Text

Cycle 15 and Refueling Outage 15 Inservice Inspection Summary Report
	ML081290415
Person / Time
Site:	Davis Besse
Issue date:	04/29/2008
From:	Allen B; FirstEnergy Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-08-136
	Download: ML081290415 (239)
	v • d • e

{{#Wiki_filter:FENOC F0NO % 5501 North State Route 2 FirstEnergyNuclear Operating Company Oak Harbor,Ohio 43449 Barry S. Allen 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 April 29, 2008 L-08-136 10 CFR 50.55a ATTN: Document Control Desk United States Nuclear Regulatory Commission Washington, D. C. 20555-0001

SUBJECT:

Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Davis-Besse Nuclear Power Station Cycle 15 and Refueling Outage 15 Inservice Inspection Summary Report In accordance with the 1995 Edition, 1996 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI, IWA-6000, "Records and Reports," enclosed is the summary report covering inservice inspection activities performed during operating Cycle 15 and Refueling Outage 15 for the Davis-Besse Nuclear Power Station. This report provides a summary of the inservice inspection nondestructive examinations, once through steam generator tubing eddy current examinations, pressure tests, and repairs/replacements. 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, rS. Allen

Enclosure:

ISI Summary Report cc: NRC Region III Administrator NRC Resident Inspector NRR Project Manager Utility Radiological Safety Board Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison) A ISI

SUMMARY

REPORT CYCLE 15 and REFUELING OUTAGE 15R (15 RFO) OUTAGE START DATE: December 30, 2007 OUTAGE COMPLETION DATE: February 14, 2008 REPORTING DATE: May 14, 2008 DAVIS -BESSE NUCLEAR POWER STATION 5501 North State Route #2 Oak Harbor Ottawa County, Ohio 43449 OWNER: FIRSTENERGY NUCLEAR GENERATION CORPORATION OPERATED BY: FIRSTENERGY NUCLEAR OPERATING COMPANY 76 South Main St. Akron, Ohio 44308 NRC DOCKET NUMBER: 50-346 OPERATING LICENSE: NPF-3 COMMERCIAL OPERATION: July 31, 1978 Page 1 of 238

15 RFO Inservice Inspection Summary Page 2 of 238 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: C. T. Daft Signature Date Reviewed By: D. J. Munson D4 Signature Date Approved By: T. A. St.Clair -1 . . Supervisor - Programs Signature Date Approved By: S.T. Plymale ýa (Irta/ o [y q -*y-..vy Manager - Technical Services Signature Date

15 RFO Inservice Inspection Summary Page 3 of 238 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 ................................................... Abstract Section 2 .................................................................... Steam Generator Eddy Current Section 3 .......................................................................... NDE M anual Examinations Section 4 ............................................................................................. Pressure Tests Section 5 ................................... Repairs and Replacements

15 RFO Inservice Inspection Summary Page 4 of 238 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 15 and the 1 5 th Refueling Outage at the Davis-Besse Nuclear Power Station. The Inservice Inspection Program 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 period of the Third Ten Year Inservice Inspection Interval which ends on May 20, 2009. The Inservice Inspection Program nondestructive examinations, eddy current examinations, and pressure tests were performed by AREVA, First Energy Nuclear Operating Company (FENOC) and Structural Integrity Associates personnel from April 2006 through completion of 15R on February 14, 2008. The NDE examinations consisted of Ultrasonic (UT), Liquid Penetrant (PT), Magnetic Particle (MT), and Visual (VT-1, VT-2, VT-3). Preservice and Inservice Inspection examinations of approximately 154 ASME Class 1 and 2 components were performed. A general visual examination of the Containment Vessel interior surface was also contacted. All examinations met the acceptance criteria of ASME Section XI. During application of a Full Structural Weld Overlay t6 the Decay Heat Drop Line Nozzle Alloy 600 dissimilar metal weld, water seepage was noted. The welding was stopped and an ultrasonic examination performed. This examination revealed a through wall axial flaw in the Alloy 600 weld material. This flaw was subsequently repaired through the application of a Full Structural Weld Overlay. Approximately 73 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. No leakage exceeding the acceptance standards of IWB-3522 was noted during the conduct of these tests. One Hundred (100) percent of the in-service tubing in both OTSG's was eddy current examined during the 15 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 1 5 th Refueling Outage, 46 tubes in Steam Generator 1-2 and 35 tubes in OTSG 1-1 were removed from service. All repairs/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 available in the FirstEnergy Enterprise Records Management System.

15 RFO Inservice Inspection Summary Page 5 of 238 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-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules

1. Owner FIRSTENERGY NUCLEAR GENERATION CORPORATION. 76 S. MAIN ST., AKRON. OHIO 44308 (Name and Address of Owner)

2. Plant DAVIS BESSE NUCLEAR POWER STATION, OAK HARBOR, OHIO 43449 (Name and Address of Plant)

3. Unit #1 4. Owner Certificate of Authorization (if required) N/A

5. Commercial Service Date July 31, 1978 6. National Board Number for Unit N/A

7. Components Inspected CLASS 1 STEAM GENERATOR TUBING Manufacturer Component or Manufacturer Or Installer State or National Appurtenance or Installer Serial No. Providence No. Board No.

OTSG 1-1 BABCOCK & WILCOX 620-0014-055 N/A N-159 Unit #2 OTSG 1-2 BABCOCK & WILCOX 620-0014-055 N/A N-158 Unit #1 Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in, x 11 in., (2) information in items 1 through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets recorded at the top of this form.

15 RFO Inservice Inspection Summary Page 6 of 238 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-1 (back)

8. Examination Dates January 2008

9. Inspection Interval from September 21. 2000 to September 20. 2012

10. Applicable Editions of Section XI 1995 Addenda Throu2h 1996

11. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.

SEE ATTACHED

12. Abstract of Conditions Noted.

SEE ATTACHED

13. Abstract of Corrective Measures Recommended and Taken SEE ATTACHED Certificate of Authorization No. (if applicable) N/A Expiration Date N/A We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code, Section XI.

Date -, - Signed FIRST ENERGY NUCLEAR By C.' . 42Ž. r¢i.,-. OPERATING COMPANY Robert J. Najuch CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of OHIO and employed by Hartford Steam Boiler Inspection & Insurance Co. of Harford, Connecticut have inspected the components described in this Owners' Data Report during the period of January 2008, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Date 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 4 1i- b52q cq)4- Commissions I A r.DL&,A.

         ;"Inspector's Si'gnate                            National Board, State, Province and No.

15 RFO Inservice Inspection Summary Page 7 of 238 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 EDDY CURRENT EXAMINATION RESULTS The ASME Class 1 tubing in the Once-Through Steam Generators (OTSG's) at the Davis-Besse Nuclear Power Station Unit #1 was examined in January, 2008, during the 15th Refueling Outage (15RFO). The examinations were conducted by AREVA (formerly known as Framatome) to meet the requirements of the Davis-Besse Unit #1 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 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 steam generator during 15RFO. The Exam was similar in scope to the previous 14RFO OTSG inspection. The findings of the 15RFO inspection matched the post 14RFO Operational Assessment predicted behavior of the OTSGs since the number and size of flaws were similar to those predicted to be observed during 15RFO. The inspection results are recorded in Condition Report 08-33469. Roll transition cracking of three OTSG 2-A upper tubesheet rolls and two OTSG 1-B upper tubesheet rolls were observed. These indications were not large enough to leak at main steam line break accident conditions Tubes A- 117-108 and A-134-2 which had repair rolls previously installed were plugged due to significant changes in the original flaws that were located outside of the new pressure boundary that was established with repair roll. These outside pressure boundary indications were located above upper tubesheet repair rolls that were installed in a previous outage. These flaws are considered outside of the RCS pressure boundary and are located in tube ends. The indications had grown significantly in circumferential extent. To avoid the potential concern for leakage contribution for the large break LOCA accident conditions, these tubes were plugged. Davis Besse is licensed for repair roll joint slippage during accidents, but plugging these tubes makes the evaluation for large break LOCA leakage more easily managed in future outages. Tube end cracking was also observed at the tube end weld heat affected zone where PWSCC of 44 upper tube sheet tube ends in OTSG 2-A and 14 upper tube ends in OTSG 1-B were observed. No lower tubesheet tube ends were observed with PWSCC in either OTSG. Most of these indications were axial, however one circumferential indication was observed in the upper tubesheet tube end of tube A-100-1. This indication was not large enough to be a challenge to the tubing integrity. This damage mechanism only contributes slightly to leakage since only three tube end cracks were large enough to leak, however these indications pose no threat to steam generator integrity since the leakage must also pass the mechanical roll in the tubesheet. Eighteen repair rolls in OTSG 2-A and five repair rolls in OTSG had been found with the upper roll transition (heel transition) of the repair rolls containing axially oriented cracked. This was the first time a new repair roll had been observed to develop PWSCC, although such cracking was expected. None of these indications were large enough to result in predicted accident leakage. At the time of this inspection there were 117 repair rolls in service in OTSG 2-A and 23 in service in OTSG 1-B.

15 RFO Inservice Inspection Summary Page 8 of 238 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 Freespan Volumetric Degradation and Adjacent to Tube Support Plates (TSPs) was observed during 15RFO in the periphery just below the 15th TSP. There were 8 indications in OTSG 2-A and 10 indications in OTSG I-B. These indications were small and not a challenge to tube integrity. The volumetric Inner Granular Attack (IGA) is likely due to the presence of sludge deposits slowly building below the drilled region of the 15th TSP. One inside diameter volumetric indication was detected in the upper tubesheet repair roll transition of tube A-85-7. This indication was detected with plus point coil and was too small to be a concern for tubing structural integrity. During 15RFO, OTSG 2-A had 582 wear indications and OTSG 1-B had 347 wear indications reported by bobbin probe. All of the wear indications measured less than 40% Through Wall (TW). The largest wear indication in OTSG 2-A was 28% TW and 22%TW in OTSG 1-B. The Davis-Besse wear depths were not structurally limiting and wear growth is essentially zero. Axial Freespan ODSCC/IGA, (Outside Diameter Stress Corrosion Cracking/Inner Granular Attack) (Groove IGA), which was first discovered during 13RFO was observed during 15RFO. 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 when the OTSGs were manufactured. There were fifteen of these indications in ten tubes in OTSG 2-A and twenty-seven indications in seventeen tubes in OTSG 1-B. The observed flaws of this mechanism were not large enough to be a challenge to tube integrity. Where double rolls were installed in the lower tubesheet of OTSG 1-B, heel cracking of the second roll was not observed during 15RFO however one lower tube sheet axial roll transition crack in the normal one inch roll in OTSG 1-B was observed in tube B-90-54. Lower tube sheet roll cracking was first identified during 14 Mid-Cycle Outage (MCO). During the 14MCO exam, the first plus point rotating coil eddy current inspection of the lower tube to tubesheet expansions were performed. During 14MCO it was discovered that in OTSG 1-B, most of the lower tubesheet joints contained two mechanical hard roll expansions anchoring the tube to the tubesheet. Normally there is only one tube expansion in the original fabricated tube to tubesheet joint. Tubing containing two rolls to form the tube to tubesheet joints contain higher residual stresses than those joints containing only a single roll. Therefore cracking within tubing containing the two roll joints is more likely. Tube B-65-52 contained some observable plastic deformation below the upper tubesheet roll expansion. This deformation was believed to be the result of a robot anchor pin applying excessive load to this tube end while installing tubing sleeves in 1993. Additionally, tube B-87-60 also had plastic deformation of the tube wall with some volumetric extent to the indication approximately 0.6 inches from the lower tube end from a robot anchor pin from work performed in 2006. To avoid the potential for PWSCC formation in this area of plastic deformation in the future, these tubes were plugged. The current robot anchor pinwas redesigned since 1993 to reduce the potential for plastically deforming tubing; however this issue will continue to be monitored for recurrence in the future. No other tubes displayed similar deformation. Tube A-143-12 had a foreign material impact penetration in the interior of the tube wall approximately 0.7 inches from the upper tube end. This impact was in the tube to tubesheet mechanical roll and did not challenge the tubing integrity. Based on eddy current inspection results and analysis, no tubing defects were large enough to meet the In-Situ pressure testing screening criteria threshold as defined in the Davis-Besse 15RFO In-Situ Selection

15 RFO Inservice Inspection Summary Page 9 of 238 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 document. Testing is required for large flaws to demonstrate that there was a margin of safety to provide assurance of their structural integrity. There were 39 tubes that were reworked and saved for service with the repair roll process in OTSG 2-A and 13 tubes that were saved for use by repair rolls in OTSG 1-B. There were 46 newly plugged tubes in OTSG 2-A and 35 newly plugged tubes in OTSG 1-B that were plugged as a direct result of the eddy current inspection findings. The 15RFO rework actions bring the cumulative plugging to 625 (4.0%) tubes plugged in the 2-A Steam Generator, and 279 (1.8%) plugged tubes in the B Steam Generator. There are 15,457-originally supplied tubes in each OTSG. No plugging limit was exceeded. The 15RFO rework actions brought the cumulative in service repair rolls to 131 in OTSG 2-A and 31 in OTSG 1-B Table 1: Number and Extent of Steam Generator Tubes Inspected During 15RFO: Davis Besse 15RFO Eddy Current Exam Scope OTSG 2-A OTSG 1-B Inspection of all newly installed repair rolls. 39 13 Periphery AFW Header to tube gap analysis to determine if the header 382 411 is moving. Full length bobbin examination of all in-service non-sleeved tubing. 14878 15213 Full length bobbin examination of 100% sleeves. 199 212 Plus Point probe exam of the sleeve at the point of entry (USE) and 199 212 parent tube pressure boundary portion extending approximately 6 inches past the sleeve end (LSE) of 100% of the sleeves (the parent tube between the bottom of the upper most sleeve roll and the t Plus Point probe inspection of non-sleeved in-service upper tube roll 14679 15001 expansions (100%) including non stress relieved upper repair roll expansions and factory re-rolls. Plus Point probe coil examination of 29% of the non-sleeved in- 4257 4351 service tubes in the upper tube sheet region from tube end including tube end, upper roll expansion and crevice to upper tube sheet exit. Plus Point probe inspection'of 25% of the in-service stress relieved 3721 0 lower tube roll expansions and tube ends in OTSG 2-A. Plus Point probe inspection of in-service stress relieved lower tube roll 0 15213 expansions and tube ends in OTSG 1-B 100%. Plus Point probe coil examination of the tubes bordering the sleeve 91 81 region. Plus Point probe coil examination of all of the flaw-like indications (I 537 506 codes, new dents, new Manufacturing Burnish Marks (MBMs) and wear per the DA) reported from bobbin.

15 RFO Inservice Inspection Summary Page 10 of 238 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 15RFO Eddy Current Exam Scope OTSG 2-A OTSG 1-B Plus Point probe coil examination of all Non Quantifiable Signals 62 86 (NQSs) and MBM indications above 14S. Plus Point probe coil examination of all Non Quantifiable Signals 0 149 (NQSs) and MBM indications above 10S -2" in outer 30 rows (expansion in OTSG 1-B only). Plus Point probe coil examination of all dent indications below 14S 208 179 (100% sample of all previously reported and new dents using a greater than or equal to 2.5 volt bobbin threshold). Plus Point probe coil examination of all dent indications greater than 316 416 or equal to 1 volt between 14S and UTE in the non-periphery region. Plus Point probe coil examination of all dent indications greater than 26 19 or equal to 0.5 volts between 14S and UTE in the periphery region. Plus Point probe coil sample inspection of lower tubesheet sludge pile 1192 1294 region tubes from LTS -3.00" to LTS +3.00 or to top of sludge pile to encompass the sludge depth. Sleeve Bobbin and Plus Point probecoil inspection of all previously 0 40 identified gross mean distortions (GMD) (39 tubes OTSG 1-B - one

.new GMD was reported during 15RFO).

Plus Point probe coil inspection of all previously identified and new 0 23 magnetic stain (MAG) indications (23 tubes OTSG 1-B) Plus Point probe inspection of 50% of the Hot Leg rolled Plugs. 280 117 Visual Welded Plug Exam (VT-1) (100%) 33 19 Visual Plug exams of all Plugs in Upper and Lower (100%) 1158 488 Total Exams 42257 54043

15 RFO Inservice Inspection Summary Page 11 of 238 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-i OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules

1. Owner FIRSTENERGY NUCLEAR GENERATION CORPORATION. 76 S. MAIN ST., AKRON, OHIO 44308 (Name and Address of Owner)

2. Plant DAVIS BESSE NUCLEAR POWER STATION, OAK HARBOR, OHIO 43449 (Name and Address of Plant)

3. Unit #1 4. Owner Certificate of Authorization (if required) N/A

5. Commercial Service Date July 31, 1978 6. National Board Number for I nit N/A

7. Components Inspected NDE EXAMINATIONS Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Providence No. Board No.

REACTOR VESSEL BABCOCK & WILCOX C24-2013-52-1 N/A N-152 CLOSURE HEAD OTSG 1-2 BABCOCK & WILCOX 620-0014-55 N/A N-158 Unit #1 PRESSURIZER BABCOCK & WILCOX 620-0014-59 N/A N-157 CLASS 1 PIPING BABCOCK & WILCOX VARIOUS N/A N/A CLASS 2 PIPING ITT GRINNELL VARIOUS N/A N/A Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets recorded at the top of this form.

15 RFO Inservice Inspection Summary Page 12 of 238 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-1 (back)

8. Examination Dates May 2006 to February 2008

9. Inspection Interval from September 21, 2000 to Sentember 20, 2012

10. Applicable Editions of Section XI 1995 Addenda Through 1996

11. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.

SEE ATTACHED

12. Abstract of Conditions Noted.

SEE ATTACHED

13. Ab'stract of Corrective Measures Recommended and Taken SEE ATTACHED Certificate of Authorization No. (if applicable) N/.. Expiration Date N/A We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code, Section XI.

Date y- I0. ,6 Signed FIRST ENERGY NUCLEAR B Ry J.ANauch OPERATING COMPANY Robert J. Najuch CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of OHIO and employed by Hartford Steam Boiler Inspection & Insurance Co. of Harford, Connecticut have inspected the components described in this Owners' Data Report during the period MAY 2006 to FEBRUARY 2008, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Date 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 4 o-1

                                                                                  "   T A-,      oo
              -\tt-nfý          (140)1       Commissions      tR -_3ý51
         -Ins'pector' s Si*-tuVe -1                        National Board, State, Province and No.

15 RFO Inservice Inspection Summary Page 13 of 238 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 since the end of 14R (April 27, 2006) through the completion of 15R (February 14, 2008) at the Davis Besse Nuclear Power Station. These examinations were completed during the second period of the Third Ten Year Inservice Inspection Interval which commenced on June 1, 2006 and is scheduled to end on May 20, 2009. Inspections were performed to meet the requirements of ASME Section XI, 1995 Edition through the 1996 Addenda. The number and percentage of ASME Class 1 and 2 and Containment examinations completed are outlined below. K Davis-Besse, Nuclear Plant Completion Code Compliance Summary,- 3rd Interval - 2nd Period IS1 - Code Edition - 1995 Editionll 996 Addenda Period 2 Total Total Total Cumm % Comp. to Cat. Item No. Description Required Sched Comp Sched Comp. Date Reactor Vessel B-A B1.11 Circumferential Shell Welds 3 0 0 0 0% 0% B-A 131.21 Reactor Vessel 1 0 0 0 0% 0% Circumferential Head Welds Reactor Vessel Shell-to-B-A B1.30 Flange Weld 1 0 0 0 0% 0% Reactor Vessel Head-to- 10 Flange Weld 0 0 0% 0% B-A Pressure Retaining Welds 6 0 0 0 0% 0% Total in Reactor Vessel Pressurizer Shell-to-Head 1 1 0 1 50% 50% Welds Circumfrential Pressurizer Shell-to-Head 1 1 0 1 50% 50% Welds Longitudinal Steam Generators (Primary B-B B2.31 Side) Head Welds 0 1 0 0 0% 100% Circumferential Steam Generators (Primary B-B B2.40 Side) Tubesheet-to-Head 0 0 0% 50% Weld B-B Pressure Retaining Welds in Vessels Other Than 3 4 0 2 29% 58% Total Reactor Vessels Reactor Vessel Nozzle Inside Radius Section 8 0 0 0 0% 0% Pressurizer Nozzle-to-Vessel Welds 2 3 0 1 20% 60% Pressurizer Nozzle Inside Radius Section 3 2 0 0 0% 40% Steam Generators (Primary B-D B3.130 Side) Nozzle-to-Vessel 2 4 0 1 17% 67% Welds Steam Generators (Primary B-D B3.140 Side) Nozzle Inside Radius 6 2 4 0 1 17% 67% Section

15 RFO Inservice Inspection Summary Page 14 of 238 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 -P2nd Period ISI - Code Edition:" 1995: Edition/I 996. Addenda Period 2 Total Total Total Cumm % Comp. to Cat. Item No. Description Reauired Sched Como Sched Como. Date B-D B3.90 Reactor Vessel Nozzle-to-Vessel Welds 8 8 0 0 0 0% 0% B-D Full Penetration Welded Total Nozzles in Vessels - 38 25 13 0 3 8% 35% Inspection Program B Reactor Vessel NPS 4 or B-F B5.10 Larger Nozzle-to-Safe End 2 2 0 0 0 0% 0% Butt Welds Pressure Retaining B-Fa Dissimilar Metal Welds in Vessel Nozzles 2 2 0 0 0 0% 0% Reactor Vessel Closure B-G-1 B6.10 HedNt Head Nuts 60 24 36 0 12 20% 60% B-G-1 B6.180 Pumps Bolts and Studs 16 8 8 0 0 0% 50% B-G-1 B6.200 Pumps Nuts, Bushings, and 16 8 8 0 0 0% 50%

                    'Washers .

Reactor Vessel Closure Studs, when removed 60 24 36 0 12 20% 60% B-G-1 B6.40 Reactor Vessel Threads in Fag Flange 1 1 0 0 0 0% 0% Reactor Vessel Closure Washers, Bushings 62 24 38 0 12 20% 62% B-G-1 B6.60 Pressurizer Bolts and Studs 12 4 8 0 4. 34% 67% B-G-1 B6.80 Pressurizer Nuts, Bushings, and Washers 12 4 8 0 4 34% 67% B-G-1 Pressure Retaining Total Bolting, Greater Than 2 in. 239 97 142 0 44 19% 60% In Diameter Steam Generators Studs, and Nuts Bolts, 4 2 2 0 1 25% 50% B-G-2 Pressure Retaining Total Bolting, 2 in. and Less In 4 2 2 0 1 25% 50% Diameter B-J B9.11 Piping NPS 4 or Larger Circumferential Welds 34 22 14 0 3 9% 42% B-J B9.21 Piping Less Than NPS 4 Circumferential Welds 42 18 24 0 11 27% 58% Piping Branch Pipe B-J B9.31 Connection Welds NPS 4 or 2 0 2 0 1 50% 100% Larger Piping Branch Pipe B-J B9.32 Connection Welds Less 11 4 7 0 3 28% 64% Than NPS 4 B-J B9.40 Piping Socket Welds 11 4 7 0 3 28% 64% B-J B9.50 Full Structural Weld Overlays 10 10 0 0 0 0% 0% B-J Pressure Retaining Welds 110 58 54 0 21 20% 50% Total in Piping ,, ,.. ,*,* a,* Pressure Vessels Welded D-r\ DIU. IV 2 2 0 0 0 0% 0% Attachments

15 RFO Inservice Inspection Summary Page 15 of 238 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 Plan~t Completion Code Compliance Summary - 3rd Interval -2nd Period ISI - Code: Edition - 1995 Editionll 996 Addenda Period 2 Total Total Total Cumm % Comp. to Cat. Item No. Description Reauired Sched Comin Sched Comin. Date B-K B10.20 Piping Welded Attachments 3 1 3 0 2 67% 100% Welded Attachments For Total Vessels, Piping, Pumps, and Valves 5 3 3 0 2 40% 60% B-L-1 B12.10 Pumps Pump Casing Welds 4 4 0 0 0 0% 0% (B-L-1) B-L-1 Pressure Retaining Welds Total In Pump Casings 4 4 0 0 0 0% 0% Reactor Vessel Vessel 3 1 2 0 1 34% 67% Interior (B-N-1) B-N-I Interior of Reactor Vessel 3 1 2 0 1 34% 67% Total Reactor Vessel(PWR) B-N-2 B13.60 Interior Attachments Beyond 12 12 0 0 0 0% 0% Beitline Region (B-N-2) Welded Core Support B-N-2 Structures and Interior Total Attachments To Reactor 12 12 0 0 0 0% 0% Vessels B-N-3 B13.70 Reactor Vessel (PWR) Core 1 0 0 0 0% 0% Support Structure (B-N-3) B-N-3 Removable Core Support Total Structures 1 1 0 0 0 0% 0% Reactor Vessel Welds in 16 11 5 0 1 7% 32% CRD Housing B-O Pressure Retaining Welds Total In Control Rod Housings 16 11 5 0 1 7% 32% Pressure Vessels Shell 5 4 1 0 20% 20% Circumferential Welds Pressure Vessels Head 0 1 0 1 100% 100% Circumferential Welds C-A C1.30 Pressure Vessels 2 1 1 0 0 0% 50% Tubesheet-to-Shell Welds C-A Pressure Retaining Welds 8 Total In Pressure Vessels 5 3 0 2 25% 38% Nozzles Without Reinforcing Plate in Vessels > 1/2in. Nominal Thickness - Nozzle 4 1 3 0 2 50% 75% to Shell Weld Nozzles Without Reinforcing Plate in Vessels > 1/2 in. Nominal Thickness Nozzle 2 1 1 0 1 50% 50% Inside Radius Section Nozzles With Reinforcing Plate in Vessels > 1/2in. C-B C2.31 Nominal Thickness 4 0 1 25% 50% Reinforcing Plate Welds to Nozzle and Vessel

15 RFO Inservice Inspection Summary Page 16 of 238 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-Be~sse Nuclear Plant Completion Code 'Compliance,Summary -3rd Interval - 2nd Period ISI - Code Edition - 1995 Editionll 996:Addenda Period 2 Total Total Total Cumm % Comp. to Cat. Item No. Description Reauired Sched Como Sched Comp. Date Nozzles With Reinforcing Plate in Vessels > 1/2in. Nominal Thickness Nozzle-to-Shell (or Head) Welds 6 2 4 0 2 34% 67% When Inside of Vessel Is Inaccesible C-B Pressure Retaining Nozzle Total Welds In Vessels 16 6 10 0 6 38% 63% Pressure Vessels Integrally C-C C3.10 0 1 0 0 0% 100% Welded Attachments C-C C3.20 Piping Welded Attachments 28 12 16 0 6 22% 58% Pumps Integrally Welded C-C C3.30 3 1 2 0 2 67% 67% Attachments Welded Attachments For C-C Vessels, Piping, Pumps, 32 13 19 0 8 25% 60% Total and Valves C-D C4.30 Pumps Bolts and Studs 12 12 0 4 0 0% 0% C-13 Pressure Retaining Total Bolting, Greater Than 2 in. 12 12 0 4 0 0% 0% In Diameter Piping Welds >/= 3/8in. Nominal Wall Thickness for Piping > NPS 4 4 2 2 0 1 25% 50% Circumferential Weld Piping Welds < 3/8 in. & > C-F-I C5.1 A 1/5 in. Nominal Wall Thickness for Piping > NPS 28 12 16 0 6 22% 58% 4 Circumferential Weld Piping Welds <= 1/5 in. C-F-1 C5.11B Nominal Wall Thickness for 13 5 8 0 3 24% 62% Piping > NPS 4 Circumferential Weld Piping Welds >1/5in. Nominal Wall Thickness for Piping >/= NPS2 and </= 23 12 1-2 0 3 14% 53% NPS4 Circumferential Weld Piping Welds <1/5in. Nominal Wall Thickness for Piping >/= NPS2 and </= 13 5 8 0 2 16% 62% NPS4 Circumferential Weld C-F-1 C5.30 Socket Welds 8 4 4 0 2 25% 50% Pipe Branch Connections of C-F-1 C5.41 Branch Piping>/= NPS 2 2 1 1 0 1 50% 50% Circumferential Weld C-F-1 Pressure Retaining Welds C-F-I In Austenitic Stainless Steel or High Alloy Piping 91 41 51 0 18 20% 57% Piping Welds >/= 3/8in. Nominal Piping > Wall NPS 4 Thickness for 20 8 12 0 4 20% 60% Circumferential Weld(1)

15 RFO Inservice Inspection Summary Page 17 of 238 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 - 2nd Period ISI!- Code Edition - 1995 Editionll 996 Adden'da Period 2 Total Total Total Cumm % Comp. to Cat. Item No. Descriotion Recauired ' Sched Como Sched Como. Date Piping Welds < 3/8 in. Nominal Wall Thickness for Piping > NPS 4 4 6 0 2 20% 60% Circumferential Weld Pipe Branch Connections of C-F-2 C5.81 Branch Piping >/= NPS 2 1 1 0 0 0% 50% Circumferential Weld Pressure Retaining Welds Total In Carbon or Low Alloy Steel Piping 13 19 0 6 19% 60% C-G C6.10 Pumps Pump Casing Welds 1 2 0 2 67% 67% C-G C6.20 Valves Valve Body Welds 2 2 0 0 0% 50% C-G Pressure Retaining Welds Total in Pumps and Valves 3 4 0 2 29% 58% E-A E1.11 Accessible Surface Areas 0 2 0 1 50% 100% E-A E1.12 Accessible Surface Areas 0 0 0 0% 0% E-A 1 Toa Containment Surfaces Total 2 0 1 34% 67% Required Augmented E-C E4.12 Examination, Surface Area Grid, Minimum Wall 1 1 0 0 0% 50% Thickness Location Containment Surfaces Total Requiring Augmented Examination I I 0 0 0% 50% E-D E5.30 Moisture Barriers 2 0 0 0 0% 0% E-D Seals, Gaskets, And Total Moisture Barriers 2 0 0 0 0% 0% E-G E8.10 Bolted Connections 25 32 0 10 18% 57% E-G Pressure Retaining Bolting 25 32 0 10 18% 57% Total F-A F1.10 Class 1 Piping Supports 12 15 0 5 19% 56% F-A F1.20 Class 2 Piping Supports 33 49 0 16 20% 60% Supports other than Piping F-A F1.40 10 11 0 5 24% 53% Supports(Class 1,2,and MC) F-A Supports 130 55 75 0 26 20% 58% Total Grand 839 402 441 4 154 19% 53% Total

15 RFO Inservice Inspection Summary Page 18 of 238 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 15 and the 1 5th Refueling Outage are identified on the attached table. Conditions requiring evaluation are noted in the referenced Condition Reports.

15 RFO Inservice Inspection Summary Page 19 of 238 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 sRRA (Rqoverage < iaeliet Reqjuest RR-A2 is applicable. Accept Coverage < 90%. Relief Request RR-A5 is applicable. isV 2 B03.140,219400 RG-SG- t-2G-50-Z//W-lR ~15-\/T-1 78 1/1'9/2'608 N/iA Accept\ Examination Category B-G-1, PressureRetaining Bolting, Greater Than 2 in. In Diameter ISI B06.010.094600 RC-RPV-NUT-025 15-VT-138 1/14/2008 N/A Accept ISI B06,010.094700 RG-RPV-NUT-026 15-VT-139 1115/2008 N/A ISI B06,010.094800 RC-RPV-NUT-027 15-VT-10 I1i2008 N/A Accept ISI B06,010.094900 RC-RPV-NUT-028 15-\T-143 1/14/2008 N/A ISI B06.010.095500 RC-RPV-NUT-029 15-VT-127 1/141/2008,. N/A Accept SI5 B06.010.095100 RC-RPV-NUT-030 15-VT-131 1/14/2008 N/A S51 ~B06.bio'0-095'2D0" RC-RPV-NUT 1-031 15AfT1 32 I14/20ý08 N/ Accept Accept ISI B06.010.095300 RC-RPV-NUT-032 15-VT-144 1/14/2008 N/'A Accept IsK [306.O06.09054bO RC-RPV-NUT-033 15-VT-1 45 ~7411 4/20o& N/A Accept is] B06,010.095500 RC-RPV-NUT-034 15-VT-1463 1/142008 Nl/Aý I B0&01.095600 RC,-RPV-NUT -03~ 15V-4 / 14Y0 / IS! B06.010.095700 RC-RPV-NUT-036 1447'V 1/14/2008 N/A

15 RFO Inservice Inspection Summary Page 20 of 238 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 0avis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 ISI B06.080.820000 RC-PZR-NUT-6 15-VT-087 1/2/2008 N/A Accept F S / B06.08b.820106 RC-PZR-NUT-i > 15-VT-086 1/21/2008 ~N/A Accept I

15 RFO Inservice Inspection Summary Page 21 of 238 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 PSI B09.050.010243 RC-PZR-WP-102 OVERLAY lb-VENDOR- 1/20/2008 N/A Accept 051 PSIl B09.050.610244 RC-PZR-VP-23 QVERýLAY 5-VENDOR-

1. 1/1012008 NiA" Accep~t

15 RFO Inservice Inspection Summary Page 22 of 238 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #l, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 058 Exmnto aeoyBK Welded Attachments for Vessels, Pipjng,~Pumps,and~Valves ISI B10.020.715500 RC-MK-A-135-PS-H29-AW 15-PT-033 1/5/2008 N/A Accept dSi >B10.020.719000 CF-33B CCA-6-.H7-AW ~ 1'5-PT-651 1)16/2008 rN/A Accepti Examination Category B-N-I, Interior of Reactor Vessel iti CB13.010.381000 RCeRPV-iNTERgCRW R1i5-Vt-108 H1/10/2008 N/A Accpts Examination Category B-0, Pressure Retaining Welds in Control Rod Housings ISh B14,01O0,717~00 1RC-RPV-I "RD-\ H--9B53754, 15ý;_PTqc f 1/1712008 N/'A Accept

15 RFO Inservice Inspection Summary Page 23 of 238 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 POWER STATION UNJIT #1 Class 2 Exami~nations ~ 15th. Refueling Outage Wobrk Summary Number ComponentlID v&Examination Exam Condition Final Status Cmet ~Scope ~ Report Date. Report f*Number ume Examination Catego~ry C-A, Pressure R~etaining~Welds in PressureVessels ISt C01.010.220500 SP-SG-1-2-WG-8-3 15-UT-052 1/17/2008 N/A Accept

   >iS1'    7C01.020.265300. DH-COOLE 'R-1-1-WEL~DA                         I_5-U 'T-007' 12/201/20,017          N/A       Accept Examination Category C-B, PressureRetaining Nozzle Welds in Vessels IS1      C02.021.2209o00>  SP-SG1( -Gý  ~     3X                          1~5-MT-0089Ii         I I/1J/00M~     N/A      Accept ISI      C02.021.220900    SP-SG-1-2-WG-23-)/Y                            15-UT-029          1/11/2008          N/A      Accept ISI      002.b21.790700 \SP-SG-1-2LM0K-300 TO MK-1          ___15-MT-007                >     1/9,2O08          N/A      Accept ISl      C02.021.790700    SP-SG-1-2-MK-300 TO MK-1                       15-UT-026          1/11/2008          N/A      Accept 151     C02.022,221 100   SP-SG-1-2-W*G-23-X/YIR                         15-UT-038          1/15/2008         N/A       Accept ISI      C02.031.266100 DH-COOLER-1-1-WELD I                              15-PT-003        12/19/2007          N/A       Accept Examination Category C-C Welded-Attachments For Vessels, Piping, Pumps,2and Valves is[      C03.020.110900 DH-33A-HCB-2-H35-AW                 *,            15-PT-019        12/19/2007          N/A       Accept 151        wC0.02.5~0                                                     15-PT-01~7       12/20/2007          NI/_      Accept 151      003.02-0.28-9400  DH-33A-HCB-2-H34-AWV                           15-PT-009        12/18/2'007         N/A       Accept I    0Q3.020.3121 00  MS-3?A-EB TB-1-28-SR1 9-AWA                   1~5-MT-004      _1/7/2008             t4/A'     Accept ISI      C03.020.337400    MS-3A-EBB-2-H14-AW                            15-MT-005            1/7/2008         N/A       Accept 0S      cw03;20.36780Q    DH-33B-GCt1B- I -HI9-AW               N        15-PTbOIO0       12/18 -20~07        N/A     NAccept IS1      C03.030.268100    HP-PUMP-i-I-WELD E                             15-PT-006        12/18/2007          N/A       Accept Examination Category C-F-I,     PressureRetaining Welds in Austenitic Stainless Steel or High Alloy Piping si .C05.011.235200        DH-33B-CCB--5-SWA
                                      .*1*/2008                                15-PT-038                               /&     Aqccept.

