-mitigation P 0I M.9b..50.10.263 .::.R*C*0CCAA-7-FW25 OVERLAY 16-VENIDOR-029 .' 120'0K Accept ' Pmito*rgat. .I I. II I.i L1 4c,I PSI B09.050.010264 RC-40-CCA-18-5-FW18 OVERLAY 16-VENDOR.-030 3/15/2010 Accept Post-mitigation PSI ,,. 809.050.010265 :::RC CCA-18-3-F*M9OVERLAY I6-VENEDOR031. ; , 4/1/2010. .... ..... Accept P*ostrnitiati:on:,*', I H iii PSI B09.050.010266 RC-RPV-WR-53-W OVERLAY 16-VENDOR-027 3/29/2010 Accept Post-mitigation PSI,, :.09.J050.01267 , RC RpV-WR-53-Y.OVERLY. . 16-VENObR-028 3:.8/2010 ' Accept ,' Po trIiiti*ti _ PSI B09.060.010256 RC-MK-B-61-1-SW69A OWOL 16-VENDOR-034 3/23/2010 Accept Post-mitigation PSI EI09.060.010258:. Rb-MK-8-56-4-SW143A OWOL 16-VEND R2 038' .: :3/25/2010, .. Accept ":ost-tigation,' I 'I . _14 PSI B09.060.010260 RC-MK-B-44-1-SW69B OWOL 16-VENDOR-032 4/12/2010 Accept Post-mitigation PI:,* :B960!0:262.. RCMK B 1SW143B O3WO. ' 1 1,.VEND.OR .35 :wL4/i2*. . .4' ,: ptj "'P*stmitiga'ion H
. ,I I 110 Examination Category B-K, Welded Attachments for Vesse/s, Piping, Pumps, and Valves
- S . . 1 .. 2,6". ... :"
0t,16:0.I-s[. -: ;- : 1, 16-UT-059 ' '7' ' 4/7/20100 ',. ' :::,"' " ' ' '0H Examination Category B-0, PressureRetaining Welds in Control Rod Housings ISI ,,.,1.1Q7 6O0:,CRPV-CRD-WH-9-B53.~ ~ 16-PT.040 '3/13/201 0:I ~tH 'I'~' cc 0) (it ISI B14.010.837800 RC-RPV-CRD-W73-B54-58 16-PT-062 4/2/2010 Accept I-.) pSi 1314,0106.839400 RC-RPV-CRD-W7,3 i.550-3i. ,16 PT2..3 ' 4/2/2010'e :.' ,. 0 ISl B14.010.839800 RC-RPV-CRD-W73-B51-39 16-PT-064 4/2/2010 Accept
.SI' .B1:010.8404001 k-RPV-CRW3-I53'51 R -. , 16-PT-065 ' 4;2/2010 '! AcceptOpt ' ' .A . " ' ' :.: . .. , U,)
l.A ISI 814.010.843900 RC-RPV-CRD-W60-B54-58 16-PT-066 4/2/2010 Accept
.;PS.I 1314.010.5500 . ,18-PT-06 .' 4/2/2010':'i*
. ;1,RC1RPV/RDW60-850-3..' ccept:fl'i ' ' ' ' .II
DAVIS-BESSE NUCLEAR POWER STATION UNIT #1 Class 1, Class 2, and Containment Examinations 16th Refueling Outage SI B14.010.845900 RC-RPV-CRD-W60-B51-39 16-PT-068 4/2/2010 Accept Co tZ
.S - 14.010 50 kR."RPVCRD-W60-B53651 ! 69 ::. 4/2/2010 *-ept ept15 ISI B14.010.850000 RC-RPV-CRD-W61-B54-58 16-PT-070 4/2/2010 Accept PSI81401.8560 '.C RPV-OR5i61B503 16-,PT-14221 Accept Ii ii'i~~I'ikHJ 11 ';'
on is] 814.010.852000 RC-RPV-CRD-W61-B51-39 16-PT-072 4/2/2010 Accept ISI 614.01%.85260O' RCRVCR-6-835 16-PýT-07 4/2/2010 ýýI Accept1 I II Examination CategoryC-A, PressureRetaining Welds in PressureVessels <0 iSI 001.010.216700 SP-SG-1-1-WG-8-2 16-UT-038 3/15/2010 Accept
.9II C01.030.217100SP-SG-- d*WT-60'16-UT309 3/ 1/2010
- 3. Accept yF:1
~0' Examination Category C-B, PressureRetaining Nozzle Welds in Vessels 15 0.3.26550,0.. DI-ICOL-I1W DC, , , 6P0i ,. 1/920*, . Acce~pt., 1 . ,.I' Examination Category C-C, Welded Attachments for Vessels, Piping,Pumps, and Valves 00 ISI '6-PT-0 t
C03.020.14800. HP-33-CCB-i2-H9-AW 1/A/2010 Acept Fih a oit SIs C03.020. 168000 HP-330-CCB3-2-H49-AW 16-PT-030 3/612010 Eval Light surface conditioning and acceptable follow up PT exam performed (16-PT-045) S.1. .. C03.020 1M 680)00 H:PýCCB-2-H49J-AW 16-PT-.4 . 3/1 2010.. Acpi ccepii t SI C03.020.328300 HP-ANCHOR-A046-AW 16-PT-008 12/18/2009 Accept 0 1 /6,2D1 Accept i . i. . 5 00 ISI C03.020.379700 CS-34-GCB-5-H19-AW 16-PT-007 12/17/2009 Accept ISI. 003.020.673500 CS ,-34-GCB-5-H124LAW ...-. 16P-0 12/1T72009, A ii.i i!iccept
;I 'iII4III I:. WI isI C03.030.268300 HP-PUMP-i WELD G 16-PT-004 12/16/2009 Accept Examination C00teg0.2o7yC- PressureMRetainDing t Greater Than2in In1Diameter SI 604.030.272300 HP-PUMP-1-2-STUD-009 15-UT-069 7/15/2008 Accept SI1 C04030.7'2400 H-PUP-12-Strup-b10io-U-G 7/16/2008'I, Accept[
isI C04.,03,0.272500 HP-PUMP-1-2-STUJD-011 15-UT-061 7/15/2008 Accept 1 1 si .030.272600 c., HP-P*.0U*P2-;SU2D-012 ,. 16-UT-062 7/1/ 08I ' Accept 1 ISI 604.030.272700 HP-PUMP-1-2-STUD-013 16-UT-060 811712010 Accept ISI C4.*030272800 HP-PUMP-1-2-STUD-14 . . 16-UT-6i: 8/17/&010 A' e.ptII j C) ISI 004.030.272900 HP-PU MP-1-2-STUD-015 16-UT-062 8/17/2010 Accept iS *04suc 3 30 oo -7 PHP-PuvP-ii-v.STD-01l 16-UT-063 18/17 /*2010',:*0. Acxept II'Ih! ', . SC) Examination Category C-F-I, Pressure Retaining
- 0H-33E*mCC8-'6-i Welds 0-SW B in Austenitic Stainless Steel or 1:*ii:*i!i;/5ii:!i:i Piii~*
T-19!l::. High Alloy Piping i!'*i:!::.::..2118/20C10 .i*',l: : Accel.':i~! pt*; III,
. Si C05.011-194500:
SI 005,011.194500 DH-33B-CCB-6-10-SWB 16-UT-004 2/18/2010 Accept
- I. .05.11,1'80400 DH-33B-G oSW E .16PT-016 2/921 'Accept!
IS[ C05,11A,180400 DH-33B-GCB-!-4-SWE 16-UT-002 2/19/2010 Accept
]SI ,C05.11A.190500 DH-338-GCB-10-6-S WF :1-T01 2 /201201,0 I Accept.:'
ISi C05.11A.190500 DH-33B-GCB-10-6-SWF 16-UT-003 2/20/2010 Accept 131 C05.11A.19.8600 DtH-336 GCB-J-11-FW46 2': 6P.23, /6200, Acpt C) SI C05.11A.198500 DH-33B-GCB-1-11-FW46 16-UT-008 2/26/2010 Accept 131 C05.11A.208000 DH-3B-G8-1019-wD 16-T-04 .2/26201 i'Accept .1 I ISl 005.11A.208000 DH-33B-GCB-10-19-SWD 16-UT-009 2/26/2010 Accept II I' I*S C05.1 X2525010
. CS-34-GCB15-3-SW F :16UT-O08 2/24/2010 Accept 'lilt '1' I I' iS0 C05.11A.252500 `6S-34-GC-5-3-SWF 16-UT-006 2/23/201..0 Accept
DAVIS-BESSE NUCLEAR POWER STATION UNIT #1 Class 1, Class 2, and Containment Examinations
. . A16th Refueling Outage ISI 005.11A.536900 DH-33A-GCB-7-4-FW14 16-UT-036 3/11/2010 Accept 1.1 00,.1113I. HP-33A- tB* iA-,F.2 .,.N
, ,6.PTý0O5J.I..,.W:_.;t/160 , , ,, /Accpt. 0 ISI 005.11B.141200 DH-33A-HCB-1'-7-SWB 16-PT-013 1/19/2010 Accept 13.. 0511.42500.DH-3AHB--W-.7, 6P- /921 Accept:I ~ ~ C ISl iS[
- 005.021.150200 HP-330-COB-2-13-SWF
.05021.150200HPm33C-. CO 2-13-*WF I,, :
16-PT-022 16iUT-007 2/22/2010 2/222*01 0 Accept Accept .5..d'Vi' ( g
. I IS1 O05.021.158600 HP-33C-CCB-2-6B-SWC 16-PT-020 2J18/2010 Accept ISI , :'05,021.158600:: HP-33C-CB-2-6B-W0C 16-UT-05: 0 2/18/2010 Accept ' I' I It: 0) -dil' IS1 C05.021.162900 HP-33C-CCB-2-11-SWG 16-PT-017 2/18/2010 Accept a ,
.1'1S" 00:¶.j 005.0o21190
* !.'.(5021-1*62900 C00.021.i65900, H:
p-330C'09*?1 '~lSW ,G::Iiii HP33-CB-t2-35-SW HP-33c'OCB-2.35-SINE .6PT-05. .;:i ;*i:!!<:* 1-U .T0-Oi i:~ .';!ii-i:}~: 1.6-PT-02 . 2/18201 3/3200 182 *:}'. 3/3/2010 . ;i H:*. ll:'H i.A
.Acept ccet {1 ~i::,,, :.]
Accept.C :,L:.2fl11i:!ii!,!iii
....... .. 'p:: I."'!
II'.i~ " *
- 2 9 ISI 005.021.167100 HP-33C-CCB-2-38-SWB 16-PT-047 3/9/2010 Accept
[SI. ::C05.021.167100 .HP-330-0CB-2-38-SWB .. , 16-UT-0 3110/2010 Accept ' . I . *. . SI 005.021.169000 HP-33C-CCB-2-41-SWG 16-PT-047 3/5/2010 Accept .< o. ,_.
`ISI C05.02.1,.1 691000 P30OB24 , 6U-l 3/5/2010' , :'cptli' i.j~~~iI:! cI.
t-ISI 005.021.173000 HP-33C-CC0-2-27-SW0 16-PT-042 3/15/2010 Accept 00 "i S C0.5021.173000 HP-330CB-2-27SW I p : . , 16-UT-037 T .. 3/17/2010 3/51200' . '"1 Accept.... .. . ISI 005.21A.576000 OH-33B-GCB-2-4-FW62B 16-PT-009 1/6/2010 Accept L-005tk.21A.60500 HP-4-GObEý-ltiF .W.6, 2:,. 16-PT-037 19200 Acet Cp ' ' ISI 005.21A.932400 HP-330-HCG-91-4B-FW54D 16-PT-003 12/16/2009 Accept . Ca ISI 005.030.100021 HP-00B-39-6-FW2I 16-PT-00! 11/5/2009 Accept SI C05.051.291400 MS-3A-EBB-1-23-FW1B 16-MT-05 3/15/2010 Accept1 ISI ::'.~::i <:005.051.291!400 MS-3A-EBB-1-7-SWA1BB ::.* C05.051.295700 MS-3A-EB.B1-I!23-. ; ::.i
, . ,1.6-UT-642*;s 16-MT-009 ; :. .*i . 3/18/!2010:!
3/19/2010 I H.i* ; ! 'Acceph,'ILI Accept I " iI i!,IIi',
. , Ci~]ii 3017m010 cr- p IS[ C05.051.342100 FW-7-EBB-3-G-SW B 16-MT-001 3/17/2010 AcceptA I-[. , 05.051.341000 E .,. ,, 16 .UT-04
. 313 /2010 . Accept..... ......... ... 0 1...ISI 051.342200 AW-7-EBB-*35G1-SWB 16-MT-005 3/15/2010 Accept 13 : ,o~sA.3ao M3-EB--1-W1A ,, ,, 16-.UT-OSS 3/221 Accepti'" ' '
Sr.;:',!'"00:!!~5.051.:342200 FWE*7DE8BB* #357*iZSWB :i;:i 16-UT-0410 3/17/*62010i:i*i i[i!bcbptl Aoccept 'II fli '*.: i~II.'
' ' *::I: . ,:'.!i: '. ': I!:* i ! ,.i: i I;i:: A;!
131 005.051A34,1000 MSV-3A-E-IBS-2-6-SWGA 16-MT-007 3/87/2010 1.i... ': CO 181 5.051k336200M C05051.3628914 *A- Eý3A~B-24 0, MS7 EiBB-4-"574i4S 3WG: .... . 16-UT-Di 16-UT-Ol ' , . 38/00 ' 3/16/2010 '.Accep Accept ............... ' ... i.ýj-i 1 C)A 4 IS IS 005.081.329800' MS-3A-EBB--10-WSWA C005.081.298500 MS-3-EBB--G1-2-SWX 16-MT-006 16-MT-004 3/187/2010 3/12/2010 Accept Accept i : IS C06.020.994700 MS-PV-ICS11B-WELD J 16-PT-044 3/18/2010 Accept 181 006.020.994800 MS-PV-IOS11B-WELD K 16-PT-043 3/18/2010 Accept Exa in . o , ........ .. E- D
. ... .Sasa s
.sket -. ,..1 I I -s . .. Y.
. . . I .
DAVIS-BESSE NUCLEAR POWER STATION UNIT #1 Class 1, Class 2, and Containment Examinations 16th Refueling Outage AUG E05.030.010004 CV-INTERIOR-MOISTURE BARRIER 16-VT-035 3/1/2010 Accept Examination Catego"..E.:hPe. Bolting :.su.I: ; ,.Tai ,g ISI E08.010.980900 CV-EP-PAP1BI-FLANGE-BOLTING 16-VT-065 319/2010 Accept CD C ISI E08.010.982300 CV-EgP-PA4AI-FLANGE-BOLTING 16-VT-068 3/9/2010 'IAept cc ISI E08.010.982300 CV-EP-PAP4BI-FLANGE-BOLTING 16-VT-063 3/9/2010 Accept CD
~1 C)
ISI E08010.982500 CV-EP-PBCDI-FLANG E-BOLTING 16-VT-079 3/9/2010 Accept CD 11I ,E0801'0.4800 RCv P0P FA-H2 O N 16-VT-067 3/9/2010 Accept cn c Co IS[ E08.010.982500 RC-EP-P2A5I-FLANGE-BOLTIN-G 16-VT-103 3/9/2010 Accept -O CD 151 IS! E08.010.989200 F&01,01.466000 CV-EP-PAP5SI-FLANGE-BOLTING IC.OR-BQLTING 16-VT-0710 16-V-1"-02 61/2010 3/9/2010 Accept Accept C) IS 6-VT-266:i'. 6/1201 I I ' '[ Examination Category,F-,Supports,, ' ' ,- -.. . iII C/) PSi F01.010.466700 RC-30-CCA-8-H2 16-VT-064 310/2010 U) f C Accept PSI .i .0i.0A65000.RC-.-:ýCCA-L8H 4 -0 0 B
" 1:.,,. 'A3/5/2010 .6-VT-056 . ' .I.ti,' Accept 0 '!' 'i i! B PSI F01.010.465700 RC-MK-A-96-PS-H3 16-V-T'-103 3/12/2010 Accept 1 4 PSI F~l010. 46580 RC-P FMK-Ak-96-PS-R2: 16-VT-104 7. 3j/~~~ Accept 1 j" IH'i 4 PSI F01.010.466000 RC-MK-A-112-PS-H4 16-VT-102 3112/2010 Accept PI FO1.010.466400b RC-MKA-105-PS-H2 16-VT-154 -3/2/2010' Accept ,
PSI F01.010.466700 RC-MK-A-95-PS-H12 16-VT-i 01 3/12/2010 Accept
-:PSI FO1.iO*0.45710 C-K*A9*CMk- PS-H15 . 16!VT,151, 3/20/2010 ' H Accept , ':'i \0 PSI F01.010.467300 RC-MK-A-95-PS-H17 16-VT-11l 3/11/2010 Accept PSI {0101 L0640%'1 ' k-A-134PS-H120 :,1-T.2ji 31/00 4 'Accept ý' ",'"' 'i.
PSI F01.010.467600 RC-MK-A-139-PS-H21 16-VT-13 3/11/2010 Accept PSI F01t01.04607RMbAb35PSH2 . ', 16V-0.7;j 3ý**/8/2010 I L' Accep ' 'I ,jilI11/.
- C)
PSI F01.010.468000 RC-SMK-A-135-PS-1-H29 16-VT-054 3/8/2010 Accept PSI .101.4684.P R)~v1~~e.1 5:S~-{6 * : , I6-\T I-1 00 ' 3/1.5/2 p 't Accept' .lLK1IfIiHiii.t! PSI F01.010.468400 RC-MK-A-135-PS-H36 16-VT-107 3/15/2010 Accept PSIýF11'4850RC-MKA13P--3 6V-O /121 Accept 1 ~~) ~ I~ PSI F01.010.468500 RM-MK-A-103-PS-H37 16-VT-l10 3/11/2010 Accept
.11.P100 70R-M-3sSH4. - 6-T003621 Accept I";
PSI F01.010.468700 RC-MK-134-PS-H34 16-VT-108 3111/2010 Accept CA 6-U psi F0 , , VT-052' 3/8/2010 ' 'Accept'I' 'iL -o0 PSI F01.010.469200 RC-FSK-M-G'CA-7-1 -PS-H26 16-VT-051 3/8/2010 Accept
~S P1d0A20..,;C 7 17-H2 46-T-205 ,62j/00:
1 c~~'I.'p.'ii] P11620.447400 DH-33B-CHi C6`-5w '16-VT- 145 3/17/2010 Accept PSI F01.020.465600 FW-7-EBB-3-3-SR26D 16-VT-I 61 is! ' P,01.0203.456600. FW-7-E2BB-313-H1- '1': - 6-YT- 14 3/17/2010 . Accept
~Cn PSI F01.020.457500 AF-6C-EBB-4-H
. Cý,Eb - Hfi*11 i!iii!ii iii.:,:!i!*!;!:!:il i 16-VT-1
*;Ai* 6ýi:* 46 ,
- 14Z PSI F01.020.373900 AF-6C-EBB4.H11.......... 4 3/11/2010 Accept IS! F01.020.458800 AF-M1155-H4 16-VT-088 PSI' F01.020.39600 WN-7-EB1-35 2SIR20 I.-.T-16 -, 7 3/15/2010 Accept PSI F01.020.462500 FW-7-EBB-3-9-SR25A 16-VT-105 sI .'F01.020.42600 .FW-7-EBB 73-9S*IR24*A I6-VT-1 06 12/17/2009 Accept 151 P01.020.673600 CS-34-GCB-5-H24 I 6-VT-007
*PSI' *'F>02u0.3152 CS-33A-HCE-3-H16'., I5-V325, V'152/20109 1/9/2009 ' 'Accep't Accept . .. 'i Psi P01.020.315300 CS-33A-HCB-3-H17 15-VT-324 6-A Psi ,zo.' I.20.377300 :DH-33B-CCB-6-HI : :,l5Y.329 2/6/2009 Accept QA PSI F01,.020.373900 DH-33B-GCB-1-H7 15-VT-335 2/6/2009 ' .. Accep' . '. . .
, ' ..... O 00
'PsI W,b'~.20.374400 DH-33B-GCB1 i.-VT-334 1113/2008 Accept Psi P01.020.451600 CS-34-GCB-5-H32 15-VT-321 ........ .... !,Ac ...... ...
*PSI "'0100560 ICS-34-GiCI&-5-H32'. 15-VT-320' IS! P01.04,0.380,900 RC-RPV-W!X AXIS SUPPORT 16-VT-049 3/5/2010 Accept RC-SG.'a1rtPEý 0 UPOT 6ATO99, IS! P01.040.540500 HP-PUMP-i-I-SUPPORTS 16-VT-006 12/16/2009 Accept SW-STRAINERK-1-2-SUPQPORS : 6VT-005 IS! F011.040.542600 P0-DAY TANK-i -i -SUPPORTS I 6-VT-003 12/15/2009 Accept N) 04
16 RFO Inservice Inspection Summary Page 28 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 The following ASME Code Cases were used during the performance of Class 1 and Class 2 Nondestructive Examinations. CODE CASE NO. TITLE N -307-3 Ultrasonic Examination of Class 1 Bolting, Table 1WB-2500-1, Examination Category B-G-1 N-460 Alternative Examination Coverage for Class 1 and Class 2 Welds N-504-2 Alternative Rules for Repair of Class 1, 2, and 3 (with limitations noted Austenitic Stainless Steel Piping in NRC Regulatory Guide 1.147) N-524 Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Piping N-526 Alternative Requirements for Successive Inspections of Class 1 and 2 Vessels N-533-1 Alternative Requirements for VT-2 Visual Examination (with limitations noted of Class 1, 2, and 3 Insulated Pressure-Retaining Bolted in NRC Regulatory Connections Guide 1.147) N-566-2 Corrective Action for Leakage Identified at Bolted Connections N-583 Annual Training Alternative (with limitations noted in NRC Regulatory Guide 1.147) N-592 ASNT Central Certification Program N-598 Alternative Requirements to Required Percentages of Examination.
16 RFO Inservice Inspection Summary Page 29 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 C, ý' Il ,;* n"** 1,h "1 1 1 Q"7Q 0-Ull'- CODE CASE NO. TITLE N-616 Alternative Requirements for VT-2 Visual Examination (with limitations noted of Classes 1, 2, and 3 Insulated Pressure Retaining in NRC Regulatory Bolted Connections. Guide 1.147 N-619 Alternative Requirements for Nozzle Inner Radius (with limitations noted Inspections for Class 1 Pressurizer and Steam in NRC Regulatory Generator Nozzles Guide 1.147) N-623 Deferral of Inspections of Shell-to-Flange and Head-to-Flange Welds ofa Reactor Vessel N-624 Successive Inspections N-638-1 Similar and Dissimilar Metal Welding Using Ambient (with limitations noted Temperature Machine GTAW Temper Bead Technique in NRC Regulatory Guide 1.147) N-639 Alternative Calibration Block Material (with limitations noted in NRC Regulatory Guide 1.147) N-652-1 Alternative Requirements to Categories B-G-1, B-G-2, and C-D Bolting Examination Methods and Selection Criteria N-658 Qualification Requirements for Ultrasonic Examination of Wrought Austenitic Piping Welds N-663 Alternative Requirements for Classes 1 and 2 Surface Examinations N-686 Alternative Requirements for Visual Examinations, VT-1, VT-2, and VT-3 N-695 Qualification Requirements for Dissimilar Metal Piping (See Relief Request RR- Welds A28)
16 RFO Inservice Inspection Summary Page 30 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 CODE CASE NO. TITLE N-700 Alternative Rules for Selection of Classes 1, 2, and 3 Vessel Welded Attachments for Examination N-722 Additional Examinations for PWR Pressure Retaining As modified by 10 CFR Welds in Class 1 Components Fabricated With Alloy 50.55a(g)(6)(ii)(E) 600/82/182 Materials N-729-1 Alternative Examination Requirements for PWR As modified by 10 CFR Reactor Vessel Upper Heads With Nozzles Having 50.55a(g)(6)(ii)(E) Pressure-Retaining Partial-Penetration Welds N-740-2 Full Structural Dissimilar Metal Weld Overlay for (See Relief Request RR- Repair or Mitigation of Class 1, 2, and 3 Items. A32 & RR-A33
16 RFO Inservice Inspection Summary Page 31 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 FORM WI-1 OWNER'S RE~PORT FOR INSEVI'VCE JN$HMCTIONS As roquirod by tho Provislonn of (hQ ASME Co0(1 Rulotu
- 1. Owner VirSt`0i10TY10QaV .OIcI~QTA(1 ony 1 iy .
76 \roi 8Ai~S, hod1 (Nnoand Addross ofOwner)
- 2. innJ~vfsBo~o Wvier PworSI~I~oi,5501IN. S0uio II. 2, OqikHorbor, O o'3l1 (Norue mildAddress of' ilon)
- 3. Mhd i 1 ,V11A ___________
- 5. ComivricrojilServico Date ~~~,I's6 ~1~lBnluubr NIA
___ __ _ muWit__ ell 7,ConissI ioiitph~(om MIII1kaitror f~isll ctr lasfollor Svghia NSu. lNIA Inbencoo & Wilcox VAV101S ______ OVA_ N* VIA ClNss2 Plph11gIC0L~)lI VIA NIA NiA Noo'ptie~fshlI~s III fbnrio lists, skxtolws, Drftrwhigs lirny ti Dsvd, pnivittcd (1)s Izo Is 8% In.x 11la (2)hIt~~lronl110 ) ms fln I Io10hF1 0 - sjia, 01i11 6 oil [Wis rjo~ilahifcl~ildcIen eOil (3)ewolsAM IsI ikiibomd and Ilia ~~hcl Is Ixoided fit 1100~P (IfiIIIS Ibun 1)11 -=9uO ituyW &*4,~ 49m~iho AsdII Old" M)plt.2) ]Au, Di~r, iiir 2).CO,
ýZ~ FattgoJ, N) O010S.2,1
16 RFO Inservice Inspection Summary Page 32 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 ITOINf N1\1S.1 (1UJnk)
- 8. Iixnmninnton J)alos Mardi 2008 (a Juno 2010 9, IlopV oi) rrliod Idenlltflfillonil 2i, Period Juma 1,20061* M\jay20?, 200913/ PI'od ,ay 21, 9009 o ,1S0vtnber 2OZQ 201?_______________
10, ]ispccotervalld0mttleatlon: Soiltciber212000 (o.Septemlber20*.2012 1I. Applivable Fdillon ofSvctlori XI 1995 Addendn '1hrou hI_996 19,. l)telltoWvlsiu)I of ihspection OilI, IPln: hln:bnm 2,t 2010) 13, Abstract of'P,xelnntllan mnd "'sts. hlohido n list of otyimhlations Aind tests And astatenii voiverhin ,status of work requirCd tor 1119 Iiisjpetion Phlo 8is" AXACI I-1)BO 1,I, Abstlrwl oftRosulls of i*xIlltltlon tlnd 'rles. tI NVV'VAClIIIDRD
- 15. Abstract oi Corrclvivo Measures. sills /tVITACIlit)
We ceir1tithat A)(ho sl oimenls ho IVIII o itSthis report Oro con'ed, I))1110cmnlnnttu1S a(It tests meet III InsptWcllonl 'Inil as required by Iho AS%11 Code, SeolIon XI, fold oq) vourccti, m*estires Iotkn con'ornu to Ihe ilies of thte ASM Caodo, Section X1. Cvrhillcnteeof Authorl~ion No. (ifipploablo) Nhit 13Tptrnflon Unto 1A, N'14'_ _ C'EhlTJ1tAT'E (1, 1N'S3ERVIGH INISPECTION 3,lire uiiiilisgiitlu, flnuidIng a %'1)i(I c,*ohitilssioll Issuled byIIIoNniliil B3ourd oflDoltfr and Ptosskrv V.ssel hrisectors and the* ,*ltoer Provhuio or Ohio Antd emjployehd by frlorlorl Slen Bollero Itrspcetoii of A*luwisn~me Co. i1nb4tfor* connc*tel.lt ianve ii1slieeteu u1se vomliloviitsl desodfied intIis Ownersr' R411ort duhilig the perod
&lrdi2008 to Juno 29010 anild saleo Ihtl to 111ltoflmykiowledgo im mnd bulvlf, Pti Owier hlmus ttinionhleXI exmindnntons mlmc-hts olur tnkrell COWTCtvo inustuw (luseriberd ij lI:1 Owoor's Itupurt III iccordulwo WithIIo Ielispcelion 'lnu mnd As relured(I by (io ASl t"Code, coIrlms NI.
"lyslgiuhlg tIis cetilflktu i161iuter 11O 1ispector )uorhills ] vireyvsuployr i*keoyAnyalya lewoxpsseid or 1lim)iled, eoncurlltIle (liV yC.Stld Fi1¢s15 mad cuncciv llnlcuslutrs des-edhi il ilis O*,cnr's Rujoni. It'llIrhemioTO, neithor 1110 Inspector nor Ilus vuploycnhr n1l t)i liable it alky mann11er for oilyl porsuntl miujiy or rolplety daniage or n hoss of uny kind arlsIng t*e11l, I) oroeo1uii
%V'il) tto,n?. h'ttemilts I W10 h Mc i! ,tivaean i _1F__l.
____________ 4____ Wil,__ 'dnert -NunudBad X
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16 RFO Inservice Inspection Summary Page 33 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power'Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 SYSTEM PRESSURE TESTS The following system leakage tests were completed by AREVA and FENOC personnel on Class 1 and Class 2 systems from March 2008 to June 2010 during Cycle 16 and the 16 th Refueling Outage for the Davis-Besse Nuclear Power Station Unit #1. These tests completed a portion of the required tests for the second and third periods of the Third Ten Year Inservice Inspection Interval. The second period ended May 20, 2009 while the third period ends September 20, 2012. Inspections were performed to meet the requirements of ASME Section XI, 1995 Edition through the 1996 Addenda. These tests do not include those associated with repairs/replacements addressed in the Repair and Replacement Section of this report. Code Case N-522, as endorsed in NRC Regulatory Guide 1.147 Revision 15, was utilized in the performance of those Class 2 tests associated with containment penetrations that are part of the containment system but the balance of their piping system is outside the scope of Section XI. Code Case N-533-1 with limitations as endorsed in NRC Regulatory Guide 1.147 Revision 15, was used for the examination of Class 1 insulated pressure-retaining bolted connections. Code Case N-616 with limitations as endorsed in NRC Regulatory Guide 1.147 Revision 15 was used to determine Class 1 bolted connections which require insulation removal and inspection per Code Case N-533-1. Code Case N-566-2 as endorsed in NRC Regulatory Guide 1.147 Revision 15 was used when bolting was not removed for visual examination when leakage was noted at bolted connections during system leakage tests. Thirty-eight Class 1 Pressure Tests were completed. This represents all of the required Class 1 pressure tests for 16RFO. Pressure boundary leakage was discovered on the Reactor Vessel Closure Head through Nozzle 4 (CR's 10-73358 & 10-74172). The affected nozzles were evaluated / repaired as outlined in the Root Cause Report for CR 10-73323. A half-nozzle repair was performed per Relief Request RR-A34 on a total of 24 nozzles including Nozzle 4. After repairs, an acceptable as-left bare metal visual examination was performed. The remaining Class I pressure tests did not reveal any pressure boundary leakage. Twenty-eight Class 2 Pressure Tests were completed. The tests performed prior to May 21, 2009 complete the required testing for the Second Period of the Third Ten Year Inservice Inspection Interval. The tests performed during the Third Period represent 20% of the required Class 2 pressure tests for the Third Period of the Third Ten Year Inservice Inspection Interval. The Class 2 Pressure Tests did not reveal any pressure boundary leakage.
DAVIS-BESSE NUCLEAR POWER STATION UNIT #1 Class 1 Class 2 Pressure Tests 16th Refueling Outage Work Scope Summary No ComponentID Examination Exam Date Condition FinalStatus Comments ::
.Re port No'. Report
...... Number S0 Examination Category B-P, All Pressure Retaining Components - Class. I Ln IS[ - 304.010.098200 RC-RVCH-BARE METAL 16-VENDOR-015 6118/2010 10-73358, Eva] Pressure boundary leakage through 10-74172, Nozzle 4. CR 10-73323 Root Cause 10-73323 describes evaluation I repair. As-left examination performed for acceptance -~ 0 after repairs.
1 n1
-15.000.CF09 CFO9.:.C I 6/26/2010! ::.:? i. A~., :
16-VT-231 Is , 15.000.CF10 CF10 6/26/2010 Accept is. 815.O00.DH14 DH'14 16-VT-234 6/26i2010 Accept (SI B15.000.OHIS H15 16-VT-223 G c" 16-VT7237 6/26/2010 Accept
- SI .B1S!.000.1H16DHI6 Oi 6/26/2010 Accept 00 (SI B15.000.RC01 RC0I 16.VT-224 1SI B15.000.RCO1 RC01 16-VT-213 6/26/2010 Accept 16-VT-224 6/26/2010 :10-,. 889
- 6/26/2Z010
- : ,Accept -*;:i::
Accept .'tl ;l* i'. (l ea.;*;,:
.!; :':. *:*. ,, .l *;;;
ISI 815.000.RC01 RC01 16-VT-225 6/26/2010 Accept -41' IS] :15.000oRC01 RCO1 1F6-VT-226 6/26/2010 Accept ISI B15.000.RC01 RC01 16-VT-227 6/26/2010 .. Accept ,. I:AS], B15.0G0.RCO1, ::RCO1 16-VT-228 6/26/2010 Accept (SI B15.000.RCO1 RC01 16-VT-229 :6/26/2010. 1-7885 Accept'!':' DH21 packing leak, iSI. B15.000.RC.01 :,.R C01 16-VT-232 6/26/2010 Accept ISI B15.000,RC13 RC13 16-VT-233 06/22010 ,Accept - i SI 1 5.000.RC013 :.RC01 16-VT-038 3!1 0/2010 Accept P-S1 B15.000.RC13 RC13 16-VT-166 3/1912010: . Accept: I 16-VT-167 4/1/2010 10-72757 Accept CCW leakage on the RVCH flange
.Boc acid on RCP 2 Code Cnse N-
'IS1 B15.000.RC13 RC13. 4/5/2010 10-74982 Info 566-2 for aoceptability ISI B15.080.010003 RC-RPV-BOTTOM HEAD 16-VENDOR-009 4/23/2010 Accept IS[I I B15.200.029600 RC-MK-A-2.- .. :CA 16-VT-043 00 3/312010 Accept ISI 315.200.537400 RC-MK-A-24-2-TCB 16-VT-047 3/3/2010 Accept
- 1. ; 3B15210.029100 fRC-MK24*,1-FMA2 164T-0581 3/9/2010 Accept C)
ISI B15.210.029200 RC-MK-A-24-1-FMA1 I 6-VT-057
!SI 81:5210.029400.! RC-MKA_-2*iPTA2 I 6AVT-041'.
- .: 3/3/2010
!.: 3/3/20!.0 : *-!;.': :., Accept
.Accept., i!:; ;*: i ;!: .f ::' I .: ; :.*:i:,~ !,i SI B15.210.029500 RC-MK-A-24-1-PTA1 I 6-VT-042
( S!..' 815.210.029700 :C. M A-241.-MBA1 I .- 16-VT- 4/0 3/3/2010 Accept , , (SI B15.210.029800 RC-MK-A-24-1-MBA2 16-47-039 00 3/3/010Accept,
- SI B15.210.030700: RC-MK-A-24-1-VNA~ 16,V -096 IS] B15.210.039100 RC-MK-A-32-1-WLB 16-VT-089 3/11/2010 Accept 01ý
. , 1SI'B. 815.210.040100 ::':RC-MK-A2*4-2ý-'MB1 164VT_090!. 3/11/2010. Accep' . I iSi B15.210.040200 RC-MK-A-24-2-FMB2 16-1v7091 3/11/2010 Accept 141 (SI l 815.210.040400 :RýCMK-A*2-PTB, 16-VT-04-4 3/3/2010 ' Accept ISI B15.210.040500 RCMK-A-24-2-PTB2 I16-VT-097 3/8/2010 Accept ISI B15.210.040600 RC-MK.A-24-2-MBBi1 16-VT-046 3/3/2010- Accept '!
SIl B15.210.040700 RC-MK-A-24-2-MBB2 16-VT-04-5 3/3/2010 Accept isi'.B15.210.041600 .:RC-MK-A-24!2- ::N8.'. 3/9/2010 Accept.
DAVIS-BESSE NUCLEAR POWER STATION UNIT #1 Class I Class 2 Pressure Tests 16th Refueling Outage Work Scope Summaty;No Component ID Examination Exam Date , Condition Final Status Comme ts I j Report No Report :.......................... Number CC Examination Categro:y C-H, All Pressure Retaining Components - Class 2 ISI C07.000.CF02 CF02 16-VT-218 6/25/2010 10-78903 Accept pipe cap leak Cr) SI1 C07 000.CFO8. CF08*,. 16-VT-216 6/2E/2010, Accept: [SI C07.000.DH08 )H08 16-VT-094 3/12/2010 Accept " [I C07.000.DtH1l, DM11, 16-VT-169 *. . 4/12/2010 j,,, Accep S1 C07.000.DH21 DH21 16-VT-095 3/12/2010 Accept I SI C07.000.HP09 HP09 . 16-,/170, 4.1 4/12/2010, Accept C;' 16-VT1-171 4/12/2010 Accept I ncn P 0 ISI C07.000.HP10 HP10
- .SI, C07,000 MSO02 MS02 16V\,T-230 . 62/00 'I Accept' C.' =
[SI C02.033.266400 DH-COOLER-1-1-OUTLET 15-VT-304 8/26/2008 Accept SI Cc07000.CSO4 CS04 1..................... 5-VT-259 . 6M/25008 . Accept 9 n.- [SI C07.000.CSO5 CS05.............15-VT-260 6/26/2008 Accept SI :C07.000.CS01 CS01 . 15-VT-246 5/8/2008 Acc**ept ISI C07.000.CS02 CS02 15-VT-247 51/9/2008 Accept 00
' 1[1 C07.000.H01 DM01 15-VT-290 :1t/2008 Accept Ac , I is[ C07.000.DHO2 DH02 15-V'-300 8/26/2008 Accept S.:: C07.000D1-103:3 HDM03 :5-VT-291;. 1 . 8/19/2008 ,!Accept: '
[SI C07.000.DH05 DH05 15-v9-301 8/26/2008 Accept
- [SI C07.000.DH66 DHO6 15-V.-302 . 20..... Accept' . .-
ISI C07.000.DHO9 DH09 15-VT-289 8/19/2008 Accept 451 C07,000;DH1O DH10 15.-VT-292 . /920 c t I [SI C07.000.DH18 DH18 15-VT-272 7/9/2008 Accept
- S1 C07.000.HPO1 HPO1 15-VT-235 . . :3/19 i2008 , Accept: ;
- ISI C07.000.HP02 HP02 15-VT-236 3/19/2008 Accept SI C07000 P2A P2A .. . .. .. .. 1-VT7307 . . 9/2/2008 Accept ISI C07,000.HP03 HP03 15-VT-237 3/19/2008 Accept 0 15 . c0:00HPO07A iHPO7A 15-WvT-315 1018208 Acep 151 C07.000.MSO1 M'SO6 15- IVT- :262 6/26/12100 8 Accept ISI ...
......... .07 000 M S0 .. M S 15 VT-263 .. 6/26 2008 . A ccep, .. o 4ý-
w*CD
-4
16 RFO Inservice Inspection Summary Page 36 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 REPAIRS AND REPLACEMENT The following repairs and replacements on ASME Class 1 and 2 components were completed at the Davis-Besse Nuclear Power Station Unit #1 from March 2008 through the completion of the 1 6 th Refueling Outage in June, 2010. Several Alloy 600 components were mitigated via weld overlays during 16RFO. Full Structural Weld Overlays (FSWOL) were applied to the (2) Core Flood Nozzle Welds, (4) Reactor Coolant Pump Suction Welds, and (3) Reactor Coolant System Cold Leg Drain Welds. Optimized Weld Overlays (OWOL) were applied to the (4) Reactor Coolant Pump Discharge Welds. During UT examination of the Reactor Vessel Closure Head (RVCH) nozzles, twelve nozzles were found to have recordable indications. A concurrent Bare Metal Visual examination of the RVCH revealed pressure boundary leakage through nozzle 4. Supplemental PT & ET examinations of the J-Groove welds were performed and these examinations confirmed an additional twelve nozzles requiring repair. In all, a total of twenty-four nozzles were modified per Relief Request RR-A34. The appropriate Code Data Form is attached for each repair. Complete documentation for repairs and replacements is available for review in the Davis-Besse Records Management System. Repairs/replacements utilizing items rotated from stock are not included in this listing as a Code Data Form is not required per IWA-4132 of ASME Section XI. Code Case N-416-3 was used to perform pressure tests following repair/replacement activities.
16 RFO Inservice Inspection Summary Page 37 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 Order Number System Description 200006739 Decay Heat Body to Bonnet studs replaced on DH33 200007521 Component Cooling Water Replaced globe valve CC 129 200008584 Decay Heat Replaced safety relief valve DH2761 200099434 Decay Heat Replaced Decay Heat Pump 2 Injection Line Relief Valve DH1550 200135667 Decay Heat Gasket, stem, and valve packing replaced for DH68 200233176 Core Flood Body to Bonnet bolting for CF31 200233202 High Pressure Injection Replaced safety relief valve HP1510 200241421 Reactor Coolant Replaced Power Actuated Relief Valve RC2A 200282957 Main Steam Replaced Snubber on Hanger HBD-27-6-H1 200282958 Main Steam Replaced Snubber on Hanger M1 148/H4 200282963 Main Steam Replaced Snubber on Hanger 3A-EBD H22 200282964 Main Steam Replaced Snubber on Hanger EBD-19-H48 200282965 Main Steam Replaced Snubber on Hanger EBD-19-H76 200282967 Main Steam Replaced Snubber on Hanger EBD-19-H1O 200282968 Decay Heat Replaced Snubber on Hanger CCB-6-H1 200282972 Decay Heat Replaced Snubber on Hanger GCB-2-H7 200282973 Decay Heat Replaced Snubber on Hanger GCB-l-HI0 200282974 Containment Spray Replaced Snubber on Hanger HCB-3-H16 200282975 Containment Spray Replaced Snubber on Hanger HCB-3-H17 200282980 Main Steam Replaced Snubber on Hanger EBD-19-H62 200298766 Main Steam Replaced MS703 200310085 Containment Spray Replaced Snubber on Hanger GCB-5-H32 (SNA92) 200310180 Containment Spray Replaced Snubber on Hanger GCB-5-H32 (SNA93) 200312302 Reactor Coolant and Replaced studs and bolts for Snubber Related Equipment Support on Hanger RC-MI 170-H2 200312302 Reactor Coolant and Replaced studs for.Snubber Support on Related Equipment Hanger RC-M 1170-H3 200312386 Main Steam Replaced safety relief valve SP17A1 200312394 Main Steam Body to Bonnet nuts and studs replaced for MS101 200312409 Main Steam Replaced Snubber on Hanger EBB-l-SR4 (SNC-225)
16 RFO Inservice Inspection Summary Page 38 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 200312464 Main Steam Replaced Snubber on Hanger EBB-1-SR4 (SNC-169) 200312465 Main Steam Replaced Snubber on Hanger EBB-1-SR4 (SNC-170) 200312466 Main Steam Replaced Snubber on Hanger EBB-1-SR4 200312560 Core Flood Bolting material replaced for CF30 200312863 Decay Heat Replaced safety relief valve DH4849 200312907 Steam Generators Steam Generator 1-2 Tube Plugging and Stabilization 200312908 Steam Generators Steam Generator 1-1 Tube Plugging and Stabilization 200320362 Reactor Coolant Replaced safety relief valve RC13A 200320363 Reactor Coolant Replaced safety valve RC13B 200327370 Main Steam Replaced Snubber on Hanger EBD-1 -SR 15 200327371 Main Steam Replaced Snubber on Hanger EBD-1-SR16 200327376 Main Steam Replaced Snubber on Hanger EBD-1-SR16 200327377 Pressurizer Replaced Snubber on Hanger CCA-8-H4 200327385 Pressurizer Replaced Snubber on Hanger PSP-1-H25 200327392 Pressurizer Replaced Snubber on Hanger PSP-1-H26 200327393 Pressurizer Replaced Snubber on Hanger PSP-1-H27 200327400 Core Flood. RPV 1-2 North Core Flood Weld Overlay 200327406 Steam Generators Replace one nut and one stud on the AFW Header of Steam Generator 1-1 200327417 Pressurizer Replaced Snubber on Hanger PS-H29 200327421 Pressurizer Replaced Snubber on Hanger PSP-1-H36 (SNC-144) 200327430 Pressurizer Replaced Snubber on Hanger PSP-1-H34 200327440 Pressurizer Replaced Snubber on Hanger PSP-1-H36 (SNC-147) 200327444 Pressurizer Replaced Snubber on Hanger PSP-1-H37 (SNC- 148) 200327446 Pressurizer Replaced Snubber on Hanger PSP-1-H37 (SNC-149) 200327460 Pressurizer Replaced Snubber on Hanger PSP-1-H17 200327466 Pressurizer Replaced Snubber on Hanger PSP-1-H20 200327470 Pressurizer Replaced Snubber on Hanger PSP-l-H21 200327498 Pressurizer Replaced Snubber on Hanger PSP-1-H3 200327499 Pressurizer Replaced Snubbers on Hanger PSP-1-H2 and PSP- I -H4
16 RFO Inservice Inspection Summary Page 39 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31. 1978 200327500 Pressurizer Replaced Snubber on Hanger PSP-1-H8 200327501 Pressurizer Replaced Snubber on Hanger PSP-1-H12 200327502 Pressurizer Replaced Snubber on Hanger PSP-1-H15 200327503 Main Steam Replaced Snubber on Hanger EBB-1-SRI 200327518 Core Flood Replaced Snubber on Hanger CCA-6-H6 200327526 Decay Heat Replaced Snubber on Hanger CCB-6-H1O 200327730 Core Flood RPV 1-1 South Core Flood Weld Overlay 200327738 Reactor Coolant RCP 1-1 Discharge Weld Overlay, RCP 1-1 Suction Weld Overlay
.200327739 Reactor Coolant RCP 1-2 Cold Leg Drain Weld Overlay, RCP 1-2 Discharge Weld Overlay, RCP 1-2 Suction Weld Overlay 200327740 Reactor Coolant RCP 2-1 Discharge Weld Overlay, RCP 2-1 Cold Leg Drain Weld Overlay, RCP 2-1 Suction Weld Overlay 200327741 Reactor Coolant RCP 2-2 Cold Leg Drain Weld Overlay, RCP 2-2 Suction Weld Overlay, RCP 2-2 Discharge Weld Overlay 200348471 High Pressure Injection Replaced valve disc for HP2B 200350926 Decay Heat Replaced Snubber on Hanger CCB-6-H5 200350927 Decay Heat Replaced Snubber on Hanger CCA-4-H1O 200379598 Decay Heat Replaced Snubber on Hanger GCB-1-H22 200379599 Decay Heat Replaced Snubber on Hanger GCB-1-H22 200379600 Decay Heat Replaced Snubber on Hanger GCB- 1-H33 200379601 Borated Water Storage Replaced Snubber on Hanger HBC-1-H4 Tank 200404719 Reactor Coolant Replaced Letdown Coolers E25-1 and E25-2 and piping/supports 200414124 Reactor Coolant Replaced bolting material for MU2B 200414552 Core Flood Replaced Snubber on Hanger CCA-6-H5 200297961 & Reactor Vessel Removal, Inspection, and Replacement of all 200409488 Control Rod Drives 200410080 & Reactor Vessel Machining, examination, welding, final - 200411925 machining, and final examination of 24 Control Rod Drive Mechanism Nozzles
16 RFO Inservice Inspection Summary Page 40 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2*NR-1/N'"- OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI I
- 5,1r 1 , rlne
- 1. Owner FirstEnergy Corp. Date Ne 76 South Main St,. Akron, OH 44308 Sheet 1 of 1
- 2. Plant . Dayis-Besse Nuclear Power Station * #1 Unit 5501 N. SR. 2, Oak Harbor, OH 43449 200006739
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng 5501 N. SR.!2. flak Harbor, OH[ 43449 Authorization No. 20 550 NSR2 akT-frborOH4344 Expiration Date 07/17/10
- 4. Identification ofSystems DH-33 Body to Bonnet studs DB-SUB049-02
- 5. (a) Applicable Construction Code ASME IUCL2 1971 Edition NOAddenda Code Case no (b) Applicable Edition of Section XlUtilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case n50 (c) Design Responslblities First Energy Corp, Nova Machine Products
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serlai No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 911MRANGES=SftX3/4- Unk Uck N/A N/A Unk Replaced No IR nME s=3 ra/x3111" Nova Machine. Products G7200 N/A N/A 2003 Replacemenrt No
- 7. Description of Work 8 Body to Bonnet studs were replaced on DH-33. The nuts were not replaced.
A VT-2 leakage test was performed satisfactory.
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure NOP psi Test Temperature NOT -F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Olowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets In the form of lists, sketches, or drawings maybe used, provided (1) size Is8 XX11 In. (2) Informattanin items I through 6on this report is included on each sheet, and (30 each sheet Is numbered and the number of sheets Is recorded at the top of this term.
16 RFO Inservice Inspection Summary Page 41 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2INR-1I/NtRR
- 9. REMARKS Nova Machine Products CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue certify that the statements made In this report are correct and the repair, modification, or replacement of the Items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules.
National Board Certificate of Authorization No. 20 to use the "NR" stampplres 17/110 Date :2: D FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Thomas G. Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have Inspected the work described In this report on Jvly '"r. T*eo and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described In this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date -7 1 Cq Signed Commissions CERTIFICATE OF COMPLIANCE N/A , certify that to the best of my knowledge and belief the statements made In this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal Injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions O1,MP.,," 5JM~jg~.M - ~
~~no~)
16 RFO Inservice Inspection Summary Page 42 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DR-eT70-9
.FORM NIS-2/NR-1/NVR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section X1
- 1. owner M1rstEnergy Corp. Date August 19, 2008 7t; ,nnth Main st.. Akron. OH 44308 Sheet 1of 2
- 2. Plant Davis-Besse Nuclear Power Station Unit 01 5501 N. SR. 2. Oak Harbor. OH 43449 200007521
- 3. Work Performed by FirstEnerg, Nuclear Operating Co. Type Code Stamp N One
;flA1T.4 R 72 0k 1-Wrhnr_ tri- 43449 Authorization No. 20 Expiration Date 07/17/10
- 4. Identiftiation of Systems Make-Up Pump 1CCW Outlet Stop Check DB-CC129 (SubsysO16-04)
- 5. (a) Applicable Construction Code ASME HI CL2 1971 Edition W72 Addenda Code Case N/A (b) Applicable Editon of Section Xt Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Coda Case N-416-3 (c) Design Responsibilities First Energy Corp, Velan Inc.
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identificaiion/ Year Repaired ASME Name at Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped I
(1) 1 1'/OGlobe Valve Velan Inc. S/N: 630-1 N/A DB-CC129 1974 Replaced Yes (1) I W'Globe Valve Velan Inc. S/N: 901025-3 N/A DB-CC129 1990 Replacement Yes.-
- 7. Description of Work Existing globe valve (s/n:630-l) was replaced with a like for Like globe valve (HT#: 901025-3) during routine maintenance.
A VT-2 initial inservice test was performed satisfactorly.
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure 74 psi Test Temperature 86 -F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists. sketches, or drawings may be used, provided (1) size ts 8 Y X11 In. (2) information in items I through eon this, renrt Is inchlued on each sheet and 130 each sheet is numbered and the number of sheets Is recorded at the too of this form. P I
16 RFO Inservice Inspection Summary Page 43 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-21NR-1JNVR-1
\
- 9. REMARKS Velan Inc.
CERTIFICATE OF COMPUANCE I, Lynn R. Ross , certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section Xl of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17110 Date 923-0o FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION Thomas G. Laps holding a valid commission issued by the National Board of Boiler ahd Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have Inspected the work described In this report on ,EELZ3 O.ao-and state that to- - the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection Code "NP" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning ie work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date & , Signed Commissions - , CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of - the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed _ _ QC.__ CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OH[O and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be-.w-liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this Inspection. Date Signed Commissions
-Itkb ý
Page 44 of 235 16 RFO Inservice Inspection Summary FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Ohio 43449 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Commercial Service Date: July 31, 1978
, Yq ;? 0 -ý-"?_
POIRM NP-I T0CAITIFICATE 1`1006P' 9A&IA044 I 1 WO ~L&I41O I$Fli'ALY As Ketluised bYith~eProisions of the ASME C~o~e.-SolalonILI Okv.I
- 1. MoeralacturtdbI.
Came~of1A~Uso~f4 oMasts Qlder)
- 2. Mo10tntetured for
- 3. Locatipeof Instatletion
- 4. ~m ~vaw \'Ia.~ N ze if. OutletSize L 1 (h) Model No., (b) N Certific ate Holdjer's (c) Canadian SeriesNo, Serial Registration (d) Cro.wing If) NaIl. (1 Ye..
or Tyvps No. No. No. to) Class Od. No. aoluil J31 - (6) Illl
-fBI~~~~~~AO comes__
1, 4OegrfCn~ difon \.'. o ip,...aeef psi. Pof VolvoPressure ClosA.. O ~ ... II5 T. Gold WAorking Pressure psit-l 100T. V Pr,5sairoRetaining Pieces Mark No. Material Spec. No. N4.Aufacturoe gparnets (at 4CaefioGo _____ ___________ ____________ P~
- %~010Z 0~ S -. C apeIW oeerfl in form of Or, lisst iharat.- 23 .rrd> on thifs 0.r. Aspect Isndadod 0.r &.4h 5,shs. 64 01,*)l ek seet I* IsrsrbtraC and rsurPo of sh*Ht~
SrorOjo fp ofttO1*4rr,M, malone 16000371rrswb.orzOknioedIron, r.O .rOoz.,ASMO.305 L4-71.r Or. N~n, r.no.NYI. 1001?
16 RFO Inservice Inspection Summary Page 45 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 1~O~Fo~N~V1 jDOOkI 9., HydicsoaestMk 5n mijo. 041, Difit,.ntiul tootorusture - .1 CERTIFICATE OF COMPUIA
.We. omlily- that thor saltemetselad - in8 this repoof are correct andnpha svr 0, at 0100,
- r. 4M to~ tIIr d014A Of,
;Aints o, av o ill.k
.~oroolin.of~o:$~E.Code .
lor Nuclear- Power Plant Colnyortaots. ton i. L. Editibon;- ILý Nl. tigned -- by-
- o. .5adInto sy bol expire O00 hiybalol. tooSM ii~od&6fahiotsr CERTIFICATION OF DESIGN Stress analyolre port fClinmoI only) an file at ____________
Oe~~~-oa~Ii~t ooaeI~le~iby (t) ~-___ Re. o nocos noto o.~ill by .i 0 C' t~ Z_________ _Pc~sut A Reg. Al.. 111Sigondlonoto rood'e.ut L0. -00 -IVY. CERTIFICATEOF SHOP INSKECTf N 1.Itro! -adr.gt.-=o6dn ta thoNti-l 80,0Ba' of Boif ~fpteaswe h Vesel aInsloaoig'- h~navae .oced the por~ a.,. d"Vtobad I. thin; Dole 0.1poft Q01. too . -lat. that aothobe".- a n ow lao. ,ed e l baoait. theN CctheIi Hlla rft#;l&0Wt.toa nltg Wed ot,vtotd h accrohrtim¶t Ina M16) the ASMECode.Stcllu Il f By: .-gnjrnghI 0 onoflab. cln n~-elpW oa.UeidtAolInsohalot roar oto .c~ot~aer ah ay.rany aposd of in~pticO, dacto~oj
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nlib.ina jnjrssW lanOroedpta+bojao lot ' Dt R00eprtoOg funerom 000.a Ii'4t aaa ay,,.a'ratiao Boo,%4tl. otocýýrr 049.-or-.-I.----I--U-
16 RFO Inservice Inspection Summary Page 46 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 r t I=Lnl*"//IL* FORM NIS-2/NR-.1N44R-4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner FirstEnergy Corp. Date June 11, 2008 N_ 76 South Main SL. Akron, OH 44308 Sheet I of 2
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, - OH 43449 CR 03-00771 a*.*.
err /. t CaNo..SC. P.O.M.o,
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng N-5501 N. SR. 2. Oak Harbor, OH 43449 Authorization No. 20 Expiratlon Date 07/17 10
- 4. Identification of Systems DECAY BIEAT REMOVAL SYSTEM (Subsys 049-02)
- 5. (a) Applicable Construction Code ASME In CL2 1971 Edition No Addenda Code Case No (b) Applicable Edition of Section X1Utilized for Repairs or Replacements. 19 95 Edition 96 Addenda Code Case No (c) Design Responsibilities FirstEnergy Corp., Anderson Greenwood Crosby
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replacedor Code Replacement Stamped t-Safety Relief Valve J.E. Lonergan Co. 304400-44-1 NIA DB-DH2761 1975 Replaced Yes t-Safety Relief Valve Anderson Greenwood Crosby N9905-0O- N/A DB-DH2761 2005 Replacement Yes 7 r o
- 7. Description of Work *.-
Existing safety relief valve (senal# 304400-44-1) was replaced with a new safety relief valve (serial # N99905-00-001) during routine maintenance, not due to failure. Alt existing flange bolting materials were reinstalled. A VT-2 initial inservice test was performed satisfactory.
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes' Other No Test Temperature N/A 7' Pressure 183 _ psi Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdown (Ifapplicable) N/A Set Pressure and Slowdown Adjustments Made Using N/A (T. enur at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size Is 8 A X 1 Ifn. (2) Information in Items 1 through 6 on this rennrt is included en each sheet, end inn eaeh sheet iv numbered and the number of sheets Is racordld at the n rtoefrtieforn, this recort is included on each sheet and t3o each sheet is numbered and the number of sheets Is recorded! at the toý of this form
16 RFO Inservice Inspection Summary Page 47 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-00R70-4 FORM NI1S-2IN1R-1ftfNt1 I ~ob N4.k.~l~
- 9. REMARKS Anderson Greenwood Crosby CERTIFICATE OF COMPLIANCE.
1, Jeffrey M. Martin certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NS" rules, National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 071171 10 Date C,/.' ,/ e FENOC Signed qcý CERTIFICATE OF INSERVICE INSPECTION 1, Thomas G. Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hatford, CT have inspected the work described in this report on l,1, *lOeand U0 state that to the best of my knowledge and belief, this-repair, modification or replacement has been completed.ih accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind . arising, from of connected with this inspection. ý . 1O 0o Date 4 Signed na Commissions t1:5 q3-356 A T cAA CERTIFICATE OF COMPLIANCE I, N/A ,certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the 'VR" stamp expires 12/13/10t National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed *_Q.C. CERTIFICATE OF INSERVICE INSPECTION 1 N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be*l,- liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
.~ ~mb,.. .
16 RFO Inservice Inspection Summary Page 48 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 Q.C.-44C-1 Sheet I of 2 FORM NV-1 FOR SAFETY AND SAFETY RELIEF VALYES As required by the Provisions of the ASME Code Rules DATA REPORT L Manufactured By Anderson Greenwood Crosby, 43 Kendrick St., Wrentham, MA 02093 Name and-Address Model No. JLT.JBS.-3-S Order No. U1953610000 Contract Date 08/25/05 National Board No., TYPE E
- 2. Manufactured For FRRST ENERGY CORP. Order No. 45165718 Name and Address 3kOwner FIRST ENERGY CORP.
Name and Address 4ILocation of Plant DAVIS BESSE 5'. Valve Identification DH2761 Serial No. N99905-00-0001 Drawing No. DS-C-99v05 Rv. B Type SAFETY RRLIEF Orifice Size 0.3473 Pipe Size _Inlet
-- 1.5 Outlet 2 Safety, Safety Relief, Pilot, Power Actuated Inch Inch Inch
- 6. Set Pressure (PSIG) 236 200 F Rated Temperature Stamped Capacity 1o GPMwATar@7o nac.F @ 10% % Overpressure_- Blowdown (paig) 10%
Hydrostatic Test (PSIG) Inlet 1100 Complete Valve 100 7 The material, design, construction and workmanship comply with ASME Code, Section III. Class 2 Edition 1971 Addenda Date WINTER 1971 Case No. N/A Pressure Containing or Pressure Retaining Components Serial No. Material Specification
- a. Castings Identification Including Type or Grade Body N900159-31-0001 ASME SA351 GR. CFSM Bonnet N97794-32-0002 ASME SA351 GR. CF8M b.Bar Stock and Forgings Support Rods Nozzle N97792-33-0004 ASME SA479 TYPE 316 Disc N97793-32-0002 ASME SA479 TYPE 316 Spring Washers N96827-35-0013 Spring Washers N9682'7.35-0014 ASME SA479 TYPE 316 Adjusting Bolt N96828-33-0008 ASME SA479 TYPE 316 Spindle N900162-31-0001 ASME SA479 TYPE 316 I/.
16 RFO Inservice Inspection Summary Page 49 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 Q.C.-44C-1 Form NV-i (Back) Certificate Holder's Serial No0. N99905-00-0001 Sheet 2 of 2 Serial No. Mate.rial Specification Identification Incdudi ng Type or Grade
- c. Spring NXl7017-0001 ASTM A.313 TYPE 316
- d. Bolting
- e. Other Parts such as Pilot Components Sonnet Stud N900163 ASME SASE4 GR. 630 Bonnet Nut N99135 ASME SA194 GR. SM
'We certify that the statements made in this report are correct.
Anderson Greenwood Crosby l //* Date iýo 10t.. 20 Q* Signed Wrentham, MA By ,.44'. . Manufacturer ' Certificate of Authorization No. N-1878 Expires 30-Sep-07 Date CERTIFICATE OF SHOP INSPECTION I, i*ieUndersigned, holding a valid comniossioa issued by the National Board of Boiler madPressure Vessel Inspectors and the State or Province of MA and employed by HSB - CT have inspected the equipment described in this Data Report on
/,I - . F - 200..q" and state that to the best of my knowledge and belief, the Manufacturer has constructed this equipment in accordance with the applicable Subsections of ASME Section III.
By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied,
.concerning the equipment described in this Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
Date A 200 6
- '-. : - Commissions MA-1420 A, N, r (Iesnetor) (National Board, State, Province and No.)
16 RFO Inservice Inspection Summary Page 50 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-4 -- 'P ÷ FORM NIS-2/1NR-41jN3.R "OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS
'As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Date August 16, 2010 76 qniifh Mnin qt ý A krnn OTT d443fl8 Sheet I 2 f2
- 2. plant Davis-Besse Nuclear Power Station Unit rr *,
S501 N. SR. 2. Oak Harbor. OH 43449 200099434 edure** Rere ~n" imieOMP.O.. seuo.. ,ota
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng 5501 N. SR. 21 Oak Harbor, OH 43449 Authorization No. 20 Extiration Date 07117/13
- 4. Identification of Systems Decay Heat Pump 2 Injection Line Relief Valve (DB-DH1550) 5, (a) Applicable Construction Code ASME3 CL.2 1971 Edition W71Addenda Code Case No (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case 416-3 (c) Design Responsibilities FirstEnergy Corp.
R tIdentifica.tiosn nf Cormnnnents Rerrairedi or Remonacd and Rentacement Comnesnents Manufacturer's National Other identlficationJ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped I ca. I 1/2" X 2" relief 3.E. Lonegan 132717-2-I UNK DH1550 UNK Replaced YES valve I ca I 1/2" X 2" relief Anderson Greenivood N99716 LINK 1DH1550 2006 Replacement YES Valve 0002 8 e. Nuts heavy hex LINK LINK UNK LINK LINK Replaced NO 5/8"-I1 IUNC 2B 8 ca. Nuts heavy hex Nova HT- 718732 N/A UNIK 2000 Replacement NO 5/8"-l UNC 2B 8 ca. 5/8" Studs UNK UN3K IUNK LINK IUNK Replaced. NO 8 mo.5/8"- I1X 3 1/4" Nova HT-229801 NIA LINK 2000 Replacement NO LINC 2B Studs During routine rnaintenantce activities the relief valve was replaced with like for like. Also, inlet bolting material was replaced, A VT-2 inservice leakage test (per code case 416-3) was performed satisfactory as part of the post repair/replacement examination.
- 8. Tests Conducted: YES Hydrostatic No Pneumatic NO Nominal Operating Pressure YES Other No Prmssure 50 psi Test Temperature N/A 'F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 '"X II in. (2) information In Items 1 through S on this report is included on each sheet, and (30 each sheet is numbered and the number of sheets is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 51 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 0B-0070-4 FORM NIS-21NR-1/,* N/t 00 Ap~ b M11-111DO,n0 Rspo,t, A0/.00
- 9. REMARKS Anderson Greenwood Co.
Nova Machine Products Corp. CERTIFICATE OF COMPLIANCE I, Jeff'ey M. Martin certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section X1of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/13 Date 08/17/2010 FENOC Signed -- ". CERTIFICATE OF INSERVICE INSPECTION 1, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on 08/17/2010 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section X1 of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arisin.rom of connected with this inspection. Date 08/17/2010 Signed 6&Commissions fiL*,,l/l
, /lLV.L CERTIFICATE OF COMPLIANCE 1, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules.
National Board Certificate of Authorization No. 316 to use the 'VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date' FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION 1, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement-described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Sinned Commissions O.P.-a lb 0040040(04 0beooO~ei, 00)1
16 RFO Inservice Inspection Summary Page 52 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070.5 FORM NIS-2/NR-1/NV-R4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl
- 1. Owner FirstEnergy Corp. Date June 2, 2008 76 South Main St., Akron, 545w OH 44308 Sheet 1 of I
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 Order# 200135667 N~par,,ge.f or*n 0~o 45,=./n JN a...4=
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR SSOI N. SR. 2. Oak Harbor. OH 43449 Authorization No. 20 N S.R
....... ~
1 2.. Oa q Habr . 434 H . Expiration Date 07/17110
- 4. Identification of Systems DH Pump 1 & 2 Discharge to SWST. -DB-DI468- (Subsys049-01)
- 5. (a) Applicable Construction Code ASME III CL,2 1971 Edition S71 Addenda Code Case 1335-6 (b) Applicable Edition of Section XI Utilized for RepairS- or Replacements 19 95 Edition 96 Addenda Code Case No (c) Design Responsibilities Firstenergy Corp, Velan Engineering Company.
A trlnntittaatinn nf flnmnnnerrts RenaIran Sr Ranier-art and Raniacemant Onmnnnnnts Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 1- 8" B.B. Gate Valve Velan Engineering Company. 0003 NIA DB-DH68 1973 Repaired yes 12 -3/4" x 4 1/2" Studs Unknown Unknown NIA NIA Unk. Replaced No 12 - 3/4" x 5 1/2" Studs Nova Machine Products HT# 732078 N/A N/A 2005 Replacement No
- 7. Description of Work During routine maintenance on the above listed valve, the valve was disassembled for gasket, stem and valve packing replaced.
Also during this maintenance, the existing body to bonnet studs were replaced with longer studs for addition nut thread engagement and not due to a stud failure. A VT-2 initial inservice leakage test was performed satisfactory.
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure 175 osi Test Temperature 82 F Pressure Relief Valves:
Service NIA Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using .',N/A at N/A NOTE: Supplemental sheets Inthe torm of lists, sketches, or drawings may be used, provided (1) size Is 8 V X 11 In. (2) Information In Items 1 through 6 on this names 5i* ncilslad Sn ear-h sheat, and L0( each sheet ts numbaered and the number ot sheets is recorded at the teD Otthis torm. this romrt Is Included on each shoat and (30 each sheet is numbered and the number of sheets Is recorded at the top Ofthis form.
i6 RFO Inservice Inspection Summary Page 53 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB.0O70.5 FORM NIS-2/N R- 1/14Wý-1
&.REMARKS N/A .':
CERTIFICATE OF COMPLIANCE I, Richard R. Cockrell certify that the statements made In this report are correct and the repair, modification, or replacement of the Items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code `NR" rules. National Board Certificate of Authorization No. 20 to use the "NR" staý "xpires 07/17/10 Date O6-oZ-OB FENOC Signed "e Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Thomas G. Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of OHIO and employed by HSB CT of Hartford. CT have inspected the work described in this report on IaG yL, "op and state that to - . the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section-XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this Inspection. Date 0 Signed'---'r 1 Commissions , " A T ItCh L CERTIFICATE OF COMPLIANCE 1, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section X1 of-the ASME Code and to the National Board Inspection Code yVR'and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed _ Q.C.__ CERTIFICATE OF INSERVICE INSPECTION N/A holding a valid commission Issued bythe National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules.. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall besr, liable In any manner for any personal injury, property damage or loss of any kind arising from or connected with this Inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 54 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-4 FORM NIS-2/NR-I/N-VR-<OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Date July 21, 2010 76 South Main St. Akron. OH 44308 Sheet I of 2
- 2. Plant Davis-Besse Nuclear Power Station Unit rw*t 5501 N. SR. 2. Oak Harbor. OH 43449 200233176
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR Naml Authorization No. 20 5501 N SR 2 Oak Harbor OTT 43449 Expiration Date 07/17/13
- 4. Identification of Systems Core Flood Tank I to Reactor Check Valve (DB-CF3 I)
- 5. (a) Applicable Construction Code ASME3 CL.I 1971 Edition S7TAddenda Code Case No (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case 416-3 (c) Design Responsibilities FirstEnergy Corp.
ldenliThalhn rat rinnnrnonf a Reneirenl ran Centered and Reralor'.ement Cramnenents 6 ..Id .... niic ....to . Co.. p .......... ne t .. o.. Replaced
..r an .. .............. Com ........
Manufacturer's National Other Identificationn Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 16 EA. STUDS t-7/g" UNK 33203 UNK tJNK UNK Replaced NO x 10-5/8 16 EA. STUDS 1-7/8" NOVA MACHINE HT-72629 N/A D683 2003 Replacement NO x 10-5/8 PRODUCTS CORP. 16 EA. NUTS-HEX; UNK 33203 UNK UNK UNK Replaced NO HEAVY 1-7/8", 8 UN 15 EA. NUTS-HEX; NOVA MACHINE HT-23016 tJNK BoG0 1996 Replacement NO HEAVY 1-7/8", 8 UN PRODUCTS CORP. I EA. NUTS-HEX; NOVA MACHINE HT-530787 LINK UNK 2002 Replacement NO HEAVY 1-7/8", 8 UN PRODUCTS CORP.
- 7. Description of Work During routine maintenance activities valve body to bonnet bolting was replaced.
A VT-2 inserviec leakage test (per code case 416-3) was performed satisfactory as part of the post repair/replacement examination.
- 8. Tests Conducted: YES Hydrostatic No Pneumatic No Nominal Operating Pressure YES Other No Pressure 2155 p~si Test Temperature 532 "F Pressure Relief Valves:
Sernice N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Btowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 X 11 in. (2) Information In Items 1 through 6 on this report is inctuded on each sheet, and (30 each sheet Is numbered and the number of sheets is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 55 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-4 FORM NIS-2/NR-1/NVR-1
- 9. REMARKS NOVA MACHINE PRODUCTS CORP.
CERTIFICATE OF COMPLIANCE 1, 'Jeffrey M. Martin , certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section X1of the ASME Code and to the National Board Inspection* Code "NR" rules. National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/13 Date 07/21/2010 FENOC Signed Q.C. CERTIFICATE OF.INSERVICE INSPECTION
!, Thomas Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by 7f:2410 T'r HSB CT of Hartford, CT have inspected the work described in this report on G7#4QQ4/.- and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection.
-~tIZ6-3 1sto & 2,11 x.,; O~k Dale _________ Signed Commissions ~E3D N 005 A CIA Cap-CERTIFICATE OF COMPLIANCE I, N/A certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules.
NationalBoard Certificate of Authorization No. 316 to use the"VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed __.C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section X1of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 56 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-Ot70-5
/ , FORM NIS-2/NR-1/NV-R-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. owner FirstEnergy Corp. Date April 9, 2008 76 South Main St.. Akron. OH 44308 Sheet 1 of 2
- 2. Plant Davis.Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 Order/ 200233202
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR, 2. Oak Harbor. OH 43449 Authorization No. 20 Expiration Date 07/17/10
- 4. Identification of Systems High Pressure Injection Pump I Suction Relief Valve - DB-HPI510 - (Subsys052-0l)
- 5. (a) Applicable Construction Code ASME III CL.2 1971 Edition W71 Addenda Code Case 1555& 1574 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case No (e) Design Responsibilities First.Energy Corp., Anderson Greenwood Crosby
&. Identification of Comnonents Renaired or Reolaced and fRenlacement Comoonents Manufacturer's National Other Identificatlon/ Year Repaired ASIM.E Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No, Built Replaced or Code Replacement Stamped I - Safety Relief Valve I.E. Lonergan Co. 304400-13-1 N/A DB-HP1510 1975 Replaced Yes I - Safety Relief Valve Andersorn Greenwood Crosby N99716 N/A DB-HP1510 2006 Replacement Yes 003
- 7. Description of Work Existing safety relief valve (serial# 304400-13-1) was replaced with a new safety relief valve (Serial# N 99716-00-0003) during routine maintenance, not due to a failure. All existing flange bolting materials were reinstallled.
A VT-2 initial inservice test was performed satisfactory. 7...
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure 34 Dsi Test Temperature -OT
'F Pressure Relief Valves:
Service NIA Size N/A Opening Pressure N/A Blowdown (it applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size Is 8 52X 11 In. (2) information In items 1 through 6 on this: rePrev is mndlldel ,,n eenh s*heet end t5[} ee,,rh s.heet Is rsnhebred and tJ'te numbier o1f sheets is r-ecrderd at the ton of thIs form this re rt is Included on each sheet and 130 each sh is numbered and the number of shoals is recorded at the top of this form
Page 57 of 235 16 RFO Inservice Inspection Summary FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 43449 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio Commercial Service Date: July 31, 1978 DB-0070-6 FORM NISe2INR-1 WAR4
- 9. REMARKS -
Anderson Greenwood Crosby CERTIFICATE OF COMPLIANCE I, Rchard R. Cockrell certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 20 to use the "NR" stf xpires 07/17/10 Date 0 q1-6.3- 0 a FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Thomas G. Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of oH16 and employed by HSB CT of Hartford, CT have inspected the work described in this report on ot
- and slate that to' the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section-XI of the ASME Code and the National Board Inspection Code "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerningtihe work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner tor any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date Signed lk'M-t 1WfM Commissions b r44 CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Cerificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed _ _ _ Q.C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSI3 CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions (N ama,W mm-i
16 RFO Inservice Inspection Summary Page 58 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 Sheet I of 2 FORM NV-1 FOR SAFE AM SAFEY RELIEF VALVES ~//,~ As required by the Provisions of tfe ASME Cede ItIles: DATA REPORT
- 1. Manuticturnd By Andarson Ce. w l Crosby, 43 Kendrick SLt.,Wretham,. MA 02093 Name and Address Model No. JLT-JS-39-S Order No. UJ967720000 Contr2a Date 10119/05 National Board No.
TYPE E
- 2. m antored For FIRST ENERGY CORP. Order No. 45171.50 Namead Address
- 3. Owner FIRST ENERGY CORP.
Name and Addresa
- 4. Location of Plant DAVIS BESSE
- 5. Valve Identification EP1510 -Serial No. N99716-(D-0003 Drawing No. SC991 RV Type SAFETYRELEF Orif Size 0.665 Pipe Size - Inlet 1.5 Oulet 2 Safety, Safety Relief. Pilot, Powe Actuated I=1 h inch
- 6. Set Pressure (PSIG) 450 -2i isl F Rated Te*m-p-rat r - - -A --oc -
StaMped Capacity f93GPMWATSL@700G*.? @ 10% % Overpressure_- Blowdown(paig) 10% Hydrostatic Tea (PSIG) Inlet 1100 Complete Valve t00
- 7. The matmrial, design. construcion and workmansbip comply with ASME Code, Section IlL Clu 2 Edition 1971 Addenda Date VijNrR49+- Case No. N/A Pressure Contining or Pressure Retaining Components. .
Serial No. Material Specifimaton Identification Including Type or Grade
- a. Castings Body N900159-32.0004 ASAMSA351 OR. CF8M N97794-37-0011 AS5E SA351 GR. CF8M b.ar Stock and Frrgig SupportRods.
Noazzle N97792-33-000 ASME SA479 TYPE 316 Disc Insert) N97793-NGfYGr ASKE SA479 TYPE 316 N90R27-36-00h15 Spring Washeis N56827-36-0016 ASMYE SA479 TYPE 316 Adjusting Bolt N96M&834-0012 ASME 5A479 TYPE 316 Spindlei N900162-32--002 AS$E SA479 TYPE 316
16 RFO Inservice Inspection Summary Page 59 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 Q.C.-44C-i Form NV-i (Back) Certficate Holder*6 Serial No. N9071&6 -0003 Sheet 2 of 2 Serial No. Material Specification I
-Grade Including Type or Spring -N4-B23so00 -73 ASTM A313 TYPE 316
- d. Bolting
- e. Other Parts such as Pilot Components Bonnet Stud N900163 ASME SA564 GR_ 630
-. *- Bonnet Nut _4j&fi7r&x IrlepoloRg ASME SA194,GR 8M We certify that the satements made in this report are correct Anderson Greenwood Crosby-Date "-jt)~i 20 0&. Signed Wrendiam, MA By --. /c>:ZýZ-Manufacturer Certificate of Authorization No. N-178 Expires 30-Sep-07 Date CER77FICATE OF SHOP INSPECTION L the undsrsigned, holding a valid commision issued by the National Board of Boiler and Pnrsur Vessel Inspectors and the State or Province of MA and employed by HSB - CT have inspected the equipment described in this Data Report on 6' 2006 and tate that to the best of my knowledge and belief, the Manmfacturer has corsscncted rids equipment in accordance with the applicable Subsections of ASME Section MII.
By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the equipment described in this Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal inury or property damage or a loss of any kind arising from or connected with this inspection. Date o . commissions MA-1420 .A N, I (National Board, State, Province and No.)
16 RFO Inservice Inspection Summary Page 60 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070.4 FORM NIS-2/NR-1/NVR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1, Owner FirstEnergy Corp. Date August 4. 2008 76 South Maiin St.. A rUn. OH 44308 Sheet 1 oft
- 2. Plant Devis-Besse Nuclear Power Station Unit #2 n a.
5501 N. SR. 2. Oak Harbor, OH 43449 200241t42t
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR, 2, Oak "arbor. .Of 43449 Authorization No. 20 Expiretion Date 07117/10
- 4. identitication ot Systems Pressurizer Power Relief Valve (PORV) DB-RC2A (SPARE) SUS
- 5. (a) Applicable Constrection Code ASMF III CL. 1971 Edition No Addenda Code Case No (b) Applicable Edition of Section Xt Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case No (c) DesignResponsibiltitis FirstEnergy Corp., Anderson Greenwood Crosby
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Seral No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped PORV Crosby Valve & Gauge C6d N56969 Ni/A DB-RC2A 1993 Repaired Yes 002 Pilot Valve Disc. Anderson Greenwood Crosby N95209 N/A N/A 2006 Replacement Yes 0010 Main Valve Disc Anderson Greenwood Crosby N90931 N/A N/A 2006 Replacement Yes 0010 Nozzle Anderson Greenwood Crosby N90931 N/A N/A 2006 Replacement Yes 0009 Nozzle (Pilot) Andersot Greenwood Crosby N90931 N/A N/A 2006 Replacement Yes 0020
- 7. Description of Work The above spare Power Actuated Pressure Relief Valve (PORV) was disassembled, refurbished with like for like replacement parts, reassembled and functionally tested (satisfactory) per procedure DB-MM-09000 then returned to stock for future use.
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other Yes Pressure 2250 psl Test Temperature N/A 'F Pressure Relief Valves:
Service Steam Size 2 A" Opening Pressure 2500 Blowdown (it applitable) N/A Sol Pressure and Blowdown Adjustments Made Using N/A at Davis Besse Nuclear Power Station NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 2 X 11 in. (2) Infornmation In items I through 6 an thin renoit is inrctudredon, earl, sheet curt 130 each sheet is nurmhered end the number ot sheels is recorded at the ten ot this loorm.-" this report is included on each sheet and 130 each sheet Is numbered and the number of sheets Is recorded at the (on of this form
16 RFO Inservice Inspection Summary Page 61 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-4 FORM NIS-2/NR-1/NVR-1
- 9. REMARKS Anderson Greenwood Crosby CERTIFICATE OF COMPLIANCE I, N/A , certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section Xl of the ASME Code and to the National Board Inspection Code "NR" rules.
National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date . FENOC Signed Q.c._.. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date Signed Commissions CERTIFICATE OF COMPLIANCE Jeffrey M. Martin , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of' the ASME Code and to the National Board Inspection Code "VR" and "NR" rules, National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/I0 Date :*9'/,9 &,/ ' FENOC Signed Q.C. CERTIFICATE OF INSERVICE INS"CTION 1, Tom Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on Au)(,,* Q9 ýj~r and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be:,': liable in any manner for any personal injury, property damage loss oI any kind arising from or connected with this Inspection. Date Qj Signed Commissions t4L '3
16 RFO Inservice Inspection Summary Page 62 of 235 FirstEnergy Nuclear Operating Company,.76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-1/NVR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Date November 7, 2008 76 South Main St.. Akron. OH 44308 Sheet I of I
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 Order 200282957 e~pdrO'" P.O.Noa..p .. so.
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No. 20 Expiration Data 07/17/10
- 4. Identiflcation of Systems Hanger HBD-27-6-HI Snubber SNA-407 Subsys 083-01
- 5. (a) Applicable Construction Code ANSI B3 1.1 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Section XI Utilized for Repairs or Replacements '19 95 Edition 96 Addenda Code Case n/a (c) Design Responsibilities Firstenergy Corp, Lisega
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Idenitifcationl Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code g
_ _ _ _'7_ _ t _ _ clacement Stamped 3018 Hydmulic snubber Lisega 61195/94 N/A SNA-407 -200t" Rlaced No 3018 Hydraulic snubber Lisega 30800149/012 N/A SNA-407 49ý t'Replacement No
- 7. Description of Work Existing Lisega Snubber 61195/94 was replaced with a new like for like replacement Lisega snubber 30800149/012.
As left inspection performed-SAT 5(i ) Cont. ANSI B31.I &MSS-SP58
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A psi Test Temperature NIA "F Pressure Relief Valves:
Service NIA Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size Is 8'A X 11 in. (2) Information in items 1 through 6on this report is included on each sheet, and (30 each sheet is numbered and the number of sheets Is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 63 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070.5 FORM NIS-2/NR-11NVR-1
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue , certify that the statements made in this report are correct arid the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules.
National Bolrd gertificate of Authorization No. 20 to use the "NR' stamp
*e'es 07/17/10 Date " FENOC Signed 1 Q.G.
CERTIFICATE OF INSERVICE INSPECTION I, Thomas G. Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have Inspected the work described in this report on IOV. Lt.I3.ooc6 and state that to thebestof my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xi of the ASME Code and the National Board Inspection Code 'NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this Inspection. Date Signed Commissions tý q113 Wt( CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made In this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section Xl of the ASME Code and to the National Board Inspection Code "VR" and CNR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed (_.C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have Inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VRC and 'NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal Injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 REO Inservice Inspection Summary Page 64 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070.5 wf..I FORM NIS-2/NR-1/NVR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Date November 7, 2008 76 SouthMain St.. Akron, OH 44308 Sheet 1 of 1
- 2. Plant Davis.Besse Nuclear Power Station Unit 5501 N. SR. 2, Oak Harbor, OH 43449 Order 200282958
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng 5501 N, SR, 2. Oak Harbor. OH 43449 Authorization No. 20 ExpIration Date 07/17/10
- 4. Identification of Systems Hanger M1148/H4 Main Steam snubber SNA-410 Subsys 083-01
- 5. (a) Applicable ConstructIon Code ANSI B31. 1 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case nJa (c) Design Responsiblltles Firstenergy Corp, Lisega A trtonttttn..tlnn cr1C.nmnnnants Renetrori nr Rontarert end Ronteremont flnmnnnc.nte Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Sodal No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 3018 Hydraulic snubber Lisega 61195/60 N/A SNA-410 24008-3 Replaced No 2 3018 Hydraulic snubber Lisega 30800149/014 NIA SNA-410 491- Replacement No
- 7. Description of Work Existing Lisega Snubber 61195/60 was replaced with a new like for like replacement Lisega snubber 30800149/014. .
As left inspection performed-SAT 5(a. Cont. ANSI B31.1 & MSS-SP58
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A psa Test Temperature N/A *F Pressure Relief Valves: .. _*
Service N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets In the form of lists, sketches, or drawings may be used, provided (1) size Is 8 A X 1 in. (2) Information In Items 1 through 6 on this report is Included on each sheet, and (30 each sheet Is numbered and the number of sheets Is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 65 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-11NVR-1
- 9. REMARKS CERTIFICATE OF COMPLIANCE Thomas M. Purdue , certify that the statements made In this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules.
National Board ertificate of Authorization No. 20 to use the "NR" stamp expires e 07/17110 Date 1i% FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Thomas 0. Laps holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described In this report on N o'.. ", 3.ec- and state that to -.... the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section-XI of the ASME Code and the National Board Inspection Code 'NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any 7 personal injury, property damage or loss of any kind arising from of connected with this inspection.
\\l Signed-mTtw¶ cr Commissions
- 03*- ,..,t/ A Date I (adnM N..tAJJ~~nhd nh CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of--
the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed _._____-,_- CERTIFICATE OF INSERVICE INSPECTION Wl~e I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHiO and employed by HSB CT of Hartford, CT have Inspected the repair, modification or replacement described In this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed In accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning the repair, modillcatlon or replacement described In this report. Furthermore, neither the undersigned nor my employer shall be;rý; liable in any manner for any personal Injury, properly damage or loss of any kind arising from or connected with this inspectibn. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 66 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-1/NVR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Date November 7, 2008 76 South Main St.. 4m. OH 44308 Sheet 1 of I
- 2. Plant Davis-Besse Nuclear Power Station Unit #1
.aro, 5501 N. SR. 2, Oak Harbor, OH 43449 Order 200282963
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oak Harbor, OH 43449 Authodzation No. 20 Exoiration Date 07/17/10
- 4. Identificatlon of Systems Hanger 3A-EBD- 19-H22 Snubber SNA-496 Subsys 083-01
- 5. (a) Applicable Constrsution Code ANSI B31.1 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case n/a (c) Design Responsibilities Firstenergy Corp, Lisega
- 6. Identification of Components Repaired or Replaced and Replacement Components _
NmofCmoet Name of manufacturer Manufacturer's Sedal No. National Board No. Other idenlification/ Jurisdictional No. Year Built Repairedor Replaced ASME Code 9c5p,=ment Stamped 3018 Hydraulic snubber Lisega 61195/46 N/A SNA-496 -2008-." Replaced No 3018 Hydraulic snubber Lisega 30800149/024 N/A SNA-496 4." Replacement No
- 7. Description of Work Existing Lisega Snubber 61195/46 was replaced with a new like for like replacement Lisega snubber 30800149/024.
As left inspection/VT-3 performed-SAT 5(a_) Cont. ANSI B31.1 & MSS-SP58
*ru, S. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure NIA pso Test Temperature N/lA 'F Pressure Relief Valves:
ServIce N/A Size NIA Opening Pressure NIA Slowdown (ifapplicable) N/A Set Pressure and Slowdown Adjustments Made Using N/A at NIA NOTE: Supplemental sheets In the form of lists, sketches, or drawings maybe used, provided (1) size Is 8 4 X 11 in. (2) Information In Items 1 through-6 on this report Is included on each sheet, and 130each sheet is numbered and the number of sheets Is recorded at the too of this form.
--. I
16 RFO Inservice Inspection Summary Page 67 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-1/NVR-1 Appf'" Mýr* WUlRMps WWMMWrtae
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue certify that the statements made.in this report are correct and the repair, modification, or replacement of the Items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules.
National Board ýertiflcate of Authorization No. 20 to use the "NR" stamp po I717/10 res Date -71 FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Thomas 0. Laps holding a valid commission.Issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have Inspected the work described In this report on ILF, 1 %3 Jeo, and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed'in accordance with Sectien-: XI of the ASME Code and the National Board Inspection Code "NR" rules. _.--_ By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning tke work described In this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal Injury, property damage or loss of any kind arising from of connected with this Inspection.
-a- Commissions IA k'43 ` ~'_ .'
CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07171710 Date FENOC Signed Q.c.______ e CERTIFICATE OF INSERVICE INSPECTION 1, N/A holding a valid commission Issued by the National Board of Boiler and Pressure Vessel -
- Inspectors and certificate of competency Issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed In accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules..1 By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described In this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this Inspection.
Date Signed Commissions
16 RFO Inservice Inspection Summary Page 68 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 flRJnnft*fl DB-0070-5 FORM NIS-2/NR-1/NVR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xi
- 1. Owner FirstEnersv Coro. Date November7, 2008 76 South Main St. Akron. OH 44308 Sheet 1 of 1 2: Plant Davis-Besse Nuclear Power Station Unit #1 N .