ISl C05.011.235200 DH-33B-CCB-6-5-SWA 15-UT-021 1/10/2008 N/A Accept ISl C05.1 1A.144100 DH-33A-GCB-8-3-SWC 15-PT-013 12/18/2007 N/A Accept 151 C05,11IA.144 100 DH-33A-GCB-8-3-SWC 'I15-UT -009- 12/18/2007 N/A Accept 151 005.141A 933700 DH-33B-GICB-10-1 1-SW0%/ ,N15-PTb-021t 12/1 19/21007' N/A Accept IS1 C05.1 1A.193700 DH-33B-GCB-10-11-SWC 15-UT-005 12/19/2007 N/A Accept JSI c05 .iA.2011~00 DH+33B-GC 'B-10-12-FV51G 15-PT-004 <12/19/2ob7 N4A t 'Accept' is] C05.11A.201100 DH-33B-GCB-10-12-FW51G 15-UT-010 12/21/2007 N/A Accept IS C05.11A.208700 DH-33B-GCB-I0-19-SW+/-H 15-PT-026 12/31/2007 N/A Accept 151 005.11A.208700 DH-33B-GOB-10-19-SWH 16-UT-O15 1/4/2008 N/A Accept LS1 V1Aý2679Q0o

b. CS-34-GCB_-ý_51-1SWA ~ 15-PT-0~2~2 12/i1786067 N/A AcieptVN .

15 RFO Inservice Inspection Summary Page 24 of 238 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 Ii C5Ub.021.15bbUU HP-33U-UUB-2-b-6WA lb-P I-024 12/18/2007 N/A Accept Limited Examination - No Credit take for the Examination ISI C05.021 .166400 HP-33C-CCB-2-36VF14 15-R-iPT 02 3~ 12/iýAB07 N/A Ac~cept ISI C05.021.166400 HP-33C-CCB-2-36-FW14 15-UT-006 12/19/2007 N/A Accept ISI c05.2A.600900~ HP-4-GB-1 I-FWV7 15_-IPT-014& 12/r9/2007 N/A A~ccept~j SI C05.21A.932800 HP-33C-HCC-91-4-SWB 15-PT-008 12/18/2007 N/A Accept S1S 0_5_.03o.0026 _HP-C..-39.26 15-*.T-001" 12/18/2007 ". N,/A Accept IS1 C05.030.1 55800 HP-FSK-M-CCB-2-3-FW8 15-PT-012 12/19/2007 N/A Accept ISI C0.4.1'60 D[<3-C-- 7-WD1PT-0 11 12/18/2O007~ N/A~.~ Accept> ~ Examination Category C-F-2, PressureRetaining Welds in Carbon or Low Alloy Steel Piping ISI C05.051.297300 MS-3A-EBB-1-19-SVWA 15-MT-002 1/7/2008 N/A Accept 131 C05.051.297300__MIS-3A-EBB-1 SWA 15-UT-0 18 1/7/2008 NI/A Accept Is! c05.0b5 1.31 3980 0 FVV-7_EBB-3ý-1-FWV29 1!s-MT-oi1 ~1/1 5i2008~ N/A 7.Accept; ISl C05.051.339800 FW-7-EBB-3-1-FW29 15-UT-031 1/15/2008 N/A Accept IS C05.05105,351000 AF-6.. EBB - 6A . . 5-MT-009 11,9/2008 .. N/A<.. Accept IS! C05.051.351000 AF-6C-EBB-4-4-FW6A 15-UT-025 1/10/2008 N/A Accept IS 1 ... 5..051,358900 AF-ISIM2 206N-FV46 .15-MT.-006 1/92008 N/A Acc.ept 1S1 C05.051.358900 AF-ISIM2 206N-FW46 15-UT-030 1/11/2008 N/A Accept IS! 09.51A335 100 MS-3A-EBB72-13-SA

                                      *5"**3/2608                                    ..                        N/A      Accept IS!      C05.51A.335100      MS-3A-EBB-2-13-SWA                       15-UT-012         1/4/2008           N/A      Accept 11$(!,05.C.51 A. 337~6 00    MJS -3A-EB2      -SC                     15-MiT-0:03      118/2008      \_N/A          Acept

15 RFO Inservice Inspection Summary Page 25 of 238 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

15 RFO Inservice Inspection Summary Page 26 of 238 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 1Il 1:l .01.11

                       .YbU400 UV-IN I FI-UI-ULNEHIAL-V I                 1 -V 1-123 1/14/2008   08-33486 Accept  Peeling/ Flaking/ Chipped Paint -

No Rust Noted Examnination Ciktegot E-C, Containment Surfaces Requiring Augmented&Examinations < IS1 E04.012.080200 CV-INTERIOR-GAP 15-UT-057 1/24/2008 N/A Accept Fvaminqtinn Cntpnnrv F-r) Ronl/ (-akotz Annr Mnithirp Rnrriprz ISI E08.010.982100 CV-EP-PAP3FI-FLANGE- 15-VT-069 1/4/2008 N/A Accept _________ BOLTING 1STI E68.061'60.97b bJV-fP-P IC2L1-FLANJGE-'IOLTIfNG 15-VT-068 11A/4/2008 NT/A< Accpt~~ SI E08.010.983800 CV-EP-P1P2MI-FLANGE- 15-VT-076 1/4/2008 N/A Accept BOLTING SI E08.010.986200 CV-ESC-OUTER-DOOR-BOLTING 15-VT-161 1/16/2008 N/A Accept

15 RFO Inservice Inspection Summary Page 27 of 238 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 ISI I-U1.UZU.J'10,UU UH-,.i/A-L toU -b

                                                 -0 d                     ID-V I U    I ILILU/LUUI INI.

PSI~ F01.020.31 8300 DH-33B-HG3-i-H'3 15>-VTA00~4 3/l 2/2007 NI/A Accept PSI F01.020.321100 DH-33C-GCB-7-H7 15-VT-009 3/13/2007 N/A Accept ISl F0I ,020.326800 H-33C-COB~-2-5 15-TVT-034 12/20/2007 tiý/A Accept PSI F01.020.367400 DH-33B-GCB-1-H43 14-VT-338 10/6/2006 N/A Accept PSI F01.020.367700 DH-33B-GCB-1-H19 15-VT-006 3/20/2007 N/A Accept SI F01.020.367900 DH-33B-GCB3-1-H19 15-VT-027 12/27/2007 N/A Accept Thiread Engaigemnent Hole not Visible Fdl1.~d.68200 bTH-'33B-GCB-I :H22 15-T-07 /2/2007 NI/A Accept

  .... Sl     F01.020.368800 DH-33B-GCB-1-H34                             15-VT-026     12/27/2007 N/A PSI     FOA0120,3701 00 DH-33B-GCB-10-H3~2                          15-VT-008     3/22/2007  N/A   Accept F01.020.371300 DH-33B-GCB-10-HN 3                           15-VT-005     3/19/2007  N/A PSI ISl VPSI  % ~F 0 .0'2'Q. 3773 00 DH-33B-GCB-6-H1'                        15-VT-050 15-VT-040 12/20/2007 12/17/2007 N/A N/A Accept F01.020.379000 CS-34-GCB-5-H29 F01.020.443200 MS-3A-E1B-1 SR19                          15-VT-1 83     1/21/2008 N/IA  Accept F01 .020.444100 MS-3A-EBB-1 SR1 1                       15-VT-002      1/19/2007 N/A

15 RFO Inservice Inspection Summary Page 28 of 238 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-[ 1. 0 15- 1/%;W;JL

                                            -  I-            0                      ,-xUuejJL

15 RFO Inservice Inspection Summary Page 29 of 238 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 Code Cases were used during the performance of Class 1 and Class 2 Nondestructive Examinations. CODE CA1SE NYO.TIL N -307-3 Ultrasonic Examination of Class 1 Bolting, Table IWB-2500-1, Examination Category B-G-1 N-460 Alternative Examination Coverage for Class 1 and Class 2 Welds 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-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. N-619 Alternative Requirements for Nozzle Inner Radius (with limitations noted Inspections for Class I 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 of a Reactor Vessel N-624 Successive Inspections N-638-1 Similar and Dissimilar Metal Welding Using Ambient (As amended by Relief Temperature Machine GTAW Temper Bead Technique Request RR-A3 1) 1

15 RFO Inservice Inspection Summary Page 30 of 238 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 CODE CASE NO. TITLE N-639 Alternative Calibration Block Material (with limitations noted in NRC Regulatory Guide 1.147) N-652 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-695 Qualification Requirements for Dissimilar Metal Piping Welds N-740 Dissimilar Metal Overlay for Repair of Class 1, 2, and 3 (As amended by Relief Items Request RR-A30) ._I

15 RFO Inservice Inspection Summary Page 31 of 238 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-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules

1. Owner FIRSTENERGY NUCLEAR GENERATION CORPORATION, 76 S. MAIN ST.. AKRON, OHIO 44308 (Name and Address of Owner)

2. Plant DAVIS-BESSE NUCLEAR POWER STATION, OAK HARBOR, OHIO 43449 (Name and Address of Plant)

3. Unit #1 4. Owner Certificate of Authorization (if required) N/A

5. Commercial Service Date July 31, 1978 6. National Board Number for Unit N/A

7. Components Inspected SYSTIEM PRESSURE TESTS Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Providence No. Board No.

CLASS 1 BABCOCK & WILCOX VARIOUS N/A N/A PIPING/COMP CLASS 2 ITT GRINNELL VARIOUS N/A N/A PIPING/COMP ___ _____ i ___ ___ ___ Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets recorded at the top of this form.

15 RFO Inservice Inspection Summary Page 32 of 238 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-1 (back)

8. Examination Dates MAY 2006 to FEBRUARY 2008

9. Inspection Interval from SEPTEMBER 21, 2000 to SEPTEMBER 20, 2012

10. Applicable Editionsof Section XI 1995 Addenda Through 1996

11. Abstract of Examinations. Include a list of examinations and a statement concerning status of work required for current interval.

SEE ATTACHED

12. Abstract of Conditions Noted.

SEE ATTACHED

13. Abstract of Corrective Measures Recommended and Taken SEE ATTACHED Certificate of Authorization No. (if applicable) N/A Expiration Date N/A We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code, Section XI.

Date *-10. Signed FIRST ENERGY NUCLEAR By 0 '. E. . OPERATING COMPANY Robert J. Najuch CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of OHIO and employed by Hartford Steam Boiler Inspection & Insurance Co. of Harford, Connecticut have inspected the components described in this Owners' Data Report during the period MAY 2006 to FEBRUARY 2008, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Date 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 4-I/Ioi

      "                                         Commissions                    73z2s6? "I -L N " c*- ,v.

Inspector's Sl'gadt!e National Board, State, Province and No.

15 RFO Inservice Inspection Summary Page 33 of 238 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 FENOC personnel on Class 1 and Class 2 systems from May 2006 to February 2008 during Cycle 15 and the 15th Refueling Outage for the Davis-Besse Nuclear Power Station Unit #1. These tests completed a portion of the required tests for the second period of the Third Ten Year Inservice Inspection Interval which commenced on June 1, 2006 and is scheduled to end on May 20, 2009. 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 14, was utilized in the performance of those Class 2 tests associated 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 14 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 14 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 Revisions 14 was used when bolting was not removed for visual examination when leakage was noted at bolted connections during system leakage tests. Seven Class 1 Pressure Tests were completed. This represents all of the required Class 1 pressure tests for the Second Period of the Third Ten Year Inservice Inspection Interval. Sixty-Six Class 2 Pressure Tests were completed. This represents 77% of the required Class 2 pressure tests for the Second Period of the Third Ten Year Inservice Inspection Interval. No pressure boundary leakage was noted during the performance of these tests.

15 RFO Inservice Inspection Summary Page 34 of 238 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 Class 1 Pressure Tests LISI B1MO0O0.,CFO9' A CF09~ 15-VT--222. 1/30/2008 N/A Accept ISl B15.000.CF10 CFO0 ISI B15.000'.H14 DH14 4 ,15-VT-2-25 C113012008 N/A Accept 6I B 15.'0006.1H15DH15 15-VT-213 1/30/2008 08-34569 Accept Packing Leakage Noted 08-34566 131 15?000.DHi16 B1 DH16 \.15WVT224 1/3012008 _ N/A Accept ISI B15.000.RC01 RC01 15-VT-210 1/30/2008 08-34563 Accept Leakage at Valve Manifold I1S B 615.0010.,RCQd1 'RtO 1 15VTYT-211I 11ý0[2008 'N//A Accept~ IS1 B15.000.RC01 RC01 15-VT-212( .1/30/2008 08-34565 Accept Pipe Cap Leakage ISI BB15.000.RC01 RC01 15-VT-214 I1/3"0/2668 N/A " Accept Is[ B15.0006.RCO1 C0 15-VT-217 1/30/2008 08-34572 Accept Packing Leakage Noted 08-34569 08-34566 131 B 5 ---RC--

                         --- -- '                             5     -18     130/2008-
                                                                              /C0        08-34697   A cc&t Tail Pi'p Leak9g ISI       B15.000.RC01              RC01                   15-VT-220      1/30/2008    08-34613   Accept Packing Leakage and Tail Pipe 08-34567           Leakage Noted 08-34562 08-34564 is]       315.600b.RC01l            RQOI                  <15-VTI-221     1/30/2%008,      NI/A   AccepIt ISl       B15.000.RC13              RC13                   15-VT-226      1/30/2008    08-32418   Accept Component Cooling Water 08-32318           Residue / Packing Leakage 08-32407 08-32200 08-33208 08-33211 08-32427

15 RFO Inservice Inspection Summary Page 35 of 238 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 A d

1
LI *
Ib I I

            %.eU[.UUU                                                       1/ 141  ~Uf
                                                                                     /jUIJ ULAt:!L  UUUUII   I-Z)44 114    1b dPPI~dUIU I

15 RFO Inservice Inspection Summary Page 36 of 238 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

                                                                                                 /ALA.A!VL    vue Seakdbt: IN-4 lb dpi Valve Seat Leakage IS1    ~C07.gD00.         ,DW01                2 15-1 E5IVNDO -R-02,q     1/1~3/200       NI/A XAcept Code Case N-522 is appjjcable' SIl      C07.000.HP04               HP04                  15-V'i-094      1/6/2008       N/A  Accept 11 S        c<
            £,74!O.HP05                HP05         ~        15-VT-1,01      1/6/2008 zN/A       Accept Pa IS1       C07.000.HP06               HP06                  15-VT-227       2/8/2008  04-06210  Accept Packing Leakage Noted SIs      C,07.0O0J0THP7       'HP07                        5-VT-228 1~.             21/8/2008      N//N Accept P        n        a     N ISl       C07.000.HP08               HP08                  15-VT-229       2/8/2008  05-05731  Accept Packing Leakage Noted IS!       0_bfb67.00HP60             HP09                  1-5Wr 16'-

L 1/17/2008 -N/A Accept IS[ C07.000.HP10 HP10 15-VT-i162 1/17/2008 06-06394 Accept Packing Leakage Noted 08-33735

15 RFO Inservice Inspection Summary Page 37 of 238 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 ISl C07.000.MS07 MS07 15-VENDOR-007 12/20/2007 N/A Accept Code Case N-522 is applicable

"15-VlND*@I*iC41 1/5I 2ý08 N/A""ode Accept asu, is ap*c,* blec ISl C07.O00.MU02 MU02 15-VENDOR-017 1/5/2008 N/A Accept Code Case N-522 is applicable 007\.000.MU03 MU0 15-VENbOR-0218 1/5/2008 N/A Accept Code Case N-522 is applicable Is' 131 C;07.O00.MUO4 MU04 15-VENDOR-019 1/5/2008 N/A Accept Code Case N-522 is applicable AC07.000.MU05 Mvu05 15-VENDOR-021 1/7/2008 ThJN/A Accept Code Case N-522 is applicable ISl C07.000.UO6 MU06 15-VENDOR-022 1/3/2008 N/A Accept Code Case N-522 is applicable ISI C07.o0.0:0NNoI ~NN0l1 ~15~-VENDOJR-628 1//l 3/2bo8 N/A ~ AcetCd aeN-2sapial C07.000 RCO3 RCO3 15-VENDOR-047 12/2/2008 N/3A Accept Code Case N-522 is applicable

   )Sl      ~cb 'obo.RC04             R004. S     15-VENDOR-031       ~1/6/2008      '     N/A ~    jAccept CoVde sea NL2-2isapplicble C07.O0O.RCO5              RC05           15-VENDOR-010             1/12/2008       Ný/A       Accept Code Case N-522 is applicable ISl      007 Obi'0.RC06            RtO6          >15-VENDOR-03Q0         1/11/2008      >N/A ~ Accept Code Case N-522 is applicable C07.O0O.RCO7              R0             15-VENDOR-023          1/12ý/200          NAcepCoeasN-522                        is applicable ISl      G,07.600.fRCO8            RC08           15-VENIDOR-012            11/3?Aý_8    ~N/A          A~ccept Code Case    N-5ý22 is applicable, C07.000.SAOI              SA01           15-VENDOR-001         12/30/2007      07-32108       Accept Code Case N-522 is applicable.

Valve Seat Leakage 7700.~1 O' S F0 15VN0~

                                                                               /1r0f2008      'N/A         ccp      oeCsN -2iap~

ISI C07.000.SF02 SF02 15-VENDOR-044 -1/20/2008 N/A Ac~cep't Code Case N-522 is applicable

15 RFO Inservice Inspection Summary Page 38 of 238 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 REPLACEMENTS The following repairs and replacements on ASME Class 1 and 2 components were completed at the Davis-Besse Nuclear Power Station Unit #1 since May 2006 which marked the completion of the 14 th Refueling Outage and completion of the 1 5th Refueling Outage in February, 2008. During the application of a Full Structural Overlay on the Decay Heat Nozzle to Elbow Alloy 600 Dissimilar Metal Weld (DH-33A-CCA-4-1-FW1) water seepage was noted. A Procedure Demonstration Initiative (PDI) qualified augmented ultrasonic examination was performed to characterize the flaw. The flaw was characterized as an axial through-wall flaw in the Alloy 600 weld material. No other flaws were identified. This flaw was subsequently repaired by the application of a Full Structural Overlay Weld. Ultrasonic examination of the weld overlay identified a flaw in the weld overlay volume over the nozzle base material which was acceptable to the requirements of Table IWB-3514-2. 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. Order Number System Description 200003042 Main Feedwater Replaced Steam Generator 2 Main Feedwater Stop Valve FW601 Body/Bonnet Bolting 200003060 Main Feedwater Replaced Steam Generator 2 Main Feedwater Stop Valve FW612 Body/Bonnet Bolting 200008135 Decay Heat Replaced Suction and Discharge Flange Bolting 200041969 Decay Heat Installed Boron Precipitation Control Piping and Hangers 200057137 High Pressure Injection Installed New Relief Valve on HP1511 200067202 Decay Heat Installed new Decay Heat Cooler 2 Bypass Flow Control Valve DH13A 200067203 Decay Heat Installed new Decay Heat Cooler I Bypass Flow Control Valve DH13B 200067204 Decay Heat Installed new Decay Heat Coolerl Outlet Flow Control Valve DH14A 200067205 Decay Heat Installed new Decay Heat Coolerl Outlet Flow Control Valve DH14B 200099433 Decay Heat Installed New Relief Valve on DHI1529

15 RFO Inservice Inspection Summary Page 39 of 238 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 200123859 Containment Spray Replaced Containment Spray Pump I Cyclone Separator CS4 Flange Bolting 200140451 Main Steam Rebuilt Steam Generator 2 Drain Line Isolation Valve MS603 200162515 Reactor Coolant System Replaced Containment Vent Header Relief Valve RC769 Inlet Flange Bolting 200189329 Main Steam Replaced Snubber on Hanger MI 148/H5 200200285 Reactor Coolant System Modified 10 Small Bore Pipe Supports and Related Equipment 200203452 Makeup and Letdown Modified 4 Small Bore Pipe Supports 200207115 Reactor Coolant System Rebuilt Pressurizer Power Operated Relief Valve RC2A 200209082 Main Steam Replaced Steam Generator 2 Drain Line Isolation Valve MS603 200209083 Main Steam Replaced Steam Generator 1.Drain Line Isolation Valve MS611 200229799 Decay Heat Replace Body/Bonnet Bolting on Decay Heat Pump 1 Discharge Check Valve DH43 200233203 Steam Generators Steam Generator 1-2 Tube Plugging 200233204 Steam Generators Steam Generator 1-1 Tube Plugging 200237871 Reactor Coolant System Replaced Snubber on Hanger M1 170/H14 200237898 Reactor Coolant System Replaced Snubber on Hanger FSK-M-CCA-18-1-H2 200237899 Reactor Coolant System Replaced Snubber on Hanger Ml 142/H22 200237901 Reactor Coolant Pumps Replaced Snubber on Hanger FSK-M-CCB-8-15-HI 200237904 Reactor Coolant Pumps Replaced Snubber on Hanger.FSK-M-CCB-8-15-H2 200237906 Reactor Coolant Pumps Replaced Snubber on Hanger FSK-M-CCB-8-22-H3 200237913 Reactor Coolant System Replaced Snubber on Hanger Ml 170/H 1I 200237914 Reactor Coolant System Replaced Snubber on Hanger M1 170/H2 200237916 Reactor Coolant System Replaced Snubber on Hanger FSK-M-CCA-20-2-H4

15 RFO Inservice Inspection Summary Page 40 of 238 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 200237917 Reactor Coolant System Replaced Snubber on Hanger FSK-M-CCA-20-1-H3 200237918 Reactor Coolant System Replaced Snubber on Hanger MI 170/H4 200237919 Reactor Coolant System Replaced Snubber on Hanger M1345/H2 200237920 Auxiliary Feedwater Replaced Snubber on Hanger MI 155/H3 System 200237921 Containment Vessel Replaced Snubber on Hanger FSK-M-HCB-Gaseous Waste 38-4-H4 200237922 Steam Generator Replaced Snubber on Hanger M1 147/H9 200237923 Steam Generator Replaced Snubber on Hanger Ml 147/H4 200237924 Steam Generator Drain Replaced Snubber on Hanger FSK-M-EBB-5-19-H1O 200237925 Steam Generator Drain Replaced Snubber on Hanger FSK-M-EBB-5-19-H5 200237926 Reactor Coolant System Replaced Snubber on Hanger Ml 113/H54 200237927 Steam Generator Drain Replaced Snubber on Hanger FSK-M-EBB-5-19-H4 200237928 Steam Generator Drain Replaced Snubber on Hanger FSK-M-EBB-5-19-HI 200237929 Steam Generator Drain Replaced Snubber on Hanger FSK-M-EBB-5-9-Hi 200237930 Steam Generator Drain Replaced Snubber on Hanger FSK-M-EBB-5-8-H 11 200237931 Steam Generator Drain Replaced Snubber on Hanger FSK-M-EBB-5-8-H12 200238292 Steam Generator Drain Replaced Snubber on Hanger FSK-M-EBB-5-1-Hi 200238293 Steam Generator Drain Replaced Snubber on Hanger Ml 170/H12 200238484 Reactor Coolant System Replace 1 Inlet Flange Stud on Pressurizer Code Safety Valve RC13A 200240268 Reactor Coolant System Replaced CRDM Quick Vent Closure Assembly 200249935 Reactor Coolant System Performed Full Structural Weld Overlay on the Pressurizer Spray Nozzle

15 RFO Inservice Inspection Summary Page 41 of 238 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 200249948 Reactor Coolant System Performed Full Structural Weld Overlay on the Pressurizer Surge Nozzle 200249949 Reactor Coolant System Performed Full Structural Weld Overlay on the Pressurizer Relief Nozzle for RC2A 200249950 Reactor Coolant System Performed Full Structural Weld Overlay on the Pressurizer Code Safety Nozzle for RC13A 200249951 Reactor Coolant System Performed Full Structural Weld Overlay on the Pressurizer Code Safety Nozzle for RC13B 200249952 Reactor Coolant System Performed Full Structural Weld Overlay on the Pressurizer Surge Line to Hot Leg Nozzle 200249953 Reactor Coolant System Performed Full Structural Weld Overlay on the Pressurizer Decay Heat Line to Hot Leg Nozzle 200249954 Reactor Coolant System Performed Half Nozzle Repair of Pressurizer Level Sensing Line (RC14A) 200249955 Reactor Coolant System Performed Half Nozzle Repair of Pressurizer Level Sensing Line (RC14B) 200249956 Reactor Coolant System Performed Half Nozzle Repair of Pressurizer Level Sensing Line (RC14C) 200249957 Reactor Coolant System Performed Half Nozzle Repair of Pressurizer Level Sensing Line (RC14D) 200249958 Reactor Coolant System Performed Half Nozzle Repair of Pressurizer Level Sensing Line (RC 14E) 200249959 Reactor Coolant System Performed Half Nozzle Repair of Pressurizer Level Sensing Line (RC14F) 200249960 Reactor Coolant System Performed Half Nozzle Repair of Pressurizer Head Vent Line Nozzle 200249961 Reactor Coolant System Performed Half Nozzle Repair of Pressurizer Sample Nozzle 200249962 Reactor Coolant System Performed Half Nozzle Repair of Pressurizer Thermowell Nozzle 200261534 Reactor Coolant Pumps Relocated Seal Injection Line Drain Valves MU247 and MU247A

15 RFO Inservice Inspection Summary Page 42 of 238 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 200266309 High Pressure Injection Installed High Pressure Line Flow Test Isolation Valve MU422 200296303 Main Steam Replaced Snubber on Hanger SR9 (Snubber SNC178) 200296330 Main Steam Replaced Snubber on Hanger SR9 (Snubber SNC234) CR-05-05569 Decay Heat Re-rated Line Class GCB-7 and GCB-8 Piping ECP 06-0039-00 Decay Heat Re-rated Line Class GCB-7 Piping

15 RFO Inservice Inspection Summary Page 43 of 238 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/N-V-R-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 10, 2008 76 South Main St.. Akron. OH 44308 Sheet I of 1

2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 Order # 200003042 Nopar CC:.

Or*wzafltc P.o.NU,Jb NO,.

3. Work Performed by FirstEnergy Nuclear, Operating Co. Type Code Stamp NR N.-

5501 N. SR. 2. Oak Harbor. 0OH 43449 Authorization No 20 50N. SR. 2 Oa Habr OH ...... Expiration Date 07/17/10 4 Identification of Systems SO 2 Main Feedwater Stop Valve DB-FW60 i (Subsvs 045-01) 5 (a) Applicable.Construction Code ASME I1ICL.2 1971 Edition S71 Addenda Code Case N/A (b) Applicable Edition of Section XI Utilized rot Repairs or Replacements 19 95 Edition 6 Addenda Code Case N/A (c) Design Responsibilities FirstEnergy Corp.

6. Identification of Comnonenta Reonrire rer, Relaeerd end Rentsrerrment (nmnonente Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Judsdictional No. Built Replaced or Cos Replacement Stamped 18" Gate Valve Ve.an Engineerig Co. 0019 N/A DB-FW601 1974 Repaired Yes.

Bonnet Bolting Material Unknown Unknown N/A N/A tUnk. Replaced No 24-1 1/8" x 9 1/4" Studs Nova Machine Products HT# 59412 N/A TC# 597A 2006 Replacement No 24-1 118" Hvy Hex Nuts Nova Machine Products Corp. HT# 13616 N/A TC# IRS 2002 Replacement No

7. Description of Work During toutine maintenance on this valve, the body to bonnet bolting was replaced during reassembly.

A VT-2 initial inservice leakage test was performed satisfactory vr*

                                                                                                                                                                        )r 8      Tests Conducted:                Hydrostatic No             Pneumatic No                 Nominal Operating Pressure Yes                 Other No Pressure     955                    psi                       Test Temperature        NOI                 '-F            .-

Pressure Relief Valves: Service N/A Size N/A 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 lists, sketches, or drawings may be used, provided (1) size is 8 Y X 11 in. (2) Information Initems 1 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 top of this form.

15 RFO Inservice Inspection Summary Page 44 of 238 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 N IS-2/N R-1/N-R AM,ýK:I.,Manuf-.urr D-t PR Wto1** be AV/achd

9. REMARKS N/A CERTIFICATE OF COMPLIANCE I, Richard R. Cockrell , certify that the statements made inthis 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" sta expires 07/17/10 Date 03-0 got& 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 andcertificate of competency issued by the jurisdiction of OHIO and employed by 0 HSB CI. of Hartford, CT have inspected the work described in this report on C~ *M.A. ..t.band C 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 3111 lo£ Signed i I

Commissions Ob (Ra~lo-q-1-30 t. m*)' J\

{ 1 .0l , (,W id n 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 o:" 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~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

J 15 RFO Inservice Inspection Summary Page 45 of 238 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-1/N-V.R4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner FirstEnergy Corp. Date March 7, 2008 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 haribor, OH 43449 Order # 200003060 Repai~aemrlotan P0., Ho., Joe Ho,eat.

3. Work Performed by FirltEnergy Nuclear Operating Co. Type Code Stamp NR q501 N SR 2. Oak Harbor, OH 43449 Authorization No 20 Expiration Date 07117J10 4 Identification of Systems SO 1 Main Feedwater Stop Valve DB-FW6I 2 (Subsys 045-0 1) 5 (a) Applicabli Construction Code ASME IlI CL.2 1971 Edition S71 Addenda Code Case N/A (b) Appticable Edition of.Section Xl Utilized for Repairs or Replacements 19 95 Edition _ Addenda Code Case N/A (c) Design Responsibilities FirstEnergy Corp. .

6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other ldentlfication/ Year. Repaired ASME.

Name of Component Name of Manufacturer Serial No, Board No. Jurisdictional No Built Replaced or Code Replacement Sta6ied

     .18" Gate Valve                 Velan Engineerg Co.                0020               NIA            DB-FW612                   1974         Repaired         Yes Bonnet Botting Material        Unknown                            Unknown            N/A            N/A                        Unk.         Replaced         No 24-1 1/8" x 9 1/4 Studs        Nova Machine Products              HET#59412          N/A            IC# 597A                   2006         Replacement      No 24-1 1/8" Hvy Hex Nuts         Nova Machine Products Corp.        HI# 13616          N/A            T"C#IRS                    2002         Replacement      No

7. Description of Work During routine maintenance on this valve, the body to bonnet bolting was replaced during reassembly.

A VT-2 initial inservice leakage test was performed satisfactory t~pt 8 Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure 956 psi Test Temperature NOT °F Pressure Relief Valves: Service N/A Size N/A Opening Pressure N/A Blowdown (Ifapplicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A (TeatMý5r,} at N/A ':7 " NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 Vi X I I in (2) Information in items 1 through 6-on this reoert is included on each sheet, and (30 each sheet is numbered and the number of sheets is recorded at the too of this form.

15 RFO Inservice Inspection Summary Page 46 of 238 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-1MVR-R4 A*o a.iapp M fe af raaaODtaHRWpra abaAtl1id i

9. REMARKS N/A CERTIFICATE OF COMPLIANCE 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"' star xpires 07/17/10 Date O37-67-2nto- FENOC al apadr (naria ag=a~oniaa) Signed 7aud drra ntataa) 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 CI. of , Hartford, C1 have inspected the work described in this report on, AhMiupW %J, and state that to- - the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Secti6h-- 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( Of3 Signed I~Y~DVW'61 Comisson - I3i9 T -Cca 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 T the ASME Code and to the National Board Inspection Code "VR" and "NRI rules.. National Board Certificate of Authorization No.. 316 to use the "VR" stamp expires 2/13/I10 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, C1 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 bei v 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 (Natariat B."rd (-Itri . iar$), m

                                                                                                                        ,a WadlUi.- ,ar -)

15 RFO Inservice Inspection Summary Page 47 of 238 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/NVfH- OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner FirstEnergy Corp. Date September 18, 2007 76 South Main St.. Akron. OH 44308 Sheet 1 of 1 2 Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Haibor, OH 43449 Order 200008135 Job W., m. NPýa OganaWn P.O. t 3 Work Performad by FirstEnergyN.,,,Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2, Oak Md~..Harbor. OH 43449 Authorization No 20 Expiration Date 07/17110 4 Identification of Systems Decay Heat Pump 1-1, DB-P42-1, (Subsys 049-02) 5 (a) Applicable Construction Code ASME [In CL2 1971 Edition no Addenda Code Case no (b) Applicable Edition of Section XfUtilized for Repairs or Replacements 19 9__5 Edition 96 Addenda Code Case no (c) Design Responsibilities . First Eneigy Corp., Nova Machine Products Inc.

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 Flange studs 16@1 11/" Nova G7504 (P516) N/A N/A 2005 Replacement no Flange studs 16@1 1/4" Nova G8391 (P517) N/A N/A 2005 Replacement no Hex nuts 30@ 1 1/18 Nova 729103 (P453) N/A N/A 2005 Replacement no Hex nuts 2@ 1 1/8" Nova 729363 (P180) N/A N/A 2005 Replacement no Hex nuts 32@ 1 1/4" Nova 150713 (P495) N/A N/A 2005 Replacement no

7. Description of Work Existing suction and discharge flange studs and nuts were replaced with new material listed above.