5501 N. SR. 2, Oak Harbor, OH 43449 Order 200282964
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No. 20 Expiration Date 07/17/10
- 4. Identification of Systems Hanger EBD-I 9-H48 Main Steam snubber SNA-497 Subsys 083-01
- 5. (a) Applicable Construction Code ANSI B31.1 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Section Xl Utilized for Repairs or Replacementa 19 95 Edition 96 Addenda Code Case n/a (c) Design Responsibilities Firstenerpy Corp, Lisega
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturers National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code 17 0 Replacement Stamped 3018 Hydraulic snubber Lisega 61195166 N/A SNA-497 -2G9'ý e No 3018 Hydraulic snubber Lisega 30800149/021 N/A SNA-497 1 Replacement No
- 7. Description ofWork Existing Lisega Snubber 61195/66 was replaced with a new like for like replacement Lisega snubber 30800149/021.
As found inspection performed-SAT. As found functional test performed-SAT As left inspection/VT-3 performed-SAT 5(a_) Cont. ANSI B31.1 &MSS-SP58
-Pt..
- 8. Tests Conducted: Hydrostatio No Pneumatic No Nominal Operating Pressure No Other No .
Pressure NIA psi Test Temperature N/A 'F -.- Pressure Relief Valves: ...... Service NIA Size N/A .. Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Slowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets Inthe form of lists, sketches, or drawings may be used, provided (1) size Is 8 Y, X 11In. (2) Information In Items 1 through 6 on this report Is Included on each sheet, and (30 each sheet Is numbered and the number of sheets Is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 69 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070.5 FORM NIS-2/NR-1/NVR-1
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue , certify that the statements made In this report are correct and the repair, modification, or replacement of the items described above conforms to Section Xf of the ASME Code and to the National Board Inspection Code "NR' rules.
National BoarY Certificate of Authorization No. 20 to use the "NRa stamp expire 07/17/10 Date )F 'NOC
.. Signed .
CERTIFICATE OF INSERVICE iNSPECTION 1, Thomas G. Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIOO and employed by HSB CT of Hartford, CT have inspected the work described in this report on NQ0f. t3 ,.cr& and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed In accordance with Section:,: X) of the ASME Code and the National Board Inspection Code "NR" rules, By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this Inspection. Date I indCommissions ý,ý3 K A c_ CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to.Section XI of-the ASME Code and to the National Board inspection Code "VA" and "NR" rules.. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 -. National Board Certificate of Authorization No. 20 to use the 'NR" stamp expires 07/17/10 .... Date FENOC Signed ._._Q.C._..,_. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xi of the ASME Code andthe National Board Inspection Code "VR" and "NR" rules . By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning-the* repair, modification or replacement described In this report. Furthermore, neither the undersigned nor my employer shall be,e liable in any manner for any personal Injury, property damage or loss of any kind arising from or connected with this inspectibn. Date Signed Commissions -
16 RFO Inservice Inspection Summary Page 70 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 -],c FORM NIS-21NR-1/W*--OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- i. Owner FirstEnerey Coro. Date February 09, 2009 76 South Main St.. Akron. OH 44308 Sheet I of I
- 2. Plant Davis-Besse Nuclear Power Station Unit N.
5501 N. SR. 2, Oak Harbor, OH 43449 200282965
- 3. Work Porformod by FlirstEnergy Nuclear Operating Co. Type Code Stamp Ng' 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No. 20 Exptration Date 07/17/10
- 4. Identification of Systems Hanger EBD-19-H76 Main Steam Snubber DB-SNA50 Subsys DB-SUB083-01
- 5. (a) Applicable Construction Code ANSI B3 1.1 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Section IUOitlzed for Repairs or Replacements 19 95 Edition 96 Addenda Code Case NIA (c) Design Responsibilities Firstenergy Corp, Grinnell
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Starnited 1.5"Hydraulic Snubber Grinnell 30513 N/A SNASO 1995 Replaced No 1.5" Hydraulic Snubber Grinnell 36833 N/A SNAbO 2008 Replacement Nol}
7, Description of Work Existing Grinnell snubber 30513 was replaced with a Configuration A replacement Grinnell snubber 36833 VT-3 inspection performed SAT. 5(a) Coni. ANSI B31.1 & MSS-SP-58 A4IL
- a. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A pso Test Temperature N/A -F Pressure Relief Valves:
Service N/A Size N/A " Opening Pressure N/A Slowdown (it applicable) N/A Set Pressure and Slowdown Adjustments Made Using N/A at N/A NOTE: Supptemental sheets In the form of lists, stetches, or drawings may be used, provided (1) size is 8 55X I1In. (2) Information in items I through 6 on this renort Is Included on each sheet, and (30 each sheet Is numbered and the number of sheets is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 71 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 D "-0 070-5 - - FORM NIS-2/NR-1/Wf ' "
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue. certify that the statements made in this report are correct and the repair, modification,'or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspectlon:,T..
Code "NR" rules. National Boarq Certificate of Authorization No.. 20 to use the "NR" stamp expires , 4_/17/10 t.... Date . FENOC Signed 4Q.C. " CERTIFICATE OF INSERVICE INSPECTION I, Thomas G.Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessei;*" Inspectors and certificate of competency issued by the jurisdiction of " OHI-O and employed by HSB CT of Hartford, CT have Inspected the work described in this report on OC-I . ig otj and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed In accordance with Section Xi of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any .warranty,expressed or implied, concerning tlie work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this Inspection. Date ý. -1J Signed 'ýt p Commissions 't 3 CERTIFICATE OF COMPLIANCE I, N/A certify that to the best of my knowledge and belief the statements made In this repor alTe: correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI ot-' the ASME Code and to the National Board Inspection Code "VR" and "NIR" rules. Nationat Board Certificate of Authorization No. 316 to use the "VR" stamp expires National Board Certificate of Authorization No, 20 12/13/O F to use the "NR" stamp expires 0717/110 Date FENOC Signed _ Q.c._ CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission Issued by the National Board of Boiler and Pressure Vessel. Inspectors and certificate of competency Issued by the jurisdiction of OHIO and employed by X HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on . and state that to the best of my knowledge and belief, this repair, modification or replacement has be.ei. completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules..::. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning.tIhe repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall b'eile" liable In any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspeotion. Date Signed Commissions .__"
16 RFO Inservice Inspection Summary Page 72 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 OB-01070-5 !'.41*1 FORM NIS-2/NR-1/NVRaH OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Date April 15, 2009 76 South Main St. Akron, O 44308 Sheet i of 1
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 200282967
- 3. Work Perdormed by Ffrst.nergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oakkarbor, OH 43449 Authorization No. 20 Exoiration Date 07/17/10
- 4. Idesltfication of Systems Hanger EBD-19-1110, Main Steam System SNA74, Subsys DB-SUBO83-01
- 5. (a) ApplicableConstructionCode ANSI B31.1 1967 Edition Later Addenda Code Case N/A (b) Applicable Edition of Section XI Utiiized for Repairs or Replacements 19 95 Edition . Addenda Code Case N/A (c) Design Responsibilitiles Firstenergy Corp, Grinnell
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdlctional No. Built Replaced or Code Replacement Stamped 1.5" Hydraulic Snubber Grinnell 70475 N/A SNA74 1995 Replaced No 1.5" Hydraulic Snubber Grinnell 36999 NIA SNA74 2008 Replacement No
- 7. Description of Work Existing Grinnell snubber 70475 was replaced with a Configuration A replacement Grinnell snubber 36999.
VT 3- inspection perfornedSAT. 5(a) Cont. MSS-SP-58
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A psu Test Temperature N/A -F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdown (litapplicable) N/A Sot Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size Is 8 Y2X 11 In. (2) Information in Items 1 through eon this report is Included on each sheet, and (30 each sheet Is numbered and the number of sheets Is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 73 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-1/N-i i ,/iý ' S. REMARKS CERTIFICATE OF COMPLIANCE 1, Thomas M. Purdue certify that the statements made In this report are correct and the repair, modification, or replacement of the items described above conforms to Section Xl of the ASME Code and to the National Board Inspection Code "NR' rules. National Board C rtificate of Authorization No. 20 to use the "NR" stamp expires 07/17110 Date _00*1>Oo° FENOC Signed 52 n. ,-1II Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Bruce North holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of OI-O and employed by HSB CT of Hartford, CT have inspected the work described In this report on q 0 1 arid state that to the best of my knowledge and belief, this repair, modification or replacement has been completed In accordance with Section Xl of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this Inspection. Date. Signed "l 6 -Commispionsit CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION 1, N/A holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT _ have Inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed In accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this Inspection. Date Signed - Commissions
16 RFO Inservice Inspection Summary Page 74 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0oos070I-FORM NIS-2/NR-l1N'U-R* OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. owner FirstEnergy Corp. Date February 05, 2009 76 South Main SL.. Akron, OH 44308 Sheet I of I
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 200282968
- 3. Work Parormod by FirstEnerelNuclear Operating Co. Type Code Stamp Ng.
5501 N. SR, 2. Oak Harbor, OH 43449 Authorization No. 20 Espiratlon Data 07/17/10
- 4. Identification of Systems Hanger CCB-6-HI Decay Heat and low pressure injection DB-SNA 79 Subsys DB-SUB049-02
- 5. (a) Applicable Construction Code ANSI B31.1 1967 Edition Later Addenda Coda Case N/A _.
(b) Applicable Edition of Section XIUtilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N/A (c) Design Responsibilities Firstenergy Corp, Grinnell
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturers National Other Identification/ Year Repaired AS)
Name of Component Name of Manufacturer Serial No. Board No, Jurisdictional No. Built Replaced or CbdO Replacement Staq*d 1.5" Hydraulic Snubber Grinnell 13262 N/A SNA79 1991 Replaced No 1.5" Htydraulic Snubber Grinnell 37000 N/A SNA79 2008 Replacement No 'i
- 7. Description of Work Existing Grinnell snubber 13262 was replaced with a Configeration A replacement Grinnell snubber 37000 r" VT-3 inspection performed SAT.
5(a) Cont. MSS-SP-58 ri,'t*
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A psi . . Test Temperature N/A -F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets Inthe form Of lsts, sketches, or drawings may be used, provided (1) size Is 8 VAX II In. (2) Information In items 1 througiP"ort this report Is Included on each sheet, and (30 each sheet Is numbered and the number of sheets Is recorded at the top of this form. Wit
16 RFO Inservice Inspection Summary Page 75 of 235 FirstEnergy Nuclear Operating Company, 76 South Main.St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-IUW (;I-9, REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue , certify that the statements made in this report are correct and the repair, modificaffon, o replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection!"* Code "NR" rules. National Boarl Crtificate of Authorization No. 20 to use the "NR' stamp expires 07/17/10 Date __FENOC Signed G. 3. . / -- Q.c. CERTIFICATE OF INSERVICE INSPECTION I, Thomas G. Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of OHIO and enpIoyed by HSB CT of Hartford, CT have Inspected the work described in this report on -_,6Z - *:acp and state that to - the best of my knowledge and belief, this repair, modification or replacement has been completed In accordance with Section-XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning'e work described in this report. Furthermore, neither the undersigned nor my employer shall be liable In any manner for any,--.- personal Injury, property damage or loss of any kind arising from of connected with this inspection. Date 44ig Signed a" &, X Commissions t"Z '3 I, r " )A CERTIFICATE OF COMPLIANCE I, N/A ,certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of: the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed .Q.C. . CERTIFICATE OF INSERVICE INSPECTION I uile I, N/A holding a valid commission Issued by the National Board of Boiler and Pressure VesseVf Inspectors and certificate of competency Issued by the jurisdiction of OHO and employed by .. HSB CT of Hartford, CT have Inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has b6*dt-completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules...: By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied; concerning"Ihe repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall bui" liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions a~5oM~,&m
16 RFO Inservice Inspection Summary Page 76 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB.0070-S .. In k FORM NIS-2/NR-1iNVR-1,OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Date February 19, 2009 76 South Main S.. Akron, Off 44308 Sheet I of 1
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2. Oak Harbor. 011 43449 200282972 3, Work Performed by FirstEnergs Nuclear Operating Co. Type Coda Stamp NR 5501 N. SR, 2. Oak Harbor. OH 43449 Authorization No. 20 Explratlon Date 07/17/10
- 4. Identification of Systems Hanger GCB-1-H7 Decay Heat and low pressure injection DB-SNA 89 Subsys DB-SUB040-02
- 5. (a) Applicable Construction Code ANSI B31.1 1967 Edition Later Addenda Code Case N/A (b) Appltcable Edition ot Section XI Utilized for Repairs or Repiacements 19 95 Edition 96 Addenda Code Case N/A (c) Design Responslblillies Firstenergy Corp, Grinnell :4
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Sedal No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 2.5" Hydraulic Snubber Orinnell 24091 NIA SNA89 1996 Replaced No 2.5" Hydraulic Snubber Grinnell 36926 N/A SNA89 2008 Replacement No
- 7. Description of Work Existing Grinnell snubber 24091 was replaced with a Configuration A replacement Grinnell snubber 36926 VT-3 inspection performed SAT.
5(a) Cent. MSS-SP-58 7."
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No ---
Pressure N/A pSI Test Temperature N/A OF F ... Pressure Relief Valves: Service N/A Size NIA .. Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental shoets in the iorm of lists, sketches, or drawings may be used, provided (1) size is 8 14X 11 In. (2) Information In Items 1 through-6 on this report Is included on each sheet, and (30 each sheet Is numbered and the number of sheets is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 77 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB'0070-5 FORM NIS-2/NR-1/NVRI4
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue certify that the statements made In this report are correct and the repair, modification. or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection .:.,
Code "NR" rules. National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date I -'I I o, FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, -p holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the Jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described In this report on 1j 13-09 and state that to-the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section-XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any'7* personal injury, property damage or loss of any kind arising from of connected with this inspection. Date- t S--09 Signed -, A.,1P_lid. Commissions CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made In this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section X1 of-- the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/tO 1I. National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07117/10 Date FENOC Signed _- Q.c.__ CERTIFICATE OF INSERVICE INSPECTION I. I, N/A holding a valid commission Issued by the National Board of Boiler and Pressure Vessel" Inspectors and certificate of competency Issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall beiw. liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this Inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 78 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-1N4-, OWNNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Data February 19, 2009 76 South Main St. Akron. OH 44308 Sheet 1 of I .s~.
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 N52,O 5501 N. SR. 2, Oak Har'bor, OHl 43449. 200282973
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp N 5501 N. SR. 2. Oak Harbor. OH 43449 Authorlzaton No. 20 Expiration Date 07/17/10
- 4. Identifieation of Systems Hanger GCB- I-H10 Decay Heat and low pressure injection DB-SNA 90 Subsys DB-SUB049-02
- 5. (a) Applicable Construction Code ANSI B3 1.1 1967 Edition Later Addenda Code Case N/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N/A (c) Design Responsibilities Firstenergy Corp, Grinnell
- 6. Identifloation of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Sulilt Replaced or Code Replacement Stamrnpd 2.5" Hydraulic Snubber Grinnell 10068 N/A SNA90 1996 Replaced No 2.5" Hydraulic Snubber Grinnell 36928 N/A SNA90 2008 Replacement No
- 7. Description of Work Existing Grinnell snubber 10068 was replaced with a Configuration A replacement Grinnell snubber 36928 VT-3 inspection performed SAT.
5(a) Cont, MSS-SP-58 51,.1.
'"I['
S. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A psi Test Temperature N/A 'F Pressure Relief Valves: Service N/A SiZe N/A ... Opening Pressure N/A Blowdown (Ifapplicable) N/A Set Pressure and Slowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1)size Is8 A X 11 In.(2) Information InItems 1 through-6.on this report IsIncluded on each sheet, and (30 each sheet Innumbered and the number of sheets Is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 79 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB.0070.5 FORM NIS-2/NR-1IN*R-1t '
- 9. REMARKS CERTIFICATE OF COMPLIANCE -.
Thomas M. Purdue , certify that the statements made in this report are correct and the repair, modification; or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection-,,.- Code "NR"-rules. National Board Certificate bf Authorization No. 20 to use the "NR" stamp 9 plres 07/17/10 Date J.) I FENOC Signed Q.C. L'l_-_ l*o*Tli.-* CERTIFICATE OF INSERVICE INSPECTION I, *h~ holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of OHIO and employed by " HSB CT of Hartford, CT have inspected the work described in this report on 3 09* and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection, ____________________),:_or Date "-t3*O9 Signed Commissions Cqt3" , 1. 09(,Q VIC CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section Xl of-the ASME Code and to the National Board Inspection Code "VR" and "NR* rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 I National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.c._on-__ CERTIFICATE OF INSERVICE INSPECTION trio 1, N/A holding a valid commission Issued by the National Board of Boiler and Pressure Vessel" Inspectors and certificate of competency issued by the jurisdiction of OHiO and employed by . HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been. completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall bed', liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 80 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0570-S .- 14q FORM NIS-2/NR-1/NWft- OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xi
- 1. Owner FirstEnergy Corp. Date January 28, 2009 N*a 76 South Main St.. Akron. OH 44308 Sheet 1 of 1
- 2. Plant Davis-Besse Nuclear Power Station Unit #11 5501 N. SR. 2, Oak Harbor, OH 43449 200282974 gruN .O eps i.. Joe b . i
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng 5501 N. SR, 2. Oak Harbor. OH 43449 Authorization No. 20 Expiration Date 07/17/10
- 4. Identification of Systems Hanger HCB-3-H16 Containment Spray DB-SNA98 SubsysDB-SUB061-01
- 5. (a) Applicable Construction Code ANSI B31.1 1967 Edition Later Addenda Coda Case N/A (b) Applicable Edition of Section XIUtilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N/A (c) Design Responsibilities Firstener.y Corp, Grinneil d.
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identiiicalion/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Starrmp9d 1.5" Hydraulic Snubber Grinnell 30515 N/A SNA98 1995 Replaced No 1.5" Hydraulic Snubber Grinneil 36997 NIA SNA98 2008 Replacement No
- 7. Description of Work 1Fxisting Grinnell snubber 30515 was replaced with a Configuration A replacement Grinnell snubber 36997 VT-3 inspection performed SAT.
5(a) Cont. MSS-SP-58
ýirap
- 8. Tests Conducted: Hydrostatic No Pneumatlc No Nominal Operating Pressure No Other No Pressure NIA psi Test Temperature NIA 'F OF Pressure Relief Valves:
Service N/A Size NIA -" Opening Pressure N/A Biowdown (it applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets Inthe form of Iists,sketches, or drawings may be used, provided (1) size is 8 1 XX I1 In. (2) Information in Items 1 througlf-Vgon this remoit is Included on each sheet, and D30 each sheet Is numbered and the number of sheets Is recorded at the too of this form..
16 RFO Inservice Inspection Summary Page 81 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-1/N~1--
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue , certify that the statements made In this report are correct and the repair, modifIcatiorirW replacement of the Items described above conforms to Section XI of the ASME Code and to the National Board lnspecilon'St.',I;:
Code "NR" rules. National Boary COrtlficate of Authorliation No. 20 to use the "NR" stamp expires 07/17/10 Date ___________ FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Thomas G. Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and erplotyed by - HSB CT of Hartford, CT have inspected the work described in this report on -X_ and state that to best of my knowledge and belief, this repair, modification or replacement has been compeletd in accordance with Secti66-XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concernlngthe work described in this report. Furthermore, neither the undersigned nor my employer shall be liable In any manner for any,. personal injury, property damage or loss of any kind arising from of connected with this inspection. Commissions I"13S'3 I Date slo Signed CERTIFICATE OF COMPLIANCE I, NIA ,certify that to the best of my knowledge and belief the statements made In this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of' the ASME Code and to the National Board Inspection Code "VA" and "N" rules, National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07117/10 Date FENOC Signed Q.c.____.- CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel - Inspectors and certificate of competency Issued by the jurisdiction of OHIO and employed by , in IISB CT of Hartford, CT have Inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has bidh-completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. , By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning'the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall besr liable in any manner for any personal Injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 82 of2235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 [ o~os-Commercial Service Date: July 31, 1978 DS-0070-5 F'* L FORM NIS-2INR-1/NVRr-T OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Date February 09, 2009 76 SouhManSt.Akron. OH 4308 Sheet I of I
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 200282975 to
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Cods Stamp NR 5501 N. SR. 2. OakHarbor. OH 43449 Authorization No. 20 Expiration Date 07117/10
-- I
- 4. Identificatlon of Systems Hanger HCB-3-H17 Contaniment Spray DB-SNA99 Subsys DB-SUB061-01
- 5. (a) Applicable Construction Code ANSI B31.1 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Section XIUtilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N/A (a) Design Responsibilities Firstenergy Corp, 6rinnell
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identilfcation/ Year Repaired ASME Name of Component Name of Manufacturer Serial No, Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 1.5" Hydraulic Snubber Grinnell 30511 N/A SNA99 1995 Replaced No 1.5" Hydraulic Snubber Grinnell 37001 NIA SNA99 2008 Replacement No
- 7. Description of Work
- Existing Grinnell snubber 30511 was replaced with a Configuration A replacement Grinnell snubber 37001 VT-3 inspection performed SAT.
5(a) Cont. ANSI B31.1 & MSS-SP-58 7-"
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure NIA psi Test Temperature N/A. 'F
°F Pressure Relief Valves:
Service NIA Size N/A Opening Pressure N/A Blowdown (If applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets In the form of lists, sketches, or drawings may be used, provided (1) size Is 8 %X 11 In. (2) Information In Items I through-S-on this report Is Included on each sheet, and (30 each sheet Is numbered and the number of sheets Is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 83 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-1 /N.R-1 A W 0..
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue , certify that the statements made in this report are correct and the repair, modification. or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection:,.ý.
Code "NR" rules. National Bo rd pertificate of Authorization No. 20 to use the "NR" stamp expires 107/17110 Date ;VI FENOC Signed Q.c. CERTIFICATE OF INSERVICE INSPECTION I, Thomas G. Laps holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of OH-IO and employed by . HSB CT of Hartford, CT have Inspected the work described in this report on and state that to-the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section-- XI of the ASME Code and the National Board Inspection Code 'NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerningthe work described in this report. Furthermore, neither the undersigned nor my employer shalt be liable in any manner for any personal Injury, property damage or loss of any kind arising from of connected with this inspection. Date _____8q Sged Commissions tAb II - A cový CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of-, the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 t National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed !?.C._-,__ CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vesse[' Inspectors and certificate of competency Issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report, Furthermore, neither the undersigned nor my employer shall beir liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this Inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 84 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2INR-1/NVR=I OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. owner FirstEnergy Corp. Date March 30, 2009
'76 South Main SL. Akron. OH 44308 Sheet 1 of 1
- 2. Plant Davis-Besse Nuclear Power Station Unit 011 5501 N. SR. 2. Oak Harbor, OH 43449 200282980 R".;,a na. ,P.O.N,. ro N,. .
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng 5501 N. ,SR. 2. Oak P~arhor. 011 43440 Authorlzatton No. 20 OFT 43449 5501 N. SR. 2 Qak Rarbor Expiration Date 07117/10
- 4. Identification of Systems Hanger EBD-19-H62, Main Steam System SNT-25, Subsys DB-SUBH083-01
- 5. (a) Applicable Construction Code ANSI B31.1 1I 67 Edition Later Addenda. Code Case N/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N/A (c) Design Responsibilities Firstenergy Carp, Grinnell
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Component Manufacturers National Other Identification/ Year Repaired ASME Name of Manufacturer Sedal No. Board No. Jurlsdictional No. Built Replaced or Code Replacement Stamped 1.5" Hydraulic Snubber Grinnell 11820 N/A SNT25 1992 Replaced No 1 5"HydraulicSnubber Grinrell 36959 N/A SNT25 2008 Replacement No
- 7. Description of Work Existing Grinnell snubber 11820 was replaced with a Configuration A replacement Grinnell snubber 36959.
VT- inspection performed SAT. 5(a) Cont. MSS-SP-58 I. I
- 8. Tests Conducted: Hydrostatic No Pneumatts No Nominal Operating Pressure No Other No Pressure _N/A arest PSI Temperature N/A *F:
Pressure Relief Valves: Servlce N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using NIA at N/A NOTE: Supplemental shoots In the form ot lists, sketches, or drawings may be used, provided (1) size Is 6 %tX 11 In. (2) Information In Items 1 through 6 on this report is included on each sheet, and (30 each sheet Is numbered and the number of sheets Is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 85 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NiS-2INR-1IWeNR
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue , certify that the statements made in this report are correct and the repair, modification, or replacement of the Items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules.
National Boafd Certificate of Authorization No. 20 to use the "NR" stamp_ expires iel7.10 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described In this report on 3-A-.- bq and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed In accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable In any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date Signed Commissionso 090 CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair. modification, or replacement of the pressure relief devices described above conforms to Section Xl of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the 'VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NP" stamp expires 07117110 Date _FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OlIO and employed by H-SB CT of Hartford, CT have Inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described In this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal Injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Comm issions
16 RFO Inservice Inspection Summary Page 86 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-4 FORM NIS-2/NR-I/NVR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. nat July, 29 2010 76 South Main St.. Akron. OH 44308 Sheet 1 of 2
- 2. Plant Davis-Besse Nuclear Power Station Unit #t' 5511 N. SR. 2. Oak :larber. OH 43449 200298766
- 3. Work Performed by FirstEnery. Nuclear Operating Co. Type Code Stamp NR 5501 N. SR, 2, Oak Harbor. OR 43449 Authorization NO. 20 Expiration Date 07/17/13
- 4. Identification of Systems Main Steam Line Warmup Drain Isolation Valve
- 5. (a) Applicable Construction Code ASME3 CL.I! 1971 Edition W72 Addenda Code Case No (b) Applicable Edition ot Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case 416-3 (c) Design Responsibililtes FirstEnargy Corp.
A Irlentificelion nf flnmnnnnnfn Senaired or Renter-srI and Rentenement flnmnrrnenls Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Seral No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped I 1/2" bolted bonnet Velan 522-2 UNK DB-MS703 1975 Replaced YES gate valve I V,"boiled bonnet Velan 041032-6 UNK DB-MS03 2006 Replacement YES gate valve
- 7. Description of Work Existing valve for MS 703 was replaced during maintenance activities. NDE (PT) was performed on the welds (per code case 416-3).
A VT-2 inservice leakage test (per code case 416-3) was performed satisfactory as part of the post repair/replacement examination.
- 8. Tests Conducted: YES Hydrostatic No Pneumatic No Nominal Operating Pressure YES Other No Pressure 877 psi Test Temperature 528 *F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdown 0f applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A st N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 1 X 11 in. (2) Information in Items I through 6 on this report is included on each sheet, and (30 each sheet is numbered and the number of sheets is recorded at the top of Ihis form.
16 RFO Inservice Inspection Summary Page 87 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-4 FORM NIS-2INR-1/NVR-1 n,daureflO. Afl,¢Iw~oMa OaIIRplpoIo be .lh,*ed
- 9. REMARKS Velan/Frainatone CERTIFICATE OF COMPLIANCE I, Jeffi'ey M. Martin certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules.
National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/13 Date 07/29/2010 FENOC Signed CERTIFICATE OF INSERVICE INSPECTION I, Thomas Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on 07/29/2010 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section .. XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection.
,1. 1. " , t
- Date 07/2912010 Signed Commissions . 'Th"O t TI .A c .
CERTIFICATE OF COMPLIANCE I, N/A certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section Xl of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/13 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and.Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section X1 of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions Nl Iwad M W, Jria r.) .
16 RFO Inservice Inspection Summary Page 88 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-1INM -OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner F7rstEnhrgT Corp. Date December 15,2008 76 South Main St.. Akron. OH 44308 Sheet I of 1
- 2. Plant Davls-Besse Nuclear Power Station Unit #1 A.Aar OIY4fO5'q.1NN 5501 N. SR. 2. Oak Harbor. OH 43449 AMd...
*e sk Cqh.,,on P.O.N". Jo No.. a
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oak Harbor, OH 43449 Authorization No. 20 Expiration Date 07/17/10"
- 4. Identification of Systems Hanger GCB-5-1432 CTMT Spray snubber SNA92 Subsys 061-01
- 5. (a) Applicable Construction Code ANSI B31.1 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N/A (c) Design Responsiblilties Firstenerpy Corp, Grinnell
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name ol Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 1.5" Hydraulic snubber Grinnell 21303 N/A SNA92 2000 Replaced No 1.5' Hydraulic snubber Grinnell 36832 N/A SNA92 2008 Replacement No
- 7. Description of Work Existing Grinnell snubber 21303 was replaced with a Configuration A replacement Orinnell snubber36832 As left VT-3 inspection performed SAT 5(a)Cont. ANSI B31.1 &MSS-SP58
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A psi Test Temperature N/A -F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure NIA Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets Inthe form of lists, sketches, or drawings may be used, provided (i) size Is 8 A X I I In. (2) Information In Items i through 6 on this report is included mis~~~~~~~~~~~~~ onamL. or, eachl shooti and a, ~u aiu~urua 0 u1 (3y0 eachshratll~~ is1ilUltarid uIl andlUtie IIIO IIUmbi lUU Ia~n Uhat Iaco s*I*G SIC 0 eU-Jat lp'L aGis feor oel I[
-sIuun
.lIU I....
16 RFO Inservice Inspection Summary Page 89 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-1IJN*-
- 9. REMARKS CERTIFICATE OF COMPLIANCE 1, Thomas M. Purdue , certify that the statements made In this report are correct and the repair, modifications-or-replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection...
Code "NR" rules. National Board Certificate of Authorization No. 20 to use the "NR" stamp qxpires P7/17/10 Date I;)] FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Thomas 0. Laps holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the Jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on 20o, _ and state that to the best of my knowledge and belief, this repair, modification or replacement has been c6mpletea in accordance with Section-XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerningthd' work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any' personal Injury, property damage or loss of any kind arising from of connected with this inspection. Date Signed Commissions _413 36 t* A CERTIFICATE OF COMPLIANCE
, __ certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules.
National Board Certificate of Authorization No. 316 to use the "VR" stamp expires t2/t3/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed _ _ Q.C.__ CERTIFICATE OF INSERVICE INSPECTION 1, 7holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by , HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall beirr liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date _ Signed Commissions
16 RFO Inservice Inspection Summary Page 90 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 - Commercial Service Date: July 31, 1978 OBD-070-5 , -/o FORM NIS-2INR-1/NVR't=' OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section X1
- 1. owner FirstEnergy Corp. Date December 15, 2008 am..
76 South Main St.. Akron. OH 44308 Sheet 1 of 1
- 2. Plant Davls-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 Order 200310180
- 3. Work Performed by ]FirstEnerg QNuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No. 20 Expiration Date 07/17/10
- 4. Identiticatton of Systems Hanger GCB-5-H32 CTMT7 Spray snubber SNA93 Subsys 061-01
- 5. (a) Applicable Constructlon Code ANSI B31.1 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Sectlon XIUtilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N/A (o) Design Responsibllittes Firstenergy Corp, Grinnell 0 i~~ntrfl,~tttm, -.1 flmmnnnont~ flonaliad n, i3aniannrl and Ranlarumant flomnonanta Manufacturer's National Other Identificatloan Year Repaired ASME Name of Component Name ofManufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Cede Replacement Stamped 1.5" Hydraulic snubber Grinnell 18380 N/A SNA93 1993 Replaced No 1.5" H*ydraulicsnubber Grinnell 36998 N/A SNA93 2008 Replacement No
- 7. Description of Work Existing Grinnell snubber 18380 was replaced with a Configuration A replacement Grinnell snubber 36998 As left VT-3 inspection performed SAT 5(a) Cont. ANSI B31.1 & MSS-SP58 nl**
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A psi Test Temperature NIA *F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Slowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets In the lorm of lists, sketches, or drawings may be used, provided (1) size Is 8 YzX 11 In. (2) Intormation In.Items I through-Son this report Is Included an each sheet, and (30 each sheet Is numbered and the number of sheets Is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 91 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 OB-0070-5 FORM NIS-2/NR-1/NVRaT
- 9. REMARKS CERTIFICATE OF COMPLIANCE Thomas M. Purdue certify that the statements made In this report are correct and the repair, modilication, or.
replacement of the items described above conforms to Section Xi of the ASME Code and to the National Board Inspection ,.- Code "NR" rules. National Board Certificate of Authorization No. 20 to use the "NR" stamp expires .4/17/10 Date J,.Q)O FENOC Signed _ ,S. Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Thomas 0. Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel': Inspectors and certificate of competency issued by the Jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on W . 8, d and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section-Xi of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable In any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date \h 8 l Signed -- t Commissions 1' ., _.%,. lp/I-I.f CERTIFICATE OF COMPLIANCE 1I, ft , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of" the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "R" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07117/10 Date _FENOC Signed Q.C. 0'r CERTIFICATE OF INSERVICE INSPECTION 1, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described In this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has be~n completed in accordance with Section X1of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described In this report. Furthermore, neither the undersigned nor my employer shall be-. liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this Inspection. Date Signed Commissions
.M~ono~M no))
16 RFO Inservice Inspection Summary Page 92 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DR-ce70.5 nR-0070-5 FORM NIS-2fNR-I/NVR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI I. Owner FirstEnergy Corp. Date July 15,2010 76 South Main St.. Akron. OH 44308 Sheet 1 of I
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, Of 43449 200312302
, Onn~fls P.O.5N. JabN,...o W0p.R
- 3. Work Performed by FirstEnersy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oakf Harbor. ON 43449 Authorization No. 20 EXOtration Data 07/17/2013
- 4. Identification of Systems RX Vessel Jnternals& Lifting Facilities Hydrolic Snubber Support RC-M1 170-H3 (SNC-413)
- 5. (a) Applicable Construction Code ASMEItI CLI 1971 Edition No Addenda Code Case N/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N/A (c) Design Responsibilities FirstEnergy Corp R htunltfirsttnn of C.omnnnanle Punnirud nr Penlarurt and Rentnrnmsnt flnn~nnnentn Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictlional No. Built Replaced or Code Replacement Stamped 3"Load Stud UNK lINK N/A UINK LINK Replaced NO 3"Loed Stud UNK LINK N/A PO 7005646 UNK Replacement NO
- 7. Description of Work Parts tisted above were replaced under routine maintenance.
A VT-3 examination test was performed satisfactory. B. Tests Conducted: Hydrostatic No Pneumatic No NomlnasOperating Pressure N/A Other No Pressure N/A psi Test Temperature N/A F Pressure Relief Valves: Service N/A Size N/A Opening Pressure N/A Blowdown (if appilcable) N/A Set Pressure and Slowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 %X t1 in. (2) Information in items 1 through 6 on thts roesortis inluetdnaon each sheet and 130each shae~tis numbered and the number of sheets is recorded at the toe ot thintorm.
...... re r is. in
... lu . e . on.
.. eac
. . sheet.an
.. . e.h .13 .. e.is.... um.. ed
.. .a.dthe.n..... of. s eets. isr.c................... isfor.....
16 RFO Inservice Inspection Summary .Page 93 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-6 FORM NIS-2/NR-I/NVR-1 ACPP lWaI Mf g WUS lU, Rep0 toW O.REMARKS None CERTIFICATE OF COMPLIANCE I, Jeffrey M. Martin certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board inspection Code "NR" rules. National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17[13 Date 07/15/2010 FENOC Signed .)- 2QC. I, Tom Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on 07/15/2010 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 07/15/2010 Signed ~ i .Commissions f'1.B i33e6 tA it A CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12(13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/13 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO _ and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section X1 of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
?4tO~~O~,dCOd
,OOJOOdOdO.Od,,o))
16 RFO Inservice Inspection Summary Page 94 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-21NR-1/NVR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. nDte Julv15, 2010 76 South Main St.. Akron. OH 44308 Sheet 1 of I
- 2. Plant Davis-Besse Nuclear Power Station Unit 5501 N. SR, 2, Oak Harbor, OH 43449 200312302 RýPw Oq.N5UN 0. 50451,, ,
- 3. Work Performed by .FirstEnergy Nuclear Operating Co. Type Code Stamp Ng 5lare, 5501 N. SR. 2. Oak Harbor, OHl 43449 Authorization No. 20 Exoiratlon Date 07/17/2013
- 4. Identification of Systems RX Vessel Internals & Lifting Facilities Hydrolic Snubber Support RC-MI 170-H2 (SNC-412)
- 5. (a) Applicable Construction Code ASMEII CLI 1971 Edition No Addenda Code Case N/A (b) Applicable Edition of Sectlon Xl Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case NfA (c) oesign Responsibilities FirstEnergy Corp R Irlenlitinatton rd lŽnmnnnent'n Renruired mrRenlur-'nrt and Panlanement flnmnnnenln Manufacturer's Notional Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No, Jurisdictional No. Built Replaced or Code Replacement Stamped 3"Load Stud UNK UNK N/A UNK UNK Replaced NO 3"Load Stud UNK TINK N/A PC 7005646 UNK Replacement NO
,"x 2 1/2" BOLT LINK tINK N/A UNK IJNK Replaced No V"x 2 1/2" BOLT I UNK I(NK N/A PO 45331211 LINK Replacement No
- 7. Description of Work Parts listed above were replaced under routine maintenance A VT-3 examination test was performed satisfactory.
- a. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure N/A Other No Pressure N/A lsi Test Temperature N/A -F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and B[owdown Adjustments Made Using N/A rreeeweet at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size Is 8 V, X 11 In. (2) Information In Items 1 through 6 on this resoort Is included on each sheet. and 130 each sheet is numbererd and the number of sheets Is recorded at the too of this form.
16 RFO Inservice Inspection Summary Page 95 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-I/NVR-1 AppW.Ma.W-.d~ 0ý R.-.f~.Mc~
- 9. REMARKS None CERTIFICATE OF COMPLIANCE 1, Jefifey M. Martin , certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules.
National Board Certificate of Authorization No. 20 to use the"NR' stamp expires 07/17/13 Date 07/1 5/2010 FENOC Signed Q 1, Tom Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on 07/15/2010 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section X1 of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. _____&__4_ & --4 IcIc3 . a I-c Date 07/15/2010 Signed " Commissions _____3"_,_ _ ______ r A . CERTIFICATE OF COMPLIANCE' I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section Xl of the ASME Code and to the National Board Inspection Code "R" and "NR' rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/13 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
.. d Wo.5
16 RFO Inservice Inspection Summary Page 96 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-1INWR-4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Date July 7,,2010 76 South Main St.. Akron. OH 44308 ". Sheet 1of I
- 2. Plant Davis-Besse Nuclear Power Station Unit 5501 N. SR. 2. Oak Harbor. OH 43449 200312386 R *pacrOwmtaU,*ao p.O.
Nb.. 4oc Nb..tic 5
- 3. Woek Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp I'm*
cfi1ll NYK I n.1, P-h,- 11 dAdAQ Authorization No. 20
*fegl Expiratton Date 07/17/2013
- 4. Identificatlon of Systems Main Steam Line 2 Code Safety DB-SPI7A1 (Sub083-01)
- 5. (a) Applicable Construction Code ASME u[t-Art. 9 1968 Edition W68 Addenda Code Case No (1b)Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition .99.6 'Addenda Code Case No (c) Design Responsibilities FirstEnergy Corp., NWS Technologies, Nova Machine Products -.
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Component Name of Manufacturer Manufacturer's National Other Identifcationt Year Repairedor ASME Serial No, Board No. Jurisdiclional No, Built Replaced Code Replacement Stamped Main Steam Safety Babcock & Wilcox (Dresser) BM-8638 N/A SP 17A6 1969 Replaced Yes Valve (6"xS")
Main Steam Safety NWS Technologies BM-08640 N/A SP17A6 1972 Replacement Yes Valve (6"x8") (Consolidated/ Dresser) II _IIII 1 318"Cont. Thread Nova Machine Products HT# 13853 N/A N/A 2002 Replacement No
- 7. Description of Work Existing Safety relief valve (s/n:BM-8638) was replaced-with a like for like safety relief valve (s/n:BM-08640) during routine maintenance.
Thcaccraii.rcl l,,-,lnimc,,.arc.;,t (I-lTd I 'lftiVr .cacalc~,i-ccliccA The associated boltin material (HT# 13853N was also re laced A VT-2 initial in-service test was completed satisfactorily. All additional materials installed are identified and recorded in the work order package,
- 8. Tests Conducted: Hydrostatic No Pneumatic NO Nominal Operating Pressure Yes Other No Pressure $862 osq Test Temperature 531t F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdown (if applicable) NIA Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 %X 11 In. (2) Information in items 1 through 6 on this renort is included on each sheet. and (30 each sheet Is numbered and the number of sheets is reoorded at the too of this form.
16 RFO Inservice Inspection Summary Page 97 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-1/NVR:--- ApprcW.
&I-MdMfl Rall LI M -AI0 t~ot
- 9. REMARKS N/A CERTIFICATE OF COMPLIANCE 1, Lynn Ross certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section X1 of the ASME Code and to the National Board Inspection Code "NR" rules.
National Board Certificate of Authorization No. 20 to use the 'NR' stamp expires 07/17/13 Date 7-7-10 FENOC Signed C . "i. Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Thomas G. Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on u* ". .o and state that to the best of my knowledge and belief, this repair, modification or replacement has been compi ted in accordance with Section Xl of the ASME Code and the National Board Inspection Code 'NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 1/'zIO Signed lk_0,.m Commissions t " "t4"TA cOu'.W
- p0,500fl (000 wd CERTIFICATE OF COMPLIANCE 1, Lynn Ross certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of -
the ASME Code and to the National Board Inspection Code "VR' and "NR' rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/13 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION _, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR' and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report; Furthermore, neither the undersigned nor my employer shall be liable in any marner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 98 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
-DB-0070-6 ,-hehA
'i' , " -
FORM NIS-21NR.-1/V,4R OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner TirstEnergy Corp. Date April 02, 2010 76 South Main St.. Akron. OH 44308 Sheet 1 of I
- 2. Plant Davis-Besse Nuclear Power Station Unit 61 5501 N. SR. 2, Oak Harbor, OH 43449 200312394
- 3. Work Perforned by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng 5501 N, SR. 2. Oak Harbor, OH 43449 Authorization NO. 20 Exliration Date 07/17t2013
- 4. Identification of Systems MAIN STEAM, DB3-SUB083-01, DM-MSIO1
- 5. (a) Applicable Construction Code ASME Ill Cl 2 1971 Edition no Addenda Code Case None (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N4-416-3 (c) Design Responsibilities FirstEnorgy Corp
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired ASME Name ot Component Name of Manufacturer - Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 2 Body to Bonnet Studs IJNK UNK UNK MS-101 UNK Replaced No 3 Body to Bonnet Nuts UNK UINK UNK MS-l0t UNK Replaced No 2 Body to Bonnet Studs Nova- HT 69251 N/A MS-101 2009 Replacement No 3 Body to Bonnet Nuts Nava HT8966364Q N/A MS- 01 2005 Replacement No 2 Body to Bonnet Studs and 3 Body to Bonnet nuts were replaced with like for like replacements.
A VT-2 inservice leakage test(per code case 416-3) was performed satisfactor'. B. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes . Other No Pressure 877 psi Test Temperature 528 *F Pressure Relief Valves: Service N/A Size N/A Opening Pressure N/A BSlowdown(if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets In ihe form of lists, sketches, or drawings may be used, provided (1) size is 8 I X I I in. (2) Information in items I through 6 on this report is included on each sheet, and (30 each sheet is numbered and the number of sheets is recorded at the top ofathis form.
16 RFO Inservice Inspection Summary Page 99 c f235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 oe.0oT0-s FORM NIS-2/NR-1/N-'R'T
- 9. REMARKS Nova CERTIFICATE OF COMPLIANCE I, Thomas M Purdue certify that the statements made in this report are correct and the repair,.modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules.
National Boar Certificate of Authorization No. 20 to use the "NR" stamp e e*. 0/7/10 Date 7/1 111 0 FENOC Signed Q CERTIFICATE OF INSERVICE INSPECTION 1, Thomas G. Laps holding a valid commission issued by the National Board of Boller and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of OHIO " and employed by HSB CT of Hartford, CT have inspected the work described in this report on J\, 2
%-s, -ojo and state that to the best of my knowledge and belief, this repair, modification or replacement has been competed in accordance with Section Xl of the ASME Code and the National Board Inspection Code 'NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date I V' .1. Signed '.*o- Commissions :3dP ". C te..,L CERTIFICATE OF COMPLIANCE 1, N/A .. , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'VR" and 'NR" rules. National Board Certificate of Authorization No, 316 to use the 'VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the 'NR" stamp expires 07/17/10 Date FENOC Signed __Q.C. CERTIFICATE OF INSERVICE INSPECTION
- 1. N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASMECode and the National Board Inspection Code "VR" and "NR' rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed __ _ Commissions (a.ma aMaova.,aomemeaO,
.I,~aanv. M4nov)
16 RFO Inservice Inspection Summary Page 100 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 '41 I,s FORM NIS-2/NR-1/NVR=T OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI, I Owner FirstEnergy Corp. Date March 23, 2010 16 South Main St.. Akron, OH 44308 Sheet 1 of I
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR, 2, Oak farbor, OH 43449 200312409 3.' Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2 Oak Iarbor, OH 43449 Authorzatlon NO. 20 Expiration Date 07/17/10
- 4. Identificeallon of Systems Hanger EBB-I-SR4 Snubber SNC-225 Subsystem 083-01
- 5. (a) Applicable Construction Coda ANSI B31.1 1967 Edition Later Addenda Code Case No Jb) Applicable Edition of Section St Utilized for Repairs or Replacements "
tO19 95 Edition 96 Addenda Code Case n/a (c) Design Responsibilities Firstenergy Corp, Lisega
- 6. Identificatiot of Components Repaired or Replaced and Replacement Components Manufacturers National Other Identificatlon/ Year Repaired ASME Name ot Component Name of Manutaclurer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 3052 H*ydraulic snubber Usega 61233138 N/A SNC-225 UNK Replaced No 3052 Hydraulic snubber Lisega 614610/23 NIA SNC-225 2010 i Replacement No II
- 7. Description of Work Existing Lisega Snubber 61233/38 was replaced with a new like for like replacement LiseSa stubber 614610/23.
As left inspectiorn/VT-3 perfortned-SAT 5(a) Cont. ANSIJ33I.1 & MSS-SP58 R Tests Coandrrored: Hvdrostattc No PneumeaticNo Nominal Osetatinao Prescora Nqo Other NO Pressure N/A gal Test Temperature N/IA "F Pressure Relief Valves: Service N/A Size N/A Opening Pressure N/A tdmylorr (if applicable) NIA Set Pressure and Blowdown Adjustments Made UsiEg N/A at NIA NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, prtvided (1) size Is 8 A X t t in. (2) Intormatlon in items t throrugh 6 on this report Is Included an each sheet, and (30 each sheet is numbered and the aumber at shoets Is recorded at thejtp of this form.
16 RFO Inservice Inspection Summary Page 101 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-1/ilLR-+
- 9. REMARKS CERTIFICAtE OF COMPLIANCE" I, Thomas M. Purdue certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'NR' rules.
National Rpard Certificate of Authorization No. 20 to use the 'NR' st*_,x 07/17/10 Date 0 .
"( - (,.........Lbe FENOC - Signed -- o Q.C.
-JACod 5"cNc- CERTIFICATE OF INSERVICE INSPECTION I, Bruce North .. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of. OHio and employed by HISB CT of Hartford, CT have inspected the work described in this report on 3 "3 4P - /0 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xtof the ASME Code and the National Board Inspection Code "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable In any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 3"30'2..)/1 Signed 4,a t. . Commissions ,tj,7"ZJ/,41!,6/Ih'/e32. CERTIFICATE OF COMPLIANCE I, N/A ,certify that-to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section X1of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed .Q.C. CERTIFICATEDOF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHI-O and employed by HISB CT of Hsartford, CT have inspected the repair; modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 102 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 r!( FORM NIS-2/NR-1/N.V 4 -OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xi
- 1. Owner FirstEnergy Corp. nate March 23, 2010 76 South Main St. Akron OH 44308 Sheet I of I
- 2. Plant Dairs-Besse Nuclear Power Station Unit #1
. 5501 N. SR. 2.Oak Harbor. OH 43449 200312464
- 3. Work Performed by FirstEnergy Nuciear. Operating Co. Type CodeoStamp NR 5501 N. SR. 2, Oak Harbor, OHE 43449 Authorization No. 20 Expiration Date 07/17/10
- 4. Identiication of Systems Hanger EBB-I-MR4 Snubber SNC-169 Subsystem 083-01
- 5. (a) Applicable Construction Code ANSI B 31.1 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Section XI Utilized for Repairs or Replacements in 95 idition 96 Addenda Code Case .1/a (c) Design Responsiblftiles Firstenerg', Corp, Lisega
- 6. identification of Components Repaired or Replaced and Replacement Components Manalacturers National Other Identificatton/ Year Repaired ASME Name of Component Name of Manufacturer Serial No.. Board No. Judsdlctional No. Built Replaced or Code Replacement Stamped 3052 Hydraulic snubber Lisega 61233140 NIA INC-169 UNK Repliced No 3052 Hydraulic snubber Lisega 61252J53 N/A SNC-l69 2009 Replacement No
- 7. Description of Work Existing Lisega Snubber 61233140 was replaced with a new like for like replacemeut Lisega snubber 61252153.
As left inspectionA7T-3 performed-SAT 5(a_) Cont. ANSISB31.1 & MSS-SPSS
- a. Tests Conducted: Hydrostatic No Pneumatic No Nomlnal Operating Pressure No Other No Pressure NN/IA lat Test Temperature N/A 'F Pressure Relief Valves:
Service NI/A Size N/A Opening Pressure N/A Bloneown (It appliuable) N/A Set Pressure and Blowdown Adjustments Made Using N/A At N/A NOTE: Supplemental sheets in the form of lists, sketches, or draerings may be used, provided (1) size is 8 Y XI It in. (2) Information In items I through eon this report is included on each shnet, and (30 each sheet is numbered and the number of sheets is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 103 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 De,-007O-.5 FORM NlS-2/NR-I/N~ft'rt
- 9. REMARKS CERTIFICATE OF COMPLIANCE
- 1, Thomas M. Po-due , certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR"nroles.
National BoarP Certificate of Authorization No. 20 to use the "NR" stamp 9e.pi' 07/17110 Date I]! FENOC Signed , - CERTIFICATE OF INSERVICE INSPECTION
.7'31o8 SC#OLL I, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OH-O and employed by HSB CT of Hartford, CT have inspectedthe work described in this report on 3 Z?- /0 and state that to the best of my knowledge and belief, this repair; modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection Code "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report, Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 3- Z9-2-410 Signed e0L*., 4441- Commissions /A8 79ZO44'A l - Of5z. CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, oi replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.c__ CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board Of Boiler and P.ressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT, have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in-accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 104 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0O70-5 I12- ,1 4 FORM NIS-2/NR-1/ 14-WNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Omner FirstEnergy Corp. Date M"ach 23, 2010 76 Sou th Main St., Akron, OHI 44308 Sheyt I of I
- 2. Plant Daeis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak ]lBarbeor, OR 43449 200312465
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR Kt;n1 N QIQ ? OaIrr t-st fiST
)TnT. 1 Authodrzation No. 20 Expiration Date 07,/17/10
- 4. IdentifieationofaSystems Hanger EBB-1-SR4 Snubber SNC-170 Subsystem 083-01 S. (a) Appllcable Coestiuctios Code ANSI 531.1 1967 Edition LaterAddenda Coda Case No (b) Applicable Edition of Section XIUtilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case n/a (c) Design Responsibilities Firstenergy Corp. Lisega
- 6. Identification of Components Repaired or Replaced and Replacement Components f M Manufacturer's National Other Identilication' Year Repaired , ASME Name of Component Name of Manufacturer Sedal No. Board No. Judsdictional No. Built Replaced or Code Replacement Stamped 3052 Hydraulic snubber Lisega 61252/40 NIA SNC-170 UNK Replaced No 3052 Hydraulic snubber Lisega 61252/54 N/A SNC-170 2009 Replacement No
_ _ _ _ __ _ _ _ __ _"r _ _
- 7. Description of Work Existing Lisega Ssubber 61252/40 was replaced %witha new like for like replacement Lisega snubber 61252/54.
KAs lefi inspectiorrfVT-3 prorr-A 5(a-)Contt. ANSI B3 1.1 & MSS-SP58
- 8. Tests Conducted: Hydrostatlo No Pneumatic No Nominal Operating Pressure No Other No Pressure NIA o.si Test Temperature N[A °F Pressure Relief Valves:
Seivice N/A Size N/A Opening Pressure N/A Blowdeown (it applicable) N/A Set Pressure and Bno',doesm Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form oflists, sketches, or drawings may be used, provided (tj-i~els 8 Y, X 11in. (2) Informatiol enitems through 6 on this report is Included on each sheet, and 130each sheet is numbered end the number of sheets is recorded at the toe of this form.
16 RFO Inservice Inspection Summary Page 105 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 0 B-SOlO-S FORM NIS-2/NR-1/N.R-T1
- 9. REMARKS CERTIFICATE OF COMPLIANCE 1, Thomas M. Purdue , certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code arnd to the National Board Inspection Code "NR" rules.
National BoardCertificte of Authorization No, 20 to use the "NR" steam x res 07/17/10 Date 3 0/0 FENOC Signed -Q.C
- r449,9 5C#(/1oC CERTIFICATE OF INSERVICE INSPECTION I, Brace North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdkition of Ol-O and employed by sHB CT of Hartford, CT have inspected the work described in this report on 3 Zf- 10/ and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 3 3 - 2010_ Signed ,,,, p Commissions A18 7'j2,465//{ , -. V* CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. Natiorial Board Certificate of Authorization NO. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 _ _Date SENOC Signed __.C. CERTIFICATE OF INSERVICE INSPECTION I., N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel I Inspectors and certificate of competency issued by the jurisdiction of O01O arnd employed by HSB CT of Htruford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules.
- By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss ot any kind arising from or connected with this inspection.
SDate- Signed - _Commissions
16 RFO Inservice Inspection Summary Page 106 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 p_&O3 2.fl/ e~~- Z OB-0070-5 I~ ,j 14 1 1 FORM NIS-2INR-1/NVR-rOWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xi
- t. Ovner FirstEnergy Corp. Date March 23, 2010 76 S Qth Main S8L.Akron, OH 44308 Sheet 1 of 1
- 2. Plant Davis-Bases Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 2003 22466
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oak H~arbor. OH '43449 Authorization No. 20 5501 N. SR. 2. ORk Harbor, OR 43449 Expiration Date 07/17/10
- 4. Identiication of Systems Ranger EB1B-I-SR4 Snubber SNC-224 Subdystem 083-01
- 5. (a) Applicabie Construction Code ANSI B31.1 W67 Edition Later Addenda Code Case No (b) Applicable Edition of Section XI Utilized for Repaim or Replacements 19 95 Edition 96 Addenda Code Case 01a (c) Design Responsibilities Filsteiiergy Corp, Lisega 5 ttantitinatinn rd tThranaeente Fteoairart rir Rnnimad antI Ronlacomant t'.nmnonenta Manufacturer's National Other Identification/ yeas Repaired ASME Name of Component Name ot Mantsacturr Seal No. Board No. Jurisdictional Na. euitt Reptaced or Code Replacement Stamped 3052 Hydraulic snubber Lisega 614610122 N/A SNC-224 UNK Replaced No 3052 Hydraulic snubber Lisega 04616220/071 N/A SNC-224 2010 Replacement No
- 7. Description of Work Existing Lisega Snubber 614610/22 was replaced wiit a new like for like replacement Lisega snubber 04616220/071.
As ieftrinspection/VT-3 performed-SAT 5(a) Cont. ANSI B31.1 & MSS-SP58
- 8. Tests Conducted: Hydrostatic No Pneumatio No Nominal Operating Pressure No Other No Pressure N/A psi Test Temperature N/A "F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Slowdown (if applicable) N/A SettPressure and BlowdwOa Adjustmsents Mada Using N/A (Te1-4,~ at N/A NOTE: Supplemental sheets in the form oftists, sketches, or draesngs maybe used, provided (it) size IsB X 11 in. (2) Information in items I through Son this report is included on each sheet, and (30 each sheet Is numbered and the number of sheets Is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 107 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 OB-0070-S FORM NIS-2INR-.1/-,R-4--
- g. REMARKS CERTIFICATE OF COMPLIANCE IT Thomas M. FPuade certify that the statements made In this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rulesT National Board Cerilficate of Authorization No. 20 to use the "NR" staminQ4::O* 7117/10 Date J/L) FENOC Signed CERTIFICATE OF INSERVICE INSPECTION I, Jacob Scholl holding a valid commission issued by the Nationat Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of 'OHIO and employed by HSB cT of Hartford, CT have inspected the work described in this report on ./-/-/D and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date q, 1 2 0/0 Signed , Commissions /146 7120A*, / CERTIFICATE OF COMPLIANCE l, NIA , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12.13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date PENOC Signed ' _ _ _.C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of 011O and employed by HSB CT of Hartford. CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neitherthe undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement d6scribed in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed _ Commissions
16 RFO Inservice Inspection Summary Page 108 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 0B.0070-5 FORM NIS-2/NR-t4INVR4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. oDrt July 9, 2010 76 South Main St., Akron, OH 44308 Sheet lotf
- 2. Plant Davis-Besse Nuclear Power Station Unit .. .... f 5501 N. SR. 2, Oak Harbor, 01 43449 200312560 .
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Cede Stamp NR 5501 N, SR. 2. Oak Harbor. OH 43449 Authorization No. 20 Explration Data 07/17/2013
- 4. Identification of Systems Core Flood Tank 2 to Reactor Check I DB- 'F30 (SUB051-01)
- 5. (a) Applicable Construction Code ASME M11 CL.I 19 7lEdition S71 Addenda Code Case No (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 9' Edition 1996 Addenda Code Case NO (c) Design Responsibilities FirstEnergy Corp,, Nova Machine Products A.identitfication of Comoonents Renaired or Reniacod and Reolacement Comnonents Manufacturer's National Other identificationf Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. JurIsdictional No, Built Replaced or Code Replacement Stamped 1 7/8" Heavy Hex Nut Nova Machine Products HT#721044 NIA N/A 2003 Replaccment No I(t tA (D905).
1 7/8" Con't Thread Nova Machine Products HT# 727214 N/A NIA 2003 Replacement No 1(& OD___________-(892) ____
- 7. Description of Work Associated bolting material was replaced (HT# 721044 (D905) and HTT#727214 (D892)) during routine maintenance.
A VT-2 was completed satisfactorily.
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No.
Pressure NOT oslo Test Temperature NOT "F Pressure Relief Valves:
.Service N/A Size N/A Opening Pressure *N/A Blowdown (it applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at NIA NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 %X Iin, (2) Information in items 1 through 6 on this resort Is lancuded on each sheet, end (30 each sheet Is numbered and the number of sheets is recordled at the nonorthis form~
thfsrbnorl IsJncludedon each sheet and 130 each sheet Is numbered and the number of sheets Is recorded at the ton of this form
16 RFO Inservice Inspection Summary Page 109 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070.6 FORM NIS-2/NR-I/NVR-- flAPPa0MA,.ldn OMlRapfl 0sbAjCs
- 9. REMARKS Nova Machine Products CERTIFICATE OF COMPLIANCE I, Lynn Ross certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XAof the ASME Code and to the National Board Inspection Code 'NR" rules.
National Board Certificate of Authorization No. - 20 to use the 'NR" stamp expires 07/17/13 Date 9'-10 FENOC Signed ry..) 'A.'1 Q.C-CERTIFICATE OF INSERVICE INSPECTION I, jcTi, ,i.% &-. L.AS. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on . f,, )'olo and state that to the best of my knowiedge and belief, this repair, modification or replacement has been comp*bted In accordance with Section XI of the ASME Code and the National Board Inspection Code 'NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 1 (o10 Signed Commissions C0n'- CERTIFICATE OF COMPLIANCE I, _ _, certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'VR" and 'NR" rules, National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12113/10 National Board Certificate of Authorization No. 20 to use the 'NR" stamp expires 07/17/13 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION Iholding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions sntoeasaa rode~dcoen,.nU) odtodaaoil~sf510.5
16 RFO Inservice Inspection Summary Page 110 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 at/7.r), itr ,'. FORM NIS-2/NR-1/NVR41-OWN ER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by iho Provisions of the ASME Code Section XA 1, owner F2rs(tEnei'gy Corp. Date -rime26,2010 76 South MaJ St.,.Akron, OH 44308 Sheet 1 of I
- 2. Plant Davis-Besse Nuclear Powee Station Unit _I 5501 N, SR. 2. Oak Harbor, OH 43449 200312863
- 3. Work Performed by Fh'st~nerge Nuclear OperatIn'g Co.
Type Coda Stamp M l5r01 W Qn) *mfIr 2..1IJIJ&l nvKIJ* *An¢ , oT(4- T *AlddQ v*A .... Authorlzatton No. 20
*J*o Expiration Data 07/17/2013
- 4. Identificatton of Systems Decay Heat Cooldown Line Relief D1-4849 (Stb049-02)
- 5. (a) Applicable Construction Coda ASME III CL.2 1871 Edlltoa w72 Addenda Code Case No (a) Applicable Editlon of SeclIonXI Utilized for RepairsorRaplscemats . .19_95Edition 1996 Addenda Code Case No (c) Destgn Responsibilities Flrstlh nergy Corp., Nova Machine Products, J*. Lonerran Co.
- 6. Identification of Components Repaired or Replaced*and Replacement Components Manufacturer's National Oiher idenftficatlan/ Year Repaired ASME Name of Caoponent Name ot Monufauarer Serial No. Board No. Jurlsdilcioaal No. Built Replaced or Code I Replacemenl Stamped 4"x6"Safety Relief J.& Lonergan Co. 7704435-104 NIA DH4849 1982 Replaced Yes Valve 4"x6"Safety Relief J.E. LonergaunCo. 304400-104-1 NIA DH4849 1976 Replacement Yes Valve (6) WW'x6"Stud Cont. Nova Machine Products 11T9721473 N/A N/A 2001 Replacement No Thread (2) /"x6" Stud Cont. Nova Machine Products H']7146153
- NIA N/A 1998 Replacement No Thread
- 7. Description of Worl Existing Safety'Relief Valve (s/n: 7704435-104) was replaced with a like for like valve (s/n: 304400-104-1) during maittenance.
3/4/" x 6" Continuous Thread Studs wveroalso replaced. (HT/R 721473 and HIT# 46153) A VT-2 Initial in-service lest "as also performed satisfactorily. All additional materials installed are Identified and recorded in the work order package.
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Oltar No Pressure 78 os Test Temperature 9 "F
- Pressure Relief Valves:
Service Safety Relief Size 4"x6" Opening Pressure 320osi. Blorodowvn (if applicable) N/A Sat Pressure and Blowdown Adjustments Made Using -Water at " Davis-Besse Nuclear Power Station NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size Is 8 %AX11 In. (2) Informalion in items 1through 6 on this report is Included on each shool, and L30each sheet Is numbered and the number of sheets Is recorded at Ihe top of this fantm.
16 RFO Inservice Inspection Summary Page 111 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-.007O,5 r . lI i 0 FORM N lS .2/NR-1.11i
- 9. REMARKS Nova Machine Products, I.Ei.Lonergan Co.
CERTIFICATE OF COMPLIANCE 1, Lynn Ross , certify that the statements made In this report are correct and the repair, modification, or. replacement of the Items described above conforms to Section Xi of the ASME Code and to the National Board inspection Code "NR"rules. National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/13 Date 6-26-2010 FENOC Signed . - , (ý6 Q.C. CERTIFICATE OF INSERVICE INSPECTION I,' holding a valid commission Issued by the National Board of Boiler and PressureVessel Inspectors and certificate of competency Issued by the jurisdiction of OHIO and employed by HSB C11 of Ilfod CT have Inspected the work described in this report on to I and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed In accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning thie work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal Injury, property damage or loss of any kind arising from of connected with this inspection. Ontoe -f Signed Commissions Tit1~1 4 iinIai 1 fý "716)/t 7110 *CERTIFICATE OF COMPLIANCE I, -+ynRen- / t certify that to the best of my knowledge and belief the statements made In this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'VR" and "NR' rules. National Board Certificate of Authorization No, 316 to use the "VR' stamp expires 12/13/10 National Board Certlflcate of Authorization No. 20 to use the "NR' starmp expires 07/17/13 Date _ r-f,//f" FENOC Signed,__ ,Q.C. J* CERTIFICATE OF INSERVICE INSPEOTION I. " holding a valid commissilon Issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by H813S Cr of Hartford, CT have Inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been-completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR and "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning t(le repair, modification or replacement described In this report. Furthermore, neither the undersigned nor my employer shall be - liable in any manner for any personal Injury, property damage or loss of any kind arising from or connected with this inspection, Date __ Signed _ _ _ _ Commissions
16 RFO Inservice Inspection Summary Page 112 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 Dn-07oTa-
-7 It4,I I HH -
FORM NIS-2/NRt1NV.R--'t5OWNER'S REPORT FOR REPAIRS*OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Data March 21, 2010 76 South Main St., Akron. OH 44308 7 Sheet 1 of I
- 2. Plant Dayis-Besse Nuclear Power Station Unit 5501 N. SR. 2, Oak Harbor, OH 43449 200312907
- 3. Work Performed by FirstEnerg,Nuclear Operating Co, Type Code Stamp NR, 5501 N, SR, 2. Oak Harbor, OH 43449 Authorization No. 20 Expiration Date 07/17/2013
- 4. identification of Systems DB-E24-2, STEAM GENERATOR 1-2
- 5. (a) Applicable Construction Code ASNMIII CI 1 1971 Edition no Addenda Code Case None (b) Applicable Edition of Section XIUtilized for Repairs or Replacements 19 95 Edition 96 Addenda CodeCase (c) Design Responsibililies FirstEnerey Cop. ARRVA
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturers National Other Identification/ Year Repaired ASME Name of Compunent Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped
- 7. Description of Work Steam Generator IA Tube Plugine and Stabilization. All work oerformed by AREVA. Work performed lAW AREVA procedures 03-1275284-016 and 03-1222961-012. See also AREVA OA data oackapes 23-9139697-000 and 23-9139697-001.
- 8. Tests Conducted; Hydrostatic No Pneumatlc No Nominal Operating Pressure NO Other No Pressure N/A psi Test Temperature N/A "F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets In the form of lists, sketches, or drawings may be used, provided (1) size Is 8 Y X 11 in. (2) Information In items 1 through 6 on thio rannrt is innhldP-drml as ar-.h -ohast ond tin0 srth shoal is nueredhoar ann the number"ot sheets is recorded at the tonof thin forn, this reoort is included on each sheet and 130 each sheet is numbered and the number of sheets is recorded at the too of this form
16 RFO Inservice Inspection Summary Page 113 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NS-2.NR,-4/,V-RFT S. REMARKS AREVA CERTIFICATE OF COMPLIANCE I, Thomas M Purdue certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section X1of the ASME Code and to the National Board Inspection Code "NR' rules. National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date -7//-7/ FENOC Signed " 'Q.c. CERTIFICATE OF INSERVICE INSPECTION I, Thomas G. Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on ,Jj. &o,-eo and state that to the best of my knowledge and belief, this repair, modification or replacementhas been compl6ted In accordance with Section Xl of the ASME Code and the National Board Inspection Code "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 7 o 10 Signed -s Commissions 5.tt,*,c ,, ,.A CCLt.* CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'VR' and 'NR' rules. National Board Certificate of Authorization No. 316 to use the 'VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed _ _Q.C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and statetthat to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR' and 'NR' rules. By signing this certificate, neither the undersigned nor,my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions (0.0~~IOoad C.a0.da**). a 0~4)
16 RFO Inservice Inspection Summary Page 114 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
. 7 -70q,-Z-95ý FORMRN*-I REPORTOF REPAIR MODIJECATION E) ORýREPLACEMEXNTE TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS
. -A
- 1. Work performed by ARE VA NPIanc. PO*s 45231709,.a - .
(Dameof NR teartihrate holder) (P.O. no., job no., etc.)
.(add-ss)
- 2. Owiner FP*rtEnrgy Company
* (nme) -,
76 South Main St,, Alaon.Ohio 44308
*(address)
- 3. Namn, addres sd ideutification oftnucleor pover ploet Davih-gesso Nuclear Power Station 51601N .SP IeOkt--rhnr (Ithn 414*9
- 4. System Steam Generator # 2 5.: Iteas WhichRekaed Repair Modification, or Replacemenat Acfivities Identification Consutrtion Code Activity Type of Mfg. Mfg, Serial Net Jusd. Na Editlion/ Code Code Rpd Item Name No. Bd. No.
No.l Bei S vsai Division Addenda Case(s)O Class Replace* Replace No. 1 (2) (1) (2) 158 N/A N/A 1972 (3) (4) (5) A Repair 2 3
*4 63
?
8 9 12
- 5. b:Items installed During Replacement Activities Identification Construection Code Typo of Isstalled or. Mfg. Mfg. Serial Nat'l Ed. Jurisd Other Year Narnc/ Edition] Code Code Item Replaced 5a Nacm No. No. No Built Section/ Addenda Case(s) Class Item No. Division (6), (8) (7) N/A WNA N/A (1t) (3) (4) NooN I
- 6. ASME Code Section X? anplicabtdfor iservice inspection: 1995 1996 None (edition) (addenda) (Code Cascs(s))
- 7. ASME Code Section XI used for repairs, modifications,or replacements:: 1995 1996 None (ediltion) (addenda) (Code Cases(s))
- 8. Coaslrofioa.Cddhusedfrrepais.,modacaions, orM eplaemente: ,1968' :." ', 2. Srner '68 1332Z4,-410-1, (edition) (addenda> (Code Cases(s))
- 9. Design responsibilifies: (8)
- 10. Ties conducted, hydrostatic Pneumatiic Q Design pressure,(9). pesure .
- pat Code Case(s) __
"htsform may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Ave., Columbus, OH 43229 N"8i R5ev.8
16 RFO Inservice Inspection Summary Page 115 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 Repaired "A" Steam Generator tubes by rolled plugging with procedures 03-1275284-016 and
- 11. Description of workt 03-1222961-012 (use o1propedy Identittedadditionalsheet(s) orsketches Is aceptable)
See QCIR 9135204 for acceptance of Installed code hardware. Stabilizerlrolled plug assemblies Installed in "A"Inlt- 67 (Stabilizer Plug P/N 1196122-002) OTSG rolled plugs Installed In 'A" Inlet - 14 (P/N 5023545-001) Rolled Plugs Installed In 'A' outet- 81 (Threaded Rolled Plug PIN 1222118-005)
- 12. Remarks; Listed below are the number codes that epply to the repair activity Items shown on the front page (1) Babcock and-Wilcox Company (2) Steam Generator #E24-2, S/N 620-0J4-55-11i (3) ASME Section III,Class I, Division I (4) Construction CodaeASME Ill. 1968 Edition, 1968 SummerAddanda (5) Code Cases 1332-4 and 1407-1 (6) AREVA NP PINs for rolled plugs- 1196122-002 (stabilizer plug), 5023545-001 (OTSG rolled plug), and 1222118-005.
(threaded rolled plug) (7) Rolled plug serial numbers and tube locations: See QCOR9135204 (J) AREVA NP Inc. (9). By others- Flrt~nerpy (00) See AREVA NP iA data oackaaes 23-9139897-000 and 23-9139697-001 CERTIFICATE OF COMPLIANCE tMark Pirc crifiy thatto the best ouomyknowledge and belief the statements made in this report are correct and the repair, modification or replaceant activities dasr-iabedabove conforms to Section XMof'the ASMffE Code sod the National board Inspection Code '"NR oues. National Board Certifirate of Authorization No. NR-6 to use e"NIR."stamp enpirasMay 17,2012
*R Certit*aHotder AEVANPIn (name)/Va Datn 60811 Signed-7YZ1ý)_ -= -. ASpec(iaist Ofi
/ (authonized represnative) .I (title)
CERTIFICATE OF INSPECTION L,-74 "*Joldng a valid commission issuedby The National Board of Biler rnd Prassura Vessel InspOtors sd cergtficat of competency issued by hajurisdiction 'of 4tL _ and employed by h'S , C 7 'f /I* ,or have impeaed the repair, modification orreplacement described in this report aon_6- - and state that to the best of my knowtedge and btline this repair, moditiration or replaemeot activity has beencompleted in acordaen with Suction XIaoftho ASME Coda rnd the National Board Inspectios Code 'NR' ruls. Bý signing this certificate, neither thetafoceralgned nor my emptlyer makes eaywarranty, expressed or implied, conerming the work described in this report Furthemore, neither the undeersigned nor my employer shall be liabtlein ay marnnerfor. any personal injury, property damage or loss ofrany kind arising from or connected with this inspection. (nup (/ (tNoational Bao d(tml. ensdoaeemeats),judsditioa, andno) V.
16 RFO Inservice Inspection Summary Page 116 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
-.ý - I..
FORM NIS-2/NR-iIN-VR4-T OWNER'S REPORT FORREPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xf
- 1. owner FirstEnergy Corp. Date March 21,2010
'76 RmurfhMain Rf. Akrnn OTT 443CIR Sheet I of I
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2. Oak Harbor. OH 43449 200312908ttemlteOafltJOP.o. NO..J05 .. itt
- 3. Work Performed by FirstEnergy Nuclear Operating Co. TypeCode Stamp 'Np 9qfICtI QP 1 irla1,ig. rhb.,' nT 43440 Authorization No, 20 Expiration Date 07/17/2013
- 4. Identification of Systems DB-E24-1, STEAM GENERATOR 1-1
- 5. (a) Applicable Construction Code ASME ItI Ct 1 1971 Edition no Addenda Code Case None (b) Applicable Edition of Section Xi Utilized for Repaim or Replacements 19 95 Edition .9 Addenda CodeCase (c) Design Responsibilities FirstEnergy Corp, Al, EVA C. Identification of Components Reoaired or Reolac~ed and Reolacement Comoonents Manufacturer's National Other Identificationt Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped
- 7. Description of Work Steam Generator IB Tube PlugdinR and Stabilization, All work performed by AREVA. Work performed IAW AREVA procedures 03-1275284-016 and 03-1222961-012. See also AREVA OA data Dackages 23-9129697-000 and 23-9129697-001.
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure NO Other No Pressure N/A tsi Test Temperature N "F Pressure Relief Valves:
Service -N/A Size NIA Opening Pressure N/A Slowdown (if applicable) N/A Set Pressure and Slowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of [isis, sketches, or drawings may be used, provided (1) size is B % X 11 in, (2) Information in items I through 6 on this report is Included on each sheet. and 130 each sheet is numbered and the number of sheets is recorded at the too of this form.
16 RFO Inservice Inspection Summary Page 117 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 OB-0070-5 FORM NIS-2/NR-IJN -1
- 9. REMARKS AR9VA CERTIFICATE OF COMPLIANCE I, Thomas M Purdue - certify that the statements made in this report are correct and the repair, modification, or.
replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board e ificate of Authorization No. 20 to use the "NR" stamp expire 07/17/10 Date L.71 to FENOC Signed ",, 4't-- _ Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Thomas G. Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of trartford, CT have inspected the work described in this report on . o,),olO and state that to the best of my knowledge and belief, this repair, modification or replacement has been compi ted In accordance with Section Xl of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date laoo 0 Signed ,TV";-kO __Commissions 14EYT3313".'TA-CERTIFICATE OF COMPLIANCE I, N/A certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date (name FENOC ctrr*p rodanza.for.) Signed (aut*thas, rehtoteatc~,(v Q.C. CERTIFICATE OF INSERVICE INSPECTION i, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of .01110 and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermoreneither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 118 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 FORMNR-. REPORTOPREPAIR MODIFICATIOND ORREPLACEMENT 45 3176-TONUCLEAR COMPONENTS ANDSYSTEMSIN NUCLEAR POWER PLANTS
- 1. Work performed by AREA NP Inc PO#s 4521708 (nama ofNR certificateholdor) .(P.O. no.,job no., etc.)
3315 Old Forest Rd, Lynchburg Va. 24501 (addTes)
- 2. Owner FirstEnergy Company 76 South Main St., Akron Ohio 44308 (addres)
- 3. Name, address and ideoantiltion of nuclear power plant Davis-Basse Nuecar PowerStation 5501NN.SR 2 OakHArb , Chi, 41449
- 4. System Steam Generator# E'24-1 5.8.ItonvoWhich Required Repair, Modification, or Replacement Activites Identification Construction Coda Activity Mfg. Serial Natl Ja d.No, O tor B tYear Nmsne/ Add n a s Repairs No Type of Mfg, Item Name No. Nuit Addeda Cane) Class Mod
'No. N' - Division IReplace 1 (2). (1) (2) 159 N/A N/A 1972 (3) (4) (5) A Repair 12 3
4 5 6 7 9 10 12
- 6. ASMIE Code Suction XI applicable for inservice inspection: 1995 1996 None (edition) (addendo) - (Code Cares(s))
- 7. ASME.Cody Secan MItrsedfor,rre'ars, modificationsor replac*rhnts:,:.' 1995 4996 None (edition) (addenda) . (Code Cases(.))
&. Construction Code used for repairs, modifications, or replacemcnts: 1968 Summer '68 1332-4,1407-1 (edition) (addenda) (Code Cases(s))
- 9. Design responsibilities: (8)
- 10. Tets conducted: hydrostatic U Pneumatic EU Design pressure (9) pressaur __ psi Code Case(s) tiis form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1056 Crupper Ave., Columbus, OH 43229 NB-81 Rev. 8
16 RFO Inservice Inspection Summary Page 119 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 Repaired "B3Steam Generator tubes by rolledpiugglng with procedures 03-1275284.016 and
- 11. Descriptlro. of wodc 03-1222961-012 (use of prop"rlyIdentifiedadditionalsheet(s) or skethels Is acceptable)
See QCIR 9135205 for acceptance of Installed coda hardware.. Rolled Plugs installed.In 'Ba Inlet- 51 (OTSG Rolled Plug P/N 5023545-001) Slabllizerlrelled plug assemblIes Installed in "Sla'det- 47 (Stabilizer Plug PIN 1198122-002) Rolled Plugs Installed In"B"outlet- 99 (Threaded Rolled Plug PIN 1222118-005)
- 12. Remarks: Listed below are the number codes that aoIV ts the reoalr activIt Items shown on the front oare (1) Babcock and Wilcox Company' (2) Steam Generator 9E24-1. S/N 620-0014-55-12 (3' ASME Section Ill. Class I. Division I
_(4) Construction Code ASME III,1968 Edition, 1968 SummerAddenda (5) Code Casee.1332-4 and 1407-1 (6) AREVA NP Inc PINs for rolled plugs- 5023545-001(OTSG rolled plug), 1196122-002 (stabilizer plug) and 1222118-005 (threaded rolled plug) (7) Rolled plug sedal numbers and tube looattons Installed: See QCIR 9135205 (8) AREVA NP Inc.. (9) By others- FirstEnergy (10) See AREVA NP INC CA data packages 23-9129597-000 and 23-9129697-001 CERTIFICATE OF COMPLIANCE
, Murk Plt=. certify that to the best of my knowledge and belief the statements made in this report are eorrectand the repair, modification or replacomeat actiyities described above conforms to Section Xt ofthe ASME Code and the National board Itspecdon Code "NI" rules.
National Board Certificate of Authorization No. NR-6to use the 'NIL"stamp expires-May-I _2012 NR Certificate Holder A"VA NP toe (namoe)- DateatreLanre2010Signed OA ieeaist I(authorized representative) (tide) CERTIFICATE OF INSPECTION L- __"_ AO..L holding a valid commission issued byThe National Board of Boiler andPressure Vessel Inspectors and onrtifiate ofcompetency issued by thejurisdiction of 09(i andemployed by, "ed7 " L"3 that to tae best of my coledgcand t the repair, modificaiea or replacement described instbs reporton
-of[ slate belief, this repair, modifieation or replacement activity has been completed in accordance with Section X1of the AShM Coda and the tNationalBoard lsIpecris Code 'NR.' rules.
By signing this eertifleate, aeithertheunderlgned neomy employer makes maywmreauty, e"pressed or implied, concerning the work described in this report. Furthermorc, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of coy kind arising from or connected with this inspection. Data I*sigued - (- Commissons Na 71 M. t)91to .)
,n7ete Qneaeti.Beaed(eeL e.)
asemet).eidcin.d
16 RFO Inservice Inspection Summary Page 120 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 flR-Sfl70-5 FORM NIS-2/NR-1/NVR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Date April 30, 2009 76 South Main St., Akron, OH 44308 Sheet 1 of 1
- 2. Plant Davis-Basee Nuclear PowerN-Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 200320362
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng/VR 5501 N. SR. 2. Oak Harbor, 011 43449 Authorization No. 20 Expiration Date 07/17/10
- 4. Identification of Systems Code Safety Relief Valve (RC13A)
- 5. (a) Applicable Construction Code ASME MICL.] 1968 Edition 1970 Addenda Code Case N/A ib) Applicable Edition of Section XIUtilized for Repairs or Replacements 19 95 Edition 1996 Addenda Code Case N/A (c) Design Responsibilities FirstEnergy Corp., Crosby Valve & Gauge Co.
- 6. Idontification of Components Repaired or Replaced and Replacement Components N Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdicltonal No. Built Replaced or Code Replacement Stamped Saftey Valve Crosby N54891 N/A DB-RC13A 1976 Replaced Yes 0001 Saftey Valve Crosby N54891 N/A DB-RC13A 1976 Replacement Yes 0002
- 7. Description of Work Existing safetv valve (serial # N-54991-00-0001) was reolaced with a refurbished safety valve (serial # N-54891-00-0002) during routine maintenance.
A VT-Sriiniliat ineervire l~slraru~ teat~van nr.rfnrmnrf anriafacinry. A VT-2 initial inservice leakage test was performed satisfactorv.
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure 2146 psi Test Temperature 652 'F Pressure Relief Valves:
Service Steam - Size 4"x 6" Opening Pressure 2500 Blowdown (If applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at NWS NOTE: Supplemental sheets Inthe form of lists, sketches, or drawings may be used, provided (1) sizeis a lb X 11 in. (2) Information In Items I through 6 on this report Is Included on each sheet, and (30 each sheet Is numbered and the number of sheets Is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 121 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 OB-0070-5 FORM NIS-2/NR-1/NVR-1
- 9. REMARKS Crosby Valve & Gauge Co.
CERTIFICATE OF COMPLIANCE 1, NIA certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on _ and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning the work described In this report. Furthermore, neither the undersigned nor my employer shall be liable In any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date Signed Commissions CERTIFICATE OF COMPLIANCE 1, Jeffrey M. Martin certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NA" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12113/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date - ,.'t"Y 6- FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OH1IO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on
-and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date S- I -o Signed Hi. iJ ,ol, Commissions P 1 T . .CIO
16 RFO Inservice Inspection Summary Page 122 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 ne.-00rI-C Di:[-nn7n-9 FORM NIS-2INR-1/NVR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Coda Section Xi
- 1. Owner Firstt~nergy Corp. Data May 1, 2009 I
'76 South X4l,I f A t,.n. U44 Sheet 1 of I
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 2010320363 sawONMNogP.O.Nt, J .
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NVR 5501 N. SR. 2. Oak Harbor, OH 43449 Authorization No. 20 Expiration Dats 07/17/10
- 4. Identification of Systems Code Safety Relief Valve (RC I3B)
S. (a) Applicable Construction Code ASME Irl CL 1 1974 Edition 1974 Addenda Code Case N/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacementa 19 95 Edition 1996 Addenda Code Case N/A (c) Design Responsibilities FirstEnergy Coip., Crosby Valve & Gauge Co. G. Identification of Components Repaired or Replaced and Replacement Components Manufacturer' National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer a Serial No. Board No. Jurisdictional No. Built Replaced or Coda Replacement Stamped Saftey Valve Crosby N59303 N/A DB-RC13B 1979 Replaced Yes 0001 Saftey Valve Crosby N56264 N/A DB-RCI3B 1976 Replacement Yes 0005
- 7. Description of Work Exisfine safety valve (serial # N-59303-00-0001) was renlaced with a refurbished safety valve (serial # N-56264.00-0005) durine routine maintenance.
A VT-2 initial inservice leakage test was performed satisfactory.
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure 2146 psi Test Temperature 652 'F Pressure Relief Valves:
Service Steam Size 4"x 6" Opening Pressure 2500 Blowdown (If applicable) NIA Set Pressure and Blowdown Adjustments Made Using N/A at NWS NOTE: Supplemental sheets In the form of lists, sketches, or drawings may be used, provided (1) size Is 8 %X I Iln. (2) Information in Items I through 6 on this report is included on each sheet, and (30 each sheet Is numbered and the number of sheets Is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 123 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB.O070-5 FORM NIS-2/NR-1/NVR-1 AppbublMan WWe *O b b, A-ýc~d l kpa*e
- 9. REMARKS Crosby Valve & Gauge Co.
CERTIFICATE OF COMPLIANCE I, N/A , certify that the statements made In this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. '20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION 1, NIA holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on _ and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed In accordance with Section Xl of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable In any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date Signed Commissions CERTIFICATE OF COMPLIANCE I, Jeffrey M. Martin , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07(17/10 Date c--/- 9 FENOC Signed CERTIFICATE OF INSERVICE INSPECTION 1, Bruce North holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on
-- and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied,. concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date o 09Signed !2 4 j64 / Commissions S(
16 RFO Inservice Inspection Summary Page 124 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 FORM NIS-2/NR-1/NVR--I'WNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1, Owner FirstEnergy Corp. nDta 04/01/2010 76 South Main St,. Akron. Off 44308 Sheet I of 1
- 2. Plant Davis-Besse Nuclear Power Station #1 unit 5501 N. SIL 2, Oak Harbor, OH 43449 200327370
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR Sg01 N. *R. 2. Ask 11rha,. flH 43449Q Authorization No, 20 5501 N SR 2 Oak Ifarbor OH 43449 Expiration Date 07/17110
- 4. Identification of Systems Hanger EBD-1-SR15, MAIN STEAM, Subsys DB-StrB083-01
- 5. (a) Applicable Construction Code ANSI B31.1 1967 Edition Later Addenda Code Oase N/A (b) Applicable Edition of Secton Xl Utilized for Repairs or Replacements . 19 95 Edition 96 Addenda Coda Case N/A (c) Design Responstbiittes Firstenergy Cori), Grimriel A trtantiticstinn ft flnrnrnnnentn Reneireri or Rorstaced and Ranlacemanl Comnonenie Manufacturers National Other Identiifcation/ Year Repaired ASME Name of Component 6 Identiicationof Name of Manufacturer compoents Reaired Serial Na. o Re PloordcN duanRelcent ds onompneta. ult Reptared or Coda Replacement Stamped 8" Hydraulic Snubber Grinnell 16846 N/A SNA907 UNK Replaced No 8" Hydraulic Snubber Grinnell 37804 N/A SNA907 2010 Replacement No
- 7. Description of Work Existing Grinnell snubber 24083 was rebuilt as a Configuration B Grinnel snubbwr and relabeled as 37804 As left inspectionfVT-3 performed SAT.
5(a) Cont. MSS-SP-58
- a. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A pst Test Temperature N/A -F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A tlowdown(if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets Inthe form of lists, sketches, or drawings may be used, provided (1) size Is 5 IliX I ltt (2) Information in Items I through 6 on this repod is included on each sheet, and (30 each sheet Is numbered and the number of sheets Is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 125 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS.2INR-1/NVn---
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M.Purdue , certify that the statements made In this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules.
National Boar Cetificate of Authorization No. 20 to use the 'NR" stamp exp.wr.. 407/17/10 Date . [41tic) .ENOC Signed Q.c. CERTIFICATE OF INSERVICE INSPECTION I, Jacob Scholl holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OFIO and employed by HSB CT of Hat tford, CT have inspected the work described in this report on 4'- 1-- / 0 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed inaccordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date L-1.2010 Signed Commissions X6~ 7f 20,446/-0/1V32-. CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'V/R" and "NR" rules. National Board Certificate of Authorization No. 316 to use the 'VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford. CT have inspected the repair, modification or replacement described inthis report on and state that to the best ofmy knowledge and belief, this repair, modification or replacement has been, completed in accordance with SectiorrX1 of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modilication or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 126 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 6 FORM NIS-2/NR-1IWRO"WNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Date 04/02/2010 76 South Main St., Akron. OR"44308 Sheet 1 of 1 fil
- 2. Plant Davis-Besse Nuclear Power Station Unit 5501 N. SR. 2. Oak Harbor, OH 43449 200327371
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng 5501 N. SR. 2. Oak -ahbor.OFT 43449 Authorization No. 20 Exiratioen Date. 07/17/10
- 4. Identificetlon af Systems Hanger EBD-I-SRI 6, MArN STEAM SYSTEM, Subsys DB-SUB083-01
- 5. (a) Applicable Construction Code ANSI B31.1 1067 Edition Later Addenda Code Case N/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Cede Case NIA (c) Design Responsibilities Firstenergy Corp, Grinnell
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identificalion/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or. Code Replacement Slamped 8" Hydraulic Snubber Grinnell 16848 N/A SNA90a UNK Replaced No 8".Hydraulic Snubber Grinnell 16830 N/A SNA908 2010 Replacement No 7, Description of Work Existing Grinnell snubber 12487 was replaced with a rebuilt like for like snubber 16830.
As left, VT-3 inspection performed SAT. 5(a) Cont. MSS-SP-58
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A psi Test Temperature N/A 'F Pressure Relief Valves:
Service , N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A (WeaMe-3, at N/A NOTE: Supplemental sheets in the fotrmof lists, sketches, or drawings may be used, provided (1) size is 8 Y X 11 in. (2) Information in items 1 through 6 en this report Is Included on each sheet, and (30 each sheet is numbered and the number of sheets is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 127 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
- 0-0070.5 FORM I4IS-2JNR-11W.W-R4-t A$aW- MSDr.11 OMRplSIA.