A VT-2 inservice 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 (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 8/2 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 top of this form.

15 RFO Inservice Inspection Summary Page 48 of 238 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 434.49 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-1tN-VR I ApION]bWouh*-o* D- R*q A ton A theW _b

9. REMARKS N/A CERTIFICATE OF COMPLIANCE I, Kevin J.Kress , 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 eire 07/17/10 Date 9F18- DOItY FENOC Signed 7 Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Tom 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 CI of Hartford. cr have inspected the work described in this report on . I% (_O and state that to the best of my knowledge and belief, this repair-, modification or replacement has been completed ih accordance With Section XI of theASME 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 inthis 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 9 I'* ? *" Signed-.- Commissions 1%'q,? k1 T A-" CERTIFICATE OF COMPLIANCE N/A certify that to the best of my knowledge and belief the statements made inthis 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 12/13/07 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 CI of Hartford, CI 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 ben liable inany manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection Date Signed Commissions (froO, MNabn8ON @01 ý.ottnhh) a.d jud*d-khio. and _))

15 RFO Inservice Inspection Summary Page 49 of 238 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 Z'. FORM NIS-2INR-1I#'-R-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 6, 2006 76 South Main St. Akron. OH 44308 Sheet i of 4 2 Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2. Oak Harbor. OH 43449 Order# 200041969 M-* RHý.AOk oA P.O.f. Jab No...-.

3. Work Performed by FirstEnerev Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. OakHarbor. OH 43449 Authorization No. 20 Expiration Date 07/17107

4. Identification of Systems Decay Heat and Low Pressure Injection (Subsys049-02) 5 (a) Applicable Construction Code ASME IC CL2 1971 Edition No Addenda Code Case NA (b) I Applicable Edition of Section XIUtilized for Repairs or Replacements 19 95 Edition 9 Addenda Code Case N416-2 (c) Design Responsibilities First Energy Corp., Velan Inc., Westin*house Electro-Mechanical Div.

6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identiticationi Year Repaired ASME Name of Component Name of Manufacturer Serial No Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped 2' Gate Valve Velan Inc.. 011025-9 .NA D1203 2001 Replacement Yes 2 Globe Valve Velan Incr. 931039-2 NA DH206 1993 Replacement Yes 3" Swing Ck. Vlv. Westinghouse Blectro-Mech

NA DH207 1979 Replacement Yes Supports First Energy Corp. NA NA See Below 2003 Repaired No

7. Description of Work

SfN 03000CS8800000002W750326 Modified piping system per ECR 03-0146-00. Fabricated new hangers M12331H3 thru H6 per ECR 03-0146-00.

Modified hangers 33C-GCB-7-H10 thiu H13 per ECR 03-0146-00. Performed NDE (PT/RT) as required by Code. Performed a VT-3 on hanger 33C-GCB-7-116 satisfactory. A VT-2 inservice leakage test was performed satisfactory. All materials installed are recorded in the work order and identified on the design drawings. _ _.... . 5.a (cont.) ANSI B31.1 & MSS-SP58-1967 Edition. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other Yes Pressure _NJ - 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 Biowdown 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) Intormation 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 tot ot this form.

15 RFO Inservice Inspection Summary Page 50 of 238 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 09-0070-4 FORM NIS-2/NR..1/N-VR4

9. REMARKS Westinghouse Electro-Mechanical Div.

Velan Inc. 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 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" star xpires 07/17/071 Date D7-0-n& FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION 1, Tom 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 H1SB CT. of Hartford, CT . have inspected the work described in this report on _1%)WAi;b 11 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 __' k1 f, Signed Commissions 16 T 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 12/13/07 National Board Certificate of Authorization No 20 to use the "NR" stamp expires 07/17/07 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 NA 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 m~,fl mm,;

15 RFO Inservice Inspection Summary Page 51 of 238 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 DATA PACKAGE NO. FORM NPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS An Required by the Provisions of the ASM Code, Section III, OR VALVES Divrision I P

1. Manufactuared and ce~rtified by VTAIfc.21.25 UAig 3N1~EJL (awn, and add~ren of N Certifcate Holder)

2. Manufactured for FRAxffi=M ZREMMOL=Gfs31. L aiT DLtRDGV~na (amumand adds'nz of purchener)

3. Locati~onof iriutallion _

(name adtaddrna) A. M~odel No., Series WO.. or Tnesi GM Drawing P. iJ2f.2zEB.L Rev .... j.. CRJI K/a S. ASMX Code, Sectionz ZIZ, Division 1t .... J1289- .1wU. I...~.*f (441,110) (addedaf date) "12o) (Code Cii o-

6. PumP or valve . MY" - Rumal inlet nice - L..- Outlet site - 2 036) (15.)

7. Materials Boy.S-12336 Bonnstfik.LU, .UL... Disk SA-35 3Clu Baiting g SA-1564, $3031100 (a) (b) (c) (d) (e)

Nato1 Cart. Body Bonnet Diax HolderIs Board Serial Serial Serial Serial No. No. up. No. No. ___NIA Ct .C . By'T Dl1IR2-3 CCE PVT 011022-6 cca ....... ByT CR 623L S ccE BVT SIsmenie sictafsrshaeet hi fern. oflist , n tba~* mots tp be needpre bedrah (idedO) use i 8 ICII, Ci)islUZIallen t h It=em II *tt0 4 Wiling Inlonladed *a eagebabeet.Mu ech oheetIanumbered and Lbs numberof sheets Isrteorded at Iks top af this ot..F IPRA.-API (IM/8 Thbs(aria (E00037) may beobtained fromsthe Order Dept.. ASMSF, 23 LAW DRIVEt BOXC 230 FaUtlId4, NJ 07007-Z300, jOP SUjP LBJ

15 RFO Inservice Inspection Summary Page 52 of 238 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 550.1 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 JUL. 21.eo ?!EEM FRAM~TOME NC 804 %32-2966 NO. 395 P.2/2 FORX XPV-1 (Back - g. 2 of -2,-_L ) Certificaba Bolder's Semrial. No. 01192lý S. Design conditions L....m.. pi 1920 --- &OR..... OF or. Valve pressure clang -10 1 (Pmassurs) t=MU*

9. col.d working prapmur* 190Psi at 1000Y 10, Hydroatatic test _30 Psi. Disk dIffemsatial test premausa 22 11.* kxenkip: MMXUGL a= ASK uaNyo1'Ory ==aflO. 1989 AMnn AI I ~CZRTXZCUZ 07 DMIUG Degign Specification Certified by V.LS*!WI _ . P.N. st - t" -ju Rag. UZ 402 Desi2z rGPOrt certified by I- . IRIMRM9=T P'N. State .... L- Re. no. -"=1~

cuv.Zyzem3 OF OMtLZA=e We oertify that thin stateseoti =a" ILa im report az. aorrect: and that LIhia pumap or valve coundosms to the rules for Construction of the ABU~ Code, Section Xzz, I)vlxivnLo1. Rt cartifiaat. CE Autuorizatin go, x-2747-31 I xpixem AnTL 20. 2004 Date OctI Is) Nae n i sine n (BRiTMCATS OF XNS1Z=CW)Y X, the undersigned, holding a Valid comice~ai Lpauad by the Ustional Board or Boilex and Pressure Vsamax2 Mepeoboxs "nad the State or frovinze of Guaz and amployad by RzrsI flU 314239DE! of have imap~eotd the pup 4 OW ValVe, 440CribAd

       '*U this D&At PePOrT oU        aLZZ                            and state that to the beat of my kcnowledge oAd belief, the certificate. Holder Dim coanstcuated Wei ptzp, or valve, in accordance with the AS=6 Code, Easetion XXU, DiVision 1.

my 010ning thin Certificate, neither tho inspector nor him employer =aken &my worrenty, expressed or inplied, coucaxmJing the oompnouet d~escribed in =a4 vata. mapot. F athermom.. neither the Luspeotor nor him saplyrw shaLl be lciabl in any meaner for any Varmonal Injuxy or property dazuage or a loss of any kind arising from or connected with ainspectiom'.

~"

Date 0 siLgned ol 114- tust Cozztaatoins2

                                                                                -ta~k    (NTT     ou
                                                                                                     ^

I-I (1) Var MAXua17 operated valves onlr. AkA Ij*,r.,j/ Gaý

15 RFO Inservice Inspection Summary Page 53 of 238 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/o9/2*o3 11:3o FAX 4192492350 WARMUHoJE f_ FORM NPV-1 CERTIFICAT¶ LDR DT REPORT FOR NLU7 MPR9ALLE+/- As RequitiW by ~t~e Provisions af the ASME C~ode- Section [11,Division 1 931039 ft, Iof-

1. MO2nuftat2Jta and ceerffled by &&,eA ~~

A00" A -'_'_ ie lW- ua anddd. .f N Cenjflaan H4vI 2.u~k'~m Maufctre _."O.ho~ Irne d adro

4. ModeNoiJ. edsoeNo...oitType~d.. 92ZZ4%eP S. AS, E Code,Se-rgon W, Divo, 1: 1: .. ... .... .

Idenwodaeetl tahini W-1 (Cadl.c- w 0, ~ oorninal Nit InMh t vtes A - - Oudeat 7,.MotoaLta Body acaa Conw ef ZI.-j 9Zk.W' oin lIn)I P I) 1d) ,e) ,

                        ....          Hiftts                                      Soelal                        sorw_....                       Serial Saw No.                            No.                       N                              No.                         . Na       e_
                  -. ,       .:**.,, *        ._L.-       *       ,              Z-...__. ..           ..
              ----------          =.*-                  -*                                                      --                                      -" ..

an vie m ts Re I. Insdd an "san efWe, t3) e sk bap~ Shto n a d im4 na e ofe, IMemit ed WivOw oatle t (12481 TMsfma 1W00mi rmvbew eialasd te. oh odiueOWL. WS 23 Law P. ans UC". Fald. NJ 07 T30O.. .

                                                                                                                                            -    -  ... r..   *7 nz  W.

15 RFO Inservice Inspection Summary Page 54 of 238 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 08/09/2003 11:30 FAX 4192492380 WAREHOUSE 0009o FORM NPV-1 (Back - Mg 2 of-_-.) centificem Wilder', sowa W,..210S pA , 8, Design con~tiong gg:ýr '.1 - .* or valve p'nwmse aim5 ~ i 9 - raw wor"n pmanure psiof30__ at I00P

10. Hydoteatc tecst .. pd.iat, a1k~m toutpnzAle.. Vol J II Ranawks,

______________________ ____________ ~z. ~.aJ. j'~IS ~ ceM"nTMo$ or aTM. DesgnSe Iu~w~aetlhdby-7 ~ -- P.L Scm g Rag.. m Oinlgn Report cerdt4fe by ~S~ -~P,. Stof. ...a.d.. Reg. ,v.. _ CERTIRCAVW OPCOMPtlhNCE we cenvy "Mt* statenmento rado in"l Mitrn.? c-m an" 1%d. " Dump nofva Conformsiha"to des %cinoamulnn of owAsmrcoft section ii.DivW6.n t N Casitcate of AUttoiqaia3* No. (01Ceilficew Heleel Ii7,-~t~~7 cRIFIC"MCE OFKIPECIO I. he wvlAime~ holdif a lid apniieon tesuad bythe Nesienal Board of reuvr esaaaflnspomfbarivan Pam

                                                                         ~ havie huipootoIme pumv. or Volvo. dwc,1      In this OantReopot an and     -w*6510 sto # 6.1 eet niyV lMWplg e bell, th. Cajilfica? Holder hae =an-san opgk'V, or %olvo. in RaM       n=e Wh%OneASW~ Ciode,snoxonIn,1Division 7.

t"ysn*.g Ww ae.tfkat, ;old=r %Mlnapeum noat hi. .,M -mInake aY wwwgf, 1010110 or miiled, cte g the neenponunt described iniotii Dom Report. Fcunhaornre, neither VWt froepctor not i Wn10V1 hl be02ab1e "opo~ Inanvyrnmwni for any Pemenl ft"uv or Pro ~y amge ore a oef a" kM arisng ftmn or tonnscmed With "hi inspotffn. em JACQUES iAARCHANDIo*o r,, 011103/ *

                       .Ndag.a     Y
                                         .vnj~'"*"       pr,...,        I""
                                                                                           ,,ld                       me,vow,= "",,

1 Fer mallyW oprilltd valwas wily.

15 RFO Inservice Inspection Summary Page 55 of 238 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 DBNPS

15 RFO Inservice Inspection Summary Page 56 of 238 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 05/10/2006

15 RFO Inservice Inspection Summary Page 57 of 238 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #l, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-S FORM NIS-2/NR-1-NV-R4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section X1 1, Owner FirstEnergy Corp. Date December 3, 2007 7n.O I 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 Harbox, OH 43449 Order # 200057137

3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oak Harbor, OH 43449 Authorization No. 20 Md,,."'

Expiration Date 0711 7/10 4 Identification of Systems H'{igh Pessuie Injection Pump 2 Suction Relief Valve - DB-HP 151 I- (Subsys 52-01)

5. (a) Applicable Construction Code ASME nI CL.2 1971 Edition W 72 Addenda Code Case No (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case No (c) Design Responsibilities .FirstEnergyCorp., Andet son Greenwood Crosby.

6. Identification of Components Repaired or Replaced and Replacement Components 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 Relief Valve Lonergan 304400-15-1 N/A DB-HP1511 1975 Replaced Yes Relief Valve Anderson Greenwood Crosby N99716-00-. N/A DB-HP151I 2006 Replacement Yes 0004 _ ._

7. Description of Work Existing relief valve (serial # 304400-15-1) was ieplaced with a new relief valve (serial # N99716-00-0004) during routine miantenance.

A VT-2 initial inservice leakage test was petformed satisfactoyy. 8 Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure 33 psi Test Temperature NOT '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 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 (30 each sheet is numbered and the number of sheets is recorded at the top of this form.

15 RFO Inservice Inspection Summary Page 58 of 238 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 - Appil.l. Ma--i D D l-ea t bF.pod.I d

9. REMARKS Anderson Greenwood Crosby 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" staI xpires 07/17/10 Date X2-.QD3--07 FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION

    , Iomn 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 CI          of Hartford, CT       have inspected the work described in this report on t                     . ý.1ft7 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 ior 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. 1'.r Signedc!mTtj i t,4 Commissions KV'B 1tt, t1 TE A

                                                                                                                            -    I...       -d      .

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 (rame dl19Sr orgmzlt~oa) Signed (iud~orii rtp~seidB ~el 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 CI 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 (lapaolt' (NadtondJ Beia*md iid.datomanta),

                                                                                                                          *=r*ir        eidto~  i ou)

15 RFO Inservice Inspection Summary Page 59 of 238 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

                                                                                                     ;~(.     'or r~"C          .

Q.C-44C-, Sheet 1 of 2 FORM NV-I FOR SAFETY AND SAFE VA] As rquired by the Provisions of the ASME Code Rules DATA REPORT

1. Manufactred By Anderson Greenwood Crosby, 43 Kendrick St., Wrentham, MA 02093 Name and Address Model No. JLT-JBS-35-S Order No. U967720000 Contract Date 10/19/05 National Board No.. -

TYPE E 2., Manufactured For FIRS1 ENERGY CORP. Order No.. 45171850 Name and Address 3.. Owner___ FIRST ENERGY CORP. Name and Address

4. J.ocation of Plant DAVIS BESSE 5.. Valve Identification BIPSI5 Serial No.. N99716-00-C0004 Drawing No. DS.C976RV Type SAFETY RELIEF Orifice Size 0.665 Pipe Size -- Inlet 1.5 Outlet 2 Safety, Safety P/Rief, Pilot, Power Actuated Inch Inch .-.. Inch

6. Set Pressure (PSIG) 450 -W 9- 57,0 F Rated Temperature 2

StampedCapacity u13GP WATER @7 DE.F @ 10-o'O rr e--Wd0, .... Hydrostatie Test (PSIG) Inlet 1100 Complete Valve 100 7.. The material, design, construction and workmanship comply with ASME Code, Section Il" Class 2 Edition 1971 Addenda Date WINTER Case No. N/A Pressme Containig or Pressure Retaining Components P 51? I t Serial No Material Specification , a., Castings Identification Including Type or Grade Body N900159-32-0005 ASME SA351 GR. CFSM Bonnet N97794-36-0009 ASMB SA35I GR. CF8M b.,Bar Stock and Foegings Support Rods Nozzle N97792-33-0003 ASME SA479 TYPE 316 Disc Insert) N97793-NGY- ASME SA479 TYPE 316 N96827-36-0022 Spring Washers N96827-36-0021 ASME SA479 TYPE 316 Adjusting Bolt N9682&-33-0007 ASNE SA479 TYPE 31. Spindle N900162-32-0003 ASME SA479 TYPE 316 7.1

15 RFO Inservice Inspection Summary Page 60 of 238 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 QC-44C-I Form NV-1 (Back) Certificate Holders Serial No.. N99716-00-0004 Sheet 2 of 2 Serial No. Material Specification

                                                                                                         "- *,c,   Including Type or Grade c Spring                                                                                                  ASrM A313 "YPE 316

d. Bolting e., Other Parts such as Pilot Components Bonnet Stud N900163 ASME SA564 GR. 630 Bonnet Nut ---Ng73- 9,*6'

                                                                                   /,      "            ASME SA1 94 GR. 8M
                                                                                             -Ze r"3        i-,to
                                                                                                               - t We certify that the statements made in this report are correct.

Anderson Greenwood Crosby Manufacturer Certificate of Authorization No N-1878 Expires 30-Sep-07 Date CERTIFICATE OF SHOP INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel.Inspectors and the State or Province of MA and employed by HSB - CT have inspected the equipment described in this Data Report on 6-2s9- 2006 and state that to the best of my knowledge and belief, the Manufac~mrer 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 3711IKIe--3 b, 200 6

                                                      -    Commissions              MA-1420 A. N. I

([aeor) (National Board, State, Province and.No..)

15 RFO Inservice Inspection Summary Page 61 of 238 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-9/NR-!PPAQROWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner          FirstEnergy Corp.                                                         Date      October 23, 2006 76 South Main St., Akron, OH 44308                                                  Sheet I of 2 2  Plant         Davis-Besse Nuclear Power Station                                         Unit                                #1 5501 N. SR. 2. Oak Harbory. OH 43449                                             Ordeo_200067202 Addr-                                                                p.,rOrgn   n P.O.N.obN.. ec, 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      07/17/07 4  Identification of Systems       DH Cooler 2 Bypass Flow Contnol Valve - DB-DH13A - (Subsys049-02) 5  (a) Applicable Construction Code           ASME II CL.2         1971 Edition           no Addenda                  Code Case no (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements       19     95     Edition      96         Addenda      Code Case      N416-3 (c) Design Responsibilities       First Energy Corp. , Enertech             .

6. Identification of Comoonent4- Rennired or Ranlar, ed antd Renlanement Comoonenta 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 6" Butterfly Valve Valtek Inc. 60284.001.1 N/A DB-DH13A 1988 Replaced Yes 6" Butterfly Valve Enerlech 11486 N/A DB-DHI3A 2006 Replacement Yes HGR-36-HBC-2-Ht IfI Gminmell HI I N/A N/A I Unk Repaired No

7. Description of Work Existing butterfly valve (60284.001.1) was reolaced with new butterfly valve (11486) per ECP 03-0579-00. Existing bolting material.

was re-used. A VT-2 inser vice test was performed satisfactory.

      *Hanger-36-HBC-2-H1 was repaired in accordance with ECP 03-0579-00. All materials used are identified and recorded in the order.

5A (Cont.) ANSI B31.1 & MSS-SP58 - 1967 EDITION OR LATER.

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 Blowdown Adjustments Made Using N/A at N/A (L..on) NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (i) size is 8 ' X 1t in. (2) Information in items 1 through 6 on this reoort is included on each sheet. and (30 each sheet is numbered and the number of sheets is recorded at the ton of this form.

15 RFO Inservice Inspection Summary Page 62 of 238 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-INY%4 9, REMARKS Enertech CERTIFICATE OF COMPLIANCE I, Richard R. Coclelo, 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" star )expires 07/17/07 Date ID-23_Z-ýf,. FENOC (none of,,,",,ofog,*J=) Signed oOoideooo Q.C CERTIFICATE OF INSERVICE INSPECTION 1, Tom 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 OHO and employed by HSB CI of Harrford, CT have inspected the work described in this report on oc'x. aA., ;.bO6 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 X Signed Commissions ,, Ar c, - Nr lO rd B w[liOf Bon Od,~ot) 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 12/13/07 National Board Certificate of Authorization No.. 20 ... to use the "NR" stamp expires 07/17/07 Date FENOC (n~onofrea* *nooaobon) Signed noo~d

                                                                                                           ,eprneobtlne)

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 CI of Hartford, CT have inspected the repair, modification or replacement described in this report on N/A 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 bea 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 (4,0nOpeco) (Notcronoa* l rn,O l =r~on

                                                                                                                                         ,B    rnen,).

(Nd Oký nan o

15 RFO Inservice Inspection Summary Page 63 of 238 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 NPV.1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES'* As Required by the PiovIslons of the ASME Code, Section Itl, Division I Pg. 1 of2

1. Manufactured and certified by --ooo ,, -o~ -'..~s-wnWlo~ovo~p.

                                                                                                  --              -otrce    -ot Shonios ,my 9s       a;  B,50CA M2&

I4ht- end add.a.. of N Cerifoite Molver) 2 Manufactured fe First Energy Corp.; PO. Box 6100; Johnstown, PA 15907-6100 I.... aondadd-es of Purohaaad 3 Location of irotallition Davis-Besse Plant; 5501 North State Route 2; Oak Harbor, OH 43449 (name and sdd-.al1 4 Model No, Series No .or Type _ _AK.... Drawing M021479 F

5. ASME Code, Section IIl D)vlsion 1; 1971 No 2 w-' None ledilionl (addenda d.al. 10-) (Code Case no I

6. Pump or valve Permaseat Valve Nominal Init ze. 6 NIA 1 SA49 p 16 .1 19 .18

7. Material: Body SA-24D Tp. 316 N/A Disk SA-479 Tp_ 316 Bolting SA-193 Cr. OSM

                                                               -,t In)                          Ib)                             (0) .                           (d)                              le)

Cert Nat I Body Bonnet Disk Holder s Board Serial Serial Serial Serial No. No, No No. No 11466L- None LIY-13609 None KNG-12983 SSuml-ntamtl infonrmoeno In fomt of latS, kslaiusm stdrawirngs mea as used pr-vlded (11 iszeIss 0 .11. {2i) nformtios in items I through 4 on this Deta Report Is included on -ah sheet 13) eash shoeat Is numberd ondthe nsmber .1 heet. Is reoordad et the tlop .1 thS torr (12181; This form 5000371 may be obtelned from the Order Dept ASME 22 Lem Drive Box 2300 Fairfield N J 07007-2300 REPRINT 6/93

15 RFO Inservice Inspection Summary Page 64 of 238 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 NPV-1 tBack - Pg.. 2 of Certificate Holder's Serial No 114B6 a Design cditions 47 _ psi 350 toerpesreutel

                                                                                                       -IF     or valve pressure class              300

pre~S:*tr.'1

9. Cold working pressure _ _720____ psi at lDCeF 1100__ _

10 Hydrootatic test ___0 pas Dies dilferontdel test pressure "-- p.; 1,

11. Remarks: QtY- IEnert6ch Project Number 810109 End CepMa'l: SA-240 Type 316 CERfIFICATION OF DESIGN Design Spocsetiorn cerrrfied by. "'Thomas R. O'Reilly, Jr. P.E State RMeg no 20742 Design Report certifedJ. Sierman P Sta ~ CA Reg no.. 23241 CERTIFICATE OF COMPLIANCE We oertlfy that the statements made in this report are torrect end that this pump or valve conforms to the rules tor construction of the ASIME Code. Section )l, Division 1..

NCertificate of Authoriration No. N-2826 10/11/08 Enertech, curtist-wrighi Pliow cordrttl Sig Dat aam Corp.- Commercial Power & services INCertifiseat Hioterl leutherloedrepresestatlsel CERTIFICATE Dy INSPECTION I. the undersigned, holding a valid commission issues by the Notional Boa(d of Soiler end Pressure Vessel Inspectors and the State or Province s - Califomria.. end employed by .. HS8 C1 Connecticut have inspected the pump, or valve described In this Data Report on f "*7 -c2t:6.

                                            'r-            and crate that to Thebest of my knowel-dge and belief, the Certificate Holder ho. con structed this pump. or valve, In accordance with the ASME Coda.. Section III,Division 1 By signtng this certificte, neither the inspector nor his employer makes asy warranty, expressed or Itnplied, concersing the oomponrnt described In this Data Report. Furthermore, neither the Inspector not his employer shell be tiablein any rmanenr for any personal in)ury or property dara*e             a loss of any kind o/r)ing from or connected with this inspection Cat-     -     Sigped                                           missions Comon           -__________    1 tA.utholrzedrlanspectod                             INart.ed. 1a- e               ad etele or se,. endnot aderientel (I) For manually operated valves only.

15 RFO Inservice Inspection Summary Page 65 of 238 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-00*70-5 i.: FORM N!S-/NR-1 ./4-4_ OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI I Owner *FistEnergy Corp. Date February 11, 2008 76 South Main St., Akron, OH 44308 Sheet 1 of 2 Davis-Besse Nuclear, Power Station Unit #1 2 Plant 5501 N. SR. 2, Oak Harbor,- OH 43449. Order# 200067203 AaM-4 Repatrorization P.O.NA. o No..eraW

3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR N-5501 N. SR. 2. Oak Harbor, OH 43449 Authorization No 20 Expiration Date 07117/10 4 Identification of Systems DH Cooler I Bypass Flow Control Valve, DIB-DH13B (Subsvs 049-02)

5. (a) Applicable Construction Code ASME III CL.2 1971 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 Responsibilities FirstEnergy Corp., Enertech, (Curtiss-Wright Flow Control 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 I - 6" Butterfly Valve Valtek Inc. 60284.001,2 N/A DB-DH13B 1988 Replaced Yes 1.- 6" Butterfly Valve Enertech. 11485 N/A DB-DH13B 2006 Replacement Yes Flange Bolting Mat'Is Unknown Unknown N/A N/A Unk. Replaced No 12 - 3/4" x 7 1/2" Studs Nova Machine Products HI# 732078 N/A N/A 2005 Replacement No 12- 3/4" Hvy Hex Nuts Nova Machine Products Hr# 727579 N/A TC# S886 2005 Replacement No 12- 3/4" Hvy Hex Nuts Nova Machine Products Corp. Hl'# 727579 N/A TC# 1377 2003 Replacement No

7. Description of Work Existing butterfly valve (serial # 60284.001.2) was replaced with a new butterfly valve (serial# 11485) during routine maintenance.

During valve change out, the existing flange bolting materials were also replaced with new bolting materials as 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 NOP psi Test Temperature NOT -F Pressure Relief Valves: Service N/A Size N/A Opening Pressure N/A Blowdown (ifapplicable) N/A " Set Pressure and Blowdown Adjustments Made Using N/A 10004 ,mm at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 ViX 11In (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 top of this form.

15 RFO Inservice Inspection Summary Page 66 of 238 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-OO70-5 FORM NIS-2/NR-1iNVR-+

                                                                                                             ,Maraactwnera AppL~atle         DataRepott,lob Afl~hedl

9. REMARKS Enertech, (ADiv of Curtiss - Wright Flow Control Corp).

CERTIFICATE OF COMPLIANCE I, Richard R. Cockrell , certify that the statements made inthis 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" stqr)expires 07/1 7/10 Date 02- I -0* 8 FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Ihomas 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 OHI1O and employed by HSB CT of Hartford, CI have inspected the work described in this report on 1=16Z -,4, aA 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 a.tI,- Signed T(Wl,,, Commissions t4,-nj TAi, ce, 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 'it 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 OF-1O 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 impliedi 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 f-,ap~clor) commissions C (Na~onaBoard(indl,ndolflemnt), ainin~dlolo**~~n, andr'.)

15 RFO Inservice Inspection Summary Page 67 of 238 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 NPV-1 CERTiFICATE HOLDERS4 DATA REPORT FC R NUCLEAR PUMPS OR VALVES* As Required by the Provisions of the ASME Coc a, Section 11. Division 1 1 Manufactured and certified by lnertech.A M. of Cu.t*W-*WhtFl-o Corvol CoOR.:mmeercial Power &SetMle,. 2950 BirchS -tt Smo t.A gPR1 tnbme~andbdid,. of N CartliffcateHoulder)

2. Manufactured for " y '-'"*I or. .sY . " ox U .tUlI

n. LOwnI, I .JL3U UU IV' inarne and address f Purchaser)

3. Location of Installation Davis-Besse Plant; 5501 North Sta 0 Route 2; Oak Harbor, OH 43449

[name ant address) 4.. Model No. Series No. or Type WAK Drawing MD214 SRev . F CRN None

5. ASME Code. Section III, Division 1: 1971 No 2 / None ledition) iaddenda del (class) ICode Case no I

6. Pump or valve Permaseat Valve Nominal inlet siz 6 Outlet size - _ 6 lin .1 fin.l

7. Material: Body SA-240 Tp. 316 Bonn, NIA Disk SA-479 Tp. 316 Bolting SA-193 Gr. 6BM V

La) (b) (c) (d) le) Cert, Nat'l Body Bonnet Disk Holder's Board Serial Serial Serial Serial No. No. No. No.. No 11485 None LIY-13606 None KNG-12980 4

Supplemental infurmation in form of sets sketches, or drawings may be used provided 11size Is B% x 11. 12) Ieformaton in items 1 through 4 en this Data Report is Included on each sheet (31 each sheet is numbered and the numbe' of sheets is recorded at the top of this form 4

if Vila) This form IEO)037] may be obtained from the Order Dept. ASME 22 La Drive. Box 2300. Fairfield. NJ 07007 23DO AEPRINT (m13

15 RFO Inservice Inspection Summary Page 68 of 238 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 NPV-I .CBack - Pg. 2 of Cae fioat Holder's Serial No 11485 B. Design conditions ,_475_._ psi 350 -F or aiva presmure tlass 300 11) lprenaurel Itempernera)

9. Cold working pressure 720 psi at 1001F 1J

10. Hydrostatic test 1100 psi Disk differential test pressure - psi

               ,II Rmr.           Oty. 1, Enertech Project Number 810109 I I , )t* ........      *                   =                     m=

End Cap Matf : SA-240 Type 316 CERTIFICATION OF DESIGN Design Specification certified by Thomas R. O'Reilly, Jr. P.E. St e MD_ Rag. no 20742 Design Report certified by Ira J. Silverman P E. St CA Se Rg no 23241 CERTIFICATE OF COMPLIANCEi We cerltiy that tne statementsl meau in this report *rrec co and That thils pure; !or valve contorms to the rules for construction of the ASME Code. Section III,Division 1. N CertificatAe of Authorization No. . N-2826 E 10/11/08 Enertech, Curtiss-Wright Flow Control ___ _______- me Corp., Commercial Power & Services Deste . ,./"-".-= r.ade ' Si ned IN Certificate -Holdar. lauthericed raprasentatiea] CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Boa of Boiler and Pressure Vessel Inspectors and the State or.Province of California end ampi ead by HSB CT oConnecticut have inspected the ump, or valve, described in this Data Report on

                                   ?-z.:IJi)iz ,and state that tothe best of my know dge and belief, the Certificate Holder has con-structed this pump. or valve, In accordance with The ASME Code, Section 1iI, ivision 1, By signing this certificate, neither the Inspector nor his employer makes any                         arrenty, expressed or implied, concerning the component described In this Data Report. Furthermore, neither the Inspector                          r his employer shall be liable in any manner for any personal Injury or property damage or a loss of any kind arising from or c                      nected with this inspection.

Datesaasigned I lAutherized InsPe rl rh[Nall.8d. lind. endorsements) and state or prov. and no I (1) For manually operated valves only.,

15 RFO Inservice Inspection Summary Page 69 of 238 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- OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xi 1, Owner FiistEnergy Corp. Date March 20, 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# 200067204 R =p wo O N o.b KP.O. , No.,.S 3 Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR Samn 5501 N. SR. 2, Oak Harbor, OH 43449 Authorization No 20 Expiration Date 07/17110

4. Identification of Systems, DH Cooler 2 Outlet Control Valve DB-DI414A (Subsys 049-02)

S (a) Applicable Construction Code ASME IlIICL.2 1971 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 Responsibilities FirstEnergy Corp., Enetech

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 Ccoe Replacement Stamped 10" Butterfly Valve Valtek Inc. 60284.002.1 N/A DB-DHI4A 1988 Replaced Yes 10" Butterfly Valve Enertech 11487 N/A DB-DH14A 2006 Replacement Yes Flange Bolfing Material Unknown Unknown N/A N/A Unk. Replaced No 16 -1" x 10 Studs Nova Machine Products HI# G8418 N/A N/A 2005 Replacement No .. 32 - 1" Hvy Hex Nuts Nova Machine Products Corp. HT# 726125 N/A N/A 2003 Replacement No

7. Description of Work During routine maintenance butterfly valve (serial #60284.002.1) was replaced with a new butterfly valve (serial # 11487).

During valve change-out, all flange bolting materials were replaced as routine maintenance. A VT-2 initial inservice test was performed satisfactory. 8 Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure 220 psi Test Temperature 100 -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 (T-4 Med-) at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 H2X 11 in (2) Information in items 1 through 6 on this reriort is included on each sheet, and 130each sheet is numbered and the number of sheets is recorded at the too of this form.

15 RFO Inservice Inspection Summary Page 70 of 238 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/N4-R-1 App*! Mfatfcl u*n DataRctsa W tobe Att0tie, i"

9. REMARKS Enertech., A Div of Curtiss Wright Flow Control Corp.

CERTIFICATE OF COMPLIANCE I, Richard R. Cockrtel , 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" sta' p ires 07/17/10 Date D3 on FENOC Signed " Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Thormas 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 tck Ze,ZtC. 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.. bate 0 P, Signed '___,," Commissions ' . . c u. - CERTIFICATE OF COMPLIANCE N/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 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 12/13/10 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*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*i, liable in anymanner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions (N.ýW &ý (M

15 RFO Inservice Inspection Summary Page 71 of 238 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 NPV-1 CERTIFICATE HOLDERS' DATA REPORT FO NUCLEAR PUMPS OR VALVES-As Required by the Provisions of the ASME Cod i, Section IlI, Division 1 Ps. I of 2 I Manufactured and certified by Eraalae* A Div. ol Cu*ne.Wri."h FlowCortrol Corp. omMercal Po-a & SeiMc: 2950 BirchSL Brea. CA92821 nrme and eddre't -of N Certifica*e Holderl 2 Manufactured for First Energy Corp.: P.O. Box 6100C1 Johnstown, PA 15907-6100 I(ame and address I I Pumfhassrt

3. Location of installation Davis-Besse Plant; 5501 North Star Route 2; Oak Harbor, OH 43449 (name and eddress) 4 Model No, Series No or Type. WAK Drawing MD214 0 Rev _ _ CRN_ None

5. ASMAECode, Section 111,Division 1: 1971 No 2 V None fedition) (addenda dal IlWass) lCede Case no.)

Pump or valve Permaseat Valve Nominal inlet size 10 Outlet size 10 6 tin ) (in.)