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Pardue ., certify that the statements made in this report are correctand the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'NR" rules.
National BoardCertifi fe of Authorization No. 20 to use the 'NR' stamp.ex l ,,07/17/10 Date " G0 " NOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION 1, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on
- and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection Code "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or lmplied,.concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or Ioss of any kind arising from of connected with this inspection. Date -s _-(t0 Signed L.IX1A 14e"L CommissionsqI('. a 1*4
' O 4 P'm Pa 1 'L' 1 [v CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section Xl of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules.
National Board Certificate of Authorization No. 316 to use the"VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FERNOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 128 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 /. I, "-Ji" FORM NIS-2/NR-1/NVR-4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergv Corn. Date 04/02/2010 76 South Main St., Akron. OH 44308 - Sheet i of I
- 2. Plant Dais-Besse Nuclear Power Station Unit 5501 N. SRI 2. Oak Harbor, OH 43449 200327376.
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng 5501 N. SR. 2. Oak Harbor. OH 43449 Authorizatton No. 20 Expiration Date 07/17/10
- 4. Ideatificationof Syslems Hanger EBD-I-SRI6, MAIN STEAM SYSTEM, SubsysDB-SUB083-01 S. (a) Applicable Construction Code ANSI B3 1.1 1967 Edition Later Addenda Code Case N/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Cede Case N/A (c) Design Responsibilitles Firstenergy Corp, Grinnell
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturers National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 8" Hydraulic Snubber Grinnell 18865 N/A SNA909 UNK Replaced No 8" Hydraulic Snubber Orinnell 16848 N/A SNA909 2010 Replacement No
- 7. Description of Work Existing Grinnell snubber 18865 was replaced with a rebuilt like for like snubber 16848.
As left, VT-3 inspection perforned SAT. 5(a) Coat, MSS-SP-58
- a. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A psi Test Temperature N/A jr Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Slowdown (Ifapplicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (i) size Is 9 %AXt In. (2) Information in Hems 1 through 6 on this report is included on each sheet, and (30 each sheet is numbered and the number of sheets Is recorded at the lop of this form.
16 RFO Inservice Inspection Summary Page 129 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/N R-I1V-R-4
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules.
National Boarý Certificate of Authorization No. 20 to use the "NR' stamp expires 07/17/10 Date _ , FENOC Signed CERTIFICATE OF INSERVICE INSPECTION I, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on /t,-,o-I0 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date I-, Signed _ ,.i, "*4 Commissions 991q 4L , k P*" I W0V CERTIFICATE OF COMPLIANCE I, N/A certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR' and 'NR' rules. National Board Certificate of Authorization No. 316 to use the"VR" stampRexpires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION 1, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section X1of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection.. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 130 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 OB-0070-5 "-7-:)&-In FORM NIS-2/NR-I/N'R-4OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Coda Section XA
- r. Osnner FirstEnergy Cerp.
- 1. Owner FirstEnergy Corp. Data 03/05/2010
.76 South Mlain cSt._A!., 011 44308 Sheet I of I
- 2. Plant Davis-Besse Nuclear Powcr Station Unit 91 5501 N. SR. 2. Oak Harbor. Off 43449 200327377
- 3. Work Performed by " FirstEnergy Nuclear Operating Co. Type Code Stamp NE 5501 N. SR. 2. Oak Harbor, OH 43449 Authorization No. 20 Expiration date 07/17/10
- 4. Identlfication aotSystems Hanger CCA-8-H4, PRESSURiZER, Subsys DB-SUB064-04 S. (a) Applicable Construction Code ANSI B3I.I "167 Edition Later Addenda Code Case NI/A (b) Appllcable Edition of Sectiun XIUtilized for Reoalrs or Replacements 19 95 Edition _96 Addenda Code Case N/A (c) Design Responsibilities Firstenergy Corp, Grinnell
- 6. Identification of Components Repaired or Replaced and Replacement Components Manuarcturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Judsdicltonal No. Built Replaced or Code
-. Replacement Stamped 1.5" Hydraulic Snubber Grinnell 30224 N/A SNC 125 UNK Replaced No 1.5" H-ydraulicSnubber Grinnell 37155 N/A SNCI25 2010 Replacement No
- 7. Description of Work Existing Grinnell snubber 30224 was replaced with a Configuration A replacement Grinnell snubber 37155.
As left inspectionsVT-3 performed SAT. 5(a) Cost. MSS-SP-58
- 8. Tests Conducted: Hydostafic No Pnaumatie No Nominal Operating Pressure No Other No
- Pressure N/A psi Test Temperature N/A *F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A .lowdown (if applicable) N/A 1 el Pressure and Glowdown Adjustrmants Made Using N/A al N/A NOTE: Supplemeetal shaeels in the form of fists, sketches, or drawings may be used, provided (1) size is 5 Y1X 11 In. (2) Information In Items I through 6 on this caon is. Included on each sheet, and (30 each sheel is numbered and the number of sheets is recorded at the too of this farm.
16 RFO Inservice Inspection Summary Page 131 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR°i/1t
- 9. REMARKS CERTIFICATE OF COMPLIANCE .
I, Thomas M. Purdue certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Boar Ce ificate of Authorization No. 20 to use the "NR" stam*8p 07/17/10 Date "3 If,!I0 LFENOC - Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Buce rtorth holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on 3j S'-/O jand state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date ._-________Signed ýJW/ PZ" Commissions N1371WO4M,. Ot/J3a-- CERTIFICATE OF COMPLIANCE 1, NA_ certify that to the best of my knowledge and belief the statements made In this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section Xl of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17110 Date FENOC Signed _.C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certiticate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
- 16 RFO Inservice Inspection Summary Page 132 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 __ '2'&1j(0 FORM NIS-2/NR-1INVR: OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Sectitn XI
- 1. Owner FirstEnergy Corp. DOat March 09, 2010 Sheet I of I 2, Plant Davis-Besse Nuclear Powiei Station Unit #1 SS01 N. SR. 2, Oak Harbor, OH 43449 200327385
- 3. Work Performed by 0FirstEnergy Nuclear Operating Co. Typo Code Stamp NR 5501 N. SR. 2. Oak Harbor, OC 43449 Authorizatlon No. 20 Expiration Date 07/17/10
- 4. tdentittcation of Systems Hanger PSP-L-H25 Snubber SNC-137 Subsystem 064-04
- 5. (a) Applicable Construction Code ANSI B31]. 1967 Edition Later Addenda Code Case No (b) Applicable EdUionof Section XIUtilized for Repairs or Replacements tg 95 Edition 96 Addenda Code Case It/a (c) Dasign Responsibilities Firsttrergy CoJrp, Lisega
- 8. Iden-tificatiorn of Commoonente Renoirod errR~eolareed and Roltacement Comnonents Manulaclurers National Othtr Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 3038 Hydraulic snubber Lisega 61219145 N/A SNC-137 UNK Replaced No 3038 Hydraulic snubber Lisega 309003791076 N/A SNC-137 2009 Replacement No
- 7. Description at Work Existinrg Lisega-Snubber 61219145 was replaced wvith a new like for like replacemerit Lisega snubber 30900379/076.
As left inspectiontVT-3 performed-SAT 5(a) Cont. Al"NSr B31.1 &MSS-SP58
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A osi Test Temperature N/A "F
. PressureRelief Valves:
SeONv N/A Size N/A Opening Pressure N/A Btovdowrn (it applicable) N/A Set Pressure and BEoi'down Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the ftrm of lists, sketches, or drawringsmay be used. provided (1) size Is 8 tb X 11 in. (2) information in Items I through 6 on this report is Included on each sheet, and (30 each sheet is numbered and the number of sheets Is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 133 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 oe-0070-5 FORM NIS-2/NR-1IN',I
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules.
National Board Certifi ate of Authorization No. 20 to use the "NR" stam / 07/17/10 Date " 10 !ENOC Signed
- Q.C.
CERTIFICATE OF INSERVICE INSPECTION 1, Bruce Norlth holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of oHno and employed by I-SB CT of Hartford, CT have inspected the work described in this report on . - " and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the*ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date /0 Signed tA ?Commissions N&872OP8 -~'S CERTIFICATE OF COMPLIANCE 1, NIA , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 3216 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07117/10 Date FENOC Signed Q.c. CERTIFICATE OF-INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of COH0 and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" mies. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification dr replacement described in this report. Furthermore, neither the undersigned nor my employer shalt be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 134 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
,l*R.ttf7nl.S 'Of eikt)
FORM NIS-2INR-11/N*Fi-OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl
- 1. Owner FirstEnergy Corp. .Data March 08, 20 10 76 South Main St., Akrop. OH 44308 Sheet 1 of I Davis-Besse Nuclear Power Station #1
- 2. Plant Unit 5501 N. SRt.2, Oak Harbor, OH 43449 200327392
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No. 20 Expiration Date 07/17/10
- 4. Identification ot Systems Hanger PSP-1-1-126 Snubber SNC-138 Subsystem 064-04
- 5. (a) Applicable Construction Code ANSI B3t.t 1967 Edition Later Addenda Code Case No (b) Applicable Edition ofSection X1Ulillzed for Repairs or Replacements 19 95 Edition 9._ Addenda Code Case tta (c) Design Responslbllities itstenrcry Corp, Lisega Manufacturer's National Other ldentfiicatlonl Year Repaired ASME Name of Component Name of Manufacturer Seflal No. Board No. Judsdicrlonar No. Built Replaced or Code Replacament Stamped 3038 Hydraulic snubber Lisnga 61219/46 N/A SNC-138 UNK Replaced No 3038 Hydraulic snubber Lisega 30900032/052 NIA SNC-138 2009 Replacement No
- 7. Description of Work Existing Lisega Snubber 61219/46 was replaced widt a new like for like reptacement Lisega snubber 30900032/052.
As Ilfr inspectiotc/VT-3 performed-SAT 5(a-) Cont. ANSI 131.1 & MSS-SP58
- a. Tests Condacted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A . si Test Temperature N/A "F Pressure Relief Valves:
Service _N/A Size N/A Opening Pressure N/A Blovdown (if applicable) NIA SetPressure aedBEtamontfAdjustments MadeUstng N/A atN/A NOTE: Supplemental sheets In the form al lists, sketches. or drawings may be used, provided (1) size is 8 t' X 11 In. (2) Informaion in items 1 through 6 on this report Is included on each sheet, and (30 each sheet Is numbered and the number of sheets Is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 135 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio.43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-FNR-FINCM-Eý CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue , certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms-to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Boar Certifcate of Authorization No. 20 to use the "NR" stamp ex 0,7/10 Date 2,/'S 10) FENOC Signed QC. CERTIFICATE OF INSERVICE INSPECTION 44wAb SC'oLLI I, Bruce North, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of 6dmpetency issued by the jurisdiction of OHIO and employed by NSB CT of tfartford, CT have inspected the work described in thisreport on .' *.5"-/ and stale that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Bate 52;/0 Signed A fz O commissions A,V6 7? P04A.Y31"/'614 -/A-, (1,"..df r a4*)
-r~
CERTIFICATE OF COMPLIANCE I, N/A. , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section Xl of. the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.c. CERTIFICATE OF tNSERVICE INSPECTrON I, NIA holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OI-O and employed by
-SB CT of -Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'VR" and "NH" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage.or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 136 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-S ."h l! 1.- " " FORM NIS-2/NR-1/N'h1OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Date March 0, 2010 76 South Main St.. Akron, O1 44308 Sheet 1 of I
- 2. Plant Davis-Besse Nuclear Power Station Unit 5501 N. SR. 2, Oak Ha.!rbor, OR 43449 9flfl327103 200327393 3: Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp 1R, 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No. 20 Expiration Date 07/17/10
- 4. Identification of Systems Hanger PSP-1-H27 Snubber SNC-139 Subsystem 064-04
- 5. (a) Applil6ablo Construction Code ANSI B31.1 1967 Edition Later Addenda Code Case No (b) Applicable Edition o6Section XIUtilized for Repairs or Replacements 19 95 Edition .96 Addenda Coda Case n/a (c) Design Responsibilities Firstenergy Corp, Lisega C hlaelltteetinn of flr-rsn-rnnnets Ranairart or Rerniacod and Rantacemant Comoonouts Manufactureers National Other Identltcation/ Year Repaired ASME Name of Component Name of Manufaeturrer Sedal No. Board No. Jurisdictional No. Suiat Replaced or Coda Replacement Stamped 303t HNydraulic snubber Lisega 61219/53 N/A SNC-139 UNK Replaced No 3038 Hydraulic snubber Lisega 30900032/053 N/A SlNC-139 2009 Replacement No
- 7. Description of Work Existing Liseoa Sn~ubber 61.219/53 was replaced with a new like for like replacement Lisega snubber 30900032/053.
As left inspection[VT-3 paliformned-SAT 5 (a_) Cont. ANSI B31.1 &MSS-SP58 B. Tests Conducted: Hydrostatic No Pneumatic No Nomtnal Operating.Pressure No Other No Pressure N/A psi Test Temperature N/A Pressure Relief Valves: Service N/A . Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blsmwdon Adjustments Made Using N/A r at N/A. - NOTE: Supplemental sheets in the term of lists, sketches,'or dra*rings may be used, provided (1) size ts 8 A, X t t In. (2) information In hems I through 6 on this roped is included on each sheet, end (30 each sheet is numbered and the number of sheets is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 137 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 D3-0070-5 FORM NIS-2INR-1/N**ff+
- 9. REMARKS CERTIFICATE OF COMPLIANCE 1, Thomas M. Purdue , certify that the statements made in this repot.are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code arid to the National Board Inspection Code "NR" rules.
National Board C rifficate of Authorization No. 20 to use the "NR" stampm 07/17/10 Date 3 lo FENOC . Signed ._Q.C.
* .Yt?4(V8SC#OLL CERTIFICATE OF INSERVICE INSPECTION 1, Bruce North . .
- holding a valid commission issued by the. National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of Ol-o and employed by HSB CT of Hartford, CT have inspected the work described in this report on '3 Z6/, and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection Code "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 3,-25"fo Signed -u/' Commissionss/l, 7 6,401, 01"/1.5 Z-CERTIFICATE OF COMPLIANCE I, N/A certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'VR" and 'NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION. I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OH-IO and employed by HSB CT of Hartford, CT have Inspected the repair, modification or replacement described In this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules. By signing this certificate, neither the undersigned nor my einployer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
-I0.
W
16 RFO Inservice Inspection Summary Page 138 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
/ 0 1770.1 FORM NR-1 REPORT OF REPAIR Z OR REPLACEMENT [E TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS
- 1. Work performed by: Weldin? Services Inc. 104770 2225 Skyland Court9Norcross, GA 30071
- 2. Owner: FirstEnergy Nuclear Operating Company 76 South Main, Akron, OH
- 3. Name, address and identification of nuclear power plant Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449
- 4. System: Unit 1, RC System Sa. Items which required Repair or Replacement Activities Identification Construction Code Activity No Type of Mfg. Mfg. Nat 1d. jurlsd. Year Name Edition Code Code Repair Item Name Serial No. No. No. Oter Built section Division Ad Case(s) Gas Replace 620-0014- Asme 1 RPV 1-2 North B& W 51,52 N-156 N/A N/A 1972 Ing/1 1968 N/A I Repair core Hlood Summer RC-RPV-WR-53-W _1968 ......
5b. Items installed during Replacement Activities Identification Construction Code Installed or Name Type of Replaced Mfg. Mfgý Natl Bd. Jurlsd. Other Section Edition Item PaItem No. Name Serial No. No. No. Built Division Addenda Case(s) Class Weld Overlay See line 11 WSI N/A N/A N/A N/A 2010 ASME XI 1995 / 1996 N-740-2 I
- 6. ASME Code Section XI applicable for Inservice inspecthon: 1995 1996 N/A
- 7. ASME Code Section XI used for repairs or replacement s: 1995 1996 N-740-2 (CWvcadO ASME III
- 8. Construction Code used for repairs or replacements: 1968 Summer 1968 N/A (Ca,*C,,(10))
- 9. Design Responsibilities: Structural Integrity Associates Inc., San Jose, CA
16 RFO Inservice Inspection Summary Page 139 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
- 10. Tests conducted: hydrostatic [] pneumatic El design pressure [ pressure __ psi Code Case(s)__
To be performedby owner
- 11. Description of work: Installed a Full Structural Weld Overlay (FSWOL) to Reactor nozzle to Pipe IAW WSI Traveler 104770-TR-105, Rev. 1 which incorporates Davls-Besse Work Order Number 200327,100. This implements a one time NRC accepted repair plan JAW Relief Request RR-A33 and amended Code Case N-740-2.
- 12. Remarks: WSI NCR's 10-208 and 10-219 initiated and closed during the performance of this repair.
-rl..^ ^ll^,.d.^ T....... .-I U^*I-. ^*II .... l-;-,.l*l 1,,*^ *d-lllT*rl.
tIle tlulitnVgtt _Upes an.U taL.to Ut Wti~ mattcrita were Ut,11 ER308 / 308L, SEA 5.9, Ht./Lot739058 / YT9160, ERNiCr-3, SFA5.14, Ht.NX7214DR, ERN[CrFe-7A, SPA 5.14, H-t.NX74W8TW Note : Ultrasonic Examination conducted Inaccordance with ASNE Section XI, Appendix VIII, 1995 Edition with 1996 Addenda. Stamping I Nameplate omitted per NBIC 5.7.2 para. b and Ohio code Chapter 4101:4-2-01 (A), (1). CERTIFICATE OF COMIPLIANCE 1, Ronald Aggen ,certify that to the best of my knowledge and belief the statements in this report are correct and the repair or replacement activities described above conform to Section X1of the ASME Code and the NationalBoardInspection Code "NR" rules. National Board "R" CertificateofAuthorizationNo. NR-69 to use the "NR" stamp expires November 6 2010 NR Certificate Holder Weldincl Services Inc. Date 4///'Q it I Signed - 4 .LD(YbQAi (~.,=I~.d~tt1i QA/QC Inspector CERTIFICATE OF INSPECTION i, -R .UCE Mkloc'ri4 ,holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of 041 f and employed by HSB-CT of Hartford, CT have inspected the repair, modification or replacement described in this report on - ' and state that to the best of my knowledge and belief, this repair, modification or replacement activity has been completed in accordance with Section X) of the ASME Code and the National Board Inspection. Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning The work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal Injury, property damage or a loss of any kind arising from or connected with this inspection, Date A -.. -O Signed " IXj ý Commissions lR9cqiIAN',IL F.T ooo
16 RFO Inservice Inspection Summary Page 140 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 FORM NIS-2JNR4-1NVR-+eWfR'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Date July 19,2010 76 South Main St.. Akron. 0H1 44308 Sheet I of 2
- 2. Plant Davis-Besse Nuclear Power Station Unit 5501 N. SR. 2, Oak Harbor, OH 43449 200327406
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng 1;101 N 5R I nlak 1-arhn-. OA 43449 Authorization No. 20 Expiration Date 07/17/13
- 4. Identlficatlon of Systems Steam Generator 1-I DB-E24-1 S. (a) Applicable Construction Code ASME3 CL.t 1968 Edition SS6Addenda Code Case 1332-4 & 1407-1 (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Coda Case 416-3 (c) Design Responsibilities FirstEnergy Corp.
- 6. Identification of Comoonents Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped See attached oendWr NR.- I form.
- 7. Description of Work(
During examination activities for the AFW thermal sleeves and the internal AFW header for Steam Generator 1-1 one nut and one stud required replacement for the man way cover. A VT-2 inservice leakage test (per code case 416-3) was performed satisfactory as part of the post repair/replacemaent examination.
- 8. Tests Conducted: YES Hydrostatic No Pneumatic No Nominal Operating Pressure YES Other No Pressure 1200 psi Test Temperature N/A "F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdown (If applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A
- n. smd) at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings maybe used, provided (1) size Is 8 1/2'X 11 in. (2) Information in tems 1 through 6 on this report is included on each sheet, and (30 each sheet Is numbered and the number of sheets is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 141 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 FBO0070-4 FORM INIS-2/NR11-1/NVR-A'-
- 9. REMARKS ,,R Areva NP Inc.
CERTIFICATE OF COMPLIANCE 1, Jeffrey M. Martin , certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 20 to use the 'NR" stamp expires 07/17/13 Date 07/19/2010 FENOC Signed Q.-. _. San~m t,Zr Qqlizflo (utnofrm~mr ro.0arwam CERTIFICATE OF INSERVICE INSPECTION I, Thomas.Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of -OHIO and employed by 71,,iio(0 T("--1Z*" HSB CT _ of Hartford, CT have inspected the work described in this report on .0;49c2e- and stlate that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date _-749?______ - Signed Commissions t'-zt"V33 *..-A oý_w CERTIFICATE OF COMPLIANCE I, N/A . , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the 'VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR' stamp expires 07/17/13 Date FENOC Signed Q.c. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of 01410 and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been. completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
.. wwý. ý .. g
16 RFO Inservice Inspection Summary Page 142 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 FORMNR- REPORT OF REPAIR MODIRCATION D ORREPLACWET X TO NUCLEAR CO FO'rNENTAND SYSTE".5 ]NSUCLEAR POWER PLANTS I.Workpamfroa.dby AREYANP Ec. I:'Mi 45231708 (narreeoNR cta~~~ebolder) (P.O.no.job=n. Nc.) 3315 OldForesitd.dLynchburg Va. 24501 2-.O ai s .. s)a.. (y
;6 Scufti Main St, A 01fia-44308 (add-~)
- 3. Nre, addms and ideatifiation facellear power plant "Dvis-B- NuclPowtrStactrin
" " WnSI 2I OakTd,I=w hi 4J449
- 4. Systn Ster*n Generator 0 E24-l 5.a.item. Wbich Required Repair, Modificalion or Replacent Aclivio"es ldnifdcatioa Cof-ruction Code Actiity No Typeof- Mfg. serial . oisd thSa Year lNo.iltDivision " Edi*ii6dn/ Code Code Item Naoe N. No. Boit .
Addenda Case(s) a* ss:. -p . 1 2) (1) C2) 159 'VA'A 1972 (3) (4) (5) A I..lce 13 4 5 16 7 8 9 10 12 5.b: ItemsInstalled During Replacement Activitie Idnti~fication . Co~bmcon Code Type of" Installed 5rt M f,. ,fSerial Nat'l Bd& Ioaisd Other Ye0 None Ediin/ Code Cde Itea Replacds a Name No. No. No Botu Sention/ Addenda C.se(s) Clas I Item No. Division " (6) 1 (z) (7) N/A N/A N/A. (10) (3) (4) None 6, ASIE Code Section X) applicable far inset-viceiM ction: 1995 1996 None (edition) (addend.) (Code C.o(a)) 7- ASIE Code Sectioo XI osed f repairs,modiftationsor *eploceastto: 199S 1996 Nne - (edition) (Cede Coses(s)) S. Coostruction Code osed for repaits. rnodifications, or ceplonetents: 1968 Swooaner68 1332-4,1407-1 (edition) (addeode) (Code Cpses(o))
- 9. Denig esaponasibilitieo (9)-
1O.Te-steondantoedhydrostaltiol Pri'snrotEjo Dcsigoprcop. (9) preasson psi Code Case(s) -- Th"-i form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Cripper Ave., Columbus, OH 43229 NB-O1 Rev. 8
16 RFO. Inservice Inspection Summary Page 143 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 Replaced *9"Steam Generator Audllary Feed Water hardware In accordance with AREVA
- 11. Description ofwonIc procedures 03-1274634-005.
(=o f prop"y enbrd odid*talsheet(s) orasketches tI soceptabl). See QCIR 9135048-000 for acceptance of Installed Safety-Related hardware.
.QY 1 each - Heavy Hex Nut V. SA194, 8, UNC,2B, 7,.1+ -Stock Code 82576406 NUT, PO# 7025890 Qty I eachtStud-Cartinuous Thread: 1', 4-3/4, 8, UNR Stock Code 15156306 STUD, (SAM93 816) PO S-0844"96 098
- 12. Remarks: Listed below are the number codes thai apply to the replacement activity items shown on the front page (I.) Babcock and W'cox Company (2) StearhGenerator #E24-1, S/N 620-0014-,55-12 j(3'ASME Section III,Class 1, Divislon I (4) Cnstructlon Code ASME I111, 1968 Edition, 1968 SummerAddenda (5) Code Cases 1332-4 and 1407-1 (6) FENOC Stock Code for Hex Nut 82576406 arid Stud 15156306 (7) Descripion of Safety-Related parts Installed'- See QCIR9135048-000 (8) AREVA NP Inc.
(9) By others- Firstlaergy (10) See FENOC Work Order 200327406 CERTIFICATE OF COMPLIANCE L David T wsk'y.cerifdythat to the best of my knoweidge and beliefths statreneus made in this report arecn= and the rcpaif. modificatio orreplacnaat acivties descrihed above conformoto Sectiono oftbe ASMi Code andthe National board Inspection Cede "NIL" udes. Natofnal Board Cer*ificateof Authorhizaion No. N to usethe "1W"staop c*nephs_aP.17 26 NR Crtificate Holder -N Dsdueec~22.3010 Signed 0A Specialist (assfitrarad r!1to (tdinl) CERTIFICATE OF INSPECTION L~BrivcE N'bt,44 holdingsa valid coursissiso issuedbyTheNatireal Boardof Baiter sod Pxeosone Vessellospeetoriand c-rtcfi'ale of cqapdeisncy issued by thojurisdiction ofjaI.sand eanployed by P *B of
- ha w iespsrted the repair, madificatisa orraplacearnt described in this report on and state that to the bunt ofDy kewledge aud belief, this repois,anrdabeabsa or replacecent aecdivity he been oomple.drii -crdo--ewith uccion M of theASEIdCode -6dtb National Board1aspeodon Code 'IL,' tuoes.
By signing this ceithr theuaderig t sacoy-player make any - Marn
-ctlificat, esprert c, irapIie4 reac-ig the wbin described-in this report PFursderaere., neither the sudersigned n*amy employer sbal1be liable Inany manaer for
.ay peaoneal injnuy,property darnageor loss of any kind
- ri ora or connected with this ibspetiaon.
Date Si~d CoSspundsaons
16 RFO Inservice Inspection Summary Page 144 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 D0055705.5 1-7-Y-5 1(b If FORM NIS-2/NR-1/NUR4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the AS;ME Code Section XI
- 1. Owner FirstEner r nat March 08, 2010 7MSouth Main St., Akron, Off 44308 Sheet t of I
- 2. Plant Dayis-Besse Nuclear Power Station Unit #1 200327417*.
5501. N. SR. 2, Oak Hatrber, OH 43449
- 3. WorkPerformed by FirstEnergNuclear Operating Co. Type Gods Stamp .'N
";-n1 N. RP ) . (la Ia-nr-lr.- 43440 Authorization No. 20 Expiration Date 07/17/10
- 4. Identification of Systems Hanger PS-H29 Snubber SNC-141 Subsystem 064-04
- 5. (a) Applicable Construction Coda ANSI B31.1 1967 Edition Later Addenda Coda Case No (b) Applicable Edition of Section Xi Utilized for Repairs or Fieplacements 19 9*5 Edition 96 Addenda CodeCase 0/a (e) Design Responsibilities Firstenergy Corr, Lisega
- 6. Identification of Components Repaired or Repiaced and Replacement Components Manufaclurer' tNational Other IdenlfgcatlonW Year Repaired ASME Nnameot Component Nomaof Manufacturer N Serial No. Scard No. turisdisionaltrNo. Built Replaned or Code Replacement Stamped 3039 Hydraulic snubber Liso a 61219/51 N/A SNC-141 fUNK Replaced No 3038 Hydraulic snubber Lisega 30900032/046 NIA SNC-141 2009 Replacement No
- 7. Description of Work Existing Liseg-a Snubber 61219/S1 weasreplaced vita oncew like for like replacemnent Lisega snubber 30900032/046.
As left inroeectioa/\rT-3 performed-SAT performed-SAT of Work for like replacement Lise*a snubber 30900032/046., : As sega Snubber 6!219/51 was re*laced with a new7. like
- left inspectiol*/T-3 Description S(ojCont. ANSI B31.1 & NISS-SP58
- a. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operatlng Pressure No i Other No P'iessure N/A Psi Test Temperature N/A 'F Pressure Relief Valves:
Service N/A Size NIA Opening Pressura. N/A Blo,'dwn (if applicable) N/A Set Pressure and Btowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets Inthe form of lists, sketches, or dratirngs may be used, provid(ed (il size Is 8 Y X ft in. (2) tIlnmotirot initems t through 6 on this report is Included on each sheet, and (30 each sheet Is numbered and the number of sheets is recorded at te top of this form.
16 RFO Inservice Inspection Summary Page 145 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB30070-5 FORM NIS-2INR-1/NVR"t-
- 9. REMARKS CERTIFICATE OF COMPLIANCE 1, Thomas M. Purdue certify that the statements made in this report are correct and the repair, modification', or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules.
National-Boar Cetficate of Authorization No. 20 to use the "NR" st ap-es 07117110 Dale FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Bruce North holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of " OHIO and employed by HSB CT -of
- Hartford, CT have inspected the work described in this report.on 3-Z5--10 and state that to the best of my knowledge and bblief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any. personal injury, property damage or loss of any kind arising from of connected with this Inspection. Dale 3"25-/to Signed 4 - ?-, 4 Commissions ./ 792b,448I--/
, . tf Z CERTIFICATE OF COMPLIANCE 1, NIA "- -, certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules.
National Board Certificate of Authorization No. 316 to use the "VR"' stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/1?110 Date FENOC Signed _ _Q.C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and bertificate of competency issued by the jurisdiction of OHIO and employed by 1-1S CT of Hartford, CT have inspected the repair, modification or replacement described in this report on
- and state that to the best of my knowledge and belief, this repair, modification or replacement has been-completed in accordance with Seotion XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the
.r.epair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection.
Date- . Signed Commissions
16 RFO Inservice Inspection Summary Page 146 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DBO-OO7tt-C *rI.n ii i~s OB-0070-5 FORM NIS-2INR-1/i4ý-i OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xi
- 1. Owne r- FirstEnergy'Corp. Data March 10, 2010 .
76 South Main St. Akron. OH 44308 Sheet 1 of I
- 2. Plant Davis-Besse Nuclear Power Station #1 Unit 5501 N. SR. 2. Oak Harbor. 014 43449 200327421
- 3. Work Performed by FirstEnergy Nuclear Operating Co. . Type Code Slamp NR VZAI N P I3 O5 T. 01t T AIAA Abtherization No. 20 E*xniraton Date 07/17/10
- 4. Idenlitication of Systems Hanger PSP-1-H36 Snubber SNC-144 Subsystem 064-04
- 5. (a) Applicable Construction Code ANSI B31.1 1967 Edition Later Addenda Code Case No i(b) Applicable Edition of Section XI Utilizedafor Repairs or Replacements 19 95 Edition 96 Addenda Code Case 1tta (c) Design Responsibilities Firstenerxy Core, Lisepa
- 6. identification of Components Repaired or Replaced and Replacement Components Manufacturers National Other Identificaton/ Yea( Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Builtt Repltced or Code Replacement Stamped 3038 Hydraulic snubber Lisega 61219/44 N/A SNC-144 UNK Replaced No 3038 Hydraulic snubber Lisega 30900032J058 NIA SNC-144 2009 Replacement No
- 7. Description of Work Existing Lisega Snubber 61219/44 was replaced with a new like for like replacement Lisega snubber 30900032/058.
As left inspection/fVT-3 performed-SAT 5(a) Corrt. ANSI B3 1.1 & MSS-SPS8
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A psi. Test Temperatuee N/A .F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure NIA 8towdoan (if applicable) NI/A Set Pressure and Blouwdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings maybe used, provided (1* size is 8 N X 11 in. (2) Information In Items 1 through 6 On this report Is included on each sheet. and (30 each sheet is numbered and the number of sheets is recorded at the teo of this form.
16 RFO Inservice Inspection Summary Page 147 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2FC R-1/A*TOFCOIA
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue ,oertify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section- XI of the ASME Code and to the National Board Inspection Code "NR" rules.
National Board Cartifi ate of Authorization No. 20 to use the "NR" stamp ,pe07117/10 Date f,0 FENOC Signed Q.C. 7-4406e. NOLL. CERTIFICATE OF INSERVICE INSPECTION I, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSR CT of Hartford, CT have inspected the work described in this report on 5. -?-/7ý and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME'Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shafl be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 3 /0 Signed Vll:! .. Comrnflssions ,AM 44AJ2/, D//4'2-CERTIFICATE OF COMPLIANCE 1, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI.of the ASME Code and to the National Board Inspection Code "VA"and "NR" rules. National Board Ceriificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION 1, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel
.Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described ih this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section X of the ASME Code and the National Board Inspection Code 'VR' and "NR" rules...
By signing this certificate, neither the undersigned nor my employer makes bny warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermpre, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions .
16 RFO Inservice Inspection Summary Page 148 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 01-0070-S 4y 4f -. lII FORM NIS-2/NR-1MNVR+ OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XA
- 1. Owner FirstEnergy Corp, Data March 09. 2010 76 South Main St.. Akron, Oil 44308 Sheet I of I
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 200327430
- 3. WaordkFormed by FirsiEnergy Nuclear Operating Co. Type Coda St*amp NR 5502 N. SR. 2, Oak Harbor, O1 43449 Aulhorization No. 20 Exsiraflion Dates07/17110
- 4. Idenlifieation of Systems Hanger PSP-I-H34 Snubber SNC-146 Subsystem 064-04
- 5. (a) Applicable Construction Code ANSI B31A. 1967 Edition Later Addenda Code Case No lb) Appflicabl Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case n/a (c) Design Responsibilities Firstenergy Corp, Lisega
- 6. Identification of Components Repaired or Replaced and Replacement Components Manntacturers National Other dentifcations Year Repalred ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 3031 Hytrauliocsnubber Lisega 61219/47 NIA SNC-146 UNK Replaced No 3038 Hydraulic snubber Lisega 30900032/047 NIA SNC-146 2009 Replacement No
- 7. Description of Work
_Existing Lisega Snubber 61219/47 was replaced with a new like for like replacement Lisega snubber 30900032/047. As left inspection/VT-3 performied-SAT 5(a-) Cont. ANSI B3f1.1 & MSS-SP58
- a. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A s3i Test Temperature NIA *F Pressure Relief Valves:
Opening Pressure N/A .Blowdown (idapplicable) N/A Set Pressureand Blovidown Adousnsments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided.(1) size Isa .Y, X Ii in. (2) Information in Items I through 6 on this report is included on each sheet, and (30 each sheet Is numbered and the number of sheets is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 149 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 0B-0070-5 FORM NIS-2/NR.1[N~fR4
- 9. REMARi(5 9.REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue certify that the statements made in this report are correct and the repair, modification, or replacement ot the items described above conforms to Section XI of the ASME Code and to the National Board Inspecton Code "NR" rules.
National Board Certif iate of Authorization No. 20 to use the 'NR" stamp expires0
- Date FENOC Signed Q.C.
!Lq086 SCERTIFICATE OF INSERVICE INSPECTION 1, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of O-11O and employed by HSB CT of Hartford, CT have inspected the work described in this report on 3- 25'- / and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described In this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date _________Signed Commissions /018 792V04A.)6/1._// ?2_ CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section X1of the ASME Code and to the National Board Inspection Code "VR" and "NR' rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 121t3/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date __FENOC Signed _Q.c. .-. CERTIFICATE OF tNSERVICE INSPECTION 1, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificrate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hargf6rd, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accdrdance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in-any manner for anypersonal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed
- Commissions
--- 'on
16 RFO Inservice Inspection Summary Page 150 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 FORM NIS-2/NR-1/NV'R-OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- i. Owner FirstEnergy Corp. Date March 10, 2010 76 South Main St.. Akron. OH 44308 Sheet I of I
- 2. Plant Davis-Besse Nuclear Power Station Unit 5501 N. SI. 2, Oak Harbor, OH. 43449 200327440
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2, Oak Harbor. OH 43449 Authorization N6 20 I. .
Expiration Date 07/17/10
- 4. tdaetilicalion of Systems Hanger PSP-l- -36 Snubber SNC-147 Subsystem 064-04
- 5. (a) Applicable Construction Code ANSI B31.1 1967 Edition Later Addenda Code Case No-(b) 'Applicable Edition ol Section XI Utilized for Repairs or Replacements 19 95 Edition .9 Addenda . Code Case fta.
(c) Design Responsibilities Pirstenergy Corp, Lisega It Irtantifiration ni flnmnnnanta Ranairari Cr Ranlacari and Rantarament flrrmnnnants NuManufacturers National Other Identification/ Year Repaired ASME Name o1 Component Name ot Menutacturer Sedal No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 3031 Hydraulic snubber Lisega 61219/55 N/A SNC-147 UNK Replaced No 303t HNdraulic snubber Lisega 30900032/048 N/A SKC-147 . 2009 .Replacement No
- 7. Description of Work Existing Lisega Snubber 61219/55 was replaced with a new like for like replacement Lisega snubber 30900032/04g.
As left inspection/VT-3 performed-SAT 5(a-) Cont. ANSIB31.1 & MSS-SP59
- 8. Tests Conducted; Hydrostalic No Pneumalic No Nominal Operating Pressure No Other No Pressure NIA psi Test Temperature N/A *F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure NIA "aBlewdown (if applicable) N/A Sel Pressure and eiomdown Adjuslments Made Using. NIA at N/A NOTE: Supplemental sheets in the form of lists, ukelches, or drawings may be used, provided (1) size Is B Y5X 11 in. (2)Information In items I through 6 on this report is included on each sheet, and 130each sheet Is numbered and the number of sheets is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 151 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-S FORM NIS-2/NR-1/N.f0I, .
- 9. REMARKS CERTIFICATE OF COMPLIANCE Thornas M. Purdue certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section X1of theASME Code and to the National Board Inspection Code "NR" rules.
National Board Certificate of Authorization No. 20 to use the "NR" stap e s 07/17/10 Date lb FENOC Signed J..CSCt ¢HOLL -CERTIFICATE OF INSERVICE INSPECTION I, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on _T 0' and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of tie ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 5Z 6- /0 Signed ,
,Commissions ( N,,l, 7'WA)VS1-'A
,3 Z-CERTIFICATE OF COMPLIANCE 1, N/A , certify that to the best ot my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section Xl of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules.
National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.c. CERTIFICATE OF INSERVICE INSFECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of - Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed _ ._ Commissions
16 RFO Inservice Inspection Summary Page 152 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 08-0070-5 FORM NIS-2/NR-1I/NVR-4-OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xi
- 1. Owner FirstEnergy Corp. Date March 09, 2010 746South gain St,. Akron. OR 44308 Sheet I of 1
- 2. Plant Davis-Besse Nuclear Power Station Unit 91 5501 N. SR. 2, Oak Harbor. OH1 43449 200327444 3., Work Performed by FirstEnergyNuclear Operating Co, Type Code Stamp NR 5501 N. "SR.2. Oak Harbhor. OTT 43449 AuthorizattontNo. 20 5501 N. SR 2 Oak Harbor OH 43449 Expiration Data 07/17/10
- 4. Identification of Systems Haegei" PSP-1-H37 Snubber SNC-148 Subsystem 064-04 S. ia) Applicable Constrmeiton Cede ANSI B31.t 1967 LEdition Later Addenda Code Case No (b) Applicable Edition of Section Xf Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case t/1a (c) Design Responslibilitles Fir-stenergy Co p, Lisega or Replaced and Replacement Components 6.Ideniiflcation of Components Repaked
- 6. icdentificat ion of Components Repaired or Replaced anti Replacement Components Mannufacturer'a National Other IdentificationI Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or " Code Replacement Stamped 3038 Hydraulic snubber Lisege 61219/43 N/A SNC- 148 UNK Replaced No 3038 Hydraulic snubber Lisegpa 309000321055 N/A SNC-148 2009 Replacement No
- 7. Description of Work Existing Lisega Snubber 61219/43 was replaced with a ntew like for like replacement Lisega snubber 30900032/055.
As left inspecdonVT-3 performed-SAT 5(a) Coat. ANSI B31.1 &MSS-SP58 B. Tests Conducted: Hydrostatic No PneumatIc No Nominal Operating Pressure No Other No Pressure N/A psi Test Temperature N/A F Pressure Relief Valves: Sereice N/A Size N/A Opening Pressure N/A Blowdown (f0applicable) N/A Set Pressure and Slowdown Adjustments Made Uling N/A at N/A LNOTE: Srpplemsntal sheets In the term t tists, sketches, or dratsings may be used, provided (1) size I3 8 Y X t I in. (2) Information in items I through 6 on h£ report is Inctaded en each sheet, and 180 each sheet Is numbered and the number of sheets is recorded at the top eo this form.
16 RFO Inservice Inspection Summary Page 153 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070.5 FORM NIS-2INR-1/N.VR4 9.REMARKS CERTIFICATE OF COMPLIANCE Thomas M. Purdue certify that the statements made In this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Bo rd Certicate of Authorization No. 20 to use the "NR" stam res/ 0717/10 Date -5/1 FENOC Signed d .- fl:eTIFII'A*TF: (S: IMSRFRXIICFeJNSPFn.TI(O I, Bruce North. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of 011HO and emnployed by HSB Cr of Hartford, CT have inspected the work described In this report on - 3 "2r- /P and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board inspection Code "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 3.2 -" Signed -. Commissions N6t/7920 Ae,.J- OII/32. CERTIFICATE OF COMPLIANCE N, N/A certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires -07/17/10 Date ______________ FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION i, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of Of-1i and employed by I1-SB CT of Hiartfotd, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code VR' and "NR" rules. By signing this certificatei neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind-arising from or connected with. this Inspection. Date Signed Commissions rausuls , a J
16 RFO Inservice Inspection Summary Page 154 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 08-D070-5 -, ,..zf2L;IlF) FORM NIS-21NR-1NWH-OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI I. Owner FirstEnergy Corp. Date March 09. 2010 76 South Main St., Akron. OH 44308. Sheet t of I
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N-SR. 2, Oak Harbor, OH 43449 200327446
- 3. Woa Performed b- FirstEnergy Nuclear Operating C(l . TYPeCodOStamp .NR 5501 N. SR. 2. Oak Harbor, OH 43449 Authorlzalion No, ,0 Expiration Date 07/17/10
- 4. IdenticationaofSystems Hanager PSP-1-H37 Snubber SAC-J49 Subsystem 064-04
- 5. (a) Applicabte Construction Code ANSI B31.t 1967 Edition Later Addenda Codt Case No (b) Applicable Edition of Section X Uttlitzedfor nepaera or Rteplacementas i 95 EdItion 96 Addenda Code Case nl/a (c) Design Responsibilities Firstenerny Corp, Lisega
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired ASME Name ot Component Name of Manufacturer Serial NO. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 3038 H/ydraulic snubber Lisega 61219/54 N/A SNC-149 UNK .Replaced No 3038 Hydraulic snubber Lisega .- 30900032/056 NIA SNC-149 2009 Replecement No
- 7. Description of Work Existing Lisega Snubber 61219/54 was replaced with a oew like for like replacement Lisega snubber 30900032/056.