7. Material; Body SA-240 Tp. 316 Bonrnt N/A Disk 3A-A79 Tp. 316 Bolting SA-193 Gr. B8M 1/ V/

(al (bi (dl {e) Cart Nat I Body Bonnet Disk Holder s Board Serial Serial Serial Serial No. No. Noý No No 11487 None LIZ-13607 None KNG-12981 Supplemertal information In form of 1l1ts. sketches, or drawings may be u"ad provide# Ill dsizeis a X 11, [2i information in items 1 through 4 on this Data Report is included an each sheet. (3 eacah sheat Is numbered and the numa er of sheets is recorded at the top of this form (12/88) This form (12000371 may be obtained from the Order Dept. ASME 22 Ltw Drive Box 2300, Fairfield NJ 07007-2300. REPRINT6A3

15 RFO Inservice Inspection Summary Page 72 of 238 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 NPV-t (Back - Pg. 2of 2_1 Ce fificate Holder's Serial No._ 11487

8. Design conditions 475 psi 350 =p o valve pressure class _ _ 300 _ 1_

I-{presasrel (ternperaturel 9 Coid working pressure 720 psi at 100*F t0 Hydrostatic test 1100 psi Disk differential test pressure psi 11 Oty. 1, Enertech Project Number 810109 End Cap MatT SA-240 Type 316 CERTIFICATION OF DESIGN Design Specification certified by Thomas R. O'Reilly, Jr. P.E, Stea MD Rag no. 20742 Design Report certified by Ira J. Silverman P.E. Sta CA Reg no. 23241 CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this pump r valve conforms to the rules for construction of the ASME Code Section Ill, Division 1. N Certificate of Authorization Na. . N-2826 - . 10/11/08 Enertach. Curtiss-Wright Flow Control _ _ _ _ _ _ _ _ Date . Name Corp.. Commercial Power & Services IN Certificate Halder] Sigi edr (authorzed representative) CERTIFICATE OF INSPECTION 1, the undersigned, holding a valid commission issued by the National Board )f Boiler and Pressure Vessel Inspectors and the State or Province of California end employ ýd by HSB CT of Connecticut have inspected the pt rrp. or valve, described in this Data Report on 2/ 2 ' ~ and state that to the best of my knowled ]e and belief, the Certificate Holder has con-structed this pump. or valve, In accordance with the ASME Code. Section III, Di islon 1 By signing this certificate, neither the inspector nor his employer makes any w arranty, expressed or implied, concerning the component described in this Data Report., Furthermore, neither the inspector no his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or cant acted with this inspection, Date Ingsted [ .Commissions [Authorized Inspectr) [Net'l.,td. leel. endorsements) anestate o, pnev.ane no I (1) For manually operated valves only.

15 RFO Inservice Inspection Summary Page 73 of 238 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-1I/NWROWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner FirstEnergy Corp. Date March 6, 2008 76 South Main St., Akron. OH 44308 Sheet I of 2 Add,,n

2. Plant Davis-Besse Nuclear Power Na~n Station Unit #

5501 N. SR. 2, Oak Harbor-, OH 43449 Order # 200067205 Hetr tdU~fz=bof90o.NiO.. 30bNa. Okc.

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 07117/10

4. Identification of Systems DH Cooler 1 Outlet Flow control DB-DHI14B (Subsys 049-02)

5. (a) Applicable Construction Code ASME IIl CL.2 1971 Edition No Addenda Code Case No (b) Applicable Edition ot Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case No (c) Design Responsibilities First Enemrgy Corp, Enertech (Curtiss-Wright flow Control Corp.)

6. Identitication 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 10" Buitertly Valve Valtek Inc. 60284.002.2 N/A DB-DH14B 1988 Replaced Yes 10" Butterfly Valve Enertech S/N: 11488 N/A DB-DH14B 2006 Replacement Yes 16-1"x 10" Studs Nova Machine Products HT#08418 N/A TC#4R609 2005 Replacement No 24- 1 Nut-Hex Hvy. Nova Machine Products Corp HIf1716864 N/A N/A 2003 Replacement No 8- 1 Nut-Hex Hvy. Nova Machine ProductsCorp. HT#726125 N/A N/A 2003 Replacement No Flange Bolting Mat'l Unknown Unknown N/A N/A ' Unk. Replaced. No

7. Description of Work Existing butterfly valve (serial# 60284.002.2) was replaced with a new butterfly valve (serial#11488) during routine maintenance.

During valve change out, the existing flange bolting materials were also replaced with new bolting materials as 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 NOP psi Test Temperature NOT '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 form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2iX 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.

15 RFO Inservice Inspection Summary Page 74 of 238 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 ApplaN, ManuMdt-.,s DatiRq=ift lOb. A ,rfl

9. REMARKS Enertech (Curtiss-Wright Flow Control Corp.)

CERTIFICATE OF COMPLIANCE I, Lynn R. Wagner , certify that the statements made inthis 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 0'6 Ls -0O- FENOC Signed Q.C, CERTIFICATE OF INSERVICE INSPECTION Thomas T, 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 ot OHIO and employed by HSB CT.. of Hartford, CT have inspected the work described in this report on MiA ýG ',2tJýMandstate 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 1lJQ, Signed J--.-,. Commissions -,4ýS 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 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 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 Hai dord. 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 bet,ý. 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 bladjn.t.*laoOn. lnoS) rnr) .

15 RFO Inservice Inspection Summary Page 75 of 238 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 U I-. FORM NPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES" As Required by the Provisions of the ASME Code, Section I11,DIvIsion 1 I Pg.. I of 2 I 1. Manufactured and certified by 2, Manufactured for Emnech. A Oiv.of Curtafi--Mghl Flow ControlCoop.Coa-ercis Po-W &Sorocos; 2950 BirchSL: BrbaeCA 62821 Iname and sddress of N Certificate Holder) First Energy Corp.; P.O. Box 6100; Johnstown, PA 15907-6100 (name and address of Purchasar) I 3. Location of Installation Davis-Besse Plant, 5501 North State Route 2; Oak Harbor, OH 43449 (name and address) 4.. Model No., Series No., or Type .vK Drawing Rev..

None I 5. ASME Code, Section III, Division 1: 1971 (ediion)

No ladd endadate) 2 ilass} None lCode Case no I I S. Pump 7 ,Material: or valve Permaseat Valve Body SA-240 Tp. 316 Nomninalnleti Bonnet size N/A 0 10 oin,3 s Outlet size Disk SA-479 Tp. 316 6 10

                                                                                                                                           }       1 Bolting SA-193    3 Gr. B8M I                       (a)

Cart (b) Nat'l (c) Body 1d" Bonnet Disk Holder's Board Serial Serial Serial I!___ SIrial'No, .:No,. No. No: 11488 None LIZ-1 3608 None LNF-16584 i ___ I__ I I _ _ _ _ _ i _ _ _ _ _ I _ _ _ _ _ I - Suppleeentad Information In form of lists, sketchae, or drawings may he used provided 1l) size Is $14 x 11, [2) information In Items 1 through 4 on ibis Date Report is Included on each cheet, (atsealsheat Is numbered and the number of sheets I. recorded At the top 61 Iths WrTa 112/131 This form JE00037) may be obtained from the Order Dept., ASME, 22 Law Drive, Box 2300 Fairfield. N.J 07007-2300. REPRINT6193 I I

15 RFO Inservice Inspection Summary Page 76 of 238 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 NPV-1 (Back -- Pg.. 2 of .2 Certificate Holder's Serial No 11488 3

80. Design conditions 475 psi 350 .F or valve pressure class 300 (1)

[pressurel) Iterperaturni

            .. Cold working pressure             720           -    psi at 100*F 10,. Hydrostetic test           1100          psi. Disk diffdrential test pressure                                                               psi

11. Remarks: Qty. 1, Enertech Project Number 810109 End Cap Matt: SA-479 Type 316 . I, CERTIFICATION OF DESIGN Design Specification certified by Thomas R. 6'Reilty, Jr. P E. State - MD Reg. no 20742 Design Report certified by ,ra'1" Silverman P..E. State CA Reg, no 2 CERTIFICATE OF COMPLIANCE We certify that the statements made in this report amecorrect end lhat this pump or valve conforms to the rules for construction of the ASME Code, Section III, Division 1..

NCertificate of Authorization No. N-2826 E Ira_1_10/11108 Enertech, Curtiss-Wright Flow Control atfatPowel'dr)& Services Sind, el4rzdrpr=tmie

                             *J    - Name     Corp., Cornmercdall~

Ri Certificate Holder) letirzdrpr.esenttiva CERTIFICATE OF INSPECTiON I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vassal Inspectors end the Stale or Province of California and employed by HSB CT of Connecticut have Inspected the pump. or valve, described in this Data Report on of --* *-end Intet that' to the best of my knowledge and belief, the Certificate Holder has con-structed this pump, or valve, in accordance with the ASME Code, Section III, Division 1.; By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the component 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 e loss of any kind arising from or connected with this Inspection. Date 01,Signed isin 4 INetil. Ed, ilncL endorseerental and state or preY. and no,] U_/4 (1) For manually operated valves only, i U

                                                                                          *                                  .                                          I

15 RFO Inservice Inspection Summary Page 77 of 238 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)-t DB-0070ý5 FORM NlS°2/NR=1/ 4 OWNER'S REPORT FOR REPAIRS OR REPLACEM=ENTS As Required by the Provisions of the ASME Code Section X1 1 Owner FitstEnergy Corp. Date November 20, 2007 Nam. 76 South Main St.. Akron, OH 44308 Sheet 1lof 2 2 Plant Davis-Besse Nuclear' Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 Order #200099433 A.dN'eaa aapa..O, a OqNzaio, P.O.No.,JobNo..e* 3 Work Performed by FiostEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2, Oak Harbor, OH 43449 Authorization No 20 Exoiration Date 07/17110

4. Identification of Systems Decay Heat Pump I Injection Line Relief Valve - DB-DHI529- (SUBSYS 049-02) 5 (a) Applicable Construction Code ASME III CL.2 1971 Edition W72 Addenda Code Case N/A (b) Applicable Edition of Section Xt Utilized for Repairs or Replacements 19 95 Edition 9 Addenda Code Case N/A id) Design Responsibilities FirstEnergy Corp., Anderson Greenwood Ciosby

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 Relief Valve J.F Lonetgan 304400-14-1 N/A DB-DH1529 1975 Replaced yes Relief Valve Anderson Greenwood Crosby N99716 N/A DB-DHI529 2006 Replacement Yes

____________________0001 _____________ _______

7. Description of Work Existing relief valve (serial # 304400-14-1) was replaced with (Serial.# N99716-00-0001) duzing routine maintenance.

Valves ate like foT like replacement s. A VT-2 initial insetvice leakage test was performed satisfactory.

8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure 188 osi Test Temperature 75 -F Pressure Relief Valves:

Service N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Biowdown Adjustments Made Using N/A (T.. M ;@...) at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 YuX 11 in.. (2) Information in items 1 through "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.

15 RFO Inservice Inspection Summary Page 78 of 238 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-1N-VR- 4 Applc-rd b ueUrer UclaR0fls be Alteled

9. REMARKS Anderson Greenwood Crosby.

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" staip.expires 07/17/10 Date 11-2 0- D7 FENOC . Signed Q.C. oi,,pepo,omeor* (f~lram a*) , (orma.d.hmtpceoor,am:eI "- CERTIFICATE OF INSERVICE INSPECTION I Tom 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 haveinspected the work described in this report on t46". r o-7 and state that to the best of my knowledge and belief, this repair, modification or replacement has been complete 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 It12:7 __t,1 Signed I [ (nlpel~r)' I* Commissions al Board Natofo fl~d aaoel A

                                                                                                                                                       *1I,V
                                                                                                                               *nd rlad~tone *oBrA 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. (flfl al repairoglvza~oaf) (ertnrl~zed*:al 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.

By signing this certificate, neitherthe 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 beii" 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 (Netiorisi BoardC[deno~nle), erAireidAAioB.ena )

Page 79 of 238 15 RFO Inservice Inspection Summary 76 South Main St., Akron, Ohio 44308 FirstEnergy Nuclear Operating Company, Ohio 43449 Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Davis-Besse Nuclear Power Station Commercial Service Date: July 31, 1978 Sheetlof2

           /
           /

FORM NY-I FORSAFETY AND SAFETY RELIEF VALVES As required by the Provisions of the ASME Code Rules

DATA REPORT

i. Manufactured By Anderson Greenwood Crosby, 43 Kendrick SL., Wrentham, MA 02093 Name and Address Model No.. JLT-j3S-35-S Order No. U967720000 Contact Date 10/19/05 National Board No. -

TYPE E

2. Manufactued For FIRSI ENERGY CORP. Order No. 451*71850 Name and Address

3. Owner FIRST ENERGY CORP.

Name and Address

4. Location of Plant DAVIS BESSE 5.. Valve Identification DH1529 Serial No.. N99716-O0-0001 Drawing No. DS-C-99716 REV. 4-.

Type SAFETY RELIEM Orifice Size 0.665 Pipe Size. -. Inlet 1.5 Outlet -2.. Safety, Safety Relief, Pilot" Power Actuated Inch Inch Inch

6. Set Pressure (PSIG) 450 ~ A80 Rated Temperature "

                                                                                                                       ' 8-a--

o1 Stamped Capacity GPM1 L193 WATER @ 70 DEG-9 @ 10 % %Overpressu~re Blowdowa (psig) 110%7. 4 Complete Valve 100 T' rostatic Test (PSIG) Inlet 1100

7. The material, design, construction and workmanship comply with ASME Code, Section 11.

197Z Class 2 Edition 1971 Addenda Da.Y _______ Caseo._NI Contan oWINr Presur PR4-9s-- Case No. N/A Pressnre Containing or Pressure Retaining Components , -"/ Serial No., Material Specification Identification Including Type ou Grade

a. Castings Body N900L59-32-0003 ASME SA351 GR. CF8M Bonnet N97794-35-0008 ASME SA351 GK CF8M Ii b.Bar Stock and Foigings Support Rods ii Norzle N97792-33-0005 ASME SA479 TYPE 316 Disc Insert) N97793-NGYC ASME SA479 IYPE 316 N96827-36-0017 Spring Washers N96827-36-018 ASME SA479 TYPE 316.

Adorinstg Bolt N96828-34-0010 ASME SA479 TYPE 316 Spindle N900162-32-O005 ASME SA479 TYPE 316

/,/

Page 80 of 238 15 RFO Inservice Inspection Summary 76 South Main St., Akron, Ohio 44308 FirstEnergy Nuclear Operating Company, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Davis-Besse Nuclear Power Station Unit #1, Commercial Service Date: July 31, 1978

Q C.-44c&

                 . V-1 (Back)              Certificate H[older's Serial No.                   N99716-00-0001                             Sheet 2 of 2 Serial No.                                  Material Specification Iyifi,        *      //.      "           Including Type or Grade e.. Spring                                                         4ý4 -0002                       '2.       ASIM A313 TYPE 316 d.. Bolting e, OtherParts such as Pilot Components Bonnet Stud                                               N900163                                 ASME SA564 GR. 630
    -*     Bonnet Nut                                                           t46;34?1 ,55                 ASME SA194 GR. 8M 7*W__.F"*-,¢cu-oG J7.'f;~

We certify that the statements made in this report are correct Anderson Greenwood Crosby . Date Z-" 20 0 L, Signed Wrentham, MA By - ,,. '. -- Manufacturer titificate of Authorization No N-1878 Expires 30-Sep-07 Date

                                                          .FTF'TK77TATi? aF S     .- Tj P 1.*P1?CTTaN 1, the undeo signed, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectois and the State or Province of MA          and employed by HSB - C1 have inspected the equipment described in this Data Report ou jf;-/-20 06           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 lIi..

By signing this certificate, neither the Inspector nor his employer makes any waTranty , 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 fam or connected with this inspection-ii Date 5"1&& ;? r 200 6

                                              &A-* .2*'    -    Commissions              MA-1420 A,N, I (Inafetor)                                (National Board, State, Province and No.)

I ./I )

15 RFO Inservice Inspection Summary Page 81 of 238 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-9_NPR-1iLRMU 1. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl 1 Owner FirstEnergy Corp. Date October 3, 2006 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, OH 43449 Order# 200123859 R.pN*-O~ro.oo P.Q.Ne.,Jo. N... .,o. 3 Work Performed by FirstEnergy Nucleax Operating Co. Type Code Stamp NR Nak.l 5501 N. SR. 2. Oak Harbor, OH 43449 Authorization No 20 Expiration Date 07/1 7/07

4. Identification of Systems CS Pump I Cyclone Separators -DB-CS4- (Subsys061-01)

5. (a) Applicable Construction Code ASME IIl CL.2 1971 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 Responsibilities First Energy Corp

6. Identification of Components Reoaired or Replaced and Reolacement Components Manufacturer's National Other Identificationl Year Repaired ASME Name of Component Name of Manufacturer Serial No Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped Flange Bolting Unknown Unknown N/A N/A Unk. Replaced No 4 - 5/8" x 3 1/4" Studs Nova Machine Products Corp. HI# 229801 N/A DB-CS4 2000 Replacement No 8 - 5/8" Hvy Hex Nuts Nova Machine Products Corp. HT# 718732 N/A DB-CS4 2000 Replacement No

7. Description of Work Existing flange bolting was replaced with new. during routine maintenance as recruired by design soecification chanee for boltina material.

A VT-2 inservice leakage test was performed satisfactory. 8 Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other Yes Pressure 32 psi Test Temperature NOT " F Pressure Relief Valves: Size N/A Service N/A Opening Pressure N/A Blowdowr* (if applicable) N/A Sot Pressure and Blowdown Adjustments Made Using N/A at N/A (Looat.on) NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2/2 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 top of this forma

15 RFO Inservice Inspection Summary Page 82 of 238 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 A/wpbrta4. M~madnursla OatsReportInbeAflacthed

9. REMARKS N/A CERTIFICATE OF COMPLIANCE Richad R. Cockiell 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" starexpires 07/17/07 Date iD-oL -O(, FENOC Signed JZ. Q.c.

CERTIFICATE OF INSERVICE INSPECTION 1, Tom 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 ...OM 3;*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 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 to 3 aoo(. Signed " ., Commissions a 'oC 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 12/13/07 National Board Certificate of Authorization No.. 20 to use the "NR" stamp expires 07/17/07 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, CI have inspected the repair, modification or replacement described in this report on n/a 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.tlo"alIord Oad an- turis

                                                                                                                       *sra    nd rn)}

15 RFO Inservice Inspection Summary Page 83 of 238 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/NWR--4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI

1. Owner FirstEnergy Corp. nate February 20, 2007 76 South Main St. A"kr. Addras OH 44308 Sheet 1 of I 2 Plant Davis-Besse Nuclear Power Station Unit #1 Name 5501 N. SR. 2, Oak Harbor, OH 43449 Order # 200140451 3 Work Performed by FitstEnetpy Nuclear Ope!ating Co. Type Code Stamp NR N5 2r 5501 N. SR. 2. Oak H arbigir, OH 43449 Authorization No. 20 Expiration Date 07/17/07 4 Identification of Systems SG 2 Drain Line Isolation Valve - DB-MS603- (Subsys 063-01) 5 (a) Applicable Construction Code ASME Ill CL.2 1971 Edition S71 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 Responsibilities First Energy Corp, Velan Engineering Co.

6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other ldentificatior/ Year Repaired ASME Name of Component Name of Manufacturer Serial No Board No Jurisdictional No. Built Replaced or Cede Replacement Stamped 4" B.B.Gate Valve Velan Engineering Co. 0038 N/A DB-MS603 1973 Repaired Yes 8 - 5/8" x 3 3/4' Studs Unknown Unknown N/A N/A UnI. Replaced No 8 - 5/8 x 3 3/4" Studs Nova Machine Products H T# 224938 N/A N/A 2005 Replacement No

7. Description of Work During routine maintenace on this bolted bonnet gate valve, the valve was disassembled, refurbished and reassembled. During reassembly, body to bonnet studs were replaced. All other pressure boundary items were teused.

A VT-2 inservice leakage test was performed satisfactory. QL 8 Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure 850 osi Test Temperature NOT '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 in the form of lists, sketches, or drawings may be used, provided (1) size is 8 14 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 top of this form.

15 RFO Inservice Inspection Summary Page 84 of 238 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/NtR-4 ApPcLUeNManufae rs 01WRepm be Acad

9. REMARKS N/A CERTIFICATE OF COMPLIANCE I, Richard R. Cockiell , 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" starpfxpires 07/17/07 Date 0-W--20 o07 FENOC Signed Q.C. (n*m of ,1 r *ug.n4. n) ?ff1t0rmtd

                                                                                             "'          reptal7I CERTIFICATE OF INSERVICE INSPECTION Tom 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                  f-3.o0,Co"T and state that to Fthe best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Sectiornf I 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 al ,100a-7 I " Signed tj ý 4iww fnl~~, Commissions t.Xt bNafIrCCO 8,a/d mM.fd I3,i T_ endo ,M~a. cLa 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 12/13/07 National Board Certificate of Authorization No 20 to use the "NR" stamp expires 07/17/07 Date IENOC 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, CI have inspected the repair, modification or replacement described in this report on N/A 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 (flflonaJBoafo ('ciftltafnc,.n1.). lit M,,dstto,,s *fldm))

15 RFO Inservice Inspection Summary Page 85 of 238 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/N.V-R-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl 1 Owner FirstEnergy Coip. Date December 2,2006 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. OH 43449 Order# 200162515 A*dd-s tpk O,5onalzoljo P.O No..JoNNo.. 3 Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR

                         *_5fl1 N. ,t1. 2. flak Harbor. 08-       43449                               Authorization No       20 551"IllN qR 2 Oak Harbor Off 43449 Expiration Date     07/17107 4   Identification of Systems        Containment Vent Header Relief Valve -DB-RC769- (SubsysO64-01) 5    (a) Applicable Construction Code          ASME III CL.2          1971 Edition         No Addenda                   Code Case NO (b) Applicable Edition of Section XlUtilized for Repairs or Replacements        19    95     Edition       96... Addenda Code Case                 No (c)   Design Responsibilities. First Eneigy Corp

6. Idantifirrntinn of flomeonnnta Rrrnairnr or Renlanrard and Re~nlro'acomnt f'lnmnonnrante 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 Relief Valve Fig. Bitg Unknown Unknown N/A N/A Unk. Replaced No 4-5/8" x 4" Studs Nova Machine Products Corp. HT# 74896 N/A N/A 2004 Replacement No 8 -5/8 HIvy Hex Nuts Nova Machine Products Corp. H1I#G8520 N/A N/A 2005 Replacement No

7. Description of Work During routine maintenenace (change out )of relief valve DB-RC769, the inlet flange bolting was replaced with new.

Studs were cut forom a piece of continues threaded tod to requited length. A VT-2 initial inservice test was completed satisfactory. 8 Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other Yes Pressure NOP psi Test Temperature NO -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/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 top of this form.

15 RFO Inservice Inspection Summary Page 86 of 238 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-1IN-WR-1 Ap9*h,, Mantjctt. DataRepattt beAtahd

9. REMARKS N/A CERTIFICATE OF COMPLIANCE Richad R. Cocki ell , 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..ex ires 07/17/07 Date 12-OZ-.- FENOC . Signed (Z "A.9- Q.C. Enm" At ra rantoaon) W(ot te rap'a laatatv) , CERTIFICATE OF INSERVICE INSPECTION 1, 1orn 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 Haitford, CT have inspected the work described in this report on DEL.,. 1 p 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 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 I151 I

                           ;, S>06     Signed                      .*

J4, Commissions tkA! 04*3Sd pA r* A A.. i I (Nattotal Eo.tt pent

                                                                                                                                           .,dttNrnen~a).
                                                                                                                           *edttoiatbottOot mAne))

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 12/13/07 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/1'7/07 Date FENOC Signed Q.C. (tothotaadre,,atoaatAt) 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 OI-O and employed by HSB C1 of Hartford, CT have inspected the repair, modification or replacement described in this report on N/A 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 0tflP-oo) (NatAnalPoeM (Itch entO,,eenwtta). eta InnadAtAtne andac))

15 RFO Inservice Inspection Summary Page 87 of 238 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 r Iq FORM NIS-2(NR-1JI.lR1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provtsions of the ASME Code Section XI

1. Owner FirktEnelgy COTap. Date February 26, 2007 76 South Main St.. Akron, OH 44308 Sheet 1 of 1 2 r'lant Davis-Besse Nuclear' Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 200189329 3 Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR 1;01 N-. qR I- Oak Ty-Arbr 0114 J1449 Authorization No. 20 Expiration Date 07/17107 4 Identification of Systems Main Steam Sys - DB-SNA411 (SUB SYS 083-01) 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 1996 Addenda Code Case N/A (c) Design Responsibilities First Energy 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 Serial No Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped Snubber LISEGA 61195153 N/A M1 149/H5 UNK replaced N/A Snubber LISEGA 30500235/095 N/A MI 148/H5 UNK replacement N/A

7. Description of Work Snubber SNA-411 S/N 61195/53 was replaced with snubber S/N 30500235/095 in hanger location M1148/H5.

5.(a) cont. ANSI B3 1.1 & MSS-SP58 1967 EDITION OR LATER 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 Slowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A at N/A N'.: E; Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 V2X11 in. (2) Information in items I through ton this reoort is included on each sheet, and (30 each sheet is numbered and the number of sheets is recorded at the too of this form.

15 RFO Inservice Inspection Summary Page 88 of 238 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-1la Rr "t' Applce a, oa . 0., Repoats b to Auýtd

9. REMARKS N/A CERTIFICATE OF COMPLIANCE I, Ronald Shalda certify that the statements made inthis 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 07/17/07 Date ?-z3/4< "7 FENOC (on,., Of,tepOBtaruza.Onf Signed r. (aot hciza e..p~r~aeroale) Q.C. ! CERTIFICATE OF INSERVICE INSPECTION 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, Cr have inspected the work described in this report on PeG.f-l o307 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 th.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 Signed ______ _____Commissions AZBg3 3 p K I

endlutf0Ioo aB no))

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 12/13/07 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/07 Date FENOC Signed Q.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 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 Xl of the ASME Code and the National Board Inspection Code "V'R" 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 inthis 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 pnsp ectr) Commissions NSLoaB Boatnal eaa=fl*emenfl,), (

15 RFO Inservice Inspection Summary Page 89 of 238 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 55Q1 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070..4 FORM NlS-21NR-1I 9WIRI OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1..OnrFi*~ e'g o Date May 26,2006

1. Ower Frst~ezgyCorp Sheet I of 1

                       '76 qnuth Main St. Akron 014 44308

2. Plant Dayis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 Order # 200200285 TP.p CoAde ___

P.O.H., Jt NR., Type Code Stamp .R-_ N 3 Work Performed by FirstEnergy Nuclear Opex atinu Co. N... 5501 N. SR, 2, Oak Harbor. OH 43449 Authorization No, 20) Explration Date 07/17107 4 Identifliation of Systems Reactor Coolant Pumps, Motors, & Lift Pump Supports (SubsysO64-03) 5 (a) Applicable Construction Code ANSI B31.1 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Section XAUtilized for Repairs or Replacements 19 9.5.._.Edition 96 Addenda Code Case No (c) Design Responsibilities _First Energy 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 tO Pipe Supports First Energ Corp N/A N/A N/A 2006 Repaired .No

7. Description of Work Modified ten small bore pipe support as required by ECR 05-0142-00.

All materail installled are recorded in the work order and identified on the design drawings. All supports were visually inspected after installation by Design Engineering and Quality Control. 5.a (cont) ANSI B31.1 & MSS-SP58 - 1967 Edition or Later B. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure .-.IA - - psi Test Temperature N/A "F Pressure Relief Valves: Service N/A Size NIA Opening Pressure N/A Blowdown (if appticable) N/A Set Pressure and Biowdown 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 'AX 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.

15 RFO Inservice Inspection Summary Page 90 of 238 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-1IW.R4

9. 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" starp-Vxpires 07/17/07 Date 05 - 2&-. o&. FENOC Signed k_* Q.C.. CERTIFICATE OF INSERVICE INSPECTION I, 'Tom 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 cr of Hartford, CT have inspected the work described in this report on AsjE" J..3a06 and state that to the best of my knowledge and belief, this repair, modification or replacement has been completea 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 t , 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 12/13/07 National Board Certificate of Authorization No.. 20 to use the "NR" stamp expires 07/17/07 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 C1 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

15 RFO Inservice Inspection Summary Page 91 of 238 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-007SP4 I FORM NIS-2/NR-1/NVRT OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions oi the ASME Code Section XI 1 owner FistEnergy Corp. Date May 17, 2006 76 South Main St.. Akron. OH 44308 Sheel 1 of I 2, Plant Devis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 Order # 200203452 3 Work Pedrormed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No 20 Expiration Dati 07/17107... 4 identification of Systems Makeup and Letdown System (Subsys065-01)

5. (a) Applicable ConstructIon Code ANSI B31.1 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 No (c) Design Responsibilities First Energy ....... ...

6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identiflcatiorn Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Coda Replacement Stamped Supports NA NA __ NA NA 2006 Replacement NA

7. Description of Work ECR 05-0142-00 modified four hangers on DCN FSK-M-CCB-8-6-HI. PG44 straps were replaced with PG53 straps. The additional material installed is recorded in the work order and identified on the design drawing.

a. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure ,NA psi Test Temperature NA -F Pressure Relief Valves:

Service NA Size NA Opening Pressure NA BSlowdown (ifapplicable) NA Set Pressure end Blowdown Adjustments Made Using NA o.., e. at NA NOTE: Supplemental sheets in the form of lists, sketches, or drawings maybe used, provided (1) size Is 8 V2X 11 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 too of this form.

15 RFO Inservice Inspection Summary Page 92 of 238 FirstEnergy Nuclear Operating Company, 76 South Main St., Akrofi, 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"0O70-4 FORM NIS,-2lNR-1INVR"1-- _____ _________bW_____

9. REMARKS NA CERTIFICATE OF COMPLIANCE 1, Melvin D. Hurley , 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 CodesNR" rules.

National Board Certificate of Authorization No. 20 to use the "NR" stamp expire 17/07 Date .. FENOC Signed CERTIFICATE OF INSERVICE INSPECTION I, Tom 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 0M-0 and employed by HSB CT of Hartford, CT . have inspected the work described In this report on . 6 and state that to the best of my knowledge and belief, this repair, modification or replacement has been comflate 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 JWIiI kL ,kAL "Isi Commissions CL CERTIFICATE OF COMPLIANCE I, 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 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 12113/07 National Board Certificate of Authorization No. 20 to use the "NR' stamp expires 07/17/07 Date FENOC Signed _---._._ CERTIFICATE OF INSERVICE INSPECTION NA holding a valid commission issued by the National Board of Boiler and Pressure Vessel 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 this report on NA 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

15 RFO Inservice Inspection Summary Page 93 of 238 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 DR43070-4 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 December 2, 2006 76 South Main St.. Akron. OH 44308 Sheet 1 of 4

2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 Order# 200207115 Madd. Rep. Orsarzeon P.o Mt.. t No..e 3 Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NRJVR 5501 N. SR. 2, Oak Harbor, OH 43449 Authorization No. 20/316 Expiration Date 07/17/07 12-13-07

4. Identification of Systems Pressurizer Power Operated Relief Valve -DB-RC2A- (Subsys064-04) 5 (a) Applicable Construction Code ASME IlI CL.1 1971 Edition W71 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 Responsibilities Crosby Valve & Gage Company, 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 Replaced or Code Replacement Stamped I - PORV Crosby Valve & Gage Co N56969 N/A DB-RC2A 1977 Repaired Yes 0001 Disc-Main Valve Anderson Greenwood Crosby N95209 N/A N/A 2005 Replacement Yes 0009 Disc - Pilot Valve Anderson Greenwood Ciosby N90931 N/A N/A 2005 Replacement Yes 0009 Nozzle - Main Valve Anderson Greenwood Crosby N95208 N/A N/A 2005 Replacement Yes 0008 Nozzle - Pilot Valve Anderson Greenwood Crosby N90932 N/A N/A 2005 Replacement No 0019

7. Description of Work Existing Pressurizer PORV (serial# N56969-00-0001) was rebuilt replacing existing pressure boundary parts with new like fot like replacements parts.

After rebuild, valve was leak tested to 2250 PSIG per procedure DB-MM-09000. i Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other Yes Pressure 2250 psi Test Temperature NOT 'F Pressure Relief Valves: Service Steam Size 2 W"' Opening Pressure No Blowdown (if applicable) No Set Pressure and Blowdown Adjustments Made Using No (a MT-nt at Davis-Besse Nuclear Power Station (L*oion 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 1through 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.

15 RFO Inservice Inspection Summary Page 94 of 238 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

                                                                                                             .Apvlsb*Ie M.,,dactn DataR  .podo Wb Attah-d

9. REMARKS Anderson Greenwood Crosby CERTIFICATE OF COMPLIANCE 1, 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" staq.R expires 07/17/07 Date J2-b2- FENOC 1in of wganLzaloni e palar Signed (autLorta*d prwl~al.)

Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Tom 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 Haitfold. Cl have inspected the work described in this report on "ber..q aoeL and state that to the best of my knowled*e 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 '.t*6* 0 Signed " Commissions RTh CtT t'. 17 C'sI.. CERTIFICATE OF COMPLIANCE Richard R. Cockrell 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 '"RW and "NR" rules.. National Board Certificate of Authorization No.. 316 to use the "VR" stamp expires 12/13/07 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/07 Date 12-01.04 FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION T, G. Laps 1'o0 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 CI of Hartford, CT have inspected the repair, modification or replacement described in this report on M and state that to the best of my knowledge and belief, this repair, modification or replacement has been ritedinaccrdance 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 \3-11 Date Signed"W igned( 111tq

                                                                ,                 amf, Commissions            ________

O).

15 RFO Inservice Inspection Summary Page 95 of 238 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 -392 "* .... FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR IDENTICAL NUCLEAR PARIS AND APPURTENANCES* As required by the Provisions of the ASME Code, Section II, Division I - Not to Exceed One Day's Production I Manufactured and uertified by Anderson Greenwood Crosby, 43 Kendrick St., Wrentham, MA 02093 (Name and Address of N Certificate Holder) 2 Manufactured for FIRST ENERGY CORP. (Name and Address of Purchaser or Owner) 3 Location of Installation DAVIS-BESSE NUCLEAR POWER PLAN! (Name and Address) 4 Type DS-C-56969-2 REV.A INCONEL 718 185,000 - 2005 (drawing no..) (mat'l spec. no.) (tensile strength) (CRN) (year built)

5. ASME Code, Section II, Division 1: 1971 W71 I --

(edition) (addenda date) (class) (Code Case No) 6 Fabricated in accordance with Const. Spec (Div 2 only) -- Revision - Date -- (no..) 7 Remarks 8 Nor. thickness (in.) -- Min. design thickness (in..) - Dia. ID (ft & in.) - Length overall (ft & in) .

9. When applicable. Certificate Holders' data reports are attached for each item of this report.

Part or Appurtenance National Part or Appurtenance National Serial Number Board No. Serial Number Board No. in Numerical Order in Numerical Order (I) N95209-37-0009 (26) _ (2) (27) _

             .(3)                                                                                      (28)

(4) (29) _ (5) (30) ....

              *(6)                                                                                    (31)

(7) (32) (8) (33) (9) '(34) (0o) (35)_ (36)_ (12) (37) _ (13) (38) (14) (39) (15) (40) _ (16) (41) (17) (42) (1,8) (43) (19) (44). (20) (45) (21) (46) (22) (47) (23) (48) _ (24) (49) .... (25) (50) 10 Design pressure -- psi Temp. -- F Hydro.. test pressure 4600 PSIG at temp. 70 0 F (when applicable) Supplnnn_.a: Wi."".0-ian hin th t-ot, o.1li n k-h.s an sroaning* ily bin..od pronided (1) .ao is B-1/2 . 11 nt) ononion in ino 2 "od3 oa his D.a. tIn.n-S *Ciklndl e'at noclrahno nh xil an is iumllinno

                                                      -       and i. ,isor
                                                              .t                Snanois nnaadnd
                                                                                         -    W a. h.p WI d.1 tlan.

TthiW Iin {5XXAUI -myb, t Ian, In Onodn Dayn 5kAIE22 L-n Prive Ba, 2300) Fltirfid NJ 1n7[02.]021o)

15 RFO Inservice Inspection Summary Page 96 of 238 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.-392 Form N-2 (Back) Sheet 2 of 2 Certificate Holder's Serial No. N95209-37-0009 CERTIFICATE OF DESIGN Design specifications certified by JOHN W. MERCHANT PH.. State VA Reg no 4418 (when applicable) Design report* certified by (whenapplicable)_P.E.. State _Reg no (when applicable) CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this (these) Disc conforms to the rules of construction of the ASME Code, Section III, Division 1.. NPT Certificate of Authorization No N-1877 Expires Sept. 30, 2007 Anderson Greenwood Crosby Date 3 - " , Signed Wrentharnt MA by "--D I-=.. > - (NPT Certificate Holder) (Authorized tepresencative) CERTIFICA TE OF INSPECTION I the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State ef-Po-eiree of /YA - and employed by HSB-CI ot Hartford-CT . have inspected these items described in tlis Data Report on 6, -3 , 20O and state that to the best of my knowledge and belief, the Certificate Holder has fabricated these parts or appurtenances in accordance with the ASME Code, Section (II, Division i. Each part listed has been authorized for stamping on the date shown above.. 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 loss of any kind arising from or connected with this inspection. Date -- 04 , 20 CS Signed / (Au -(Commissions MA-1420 AeNI S(Authorized Inspector) (Niat'l Bd. (inc. endorsements) and stare ar prov.. and no)

Page 97 of 238 15 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 QC-392 "" Shee'lo f 2 FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR IDENTICAL NUCLEAR PARTS AND APPURTENANCES* As required by the Provisions of the ASME Code, Section II, Division 1 - Not to Exceed One Day's Production i Manufactured and certified by Anderson Greenwood Crosby, 43 Kendrick St., Wrentham, MA 02093 (Name and Address of N Certificate Holder) 2 ilanufýactured for FIRST ENERGY CORP. (Name and Address of Purchaser or Owner) 3 Location of Installation DAVIS-BESSE NUCLEAR POWýER PLANt (Name and Address) 4 Type DS-C-56969 REV.G INCONEL 718 185,000 - 2005 (drawing no.) (mat'l.. spec. no..) (tensile strength) (CRN) (year built)

5. ASME Code, Section II1, Division 1: 1971 Wit I__

(edition) (addenda date) (class) (Code Case No.) 6 Fabricated in accordance with Const Spec.. (Div. 2 only) - Revision - Date -- (no.)

7. Remarks

8. Nom., thickness (in.) -- Min design thickness (in.) - Dia. ID (ft & in.) "-__Lengthoverall (ft & in,.) --

9. When applicable, Ceitificate Holders' data reports are attached for each item of this report.

Part or Appurtenance National Part or Appurtenance National Serial Number Board No. Sesial Number Board No. in Numerical Order in Numerical Order (I) N90931-35-0009 (26) (2) (27) (28) (3) (4) (29)_ (5) (30) (6) (31) (7) (32) (8) (3 3) . (9) (34) (0o)_ (35) . (I1) (36) (12) (3 7) . (13) (38). (14) (39) (15) (40)_ (16) (41) _ (17) (42) .., (18) _ _ (43) (19) (44) (20) (45) (21)_ (46) (22)_ - (47) (23) (48) (24) (49) (50) C (25) 10 Design pressure - psi.. Temp. " F Hydro. test pressure 4600 PSIG at temp 70 (when applicable)

          - suppic   A ijnformansionin ~ts form of liosssketches or drawings may bk me      provided (1) size is 8-tO2 x 11 (2) informadoain is*es; 2, and3 on (his Dan Report asincluded on maceshem Q3) each she" is r  hberedtnri Lhe, nssber of sts   is oo*sdsdat the
                                                                                     .is                sp of dlis form This fosm (55040) may bh obtained from the Order DeKp. ASME 22 Law Drive Box 2300 Fairfield NJ D7007-V2DO

Page 98 of 238 15 RFO Inservice Inspection Summary 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 -392 Sheet i! 0 2 FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR IDENTICAL NUCLEAR PARTS AND APPURTENANCES* As required by the Provisions of the ASME Code, Section III, Division I - Not to Exceed One Day's Production

           -1 Manufactured and certified by                               Anderson Greenwood Crosby, 43 Kendrick St., Wrentham, MA 02093 (Name and Address of N Certificate Holder) 2 Manufactured for                                                                   FIRST ENERGY CORP.

(Name and Address of Purchaser or Owner) 3 Location of Installation DAVIS-BESSE NUCLEAR POWER PLANT (Name and Address)

4. Type DS-C-56969 REV.G INCONEL 718 185,000 - 2005 (drawing no.) (mat'l.. spec. no..) (tensile strength) (CRN) (year built)

5. ASME Code, Section I. Division 1: 1971 W71 1 --

(edition) (addenda date) (class) (Code Case No.) 6 Fabricated in accordance with Conast Spec.. (Div. 2 only) _ -- Revision - Date -- (no.) 7 Remarks

8. Nom., thickness (in.) -- Min design thtickness (in.) - Dia. ID (ft &in..) -- Length overall (ft & in.) --

9. When applicable, Certificate Holders' data reports are attached for each item of this report.

Part ot Appurtenance National Part or Appurtenance National Serial Number Board No. Serial Number Board No. in Numerical Order in Numerical Order (1) N90931-35-0009_________ (26) (27) (28) (3)-_______________ (29) (5) ____________ _______ _ (30) (31) (7) ___ ____ ______ _______ _ (32) (33) (9) _____________ -_ _ _ _ _ (34) (10)_________ (35) (36) (12) .- (37) (13) ________ (38) (14) _________ (39) (15) _____ (40) (16) _______ _ (41) (42) (178) __ __ (43) (19) - (44) (20) _____________ (45) (46) (47) (23) -- (48) (24) - ________ (49) (25)_._________ (50) 10 Design pressure - psi.. Temp. F Hydro. test pressure 4600 PSIG at temp 70 " F (when applicable) S upplon ni inormaiof in a I.-m of 0i0 sk0chs of drawings may be wed provided (1) sizei is -1/2 x I1t (2) inormationin iaams2 and3 an tis Do= Report ia ind;non t*obn00d ne shn ch shon 03) -o.9 shn ia*, -Wnb ot Stozn is r.rdnd o d.* o P of mis f0-v ns14

                                 -                      Th;s form (E00040) may be obmined from th Order Dept. ASME. 22 Law Drive. Box 2300 FairiOnd NJ 07007-2300

15 RFO Inservice Inspection Summary Page 99 of 238 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.-392 Sheet I Qcf2 FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR IDENTICAL NUCLEAR PARTS AND APPURTENANCES* As required by the Provisions of the ASME Code, Section UI, Division I - Not to Exceed One Day's Production I Manufactured and certified by Anderson Greenwood Crosby, 43 Ke,.endlrck St., Wrentham, MA 02093 (Name and Address of N Certificate Holder) 2 Manufactured for FIRST ENERGY CORP. (Name and Address of Purchaser or Owner)

3. Location of Installation DAVIS-BESSE NUCLEAR POWER PLANT, (Name and Address) 4 Type DS-C-56969-2 REV.A ASTM A182 F316 N/A -- 2005 (drawing no..) (matT1. spec. no) (tensile strength) (CR.N)" (year built)

5. ASME Code, Section ffI, Division 1: 1971 W71 i --

(edition) (addenda date) (class) (Code Case No.) 6 Fabricated in accordance with Const. Spec. (Div. 2 only) - Revision - Date (no .)

             '7 Remarks

8. Nom. thickness(in.) -- Min.. designthickness(in) -- Dia.lD(ft&in) -- Lengthoverall(ft&in) --

9 When apolicable. Certificate Holders' data reports are attached for each item of this revort, Part or Appurtenance National Part or Appurtenance National Serial Number Board No. Seial Number Board No. in Numerical Order in Numerical Order (1) N95208-36-0008 (26) (2) (Z7) __ _ _ _ _ (35 (28) ____ (4) (29). (5) (30) (6) (31)...___ (7) (8) (33) (34)_ (9) (10),______ __ (35) (11) ..... _ ______ (36) (12) (07) (13) (38) (14) (39)- (15) (40) _ ___ (16) ____________ (41) (17) (42)_ (19 ) ... ... (44) (20) (45)_ (21) (46) (22)_ (47) _ _ (23) (48). (24) (4*9). . . . .. . . .. (25)_..... (50).______ 10 Design pressure -- psi. Temp -- a F Hydro. test pressure 4600 PSIG at temp.. 70.. - F (when applicable)

t grppklssrm entl i s o - r' i t* il aro sm arra o ls r, oordraw ings may b r eu s d pro vil c (l) sirr is 5- 12 1/l x II ~si ir or, aarior a tr n s 2a rs this O s rs sp i is int*,dt on 13)cacrhshoot is nrmbcrt antd the owaber ofdlt; is towrded at 5w top offits form hst, ss (t This rorm (EO0040) may be obtainusdfron ileOrder Dspt . ASME 22 L.- Drive Box 23)0 Falrfitld, NJ a7OO7-2300

15 RFO Inservice Inspection Summary Page 100 of 238 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 -392 Form N-2 (Back) Sheet 2 of 2 Certificate Holder's Serial No N95208-36-0008 CERTIFICATE OF COMPLIANCE

         -We certify that the statements made in this report are correct and that this (these)         Nozzle conforms to the rules of constrtuction of the ASME Code, Section Mi, Division IL NPT Certificate of Authorization No           N-1877       Expires      Sept. 30, 2007 Anderson Greenwood Crosby Date    ,qCVL o*                signed S.                . Wrentham, MA-         :       by    '      ..-.   "_____'

(NPT Certificate Holder) (Authorized Representative) CERTIFICATE OF INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of 40 and employed by HSB-CT of Hartford-CT .... hae inspected these items described in this Data Report on

                           !7-1 __    , 20 Zý_       and state that to the best of my knowledge and belief, the Certificate Holder has fabricated these parts os appurtenances in accordance with the ASME Code, Section M, Division 1.. Each part listed has been authorized for stamping on the date shown above.,

By signing this certificate, neither the Inspector nor his employer' makes any wauianty, 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 loss of any kind arising from or connected with this inspection. Date --- _ Signed JAsae.commissions MA-1420 AsNr I/Authorized Inspector) (Nat'l. ad (incl., endorsemens) and state or prov.. and nno.) V.

15 RFO Inservice Inspection Summary Page 101 of 238 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 3 1, 1978 DB-0070-5, FORM NIS-2/NR-1/I.fM-OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS of the ASME Code Section Xl As Required by the Provisions 1, Owner FirstEne'gy Corp. Date Fcbiuary 12, 2008 76 South Main SL. Akron, OH 44308 Sheet 1 of 2 Station Unit #) 2, Plant Davis-Besse Nuclear PowerN-r 5501 N. SR. 2, Oak Harbor, O1 43449 Order # 200209082 NPra f Orgniu. n P.O.No. Jb b .. .w

3. Work Performed by Firstlnergy Nuclear Operating Co. Type Code Stamp NR N5a O 5501 N. SR. 2, Oak Har~bor, OH 43449 Authorization No, ..20 Expiration Date 07/17/10

4. Identification of Systems SG 2 Drain Line Isolation DB-MS603 I (Subsys 063-01) 5 (a) Applicable Construction Code ASME m CL2 1971 Edition W72 Addenda Code Case No (b) Applicable Edition of Section XlUtilized for Repairs or Replacements 19 95 Edition 96 Addenda Code 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 Identlitcation/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No Jurisdictional No, Built Replaced or Code Replacement Stamped 4' Bolted Gate Valve Velan Engineering Co. s/n: 0038 N/A DB-MS603 1973 Replaced Yes 4" Bolted Gate Valve Velan Inc. s/n: 082001-1 N/A DB-MS603 2008 Replacement Yes

7. Description of Work Removed existing gate valve (s/n:0038) and replaced it with a new like for like replacement gate valve (s/n: 082001-1).

A VT-2 initial inservice 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 (ifapplicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A (UeotMediu) .. at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is a 1/2X 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.

15 RFO Inservice Inspection Summary Page 102 of 238 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-D070-5 FORM NIS-2/NR-1/NVR-1 Ap .a er Dablta - Wq: WoAttched S. REMARKS Velan Inc. CERTIFICATE OF COMPLIANCE I, Lynn Wagner 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 C - CERTIFICATE OF INSERVICE INSPECTION 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 CI of Hartford, CT have inspected the work described in this report on CES fl)*

                                                                                                            -      AotBnd 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 th.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 - . Signed __ _ _iCommissions 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 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 "4C and 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 C1 of Hartford, C I 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 31cr -m p *r~orfl4flSs), obo~dbIb,. .bo

Page 103 of 238 15 RFO Inservice Inspection Summary 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

                                                                           #082001-1 THRU -2 FORM NPV-i CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES As Required by the Provisions of the ASME Code, Section III, Division i Pg. 1 of 2

1. Manufactured and certified by Velan Inc., 550 Mc Arthur Street. Montreal. Quebec, H4T 1XB, Canada.

(name and address of N Certificate Holder)

2. Manufactured for First Energy Corp., 5501, North State Route 2. Oak Harbor, OH._ 43449, United States.

(name and address of Purchaser)

3. Location of installation Davis - Besse Nuclear Power Plant / Fiýst Energy Corp., 55D1. North State Route 2. Oak Harbor.

OH, 43449, United States. (name and address) 4..Model No., Series No., or Type B12-2D54B-02PS Drawing P012-641860-N01 Rev. B CRN NIA

5. (X)ASME Code, Section III,Divislon 1: 1971 Winter 1972 2 (edition) (addenda date) (claiss) (Code Case no.)

6. Pump or valve 600# BOLTED BONNET GATE VALVE Nominal Inlet size 4" Outlet size 4" (in.) (in.)

7. (XXCMaterial: Body ASME SA105 Bonnet ASME SA1 05 Wedge ASME SA105 Bolting ASME SA 193, Gr.B7 ASME SA 194, Gr.2H (a) (b) (c) (d) (e)

Cert. Nat'l Body Bonnet Wedge Holder's Board Serial Serial Serial Serial No. No. No. No.. No. 082001-1 N/A 7443 17424 7082 082001-2 N/A 7445 17423 7081 (X) Blow Out Pluq ASME SA1 05 082001-1 P708 082001-2 P707

           *Supplementat information in form of lists, sketches. or drawings may be used provided (1) size is t %, x 11, (2) information in items 1 through 4 on .ths Data Report is included on each sheet, (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

(12183) This form CE00037) may be obtained from the Order Dept.. ASME, 22 Law Drive, Box 2300, Ftl- [PAGIE -O

15 RFO Inservice Inspection Summary Page 104 of 238 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 NPV-1 (Back - Pg. 2 of 2 Certificate Holders Serial No. # 082001-1 THR U -2

8. Design conditions 915 psi 536 F or valve pressure class SO.LB ()

(pressure) (temperature)

9. Cold working pressure 1440 psi at 100' F 10, Hydrostatic test SHELL - 2175 psi, Disk differential test pressure N/A psi SEAT - 1500 k _

           ,I.f I¢1
                  ...... L.        1t*: 121111T VAI UI-.- }lk'*,WlNi';

1 1.Kema_:

                                   .(K MATERIAL CODE CONFORMS TO ASME SECTION I1,1995 EDITION, ADDENDA                                  1996.

CERTIFICATION OF DESIGN Design Specification certified by PAUL N. CARR P.E. State OH., USA - _Reg.. no.. E-39003 Design Report certfifed by S. ISBiTSKY .P.E. State QUE., CANADA- Reg. no.. 2211 CERTIFICATE OF COMPLIANCE We certify that the statements made In this report are correct and that this pump or valve conforms to the rules for construction of the ASME Code, Section III,DMsion 1.. N Certificate of Authorization No. N-2797. 2 Expires 20 A 2010 0r. Date 02 Jan. 2008 Name VELAN INC. Signed IN Certificate Holder) (uthorize representative) CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of QUEBEC and employed by REGIE DU BA IMENT of QUEBEC have inspected the pump, or valve, described In this Data Report on. ' ./2s'*.o , and state that to the best of my knowledge and belief, the Certificate Holder has constructed this-gump, or valve, in accordance with the ASME Code, Section III, Division 1. By signing this certificate, neither the inspector, or his employer makes anywarranty, expressed or implied, concerning the component described in this Da t. rurthermore, neither the inspector nor his employer shall be liable in any manner for any sonal injury or r e da ge or a loss of any kind arising from or connected with this inspection.

                                                                                                                 -J.-P.FACHINETf1 QC# 138 3 Date                  ,          Aigned                                              Commissions __                                   _
                                                   \(A ttorlzklnspacfor)                 (Nat'l. Bd. (Incl. enoV~f                               no.

(1) For manually operated valves

\J

15 RFO Inservice Inspection Summary Page 105 of 238 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 i. Owner FORM NIS-2/NR-1/NVR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS FirstEnergy Corp. As Required by the Provisions of the ASME Code Section X1 Data February 12, 2008 76 South Main St, Akron, OH 44308 Sheet I of 2 2, Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 Order # 200209083 septgru*elzaMon ,t. NO..Ol*

                                                                                                                                        ,tN.,JOb 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       0.7/17/10

4. Identification of Systems SG 2 Drain Line Isolation DB-MS611 (Subsys 063-01)

S (a) Applicable Construction Code ASME I CL2 1971 Edition W72 Addenda Code Case No (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N-416-3 (c) Design Responslbilities First Energy Corp, Velan Inc.

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. Butt Replaced or Code Replacement Stamped 4" Bolted Gate Valve Velan Engineering Co. s/n: 0052 N/A DB-MS6I1 1973 Replaced Yes 4" Bolted Gate Valve Velan Inc. s/n: 082001-2 N/A DB-MS611 2008 Replacement Yes

7. Description of Work Removed existing gate valve (s/n:0052) and replaced it with a new like for like replacement gate valve (s/n: 082001-2.)

A VT-2 initial inservice leakage test was performed satisfactory. i;x.'

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 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 8 YSX It in, (2) Information in items 1 through 6 on this reoort is included on each sheet. and (30 each sheet is numbered and the number of sheets is recorded at the too ol this form.

15 RFO Inservice Inspection Summary Page 106 of 238 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 AppkebWe Manul.W,, O- , be Aflehed pon W --

9. REMARKS Velan Inc.

CERTIFICATE OF COMPLIANCE I, Jeffrey M. Martin , certify that the statements made inthis 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 epires 07/17/10 Date ,Z-/2-F'

ENOC SignedqW-" QC.

CERTIFICATE OF INSERVICE INSPECTION 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 CI of Hartford. CI have inspected the work described in this report on fI-*-. V-,.. ,oBand state that to the best of my knowledge.and belief, this repair, modification or replacement has been completed-ih accordance with Section X1 of the ASME Code and the National Board Inspection Code ',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 in any manner for any personal injury, property damage or loss of any kind arsing from of connected with this inspection. Date _7_ 1 Z 8_ S ig n e d "- 4r Co m m iss io n s A E3 j. A "" LG - and ]uftnd~il aM ) CERTIFICATE OF COMPLIANCE 1, _, 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 12/13110 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, _ _holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and certificate of competency issued by the jurisdiction of OH11O and employed by HSB CI 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 ber," liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspectior. Date Signed Commissions

Page 107 of 238 15 RFO Inservice Inspection Summary FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Harbor, Ohio 43449 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Rt. 2, Oak Commercial Service Date: July 31, 1978

                                                                           # 082001-1 THRU -2 FORM NPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES As Required by the Provisions of the ASME Code, Section III, Division 1 Pg. I of 2

1. Manufactured and certified by Velan Inc.. 550 Mc Arthur Street. Montreal. Quebec, H4T IXX. Canada.

(name and address of N Certificate Holder) 2- Manufactured for First Enerqy Corp., 5501, North State Route 2. Oak Harbor, OH.. 43449, United States. (name and address of Purchaser)

3. Location of installation Davis - Besse Nuclear Power Plant I First Energy Corp., 5501, North State Route 2, Oak Harbor, OH., 43449, United States.

(name and address)

4. Model No., Series No.. or Type B12-2054B-02PS Drawing P012-641860-N.1-_ Rev. B CRN N/A

5. (X)ASME Code, Section III, Division 1: 1971 Winter 1972 2 NIA (edition) (addenda date) (class) (C ode Case no.)

6. Pump or valve 600#BOLTED BONNET GATE VALVE Nominal inlet size 4" Outlet size 4C (In) (inn.)

7, (XX) Material: Body ASME SAJ D5 Bonnet ASME SA1 05 Wedge ASME SAlt5 Bolting ASME SA 193, Gr.a7

                                             . .. . . .                                                                              . ASME SA194- Gr.ZH (aZ)                               (b)                          (c)                           (d)                             (e)

Car, NtVl Body Bonnet Wedge Holder's Board Serial Serial Serial Serial No. No. No.. No.. No., 082001-1 NIA 7443 17424 7082 082001-2 N/A 7445 17423 7081 (XM1 Blow Out Plu _ _ ASME SA105 082001-1 P708 082001-2 P707

           'Supplemental infoTmation in fornm of lists, sketches, or drawings may be used provided (i) size is 8 % x 11, (2) information In items 1 through 4 on this Data Report is included on each sheet, (3) each sheet is numbered and the number of sheets Is recorded at the top of this form, (121BS)        This form (E80037) may be obtainhd from the Order Dept., ASME, 22 Law Drive, Box 2300, Fairfiald1 l+ J      .- *,.

Page 108 of 238 15 RFO Inservice tnspection Summary 44308 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio Power Station Unit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Davis-Besse Nuclear Commercial Service Date: July 31, 1978 FORM NPV.1 (Back - Pg. 2 of. 2.) Certificate H1oderes Serial No.. # 0820DI -1 THRU -2

8. Design conditions 915 psi 536 F or valve pressure class sooLS ()

(pressure) (temperature) 9,. Cold working pressure 1440 psi at 100' F

10. Hydrostatic test -~---. psi Sfli1- -S5I - __ I*s.tis~ Uwere,La.l mt ipressure MIrcA....,

psi SACIIITh - 1500F TJ( Ii.. Remarks, AS Bull TVAI Vr DRAWING W MATERIAL CODE CONFORMS TO ASME SECTION I1,1995 EDITION.ADDENDA - 1996. CERTIFICATION OF DESIGN Design Specification certified by. PAUL N. CARR P.E. State, OH-., USA - Reg. no..-E-39003 De~sign Report certified by S. ISSITSKY P.E. State QUE., CANADA Reg. no.. 22115. CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this pump or valve conforms to the rules for construction of the ASME Code, Section III, Division 1. N Certificate of Authori.ation No. N-2797- 2 Expires 20 Apr. 2010 Date 2 Jan. 20..08. Name VELAN INC. Signed_ CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of QUEBEg and employed by REGIE D MENT of QUEBEC have inspected the pump, or valve, described in this Data Report on 61,aýý-4

                                                                                                              .and                   state that to the best of my knowledge and belief, the Certificate Holder has constructed 'tis'Oump, or valve, in accordance with the ASME Code, Section III, Division I.

By signing this certificate, neither the inspector or his employer makes any warranty, expressed or implied, concerning the component described in this Datfieort. urthermore, neither the inspector nor his employer shall be liable in any manner for any peronal injury or er daage or a loss of any kind arising from or connected with this inspection.

                                                   ,.            I                                           J-.P.FACHINETI           QCc 1381_3 Datej*,      eAL*              Signed                                           Commissions h7ori.a lnspmfor)          (Nat'l. Bd. (incl. endogumsjuIkeej,1pg1      AA eeN
                          ¢                       *.-   !

(1) For manually operated valves

                                                                                                                          ~GE ~.L.OF

15 RFO Inservice Inspection Summary Page 109 of 238 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-114VR-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 4, 2008

                        '74 FQrnth M       *tAkron-Ai      01-IA4 T      R                                         Sheet 1 of I

2. Plant Davis-Besse Nuclear- Power Station Unit #1 5501 N. SR. 2. Oak Harbor. OH 43449 Order# 200229799 Nopmr O~oaua~n00ONo.,JoO No..$1*

3 Work Performed by FirstEnergy Nuclear- Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No, 20 5501 N. M 2-Oak Harbor, OH 43449 Expiration Date 07/17110 4 identification of Systems DH Pump I Discharge Check Valve DB-D- FH43 (Subsvs 049-02) 5 (a) Applicable Construction Code ASME M CL.2 1971 Edition S71 Addenda Code Case No (b) Applicable Edition of Section XAUtilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case No (c) Design Responsibilities FirstEnergy Corp.

6. Identification of Components Repaired or Replaced and Replacement Components ManufactLrer'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 10" Check Valve Velan Inc. 0013 N/A DB-DH43 1972 Repaired Yes" Bolting Materials Unknown Unknown N/A N/A Unk. Replaced No 8 - 1 "H.v Hex Nuts Nova Machine Products HI# 716864 N/A . N/A 2003 Replacement No 8 - I" x 5 3/4" Studs Nova Machine Products HT# 731206 N/A N/A 2005 Replacement No

7. Description of Work During routine maintenance on this bolted bonnet check valve, the valve was dissasembled, refurbished and reassembled.

During reassembly, the body to bonnet bolting materials were replaced. All other pressure boundary items were reused. A VT-2 initial inservice leakage test was performed satisfactory. 18.. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure 170 osi Test Temperature NQOT °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 1/2/X 11 in. (2) Inforrnation 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.

15 RFO Inservice Inspection Summary Page 110 of 238 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/NjVR-

9. REMARKS N/A CERTIFICATE OF COMPLIANCE I, Richard R. CockrelI , 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" starnp-epires 07/17/10 Date O2-oq-09 FENOC Signed _ ki *. Q.C. 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

OH1O and employed by HSB C7 of Hartford, CT have inspected the work.described in this report on F am.4-,
and state that to the best of my knowledge and belief, this repair, modificationor 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 shall be liable in any manner for any. personal injury, property damage or loss of any kind arising om of connected with this inspection.. Date d b Signed .. Commissions .i.i,, 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 12113/10 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed ___Q.c._____- (rnameo el epa cgarualtrn) (Sutho~frd tsWO talabo) 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 OI-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 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 Od-. -d

15 RFO Inservice Inspection Summary Page 111 of 238 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 DýZ -PW 200o253 I33 FORM NR-I REPORT OF REPAIR 0 MODIFICAIION E OR REPLACEMENT m] TO NUCL EAR COM.PONENI S AND SYSTEMS IN NUCLEAR POWER PL ANTS I Work performed by AREVA NP Inc. PO#s 45231708 (name of NR certificate holder) (P Ono job no, etc) 3315 Old Forest Rd, Lynchburg Va. 24501 (address) 2 Owner FirstEnergy Company (name) 76 South Main St., Akron Ohio 44308 (address) 3 Name, address and identification of nuclear power plant Davis-Besse Nuclear Power Station 5501 N SR 9 Oak Haro, Ohio43449 4 System Stram Generator # E24-2 5.a: Items Which Required Repair. Modification, or Replacement Activities Identification Construction Code Activity No p f f ra t l urisd BNdgS Oh r Year Se ctioa/ E dition ,/ C ode. C ode Repair/ Nypeof Mfg Mig serial Nat' IName' Item Name No. No. No Other Built Division DiisonReplaceAddenda Case(s) Class Mod! I (2) (1) (2). 158 N/A N/A 1972 (3) (4) (5) A Repair 2 4 5 6 7 8 9 t0 11 12

5. h: Items Installed During Replacement Activities Identification Construction Code Type of Installed or Mfg. Mfg. Serial Nat'l Bd Jurisd Other Year Name! Edition] Code Code Item Replaced 5a Name No No No Built Section! Addenda Case(s) Class Item No Division (6) I1 (8) (7) N/A N/A N/A (10) (3) (4) None I 6 ASME Code Section XI applicable for inservice inspection : 1995 1996 None (edition) (addenda) (Code Cases(s))

7 ASME Code Section XI used for repairs, modifications,or replacements:: 1995 1996 None (edition) (addenda) (Code Cases(s)) 8 Construction Code used for repairs, modifications or replacements: 1968 Summer 68 1332-4, 1407.t (edition) (addenda) (Code Cases(s)) 9 Design responsibilities: (8) 10 Tests conducted: hydrostatic E] Pneumatic E .Design pressure (9) pressure __ psi Code Case(s) __ rhis form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Ave,, Columbus, OH 43229 NS-81 Rev 8

15 RFO Inservice Inspection Summary Page 112 of 238 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 03-1275284-013 and 11 Description of work: 03-1222961-010 (use or properly identified additional sheet(s) or sketches is acceptable) See QCIR 9070372-000 for acceptance of installed code hardware. Stabilizer/rolled plug assemblies installed in "A" inlet- 42 (Stabilizer Plug P/N 1196122-002) OTSG rolled plugs installed in "A"inlet -4 (P/N 5023545-001) Rolled Plugs installed in "A" cutlet- 46 (Threaded Rolled Plug P/N 1222118-005) Remarks: Listed below are the number codes that apply to the repair activity items shown on the front page (1) Babcock and Wilcox Company (2) Steam Generator #E24-2. SIN 620-0014-55-11 (3) ASME Section Ill, Class 1, Division I (4) Construction Code ASME 11. 1968 Edition, 1968 Summer Addenda (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 QCIR 9070372-000 (8) AREVA NP Inc. (9) By others- FirstEnergy (10) See AREVA NP QA data oackaoes 23-9064671 and 23-9070075 CERTIFICATE OF COMPLIANCE t, Nick Simite certify that to the best of my knowledge and belief the statements made in this report ar correct and the repair, modification or replacement activities described above conforms to Section XI of the ASME Code and the National board Inspection Code "NR" rudes. Naotinal Board Certificate of Authorization No NR-64 to use the NR" stamp expires May IT 2009 NR Certificate Holder AREVA NP Inc (name) Date 3/07/08 Signed ( .Maaineer, OAJC Onenations (authorized representative) (title) CERTIFICATE OF INSPECTION I 1boreas Q. 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 HSBCT of H have inspected the repair, modification or replacement described in tisis report on March 7, 200. nd state that to the best ofimy 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 loss of any kind arising from or connected with this inspection Date Match 7- 00 Signed                            i    (4ACommissions (itipotar)

__hlO( N4B9330 NI AOhio C'ommnr (National Board (incl endorsements) jurisdiction. and no )

15 RFO Inservice Inspection Summary Page 113 of 238 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;? 3,era" ':ý0-12 3 0 '4 FORM NR-I REPORT OF REPAIR (R MODIFICATION C OR REPLACEMIENT 0 1O NUCL EAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS 1 Work performed by Framatome ANP Inc. PO#s 45231708 (name of NR certificate holder) (P 0 no ,job no, etc.) 3315 Old Forest Rd, Lynchburg Va. 24501 (address) 2 Owner FirstEnergy Company (name) 76 South Main St, Akron Ohio 44308 (address) 3 Name., address and identification of nuclear power plant Davis-Besse Nuclear Power Station 5St I N -SR.2. IO'k H rbnorOhion43449 4 System Steam Generator # E24-1 5,a: Items Which Required Repair, Modification, or Replacement Activities Identification Construction Code Activity Mfg Mfg Serial Nat'l larisd Year Name Edition/ Cade Code Type of Item Name No Bd No Other .ait i o A ) Class MoS No. Division Addenda Case(s Replace 1 (2) (1) (2) 159 N/A N/A 1972 (3) (4) (5) A Repair 2 3 4 5 6 7 9 10 I1 12 ______________

5. b: Items Installed Daring Replacement Activities Identification Construction Code Type of Installed or Mfg Mfg. Serial Nat'l Bd ureisd Other Year Name/ Edition/ Code Code Item Replaced 5a Name No No No Built Section/ Addenda Case(s) Class Item No. Division (6) 1 (8) (7) N/A N/A N/A (10) (3) (4) None I 6 ASME Code Section XI applicable for inservice inspection: 1995 1996 None (edition) (addenda) (Code Cases(s))

7 ASME Code Section XI used for repairs, modificationsor replacements:: 1995 1996 None (edition) (addenda) (Code Cases(s)) 8 Construction Code used for repairs, modifications, or replacements: 1968 Summer 68 1332-4, 1407-1 (edition) (addenda) (Code Cases(s)) 9 Design responsibilities: (8)

10. tests conducted: hydrostatic [] Pneumatic El Design pressure (9) pressure _ psi Code Case(s) __

This form may be obtained from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Ave, Columbus, OH 43229 NB-B1 Rev. 8

15 RFO Inservice Inspection Summary Page 114 of 238 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 "B" Steam Generator tubes by rolled plugging with procedures 03-1275284-013 and 11 Description of work: 03-1222961-010 (use of property identified additional sheet(s) or sketches is acceptable) See QCIR 9070372-000 for acceptance of installed code hardware. Rolled Plugs installed in "B" inlet- 8 (OTSG Rolled Plug P/N 5023545-001) Stabilizer/rolled plug assemblies installed in "B inlet- 27 (Stabilizer Plug P/N 1196122-002) Rolled Plugs installed in "B" outlet- 35 (Threaded Rolled Plug PIN 1222118"005)

12. Remarks: Listed below are the number codes that apply to the repair activity items shown on the front page (1) Babcock and Wilcox Company (24 Steam Generator #E24-1, S/N 620-0014-55-12 (3) ASME Seciion III, Class I, Division I (4) Construction Code ASME Ill, 1968 Edition, 1968 Summer Addenda (5) Code Cases 1332-4 and 1407-1 (6) AREVA NP Inc P/Ns for rolled plugs- 5023545-001(OTSG rolled plug) 1196122-002 (stabilizer plug) and 1222118-005 (threaded rolled plug)

(7) Rolled plug serial numbers and tube locations installed: See QCIR 9070372-000 (8) AREVA NP Inc. (9) By others- FirstEnergy (10) See AREVA NP INC QA data packages 23-9064671 and 23-9070075 CERTIFICATE OF COMPLIANCE I, Nick Smile certify that to the best of my knowledge and belief the statements made in this report arecorrect and the repair, modification or replacement activities described above conforms to Section Xl of the ASME Code and the National board Inspection Code "NR" rules. National Board Certificate of Authorization No NR-64 to use the "NR' stamp expires May.17 2009 NR Certificate Holder AREVA NP tnc (name) Date March 7. 2008 Signed PAS -I 5ý Manager OA/QC Operations (authorized representative) (title) CERTIFICATE OF 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 thejurisdiction of Ohio and employed by HSBCT o artford CT have inspected the repair, modification or replacement described in this report on March 7- 2008 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 loss of any kind arising from or connected with this inspection Date March 7 2008 Signed                           _9&P,"*.t4:4:                    Commissions NB.9330 N IA Ohio Comm (imsltctor)            (National Board (inel endorsements) jurisdicdain and no)

15 RFO Inservice Inspection Summary Page 115 of 238 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 FivstEnergy Corp. Date January 30, 2008 7iA Rnth Mos.i Rt A I-., ("IT ddAVII Sheet 1 of 1 2 Plant Davis-Besse Nuclear Power Station Unit #1 N5k 5501 N. SR. 2, Oak Harbor-, OH 43449 Order # 200237871 FNpS oqakOr zati P.O.No. JobNo.,Pt 3 Work Performed by FirstEnesgyNuclear Operating Co Type Code Stamp N'R. 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No, 20 NoN, Expiration Date 07/17/10 4.. Identification

          .............      of
                             . Systems
                                . j ..  ..      Hanzer MI 1701H14                     DB-SNC417                    (Subsvs 062-01) 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      No (c) Design Responsibilities             First Energy Corp, Lisega Inc.                                           .