As left inspection/VT-3 performed-SAT 5(a) Cont. ANSI B31.1 &MSS-S5S8
- a. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A PSI Test Temperature NIA 'F Pressure Relief Valves:
Sernice N/A Size N/A Opening Pressure N/A alimatovn I1 appltcaOle) N/A Set Pressure and Blaowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawinagsmay beused. provided (t) size is a Y X It In. (2) Information Initems I through 6 on thle ann~iinrtI ,rInchld~nn aehchee nntSrh,,rN peh hMI.,enufherd *nedth,.h erntnh o , heets Iserecrded alt Ie 1nn ofthieform. this fenort Is Included on each sheet and 130each sheet Is numbered and the number of sheet$ Is recQrded at (he ton of this form
16 RFO Inservice Inspection Summary Page 155 of 235-FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-bo30-5 FORM NIS-2JNR.11NVR'
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Punrde , certify that the statements made in this report are correct and the repair, modification, or "replacemednt of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'NR" rules:
National Board Certificate of Authorization No. 20 to use the "NR" stamp ex s .. "07/17/10 Date ? /0 FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION ___Brce. North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of Oilf0 and employed by HS.B.CT of I-lartford, CT have inspected the_,'Wgrk de.scribed in this report on 3 -2 $- /0 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from ot connected with this inspection. Dat 225- 10 Signed . ~ - iCommissions /)72JA6 t'1 . CERTIFICATE OF COMPLIANCE K/A N, certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National-Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.C. CERTIFICATE OF INSERVIGE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel I Inspectors and certificate of competency issued by the jurisdiction of O11O and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described In thit report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code-and the National Board Inspection-Code "VR" and "NR" rules. I By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be I liable in any manner for any personal injury, property damage or loss of any kind arising.from or connected with this. inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 156 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 ne-stun-s DE3-0070-5 3-)J-10 FORM NIS.2/NR-1/N'V'R--4-OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Ovmer FirstEnergy Corp. Date March 10, 2010 76 Southr Mait St.. Akron. OH 44308 Sheet I of I
- 2. Plant Davis-Besse Nuclear Power Station Unit
#1 5501 N. SR. 2. Oak Harbor. OH 43449 200327460
- 3. Work Performed by "FirstEnergy Nuclear Operating Co. Type Code Stamp 0/NR 5001 N%R.3 Ilt I-h- n-T" (111t,,dd Authorization No. 20 Expiration Date 07/17/10
- 4. Identification of Systems Hanger PSP-1-H17 Snubber SNC-159 Subsystem 064-04 S. (a) Applicable Construction Code ANSI B31.1 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Section X1Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case r/a (c) Design Responsibliles Firsrteeerg' Corp. Lisega 0 trtarrrilrr-crlrrr,sI -rrrcmrc tlc,.ctrcd rrr Rerrlanart cnrt Rnntcrrrrnant Crnrrrnnnntc Manufacturer's . National Other ldenlificallotV Year Repaired ASME Name ot Component Name of Manufacturer Serial No. Board No. Jursdicltional No. Built Replaced or Code Replacement Stamped 3038 Htydraulic snubber Lisega 61219/59 NIA SNC-159 UNK Replaced No 3038 Hydraulic snubber Lisegoa 30900032/049 N/A SNC-159 2009 Replacemcnt No
- 7. Description of Work Existing Lisega Snubber 61219/59 was replaced witl a new like for like replacement Lisega snubber 30900032/049.
As left inspeetionfVT-3 performed-SAT 5(a_)Cont. ANSI 031.1 &MSS-SP58 B. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure' N/A psi Test Temperature N/A 'F Pressure Reilel Valves: Service N/A Size N/A Opening Pressure N/A -lowdown (if applicable) N/A Set Pressure and SRowdown Adjustments Made Using N/A at N/A NOTE: Supptemental sheets In the form of lists, sketches, or drawings maybe used, provided (11size Is f Xti, in.()Inormatlon 12 in Items I through Son this report is Iecluded on each sheet, and (30 each sheet Is numbered and the number ofsheets is recorded at the topo s fr'm.
16 RFO Inservice Inspection Summary Page 157 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-070-5 FORM NIS-2/NR-1/N#-R4
- 9. REMARKS CERTIFICATE OF COMPLIANCE 1, Thomas M. Purdue , certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'NR" rules.
National Boaed Certiticate of Authorization No. 20 to use the "NR1" stamp es 07117110 Date /0 FENOC Signed 7. Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT . have inspected the work described in this report on 3 - Z 5" /0 and state that to thebest of my knowledge and belief, this repair-mnodification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of corinected with this inspection. Date .Z -/o.. Signed , Commissions 1.? _ __/1_,6 _,_ _-._-_ 1 -0y CERTIFICATE OF COMPLIANCE 1, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, moditication, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12113/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.C._. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of fartford. CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed CG~mmissions
16 RFO Inservice Inspection Summary Page 158 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 0B-0070-5 , 3/ýýCho FORM NIS-2/NR-1/NVR-1-OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xt
- 1. Owner FirstEnergy Corp. Date March 25, 2010 76 Soutl Main SL, Akron, OU 44308 Sheet I of 1 P. Plant Davis-Besse Nuclear Power Station Unit - #1 5501 N. SR. 2, Oak Harbor, OH3 43449 _ - 200327466
- 3. Work Performed by irstEner.y Nuclear Operating Co. Type Code Stamp NA 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No. 20 Exotratton Date 07/17/10
- 4. Identification of Systems Hanger PSP-1-H20 Snubber SNC-1tlt Subsystem 064-04 S. (a) Applicable Construction Code ANSI 1331.1 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Section XI Utlitzed for Repatm or Replacements 19 95 Edition 96 Addenda Code Case n/a (c) Design Responsibilities Firsteirergy Corp. Lisega
- 6. Identification of Components Repaired or Replaced and Replacement Components NManufacturor's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictlonal No. Built Replaced or Code Replacement Stamped 3038 lyrdraulic snubber Lisega 61219148 N/A SNC-189 UNK Replaced No 3038 H-ydraulic snubber Lisega 30900032/054 N/A SNC-189 2009 Replacement No
- 7. Description of Work Existing Lisega Snubber 61219/48 was replaced with a new like for like replacement Lisega snubber 30900032/054.
As left inspectionfVT-3 perfonned-SAT 5(a-) Cont. ANSIB331.1 &MSS-SP58
- a. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A tsi Test Temperature N/A 'F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdeeon (it applicable) N/A Set Pressure and Blowdown Adfustments Made Using N/A at N/A NOTE: Supplemental sheets In ihe form of lists, sketches, er drawings may ire.qsad,.provided (t) niceiS8 fir X it in. (2) Informallon In items I through 6 on this report is Included on each sheet, and (30 each sheet is numbered and the number of sheets is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 159 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-1/NWfl-I-
- 9. REMARK(S CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section X1of the ASME Code and to the National Board Inspection Code "NR" rules.
National Board Ce ificate of Authorization No. 20 to use the "NR" stam*m *e. 07/17/10 Date' FENOC Signed ., JACOB SC14oLL - 1, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford. CT have inspected the work described in this report on 2,, t/o and state that to the best of my knowledge and belief; this repair, modification or replacement has been completed In accordance with Section XI of the ASME CQde and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 3 -25"-/1 Signed 9.4- e -4*... Coommissions N)877*2/0,08/, tt*, .&- CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made In this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the NR" stamp expires 07/17/10 Date ______________ FENOC Signed Q.C. CERTIFICATE OfFlNS ERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate oflcompetency issued by the jurisdiction of OHrO and employed by HSB CT of Harrferd, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor myaemployer shaltbe liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 160 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0B70. "rV *3/25/IO 5 FORM NIS-2INR-1/N R-'OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl nI.Owne FirstEnerev Corn. Date MarCh25,2U5U 76 Soutblvlain St., Akron,-OH- 44308 Sheet I of I
- 2. Plant Dais-Besse Nuclear Power Statten Unit #1 5501 N. SR. 2, Oak Harbor, OR 43449 200327470
- 3. Work Performed by FirstEnergy Nuelear Operating Co. Type Code Stamp Nt.
5501 N. SR. 2* Oake Iarbor. Oil 43449- Authorization No, 20 5501 N. SR. 2ýOak Harbor 011 43449 - Exliration Datae 07/17/10
- 4. Identification of Systems "Hanger PSP-I-2-12i "Snubber SNC-162 Subsystem 064-04
- 5. (a) Applicable Construction Code ANSI B3tI 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code-Case n/a (c) Design Responslbllities Firstencray Core, Lisega
& lrlentifinatine cr1flnmnernenrs Rerratrad or Rerdanert and Rantacement Comnenents Manufaclurer's National Other identtticallorst Year Repaired ASME Name of Component Name of Manufacturer Serial No, Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 3038 Hydraulic snubber Lisega 61219149 N/A SNC-162 UNK Replaced No 3038 Hydraulic snubber Lisega 309000321071 N/A SNC-162 2009 Replacement No
- 7. Description of Work Existing Liscga Snubber 61219/49 was replaced widt a tnew like for like replacement Lisega snubber 30900032/071.
As left inuspectiolV'VT-3 perforrned-SAT 5(a.) Cont. ANSIB31.1 &MSS-SP58
- a. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure NkA eel Test Temperature N/A 'F Pressure Relief Valves:
Service NIA Size NIA Opening Pressure N/A 91Oteown (if applicable) N/A Sot Pressure and BlowdowstAdjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or dravwngs may bd used, provided (1) size is 8 A X It In. (2) Infornation is items I through 6 on this report is included on each sheet, and (30 each sheet Is numberod and the number of sheets Is recorded at the top of this form,
16 RFO Inservice Inspection Summary Page 161 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-1/NW"R-4-"
- a. REMARKS CERTIFICATE OF COMPLIANCE 1, Thdias K Purdue ,certify that the statements made in this report-are correct and the repair, modification, or replacement of the items described above conforms to Section X1of the ASME Code and to the National Board Inspection Code "NR" rules.
National Boa d Certificate of Authorization No. 20 to use the "NR" stamp ex07/17/10 Date 6FENOC Signed
,,JT eOBseyo,.t. CERTIFICATE OF INSERVICE INSPECTION 1, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by E)S CT of Hartford, CT have inspected the work described in this report on 2 5- -/1 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board inspection Code "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date ? /f Signed 4 0,,'C'*, t Commissions it192tJ//I/"/3Z CERTIFICATE OF COMPLIANCE 1, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12113/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/f7/10 Date FENOC Signed _ _c. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this relfiir, modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection C'ode "VR" and "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair "rhdificatidih or replacement described in this report. F"urhermore, neither the undersigned nor my employer shalt be liable in any mannertfor any personal injury, property damage or loss of any kind arising from orconnected with thisInspection. Date Signed Commissions.
.,i,.s*b, I~
- A*ird
16 RFO Inservice Inspection Summary Page 162 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 - 01-0070-5 4 FORM NIS-2INR-1/N4'ROWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section X)
- 1. Owner FirstEnergy Corp. Date March 16, 2010 76 South Main St., 4kron, O[ 44308 Sheet I of 1 -
- 2. Plant Davis-Besse Nuclear Power Station Unit fill
.5501 N. SR. 2, Oak Hzairbor, OH 43449 _. " 200327498
- 3. Work Performed by FirstEnergy Nuclear Opeirafing Co. Type Code Stamp Np 5501 N. SR. 2, Oak Harbori. OH 43449 Authorization No. 20.
Expiration Date 07/17/10
- 4. idenftfication of Systems _Hanger PSP-1-E3 Snubber SNC-190 Subsystem 064-04
- 5. (a) Applicable Construction Code ANSI B3t.1 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Section X1Utilized ftr Repairs or Replacements t19 95 Edition .9 Addenda Code Case n/a (c) Design Responsibilities Firstenergy Cori, Lisega
- 6. identification of Components Repaired or Replaced and Replacement Components Manufcturer's National Other Identification/ Year Repaired ASME, Name of Component Name of Manufacturer Serialt No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 3038 Hydraulic snubber Liseqgr 61219/60 NIA SNC-190" UNK Replaced No 3038 Hydraulic snubber Lisega 30900032/073 NIA SNC-190 2009 Replacement No
- 7. Description of Work Existing Lisega Snubber 61219160 was replaced with a new like for like replacement Lisega saubber 30900032/073.
As left inspectiorrfVT-3 erformed-SAT 5(a_) Cont. ANSI B31.1 & MSS-SP58 B. Tests Conducted: Hydrostatic No Pneumatic No NominalOperatlng Pressure No Other No Pressure _N/A psi Test Temperature " N/A F Pressure Relief Valves: Service NIA Size NI/A Opening Pressure NIA Blowdovn (if applicable) N/A Set Pressure andBlowtdownAdjustments Made Using N/A at N/A NOTE: Supplemental sheets in the torm of lists, sketches, or draedngs may be used, provided (1) size is 8 Yt X 11 in. (2) information in items I through en 6 rhis reportis Included on seahsheesort and30 each seet is numbered and the number of sheets is recorded at the too of this form.
16 RFO Inservice Inspection Summary Page 163 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. RtL 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 OB-0070-5 FOAM NIS-2/NR-1/Wft7
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, TIonas M. Purdue , certify that the statements made In this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board inspection-Code 'NR" rules.
National Be d Ce 'ficate of Authorization No. 20 to use the "NR" steme s Z 07/17/10 Date .5 ;1-51 1tý -NOC Signed QC J/Co S . CERTIFICATE OF INSERVICE INSPECTION I, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of 01110 and employed by HSB-CT of Hartford, CT have inspected the work described in this report on 5"1Z5-/ 1 and state that to the best of my knowledge'and belief, this repair, modification or replacement has been completed in accordance with Section Xf of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 3"2f/0 Signed 41/A" _ Commissions APA 7q244918/- tMi'/Y2.-
- rdt*,r,,,- o'i*)
CERTIFICATE OF COMPLIANCE . 1, N/A certify Ihat to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.c. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Ihspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employee shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions . ,
16 RFO Inservice Inspection Summary Page 164 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DR3-O0170-5 -13 1,, ?AA 15Vq f - / FORM NIS-2JNR-11NV-iI-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS I As Required by the Provisions of the ASME Code Section Xl
- 1. Owner FirstEnergy Corp. Dae 0 MarchS 16, 20I0 I 76 South Main St., Akron, OH 44308 StheetI ot I
- 2. - Plant Davis-Besse Nuclear Power Station -Unit 5501 N. SR. 2. Oak Harbor. OH 43449 20032 7 4 9924ý.lto
- 3. Work Pertormed by irstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2, Oak Harbor, OH 43449 Authorization No. 20 Exptration Date 07/17/10
- 4. Identification of Systems Hanger PSP-.1H2 Snubber SNC-189 Subsystem 064-04 S. (a) Applicable Constructioa Code ANSI 31.I t967 Editlon Later Addenda Code Case No (6) Applicable Edition of Section Xt Utilized for Repairs or Replacements O9 95 Edition 96 Addenda Code Case tnia (c) Design Responsibilities Firsteltergy Cori, Liseea S trlnntttewtinn of Connnnnntw Ronairad or Ronlanad anti Ranlanament flnnnnnants n
Name at Manutctarer Manufacturer's National Other Identification/ Year Repatred ASME Nameof Companent N Serial NO. BoardNo. Jurlsdictlonal No. 8uilt Replaced oa Code Replacement Stamped 303S Hydraulic snubber Liesea 61219157 N/A SNC-189 UNK Replaced No 3038 H'ydraulic snubber Lisega 30900032/072 NIA " SNC-189 2009 Replocement No
- 7. Description of Work
.Eisting Lisega Snubber 61219/57 was replaced with a new like for like repladcment Lisega snubber 30900032/072.
As left iuspectiotnfVT-3 peiformred-SAT 5(aj Cont. ANSI B31.1 & MSS-SP58
- a. Tesls Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A psi Test Temperature N/A 'F Pressure Relief Valves:
Serviea "1,/t Size NJCA Opening Pressure NIA Slowdown (it applicable) NT/A " Set Pressure and Blowdown Adjustments Mede Using NIA at N/A - - NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size Is 8 A X 11 in. (2) Information In items I through 6 on ithis report is included on each sheet. and (30 each shoal is numbered and the st of this form.
16 RFO Inservice Inspection Summary Page 165 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2INR-1/WUI. 9. REMARKS _7-
- CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section Xlof the ASME Code and to the National Board Inspection Code "NR" rules.
National Board Certificate of Authorization No. 20 to use the "NR" stamp 5s2 k.7/1i7/10 Date - "5 FENOC Signed _ Q.C f'AcO,6 90104t, CERTIFICATE OF INSERVICE INSPECTION I, Bruce North .* holding a valid commission issued by the National Board of Bolter and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of O6IO and employed by HSB CT of Hartford, CT have inspected the work described in this report on 5'- 5-(0 . and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner forany personal injury, property damage or loss of any kind arising from of connected with this inspection. Date -2 /0 Signed ! c Ž. Commissions A.)674z 0 / 14),'1' 3_- CERTIFICATE OF COMPLIANCE 1, NIA , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board inspection Code '"VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the 'NR" stamp expires 07/17/10 Date FENOC Signed Q.c. CERTIFICATE OF INSER VICE INSPECTION I, NIA holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state thaLto the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASMECode and the National Board Inspection Code "VR" and "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed. Commissions
16 RFO Inservice Inspection Summary Page 166 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 ý 1.11"11. FORM NIS-2/NR-1/NFF-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS J'$o As Required by the Provisions of the ASME Code Section X1 g"
- 1. Owner FirstEnergy Corp. Date March 16, 2010 76 Soutl Main St.., Akron., O 44308 Sheet I of 1
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 206327499-~4--1
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2, Oak Harbor, OH 43449 Authorizatlon No. 20 Expiration Date 07/17/10
- 4. Identificaseon of Systems Hanger PSP-/-H4 Snubber SNC-191 Subsystem 064-04
- 5. (a) Applicable Conslructlon Code ANSI B31.1 1967 Edtlion Later Addenda Code Case No (b) Applicable Edition oaSection XlUtilized for Repairs or Replacements 19 95. Edition 96 Addenda Code Case "/a (r) Design Responsibilities Firstenerey Corp, Lisega
- 6. Identification of Components Repaired or Replaced and Replacement Components Existin! Licega Snubber 61219/56 was reolaced with a new like for like reolacement Lisega snubber 30900032/074.
As left inspectionrfVT-3 performed-SAT 5(a) Coont.ANSIB133.1 &MSS-SP58
- 8. Tests Conducted: Hydrostatic No - Pneumatic No Nominal Operating Pressure No Other No Pressure N/A psi Test Temperature N/A 'F Pressure Relief Valves:
Serice " N/A Size . N/A Opening Pressure N/A Slowdown (if applicable) NtA Set Pressure and Blowdown Adjustments Made Using NIA at N/A NOTE: Supplemental sheets in the form of lists, sketches, or dravings may be used, provided (1) size is 8 A X t I in. (2) Information in items I through 6 on thin rnoo[rt In loIncrhd~rnO'n ,-rh nhtar and PanF ',nh ',hnnt in .- ',bre nnhrd Ihre ,nl,a'ntr cf sheets, in recorded at tbn ton at thinterm. this report Is included on each sheet and (30 each sheet is numbered and the number of sheets is recorded at the ton of this form.
16 RFO Inservice Inspection Summary Page 167 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DS-0070-5 FORM NIS-2/NR-1/1N-fR--
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas K Purdue , certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to theNational Board Inspection Code "NR" rules.
National Board Ceaitfcate of Authorization No. 20 to use the 'NR" stp 7/17/10 Date tFENOC Signed T4( .oB.L." " CERTIFICATE OF INSERVICE INSPECTION I, Bnice North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHUO and employed by HSB CT of Hartford, CT have inspected the work described in this reporton 3- _10 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed ofimplied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection.
.Date -2*--/0 Signed -a7 Commissions _F_7_2_4A__/-4_FZ-_
CERTIFICATE OF COMPLIANCE 1, N/A , certify that to the best of my knowledge end belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR* stamp expires 12/13/10 - National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Qc. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hairford, CT have inspected the repair, modification or replacement described in this report on and state thatto the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. I Date. Signed Commissions _
16 RFO Inservice Inspection Summary Page 168 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 D"-OT7O-5 -.641 rf o FORM NIS-2/NR-1/N*4R-I-OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisons of the ASMe Code Section XI I
- 1. Ozvner F.rstEnergy Corp. Date March 19, 2010 tO OULLut Maitnl0L. AAKro, U1"qU uIl Sheet 1 of I
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 200327500
- 3. Work Performed by FirstiergVyNuclear Operating Co. Type code Stamp NrR 5501 N. SR. 2. Oak Harbor, OH 43449 Authorization No. 20 Exilratlon Date 07/17/10
- 4. Identitltationof Systems Hanger PSP-1-H8 Snubber SNC-194 Subsystem 064-04
- 5. (a) Applicable ConstructionCode ANSI B31.1 _ 167 Edition Later Addenda Code Case No (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case n/a (c) Design Responsibilities Firstenergy Corp, Lisega
& trfentitiratirsn of Comnonnofa Reseired or Reniacad and Rentacameot Comnoneots Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. drudsdictional No. Built Replaced or Code Replacement Stamped 3038 Hydraulic snubber Lisega 61219/58 N/A SNC-194 UNK Replaced No 3038 Hydraulic snubber Lisega 3090032/075 N/A SNC-194 2009 Replacement No
- 7. Description of Work Existing Lisega Snubber 61219/58 was replaced with a new like for like replacement Lisega snubber 3090032/075.
As left inspectionlVT-3 petformed-SAT 5(aJ Cont. ANSI B31.1 & MSS-SP58
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure NIA psi Test Temperature N/A -F Pressure Relief Valves:
Service N/A Size N/A (ripening rressure N/A oeSwo*,oo ((fappllcaole) NtA Set Pressure and Blovordwn Adjuntments Made Using N/A at N/A NOTE: Supplemental sheets Inthe form of lists, sketches, or drawings maybe used, provided (1) size is 8 YSX 11 In. (2) Information In Items 1 through 6 on thin rennd [ intl',,rftd on ,,h ',n~ti ht, Ota eh,sheet t* ,rnltmheradnndthe nnnmber oi sheers in ratrerdad et the,ton cf hirislerm innC thisre rt is included on each sheet and MOeach sheet Is numbered and the number of sheets Is recorded at the to ofthisform
16 RFO Inservice Inspection Summary Page 169 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-1/NVfRV
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue , certify that the statements made In this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules.
National Board Crti icate of Authorization No. 20 to use the "NR" stammpLrs..- ! 07/17110 2 Date t- _C_ I FBPNOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION 1, Jacob Scholl holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and erpployed by HSB CT . of Hartford, CT have inspected the work described in this report on 2-7 -/0 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this Inspection. Date '- -/ Signed 6d? -ve ý Commissions A/6 71ZO ýM81_ofq32-CERTIFICATE OF COMPLIANCE I, NIA , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section Xl of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12113/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed _ _ _ _ CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have Inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of theASME Code and the National Board Inspection Code "VW"and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 170 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 D"-0070-5 p31"b FORM NIS-2/NR-JtNVR-'*"OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASMS Code Section X)
- 1. Owner FirstEnergy Corp. ,*,Date March ] I. 2010 76.South Main St., Aq%..* OH 4430)8 Sheet I of, 1 '
"2. Plant Davis-Besse Nlucleair Power Station Unit * #
. 5501 N. SR. 2, Oak Harbor, OH1 43449 200327501 .
- 3. Work Performed by FirstEnerg' Nuclear Operating Co. T.ypeCode Stamp NP.
5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No. 20 Expiration Date 07117110
- 4. Identiication of Systmas Hanger PSP-1-HJ2 Snubber SNC-198 Subsystem 064-04
- 5. (a) Applicable Construction Coda ANSI B31.1 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Section XI Utitized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case n/a (c) Deslirg Reep6tnlblifflea Firsteltergy Corp. Lisega
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year " Repaired ASME Nane of Corponent Name of Manufacturer Serial No. Board No. Judsdiettonal No. Built Replaced or Coda I. Replacement Stamped 3038 Hydraulic snubber Lise a 61219/50 NIA SNC-198 UNK Replaced No 3038 Hydreutic snubber Lisega 30900032/076 N/A SNC-198 2009 Replacement No
- 7. Description of Work Existing Lisega Snubber 61219150 was replaced with a roew like for like replacement Lisega snubber 30900032/076.
As left inspection/VT-3 perforined-SAT 5(a.) Cont. ANSI 131.1 & MSS-SP58
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other Ne Pressure N/A psi Test Temperature N/A "F Pressure _tellef Valves:
Service N/A Size N/A Opening Pressure N/A . Blodown (if applicablej NIA Set Pressure and Btlvd.ouun Adjustments Maade Using N/A at N/A. NOTE: Supplemental sheats in the form of lists, sketches, or drawings may be used, provided (1) size is 8 Y2X f1 In. (2) Information Initems I through 6 on this report Isincluded on each sheet, and (30 each sheet is numbered and the number of sheets isrecorded.al the top of this form.
16 RFO Inservice Inspection Summary Page 171 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 Q5-0076-5 FORM NlS-2INR-10P~4R
- 9. R5MARKS CERTIFICATE OF COMPLIANCE.
1, Thlomas M1.Purdue ., certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Bo rd Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/t10 Date ' lr- FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION 1, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of OuIO and employed by HSB CT of Hartford,CT have inspected the work described in this report on .
- r- 10/ and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection Code "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 3-25-/O Signed Commissions , ?LV2 g -A)/- I//,q32_ CERTIFICATE OF COMPLIANCE I, NI/A certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section X1of the ASME Code and to the National Board Inspection Code '"VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued byithe National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHtO and employed by HIB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code ."VR" and "NR" rules... By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. IDate DSigned Commissions
16 RFO Inservice Inspection Summary Page 172 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 D07-05-5 =119 (9 f>
/
I, , FORM NIS-2/NR-1/NW-t-OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl
- 1. Ovner FirstEnergy Corp. Date March 19, 2010 76 South Main St.. Akron, OH 44308 Sheet I of I
- 2. Parat Darts-Besse Nuclear Power Station Unit #1 5501 N. SR. 2. Oak H4arbor. OH 43449 3, Work Pertermed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR
*=O1 N5 01? 9. fletT-IhAr.. Ct:[ {5d4 Authorization No, 20 5501 N QR 2 OalTT-,h-r QIT 434AQ Exosratlon Date 07/17/10
- 4. Identification of Systems Hanger PSP-1-H15 Snubber SNC-201 Subsystorm 064-04
- 5. (a) Applicable Construction Code ANSI B31.1 1967 Edition Later Addende Code Case No (b) Applicable Edition ot Section XI Utiltzed for Repatre or Replacements 19 9.5 Edition 96 Addenda Code Case n/a (1) Design Responsibilities Firstenergy Corp, Lisega
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other identification/ Year Repaired ASME Name of Component Name of Manufacturer Sertal No. Board No. JurisdictionaeNo. Built Replaced or Code Replacement Stamped 3042 Hydraulic snubbr Lisega 61254101 N/A SNC-201 UNK Replaced No 3042 Hydraulic snubber Lisega 30900165/049 N/A SNC-201 2009 Replacement No
- 7. Description of Work Existing Lisega Snubber 61254/01 was replaced with a new like for like replacement Lisega snubber 30900165/049.
As left inspectionrVT-3 performed-SAT 5(a) Cont. ANSI R31.1 & MSS-sP58
- a. Tests Conducted: NHydrostaticNo Pneumatic No Nominal Operating Pressure No Other No Pressure N/A PSI Test Temperature NIA *F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdon (Itapplicable) N/A Set Pressure and Blowdovn Adjustments Made Using N/A at N/A NOTE: Supplemental sheets Inthe form of lists, sketches, or drawings may be used, provided (I) size Is 8 A X 11In. (2) information in items I through 6 on this aeport Is included on each sheet, and (30 each sheet is numbered and the number of sheets is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 173 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB.507o-5 FORM NIS-2INR-1INVR1-f-
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Tflomas M.Purdue ,certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XIof the ASME Code and to the National Board Inspection Code "NR" rules.
National Board Certificate of Authorization No. 20 to use the 'NR" stamp--pis 9 011710 Date L-i FENOC Signed Q.. . CERTIFICATE OF INSERVICE INSPECTION I_ Jacob Scholl holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and elnployed by HSB CT of Hartford. CT have inspected the work described inthis report on - ' -/ 0 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date V - 2"/C Signed V _ commissions 1V8 7'z =,WM / - ot0 t 3 2-CERTIFICATE OF COMPLIANCE 1, N/A certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12113/10 National Board Certificate ofAuthorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.C, CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHI-O , and employed by HSB CT of Hartford, CT have Inspected the repair, modification or replacement described inthis report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xi of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described In this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected wth this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 174 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-6 ,-1, ' FORM NIS-2/NR-1/NVRF'I OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FrstEnergy Corp. Date 03/23/2010 76 South Main St.. Akron. OH 44308 Sheet I of I
- 2. Plant Davis-Besse Nuclear Power Station Unit /T#
200327503 5501 N. SR. 2. Oak Harbor. OH 43449 200327503 new,OMnCJssPa.ON.K0,N No.Wk5
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng
,;Iz1l NY It3 r)
(t.l'o N14A0 05 Authortzation No. 20 Addr*= Expiration Date 07/17/10
- 4. Identification of Systems "Hanger EBB-I-SRI, MAIN STEAM, Subsys DB-SUB083-01
- 5. (a) Applicable Construction Code ANSI B31.1 1967 Edition Later Addenda Code Case N/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case NIA (c) Design Responsibilities Firstenergy Cori, Grinnell
- 6. tdentificalion of Comoonents Renaired or Reolaced end Reotacement Comeonents Manufacturer's National Other Identiftation/ Year I Repaired ASME Name of Component Name of Manufacturer Sedal No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped
.4"Hydraulic Snubber OrinneoJ 24083 N/A SNC220 UNK Replaced No
-4" Hydraulic Snubber Grinnell 12445 N/A SNC220 2010 Replacement No
- 7. Description of Work Existing Grinnell snubber 24083 was replaced with a Configuration A replacement Grinnell snubber 12445.
As left inspection, VT-3 performed SAT. 5(a) Cotnt. MSS-SP-58
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other NO Pressure N/A psa Test Temperature N/A F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 %X 11 in. (2) Information in items 1 through 6 on this retort is included on each sheet, and (30 each sheet is numbered and the number of sheets is recorded at the toe of this form.
16 RFO Inservice Inspection Summary Page. 175 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 (3.-0070.6 FORM NIS-2/NR-1INVR'V"
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue , certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'NR" rules.
National Boad Certificate of Authorization No. 20 to use the "NR' stamp e . 0/17/10 Date 5 l31,o Signed Q.o. CERTIFICATE OF INSERVICE INSPECTION 1, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of . OHIO- and employed by HSB CT ' of Hartford, CT have inspected the work described in this report on q-- - 10 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board-Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date -1'--f0 Signed 6,t Al99 Commissions qC1l [q " o ,,ft 0 CERTIFICATE OF COMPLIANCE I N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR' stamp expires 12/13/16 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed __.C, CERTIFICATE OF INSERViCE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHiO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code VR' and 'NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. DateI Signed Commissions
~S.S.00I00,~d(.,d OSOonto00(0).
SOd(0(0(000000.
,OdSoil
16 RFO Inservice Inspection Summary Page 176 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DS-0070-5 FORM NIS-2/NR-1/NV`R-1-OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XA
- 1. Owner Firstgnergy Corp. Data 03105/2010 76 Sautht Main St.. AkMronH O 44308
- Sh~eet Iof I
- 2. Plant Davis-Resse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449. 200327518
- 3. Work Performed by FirstEnergy Nuclear Operathing Co.
Type Code Stamp NR sam. 5501 N. SR. 2. Oak Harbor. 0O- 43449 Authorization No. 20 A!Jdr*$ Expiration Date. 07/17/10
- 4. Identification of Systems Hanger CCA-6-H6, CORE FLOOD SYSTEM, Subsys DB-SUB051-01
- 5. (a) Applicable Construction Code ANSI B31.1 1967 Edition Later Addenda Code Case N/A (b) Applicable Edition of Section XIUtilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N/A (c) Design Responsibilities Firstenergy Corp, Grinrnell
- 6. Iidentification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Buiit Replaced or Cods Replacement Stamped 2.5" HRdraulic Snubber Grinnell 10128 N/A SNC280 IJNK Replaced No 2.5" Hydraulic Snubber Grinnell 37500 N/A SNC280 2010 Replacement No
- 7. Description of Work Existing Grirrell snubber 10128 was replaced with a Configuration A replacement Orinnell snubber 37500.
As left inspection, VT-3. performed SAT. 5(a) Coat. MSS-SP-58
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure 1N/A psi Test Temperature N/A *1 Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Slowdown (If applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawiogs may be used, provided (1) size Is 8 %X 11 In. (2) Information In items 1 through 6 on thris report is included on each sheet, and (30 each sheet is numbered and the number ofsheets is recorded at the top of this form,
16 RFO Inservice Inspection Summary Page 177 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NlS-2/NR-1/?N4'lr Appfl Ma- OR~pod to-Dsý aan
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue certify that the statements made In this report are correct and the repair, modification, or replacement of the items described aboveconforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules.
National Board ertificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date ,5Z131(0 FENOC Signed Q.c. CERTIFICATE OF INSERVICE INSPECTION I, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on .3 -,S -L0 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed In accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date Date .*"Siged OO"* K jI~7 ,
-OSigned Commissions 9glA 1*,,,b-.O 4 ... fnn,n,.
f£ 1 ..Cope,0o / CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the 'NR" stamp expires 07/17/10 Date FENOC Signed Q.c. CERTIFICATE 6FINSERVICE INSPECTION 1, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report.. Furthermore, neilher-the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
~
5-,sped,, ~~ ~ ~ ~ ~ (NdntBar
ý Md ortd~
16 RFO Inservice Inspection Summary Page 178 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DO-OO0070.5 Lf.- 4 1JI0 FORM NIS-2/NR-1IN:'1fi--OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Date 03/22/2010 76 Scoth Main St., Akr*o, OH 44308 Sheot 1 of I
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2. Oak Harbor, OH 43449 200327526
- 3. Work Performed by FirstEnergyNuclear Operating Co. Type Code Stdmp N*R
;r(11 N.R In.t
. IT-arhk, n 411431,0 Authorization No. 20 Explratlon Date 07/17/10
- 4. Identifcation of Systema Hanger CCB-6-H{0, DECAY HBEAT, Subsys DB-SUB049-02
- 5. (a) Applicable ConstnJction Code ANSI 331.1 1967 Edition Later Addenda Code Case N/A (ib) Applicable Edition of Section XI Utilized for Repairs or Replacements 1g 95 Edttion 96 Addenda Code Case N/A (c) Design Responsibilitles Firstenerge Corp, OGrnnell
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturerfs National Other tdenttflcaltnnf Year Repaired ASME Name of Component Name of Manufacturer Serial No. Beard No. Judsdictional No. Built Replaced or Code Replacernent Stamped 2.5" tydraulic Snubber Grinnell 10163 N/A SNC288 UNK Replaced No 2.5" Hydraulic Seebber Grinnell 37501 N/A SNC289 2010 Replacement No
- 7. Description of Work Existing Grinnell snubber 10163 was replaced with a Configuration A mplacement Orinnetl snubber 37501, As left inspcctioofVT-3 performed SAT.
5(a) Cont. MSS-SP-58
- 8. Tests Conducted: Hydrostalic NO Pneumatic No Nominal Operating Pressure No Other No Pressure N/A psi Test Temperature NI/A 'F Pressure Rellte Valves:
Service N/A Size N/A Opening Pressure N/A Blowdowni(f applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplnrmental sheets in the form of lists, sketches, or drawings may be used, provided (1) saze is 8 Y. X 11in. (2) Information in items 1 through 6 on thin repor Inincluded en each shoat, and (30 each sheet Is numbered and the number oa sheetsIs recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 179 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NlIS-2INR-llftAfR.-I-
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M. Purdue , cerify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules.
National Board C rificate of Authorization No. 20 to use the 'NR" stamp ex ies ,07/17/10 Date ENOC Signed Q.c. CERTIFICATE OF INSERVICE INSPECTION I, Sacob Schoe. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of 01UO and employed by HSB CT of Hartford, CT have inspected the work described in this report on q" ;- 1 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this Inspection. Date - 20 Signed 4J A',* Commissions 1Ve79204A)81-61/t/2_ CERTIFICATE OF COMPLIANCE NIA certify that to the best of my knowledge and belief the statements made In this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12113/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed _ _ _ _ CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described In this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal Injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 180 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 oB-0070.5 FORM NIS-2/NR-1/NV-R OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp Date 03/15/2010 76 South Main St.. Akron, OH 44308 ,Sheet 1 of I
- 2. Plant Davis-B asseNuclear Power Slation Unit 5501 N. SR. 2, Oak Harbor, OH 43449
- 3. Work Performed by 'irstEperg, Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oak Harbor, Off 43449 Authorization No. 20 Exniration Date 07/17/10
- 4. Identilicatlon of Systems .Hanger CCB-6-H5, DECAY HEAT SYSTEM, Subsys DB-SUB049-02 S. (a) Applicable Construction Code ANSI B3 1.1 t 167 Edition Later Addenda Code Case N/A (b) Applicable Edition of Seclion AIUtilizedfor Repairs or Replacements 19 95 Edition 96 Addenda Code Case NIA (c) Design Responsibilities Ffrttenergy Corp, Grinnell 6 Identification of Components Renaired or Replaced and Replacement CompOnents Ma"ufatlurer's National Other Identlfieation/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No, Jurisdictional No. Built Replaced or Code Replacement Stamped 2.5" Hydraulic Snubber Grinnell 117911 NIA SNC284 UNK Replaced No 2.5" Hydraulic Snubber Grinmetl - 37616 N/A SNC284 2010 Replacement No
- 7. Description of Work Existing Grinnell snubbetr 17911 was replaced with a Configuralion A replacement Gritleell snubber 37616.
As left inspectioni/%T-3 performed SAT. S(a) Cont. MSS-SP-58
- a. Tests Conducted: Hydrostatic No PneumaticnNo NomnlnaI Operating Pressure NO Other No Pressure N/A pal Test Temperalure N/A 'F Pressure Relief Valves:
Servica N/A Size N/A Opening Pressure N/A Btodeown (Ofappllcable) N/A Set Pressure and Bladoswn Adjustments Made Using NIA at NIA NOTE: I rhie Sapplemenlalsheetsanhe lormOf r.ercr is indtreric cc Rs eheet andt lists, sketchen, rntt cuch orcdrawings thu beused, cheet je numbehred undmay providedt(t) size Is 0*at' theItt ase mheutur oncheats is renorded in.St(2) thisInlormatonn torm. Ilteas I tthrough6on is I, and 1311each sheet is numbered and the number of sheets is recorded at the ton of this form.
16 RFO Inservice Inspection Summary Page 181 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-INAf"- S, REMARKS CEMRTIFICATE OF COMPLIANCE I, Thomas M, Purdue , certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and-to the National Board Inspection Code 'NR" rules. National Board ertili ate of Autorization No. 20 to use the "NR" stam l 07/17/10 Date ~ OFENOC Signer_ Z;44&__2___C 1'4C06 SCt'LC CERTIFICATE OF INSERVICE INSPECTION I, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on ,9 / 0 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xi of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 3-3C'-2O Signed Commissions MS 7q1et.,AAi/ efgq3Z CERTIFICATE OF COMPLIANCE I, N/A certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of. the ASME Code and to the National Board Inspection Code VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the 'VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.C. CERTIFICATE OF INSER VICE INSPECTION 1, NIA holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHtO and employed by HIS1 CT of Hanford, CT have inspected the repair, modification or replacement described in this report on and state that to the best-of my knowledge and belief, this repair, modification.or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 182 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 . ý 5 /( L FORM NIS-2/NR-1//NV41--OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1., Owner FlirtEnergy Corp. Date 03/22/2010 Q ett. rlisf.. 0+ AtL-,, UTJ 44-nQ Sheet 1 of I 0 a n .. ran.
- 2. Plant Davis-Besse Nuclear Power Station Unit #14 5501 N. SR 2, Oak Harbor, OH 43449 200350927 tfepýa sO.5,, P.O.N0. It,.0
- 3. Work Performed by .FhistEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No. 20 Expiration Date 07/117/10
- 4. Identification of Systems Hanger CCA-4-H10, DECAY HEAT, Subsys DB-SUB049-02
- 5. (a) Applicable Construction Code ANSI B31.1 1967 Edition Later Addenda Code Case N/A (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N/A (e) Design Responsibilities Firstenerey Cor . Grrinell
- 6. Identification of ComponentsRepaired or Replaced and Replacement Components
" Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Reptaced or Code Replacement Stamped
.IS"Hydraulic Snubber Orinnell 11817 N/A SNC286 UNK Replaced No 1.5" Hydraulic Snubber Grinnell 37629 NIA SNC286 2010 Replacement No 7, Description of Work Existing Grinnell snubber I 1817 was replaced with a Configuration A replacement Grinnell onubber 37629.
As left inspection, VT-3 performed SAT. 5(a) Cont. MSS-SP-58
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A .psi Test Temperature N/A Pressure Relief Valves:
Servico N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A (r. .,..,4 at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 %X t in. (2) Information in items 1 through 6 on this report is included an each sheet, and (30 each sheet Is numbered and the number of sheets is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 183 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB.0070-5 FORM NIS-2/NR-I/NYR---t
- 9. REMARKS CERTIFICATE OF COMPLIANCE I, Thomas N4.Purdue , certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'NR" rules.
National Bo ad Cprtificate of Authorization No. 20 to use the 'NR' stampesex07/is/10 Date (0o-) FENOC Signed CERTIFICATE OF INSERVICE INSPECTION I, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on q-*_() and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed In accordance with Section XI of the ASME Code and the National Board Inspection Code "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date .*-i2-l0 Signed ,. 01 .'Q Commissions qqC1"f 14I6 OIL,(IieAoc 0 CERTIFICATE OF COMPLIANCE I N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section X1of the ASME Code and to the National Board Inspection Code "VR"and "NR" rules. National Board Certificate of Authorization No. 316 lo use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.c. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described In this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Bpard Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
- t~,eThtts).
aMoinon,,, *0) 00.))
16 RFO Inservice Inspection Summary Page 184 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
. FORM NIR-l REPORT OF REPAIR Z OR REPLACEMiENT E TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS
- 1. Work performed by: Welding Services Inc. 104770 2225 Skyland court, Norcross, GA 30071
- 2. Owner: FirstEnergy Nuclear Operating Company
.76 South Main, Akron, OH 3, Name, address and Identification of nuclear power plant Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449
- 4. System: Unit 1, RC System 5a. Items which required Repair or Replacement Activities Iden tlion ct Construction Code Activity No Tyeo oType of f..N9 Mfg, Mfg. alB.
Nanl8d .us. urd. Other o Yeart Sectionl Name / EditUoi Code Code Repair Item Name Serial No. No. No. Built OMDlon Addenda Case(s) Class Replace 620-0014- Asme 1 RPV 1-i South B& W S1,52 N-156 N/A N/A 1972 Ing/l 1968 N/A I Repair Core Flood Summer RC-RPV-WR-53-Y 1 1968 5b. Items Installed during Replacement Activities Identification Construction Code Installed or Name Type of Replaced Mfg. Mfg. Natil Bd. Jurlsd. Yea e Edition Code Code Item Sa item S tmN.Other ItmNo. Name Serial No. No. No. Builtt Section Division Addenda Case(s) Class Weld Overlay See Line 11 WSI N/A N/A N/A N/A 2010 ASMEXI 1995 / 1996 N-740-2 1
- 6. ASME Code Section XI applicable for Inservice Inspection: 1995 1996 N/A Sadde&) (Ceo,C-140
- 7. ASME Code Section XI used for repairs or replacements: 1995 1996 N-740-2 (e0"*)(-dera) (coieca1s)0 ASME III
- 8. Construction Code used for repairs or replacements: 1968 Summer 1968 N/A
£druaraiTnfearitv Associates Inc., San Jose. CA
- 9. Design Responsibilities: JUl cite
.. . . Sa ....Jo
.Inc e C .
... ........ Ine ,t Ass
16 RFO Inservice Inspection Summary Page 185 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 10, Tests conducted: hydrostatic E5 pneumatic El design pressure 1 pressure . psi Code Case(s) __ To be performedby owner
- 11. Description of work: Installed a Full Structural Weld Overlay (FSWOL) to Reactor nozzle to Pipe 1AW WSI Traveler 104770-TR-10S, Rev. 1 which incorporatsaDais-Besse Work Order Number 200327730. This implements a one time NRCaccepted repair plan lAW Relief Request RR-A33 and amended Code Case N-740-2.
- 12. Remarks: WSI NCR's 10-208 and 10-215 Initiated and closed during the performance of this repair, The following Types and Heats oF filler material were utilized: .
ER308 / 308L, SFA 5.9, Hr./Lot739058 /YT9160, ERNICr-3, SFA 5.14, Ht.NX7214DR, ERNICrFe-7A, SFA 5.14, Ht.NX74W8TW Note : Ultrasonic Examination conducted in accordance with ASME Section XI, Appendix VIII, 1995 Edition with 1996 Addenda. Stamping / Nameplate omitted per NBIC 5.7.2 para. b and Ohio code Chapter 4101:4-2-01 (A), (1). CERTIFICATE OF COMPLIANCE I, Ronald Aggen , certify that to the best of my knowledge and belief the statements in this report are correct and the repair or replacement activities described above conform to Section Xl of the ASNE Code and the NationalBoardInspection Code "NR" rules. National Board "R" Ceitificate ofAuthorizatiobn No. NR-69 to use the "NR" stamp expires November 6 2010 NR Certificate Holder Weldina Services Inr.. Date t_* Signed QA/QC Inspector a CERTIFICATE OF INSPECTION I, R.kiLF_ opI-T4 ,holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of 1(41o and employed by HSB-CT of Hartford, CT have Inspected the repair, modification or replacement described in this report on q- _ 1-10 - and state that to the best of my knowledge and belief, this repair, modification or replacement activity has been completed In accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules, By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning The work described In this report. Furthermore, neither the undersigned nor my employer shall be liable In any manner for any personal injury, property damage or a loss of any kind arising from or connected with this inspection. Date .11 -z.L Signed 4- 1" Commissions Ngqq.gA RlL'T t10ýý10 C_1 lot)
16 RFO Inservice Inspection Summary Page 186 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 FORM NR-I REPORT OF REPAIR 0 OR REPLACEM],NT El TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS 1.Work performed by: Welding Services Inc. 104770 2225 Skyland Court, Norcross, GA30071
- 2. Owner: FirstEnergy Nuclear Operating Company 76 South Main, Akron, OH
- 3. Name, address and Identification of nuclear power plant Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449
- 4. System: Unit 1, RC System 5a. Items which required Repair or Replacement Activities Identification Construction Code Activity Typ o Mf.Mg. cal d. Ju~s. Yar Section Name / I Addenda EI io!/ecttonCase(s)
Cd Cde Class Rai/ Replace No Itemof Type Name
*o IeNm MFg.