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 Snubber Lisega Inc. 61195/57 N/A DB-SNC417 Unk. Replaced No*

Snubber . Isega Inc. 30600271/099 N/A DB-SNC417 2006 Replacement No

7. Description of Work Existing Lisega snubber (serial # 61195/57) was replaced with a new like for like replacement snubber (serial # 30600271/099).

VT-3 Visual Inspection was completed satifactory.

5. (a) Cont. ANSI B31.1 & MSS-SP58 a Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A psi Test Temperature N/A oF 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 NIA (T.,~aol at N/A U.o4___W 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 reoort is included on each sheet, and 130each sheet is numbered and the nu~mher of shm*ts is ,rsderdd at the the nI this form. 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

15 RFO Inservice Inspection Summary Page 116 of 238 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.INR-1/NV-F H .

9. REMARKS N/A CERTIFICATE OF COMPLIANCE Richaid R. Cockrel] , certify that the statementsmade 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" sta p e ires 07/17/10 Date D1 of? FENOC Signed . Q.C. {r0t0eo P0 00ai

                                                              *g0000*tn)                          (m.hoo,.Z edr  ta 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                OHTO         and employed by HSB CT         of Hanfford, C1        have inspected the work described in this report on 3                  .vkQoro 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 t-h.e work described in this report.. Furthermore, neither the undersigned toir 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 \ jO n Signed "lrn'k ý e Commissions r*l3'1O '4 :- 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 12J13/10 National Board Certificate of Authorization No 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.C. -r> 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 C1 of Hartford, C1 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

                                                                                                                       -*rj.Wi~di-n ard -))

15 RFO Inservice Inspection Summary Page 117 of 238 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-1N-VR-- OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS ... As-Required by the Provisions of the ASME Code Section XI

1. Owner FirstEnergy Corp. Date Januaiy 28, 2008 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, OH 43449 Order# 200237898 Mdre*s RAep,.rgwnzma,P. Jo. No.,.1

3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng 5501 N. SR. 2. Oak Add Harbor. OH 43449 Authorization No 20 rca, Expiration Date 07/17/10 4 Identification of Systems Hanget CCA-18-1-H2, DB-SNC419 (Subsys 065-01 5 (a) Applicable Construction Code ANSt B31.1 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Section XAUtilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case No (c) Design Responsibilities FiistEnergy Corp., Lisega Inc

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 Snubber Lisega Inc. 61195/88 N/A DB-SNC419 Unk. Replaced No Snubber Lisega Inc. 30600271/050 N/A DB-SNC419 2006 Replacement No

7. Description of Work Existing Lisega snubber (serial # 61195/88) was replaced with a new like foi like replacement snubber (serial# 30600271/050). "

5.(a) cont. ANSI B3 1.1 & 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 N/A Blowdown (if applicable) N/A Set Pressure and Slowdown Adjustments Made Using N/A at N/A [L~aleoa) NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size Is 8 1/ 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. -

15 RFO Inservice Inspection Summary Page 118 of 238 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 3 1, 1978 DB-0070-5 FORM NIS-2/NR-IM(R4 ApolCtWMaa4drd- 0ataRFru baAItrC2.,4 S. 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" starr arpires 07/17/10 Date 01-2-09g FENOC Signed W 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 ýAtj.. 7e 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 "NA" rules By signing this certificate, neither the undersigned nor my employer makes any warranty, expressed or implied, concerning .he 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 01-be Signed

N - Commissions k' 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 "yR" 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, CI 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 i-adxtb- .. d

15 RFO Inservice Inspection Summary Page 119 of 238 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-R-t OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI . . 1 Owner FirstEnergy Coip. Date January 28, 2008

                      '7rt Qrf thm-n., it      A I--r. AsT 44trtAR                                        Sheet I of I

2. Plant Davis-Besse Nuclear Power Station Unit #1 N0 5501 N. SR. 2. Oak Harbor, OH 43449 Ordei# 200237899

3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No. 20 Exs*ration Date 07/17/10 4, Identification of Systems , Hanger M1 142I*.2, DB-S& (Subsvs 064-04" 5 (a). Applicable Construction Code ANSI B31.1 196 7 Edition Later Addenda Code Case No (b) Applicable Edition of Section XIUtilized for Repairs or Replac ements 19 95 Edition 9 Addenda Code Case No (c) Design Responsibilities FirstEnergy Corp., Lisega Inc.

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 Snubber Lisega Inc. 61195/70 N/A DB-SNC420 Unk. Replaced No Snubber Lisega Inc. 30600271/084 N/A DB-SNC420 2006 Replacemnt No

7. Description of Work Existing Lisega snubber (seriaI# 61195/70) was replaced with a new like fos like replacement snubber (serial# 30600271/084).

5.(a) cont. ANSI B31.1 & MSS-SP58 L-

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 (ifapplicable) 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 1 X 11 in. (2) Information in items 1 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 top of this form,

15 RFO Inservice Inspection Summary Page 120 of 238 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*dR--1 A~pP-cI Me-1-cI,. 5.1 R18p W. beAfl.,,1d

9. REMARKS N/A CERTIFICATE OF COMPLIANCE Richard R. CockrelI , 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" sta~q5rqxpires 07/17/10 Date o I-29-0G. FENOC (* oflee org.-7bo) Signed I ' qjs,,* (8uS ,rtz n~O,,,O l.O) 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 CI of Hartford, CI have inspected the work described in this report on ."AS t 0 6 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, conceming 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 1t~Iiey toq Commissions

                                                                                                                            .lW f  dl8 ýfO.

and. m)) 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 mprosonal5.=)"' (authorited 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, CI 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. uale S~iyIIu Commissions (1_.,r) IN-behdS.Oo,(fl61o

15 RFO Inservice Inspection Summary Page 121 of 238 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-1IN-VR- OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner FirstEnergy Corp. Date Januaty 28, 2008 76 South Main St.. Akron. OH 44308 Sheet 1 of 1 Station #1 2 Plant Davis-Besse Nuclear Power- N'-* Unit 5501 N. SR. 2, Oak Harbor, OH 43449 Order # 200237901 2da= SAV- OrgwizaM P.O.N, No No.,NW.. 3 Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp N'R 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No. 20 Expiration Date 07117/10 4 Identification of Systems Hanger CCB-8-15-HI, DB-SNC425 (Subsvs 064-03"

5. (a) Applicable Construction Code ANSIB 31.1 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Section X1Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case No (c). Design Responsibilities First Energy Corp, Lisega Inc. .

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 JurisIdictional No.. Built Replaced or . Code Replacement Stamped Snubber Lisega Inc. 61195/29 N/A DB-SNC425 Unk. Replaced No Snubber Lisega Inc. 30600271/085 N/A DB-SNC425 2006 Replacement No

7. Description of Work Existing Lisega snubber (serial # 61195/29) was replaced with a new like for like replacement snubber (serial# 30600271/085) 5 (a) Cont. ANSI B31.1 & MSS-SP58 8 Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A pel Test Temperature N/A -F Pressure Relief Valves:

Service N/A Size N/A Opening Pressure N/A Slowdown (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 is 8 V.X 11 in. (2) Information In items i through6 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.

15 RFO Inservice Inspection Summary Page 122 of 238 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.NW ... AppkflP. kte a df .~f*J Dat.Repotl=k bD Mtac&Od

9. 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" staCl, &res 07/17/10 Date DO-2_8-OS FENOC (hna,. cimpal,,,*nrn~ahc) Signed I .,tza~riZ*d

                                                                                                                ,.*nbe.rta*,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 C1 of H--tford, CT have inspected the work described in this report on J". Zq. 2 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 h.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 1In, Signed I 1rnumw O4 Commissions ~'~ mc*jui~e

rd))

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 0VR" stamp expires 12/13/10 National Board Certificate of Authorization No., 20 to use th- "NR" stamp expires 07/17/10 Date FF-.NOC 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 O-HO and employed by HSB CT of H4antfoid, 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 v Commissions

                                                                                                                                              'ciefldw.m.,,D.
                                                                                                                                .,ci  aciD1or~

arci005

15 RFO Inservice Inspection Summary Page 123 of 238 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-1INAPV- OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI I Owner FirstEnergy Corp. Date January 28, 2008 76 South Main St.. Akron, OH 44308 Shreet 1 of I 2 Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, 0H 43449 Order# 200237904 R O,Fmepaw, P.O.No..JobNo.,e. 3 Work Performed by FirstEnerxgNuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oak Mdd,oa Harbor, OH 43449 Authorization No. 20 Expiration Date 07/17/10 4 Identification of Systems Hanger CCB-8-15-H2, DB-SNC426 (Subsys 064-03) 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 No (c) Design Responsibilities fiistEnergy Corp., Lisega Inc . R lrlenrifinseinn of ('.nmnnnnnts Renairarl or Pnntsrnd anti Rcnltaromont flnmnnnanta 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 Snubber Lisega Inc. 61195/45 N/A DB-SNC426 Ulnk. Replaced No Snubber Lisega Inc. 30600271/098 N/A DB-SNC426 2006 Replacement No

7. Description of Work Existing Lisega snubber (serial # 61195/45) was replaced with a new like for like replacement snubber (serial# 30600271/098).

15(a) cnt & 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 N/A Blowdown (if applicable) N/A Set Pressure and Slowdown Adjustments Made Uaing N/A at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8a X 11 In..(2) Information in items I through &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.

15 RFO Inservice Inspection Summary Page 124 of 238 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 N1S-2IN1R-VIW/Y-Mee APPý1W-ee D RepotWWob

                                                                                                                               -eeOi       ANlrau

9. REMARKS N/A CERTIFICATE OF COMPLIANCE I, Richaid R..Cockeloc 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 "NA" rules, National Board Certificate of Authorization No.. 20 to use the "NR" star yires 07/17110 Date Ol-28..og 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 Haitford, CI have inspected the work described in thisreport on J/,, a%, E* 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 \t* yS Signed - .. t , Commissions tVR " IfA CO eM1 ýJe ad 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 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 'yR' 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. >ff' (au*o*ed rn - 907mtnde) ;- - 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 Hartfotd, 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 beirc 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 Neme~al Boend(PCIeneenenen,). eedp.madt.Rena. aMne))

15 RFO Inservice Inspection Summary Page 125 of 238 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-WtLR4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

                                      ...             As Required by the Provisions of the ASME Code Section X1 I Owner          FirstEnergy Corp.                                                          Date      January 28, 2008 N_       H4 76 South Main St., Akron. OH 44308 Sheet I of 1

2. Plant Davis-Besse Nuclear Power Station Unit #1 N5R k O 5501 N. SR. 2, Oak Harbor-, OH 43449 Order# 200237906 R

F.pirOrgant.P.O No.J,b*NO.et. 3 Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No 20 Expiration Date - 07/17/10 4 Identification of Systems Hanger CCB-8-22-H3, DB-SNC427 (Subsys 064-03)

5. (a) Applicable Construction Code ANSI B3 1.1 1967 Ediftion Later Addenda Code Case No (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95._.5 Edition 96 Addenda Code Case No (c) Design Responsibilities FirstEnergy Corp., LisRega Inc

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 Snubber Lisega Inc. 61195/40 N/A DB-SNC427 Unk. Replaced No Snubber Lisega Inc. 30600271/046 NIA DB-SNC427 2006 Replacement No

7. Description of Work Existing Lisega snubber (serial # 61195/40) was replaced with a new like for like replacement snubber (serial# 306002711046).

5.(a) cont. ANSI B31.1 & MSS-SPS8 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 (T*I MWium :W 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-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.

15 RFO Inservice Inspection Summary Page 126 of 238 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 4p-tct IMN-W or. pw..p,.GE. W.ý

9. 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 XAof the ASME Code and to the National Board Inspection Code "NR" rules.

National Board Certificate of Authorization No. 20 to use the "NR" starpp-eypires 07/17/10 Date I FENOC fJ-2Eg.r6 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 A.h1,.- 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, concerningth 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 117-ero0 Signed 1`lrtW , Commissions "CI-339 (N 1', I A (. 9-,d 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 07117110 Date ______________FENOC Signed _ _.C._-_v CERTIFICATE OF INSERVICE INSPECTION f, 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 (Nýoa Bocof0ý',4f.,~)

15 RFO Inservice Inspection Summary Page 127 of 238 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #l, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-1/NV-.4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section X. 1 Owner FirstEnergy Corp. Date Januaxy 30, 2008 76 South M4.ain St., Akron,. OH 44308 Sheet 1 of I 2 Plant Davis-Besse Nuclear Power Station Unit 41 5501 N. SR. 2. Oak Harbor-, OH 43449 Order #200237913 3 Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng. _ _ N5arb 55,01 N. SR.ý 2- Oak 1Harbor. OH 41449 Authorization No, 20 Addtlil Expiration Date 07/17/10 4 Identification of Systems Hanger M 1170 / H1 I DB-SNC414 (Subsys 062-01).

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 No (o) Design Responsibilities First Eneray Corp., Lisega Inc.

6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer SerialNo. Board No Jurisdictional No. Built Replaced or Code Replacement Stamped Snubber .Lisega Inc. 30500235/015 N/A . DB-SNC414 Unk. Replaced No Snubber Lisega Inc. 30600271/097 N/A DB-SNC414 2006 Replacement Noo

7. Description of Work Existing Lisega snubber (serial # 30500235/015) was replaced with a new like for like replacement snubber serial # 30600271/097).

5. (a) cont. ANSI B31.1 & MSS-SP58 A VT-3 inspection was performed satisfactory.

NIL-

8. Tests Conducted: 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 (ifapplicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A f1WMdt-um 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 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.

15 RFO Inservice Inspection Summary Page 128 of 238 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,N44R . Appk-*tr , r~fl -a,, Omw p0- to-f W Attahed

9. REMARKS N/A CERTIFICATE OF COMPLIANCE I, Kevin J.Kress , certify that the statements made inthis 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 exps_. 077/170 Date 1-;O 08 FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, 1homas 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 C1 of Hartford, CT have inspected the work described in this report on , RS .l,oc, and state that to. the best ofmy 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 inthis 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 -'* q1.'I. G,1 ,Commissions 3A&. A 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 12113/07 National Board Certificate of Authorization No. 20 to use the "NR' stamp expires 0711 7/10 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, C7 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 inthis 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 ate .... Signed Commissions (~~dapaotc,) ~~~~(N.Itata addiadd, od 10 toaoea. d

15 RFO Inservice Inspection Summary Page 129 of 238 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-1ANWR--t OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section X? 1 Owner FitstEnergy Corp. N~m.... . Date January 29, 2008 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, OH 43449 Order# 200237914, A~M~,. ~,gnMiA n P.O-No.,JobNo.,etc.

RepAir 3 Work Performed by _FirstEnemcy 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 MI170/H2 DB-SNC412 (Subsys 062-01) 5 (a) Applicable Constructon Code ANSI B31.1 1967 Edition Later Addenda C ode Case No (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case No (c) . Design Responsibilities- First Energy Corp, Lisega Inc.

6. Identification of Components Repairedor 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 Snubber Lisega Inc. 61200/17 N/A DB-SNC412 Unk Replaced No Snubber Lisega Inc. 30700256/008 N/A DB-SNC412 2007 Replacement No

7. Description of Work Existing Lisega snubber (serial # 61200/17) was replaced with a new like for like replacement snubber ( serial # 30700256/008).

VT-3 Visual Inspection was completed satisfactory.

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 N/A Blowdown (if applicable) N/A Set Pressure and Slowdown Adjustments Made Using N/A (ut. Medim . .. at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size Is V/2X 11 in (2) Information in items 1 through 6 on this report is included on each sheet, and (30 each sheet isnumbered and the number of sheets is recorded at the top of this form. _

15 RFO Inservice Inspection Summary Page 130 of 238 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-14VR-.4

9. 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" sta, p i res 07/17/10 Date O1 -2q-Oe FENOC Signed -- -- ! UQ, 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, CI have inspected the work described in this report on Mk-& WDqand state thatto" M the-best of y 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 Jdu sitz!L commissions ~ - - AI ~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 (nata.ci wnr,wcmor*rrt,: Signed (,abheized,,sab~e) 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

15 RFO Inservice Inspection Summary Page 131 of 238 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 08-0570-5 FORM NIS-2/NR-1/NV-R-- OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section X1 1 Owner FirstEnergy Corp. Date January 28. 2008 76 South Main St.. Akron, OH 44308 Sheet I ot 1

                                                                                                                             ... . . ..   #1 2   Plant        Davis-Besse Nuclear Power Station                                          Unit N02, 5501   N. SR. 2, Oak Ha rbor- OH 43449                                              Order# 200237916 3   Work Performed by       FirstEnerg Q Nuclear Operating Co.                              Type Code Stamp           NR 5501 N. SR. 2, Oak Addrn.Harbor, OH 43449                                     Authorization No.        20 Expiration Date       07/17/10

4. Identification of Systems Hanger CCA-20-2-H4, DB-SNC429 (Subsvs 064-02 5 (a) Applicable Construction Code ANSI B31.1 11967 Edition Later Addenda Code Case No (b) Applicable Edition of Secton XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case No (c) Design Responsibilities FirstEnergy Corp., Lisega Inc 6, Identification of Comoonents Repaired or Reotaced and Replacement Comoonents 6.idniicto of Comonnt Reaie Relae ....... Relcmn........ Component 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 Snubber Lisega Inc. 61200/18 N/A DB-SNC429 Unk. Replaced No Snubber Lisega Inc. 30700256/010 N/A DB-SNC429 2006 Replacement No

7. Description of Work Existing Lisega snubber (serial # 61200/18) was replaced with a new like for like replacement snubber (serial# 30700256/010).

5.(a) cont. ANSI B331.1 & MSS-SP58 a Tests Conducted: Hydrostatic No. Pneumatic No Nominal Operating Pressure No Other No Pressure N/A ppsi 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 (rT.,Mýd.,) at N/A tLooa Ic NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 Y2 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 top of this form.

15 RFO Inservice Inspection Summary Page 132 of 238 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-4 AppIIsN Ma.n D.. Repomt bebooth,,

                                                                                                                                -ac.rs

9. 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" st*" ýpxpires 07117/10 Date OJ-I9-.Dg FENOC . (nnm= 'ootrep~r¢jrJonot) Signed *J (autbooi~*prooolo) . 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, C1 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 inaccordancewith 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 th.e work described in this report. Furthermore, neither the undersigned nor my employer shall be liable inany manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection..

Date T O Signed "t-,4.A Commissions (13 q-33 t. A" and bo snrdno5*

*)

CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statements made inthis 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 tFENOC ihm, 01reio~amer O~ Signed ({aohnzd rep,. , e} 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 (1-.) (NhIenM Boad(1*01

                                                                                                                                          .obonabr.e4nh).

hodjob01ohOth. hod

15 RFO Inservice Inspection Summary Page 133 of 238 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-1INVR---OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Cod6e Secton XI 1 Owner FirstEnei gy Coip. Date January 28, 2008 Cam. 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, OH 43449 Ordet# 200237917

3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR rfl1 V _ I _ak arbhor OH 43449 Authorization No. 20 Md-,

Exoiration Date 07/17/10 4, Identification of Systems Hangei CCA-20-1-H3, DB-SNC428 (Subsvs 064-02)

    .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     No (c) Design Responsibillties . FirstEnergy Corp., Lisega Inc

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 Snubber Lisega Inc. 61200131 N/A DB-SNC428 Unk. Replaced No Snubber Lisega Inc. 30700256/080 N/A DB-SNC428 2007 Replacement No

7. Description of Work Existing Lisega snubbet (serial # 61200/31) was replaced with a new like for like replacement snubber (serial# 30700256/080).

5(.a) cont. ANSI 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 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 Tet Medium) 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 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 lop of this form.

15 RFO Inservice Inspection Summary Page 134 of 238 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/N-VR-..

                                                                                                  .         Mar.flu~a
                                                                                                    .Ap4tcaMS       n Dlat,He~pcn b. Albt~l.d

9. REMARKS N/A CERTIFICATE OF COMPLIANCE I, lZichard 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" staiepres 07/17/10 . Date 01 -2ff-D8 FENOC Signed - Q.C. 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 C- of Hartford, CT have inspected the work described in this report on aop, and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Sectionr 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 7 nmaP Commissions 95'R ,, ,L& 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 X] 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 .t* 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, CI 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 (Ne*iaI Bourn@rnI

                                                                                                                              .r4os.mrnos~.
                                                                                                              ~M~6OBorn .ndtto})

15 RFO Inservice Inspection Summary Page 135 of 238 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 3 1, 1978 DB-0070-5 FORM NIS-2/NR-1IN-uýR4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner FirstEner'gy Corp. Date January 29,2008 76 South Main St., Akron, -. 1.esOH 44308 Sheet 1 of I 2 Plant Davis-Besse Nuclear Power Station Unit 5501 N. SR. 2, Oak Harbor-, OH 43449 Order# 200237918 ' HepwrLrg -,-on P.O.NO.. raN..010

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 MI 170/H4 DB-SNC493 (Subsys 062-01) 5, (a) Applicable Construction Cede ANSI B3 1.1 1967 Edition . Later Addenda Code Case No (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 16 95 Edition 26 Addenda Code Case No (c) Design Responsibilities First Energy Corp. Lisega n.c . . . --

6. Identification of Components Repaired or Replaced and Replacement Components M Manufacturer's National Other IdentificatiorV Year Repaired ASME Name of Component Name of Manufacturer Serial No Board No. Jurisdictional No Built Replaced or Code Replacement Stamped Snubber Lisega Inc. 61195/111 N/A DB-SNC493 Unk. Replaced No Snubber . Lisega Inc. 30600271/088 N/A DB-SNC493 2006 Replacement No

7. Description of Work.

Existing Lisega snubber (setial# 61195/111) was replaced with a new like for like replacement snubber (serial #30600271/088) VT-3 Visual inspection was completed satisfactory.

5. (a) Cont. ANSI B33Ll & MSS-SP58 s . . . .. .. ... :=. ....

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 Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Blowdown Adjustmnents Made Using N/A at N/A NOTE: Supplemental sheets in the form of ists, sketches, or drawings may be used, provided (1) size is 8 /z X 11 in..l2) 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.

15 RFO Inservice Inspection Summary Page 136 of 238 FirstEnergy Nuclear Operating Company, 76 South Main Stk, 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-2INR-1JNMRY4 App]lAbl,W-nt-,a

9. REMARKS 0-mOaRepors b. AU=hW 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" stap'Mires 07/1'7/10 Date 01 -2.c9- 00 FENOC (nail. of tapadr orgartZallo.,( Signed .

                                                                                                   "7  (au~ hoiz~d toanm 1ra 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 inthis report on .A aeXe, 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.. 1 1 Signed T "* el, Commissions 41B ,1," (N.-a~o~( and Iinns il-lma afH no))mn- n( 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 07117/10 Date _FENOC Signed Q.C. A 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 OIO and employed by HSB C1 of Hartford, CI 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 __ (l..a~t) (Nabnai* msc=oa findaitfl)n) s

15 RFO Inservice Inspection Summary Page 137 of 238 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/WN-R4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner FirstEnergy Corp. Date January 29, 2008 76 South Main St.. Akron, OH 44308 Sheet I of I 2 Plant Davis-Besse Nuclear Power Station Unit #1 Na-e 5501 N. SR. 2, Oak Harbor, OH 43449 Order# 200237919 Oýa-z.EttnP.O No.,JobNo..ý.t 0aep

3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR Harbor. OH 43449 5501 N. SR. 2. Oak Aod*me Authorization No. 20 Expiration Date 07/1'7/10 Hanger M1345IH2 DB-SNC492 S (Subsys 065-01)

4. Identification of Systems

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 No (c) Design Responsibilities First Energy Corp, Lisega Inc.

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 Snubber Lisega Inc. 61195/100 N/A DB-SNC492 Unk. Replaced No Snubber Lisegalric. 30600271/052 N/A DB-SNC492 2006 Replacement No

(

7. Description of Work Existing Lisega snubber (serial # 61195/100) was replaced with a new like for like replacement snubber (serial # 30600271/052).

VT-3 Visual Inspection was completed satifactory.

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 N/A Slowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A

                                                                        .    ..   .. . .......                                 (Ites!Mtaium) at   N/A NOTE: Supplemental sheets In the form of lists, sketches, or drawings may be used, provided (1) size Is 8 1/2X 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 recorded at the too of this form.

15 RFO Inservice Inspection Summary Page 138 o f 238 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-1INVR .. Apphim.. M Aaeat DreM

                                                                                                                                   ,aRlpera0 be A-aChed

9. 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 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" sta~t7xpires              07/17/10 Date      01-2_91-06r                              FENOC                        Signed            .         .c CERTIFICATE OF INSERVICE INSPECTION
       , rhomas 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 C1         of Hartford, C-1       have inspected the work described in this report on                  ,MI,,        3,8 UO5and state that to thebest of my knowledge and belief, this repair, modification or replacementhas 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 Dae IjjýD0 ige- mCommissions ~~ m 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 07/17110 Date (nme.otteplr*Abart.opb

signed SFENOC -- ar,orad ,apmmatat,*) 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, CI 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 AbA andWdadadlon. raIl

15 RFO Inservice Inspection Summary Page 139 of 238 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/\N-1-4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

                                                  .... As Required by the Provisions of the ASME Code Section XI 1 Owner          FistEnergy Corp.                                                         Date      January 29, 2008 76 South Main St., Akron. OH 44308                                                 Sheet I of 1 2    Plant       Davis-Besse Nuclear Power Station Unit                                     #,

5501 N. SR. 2, Oak Harbor, OH 43449 Order# 200237920 Rp O'g "feimn P.O.fý, Jo No., 0. 3 Work Performed by FirstEnery Nuclear Operating Co. Type Code Stamp Ng 5501 N. SR. 2. Oak Harbor, OH 43449 .Authorization No 20 Exmiration Date 07/17/10 4 Identification of Systems Hanger M1 155/H3,. DBzSNC486 (Subsys 050-03) 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 No

         .(C). Design.Fesponsibilities     1irstEnerpy Corp., Lisega Inc                 .

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 Snubber Lisega Inc. 61200/12 N/A DB-SNC486 Unk. Replaced No Snubber Lisega Inc. 30700256/009 N/A DB-SNC486 2007 Replacement No

7. Description of Work E ti Lisega snubber (serial #61200/12) was replaced with a new like for like replacement snubber (serial# 30700256/009).

A VT-3 visual inspection was completed satisfactory. 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 N/A Blowdown (if applicable) N/A Set Pressure and Slowdown Adjustments Made Using N/A

                                                                                                                       ... u
                                                                                                                              ... d~..,*.)                            - "

at NIA NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 Y2X 1 in (2) Information in items I through 8 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.

15 RFO Inservice Inspection Summary Page 140 of 238 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/NR-1-..

                                                                                                      ,ptaI   Marlaclr
                                                                                                                     ,we,DM. R~pn.ioh tactec

9. REMARKS N/A CERTIFICATE OF COMPLIANCE I, Richard R. Cockrell _ certify that the statements made inthis 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' st expires 07/17/10 Date 01 0.0 FENOC Signed Q.

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, CI have inspected the work described in this report on ýA. 3,t and state that to the best of my knowledgeand 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 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 12/13110 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 Hartford, CI 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.4 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

                                                                                                                 ~C~iona~

8aad ~

15 RFO Inservice Inspection Summary Page 141 of 238 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-4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner FitstEnergy Corp. Date Januaýy 28, 2008

                      '76 'Q..,th V1.1. qt - Alr-n OTT ddIAR                                             Sheet 1 of I 2 Plant          Dayis-Besse Nuclear Power Station                                         Unit                              #1 5501 N. SR. 2. Oak Harbor. OH 43449                                              Order# 200237921 3, Work Performed by         FirstEnergv Nuclear Operating Co.                             Type Code Stamp        NR 5501 N. SR. 21Oak Harbor. OH 43449                                         Authorization No       20 Expiration Date     07/17/10

4. Identification of Systems Hanger HCB-38-4-H4 , DB-SNC481 (Subsys 062-02)

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 No (c) Design Responsibilities FirstEnergy Corp., Lisega Inc

6. Identification of Components Repaired or Replaced and Replacement Components Manufacturers National Other identification/ Year Repaired ASME Name ofComponent Name of Manufacturer Serial No Board No Jurisdictional No Built

Replaced or Code Replacement Stamped Snubber Lisega Inc. 61195/77 N/A DB-SNC481 Unk. Replaced No Snubber 1.sega Inc. 306002711091 NlA DB-SNC491 2006 Replacement No

7. Description of Work /

Existing Lisega snubber (serial # 6195/77) was replaced with a new like for like replacement snubber (serial# 30600271/091). 5.(a) conL 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 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 Is8 'KX 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 atthe top of this form.

15 RFO Inservice Inspection Summary Page 142 of 238 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 INIS-21NR-1IVR . Apý)..ý M d- Cknmzme P ftato-rt 0e*Apc

9. REMARKS N/A CERTIFICATE OF COMPLIANCE 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" star ires 07/17/10 Date ()j 0-V FENOC Signed J.2, , 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 Haitford, C1 have inspected the work described in this report on 3O1,00BI, ae-- and state that to the best of my knowledge and belief, this repair, modification or replacement has been completedin 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 t-h 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 bSl Signed -" Commissions (NAt bord (ind CERTIFICATE OF COMPLIANCE I, N/AA, 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.__ 04(

                                                         ,.rlpmr of,g O il)~                           I~zhde ,tno,,nonno*,)

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, CI 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 Codeand 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 mfanner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions Ilntpnotn) (NabnotRn, o iC In 6mren,fl)r~~,*

Page 143 of 238 15 RFO Inservice Inspection Summary 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-2JNR-11NVR4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner FirstEnergy Corp. Date January 29, 2008 76 South Main St.. Akron. OH 44308 Sheet I of I

2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. S1L 2, Oak Harbor, OH 43449 Order# 200237922

3. Work Performed by FirstEnerxy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oak Harbor, OH 43449 Authorization No, 2__

Expiration Data 07/17/10 4 Identification of Systems Hanger M1 147/H9, DB-SNC473 (Subsys 063-01 5 (a) Applicable Construction Code ANSI B31.1 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Section X Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case No (c) Design Responsibilities FirstEnergy Corp., Lisega Inc

6. Identification of Comnonents Renaired or Reolaced and Reolacemant Comnonents Manufacturer's National Other ldentification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No Board No.. Jurisdictional No. Built Replaced or Code Replacement Stamped Snubber Lisega Inc. 61200/25 N/A DB-SNC473 Unk. Replaced No Snubber Lisega Inc. 30700256/079 N/A DB-SNC473 2007 Replacement No

7. Description of Work Existing Lisega snubber (serial # 61200/25) was replaced with a new like for like replacement snubber (serial# 30700256/079).

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 N/A Blowdown (if applicable) NIA 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 Y. X11 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.

15 RFO Inservice Inspection Summary Page 144 of 238 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/NYR 1 APOJcaleManWlcu*l, Damla wq~n w Ae

                                                                                                                                  ,ta,ch

9. REMARKS N/A CERTIFICATE OF COMPLIANCE 1, 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 "NFI" stap e ores; 07/17110 Date 03-29-0,Y 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 Haitford, CT have inspected the work described in this report on JAI. .", E,.*,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 andthe National Board Inspection Code "NR" rules..*............ By signing this certificate, neither the undersigned nor myemployer makes any warranty, expressed or implied, concerning th-e work described inthis 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 DI& Signed Commissions tAfZ3 VAI PS M 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 _YENOC 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 OH3O 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 inthis 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

15 RFO Inservice Inspection Summary Page 145 of 238 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-2JNR-1/NkR4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl . . 1, Owner FiistEner-gy Corp. Date January 28, 2008 76 South Main St, Akron, OH 44308 Sheet 1 of I 2, Plant Davis-Besse Nuclear- Power Station Unit 5501 N. SR. 2, Oak Har bor, OH 43449 Order# 200237923 R.0r O-n n P.O. o.,Jb W.,

3. Work Performed by FirstEnergy Nuclear- Operating Co. Type Code Stamp Ng

                         -;01 N._R. 2. Oak Harbor. OH 43449                                        Authorization Noý      20 M&_r Expiration Data     07117110

4. Identification of Systems Hanger Ml147/H4 DB-SNC472 (Subsys 063-01)

5. (a) Applicable Construction Code ANSI B31ll 1967 Edition Later Addenda Code Case No (b) Applicable Edition of Section XlUtilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case No (c) Design Responsibilities FirstEnergy Corp., Lisega Inc

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. Buit Replaced or Code Replacement Stamped Snubber Lisega Inc. .,61200/10 N/A DB-SNC472 Unk. Replaced No Snubber Lisega Inc. 30700256/078 N/A DB-SNC472 2007 Replacement No

7. Description of Work Existing Lisega snubber (serial # 61200/10) was replaced with a new like for like replacement snubber (serial# 30700256/078).

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 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 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.

15 RFO Inservice Inspection Summary Page 146 of 238 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-0075-5 FORM NIS-2/NR-1/NW4R-4 App~clb aMratadvmemDataR*p~i to-e AtItached

9. REMARKS N/A CERTIFICATE OF COMPLIANCE I, Richard R.Cocklr- , 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" stan-i cpires 07/17110 Date 61, 49i FENOC (fltafle of repirorganizationl Signed ' (aui rcf2 d mprosO tafa CERTIFICATE OF INSERVICE INSPECTION I, Ihomas 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 3w:2q9 uee 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 _ __Signed ajwz~ma Commissions 1A 30 A-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. (can ofl npaeaainaabo(rz* (aalafd refaoOnlaI,'*( 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, CI 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 "NA" 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 (Inspeefa') (Nailohan lind . Bt~,id e rff

15 RFO Inservice Inspection Summary Page 147 of 238 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 5501 N. St. Ri. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2INR-1IMV44 OWNER'S REPORT FOR REPAIRS OR. REPLACEMENTS As Required by the Provisions of the ASME Code Section XI I Owner FirstEnergy Corp. " Date Januai y 28, 2008 76 Soutih Main St., Akron, OH 44308 Sheet 1 of 1 2 Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor- OH 43449 Order # 200237924 3 Work Performed by FirstEnergy Nuelear Opel ating 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 EBB-5-19-H1O DB-SNC4'71. (Subsys 063-01) 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 No

        ..c) Design Responsibilities       First Energy Corp,i:.isega Inc.                                                              .

6. Identification of Components Repaired or Replaced and Reolacement Componnents 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 Snubber Lisega Inc. 61195/96 N/A DB-SNC471 Unki Replaced No Snubber

Lisega Inc. 30600271/044 NIA DB-SNC471 2006 Replacement No

7. Description of Work Existing Lisega snubber (serial # 61195/96) was replaced with a new like for like replacement snubber (serial #30600271/044).

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 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 'i X 11 in, (2) Information in items 1 through 6on 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. -

15 RFO Inservice Inspection Summary Page 148 of 238 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-1/N4VR4.......

9. REMARKS N/A CERTIFICATE OF COMPLIANCE I, Richard R. CockreU ,.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 NationalBoard Inspection Code "NR"rules.

National Board Certificate of Authorization No. 20 to use the "NR" stanrnxpires 07/17/10 Date 01 -2 -0 FENOC (nartnnol nagar,aj) repaWn, Signed (01thorZe

                                                                                                               ,.enrentIal*

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 CJ of Hartford,CI have inspected the work described in this report on , and state that to the best of my knowledge and belief, this repair, modification or replacerrent 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 - " t* 6Me& CERTIFICATE OF COMPUANCE N/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 X1 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 12/13/10 National Board Certificate of Authorization No, 20 to use the "NR" stamp expires 07/17/10 Date _ __FENOC name 01wpaao~gatznaJc Signed _._.___,- (ad~morzorhn~menahtiav) 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 CI 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 (Nadml'oard (-1 rn*dj~Idwmion

                                                                                                                                              ~o,.n.)

A n))

15 RFO Inservice Inspection Summary Page 149 of 238 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-VR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI ------------

1. Owner FirstEne.gy Corp. Date January 28, 2008 76 South Main St.. Akron, OH 44308 Sheet 1 of 1

2. Plant Davis-Besse Nuclear Power Station N-! Unit #1 5501 N. SR.O2HOak Aarbor- OH 43449 * *dte*

Order# 200237925 RFV. Orgnrýý~o P.0- tN,.dJbN.,,e¢ 3 Work Performed by FirstEnergy Nuclear Ope. ating Co. Type Code Stamp NR 5501 N. SR. 2.-Oak Harbor, OH 43449 Authorization No, 20 Explration Date 07/17/10 4 Identification of Systems Hanger EBB-5-19-H5, DB-SNC470 (Subsys 063-01)

5. (a) Applicable Construction Code ANSI B31.1 1967 Edition Later Addenda Code Case No 4-(b) Applicable Edition of Section XI Utiized for Repairs or Replacements 19 .95 Edition 96 Addenda Code Case No

        . (c) Design Responsibilities     Fi~stEnergy Corp., Lisega Inc

6. Identification of Components Repaired or Replaced and Replacement Components -

Manufacturer's National Other Idantifiation/ Year Repaired ASME' Name of Component Name of Manufacturer Serial No. Board No Jurisdictional No Built Replaced or Co.'6, Replacement Starmnpd Snubber Lisega Incý 61195/112 N/A DB-SNC470 Utnk. Replaced NO Snubber Lisega Inc. 30600271/081 N/A DB-SNC470 2006 Replacement No

7. Description of Work Existing Lisega snubbei (serial # 61195/112) was replaced with a new like for like replacemnent snubber (seriat# 30600271/081).

5.(a) cont. ANSI B31.1 & MSS-SP58

8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A esl Test Temperature N/A F Pressure Relief Valves:

Ser'ice 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 rists, sketches, or drawings may be used, provided (1) size Is 8 Y2X 11 in (2) Information In items I through 60on 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.

15 RFO Inservice Inspection Summary Page 150 of 238 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-1INR-1 AppicolýM-On -~trVWaRý Wpl' WoMdot d

9. REMARKS N/A CERTIFICATE OF COMPLIANCE I, Richaid R. Cockrel, 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" starp'Zpires 07/17/10 Date 0 1 '-oe. '(flir FENOC CIr,,~Crrrgjnnzation Signed au i hZderfla" .... Q.c. 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 Hartford, CT have inspected the work described in this report on Apu. ,3apl9 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 thi 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 Iba[0 Signed "-e n&* Commissions A 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.lnspection 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 FFNOC atrn l repFi organi-aioN) Signed Q.C. ato~drp~**

                                                      -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 C1.        of Hartford, CI       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 ben, completedin 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 (I,~r.h.)

                                                                                                                            .rdI.aidh.h.t, .odlOD

15 RFO Inservice Inspection Summary Page 151 of 238 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-11-VR--4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI ,L :-*. 1 Owner FixstEnergy Corp. Date January 21, 2008 nth Main St Of4 &dAfig Sheet 1 of 1

2. Plant Davis-Besse Nuclear Power Station Unit .... 9 #1 Order# 200237926 5501 N. SR. 2. Oak Harbor. OH 43449 Add-* R.P.i Orgnzonp. O.N- Jb o,==

3 Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng_ 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No, 20 ExDlration Date 07/17/10 4 Identification of Systems Hanger M11131H54, DB-SNC434 (Subsys064-02) . 5 (a) Applicable Construction Code ANSI B31.1 1967 Edition Later Addenda Code Case N/A (b) Applicable Edition of Section X1Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case No (c) Design Responsibilities FirstEnergy Corp.,Lisega Inc.

6. Identification of Components Repaired or Replaced and Replacement Components of Manufacturer Manufacturer's National Other ldentification/ Year Repaired ASME Name of Component Name Serial No.. Board No. Jurisdictional No. Built Replaced or "Code Replacement Stamped Snubber Lisega Inc. 61195/25 N/A DB-SNC434 UnIL Replaced No Snubber Lisega Inc. 30600271/100 N/A DB-SNC434 Uuk Replacement No -

7. Description of Work Existing snubber (serial#61195/25) was replaced with a like for like new replacement snubber (serial#30600271/100) dufing routine maintenance not due to a failure.

5.a cont. ANSI B3 1.1 & MSS-SP58 1967 Edition or Later 8 Tests Conducted: Hydrostatic Yes Pneumatic Yes Nominal Operating Pressure Yes Other Yes 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 (r..,Mod,-) at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) slze is 8 Y2 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 top of this form.

15 RFO Inservice Inspection Summary Page 152 of 238 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 NI1S-2/lNR-1)N:VR-1 Appljubl,Manuf"-u Daa Rsfrts 1, eAtce ,.

                                                              &.REMARKS N/A                                                                                                                                          '::

CERTIFICATE OF COMPLIANCE I, Richard R. Cockrell certify that the statements made inthis 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" starpTjxpires 07/17/10 Date _1-21-o8 FENOC Signed Q.c. CERTIFICATE OF INSERVICE INSPECTION I, 1. VCE. I"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, CI have inspected the work described inthis report on 1-; *- 0 , and state that to v the best of my knowledge and belief, this repair, modification or replacement has beencompleted in accordance with'Secti", 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 inthis 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 q 1. A 1 .... w CERTIFICATE OF COMPUANCE

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 oft' 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 . 1, National Board Certificate of Authorization No.. 20 to use the "NR" stamp expires 07117/10 . Date IFENOC Signed Q.C.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 bi,- 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 _._ (Irnpstmi Bauzd (Nalioml Ond.rndo an=*,,, -

15 RFO Inservice Inspection Summary Page 153 of 238 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 0DB-0070-5 FORM NIS-2INR-1INYR4- OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section X]

1 Owner FiastEnergy Corp. Date January 28, 2008 76 South Main St.. Akron, OH 44308 Sheet 1 of 1

2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor- OH 43449 Order # 200237927 eep.-rUos -an n PO. No, NO, .

3 Work Performed by FirstEneiry 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 Hnager EBB-5-19-H4, DB-SNC469 (Subsys 063-01) 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 No (c) Design Responsibilities First Energy Corp, Lisega Inc..,

6. Identification 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. Jurisdictional No. Built Replaced or Code Replacement Stamped Snubber Lisega 61195/105 N/A DB-SNC469 Unk- Replaced No Snubber Lisega. 30600271/049 N/A DB-SNC469 2006 Replacemeat No

7. Description of Work Existing Lisega snubber (serial # 61195/105) was replaced with a new like for like replacement snubber (serial # 30600271/049) :.

5 (a) Cont. ANSI B31.1 & MSS-SP58

8. Tests Conducted: Hydrostatic Noý 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 Blowdown Adjustments Made Using N/A at N/A (Litoa,) .. 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 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.

15 RFO Inservice Inspection Summary Page 154 of 238 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 NISr2/NR-IJ*-

AFpOc-leMA n nýmData FRi' a he iob Abl. S. REMARKS N/A CERTIFICATE OF COMPLIANCE I, Richard R. Cocleil , 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" sta.rbires 07/17/10 Date 01 -.29-D FENOC Signed k S 4 Q O.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 C'T of Hartford, CI have inspected the work described in this report on .3Ai. pg, 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 inthis 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 Sgnd jf 4 Commissions Niq1 andJils*'s-ioDmi. Snd.00;) r 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 "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 .-Hartfoid, 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 (Nato.- BooM (1oi.nd1~ o;

15 RFO Inservice Inspection Summary Page 155 of 238 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #f1,5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-0070-5 FORM NIS-2/NR-1/NA-R-1 OWNER'S REPORT FOR REPAIRS OR REPL.ACEMENTS As Required by the Provisions of the ASME Code Section Xl 1 Owner FirstEnergy Corp. Date Januasy 28, 2008 76 South Main St.. Akron. OH 44308 Sheet I of I 2 Plant Davis-Besse Nuclear Power- Station Unit #1 550i N. SR. 2, Oak Harbor, OH 43449 Order# 200237928 3 Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oak Harb~or, OH 43449 Authorization No 20 Expiration Date 07/17110 4 Identification of Systems Hanger EBB-5-19-H1 DB-SNC468 (Subsvs 063-01)

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 9k5 Addenda Code Case No (c) Design Responsibilities FirstEnergy Corp., Lisega Inc A. Identitication of Componnents Reeairor or Renlaned and Rtenlacement Comnoonenta 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 Snubber Lisega Inc. . 61195/98 N/A DB-SNC468 ijnk. Replaced , No Snubber Lisega Inc. 30600271/096 N/A tDB-SNC468 2006 Replacement No

7. Description of Work Existing Lisega snubber (serial # 61195/98) was replaced with a new like for like replacement snubber (serial# 30600271/096).

5.(a) cont. ANSI B31.1 & MSS-SP58 8 Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure N/A "si Test Temperature N/A oF Pressure Relief Valves: Service N/A Size N/A Opening Pressure N/A Blowdown (if applicable) N/A Set Pressure and Glowdown Adjustments Made Using N/A (frotCMeas) 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 reeort is included on each sheet, and (30 each sheet is numbered and the number of sheets is recorded at the too of this form.

15 RFO Inservice Inspection Summary Page 156 of 238 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/NV-4R-- 4~pllc~ale ~ Ms~aon Dal0Reprr tow Mactsd

9. REMARKS N/A CERTIFICATE OF COMPLIANCE I, Richard R. CocrelI , certify that the statements made inthis 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 ýto use the "NR" st' pires 07/17/10 Date D -9a- (t,.fl FENOC sr~zadiztlo)* repoirOt Signed / ( z t~~ ~~ a C-& QQ.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 empioyed by HSBCI of Har-foid, CI have inspected the work described in this report on .O0MA_ at and state that to the best of my knowledge and belief, 'this repair, modification or replacement has been complete-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, concerningt-he 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 tl-LýEfa Signed

k N-* Commissions 'Tr"*-

A CERTIFICATE OF COMPLIANCE N/A certify that to the best of my knowledge and belief the statements made inthis 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 ' 12/13110 National Board Certificate of Authorization No. 20 to use the 'NR" stamp expires 07/17/10 Date (fatonr FENOC oft~ep*,otrgotztrfzl)* Signed fsuttofts*l

                                                                                                               ,.pr*,*rtsto )

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 Harford, 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 with this inspection. Date Signed Commissions

15 RFO Inservice Inspection Summary Page 157 of 238 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 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, 2008 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, OH 43449 Order# 200237929 MepnnrgjuZUlnI'S.o..r*JoNNo..6t0.

3. Work Performed by FirstEnergy NutlearU Operating Co. Type Code Stamp .N 5501 N, SR. 2. Oak Harbor, OH 43449 Authorization No. 20 Exsiration Date 07/17/10 4 Identification of Systems Hanger EBB-5-9-HI, DB-SNC451 (Subsys 063-01)

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 No (c) . Design Responsibilities FirstEnergy Corp., Lisega Inc

6. Identification of Comoonents Repaired or Reolaced 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 Snubber Lisega Inc. 61200/24 N/A DB-SNC451 Unk. Replaced No Snubber Lisega Inc. 30700004/009 NIA DB-SNC451 2007 Replacement No

7. Description of Work Existing Lisega snubber (serial # 61200/24) was replaced with a new like for like replacement snubber (serial# 307000041009.

5.(a) cont. ANSI 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 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 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 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. ,

15 RFO Inservice Inspection Summary Page 158 of 238 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 NI1S-2/NR-1/N.W4-4

                                                                                                       .PPl-bl, Mnualý ý Qý~P  rMWob, M1*6

9. REMARKS N/A CERTIFICATE OF COMPLIANCE I, Richard R.Cockrel , certify that the statements made inthis 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 O1-29-09 ,ENOC 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 C1 of Hartford, C1 have inspected the work described in this report on 1A4).Zt r'B 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 -%Ovft "commissions ~ tII ~~ 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 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 C1 of Hartford, C1 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

15 RFO Inservice Inspection Summary Page 159 of 238 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/NV4R4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI i.. Owner FIrstEnergy Corp. .. Date January 31,2008 76 South Main SL Akron OH 44308 Sheet 1 oIl

2. Plant Davis-Besse Nuclear Power Station Unit#1 ?2 7 5501 N. SR. 2, Oak Harbor, OH 43449 Order# 200237930 3 Work Performed by FirstEnergNuclear Operating Co. Type Code Stamp Ng 5501 N. SR. 2. OakHarbor.OH 43449 Auittorization No.. 20 Expiration Date 07/17110 4 Identifcation of Systems Hanger EBB-5-8-HI I DB-SNC449 (Subsys 063-01)

5. (a) Applicable Constwrtion Code ANSI B31. L __ 1967 Edaton Later Addenda Code Case No (b) Applicable Edition of Section XtUtilized for Repairs or Replacements 19 95. Edition .96 Addenda Code Case No (c) Design Responslbilities FirstEnergy Corp., Lisega Inc

6. Identification of Components Repaired or Replaced and Replacement Components Manufacturers National Other ldentificaton/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No.. Jurisdictional No.. Built Replaced or Code Replacement Stamped Snubb*r .. Usega Inc. t61195/68 N/A DB-SNC449 Unic. Replaced No Snubber Lisega Inc. 307000011065 N/A * . DB-SNC449 2006 Replacement No

7. Description of Work Existing Lisega snubber (serial #.61195/68) was replaced with a new like for like replacement snubber (serial# 30700001/065).

5.(a).coML ANSI B31.1 & MSS-SP58 7-- B. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Noe Other No Pressure NIA/ Ds! Test Temperature N/A -F Pressure Relief Valves: Service N/A Size N/A Opening Pressure NIA Slowdown (it applicable) N/A Set Pressure and Biowdown Adjustments Made Using N/A at N/A "_'" NO'E: Supplemental sheets in the torm of lists. sketches, or drawings may be used, provided (1) size Is 8 % X I4 in. (2) tntormation 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 top of this form. -

15 RFO Inservice Inspection Summary Page 160 of 238 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-S FORM NIS-2INR-I1/NW-

9. REMARKS N/A CERTIFICATE OF COMPUANCE 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' sta-Jj ires 07/17/10 Date 6i-3i-o* 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 . -artford, CT have inspected the work described in this report on .. AA-'&. 1co-* 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 imptled, 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 1131108 Signed'____ Commissions ______________A CERTIFICATE OF COMPUANCE 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 077117/10 Date FENOC Signed Q.C.__n-

CERTIFICATE OF INSERVICE INSPECTION 0,u 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

15 RFO Inservice Inspection Summary Page 161 of 238 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/N4-R-4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section X( . I Owner FirstEssexegy COX p. Date January 28, 2068 NL,.~A- AA OTT 44';AR Sheet I ofIl 74 Qo fb X4.1 StA 2 Plant Davis-Blesse Nuclear Power Station Unit #1 5501 N. SR. 2. Oak Harboar. OH 43449 Order # 200237931 AM,* o0,r.kn P.O.No. JobW,., wapw

3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng.,

5501 N. SR. 2. Oak Harbor, OH 43449 Authorization No 20 Explraiion Date 07/17/10

4. Identification of Systems Hanger EBB-5-8-H12 DB-SNC450 (Subsys 063-01) 5 (a) Applicable Construction Code ANSI B3 1.1 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 No (o) Design Responsibilities First Energ" Corp, Lisega Inc.

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 Snubber Lisega Inc. 61195163 N/A DB-SNC450 Unrc, Replaced No Snubber Lisega Inc. 30700001/064 N/A DB-SNC45G 2007 Replacement No

7. Description of Work Existing Lisega snubber (serial # 61195/63) was replaced with a new like for like replacement snubber (serial # 30700001/064).

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 NI/A 'F Pressure Relief Valves:

Service N/A Size N/A Opening Pressure N/A Slowdown (tf applicable) N/A Set Pressure and Slowdown Adjustments Made Using N/AI at N/A NOTE: Supplemental sheets Inthe form of lists, sketches, or drawings may be used, provided (1) size is 8 1hX 11 In (2) Information in "ers 1through 6 on this renort is included on each sheet, and (30 each sheet is numbered end the number of sheets is recorded ,at the ton nt this torn, this r nort is included on each sheet and (30 each sheet is numbered and the n ber of sheets is recorded at the ton of this form

15 RFO Inservice Inspection Summary Page 162 of 238 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-2/NR-1IN-VR-1

9. REMARKS N/A CERTIFICATE OF COMPLIANCE I, Richard R. Cocki*il ,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 "NA" rules National Board Certificate of Authorization No. 20 to use the "NR" stap1-kxpires 07/17110 Date OJ'-2.E?-o FENOC Signed *2Si.tJ.---=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 Hazrtford, CT have inspected the work described in this report on JA. 3!,Jap,? 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 th.-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 Signed *CAw-._ Commissions

0' O 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 07117/10 Date IFENOC 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 andemployed 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

                                                                                                               *nd rbftndon andn..D

15 RFO Inservice Inspection Summary Page 163 of 238 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/N-VR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

                         .....                         As Required by the Provisions of the ASME Code Section XI 1 Owner         FirstEnergy CoI p.                                                        Date      January 28,2008 N.-

76 South Main St.. Akron. OH 44308

                                          ,Adam.8                                                          Sheet I of t 2    Plant       Davis-Besse Nuclear Power Station                                         Unit                                  #1 5501 N. SR. 2. Oak Harbor. OH 43449                                               Order# 200238292 Adll                                                               Reprmr   alozn P... No.,  .a, 3    Work Performed by       FirstEnexgy Nuclear, Operating Co.                            Type Code Stamp         NR 5501 N. SR. 2. Oak Harbor, OH 43449                                         Authorization No       20 Exolration Date     07/17/10

4. Identification of Systems Hanger EBB-5-I-H1, DB-SNC437 (Subsys 063-01) 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 No (c) Design Responsibilities FirstEnergy Corp., Lisega Inc

6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired AStIE Name of Component Name of Manufacturer Serlal No, Board No. Jurisdictional No, Built Replaced or Code Replacement Stamped Snubber Lisega Inc. 61200/15 N/A DB-SNC437 Unk. Replaced No :u-Snubber Lisega Inc. 30700003/115 N/A DB-SNC43 7 2007 Replacement No

7. Description of Work Existing Lisega snubber (serial # 61200/15) was replaced with a new like for like replacement snubber (serial# 30700003/115).

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 N/A Blowdown (if agiplicable) 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 1/2X t1 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.

15 RFO Inservice Inspection Summary Page 164 of 238 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-1VNYR41---.
                                                                                                           ,J. M.

Appl4 r OataRCau a b; _-th.d

9. 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 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" stam, "pires 07/17/10 Date O -1s-.2-o 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 C1 of Hartford, CT have inspected the work described in this report on Vi4 'z' 'xe 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 inthis 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 k[2410-6 Signed )mC 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 07/17110 Date FFNOC 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 inaccordance 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 inthis 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 _

15 RFO Inservice Inspection Summary Page 165 of 238 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/Nf -R4-OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner FirstEnergy Corp. Date Januaxy 30, 2008 76 South Main St.. Akron. OH 44308 Sheet I of 1 2 Plant Davis-Besse Nuclear Power Station Unit #1 Na. 5501 N. SR. 2, Oak Harbor, OH 43449 Order #200238293 Mdra. Rpe, OrqglnizbfP.D. W ,et..

3. Work Performed by FirstEneigy Nuclear Operating Co. Type Coda Stamp. N _

5501 N. SR. 2. Oak Harbor, OH 43449 Authorization No 20 Expiration Date 07/17/10 4 Identification of Systems Hanger M1170/H12 DB-SNC415 (Subsys 062-01) 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 No (c) -Design,Responsibilities First Energy Corp, Lisega-Inc.

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 Snubber Lisega Inc. 61200/20 N/A DB-SNC415 Unk. Replaced No Snubber Lisega Inc. 30700003/119 N/A DB-SNC415 2007 Replacement No

7. Description of Work Existing Lisega snubber (serial # 61200/20) was replaced with a new like for like replacement snubber (serial # 30700003/119).

VT-3 Visual Inspection was completed satifactoty. 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 N/A Blowdown (Ifapplicable) -N/A- -. Set Pressure and BlIwdown Adjustments Made Using N/A lTes M~ed) at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 814 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.

15 RFO Inservice Inspection Summary Page 166 of 238 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-VR--- 4AIPPWManudalt*enOalaRep©mWa. Aljh

9. REMARKS NiA 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 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" star 1pres e 07/17/10 Date 0) - E3 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, CI have inspected the work described in this report on IJMj.3, !COQ and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance7with 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 inthis report. Furthermore, neither the undersigned nor my employer shall be liable inany manner for any . personal injury, property damage or loss of any kind arising from of connected with this inspection. Date_____________lell Commissions 35 t2A 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 "NW"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 "NRH stamp expires 07/17/10 Date ( FENOC Ce,0ao ©grt capi ntad Signed _ _ (oatma~ze,.,oneI~n~e) _ 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 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 inthis 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 (Inweclot) Commissions (Ntanal2OalOi~neon~oooa~ncn,a) hi hiadidions. andno.)I

15 RFO Inservice Inspection Summary Page 167 of 238 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-1iNVR 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, 2008 76 South Main St., Akron, OH 44308 Sheet 1 of 1 2 Plant Davis-Besse Nuclear Power Station Unit #1 N52o 5501 N. SR. 2, Oak Harbor, OH 43449 Order# 200238484

3. Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp Ng NlH ,

5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No. 20 ExDiration Date 07/17/10

4. Identification of Systems Pressurizer Code Safety Relief Valve DB-RC13A (Subsys064-04)

5. (a) Applicable Construction Code ASME III CL.I 1968 Edition S 70 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 Responsibilities- FirstEnergy Corp.

6. Identification of Components Reoalred or Renlaced 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' 1-1 1/8" Inlet Flg. Stud Unknown Unknown N/A N/A Unk. Replaced No 1-1 1/8" Inlet Fig. Stud Nova Machine Products Hr# 722735 N/A TfC# 0A57 2006 Replacement No

7. Description of Work During the change out (routine maintenance) of the above listed valve, one inlet stud was replaced due to damage during removal.

All other existing bolting materials were re-used. A VT-2 initial inset vice 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 (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 (1) size is 8 '/ 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 top of this form.

15 RFO Inservice Inspection Summary Page 168 of 238 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/NWR-I-Appý4 ManW -re Dat RýNSý b h

9. 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 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" starrppires 07/17/10 Date 62 -1 *- . FENOC Signed. _2 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 CI of Hartford, CT have inspected the work described in this report on VeS. a. 3.001& 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 mSigned

                                                             '         .                       Commissions 11Z 73u3                 tR CERTIFICATE OF COMPMANCE 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  _       _C.

(n-. .f rWaa* u.,eln alozd *N la ) 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 C*I 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 inaccordance 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 inany manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection. Date Signed Commissions (Inv ýet) (-.-I 8-ad (-I oo~~,)

15 RFO Inservice Inspection Summary FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Page 169 of 238 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 REPORIOFREPAIRE MODIPICAIION[-' OR REPLACOMENTI - To NUClEAR COMPONENTS AND SYSTEMS [N NUCLEAR POWER PLANTS 1 Work performed by AREVA NP tnc.. PO#s 45255618 (name ofTNRcertificate holder) (F0 no, job no, etr) 3315 Old Forest Rd, Lynchburf; Va. 24501 (address) 2 Owner FirstEneorR Company (enme) 76South Main St, Akron Ohio 44308 (address) 3 Name, address and ideatificatien of nuclear power plant Davis-Besse Nuclear Power Station 5510 N SR 2 fOak 74e,,,,- Q1,i 43449 _________ 4 System Reactor Vessel Head # C24-2013-52-1 5.a: Items Which Required Repair, Modification, or Replacement Activities identification, Construetion Code Activity Na'l-rnt Cd Repair/ No Tye of Mfg. Mfg. Serial t Juresd. i Other Year Sec Edtion/ Code Cla M [temn Nome No, No NO dNo Bilt Se BultDivision AdetdsCaeos Replace 1 (2) 2) N-152 NIA N/A 1975 (3) (4) (5) A Replace 2 3 4 6 7 8 11 II

5. b: Items installed During Replaeerit Activities Identification Construction Code Type of Installed or Mfg Mfg Serial Nat'l Bd. furisd Other Year Namef Edition/ Code Code Item Replaced 5a Name No. No No Built Section/ Addenda Case(s) Class Item No Division (6) . (8) (7) N/A N/A N/A (10) (3) (4) None I

6. ASME Code Section XI applieable for Inservice inspection: 1995 1996 None (edition) (addenda) (Code Cases(s))

7 ASME Code Section XI used for repairs, modiflcations,or replacements:: 1995 1996 None (edition) (addenda) (Cede Casen(s))

8. Construction Code sed for repairs, modifications, or replacements: 1986 None None (edition) (addenda) (Code Cases(s))

9. Drsignaresponsibilities: (8) __

10 Tests conducted: X hydrostatic Pneumatic E- Design pressure (9) pressure 2155 psi Code Case(s) NA fsvstem leakase) rhis form mav be obtained from The National Board of Boller and Pressure Vessel tInsectors.. 1055 Cruoer Ave.. Columbus. OH 43229 NB-81

15 RFO Inservice Inspection Summary Page 170 of 238 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 of work: with AREVA procedure 03-12216144-04 with SDCN 30-9069180-000 (use of properly Identifiedadditional sheet(s) or sketches Is acceptablo) Quick Vent Closure Assembly with Bearing Plates SIN 76-00024-001-08-01 12, Remarks: Listed below are the number codes that apply to the repair activity Items shown on the front page (1) Babcock and Wilcox Company (2) Reactor Vessel Head # C24-2013-52-1 (3) ASME Section It1,Class f, Division I (4) Construction Code ASME 11t,1968 Edition, 1968 Summer Addenda

15) Code Cases 1332-4. 1492, and 1359-1 (6) AREVA P/N for Closure Assembly 7079271-032 (7) Quick Vent Closure Assembly with Bearing Plates SIN 76-00024-001-08-01 (8) AREVA NP. Inc (9) By others- FirstEnergy .,

(10) See AREVA NP CA data packages 23-9070650-000 CERTIFICATE OF COMPLIANCE 1, Nick Similo,certify that to thebest of my knowIedge snd belief the statements made in this report are correct and the repair, modification oa replacement activities described above conforms to Section X of the ASMS Code and the National board Inspection Cods "N'*"roles. National Board Certificate of Authorization No NR-64 to use the 'N." stamp expires-May 11 2009 NPRCertificate Holder AREYA NP Ina (name) 5 Date 208, Signed_ . ., Manaser oA/oC Operatons (authorized representative) (title) CERTIFICATE OF INSPECTION I, Thomas C. Lea, holding a valid commission issued by TheNational Board of Bailor and Pressure Vessel Inspectors and certificate ofcompetency issued by thejurisdiction of Oh10and employed by HSBCT of Hartford CT have inspected the repair, modification on replacement described in this report on April 2. 2008 and statethat 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'miles By signing this certificate, neither the undersigned nor my employer makes any warranty, eprepsed or implied, conreming the woik desosibed in this report Furthermore, neither the undersigned noa my employer shall be liable in say manner for any personal injury, property damage or lost of any kind arising from or connected with this inspection Date5April2Z2.00     Signed   ii1aion*                                      -      Commissions NB3930N IAOhlo Comms br-specor)            (NationalBoard(int] endorsereasns),jurisdiction, aedan)
                        /

15 RFO Inservice Inspection Summary Page 171 of 238 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-1WR--I OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner FirstEnergy Corp. Date February 6,2008 N OH 0 76 South Main St.. Akron. OH 44308 Sheet I of 2

2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 Order# 200249935 .

                                                                                                                    ,-erurgszaa*,zrIu. N4o.Job No.,eC 3 Work Performed by         FirstEnergy Nuclear Operating Co.                             Type Code Stamp         N-R 5501 N. SR. 2. Oak Harbor, OH 43449                                        Authorization No       20 Expiration Date      0G7/17/10 4    Identification of Systems     Pressurizer          DB-r002                           (Subsys 064-04)

5. (a) Applicable Construction Code ASME III CL. 1 1968 Edition 68 Addenda Code Case No (b) Applicable Edition of Section XtUtilized for Repairs or Replacements . 19 95 Edition 96 Addenda Code Case N-41I6-3 (c) Design Responsibilities FirstEnergy Corp., Welding Services Inc.(WSI), Structural Integrity Asso-'a*-.* Inc.

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 Pressurizer Babcock & Wilcox 620-0014-59 N-157 DB-T002 1972 Repaired Yes

7. Description of Work The existing 4" pressurizer spray nozzle weld was weld overlayed by WSI.

All phyical work was performed by WSI per PO# 103571 and WSI traveler# 103571-TR-002 All work completed by WSI is documented on "NR-27 Report of Repairs. FirstEnergy Corp. (DB) performed a VT-2 initial inservice leakage test. Test was satisfactowy. 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 (itapplicable) N/A Set Pressure and Blowdown Adlustments Made Using N/A (TW. in 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.6Bon 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.

15 RFO Inservice Inspection Summary Page 172 of 238 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-U1IWR-. .

9. REMARKS Welding Services Inc.

CERTIFICATE OF COMPLIANCE Richard R. Cockiell 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" starq-*pires 07/17/10 Date o2_-W,, o . 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 OHI-O and employed by HSB CT of Harnford, CT have inspected the work described in this report on V"2LB. -7, and state that toý - the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Sectidihv " 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.JJWB Signed __T__,, _____,_. _Commissions ______ __tk C,__ __________________A an u~*Z*adno

))

TAC1.I CERTIFICATE OF COMPLIANCE I, N/A , certify that to the best of my knowledge and belief the statemnents 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. Y1. 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 CI 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~ra 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 W 0,dý- Mn~~f

15 RFO Inservice Inspection Summary Page 173 of 238 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

                                                                                                                                                                                    ?sa ;; ?