MItg. Serila era No.
- o. NailN.
Bd No. Jturisd No. No Otoer ter Year BuIlt Bit Division_____ Adden Code Code Replace Asme I RCP 1-1 B& W N/A N/A N/A N/A 1977 ilI/I 1971 N/A 1 Repair Suction to 1971 RC-MK-B-67 FW134B Summer 5b. Items Installed during Replacement Activities Identification Construction Code Instailed or Name / d Type of Replaced Mfg, Mig. Nail Bd. Jounsd, Year n Edition Code code Item SeItem N. Nm e. Name eniN. Serial No. N.No. No. No. Other Built Section/ Addenda oe Case(s) Cd Class Division a Case-s) C WeldOverlay See line 11 WSI_ N/ N/A NIA N/A 2010 ASMVE XI 1995 /1996 N4-740-2 1
- 6. ASME Code Section XI applicabe for InservIce inspection: 1995 1996 N/A
- 7. ASME Code Section XI used for repairs or replacemenl s: 1995 1996 N-740-2 5e55o) (ad~ed,)
ASME III
- 8. Construction Code used for repairs or replacements: 1971 Summer 1971 N/A
- 9. Design Responsibilities: Structural Intearitv Associates Inc.. San Jose. CA
16 RFO Inservice Inspection Summary Page 187 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
- 10. Tests conducted; hydrostatic F- pneumatic UJ design pressure C pressure _ psi Code Case(s)
To be performed by owner
- 11. Description of work: Installed a Full Structural Weld Overlay ,FSWOL) to Suction nozzle (I-1) to pipe IAW WSI Traveler 104770-TR-i02, Rev. I and Rev.2 which Incorporates Davis-Besse Work Order Number 200327738. This Implements a one time NRC accepted repair plan IAW Relief Request RR-A33 and amended Code Case N-740-2.
1.2. Remarks
WSI NCR's 10-216 and 10-313 initiated and closed during th'e performance of this repair. Note : Ultrasonic Examination conducted In accordance with ASME Section XI. Aopendix VIII. 1995 Edition with 1996 Addenda. The following Types and Heats of filler material were utilized: ER308 / 308L, SFA 5.9, Ht./Lot 739058 / YT9160, ERNiCr-3, SFA 5.14, Ht.NX7214DR, ERN[CrFe-7A, SFA 5.14, Ht.NX78W4TK Stamping I Nameplate omitted per NBIC 5.7.2 para. b and Ohio code Chapter 4101:4-2-01 (A), (1). CERTIFICATE OF COMPLIANCE I, Ronald Aggen , certify that to the best of my knowledge and belief the statements In this report are correct and the repair or replacement activities described above conform to Section XI of the ASME Code and the NationalBoiad Inspection Code "NR" rules. National Board "R" Certificate ofAuthorization No. NR-69 to use the "NR" stamp expires November 6 2010 NR Certificate Holder Welding Services Inc, Date, t Signed L OC Supervisor W0, CERTIFICATE OF INSPECTION I, t)l£.u C WkI.tO&vl4. , holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of 01+0O and employed by HSB-CT of Hartford, CT have Inspected the repair, modification or replacement described In this report on qf -1, -w and state that to the best of my knowledge and belief, this repair, modification or replacement activity has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. 5y signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning The work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or a loss of any kind arising from or connected with this Inspection. Date / Signed 1 -v764 Commissions r i t
- roK oeod, r. Ad,,.,rI f~to.w WO.) I
16 RFO Inservice Inspection Summary Page 188 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 S' FORM NR-rREIPORT OF REPAIR Dq TO WIICCLEAR COMPlONENTS AND) SYSTEMS IN NULCLEAR POWER PLANTS OR REPLACEMENT []
- 1. Work performed by: Welding Services Inc. , 104770 2225 Skyland Court Norcross, GA30071
- 2. Owner: FirstEnergy Nuclear Operating Company 76 South Main, Akron, OH
- 3. Name, address and identification of nuclear power plant Oavls-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449
- 4. System: Unit 1, RC System 5a. Items which required Repair or Replacement Activities Identification Construction Code Activaty No Type of Mfg, MNfg. NaqPd. Juiad. Year Name'/ Edition / Code Code Repair /
Item Name Serial No. No. No. other Built Section Division I Addenda Case(s) Class Replace 1 RCP 1-1 B&W N/A N/A N/A N/A 1973 USAS 131.7 N/A 1 Repair 1-V& 1-Discharge ,,VI RC-MK-a-59 SWI43B 5b, Items installed during Replacement Activities Identification Construction Code Installed or Name / Type of Replaced Mfg. Mfg. Nati Sd. ]urlsd. Other Yeart Edition Cod Code Item Sa Item No. Name Serial No. No. No. Built Secion Addenda Case(s) Class Weld Overlay .See line 11 WSI N/A N/A N/A 1I1A 2010 ASME XI 1995 / 1996 N-740-2 I
- 6. ASME Code Section XI applicable for inservice inspection: 1995 1996 N/A
- 7. ASME Code Section XI used for repairs or replacements: 1995 1996 N-740-2 ASME Ill
- 8. Construction Code used for repairs or replacements: 1971 Summer 1971 N/A ruura{ IntarianJoeC (Addo(Io
- 9. Design Responsibilities: Structural Inteciritv Associates Inc.. San lose, CA
16 RFO Inservice Inspection Summary Page 189 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St.; Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
- 10. Tests conducted: hydrostatic [3 pneumatic E] design pressure C pressure __psi Code Case(s)_
To be performedby owner 1 11. Description of work: Installed a Optimized Weld Overlay (OWOL) to discharge nozzle (1-1) to pipe IAW WSI Traveler 104770-TR-103, Rev. 1 which Incorporates Davis-Resse Work Order Number 200327738. This Implements a one time NRC accepted repair plan IAW Relief Request RR-A32.and amended Code Case N-740-2.
- 12. Remarks: WSI NCR's 10-207, 10-311 and 10-315 Initiated and closed durng the performance of this repair.
Note : Ultrasonic Examination conducted In accordance with ASME Sectlon XI, Appendix VIII, 1995 Edition with 1996 Addenda. The following Types and Heats of filler material were utilized: ER308 I308L, SFA 5.9, Ht./Lot 739058 / YT9160, ERNICr-3, SFA 5.14, Ht.NX7214DR, ERNiCrFe-7A, SFA 5.14, Ht.NX74W8TW Stamping / Nameplate omitted per NBIC 5.7.2 pare, b and Ohio code Chapter 4101:4-2-01 (A), (1). CERTIFICATE OF COMPLIANCE I, Ronald Aggen , certify that to the best of my knowledge and belief the statements in this report are correct and the repair or replacement activities described above conform to Secton Xt of the ASME Code and the NationalBoardInspection Code' NR" rules. National Board "R" CertificateofAuthorization No. NR-69 to use the "NR" stamp expires November 6 2010 NR Certificate Holder Welding Services Inc. Date 1-EIL7-IO0 Signed 7zýý Q QC Supervisor CERTIFICATE OF INSPECTION I, "3io(6c Ir*. -i , holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of 04Io - and employed by HSB-CT of Hartford, CT have inspected the repair, modification or replacement described in this report on q.-l- iC and state that to the best of my knowledge and belief, this repair, modification or replacement activity has been completed in accordance with Section X1 of the ASME Code and the National Board Inspection Code "NR" rules. By signingthis certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning The work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or a loss of any kind arising from or connected with this inspection. Date _________ Signed ".,. Commissions 9 9 3-*/00io(stPDO il o
16 RFO Inservice Inspection Summary Page 190 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 I01l6c"Ju2 FORM NR-1 REPORT OF REPAIR [ OR REPLACEMENT E TO NUCLEAR COM]PONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS
- 1. Work performed by: Welding Services Inc. 104770 2225 Skyland Court,. Norcross, GA 30071
- 2. Owner: FirstEnergy Nuclear Operating Company 76 South Main, Akron, OH
- 3. Name, address and identification of nuclear power plant Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449
- 4. System: . Unit 1, RC System Sa. Items which required Repair or Replacement Activities Identification Construction Code aActvity NO Type of Mfg. Mfg. Nanlad. ulaisd. Ot Year Name// Edition / Code code Repair !
Item Name Serial No, No. No. Built Dection/ Addenda Case(s) (lass Replace Division eda css) as Rple Asme I RCP 1-2 B& W N/A N/A N/A N/A 1977 111/1 1971 N/A I Repair Suction to 1971 RC-MK-A-67 FW1059 Summer 5b. Items Installed during Replacement Activities Identification Construction Code Installed or SeN' d Type of Replaced Mfg. Mfg. Nail Ed. suresd.Other Yer Edition / Code Code itear~ o Item 5a Item No. Name Serial No. No. No. Built Division Addenda Case(s) Oass Weld Overlay See line 11 WSI N/A N/A N/A TNA 2010 ASME XI 1995/ 1996 N-740-2 1
- 6. ASME Code Section XI applicable for Inservice inspection: 1995 1996 N/A
- 7. ASME Code Section XI used for repairs or replacements: 1995 1996 N-740-2 (Odbo) (.*M.)06 ((006009(Q)
ASME III
- 8. Construction Code used for repairs or replacements: 1971 Summer 1971 N/A 10060 (6*Odd".)4 CoolSW))
- 9. Design Responsibilities: ictural Integrity Associates Inc., San lose, ýCA
16 RFO Inservice Inspection Summary Page 191 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio44308 Davis-Besse.Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 10, Tests conducted: hydrostatic [J pneumatic E] design pressure . E pressure __ psi Code Case(s) To be performedby owner
- 11. Description of work: Installed a Full Structural Weld Overlay (FSWOL) to Suction no2Zze (1-2) to pipe IAW WSI Traveler 104770-TR-102, Rev. I and Rev.2 which incorporates Davis-Besse Work Order Number 200327739. This Implements a one time NRC accepted repair plan lAW Relief Request RR-A33 and amended Code Case N-740-2.
- 12. Remarks: WSI NCR's 10-216 and 10-314 Initiated arnd closed during the performance of this repair.
Note : Ultrasonic Examination conducted inaccordance with ASIVE Section XI, Appendix VHI, 1995 Edition with 1996 Addenda. The followingTypes and Heats of filler material were utilized: ER308 / 308L, SSA5.9,m-It/Lot 739058/ YT9160, ERNICr-3, SA 5.14, Ht.NX7214dR, ERNICrFe-7A, S0A 5.14, H-2 t.NX78WA TK Stamping / Nameplate omitted per NBIC 5.7.2 pare, band Ohio cede Chapter 4101:4-2-01 (A), (1). CERTIFICATE OF COMPLIANCE I, Ronald Aggen . , certify that to the best of my knowledge and belief the statements in this report are correct and the repair or replacement activities described above conform to Section XI of the ASME Code and the ANational BoardInspect/on Code"NR" rules, National Board "R" CertificateofAuthorization No. NR-69 to use the "NR" stamp expires November 6 2010 NR Certificate Holder Welding Services Inc. Date +- - Signed QC_0__ Suervisor CERTIFICATE OF INSPECTION I, rA C E_ zrl4 , holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of 0141o1 and employed by HSB-CT of Hartford, CT have Inspected the repair, modification or replacement described in this report on 10 and state that to the best of my knowledge and belief, this repair, modification or replacement activity has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules, By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning The work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal inJuiy, property damage or a loss of any kind arising from or connected with this inspection. Data 'iI i-loQ__ Signed .Commissions 9'151 A 4L OAPfv i~/
16 RFO Inservice Inspection Summary Page 192 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 FORM NR-1 REPORT OF REPAIR [] OR REPLACEMENT El TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS
- 1. Work performed by: Welding Services Inc. 104770 2225 Skyland Court, Norcross, GA 30071
- 2. Owner: FirstEnergy Nuclear Operating Company 76 South Main, Akron, OH
- 3. Name, address and identification of nuclear power plant Davls-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449
- 4. System: Unit 1, RC System 5a. Items which required Repair or Replacement Activities Identification Construction Code Activity Type of MNg. Mfg. Nal Bd. Jurlsd. Other Year e Editin / Code Code Repair No Item Name Serial No. No. No. Built Section! Addenda Case(s) Class Replace I RCP 1-2 B&W N/A N/A N/A NIA 1973 USAS 131.7 N/A 1 Repair 1-V& 1-Discharge VI RC-MK-B-44 SW69B Sb. Items installed during Replacement Activities Identification Construction Code Installed orName Type or Replaced Mfg, Mfg. Nail Bd. Jurisd. Other Year e Edition Code Code Item 5a Item No, Name Serial No. No. No. Built Division Addenda Case(s) Class Weld Overlay See line 11 WSI N/A N/A N/A N/A 2010 ASMEXI 1995 / 1996 N-740-2 1
- 6. ASNE Code Section XI applicable for inservice inspecti!on: 1995 1996 N/A-
- 7. ASNE Code Section XI used for repairs or replacement s: 1995 1996 N-740-2 ASME III
- 8. Construction Code used for repairs or replacements: 1971 Summer 1971 N/A
- 9. Design Responsibilities: Structural Intearitv Associates Inc., San Jose. CA
16 RFO Inservice Inspection Summary Page 193 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
- 10. Tests conducted: hydrostatic [I pneumatic [] design pressure pressure __ psl Code Case(s) __
To be performed by owner
- 11. Description of work: Installed a Optimized Weld Overlay (OWOL) to discharge nozzle (1-2) to pipe JAW WSI Traveler 104770-TR-103, Rev. I which Incorporates Davis-Besse Work Order Number 200327739. This Implements a one time NRC accepted repair plan 1AW Relief Request RR-A32 and amended Code Case N-740-2.
- 12. Remarks: WSI NCR's 10-312 Initiated and closed during the performance of this repair.
Note : Ultrasonic Examination conducted in accordance with ASME Section XI, Appendix VIII, 1995 Edition with 1996 Addenda. The following Types and Heats of filler material were utilized: ER308 / 308L, SFA 5.9, Ht.ILat 739058 / YT9160, ERNICr-3, SFA 5.14, Ht.NX7214DR, ERNiCrFe-7A, SFA 5.14, Ht.NX74W8TW Stamping / Nameplate omitted per NBIC 5.7.2 para. b and Ohio code Chapter 4101:1-2-01 (A), (1). CERTIFICATE OF COMPLIANCE I, Ronald Aggen certify that to the best of my knowledge and belief the statements in this report are correct and the repair or replacement activities described above conform to Section XI of the ASME Code and the NationalBoardInspection Code"NR" rules. National Board "R' Certificate ofAuthorlzation No, NR-69 to use the "NR" stamp expires November 6 2010 NR Certificate Holder WeldIng Services Inc. Date 4-1,4c- 10 Signed _____________ Q-Q CERTIF ICATE OF INSPECTION I, Pz t.- I'o(-ri4 ,holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of 011,- and employed by HSB-CT of Hartford, CT have inspected the repair, modification or replacement described in this report on gjjlqttO and state that to the best of my knowledge and belief, this repair, modification or replacement activity has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning The work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or a loss of any kind arising from or connected with this inspection. 1 Date q-lq-tO Signed e,
, commissions C01W1 flli f 4 T O()1-ýA ,'illeo
.6-IB -tj W~Ldbsd N.)
16 RFO Inservice Inspection Summary Page 194 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 FORM NR-1 REPORT OF REPAIR [ OR REPLACEMENT E] TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS
- 1. Work performed by: Weidirno g~rvcee Tnec.7 es Inc.
L . , , .U *
- 2. Owner: flt nergy Nuclear Operating Compahy 76 South Main, Akron, OH
- 3. Name, address and Identification of nuclear power plant Davis-Besse Nuclear Power Station -
5501 North State Route 2 Oak Harbor, OH 43449
- 4. System: . . . Unit 1, RC System 5a. Items which required Repair or Replacement Activities
- Identification - Construction Code ] Activity No . Type of I Mfg. Mfg. Natl ad. Jurisd. Year Name1 Edition Ccode Code Repair]e*
Item.. .. Name*.. Serial No.m. No. No. Nuit Ot. Buit DMlon 5eclon Addenda.. Case(s)"
.. Cass
.. Repiace lac
* " ~ ~Asm e ' - " . Repair.
I RCS 1-2 B&W. N/A N/A N/A N/A 1972 111/1 1971. N/A' Repair Cold Leg Drain . ,. to 1971 , ,.. RC-40-CCA-18 ieN9 Summer 5b. Items Installed during Replacement Activities Identification " Construction Code Installed or Name / Type of Replaced Mfg. Mfg. Nall Rd. Jurisd. Other Year Edition Cods Code Item SaItem No. Name Serial No. No. No. Built Section Addenda Case(s) Class Division Weld Overlay See line 11 WSI N/A N/A. NA NIA 2010 ASMEXI 1995 / 1996 N-740-2 I L ~L __
- 6. ASME Code Section XI applicable for inservice inspection: 1995 1996 N/A.
WW.) cass5 (CMod
- 7. ASME Code Section XI used for repairs or replacements: 1995 1996 N-740-2 ASME III
- 8. Construction Code used for repairs or replacements: 1971 Summer 1971 N/A
(,Aoo)
- 9. Design Responsibflities: uctural Integrity Assodates Inc., San Jose, CA
16 RFO Inservice Inspection Summary Page 195 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
- 10. Tests conducted: hydrostatic [] pneumatic [3 design pressure- E pressure _____"_psi Code Case(s)
To be peformed by owner 1I, Description of work: Installed a Full Structural Weld Overlay (FSWOL) to Cold Leg Drain nozzle (1-2) to elbow JAW . WSI Traveler 104770-TR-104, Rev. 1 and 104770-TR-106, Rev.0, which incorporates Davis-Besse Work Order Number 200327739. This Implements a one time NRC accepted repair plan 1AW Relief Request RR-A33 and amended Code Case N-740-2.
- 12. Remarks: WSI NCR's 10-205, 10-218 and 10-220 Initiated and dosed during the performance of this repair.
The following Types and Heats of filler material were utilized; ERNiCrFe-7A, SFA 5.14, Ht.NX75WITK Note : Ultrasonic Examination conducted In accordance with ASNE Section XI; Appendix VIII/,1995 Edition with 1996 Addenda. Stamping / Nameplate omitted per NBIC 5.7.2 para. b and Ohio code Chapter 4101:4-2-01 (A), (1). CERTLFICATE OF COMPLIANCE I, Robert Norman , certify that to the best of my knowledge and belief the statements in this report are correct and the repair or replacement activities described above conform to Section XI of the ASME Code and the NationalBoard Inspection Code"NR" rules. National Board "R" Cen'ifcateofAuthorization No. NR-69 to use the "NR" stamp expires November 6 2010 NR Certificate Holder Welding Services Inc. Date"ý/J /I/ Signed . QC Supervisor CERTIFICATE OF INSPECTION i, -T7i*'o, 5**Lt_ , holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of 0,)/fi - and employed by HSB-CT of Hartford, CT have inspected the repair, modification or replacement described in this report on /-/-1/. /0 and state that to the best of my knowledge and belief, this repair, modification or replacement activity has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty; expressed or Implied, concerning The work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal Injury, property damage or a loss of any kind arising from or connected with this Inspection. Date /-/112?16' Signed Commissions 2i vP 4/ 52-
16 RFO Inservice Inspection Summary Page 196 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 FORM NR-1 REPORT OF REPAIR Z OR REPLACEMENT E] TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS
- 1. Work performed by: Weldin1Services Inc. 104770 2225 Skyland Court, Norcross, GA 30071
- 2. Owner: FirstEnergy Nuclear Operating Company 76 South Maln, Akron, OH
- 3. Name, address and Identification of nuclear power plant Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449
- 4. System:. ..... Unit 1, RCSystem 5a. Items which required Repair or Replacement Activities Identification Construction Code Activity No TNat Bd. 2arisd, Year Name / Edition / Code Code Repair/
Type of N M efg Mfg. i NO. . N. Btuer Section/ A Item Name Seral No. No. No. Built Division Addenda Case(s) Class Replace Asme 1 RCP 2-1 B& W N/A N/A N/A N/A 1977 111/1 1971 N/A . Repair Suction to 1971 RC-MK-A-67 FWI05A Summer 5b. Items installed during Replacement Activities Identification Construction Code Installed or Name Type of Replaced Mfg. Mfg. Nail ed. Jurlsd. Other Year e / Edition Code Code Item 5a Item No. Name Seuial No. No. No. Built Decion Addenda Case(s) Class Division Weid Overlay See line 11 IASI N/A N/A N/A N/A 2010 ASME XI 1995 /1995 N-740-2 1
- 6. ASME Code Section XI applicable for Inservice inspectii on: 1995 1996 N/A
- 7. ASME Code Section XI used for repairs or replacement s: 1995 1996 N-740-2 ASME III
- 8. Construction Code used for repairs or replacements: 1971 Summer 1971 N/A (code ý00
- 9. Design Responsibilities: Structural Inteqrity Associates Inc., San Jose, CA
16 RFO Inservice Inspection Summary Page 197 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
- 10. Tests conducted: hydrostatic El 'pneumatic El design pressure E pressure __ psi Code Case(s) __
?"obe performed by owner
- 11. Description of work: Installed a Full Structural Weld Overlay (FSWOL) to Suction nozzle (2-1) to pipe LAW WSI Traveler 104770-TR-102, Rev. 1 which incorporates Davis-Besse Work Order Number 200327740. This implements a one time NRC accepted repair plan IAW Relief Request RR-A33 and amended Code Case N-740-2.
- 12. Remarks: WSI NCR's 10-204, 10-206, 10-211 and 10-142 initiated and closed during the performance of this repair.
Note : Ultrasonlc Examination conducted in accordance with ASME Section XI, Appendix VIII, 1995 Edition with 1996 Addenda. The following Types and Heats of filler material were utilized: ER308 / 308L, SFA 5.9, Ht./Lot 739058 / YT9160, ERNiCr-3, SFA 5.14, Ht.NX7214DR, ERNICrFe-7A, SFA 5.14, Ht.NX78W4TK Stamping / Nameplate omitted per NBIC 5.7.2 para. b and Ohio code Chapter 4101:4-2-01 (A), (1). CERTIFICATE OF COMPLIANCE I, Robert Norman , certify that to the best of my knowledge and belief the statements in this report are correct and the repair or replacement activities described above conform to Section XI of the ASME Code and the Alational BoardInspection Code "NR" rules. National Board "R" CertificateofAuthorizatfon No. NR-69 to use the "NR" stamp expires November 6 2010 NR Certificate Holder Welding Services Inc. 1 DatWd7'd/ 6 Signed CQC Supervisor CERTIFICATE OF INSPECTION I, -A Cog* 504oLi- , holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of 04 I and employed by HSB-CT of Hartford, CT have inspected the repair, modification or replacement described in this report on o?/- /0 and state that to the best of my knowledge and belief, this repair, modification or replacement activity has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning The work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injurj, property damage or a loss of any kind arising from or connected with this Inspection. Date q. ?- Zo /o Signed e.4 Commissions A-'7. t'Ave/- f2'
16 RFO Inservice Inspection Summary Page 198 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
. FORM NR-1 REPORT OF REPAIR Z OR REPLACEMENT E]
TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS
- 1. Work performed by: Weldng Services Inc. .104770
. . .. P ....
2225 SkylaIhd Court, Norcross, GA 30071
- 2. Owner: FirstEnergiy Nuclear Operating Company
.76 South Main, Akron, OH 3, Name, address and identification of nuclear power plant Davis-Besse Nuclear Power Station
.. 5501 North State Route 2 Oak Harbor, OH 43449
- 4. System: . Unit 1, RC System 5a. Items which required Repair or Replacement Activities Identification construction Code _ Activit No Type .pf. MNig. Mfg. Natl ad. Judsd. o er Name/ Edition / Code Code Repair./
Item Name Serial No. No. No. Built.- Sctlon Adde Case(s) Class Replace Asmo 1 RCS 2-1 .: B&W N/A N/A N/A N/A 1972 111/1 1971 N/A Repair Cold Leg Drain ' to 1971 RC-40-CCA-1a FW25 Summer Sb. Items installed during Replacement Activities Identification Construction Code Installed or Name Type of Replaced Mfg. Mfg. Natl Bd. Jurisd. Other' Year Nei Editon Coda Coda Item SaItem No. Name Serial No. No. No. *Built Division1 Addenda Case(s) Class Weld Overlay See line 11 WSI N/A N/A N/A N/A 2010 ASME XT 1995/ 1996 N-740-2 1 11Ž __mE
- 6. ASME Cod6 Section ,i applicable for Inservice inspecti,on: 1995 1996 N/A (W) [(06W.)
- 7. ASME Code Section XI used for repairs or replacement s: 1995 1996 N-740-2 ASME III
- 8. Construction Code used for repairs or replacements: 1971 Summer 1971 NIA (C-leC-4))
- 9. Design Responsibilities: Structural Integrity Associates Inc.,I San Jose, CA
16 RFO Inservice Inspection Summary Page 199 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
- 10. Tests conducted: hydrostatic E- pneumatic E] design pressure 'E pressure
- psi Code Case(is)
To be performedby owner i1. Description of work: Installed a Full Structural Weld Overlay (FSWOL) to Cold Leg Drain nozzle (2-1) to elbow IAW WSI Traveler 104770-TR-i04, Rev. 1, which inrcorýorates Davis-Besse Work Order Number 200327740. This Implements a one time NRC accepted repair plan IAW Relief Request RR-A33 and amended Code Case N-740-2.
- 12. Remarks: The following Types and Heats of filler material were utilized:
ER308 / 308L, SFA 5.9, Hr./Lot 734815 / XT8659, ERNiCr-3, SFA 5.14, Ht.NX6764DR, ERNICrFe-7A, SFA 5.14, Ht.NX75WlTK Note: Ultrasonic Examination conducted in accordance with ASME Section XI, Appendix VIII, 1995 Edition with 1996 Addenda. Stamping ] Nameplate omitted per NBIC 5.7.2 para. b and Ohio code Chapter 4101:4-2-01 (A), (1). CERTIFICATE OF COMPLIANCE I, Robert Norman , certify that to the best of my knowledge and belief the statements In this report are correct and the repair or replacement activities described above conform to Section XI of the ASME Code and the NationalBoardInspection Code "NR" rules, National Board "R" CertificateofAuthorization No, NR-69 to use the "NR" stamp expires November 6 2010 NR Certificate Holder Welding Services Inc. Date / Signed
- QC Supervisor CERTIFICATE 01F INSPECTION I, -7T4eoB 5 Ct/1. 1 , holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of o4i/o and employed by HSB-CT of Hartford, CT have inspected the repair, modification or replacement described In this report on q- 6'-2o(o and state that to the best of my knowledge and belief, this repair, modification or replacement activity has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules, By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning The work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal Injury, property damage or a loss of any kind arising from or connected with this Inspection.
Date 6-I-* 2010
- Signed (9 -1,,4W Commlssions A)9r' g., /tA)g,. 6,0532-
16 RFO Inservice Inspection Summary' Page 200 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 FORM NR-1 REPORT OF REPAIR 0 OR REPLACEMENT nl TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS
- 1. Work performed by: Welding.~ *Services
- ?ad, inc.
. ..'. 104770 o 5,ob.
.2225 Skyland Court, Norcross, GA30071
- 2. Owner: FirstEnergytuclsar Oeating Company 76 South Main, Akron, OH
. ' ) . ..
- 3. Name, address and Identification of nuclear power plant Davis-Besse Nuclear Power Station
. .5501 North State Route 2 Oak Harbor, OH 43449
- 4. System: . ,. Unit 1, RC System 5a. Items which required Repair or Replacement Activities
.. ... . Identification Construction Code Activity Na Type of Mfg. Mfg. Natl Dd. Jurlsd. Omer Year secton / Edition I Code code Repair /
0 Item Name Serial No. No. No.. Built Division Addnda Cases) Class Replace I RCP 2-1 B&W N/A N/A N/A N/A 1973 USAS B31.7. N/A s Repair
.. .. . . 1-V& I-Discharge VI
- RC-MK-B:61 SW69A 5b. Items Installed during Replacement Activities Identification Construction Code Installed or Name Edition Code Code Type of Replaced Mfg. Mfg. Nal Bad. Jurlsd. Other Year Section / Addenda Case~s) coass Item SaItem No. Name Serial No. No. No. Built Division Weld Overlay See line 11 WSJ N/A N/A N/A N/A 2010 ASMEXI 1995 1996 N-740-2 I
- 6. ASME Code Section XI applicable for Inservice Inspection: 1995 1996 N/A (arn.) . - . (eCa~eC))
- 7. AS.E Code Section Xi used for mpair or replacements: 1995 1996 N-740-2 ASME III
- 8. Construction Code used for repairs or replacements: 1971 Summer 1971 N/A
- 9. Design Responsibilities: Stnictural Integrity Associates Inc., San lose, CA
16 RFO Inservice Inspection Summary Page 201 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
- 10. Tests conducted: hydrostatic [0 pneumatic El design pressure pressure psi Code Case(ss) n To be performedby owner 11, Description of work: Installed a Optimized Weld Overlay (owo to discharge nozzle (2-1) to pipe lAW WSI Traveler 104770-TR-103, Rev. 1 which incorporates Davis-Besse .Work Order Number 200327740. This Implements a one time NRC accepted repair nian LAWRelief Reauest RR-A32 and amended Code Case N-740-2.
- 12. Remarks: Note : Ultrasonic Examination conducted inaccordance with ASMESection X1,Appendix VIII, 1995 Edition with 1996 Addenda.
The followina Tvoes and Heats of filler material were utilized: . ER308 / 308L, SFA 5.9, Ht,/Lot 739058 / YT9160, ERNiCr-3, SFA 5.14, Ht.NX7214DR, ERNiCrFe-7A, SFA 5.14, Ht.NX74W8TW Stamping / Nameplate omitted per NBIC 5.7.2 para. b and Ohio code Chapter 4101:4-2-01 (A), (1). CERTIFICATE OF COMPLIANCE I, Robert Norman , certify that to the best of my knowledge and belief the statements in this report are correct and the repair or replacement activities described above conform to Section XI of the ASME Code and the National $oardfInspection Code"NR" rules. National Board "R" Certificateof Author/zation No. NR-69 to use the "NR" stamp expires November 6 2010 NR Certificate Holder . Welding Services Inc, Date 2_1-____ Signed QC Supervisor CERTIFICATE OF INSPECTION I, J-I7 CO6 Sc,-C! L , holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of cl/It1O and employed by HSB-CT of Hartford, CT have inspected the repair, modification or replacement described In this report on z- o0 and state that to the best of my knowledge and belief, this repair, modification or replacement activity has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning The work described in this report. Furthermore, neither the undersigned nor my employer shall.be liable in any manner for any personal injury, property damage or a loss of any kind arising from or connected with this inspection. Date 4.-.ý - 20 / 0 Signed Commissions 1(6 7f204AJt? 4/l 'I_
16 RFO Inservice Inspection Summary Page 202 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 FORM NR-1 REPORT OF REPAIR Z OR REPLACEMENT [] TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS
- 1. Workperformed by: Welding Servlces Inc. 104770 2225 Skyland Court, Norcross, GA 30071
- 2. Owner: FirstEnergy Nuclear Operating Compahy 76 South Main, Akron, OH 3; Name, address and identification of nuclear power plant Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449
- 4. System:. Unit 1, RC System 5a. Items which required Repair or Replacement Activities Identification ....... ~~~~~Name] Construction dIon/ Code Cd Cde Activity Rpr No Type of. Mfg.. Mg. Natl ad. Jurlsd. Year eo Editn Code code Repair Item Name Serial No. No. No.. Other Built Section nd Cse(s) cass Replace I RCP 2-2 8&W N/A N/ NIA N/A N/A 1973 USAS B31.7 N/A 1 Repair
*1-V&I-Discharge VlI RC-MK-B-56-1-.
SWI13A 5b. Items Installed during Replacement Activities Identification Construction Code Installed or Name Type of Replaced Mfg. MNf. Nati Rd. Jurisd. Other Year Ne f Edition / Code code Item 5a Item No. Name Serial No. No. No. Built Division Addenda Case(s) Class Weld Overlay See line 11 WSI N/A N/A N/A N/A 2010 ASME XI 1995 / 1996 N-740-2
- 6. ASME Code Section XI appilicable for insernlce InspectiIon: 1995 1996 N/A
- 7. ASME Code Section XI used for repairs or replacemen tS: 1995 1996 N-740-2 ASME III
- 8. Construction Code used for repairs or replacements: 1971 Summer 1971 N/A (C'4"aw*)s
- 9. Design Responsibilities: r ~~
Structural Integritv Associates Inc.. San. Jose.
. . I CA
16 RFO Inservice Inspection Summary Page 203 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
- 10. Tests conducted: hydrostatic [] pneumatic E] design pressure E pressure psi Code Case(s) __
To be performedby owner
- 11. Description of work' Installed a Optimized Weld Overlay (OWOL) to discharge nozzle (2-2) to pipe lAW WSI Traveler 104770-TR-103, Rev. 1 which Incorporates Davis-Besse Work Order Number 200327741. This Implements a one time NRC accepted repair plan 1AWRelief Request RR-A32'and amended Code Case N-740-2.
- 12. Remarks: WSI NCR's 10-210 and 10-217 Initiated and closed during the performance of this repair.-
Note : Ultrasonic Examination conducted In accordance with ASME Section XI, Appendix VIII; 1995 Edition with 1996 Addenda.
. The following Types and Heats of filler material were utilized:
ER308 / 308L, SFA 5.9, Ht./Lot 739058 / YT9160, ERNiCr-3, SFA 5.14, Ht.NX7214DR, ERNICrFe-7A, SFA 5.14, Ht.NX74WSTW Stamping / Nameplate omitted per NBIC 5.7.2 para. b and Ohio code Chapter 4101:4-2-01 (A), (1). CERTIFICATE OF COMPLIANCE I, Robert Norman , certify that to the best of my knowledge and belief the statements in this report are correct and the repair or replacement activities described above conform to Section XI of the ASME Code and the NationalBoardInspection Code"NR" rules. National Board "R" Certilfcate ofAuthorization No. NR-69 to use the "NR" stamp expires November 6 2010 NR Certificate Holder Welding Services Inc. QC Supervisor Date 'Signed CERTIFICATE OF INSPECTION . I, _TAeC>'$ z',4O L L. , holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of /OH'IO and employed by HSB-CT - of. Hartford, CT have Inspected the repair, modification or replacement described in this report on 4'16. 20/ o and state that to the best of my knowledge and belief, this repair, modification or replacement activity.has been completed In accordance with Section XGof the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning The work described in this report. Furthermore, neitherthe undersigned nor. my employer shall be liable in any manner for any personal Injury, property damage or a loss of any kind arising from or connected with this inspection. Date L. " Signed aa-¢e *. e Commissios A,6~ 7ý?90o 1 Sio 6-~'
16 RFO Inservice Inspection Summary Page 204 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 FORM NR-1 REPORT OF REPAIR [] OR REPLACEMENT 0] TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS
- 1. Work performed by: Welding Services Inc, 104770
' 2225 Skyland Court, Norcross, GA 30071
- 2. Owner: FirstEnergy Nuclear Operating Company 76 South Main, Akron, OH
- 3. Name, address and identification of nuclear power plant Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449..
- 4. System: Unit 1, RC System 5a. Items which required Repair or Replacement Activities Identltlcation Construction Code Actvty Nfg. Jurlsd. Year Name/ Edition/ Code Code Repair /
No T.ype Item of
. Mg..
Name Serial No. Nal Dd. _____Aiddin No. No. Built Division Add eoda. Case(s) Class. Replace
. - ~~~Asme ,'
I RCP 2-2 B &W N/A N/A N/A N/A 1977 I1I/1 1971 N/A I Repair Suction .____- to 1971 , '" RC-MK-A-67-. - FW134A . Summer Sb, Items Installed during Replacement Activities Identification Construction Code Installed or Name Type of Replaced Mfge Mfg. Nato Rd. No.sd, other Year Section / Edition / Code Code Item 5a Item No. Name Serial No, No. No t Built Division Addenda Case(s) Class Weld Overlay See line 11 WSI N/A N/A N N/A 2010 ASME XI 1995/ 1996 N-740-2 I
- 6. ASME Code Section X) applicable for inservice Inspect Ion: 1995 1996 N/A 7, ASME Code Section XI used for repairs or replacemen ts; 1995 1996 N-740-2 (CN/Aý))
ASME IlI
- 8. Construction Code used for repairs or replacements: 1971 Summer 1971 N/A
(,0 ) .. (-M )
- 9. Design Responsibilities: Structural Integrity Assocates Inc., San Jose, CA
16 RFO Inservice Inspection Summary Page 205 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 1.0.Tests conducted: hydrostatic E pneumatic [3 design pressure [ pressure __ psi Code Case(s) __ To be performedby owner
- 11. Description of work: Installed a Full Structural Weld Overlay (FSWOL) to Suction nozzle (2-2) to pipe IAW WSI traveler 104770-TR-102, Rev. 1 which Incorporates Davis-Besse Work Order Number 200327741. This implements a one time NRC accepted repair plan IAW Relief Request RR-A33 and amended Code Case N-740-2.
- 12. Remarks: WS1 NCR's 10-206, 10-213 and 10-214 Initiated and closed during the performance of this repair.
Note : Ultrasonic Examination conducted In accordance with ASME Section XI, Appendix VIII, 1995 Edition with 1996 Addenda. " The following Types and Heats of filler material were utilized: ER308 / 308L, SFA 5.9, Ht./Lot 739058 / YT9160, ERNICr-3, SEA 5.14, Ht.NX7214DR, ERNICrFe-7A, SFA 5.14, Ht.NX78W4TK Stamping / Nameplate omitted-per NBIC 5,7,2 para. b and Ohio code Chapter 4101:4-2-01 (A), (1).."...' CERTIFICATrE OF COMPIIANCE I, Robert Norman , certify that to the best of my knowledge and belief the statements in this report are correct and the repair or replacement activities described above conform to Section XI of the ASME Code and the NationalBoardInspection Code "NR" rules. National Board "R" CertificateofAuthorization No. NR-69 to use the "NR" stamp expires November 6 2010 NR Certificate Holder Weldino Services Inc. Date /21 ý io0Signed C-) J............. DSQC Supervisor CERTIFICATE OF INSPECTION 1, J3ti0A !'C46 LL , holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of 0. Y/1 0 - and employed by HSB-CT of Hartford, CT have Inspected the repair, modification or replacement described in this report on .. 2-6 10 and state that to the best of my knowledge and belief, this repair, modification or replacement activity has been completed In accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate,.neitherthe undersigned nor my employer makes any warranty, expressed or Implied, concerning The work described in this report. Furthermore, neither the undersigned nor my employer shall be liable In any manner for any personal injury, property damage or a loss of any kind arising from or connected with this inspection. Date L- "20[0 Signed L.6 0. A commissions /J7f2OAv -,OH'/39,."
16 RFO Inservice Inspection Summary Page 206 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 04 '-0 FORM NR-1 REPORT OF REPAIR Z OR REPLACEMENT El TO NUCLEAR COMEPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS
- 1. Work performed by: WeldinQ Services Inc. 104770
.2225 Skyland Court, Norcross, GA 30071
- 2. Owner: " FrstEnergy Nuclear Operating Company 76 South galn,Akron, OH
- 3. Name, address and Identification of nuclear power plant Davis- Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449
- 4. System: Unit 1, RC System 5a. Items which required Repair or Replacement Activities Identification Construction Code Activity Mfg. Mfg. Nat1ad. Jurlsd, YeaIr Name / Edition ' Code Code Repair!
No Itemof Type t Name Na_ Serial rNo No. No.o No. O. N h lt er Built Section/ Division A Addenda Case(s) Cass Replace Asme I RCS 2-2 B&W N/A N/A N/A N/A 1972 hi/11 1971 N/A I Repair Cold Leg Drain to 1971 RC-40-CCA-18 FW18 Summer 5b. Items installed during Replacement Activities Identification Construction Code installed or Name [ Type of Replaced Mfg. Mfg. Nael 8d. udsd. Year Section Edition / Code Code Item 5a Item No. Name Serial No. No. No. t hAddenda ilt Case(s) Class Division A Weld Overlay See line 11 WSI N/A N/A N/A N/A 2010 ASMEXI 1995/ 1996 N-740-2 I
- 6. ASME Code Section XI applicable for Inservice inspection: 1995 1996 N/A (eavoN) (W1 ) OCode UW)
- 7. ASME Code Section XI used for repairs or replacement s: 1995 1996 N-740-2 ASME III
- 8. Construction Code used for repairs or replacements: 1971 Summer 1971 N/A
- 9. Design Responsibilities: Structural Integrity Associates Inc., San Jose, CA
16 RFO Inservice Inspection Summary Page 207 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
- 10. Tests conducted: hydrostatic [I pneumatic El design pressure - pressure _ psi Code Case (s)
To be performed by owner
- 11. Description of work: Installed a Full Structural Weld Overlay (FSWOL) to Cold Leg Drain nozzle (2-2) to elbow IAW WSI Traveler i04770-TR-104, Rev. 1, which incorporates Davis-Besse Work Order Number- 200327741.
This implements a one time NRC accepted repair plan IAW Relief Request RR-A33 and amended Code Case N-740-2.
- 12. Remarks: WSI NCR's 10-209 and 10-212 initiated and closed during the performance of this repair.
The following Types and Heats of filler material were utilized: ER308 / 308L, SFA 5.9, Ht./Lot 734815 / XT8659, ERNICr-3, SFA 5.14, Ht.NX6764DR, ERNiCrFe-7A, SFA 5.14, Ht.NX7SWITK Note : Ultrasonic Examination conducted in accordance with ASME Section XI; Appendix VIII, 1995 Edition with 1996 Addenda. Stamping I Nameplate omitted per NBIC 5.7.2 para. b and Ohio code Chapter 4101:4-2-01 (A), (1).... CERTIFICATE OF COMIPLIANCE I, Robert Norman , certify that to the best of my knowledge and belief the statements in this report are correct and the repair or replacement activities described above conform to Section XI of the ASME Code and the NationalBoardInspection Code'"NR" rules. National Board `R" CertificateofAuthorization No. NR-69 to use the "NR" stamp expires November 6 2010 NR Certificate Holder Welding Services Inc. DateZ- ',"/*1 Signed . QC Supervisor CERTIFICATE OF INSPECTION I, -TAeo'g C/-L. ,holding a valid commission Issued by the National Board of Boller and Pressure Vessel Inspectors and certificate of competency Issued by the jurisdiction of 6 Itlo and employed by HSB-CT of Hartford, CT have inspected the repair, modification or replacement described in this report on .- 6%. Zo (0 and state that to the best of my knowledge and belief, this repair, modification or replacement activity has been completed In accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or Implied, concerning The work described in this report. Furthermore, rigither the undersigned nor my employer shall be liable In any manner for any personal Injury, property damage or a loss of any kind arising from or connected with this inspection. Date -2,'p S-Signed Commissions A68 7921? AAJe,'- O'qy2
16 RFO Inservice Inspection Summary Page 208 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DS-0070-4 I L"A - _,o
. . .- / ',2-;1r. -
FORM NIS-2/NR-I.MVR4I-OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Date July 21, 2010 76 South Main St., Akron. OH 44308 Sheet 1 of2
- 2. Plant Davis-Besse Nuclear Power Station Unit 111 5501 N. SR. 2, Oak Harbor, OH 43449 200348471 Aass nerPera1nQ.- P.O.Na, abe,.. M.
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR
- 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No. 20 Exoiration Date 07/17/13
- 4. Identification of Systems Hligh Pressure Injection Line 2-2 Isolation Valve (DB-HP2B)
- 5. (a) Applicable Construction Code ASME P&V-I NO Edition NO Addenda Code Case No (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case NO (c) Design Responsiblitties FiratEnargy Corp.
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired ASME Name ot Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped I EA. 2 %" VALVE UNK HP-HV2B UNK DB-HP2B UNK Replaced NO DISC, I EA. 2 A" VALVE VELAN INC. 4096 UNK DB-HP2B 1991 Replacement NO DISC.
- 7. Description of Work Ouring rootine rnaintenances activities the installed valve disc was replaced with new like for like.
No leakage teat in required for replacement of valve internals.
- 8. Tests Conducted: YES Hydrostatic No Pneumatic No Nominal Operating Pressure YES Other No Pressure N/A psi Test Temperature NIA "F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A soa-0n NOTE: Supplemental sheets In the form of lists, sketches, or drawings may be used, provided (1) size is 8 ' X 11 in. (2) Information in items I through 6 on fhis teentr i* includedar an *eah shear and (3n each sheat in numbehred and the number of sheets is recorded at raera atotfhisfarm this tecort is included on each sheet and 30 each sheet is numbered and the number of sheets is recorded at the ton of this form FORM NIS-2/NR-1/NVR-1 AWe - ,Sa~~
-a, no.
-- - 1I-w S. -...
16 RFO Inservice Inspection Summary Page 209 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-4
- 9. REMARKS VELAN INC.
CERTIFICATE OF COMPLIANCE I, Jeffrey M. Martin certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/13 Date 07122/2010 FENOC Signed Q.c. CERTIFICATE OF INSERVICE INSPECTION I, Thomas Laps holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on 07/2212010 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section X1 of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 07/22/2010 Signed "" movwx Commissions tj13 q-33'0i tCAA .co Oqt.
-CERTIFICATE OF COMPLIANCE I, N/A certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section Xl of the ASME Code and to the National Board Inspection Code "VR" and "NR' rules.
National Board Certificate of Authorization No. 316 to use the 'VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section X1 of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed _ Commissions
16 RFO Inservice Inspection Summary Page 210 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DR-Gf170-4 , I,..*'L.,*.io FORM NIS-2/NR-I/NVRI- OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp.
Date. August 18, 2010 76 R-nth Main qt. A k-,~ O)H dd3I(IR Sh0eet1 o92
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 200379598 5501 N. SR. 2. Oak Harbor, OH 43449
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2, Oak Haibor, OH 43449 Authodzation No. 20 Exoiration Date 07/17/13
- 4. Identification of Systems Hanger GCB-1-H22 DECAY HEAT AND LOW PRESSURE INJECTION SNA103 DB-SUB049-02
- 5. (al Applicable Construction Code ANSI 13 1.1 OgS7Edition Addenda Code Case No (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case (a) Design Responsibilities FirstEnergy Corp.
- 6. Identification of Components Repaired or Reolaced and Reolacement Components Manufacturer's National Other identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 2.5" Hydraulic Snubber Grinnell 9869 NIA SNA103 UNK Replaced NO 2.5" Hydraulic Snubber Grinnell 37625 N/A SNA103 UNK Replacement NO
- 7. Description of Work Existing Grinnell snubber 9869 was replaced with a rebuilt like for like snubber 37625.
As-left VT-3 inspection performed satisfactoty. 5(a) Cont. MSS-SP-58
- 8. Tests Conducted: No Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A ns5 Test Temperature N/A '17 Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using NI/A at NJA NOTE: Supplemental sheets in tbe form of lists, sketches, or drawings maybe used, provided (1) size is 8 %AXil In. (2) Information In items I through 6 on this resort is included on each sheet, and (30 each sheet is numbered and the number of sheets is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 211 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 OB-0070.4 FORM NIS-21NR-1/*L-
- 9. REMARKS Grinnell CERTIFICATE OF COMPLIANCE 1, Jeffrey M. Martin , certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules.-
National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/13 Date 08/18/2010 FENOC Signed t5ý, - Q'C. CERTIFICATE OF INSERVICE INSPECTION I, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on 08/19/2010 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 08/19/2010 Signed 1&1'14 e Commissions rIL),..t..o
&4ý,,,"/eo an N*lul,*lt*ia.
anidno.)) CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR' rules. National Board Certificate of Authorization No. 316 to use the "VR' stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/13 Date FENOC Signed Q.c. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the Nationat Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions V-`no* iNSIiCAA) 6000('nO ,fld0n.mnISi. AndNI,440n,.460001)
16 RFO Inservice Inspection Summary Page 212 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-4 FORM NIS-2INR-1jt/ rW6vvNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Date August 17, 2010 76 South Main St., Akron. OH 44308 Sheet 1 of 2
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 200379599 Rep&55.a5kuP.O. No..auý tos.c'
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR, 2. Oak Harbor, 0 H 43449 . Authorization No. 20 Expiration Date 07/17/13
- 4. Identification of Systems Hanger GCB- 1-1122 DECAY HEAT AND LOW PRESSURE INJECTION SNA 104 DB-SUB049-02
- 5. (a) Applicable Construction Code ANSI B3 1.1 196l7Edition Addenda Code Case No (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edilion 96 Addenda Code Case (c) Design Responsibilities FirstEnergy Corp.
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 2.5" Hydraulic Snubber Grinnell 9868 N/A SNAI04 UNK Replaced NO 2.5" 1l- draulic Snubber Grinnell 37624 N/A SNA 104 UNK Replacement NO
- 7. Description of Work Existing Grinnell snubber 9868 was replaced with a rebuilt like for like snubber 37624.
As-left VT-3 inspection performed satisfactory. 5(a) Cont. MSS-SP-58
- 8. Tests Conducted: No Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A psi Test Temperature N/A 'F Pressure Relief Valves:
Service N/A Size NIA Opening Pressure N/A Blowdown (if applicable) NIA Set Pressure and Blowdown Adjustments Made Using N/A treeMowo:,l at NIA NOTE: Supplemental sheets in the formof lists, sketches, or drawings may be used, provided (t) size is 8 ' X 11 in. (2) Information in items 1 through 6 on this ruoss is included on each sheet, and 130each shuet is numbered and the number of sheets is recorded at the too of this form.
16 RFO Inservice Inspection Summary Page 213 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 D0-0070-4 FORM NIS-21NR-1>VPR--t Anka&. L*n4*d,,,a,3 DM1 Repot tbs.. d
- 9. REMARKS Grinecli CERTIFICATE OF COMPLIANCE I, Jeffi'ey M. Martin , certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspecfiorv -
Code "NR" rules. National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/13 Date 08/17/2010 FENOC Signed Q.c. CERTIFICATE OF INSERVICE INSPECTION 1, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on 08/19/2010 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising flom of connected with this inspection. UI&- Date 08/1912010 Signed /-Uw lý Commissions qq.L' A 14 r- 0/4 w,,,4tOl CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR' stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/13 Date FENOC Signed Q.c_
,oe~pa (n=meof -oo0*n0,*) l.t*th=)
(tu*O~dLed,.epoe CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on _._ and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions Q000M0~ O~,~ooo0000 0 (MO0000,0,,,. 000).
*,0j04.01040.00000)1
16 RFO Inservice Inspection Summary Page 214 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 r2.O07M-4 N I. ' FORM NIS-2/NR-1/ýNAR4OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section X1
- 1. Owner FirstEnergy Corp. Drat August 16,2010 711 Rnqth Main Rf.. Arn.. 011 4A30dtt Sheet I of 2
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2. Oak Harbor. Off 43449 200379600 AeNoa-q P.O.Nl.. NO.
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No. 20 Expiratlon Date 07/17/13
- 4. tdentificatlon of Systems Hanger GCB-l-H33 DECAY HEAT AND LOW PRESSURE INJECTION SNA 105 DB-SUB049-02
- 5. (a) Applicable Construction Code ANSI B3 1.1 1967Edition Addenda Code Case No (b) Applicable Edition of Section Xi Ulitized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case (c) Design Responsibilities FlmtEnergy Corp.
P Irianfifs-,tinn rd ttnmnnnentn Beneirjari or Renianeri non Ronlanement flomonnonts Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 2.5" Hydraulic Snubber Grinnell 10364 N/A SNAI05 UNK Replaced NO 2.5" HIydraulic Snubber Grinnell 37615 N/A SNA105 UNK Replacement NO
- 7. Description of Work Existing Grinnell snubber 10364 was replaced with a rebuilt like for like snubber 37615.
As-left VT-3 inspection performed satisfactory. 5(a) Cont. MSS-SP-58
- 8. Tesis Conducted: No Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A psi Test Temperature N/A "F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 1 X 11 in. (2) Information in items 1 through 6 on this redort is included on each sheet. and 130each sheet is numbered and the number of sheets is recorded at the too of this form.
16 RFO Inservice Inspection Summary Page 215 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-4 FORM NIS-2/NR-1/NVR1 / -
- 9. REMARKS Grinnell CERTIFICATE OF COMPLIANCE I, Jeffrey M. Martin ., certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Seotion-XI of the ASME Code and to the National Board Inspection Code 'NR" rules.
National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/13/13 Date 08/16/2010 FENOC Signed . CERTIFICATE OF INSERVICE INSPECTION I, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of. Hartford, CT have inspected the work described in this report on 08/19/2010 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 0811912010 Signed 914,t //01 Commissions q9,? A ,ItL Iowl CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and 'NR' rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/13 Date FENOC Signed Q.C. (nameo/repa="
,O nlfl=o) (flu o d,,prtsentfltk',)
CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 216 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 0B-0070.4 . /I =,,, i "t'- FORM NIS-2/NR-1///R'1/t5/NER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 (Oner FirstEnergy Corn. Date August 17, 2010 76 South Main St.. Akron, OH 44308 Sheet I of2
- 2. Plant Davis-Besse Nuclear Power Station Unit ff1 5501 N. SR. 2, Oak Harbor, OH 43449 200379601
- 3. Work Performed by iFirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR&2. Oak Harbor. OR 43449 Authorization No. 20 Expiration Date 07/17/13
- 4. Identification of Systems Hanger HBC-]-H4 EMERGENCY SUMP BORATED WATER STORAGE TANK (SNAI IS)
- 5. (a) Applicable Construction Code ANSI B3 1.1 1967 Edition No Addenda Code Case No (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case (c) Design Responsibilities FirstEnergy Corp.
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturers National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 25" Hydraulic Snubber Grinnell 12035 NIA SNAI 1;8 lNK Replaced NO 2.5" Hydraulic Snubber Grinnelt 37623 NIA SNAI 18 lINK Replacement NO
- 7. Description of Work Existitg Grinnell snubber 12035 was replaced with a rebuilt like for like snubber 37623.
As-left VT-3 inspection performed satisfactory. 5(s) Cosit. MSS-SP-58 B. Tests Conducted: No Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A osi Test Temperature N/A *F Pressure Relief Valves: Service N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 Y X 11 In. (2) Information in items 1 through 6 on this reeort is included on each sheet, and (30 each sheet is numbered and the number of sheets is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 217 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB.0070-4 , . o FORM NIS-2/NR-1_j1
- 9. REMARKS Grinnell CERTIFICATE OF COMPLIANCE I, Jeffrey M. Martin , certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules.
National Board Certificate of Authorization No. 20 to use the 'NR" stamp expires 07/17/13 Date 08/16/2010 FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Bruce North holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on 08/19/2010 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection Code "NR' rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 08/1912010 Signed ,AU i Commissions (I AT4L 014 a ,J96V CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/13 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and slate that to the best of my knowledge and belief, this repair, modification or replacement has been. completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be - liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 218 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 t~97007-4 -... AAA7_ s -1 c FORM NIS-2/NR-I. nOWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- i. Owner FirstEnergy Corp. Date July 27, 2010 76 South Main St.. Akron. OH 44308 Sheet 1 of 2
- 2. Plant Davis-Besse Nuclear Power Station Unit 5501 N. SR. 2. Oak Harbor. OH 43449 200404719- e=*reomn.,eae,p.,,.en..ken,..ke
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng 5501 N. SR. 2. Oak Harbor, OH 43449 Authorization No. 20 Expiration Date 07/17/13
- 4. Identification ofSystems RC LETDOWN COOLERS DB-E25-I & DB-E25-1 PIPING SUPPORTS/ HANGERS
- 5. (a) Applicable Construction Code ASME3 CL.1 Editionl996 Addenda 95 Code Case N/A (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements 19 95 Edition __96 Addenda Code Case 416-3 (c) Design Responsibilities FirstEnergy Corp. -
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturers National Other ldentificationt Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped See vendors (PCI) NR-I report for material.
- 7. Description of Work Vendor (PCI) replaced the Reactor Coolant letdown coolers I & 2 with new like for like and made the necessary welds to restore piping supports removed as part of interference during 16RFO. A VT-3 was performed on hangers 10 & 11.
No piping attachment welds were mnade. A VT-2 inservice leakage test (per code case 416-3) was performed satisfactory as part of the post repair/replacement examination.
- 8. Tests Conducted: YES Hydrostatic No Pneumatic No Nominal Operating Pressure YES Other No Pressure 2155 psi Test Temperature 532 'F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Slowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 X 11 In. (2) Information in items 1 through 6 on this report is included on each sheet, and 130each sheet is numbered and the number of sheets is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 219 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 B-0070-4 FORM NIS-2/NR-1/NVR-1 All-
- 9. REMARKS PCI CERTIFICATE OF COMPLIANCE I, Jeffrey M. Martin ,certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules.
National Board Certificate of Authorization No. 20 to use the 'NR" stamp expires 07/17/ 3' Date 07/27/2010 FENOC Signed , Q.r-CERTIFICATE OF INSERVICE INSPECTION I, Thomas Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on 07/27/2010 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code 'NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 07/27/2010 Signed 4A AZ,,,01_ Commissions ________-___________ CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the 'NR" stamp expires 07/17/13 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on r_ and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Sianed Commissions mImO0..0.5,)
16 RFO Inservice Inspection Summary Page 220 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
....... NUCLEAR REPAIR FORM NR-1 REPORT OF REPAIR E OR REPLACEMENT [
TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS
.York performed by: PCI Energy Services PCI- 1254-02 One Energy Drive, Lake Bluff, Illinois 60044
- 2. Owner: First Energy Nuclear Operating Company
- 3. Name, address and identification of nuclear power plant: Davis Desse Nuclear Power Plant, Unit 1, 5501 N. State Route 2, Oak Harbor, 0H. 43449
- 4. System: Letdown Coller 1-2 5a. Items that Required Repair or Replacement Activities Idcntification Construction Code Activit Namsei Repair?
Mfg. Mfg, Nat'l Bd. Juis. Yrsr Section? Edition/ Code Code Mod/ No Type of Item Name SerialNo. No. No. Other Built Division Addenda Case(s) Class Replace I Letdown Grahm" 7T007-1 197 o No Data No Data No Replace 2 Cooler Mfg. .. Data 3 4 Letdown Grahas. 71007-1 1971 No Data No Data 4o Data No Replace 5 Cooler Data 6 7 8 9 to Sb.Items Instatled Durn* Replacement Activities Identification Construction Code Installed or Mfg.. Name/ Type of Replaced Mfg. Serial Nat't Bd. Jurisd. Year Section? Edition/ Code Code Item 5a Item No. Name No. No. No. Other Built Division Addenda Case(s) Class Leadown A Grahaa 71007-2 18001 1989 ASME [I1 1977Ed - 3
" Cooler Mr Div. I 1978SAd Letdown A Graham 71007-2 18000 1989 ASME VIm 1986 Ed s051 Cooler Mfg. Div. I 1987 Ad
- 6. ASME Code Section XI applicable for inservice inspection: N/A N/A N/A
- 7. ASME Code Section X0 used for repairs or replacements: 1995 1996 N416-3
- 8. Construction Code used for repairs or replacements: ASME ItICL2 01 2003 N/A
- 9. Design responsibilities:
- 10. Tests conducted: hydrostatic ] pneumnatic D design pressure E] pressure - psi. Code Case(s): N416-3 NUCLEAR REPAIR
16 RFO Inservice Inspection Summary Page 221 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
\ \v
\
- 11. Description of work Work performed was removal and replacement of 1-2 Letdown cooler and associated interferences.
The 1-2 Cooler (2) 3" RCS, (2) 4" CCW, (1) M'"Vent, (1) 1" Drain and (2 low point drain valve lines where cut for cooler removal. To facilitate in the removal, (1) bolted support and (6) hanger straps where removed. 1-2 was replaced with a new cooler received from site storage. Existing piping and new cooler where prepped and welded into place. 3 and 4 inch butt welds, 3/4 and 1 inch piping (fillet welds) reinstalled. NDE (PT) was performed on all welds, 100% Radiography performed on the 3" and 4"butt welds. Hanger straps and Support reinstalled. All reinstallation final inspections found acceptable. This Removal and Installation was performed per PCI Traveler 901254-02 Rev.] and Davis Besse Maintenance Work Order No. 200398492.
- 12. Remarks: Weld -Procedures Used PCI WPS (I MN- GTAW/SMAW Rev.8) and PCI WPS (8 MN- GTAW Rev.l).
PCI WedWirerUsed ER316/316L/8" PCI#3684,3/32"PCI#3793 ER70S-6 118"PC1# 3787, 3/32" PCI# 3662 E7018114R 1/8" l'CI# 3758 NR Name Plate Omitted Per NBIC Part 3, 5.7.2 para. b. PCI' did not pef- prsue et Over Pressure Protection provided by others J CERTIFICATE OIFCOMPLIANCE I. Leslie W. Bissett ,certify that to the best of my knowledge and belief the statements made in this report are correct and the repair or replacement activities described above conform to Section XI of the ASME Code and the NationalBoard Inspection Code "NR" rules, National Board Certificate ofAuthorization No: NR-74 to use the "NR stamp expires September 16, 2012 NR Certificate Holder PCI Energy Services LLC Date: Signed /57 2 / .. .. Quality Control (Wl)
,'/z 7la.0o 61 C RIIAlT, OF INSPECTION 1, ,-7.4"06 *'gect. ; holding a valid cormnission issued by The National Board of Boiler and Pressure Vessel inspectors and certificate of competency issued by thejurisdiction of: OHIO and employed by:
HSB CT. of Hartford CL. have inspected the repair or replacement described in the report on 7'-
- and state that to the best of my knowledge and belie&this repair or replacement has been completed in accordance with Section XI of the ASloIE Code and the National BoardInspection Code "NW."rules.
By signing this certificate, neither the undersigned nor my employer makes any warraaty, expressed or implied, concerning the work described in this report Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property dam age or loss opny kin darising, om o0, - "eated w ith this inspection. D ate : 5 7 .z , so oSign ed Co mns sions A ),J
16 RFO Inservice Inspection Sumliiary Page 222 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 ri NUCLEAR RFPAIP FORM NR-1 REPORT OF REPAIR Ei OR REPLACEMENT Z TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS
/ork performed by: PCI Energv Services PCI-1254-01 t=~&ar~~e~uIar (PO.ar ;.b..-
(3rn~~ Drive Islee Bluff illinois 611044
....... En - Drive.-... . Illnoi 60044
- 2. Owner: First Energy Nuclear Operating Company
.- 7)
- 3. Name, address and identification of nuclear power plant: Davis Besse Nuclear Power.Plant, Unit 1, 5501 N. State Route 2, Oak Harbor, OH. 43449
- 4. Systemt: Letdown Cooler 1-1 Sa. Ihems that Required Repair or Replacement Activities Identification Construction Code Activity Name! Repair!
Mfg. Mfg. Nat'] Bd. Juris. Year Section/ Editiojil Code Code Mod/ No Type of Itemu Name Serial No. No. No. Other Built Division Addenda Case(s) Class Replace I Letdown Grahom 63511-1-- , 1989 ASME I1I 1977Ed 2 Replace 2 Cooler Ifg. 1979Ad 3 4 Letdown tiraltam 63511-1 1989 ASMEVIII 1989LEd 2 Replsee 5 Cooler Mfg. 1989Ad 6 7 8 9 S11 5b. Items Installed During Replacement Activities Identification Construction Code Installed or Mfg. Name/ Type of Replaced Mfg. Serial Nat'l Bd. Jurisd. Year Sectionl Edition! Code Code Item Sa Item No. Name No. No. No. Other Built Division Addenda Case(s) Class Letdown A Energy N36141-1 2010 ASMIEIII 1977Ed 3 Cooler Steel Dir. I 1979WAd Letdown A Energy M36141-1 20110 ASME VIII 2t7Ed Cooler Steel Div. I 2009Ad _ [,,,____ _ _ _ _ _ _ _ __
- 6. ASME Code Section XI applicable for inservice inspection: N/A N/A N/A
- 7. ASME Code Section XI used for repairs or replacements: 1995 1996 N416-3
(-a-) (ere)- M)
- 8. Construction Code used for repairs or replacements: ASMI111 eCL2 01 2003 N/A
- 9. Design responsibilities:
Tests conducted: hydrostatic E] pneumatic [] design pressure F] pressure - psi. Code Case(s): N416-3 NUCLEAR REPAIR
16 RFO Inservice Inspection Summary Page 223 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978
- 11. Description of work Work performed was the removal and replacement of 1-1 Letdown cooler and associated Interferencea.
The 1-1 Cooler(2) 3" RCS ,(2) 4" CCW,(l)3/" Vent, (1)1" Drain and (2 low point drain valve lines where cut for cooler removal. To facilitate in the removal, (1) bolted support and (6) hanger'straps where removed. 1-1 was replaced with a newly fabricated cooler. Existing piping and new cooler where prepped and welded into place. The 3"and 4" butt welds, 3", and l"piping (fillet welds) reinstalled. NDE (PT) was performed on all welds. 100% Radiography was performed on the 3" and 4" butt welds. Hanger straps and support reinstalled. All reinstallation final inspections found acceptable. This Removal and installation was performed per PCI Traveler 901254-01 Rev. 1, and Davis Besse Maintenance Work Order No. 200398491.
- 12. Remarks: Weld Procedures Used . PCI (WPS- 1 MN-GTAW/SMAW Rev. 8) and WPS (8 MN-GTAW Rev. 1)
PCI Weld Wire Used. ER316/316L 1/8" PCI# 3684, 3/32" PCi# 3793 ER70S-6 1/8" PCI# 3787, 3/32" PCI# 3662 E7018H4R 118" PCI# 3758 NR Name Plate Omitted Per NBIC Part 3, 5.7.2 para. b. PCI did not perform pressure test Over Pressure Protection provided by Others CERTIFICATE OF COMPLIANCE Leslie W BIssett , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair or replacement activities described above conform to Section X1 of the ASME Code and the National Board Inspection Code "N1'" rules. National BoardCertificateof Authorization No: NR-74 to use the "N'R stamp expires September 16, 2012 NR Certificate Holder PCT Energy Services LLC Date: , Sianed r . Oualitv Q ... . ,.Control
- 3A,7/.2 0/o -1/
L, .-TYOO * .(O.L 15 ,holding a valid commission issued by The National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OfHO and employed by: HSB CT. of Hartford,CT. have inspected the repair or replacement described in the report on 3 - Z7 2./D. and state that to the best of my knowledge and belicf this repair or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Imspection Code "N'R rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore. neither the undersigned nor my employer shall be liable inany manser for any personal injury, property damage or loss of ykind .s fo0 eo dnted with this inspection. Date:* 5- 7 , Zip /[0 Signed Commissions A/,/l 7"t.44)81. fqii,_- 2
16 RFO Inservice Inspection Summary Page 224 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 FORM NIS-2/NR-1/NVR-i OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl
- 1. Owner FirstEnergy Corp. Date July 8, 2010 76 South Main St.. Akron. OH 44308 Sheet 1 of I
- 2. Plant Davis-Bease Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, 011 43449 200414124
- 3. Work Performed by FirstEnergy Nuclear Operatina Co. Type Cede Stamp NE 5501 N. SR. 2, Oak Harbor, OH 43449 Authorization No. 20 Expiration Date 07/17/2013
- 4. Identification ot Systems Reactor Coolant Letdown Cooler Inlet DB-MU2B (SUB065-01")
Products
- 5. (a) Applicable Construction Code ASNM ItI CL, 1 1971 Edition No Addenda Code Case No Machine Nova (b) Applicable Edition of Section XI Utilized Corp.,
for Repairs or Replacements 19 95 Edition 1996 Addenda Code Case NO FlrstEnergy (c) Design Responsibilities FirstEnargy Corp., Nova Machine Products
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturers National Other Identification] Year Repaired . ASME Name of Component Name of Manufectumr Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped M" Cont. Thread Rod Nova Machine Products I-IT# 732078 N/A N/A 2005 Replacement No
`"Heavy tex Nut( I ) Ndva Machine Products HT# 724392 N/A N/A 2003 Reptacement No 5/4"Heavy Rex Nut 14) ,Nova Machine Products HT# 726176 N/A N/A 2003 Replacement No
'/4" Hteay Hex Nut S Nova Machine Products - HT# 726176 N/A N/A 2003 Replacement No 7, Description of Work Associated boltine material was rerlaced during routine maintenance.
'W" Heavy hex nuts with HT# 726176 was ordered under different PO's and received at different times therefore have different oanerwork.
All other materials reolaced are listed in the work order oackage. A VT-2 was nerfornmed satisfactorily.
- 8. Tests Conducted: Hydrostatic No Pneumatic No Nominat Operating Pressure Yes Other No Pressure NOP , psiq Test Temperature NOT 'F Pressure Relief Valves:
Service NIA Si ze N/A Opening Pressure NIA Slowodown (if applicable) NIA Set Pressure and Otowdown Adjustments Made Using NIA at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 Y1/X 11 In. (2) Information initems I through 6 on this report is included on each sheet. and (30 each sheet is numbered and the number of sheets is recorded at the too of this form.
16 RFO Inservice Inspection Summary Page 225 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0D70-5 FORM NIS-2/NR-1/NVR'-'t
- 9. REMARKS Nova Machine Products CERTIFICATE OF COMPLIANCE I, Lynn Ross certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR' rules.
National Board Cerificate of Authorization No. 20 to use the "NR" stamp expires 07/17/13 Date -i [fl PENOC Signed .Q.C. CERTIFICATE OF INSERVICE INSPECTION 1, Two mAb C G., WAfS holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on k) .. Zto, and state that to the best Of my knowledge and belief, this repair, modification or replacement has been compl ted in accordance with Section X1 of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection., Date C)( Signed Commissions t~ ýý CERTIFICATE OF COMPLIANCE I, , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR' rules. National Board Certificate of Authorization No, 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No, 20 to use the "NR' stamp expires 07/17/13 Date FENOC Signed _._.c. CERTIFICATE OF INSERVICE INSPECTION I, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on
- and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASrViE Code and the National Board Inspection Code "VR" and "NR" rules.
By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, propertyd-amage or loss of anykind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 226 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 FORM70- NI-IN- /NV ,-W ' REOR FOIEARSOfELAEET FORM NIS-21NR-1/NV.R--1-OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Data 05/21/2010 76 South Main St.. Akron, OH 44308 Sheet 1 of1 -
- 2. Plant Davis-Beasse Niclear Power Station Unit 41 5501 N. SR. 2, Oak Harbor,
*d,s=s OH 43449 200414552Repuk Orgarnz=oPO*.Njob to.. Cal
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ngt 5501 N. SR, 2. Oak Harbor, OH 43449 Authorization No. 20 Exotratinon Date 07/17/10
- 4. Identification of Systems Hanger CCA-6-1`15, CORE FLOOD SYSTEM, Subsys DB-SUB051-01
- 5. (a) Applicable Construction Code ANSI D3 1.1 1967 Edition Later Addenda Code Case N/A (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N/A (c) Design Responsibilities Firstonergy Corp, Grinnell
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 2.5" Hydraulic Snubber Grinnell 12487 NIA SNC274 UNK Replaced No 2.5" Hydraulic Snubber Grinnell 37619 NIA SNC274 2010 Replacement No
- 7. Description of Work Existing Grinnell snubber 12487 was replaced with a Configuration A replacement Grinnell snubber 37619.
As left, VT-3 inspection performed SAT. 5(a) Cont. MSS-SP-58
- 8. Tests Conducted: Hydroslalic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A psi Test Temperature N/A F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Slowdown (it applicable) N/A Set Pressure and Blowdon Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 Y X t I In.(2) Information in items 1 through 6 on rths raeset is inntluded on eachs s;heo and (SO earih sheet is numnbered ;and Iho nitmder at sheets is recorded at the ton ot this forn* this repon is inoluded on each sheet and (30 each sheet Is numbered and the number of sheets is recorded at the ton of this form
16 RFO Inservice Inspection Summary Page 227 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM N 9, REMARKS CERTIFICATE OF COMPLIANCE I, Thomas M.Purdue certify that the statements made in this report are correct and the repair, modification, or. replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.IO CERTIFICATE OF INSERVICE INSPECTION I, BruceNorth holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on .- )5-/0 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date Signed A commissions 5qq " fJ, CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed __C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection Code "VR" and 'NR" rules. By signing this cqrtificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my.employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 228 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-O07O-4 FORM NIS-2/N2PUNVR_ I WNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. owner FirstEnergy Corp. Date July 29, 2010 76 South Main St.. Akron, OH 44308 Sheet I of 2
- 2. Plant Davis-Besse Nuclear Power Station Unit #!
5501 N. SR. 2, Oak Harbor, OH 43449 200297961 & 200409488 R.n-e0o ioo* P.o.50. -
- 3. Work Performed by "FirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oak-Harbor. OH 43449 Authorization No, 20 Expiration Date 07/17113
- 4. Identification of Systems Reactor Vessel DB-TI RC
- 5. *a) Applicable Construction Code ASME3 CLI 1958 Edition 568 Addenda Code Case No (b) Applicebte Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code case 416-3 (c) Design Responsibilities FirstEnergy Corp.
- 6. Identification of Components Repaired or Replaced and Replacement Components Manufacturers National Other Identificatlon/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdlctional No. Built Replaced or Code Replacement Stamped See attached vendor (AREVA) NR- I form.
- 7. Description of Work During 16RFO all the Control Rod Drives were removed and the associated bolting was removed, inspected and replaced as required.
One Head Vent Line Nozzle Bolt was replaced. One of the CRDMs APSR "C" subassembly for location (D 10) was replaced. A VT-2 inservice leakage test (per code case 416-3) was performed satisfactory as part of the post repair/replacement examination.
- 8. Tests Conducted: YES Hydrostatic No Pneumatic No Nominal Operating Pressure YES Other No Pressure 2155 lost Test Temperature 580 "F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings maybe used, provided (1) size Is 8 Y4X 11 In. (2) Information in items i through 6eon this raced is included on each sheoL, and f30 each sheet is numbered and the numher of sheets to recorded at the tee et this term. this report is included an each sheet and f3O each sheet is numbered and the number of sheets Is recorded at the ton of this form.
16 RFO Inservice Inspection Summary Page 229 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 0B.0070-4 FORM NIS-2/NR-I/NVR-1
- 9. REMARKS Areva NP Inc.
CERTIFICATE OF COMPLIANCE 1, Jeffrey M. Martin certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code "NR" rules. National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/13 Date 07/29/2010 FENOC Signed Q.c. CERTIFICATE OF INSERVICE INSPECTION I, Thomas Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by 4ljto HSB CT of Hartford, CT have inspected the work described in this report on 9.ý-lSel4. and state tha"iJc0 the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section Xi of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 'W"O.2&44 Signed Commissions *A32' , , CERTIFICATE OF COMPLIANCE 1, N/A certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section Xl of the ASME Code and to the National Board Inspection Code "VR" and "NR' rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR' stamp expires 07/17/10 Date FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, N/A holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report, Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions
16 RFO Inservice Inspection Summary Page 230 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-4
'5---,
FORM NIS-Z2#R'tMVRi OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner FirstEnergy Corp. Dart July 16, 2010 76 South Main St.. Akron. OH 44308 Sheet 1 of 2
- 2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2. Oak Harbor. OFT 43449 200410080 & 200411925
- 3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ngi M I1 n3 FlN-ha- M4 J1AAQ Authorizaton No. 20 Expiration Date 07/17/13
- 4. Identification of Systems Reactor Vessel DB-T1 RC
- 5. (a) Applicable Construction Code ASME3 CL.1 1971 Edition No Addenda Code Case No (b) Applicable Edition of Section Xi Utilized for Repairs orReplacements 19 95 Edition 96 Addenda code Case 416-3 (c) Design Responsibilities FirstEnergy Corp.
II I,-Lfjfl,-aH,-,,, .rCCnrnnnnantn Ranairori or Renianarl anti Renlanement flomnonanto Manufacturer's National Other Idetefication/ Year Repaired ASME Name of Component Name of Manufacturer Serial No, Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped See attached vendor NR-1 form.
- 7. Description of Work 24 existin2 CRDM nozzle penetrations were modified per ECP 10-0141 due to identification of flaws caused by Primary Water Stress Corrosion Crackin2 (P'WSCC). The modification consisted of defect removal by machininR, examination of area to be repaired, weldtin_', finish machinin"* and final examinations ofrenair. The nozzles repaired are numbers 1.3,4.10.16.21,24.27.28.29.33.40,43,48, 51,55,57,58,59,60,61,64,66 and 67.
A VT-2 inservice leakage test (per code case 416-3) was performed satisfactory as part of the post repair/replacement examination.
- 8. Tests Conducted: YES Hydrostatic No Pneumatic No Nominal Operating Pressure YES Other No Pressure 2155 osi Test Temperature 580 "F Pressure Relief Valves:
Service N/A Size N/A Opening Pressure N/A Blowdown (if applicable) NIA Set Pressure and Blowdown Adlustments Made Using N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 %X It in. (2) Information in items 1 through 6 on this recort is included on each sheet. and (30 each sheet is numbered and the number of sheets is recorded at the top of this form.
16 RFO Inservice Inspection Summary Page 231 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-4 FORM NIS-2INR-IINVR-I AWN- M-1-f ww [dtaReNpnIW. M-Wad
- 0. REMARKS Areva NP Inc.
CERTIFICATE OF COMPLIANCE 1, Jeffrey M. Martin , certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above conforms to Section XI of the ASME Code and to the National Board Inspection Code 'NR" rules. National Board Certificate of Authorization No. 20 to use the 'NR' stamp expires 07/17/13 Date 07/16/2010 FENOC Signed Q.c CERTIFICATE OF INSERVICE INSPECTION I, Thomas Laps holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the work described in this report on 07/16/2010 and state that to the best of my knowledge and belief, this repair,. modification or replacement has been completed in accordance with Section Xl of the ASME Code and the National Board Inspection Code "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the work described in this report Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection. Date 0-7/4-7igned
-_T t 1 P Commissions tA't4 ti 1D (%ak.
CERTIFICATE OF COMPLIANCE 1, N/A , certify that to the best of my knowledge and belief the statements made in this report are correct and the repair, modification, or replacement of the pressure relief devices described above conforms to Section Xl of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.C. (nalms oDrDP~k rganiwnk (aAaoalo, rCN*XDDOW) CERTIFICATE OF INSERVICE INSPECTION I, NIA holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OHIO and employed by HSB CT of Hartford, CT have inspected the repair, modification or replacement described in this report on and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Section XI of the ASME Code and the National Board Inspection Code "VR" and "NR" rules. By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall be liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions N.- - 0m.
16 RFO Inservice Inspection Summary Page 232 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 APPENDIX 5 - NATIONAL BOARD FORMS FORM NR-1 REPORT OF REPAIR FJ OR REPLAcmENT El TO)NUCLEAR COMPONENTS AND SYSTEMIS IN NUCLE AR POWER PLANTS
- 1. Wrkpefurooedby, AREVA NP Inc. L.500466 3315 Old Forest Roa, rOy q, Virqiia., 24501 United States' 7 wner FiretEnergy Nuclear Operating Company -
76 S. Main Street, Akron, Ohio 44308 3.- Nay addr andiderdificasonof nude-rpowerplant Davis-Besse Nuclear Station Dnit 1 5501 North State Route 2, Oak lirbcr, Ohi. 43449
- 4. System Reactor Coolant 5a, itans that RequirdRilepairarReplacesaaentActivitlea Identifiction" Canstrudiom Code . Activity Mf. Naelae Type of Mfg. serial Natl Rd hs Year Section/ Edition/ Code Code 'Repair/
No. Item Name No. No. Na. Other Built Division Addenda Cave(.) Clasa Replace USA N/A 1975 Ln 12 1965/S55 On 12 A Repair 1 hn 12 Ln 12 Ln 12 N-152 2 : 3 , 4
- 6" 7
9 10 12 " 5b. lteme installed D-atng Replacerent Adiities Identificatio Constrarioen Code Iat.1led or Namel Type of Replaced mfI Nf,*g Neal Bd Jets. Year Selaon/ Edidoe/ Code Code Item Sa Item No. Name Serial No. No, NO. Other Built Division Addenda Case(s) Cloas
- 6. AS&MCode Sectin XI applicable for insaevicetieapecion 1995 1996 N-729-1
- 7. ASidE Code&SectonXI aed forrepairs or replacav e.t.: Line 12 Line 12 Line 12
- 8. Con*atction Code used fornepaotes or relasentw 1989 none Line 12 1.
1-gn responiL ~aes
- AsRE N59 Ine.
- 10. Tets eonducted: E]hydrsottaic -lpneematic [Ldesignpreseure presaurel* l 12 ptsi(MPa) Code Case(s)i-46-3 h9slavamaybeotaed toreeTheNainal BoardofBoat act P-ee, WsW qctom. IMS CapierA, Vee C*ht, oH43 N81 W
16 RFO Inservice Inspection Summary Page 233 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 NAIMONAL BOARD INSPECTION CODE l.TDesriptium.of work The modification of twenty four (24) control rod drive mechanism (CRDM) nozzle penetration locations consisted of removal of the 1 lwer nnrtzino of the CRDM nozzle and a nortion of the CIfDM nozzle lower ýortion of the CRDM nozzle and a -ortion of the CRDM nozzle to reactor vessel closure head(RVCH)partial penetration J-groove original weld that contained flaws. The new pressure boundary CRDM nozzle to RVCH weld is located up in the penetration bore above the original weld.. The upper portion og the CRDM nozzle remains in place. The surfaces of the new welds consisted of Primary water stress corrosion.,cracking,(PWSCC) resistant material. Remediation was nerformed to increase the resistance to PWSCC on the most susceptible region. of the. modified CRDM nozzles. m2RSS'Line Sa Identification Type of Item - Reactor Vessel Closure Head Mfg. Name - Babcock and Wilcox Company Mfg. Serial No. - C24-2013-52-1 Line 5a Construction Code Name/Section/Division - Nuclear Vessels/III/l Code Cases 1332-1, 1492, 1395-1 Line 7 1995 Edition, 1996. Addenda and Code Case N-638-1 as modified by NRC Relief Request Nos. RR-A34, Supplements & NRC RAI Responses (Letters L-10-099/01'" Line 8 Code Cases N-474-2 Section II, 2142-2 Section IX Line 10
.Test pressure - nominal Operating pressure -2155 psiq CE*RIMFICAI OF COAMLIANCE tA¢cer " .eeltifythat othebeat ofmy naeledgeadbui thestt ,, m.a.dinvh epot correct and the repair or replareoertt activities described above conform to Section XI of the ASME Code =ndthe National Board hnsperaon Code NRHnoles.
NationalBordCertificakofAuthozionoh No. NR-64 to000utsNR-Apepire May 17 2012
'NiR-CortjcateHoldar AREVA NP Inc.
A A C 0. __9si_ Dat_ (VA CETIFICATE OF INSPECTION
/ holding a valid comMndssion issooedby The National Board of Boilar and Presnure Vessel tespecosadW osei7 a of espetme~y iossud by the juriadictiss, of 1Ad i tnd seployas by if'Y7FoP, haveinspectedtherepar orrep'lcmnmtdesribedinthisreporton m20/O a s-otate that othebest of my knowledge and belief, thin eair or replacenent activity has beenýcompleted in accordance with Section XI of the ASME Code and the Naotnal Board Inj cties Code"NR" roles.
By signing this certificate, neith er -i--dignedioor.sy,employer meb any -#aronit-, expressedd or ieplied.cusceng the work descibed in this report Furthenmore, neither the undersigned normy employer shall be liable in any manner for any peoosol ineiy,poperty damage, ýlosf/ ý gi or comnected with daisInsecrtim. Dote berI a o/ Sanl C. . 1I Y0X1i 4
16 RFO Inservice Inspection Summary FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Page.234 of 235 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 FORM NR-1 REPORT OP REPAIR M MODIFICATION [] OR REPLACEMENT [] TONUCLEAR COMPONENTS AND SYSTEMS INNUCLEAR POWER PLANTS I. Work performned by AIEEVA NP Inc.. PO#s 45255618 (amra caflN erifnlati holder) (2,O, so,,job no., VI) 3315 Old ForsitRd, Lynehburg Va. 24501 (add,=)
- 2. Owner virsi[nacroyc.onusv (nam.)
76 South Main.SL,Akron Ohio 44308 (addrese)
- 3. Name, address and identafication ofnuclear power plian Daise.Beos Naueclr Power Station
*5 IWS* NS fl abrhrOflhio4-A49
- 4. System Reactor Vas.) Head# C24-2013-52-I
.5aItems Which gbloR n d Repair. MDdidlwtlon, or ReplaoreentActivitie-Identificaion. Constelood Cede Activity Na Typea? Mfg. Mfg Scdal Natl Nan ene NdY Editin- Code Code Repaid NO f M Jufisd. the, t Addenda CaYear) Clo n Bee Nam4 No. No. NO. Division l (2) (1) (2) *N-152 N/A N/A 1975 (3) (4) (5) A Rsplaco 3
4 . S . - ___ IIQ II 12
- 5. b:Items Installed During Replacement Activities Identification . Coenstrcion Code Typeof 1,ns1alled or. ' Mdg. Mf'g.Serial Nat'l Bd Jurisd Other Your Nnte./ rditin/ Cad, Cade RIe ed a Name pla, No. No. No Built Seeodn/ dd Cse(s) Closs termNo. [ Division (6) 1 (8) (7) NA _ NIX N/A (10) (3) (4) INoes
- 6. ASMB CodeSecionRX appliablefor inserviccInspecton 1995 1996 Nonee (edition) (addenda) (Code Casoes())
- 7. ASME Code Section XI used for repairs, modifleations,or repplaeomet:: 1995 1996 None (edition) (addenda) (CodeCaasos())
- 8. Construction Code used fnsrepairs, modiflatllons, or oeptcements: 1986 None None (editlio) (addenda) (Codo Cancs(a))
- 9. Design responsiilities: (8) 10, Tests conduoted: X hydsostatd Pe.umatio [] Designpprnsure(9) pressuro 2155 psi Code Case(s) NA (systeemleakatte) this form may be obtained from The National Board of Bonler and Pressure Vessel Insoectors. 1055 Cruooer Ave., Columbus, OH 43229 NB-81
16 RFO Inservice Inspection Summary P'age 235 of 235 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 Repaired Reactor Vessel Head by replacing Quick Vent Closure Assembly at CRD Location B-10 11, Description oftworkh: vIthAREVA procedure 03"12216144-04 with SDCN 30-9069180-000 (use oaproperly Identlled additionalsheets) or sketches is aceptable) . Quick Vent Closure Assermbly Woith Bearng.Plates SIN 76-00024.001-08-01
- 12. Remarks: Listed below are the number codes that apply to iha'repair activity Items shown on the front page (1i Babcock end Wilcox Cornoanv (3) ASCoEScilonCiod Ciass IlDivisitn I (4) Consairuut.on Code ASME*ii,. 1988 Editlon, 1960 Summer Addenda (5) Code Cases 1332-4, 1492, and 1369-1 (6) AREVA PIN for Closure Assembly 7079271-032 (7) Quick Vent Closure Assembly vith Bearino Plates SN 7600024-001-08-01 (8) AREVA NP. ]no (9) By others- FirstEnergy .
(10) See AREVA NP QA data packoages 23-9070650-000 CERTIFICATE OF COMPLIANCE LNic,k iP that to the bestofmrylorowledge ciiseito and belief thestateomentsmade in Ihisreport are correctend the repair, " modification or replacemsnt activities described above coneoens to SuclionXI of the ASPABCode and theNational boardInspection Ccdea"N" eslor. Nationsl Board Certificate oef.Authoeentlon No.hmcteose the "'R.stampcspirrMaly*1720*95 NR Certificate Holder AEYA Ne fn (name) " Da(eAptrllh3009 Signed 4AS . Mcnascr CA1OC rttle)n (authoreizedropsesooletive) (title)
], thomrea 0 Los holding a valid commission issue by CERTIFICATE OF INSPECTION N yThe National Board of` oiler end Pressure Vessel Inspectors and critilcate oefomppetosy issued by thojurisdiction ef oedfsiemployedbyUjVql oflatford. T have nespected the repair, modirteation or replacement describe in thisreport onh.tL 2* E1 andstatethatto thebest of my knowledge and bliert thisrepair, modificellonor replacement actlivilthas hee completed in accoedancewith Section X1of tho ASME Code endthe National Bserd.tsnpectiso Ca*d 14,Rtca.
By signing this certifieate, neither the undersigned normy employer makesanywarranty, expressed or Impliled,concering the workdnoribMdin this report. Frrthurmore. neither the undersigncd normy employerrsbtl beliable in any moaner fur any personal injuy, property damage or tlos ofany kindarising from orconnected with this inspection. D*ate. - Olgond QiSS1 be ... o oie s( N1 Niional OhioC aome n33511N LA
.- knrcn~) ord(Sort.eodorarmrnoLJoniadtlonati (NtQlatl 3ooa oN.n )}}