FORMNE-I 10/PORt OF REPAIRF] ItdODIFICAIIONF] ORREPIACEMEN rF]1 TONUCLEARCOMIPONENTS AND SYSTEMNS IN NUCLEARPOWERPLAN1S I Woruprf*omcslby Weldng Services Inc. 1 3571 'NR-27" Weoll~o~rbd.1(P.O.-pe-2225 Skyland Court, Norcross, GA 30071 20Surr. F0i- EnergyCorp. 76 S Main, Akron. OH 3 Nae rdd-. deefi6o5aufoofre.r powe plans Dav/Eese, 5501 N. State Rte. Z,Oak Harbo, Oh'o 43449 4 Syrtero Reactor Coolin 9 System "RCS" 5a.l*ernWhichRoeuiredRe"/nir, Modifimlon or Rcprecemeot Ackd0des ldeeificatios CrooneuboiCode "Adivi/0 No I mMypof l a Nm ¢aNoMf Ol NOR1d usdo OhrYcrtt Noted EditionC"P-..a(S Coede Code l Secton'3 Addenda *= o!R RCS B&W 520-0014-59 N-157 N/A N/A 1972 Diisfo. AS ME WA 1 Repair Spray Nozle . 0/v. 1008 5b. t1001 booOlolring ReplaemoentAcfioiri idoorifin*e*o Coeauede Code Iyeo.f be. ,lroroleeyIteced Mik. M N

                                                                                                   -               01e0     Ye       No       en, r/           Code Wu/a                                     BW"                      ddoo      Cod
                                          $a     NO Nol.         Name       SItme          NS.1al NoSo       NIRd1 NO                0it      So0 Mv~iden      Adea e       os               CoedCls()

Weld Overlay "see e &- WSI N/A N/A N/A N/A 2007 ASMErIX 10/0 N-740

6. ASEIECode Secoeoe X appliebla for in-e/so inseproion: 1996OS NIA

7. ASMECodeSeed X- roedrofr eyeodirioaeosor ilecre:r: 1995 1996 N-740, See lie 11 Co-eaoaon Code .eed forlepain modisiatonoo repleceomen ASMEIl, 1008 Saummrer 196S W/A 9 De eeyseealree FENOC Fist EnergZyN/dear Operol/eg Co.

10 Teorasc.ndunte hydrostaic F] prroor [] deignprosure [F'] see - In CodeCeerls) N/A PressureTest to beperformed by owner. (I Descripti of woak The Spray Structural Weld Overlay was performed in accordance with WSI Traveler 103571 -TR-002 latest Rev. (eme properlyidee/led eddidtnelsdloc) or skLtsr ) is eacpte*ble) which incorporates Davis Besse SAP work order number 200249935. This implements a one time NRC accepted repair plan In accordance with Relier Request RR-A30 and for amend code case N-740 WS1field weld rnumber. Spray-WOI. Davis Besse gteldi weld number 'D , Weld#fRC-PZR-VdP-1t52 ______

                                                                                                      "Stainless Stool" Weld RC-MK-A-90-PW5O 12.Remrarkrs WPS used for Weld Overlay01-43-M8-T-8303             ,Seav 102830 Rh[: Weld woietscd ERNiCrFe-1A SFA 5.14.035 CERTIFICATE OF COMPI lANCE I,               James E. Hertz            , neasfy that to the belst ybkn, dge and betlif thr sttementsrooden dr/s report are Corresetad the repair.moocdfmdaoo       orrrepinceot activitiesdeserbed above cosforr to Section Xf of the ASME Code and the National BoardInsperios Coda 'NR! ors Nadionel
                                 .Ioard Certficate odAuthorizatio* No                              NR-OS          1 o.Wdee'NE seinp erpinro Nov.69              2010 NE Certificate Holdder                                                         Weding Sevices Inc.

Daoe 111812We Si e ' QNQC iospeder ERTIFICATE OF INSPECTION

                             ,      "miA        e.
                                                 -       ,-d.           held/ngVS,, coovo.seonm/s1sedbyThNl..a.Ional Board of o/iereand Pressore Vsel lenrectoao an4 eand/Onotoof srnapetaresy      isued by theejusdiction of                      a- "r* 0                andesoployedby respecttede themtsn, casdrlterss on             s       eroos- roe/narenportb
                                                                                  *rn*bed                                                       a*ndtatlrn     thot.

best of my kaoedecdo and belief. dr/a repair, modifrati on or replscetent aectvityhbooboo noonleted. accorda=.vide Section X of the ASME Code andthe Nationl BoordInscction Code *NR-rules By sipinar this crtie/car, neither throrder/red =wo mryexrplsor maoes aroy wýor*y, srsoo ot ipliped, cncsner/ the work described ia this report Furthemneme, seitber the undersigrd umor y e.eloyer sball be liable in rnomnner for eryyersotoairjr-o, propertydanago on Ioss of any kird arisigorh ornoreteeed withthis inspction Dare 0%L4(qSse04iI Ioa.r .e. im i _ Cormioronrrr tx~A A V rrr-er5eersrek/Ci~

15 RFO Inservice Inspection Summary Page 174 of 238 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/WR-I4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner FirstEnergy Corp. Date February 6, 2008

                       'if  ~Rnth     M%4Aiiqf    A krrn.-01?4 4431)8                                         Sheet I of 2 2     Plant        Davis-Besse Nuclear- Power Station                                           Unit                                #1 5501 N. SR. 2, Oak Harbor, OH 43449                                                 Order# 200249948 Bep* OqWanH P.O.No..JaNo., at 3 Work Performed by              FirstEner'g, Nuclear Operating Co.                             Type Code Stamp         NR Nam        O 8_=01   N. SR. 2. Oak Harbor, 01-         43449                               Authorization No.      20 Expiration Date     07/17/10

4. Identlfication of Systems Pressurizer DB-1002 (Subsys 064-04)

5. (a) Applicable Construction Code ASMvE III CL.I 1968 Edition 68 Addenda Code Case No (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N-416-3 (c) Design Responsibilities FirstEnergy Corp., Welding Services Inc.(WSI). Structural Integrity Associates Inc.

6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Nanie of Manufacturer Serial No Board No. Jurisdictional No Built Replaced or . Code

Replacement Stamped Pressurizer Babcock & Wilcox ., 620-0014-59 N-157 DB-T002 . 1972 kepaired Yes

7. Description of Work The existing 10" pressufizer surge nozzle weld was weld overlayed by WSI.

All phyical work was performed by WSI per PO# 103571 and WSI traveler# 103571-TR-004 All work completed by WSI is documented on "N'R-21 Report of Repairs. FirstEnergy Corp. (DB) performed a VT-2 initial inservice leakage test. Test was 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) NIA Set Pressure and Blowdown Adjustments Made Using N/A (rat Medar) at N/A (Loeuoa) - NOTE: Supplemental sheets in the form of list,, sketches, or drawings may be used, provided (1) size is 8 1/2i 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 top of this form.

15 RFO Inservice Inspection Summary Page 175 of 238 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/N4WJ: ApJcwfl,M,~n*,~,f . OatWRFpoýt M ac

9. REMARKS Welding Services Inc.

CERTIFICATE OF COMPLIANCE I, Richard R. Cockaill 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" stawrp)expires 07/17/10 Date O2-06,-Da FENOCaaol".) d ,,p~kr (name Signed Q.C. (..Atataea,ep rnatVa) .. CERTIFICATE OF INSERVICE INSPECTION i, Thomas C. 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 C1 of Hartford,-C-.- have inspected the work described in this report on F. and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Sectish:: 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 El

                  -7*                  Signed          trp*J
                                                           .     ."*1                        Commissions          RG4133   (Nndorza        9TA Boaa(id ando*amat,),   c,cwk.

CERTIFICATE OF COMPLIANCE I, N/A certify that to the best of my knowledge and belief the statements made in this report arre 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. a-(nam afre.pair oO wno;a.,) (afl,(haazd rapraentar~ae(} 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 C7 of Hartford, C I 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 "NRW 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-re 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 (BadonAfBoat,(JoB attdotaawna,).

                                                                                                                           ~dIBaBona mda)(

15 RFO Inservice Inspection Summary Page 176 of 238 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% FORM1NE-I REPORC OF MRPAREN A MODrNFIC.ATIONF OR REPIACEMTENSI 01NUCLEAR COMPONENTS ANDSYSTEMS [NNUCLEAR P'OWERC PLANTiS I W.oLpo.r/by Weld,,gServices ino 1035i71 'NR-21' 2225Sbortand Court,Nooo.IA 357 2 Ov.-e F/Z rrary Corp. 76S MeN.Aknoe, OHl 01

3. NaeoaddoaorIdalexoon0of 0leo, 0o0 plant Oavts-o-90e. 5501N.StoteRto.2,0Oak Harbor,Ohio 434,49 4 G'-,0 Reant., Cootte Syotar "RCS" ldr~iorC~osonzooo Code iy R. T boO 0

                                                                 .oed Naml o-         MeBd                   Oisr                    to?

Seo AEdina( Crple Code Can s) Cod/ e RaSor4MC I RCS R&W 920-0014-59 N-1S? 57A N/A 7 1101 19l8 N/A 1 Repair PZR Surge r1o61 5b, IrmoIoaed DoieasReploeot Aefi0i, Ideatiffodon COneroi-oOCode Typ, bo h- slad. N Mfg m Id Nanr No l War end, ! E1or! Cod, Cod Cloas eNoo. IN_&. N- Ndd. C.O() WeildO eoy #11-12 I A N/A N/A NIA 2007 AS 5XI96/ N-740 ERNICrF.e7A "see I1 Heat # NXOTS6Tt( 1

6. ASMACode tSsl.)O orleol e.iorN,-r*erpr i o 1995 1996 NIA 7 XS4fe Co& Seetion XMmdee repo&rooda6ooidm0 oprroroaro: 1995 1996 N-740, See feei11 3Coneuoion Code usedtorrepai.004 tio,4000 orrloe-ee AS/C Ill.1960 Sroener1069 N/A 100,00 Oddord) .(00*,dO,)

9 Desigae/ olbildo FENOC First Energy Nuclear Operatlng CO. 1950 Teots ordad khodrrro ED P oror drritop- E]o prooerao _ _Pei CodeCore/el NIA PressureLest to be performed by owner. i Dnerptooruetc i

                                                                                     /(0op~oporty~d9i~d eddfir/ml      dxoteoe*)- e/or) re0orp0blt.

Pressurizer surge Structural Weld Overlay waoperformed in accordlance writhWSI Troveler 103571 -TR-004RevJ 0Sft 0/CinIcorpratesf Davis Besse SAP work order number 200260265. This implements a one time NRC accepted repair plan In accordance With ReOief Request RR-A30 and for amend code case N-740

12. Remarks WOOmed =f Well Oriry tFA RA1 Weeuv0e W00os-WO %RN CVDA 5.15 B*s 111*9R-TIfK WSI Ito/A WeldN-b.teeOoýeWOL:Davis11-re5o1dWeldNosebeeRC.PZR.WP.23 CERTIFICATE OF COMPL LANCE I, James E. Heetz , cortify that to de best of my knowledge: od beliafthe stafi ar rotde iia d report oo Correr and thorepair.soddfmicatao wesyloome-e -6,it-0 d-ieeiod aoboel oofforsatoSeoorre )a of 01/ ARMSCode rod

                          .th Nortrod Soord    Inspe~orioCode 'Nt"rrs,n Nation.l BoardCertificareof         rtroei     No               NR-59           to .e the 'NRt  stmp ropirf Nov. 6            .2010 NR Cor.ri te Holder  .,e                                                   l     Servoces Inc.

Date 1/15/2008 S/good QA/OCInspector CERTIFICATE OF INSPECTION I, "JT oC&W (e". otirg ovalid orsoioso issuedby The ioalBo of Boi0Sr ad PressurVe Von brp aoesdotfa,rlror of oporpenero4oved byrbejurisdioetonof red emoployed by eopeorediI/orep-.e roodificatoonor reetoorso dreeibordir this reprort lfg ds to h bootof ey koowledgeood belift "e rpar. ro*dicatioore rrmpleoot setvity has be; d a,0 odan0e 04th e0n4p SRcmonXG ofothe ASMECode asd tbeNatonao Board brerror Code 'N*Eruoeo By osioor this ctdiocate. neither fix ondrofignednor myesaployr makes aoy warraooy expres* d or Irpiod, concerning the work deoribed a thisreport oorbianooe.s/itrer the urdeigreed nor my employer ralal be liable in amyonaer for any pe*onal injeay,proporty dmaeo ore lon ofsoy kindorisc b*oororcooeoeod rth thisb/espetio*,. 0 wio Dote \ýtlo(C6 S4-od :7UCosooirioso 4e.3.

15 RFO Inservice Inspection Summary Page 177 of 238 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 FORM NIS-2/NR-1/NVR4- OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI

1. Owner FixstEnerev Corip. Date Februauy 6, 2008 04n-76 South Main St.. Akron. OH 44308 Sheet I of 2 Davis-Besse Nuclear Power Station Unit #1 2 Plant 5501 N. SR. 2. Oak Harbor, OH 43449 Order# 200249949 Add-= Rep.NOgagao- P.O.NO..JobNo.,

3 Work Performed by FisstEnergy Nuclear Operating Co. Type Code Stamp NR 52n , 5501 N. SR. 2. Oak Harbor. 011 43449 Authorization No. 20 Expiration Date 07/17/10

4. Identification of Systems Pressurizer DB-1002 (Subsys 064-04)

5. (a) Applicable Construction Code ASME M CL 1 1968 Edition 68 Addenda Code Case No (b) Applicable Edition of Section XIUtilized for Repairs or Replacements 19 95 Edition . .. Addenda Code Case N-41i 6-3 (c) Design Responsibilities FirstEnergy Corp., Welding Services Inc.(WSI), Structural Integrity Associates Inc.

6. Identification of Components Repaired or Replaced and Replacement Components Name of Component Name of Manfacturer Manufacturer's National Other Identification/ Year Repaired ASME Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped Pressurizer Babcock & Wilcox 620-0014-59 N-157 DB-T002 1972 Repaired Yes

7. Description of Work The existing 2 1/2" pressurizer relief nozzle (RC2A) weld was weld overlayed by WSI.

All phyical work was performed by WSI per PO# 103571 and WSI traveler# 103571-TR-003-1 All work completed by WSI is documented on "NR-26 Report of Repairs. FirstEncrg Cotp. (DB) pesfonmed a VT-2 initial inservice leakage test. Test was satisfactoy. 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 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 V2X 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. .

15 RFO Inservice Inspection Summary Page 178 of 238 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/ V ............... ..

                                                                                                                     /*~*M"n     --re DZ Rý    toWe--r~

9. REMARKS...

Welding Services Inc... CERTIFICATE OF COMPLIANCE Richard R. Cockrell RI, 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" stat pxpires . 0717/10 Date D Z o 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 OHfIO and employed by HSB.CT of Hartford, CT have inspected the work described in this report on Fr,. 7,.008 and state that to'-, the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Sectid6l-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 ~to 1 4 rklu_ 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 Xl of the ASME Code and to the National Board Inspection Code "VR" and "NR" rules. Z National Board Certificate of Authorization No. 316 to use the "VR" stamp expires 12/13/10 J National Board Certificate of Authorization No.. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.C. * (,.rn ofn~pzto f~izn) ,pr.not~t .) (4unorof.d 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 OHI-O and employed by HSB C1 of Hartford, CI 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 __

                                                                                                                             ý.Wll 0-fko~..d o

15 RFO Inservice Inspection Summary Page 179 of 238 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 434.49 Commercial Service Date: July 31, 1978 73* FORMNR-1 REPORT OF REPAIRF[' MODIFICA1ON"' . ORREPLACEMENI [] TO NUCLEARCOMPONE TS AND SYSTEMS N NUCLEAR POWER PLANTS I WorkpofTd by. Weidlng Services Inc. 103571 "NR-26 2225 Skyland Court,Nroross, GA 30071 2 0%,, First Energy Corp. 76 S Main. Akron, OH 3 Noo- ad- Wdemtt-a -lnrpoo , plao Davis-Besse, 5501 N. State Rie. 2. Oak Harbor. Ohio 43449 4 Sy-t Reactor Cooling System 'RCS" fteoN ohwt*tned Oýnpot, Modifiom 0 or Oeplaoner. Aoividne riedaorison I [ 1Nami" CootasotionCode Ao'ity 0 No Typeat h- M Mfg Non oi. o o ymt So*o CdodCl0 Rpaid Mod' pRoae NN SEonNo No tutsd. 14M od=* d Orr R"h'a mt Division C-0) I CS SRV-i :62"014-5E N-167 N/A NIA 1972 ASIE DIV.I 108 19 WA I Repair 5b.It-eLm.ttEd Doomn, Flh, AI, li.t Id=,gifi.6 C-.l~o Cod. Typeo l" Item a Ualarmdriaood MQ& Mf. !Nan' Rd No "Ms Oebr Ve_ S~, EdiftVc C~de

5. Itm o N-No* N- o N.N Ba* cm/Add =*s Cod. CL-*

SeralNo - No j*~" ~ Diumdo Add."~t Co,~)I on Weld Ov-tay os.e"I 11 & WSI N/A N/A NA N/A 2007 AEMEXI 95/96 N-740 i 11 of fral 6 AlSE Cod, S eefa ppliothiefor ho-noim iepaniar:1 1908N/ 7 ASME* Co.e Sftia 3a usedforripi. roodL6*ifioiaor , 1995 1996 N-740, Sea rie I1 oCod od, ad forrepso,. moodtamo ir-torrope, ASME!n,19M Summeor 1908 W/A 9 Draiorrpo-Wifide FENOC First Energy Nutele Operatng Co. M0Teo condednod fydonen F] Opoarrr E] Ooi p-ao F-1 F__ psi Code C-0l) N/A

                                                                    *Pressure Test to beperformed by owner.

il foipdre orf oa. Pr'r. Relief Nozzle "SRV-1 Repair started with a Stainless Steel Butter lay*r prior to a Structural Weld Overlay and inaedAd

                                    -     -o          withnWSI T           e*r 1o 7                  ..or 1e         wh      i6noro           or d) tes       is          Porortaa) wooperforenrdIn accordance with WSt Traveler 103571                        -TR-0093-1       Rev.)0 whitchIncorporates     Oasis Eeso SAP work order somber 200249S49.

This implements a one finmeNRC acepted repair plan in accordance wt Relief Request RR-A30 and for amend code case N-740

12. Rennarks WPS used for Staionles Stent "Butterlayer ()"0-T-00t.Roooer SS R/O; Weld ein, sendER.308L SPA 59 .035 WPS seodforWeld Overlay t0--W:T-is4-Top FiR; Weld ieine uood ERNiCrR-7A SPA 5,*4 .035 WSI Finld Weld Nambor SRV-1-WOL: Davis Besse Field Weld Nraobeo RC-PZR-WP-97-Z/W CERTIFICATE OF COHPL lANCE

                           ,               JamnesE, Hert               , otfy 0nitob tho bdstof my khowedge andhbotifthe staeteor made i this reportaý Comno-and dte repair, rtodraf-oasos repta*-tie ereeties         i      dnsrri above coidoeato SOcnonXI of din ASME Code sod the National Boardt]perlosn Code NR"nrles Nonai Bared Cerfulate of AWh-5iM N.                                         NR-69            toathe '1NRstamp xpiron Nov. 6 ..              2010 NR Cosifloa Holdea"                                                                 Welding Set)ervicesInc.___                               =

Oatt, 1117r0081 ~~n OP/aC lsspew0r 1.. I . A CATE OF INSPECTION t.~Qrs~A~m&.j..A~htde8 aooald conooresion iseinedby The Naoira oao of 00dmrend P-reorVeren ln n md. eatifi~at of e roooter issed by thujteosdiotion of 6"rd employed by nspeotad the repair, mediforo ororreplonaotr describedin th0 report " %rson otteern to the hoetof my hooorltdke andbelie thisrepair, aeodif eionoo reptaoameaor.toiiy has been coragetEd 0"mhO oorda*oe with Sectito la of tho ASMS Code and rho Nadonal Board hnspeetion Code "NR"rues By sigoing Oiseceortiate, roither rimradnedigied oor ray enployer rmake,ary -rrenty,-opresaedor imtpled, oaoemi*g the -tkd ieon*ed in this rtpon Furtheonotrc,neiter theOedrdesirnd nor my enrployer "Iallbe liable in -y mtaner for apy per onal ir00a. propaetydamagea. sefof hy ind or weioi Innoot with thisintpectrn, Lnd' t 0,,.U i..re1ofartyland

15 RFO Inservice Inspection Summary Page 180 of 238 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-11N-V-R-4-OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner          FirstEnergy Cotp.                                                           Data      February 6, 2008 76 South Main SL. Akron. 014 44308                                                    Sheet 1 of 2

2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 Ordei# 200249950 SpaUr.OrUap-bloP... NO.,

                                                                                                                                             .. Job.

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 07117/10

4. Identification of Systems Pressurizer DB-'1002 (Subsys 064-04)

5. (a) Applicable Construction Code ASIE ILNCL 1 1968 Edition 68 Addenda Code Case No (b) Applicable Edition of Section X1 Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N-41f6-3 (c) Desi.gn Responrsibilitias FirstEnergy Corp., Welding Services'Inc.(WSI), Structural'Integrity AssocijitesInc.

6. Identification of Components Repaired or Replaced 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 Pressurizer Babcock & Wilcox 620-0014-59 N-157 DB-T002 1972 Repaired Yes

7. Description of Work The existing 3"pressurizer safety relief nozzle (RC13A) weld was weld overlayed by WSI.

All phyical work was peiformed by WSI per PO# 103571 and WSI traveler# 103571-TR-003-2 All wotk completed by WSI is documented on "NR-24 Report of Repairs. FirstEnergy Corp. (DB) performed a VT-2 initial inseivice leakage test. Test was 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 (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 Y X 11 in. (2) Information in Items 1 through 6-on this reoort is Included on each sheet, and (30 each sheet is numbered and the number of sheets is recorded at the top of this form..

15 RFO Inservice Inspection Summary Page 181 of 238 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 D1-0670-5 FORM NIS-2/NR-14WR 4

9. REMARKS Welding Services Inc.

CERTIFICATE OF COMPLIANCE 1, Richard R. Cockiell , 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" staqr)xpires 07/17/10 Date (,,mo FENOC we ol0f~00n) roped Signed (ea01ooro01,e rpme ta0w1e. 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 CI . of. Haztford. CT have inspected the work described in this report on .- C-c. ~o, joo,.and state that to-the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with.Secti6hn= 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 inthis 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 oCommissions CERTIFICATE OF COMPUANCE 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 "VT and "NR" rules. National Board Certificate of Authorization No. 316 to use the VR" stamp expires 12/13/10 '1 National Board Certificate of Authorization No., 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed Q.C. Th 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 O1110 and employed by HSB C1 of Hartford, CI 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 "R" 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 inthis report.. Furthermore, neither the undersigned nor my employer shall beire 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 __ tk08e010l~ (lýe80 Scam8 o,01l0ed0o_ 1o

15 RFO Inservice Inspection Summary Page 182 of 238 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 o RUEORTOF pEPAIR Dy MO hIF-CATIONE OR REPLACEM-EN d- ~. -S -8 TONUCLEAR COM/PONENTS ANTD SYSTEMS INNUCLEAR POWER PLAN-IS I WorNperfor/edby. Welding Servics Io. 103571 'NR-247 2225 Skyland Court, Norcrows, GA 30071 2000,0 First Energy Corp. or 7E S Main, n, ON 3 Nane adlos tdolofiao o/onIf nuopboo plt Daviou-Nese, 5501 N. Sate Rte.2, Oak Harbor, Ohio 43449

4. yslent Reactor Cooling Systoem -RCS" 5&ltens WhichReqoird Repair,Modificaion ,

0, RoplacnenltAoýixitiel Idenifiestioa Ce-onno Code Actiity MNg MTN. Nell 1 B9 N99ei " ;d:o Code No Tpe I"No Itan" urisd.No otthr YeerfBuilt S.WR$ Codeo Roplo Repoi//Moad/ N-~ SerallNIL NNo o 00 eo n ,,l, Addend.'Ceo/,)

                                  -RCS           B&W         620-0014-                -57          N/A        N/A       1972      ASME 1         T1MR       N/A       1               Repar SRV-2 0     1.      109, 5b. Itb oo[*la*ed  DonegRe'placenomf   A_                                                                                                                           _     __        _

Ty of lon lnalSeodorrepblacd Mfg 0: Jared 0 - Yea N Cco. c No No/Iad NoR B- SIntn ECd.d CCode 5a]1N

M4cNo N. No. ui Division Addooo (flc/o)

Weld Overlay '- JIMIR I & WSE WA /A NA NA 2007 ASMF Xl 509 N-- -I - 12 of this form" 6 ASMER Code STootoXl applicableIom io-ori ijopalnon: 1.g5 '996 N/A 7 ASMECoded, fo*0 htoio, b orredlnasent/ 1995 99 n1 N-740, See/W/ 9 Co nnoforr rne.~rs iosooocCOde ooooER onoa, ,woooooour ASE 510,10 Onoo nroe1968 N/A

                                                                                              .t..                 l1)                   C -                           .

9 DDOrpo nooobdioea FENOC Fir Energy Nucleao OperatingCo. oRToo comoctdo0 hedroooiof El oonoac [3 doosp-.a,~ p--on po CcdeCcooO NIA

PressureTest to be performed by ownter, 11 DIc*pd oF,ok Safety Relief Valve SRV-2 Repair started Wth a Stainless Steel Butter layer prior to a Structural Weld Overlay and (m ofposperty ientified sddioda,dodts) orde/tn(o) is nMnvlto) was performed in accordance with WSI Traveler 103571 -TR-003-2RevJ 0 which Incorporates Davis Besse SAP work order number 200249950.

This implements a one time NRC accepted repair plan in accordanos with Relief Request RR-A30 and for amend code case N-740

12. Remarks WPS used for Stainess Sted nButter layer 08-09-T-001-Baort SS RJN;Weld wire used lR08L SFA 5.9.035 WPS used forWeld Overlay 01-08-T-804-Top RMf; Weld woneusedER.NiCrFe'-A SFA 5.14t035 WSI FPld Weld Nuwbepr SRV-2-WOL: Davis Besse Field Weld Nurnber RC-PZR-WP.-91 .WX CERTIFICATE OF COM-PI. ANCE I, Jarnes R. Hertz , setoif drotWthe best o f my noowl,4e andbelief e stetcee/to rnade m thinreportare Cornect;od the repair,modiication or replonoeet activitiesderbed dooveoncfon to Sec0tonXi of tndeASM Coda nod thoNeiooBoor Ad c penifti ! "*'. ,'k Nationot Boord C -ot/inate 5 insA No NR-69 to o*ete 'NR stopepit*s Nov, 6 2010 NR Ceioificoe Holder ' " We/ding Servies Inc.

Date" 1/17/2009 Signl QA/QC Inspector CERTIFICATE OF INSPECTION I. T***9mm G, AN (G ,holdiog asalid ncoomiseion i.ood by The NatioalBoard of Baher aed Pratcau,Vessel Inspectors o oeifoiocate of ompetenay ioued by doejurisdiction of .0 10 ' endoployedby Inspoted the repoir, oodficatlion or replnaoraoerdescrtib*d tis repon a ate ldWar to rho be of motkoonlodlae andhi//f, tb/ repir, ooodifieation or roplocneneo activitylionbeennoo no in aordnonloe withi Secnion30 of the AS//RECode andtde National Board Inspe*tio Cod. "N1W mi/c doc/tificoe noidleo he Ild-igned c*r ratycraployercaloraooy arty. opressed or implied, concein/ng By signing this the workdenscrbedin dds report FP*,thenteon .ciethAr the nrodcraigednot oey e=ployer shall be liable/ any an0a006 fr

                            .1y 9600000iooroy property400005000ior.            lo      ay bind oris
                                                                                     /co                 ooooonornectdwi/h 5im'peouno*

Dote ____ s 03 Cooetornaisons 'lot,

15 RFO Inservice Inspection Summary Page 183 of 238 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 Dd-0070-5 FORM NIS-2/NR-1/N-VR 4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl

1. Owner FirstEnergy Corp. Data February 6, 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# 200249951 N,?GdOnpn*g*o P.O.N., Job No.. W.

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 Piessmizer DB-T002 (Subsys 064-04)

5. (a) Applicable Construction Code ASME 1]1CL 1 1968 Edition 68 Addenda Code Case No (b) Applicable Editon of Section Xl Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N-416-3 (c) Design Responsibilities FirstEnergy Corp.. Welding Services Inc.(WSI), Structural Integrity Associates Inc.

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 Pressurizer Babcock & Wilcox 620-0014-59 N-157 DB-T002 1972 Repaired Yes

7. Description of Work The existing 3" pressurizer safety relief nozzle (RCI3B) weld was weld oveilayed by WSI.

All phyical work was perfotmed by WSI per PO# 103571 and WSI traveler# 10357 1-TR-003-3 All work completed by WSI is documented on "NR-25 Report of Repairs. FirstEnergy Corp. (DB) petformed a VT-2 initial inservice leakage test...Test was 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 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 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.

15 RFO Inservice Inspection Summary Page 184 of 238 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-1/NV-R-1........

9. REMARKS...

Welding Services Inc. - CERTIFICATE OF COMPLIANCE Richarfd R. Coclkeli , certify that the statements made in this report are correct and the repair, modification, or replacement of the items described above confor'ms 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" sta)Pr ~expires 07/17/10 Date O2-04-013 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 inthis report on. . --- '.* , 3.0 and state that toL the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Secto6i: Xrof 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 9161o0& Signed -mw~.i '.2

Commissions tAB' VA

                                                                                            ~~and                            $0ju*,=ad ,o )5 CERTIFICATE OF COMPUANCE 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 "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 (10100 ota bUtntimUton( Signed '_Q.C. (uud~olzed

                                                                                                           ,opm..n~an)ltvi 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                  OHIHO      and employed by HSBC1          of Hartfoid, C1        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 bei-r 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

15 RFO Inservice Inspection Summary Page 185 of 238 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

                                                                                                                                                                                 "* z 4i.=qZ FORMNR I           REPORTOF REPAIR[]                            MO*IFICATION[                 OR REPLACEýMENI 1    O NUCLEARCOMPONENI              S AND SYS] EMS IN NUCLEARPOWER PLANTS I Wolpc ,om,         ,by                                                Welding SeNiees Inc.                                                     103571       "NR-254 2225 Skylaod Court. Noraross, GA 30071 20                                                                                           iRrst rerM Corp.

76 S Ma*,n, Akron, OH

             '3 Noon, ad&-        t       iooi s o1oot       pooep.-oo                                               Davis-Besse, 5501 N. Stale Rte. 2, Oak Harbor, ONo 43449 SSy"tem                                                                     Reactor Cootling System "RCS" 5 1.If r-WhiChRo  oqoMhr t R4pr,.Moadior us or       o         a1.

aRe

                                                                            .* .tatmmt                                                                 c Idetificad.o                                                               Cosonstjo CodI                        AIl/V No lopoot    Oou                           "             N.l dI      JridNo         0,hr    YSrBuilt     N"sr"         Mdt/iort Code Clot             Rý)   /otTRapt...

Vsol Nae SerbdNo No 5Io-"W Di*isioo Aduds Cae(s)etI S RCS 020-001445t 6W N-157 NIA 1972 ASME_ 1068 N# 1 Repair I RV-3 DO t* 5b. It..s to-fs/lo DMen Rqltsyoar Ari~ies t/eeifloa/os Cmoasuaio Coda T'T,sof rem orda-pse my/ u g ?/V& Outln ode, I/d oS Code trinNo Nem Sad Sa No. No. Bitt cdhito Addenda Call.) Wed Overlay s0 firm I11 & SI N/A N/A N/A N/A 2007 ASMEX1 516 N-71 form, 12eof ths 6 ASME*C*6eSewdm* pwmblefor .- ~n*i*.edm 1995 1996 NIA SASMECedeSeanon XMnsd fmrte,, mtoiteioor.amplaoeert 1995 1996 N-740, See ThneI1 2 CcmtterooneCossd-dfor opos urodifaSiormoo01Ietooosr ASMESt.ý 1000 SvuR/re 1900 N/A 9 tea rpu tboa. EN/ICFoo E.r I/odeurOperattr Co. 10 Teoncoodord~j: trud- r7s pasrooe E lIe/spemr psoe VJ Psi Ca/uCotecs) NIA

PressureTest to beperformed by owner.

It Droujras,/-ouk Safety Relief Valve "SRV-3' Repair started with a Stainless Steel Butter layer prior to a Sittestural Weld Overlay and was performed in accordance with WSI Traveler 103571.TR-003.3RevJ 0 which inoorporates Davis Besse SAP work order number 200249951. This implements a one time NRC accepted repair plan in accordance orith Relief Request RR-A30 and for amend code case N-740

12. Retmarks WPS used for Sta/less Steel "Butter layer" 00-00-T-001-Buter SS Rio; Weld wire used ER309L SPA5.9.035 WPS used far Weld Overlay 0--08-T-804-Top R/1;Weld wire used ERN/CrFo-TA SFA 5.14.035 WSI Field WeldNtumbe.SRV-3-WOL: Davis BesseFieldWeldNumber RC-PZR-WP-91-YiZ CERTIFICATE OF COMPLIANCE t.. . .. JoaoesE. Hertz , es-ol7 that to thebest of my know edSe and belief tIe soaron*sts nudsin riserepot am Corost and thercpmsinoritnoton ;rorsplueamutactivities described above oorform to SwumooXI ofthd ASMNE Code and the Nasi/.. Boardtiopotion Cods IR miles NatiooalBoardCatificste oo/Autluas, I o. NR-69 toose T'NSRstamp..pismaNov. 6 . 2010 NR Coos/floors Hottr Wedn Services____Inc.

Dam 1/17/200 Signed OANOC Inepector

                                ~I* UCE             N
                                                    .5--O*T4.           took/erg.ooioea  2X--0 cmns/e      12  ATEb/uT is/susdt* OF INSPECTION Nfotrerl Bond   ol Boitr out Prsesue Voet/

an t dfilowe bo of c paert y tre-ot bythe jurisclction of 401+10 t eoptoyed by ihsoeruedthe repair. odiffioation or r sloos=o desan*:doth ti ris roern

                                                                                                       -Pd                             f             d ts thatto the bentof my knowledgoandrbeal this repaae,modificatior s retplaceornacti/ity has been ompltodt wooroteouswith Section X[ of*   IoASME Coto rodthe NalbsI Board pt*efios Cod 'NR' rlus By signing this co*slreatw eith-r ft odersrsno nor my employermaes mnywarsanty exprsse-dor implied, cousr/*g Ahewo do.trdt is do/s spostol       F.bo           , nitr   thedoe signed not oray employteyr shaglbe liatle i my -- r   -tfur uypesonal injury pmoproty        daoags usa loss of anyododaising frosor suesced sith this ispeaction Damo           I-lPc0             sigos.                                                       oaou~iuoa       qqc5       AH NI          oktl-

15 RFO Inservice Inspection Summary Page 186 of 238 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-1INR4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner FirstEnerse Corp. Date February 6,2008 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# 200249952 RepakOrganizatlOn P.O.No. Job Na....5

3. Work Performed by FirstEnergy NuclearOperating Co. Type Code Stamp N 5501 N. SR. 2. Oak Md-e Harbor. OH 43449 Authorization No 20 Expiration Date 07/17/10

4. Identification of Systems . Pressurizer DB-7002 (Subsys 064-04) 5 (a) Applicable Construction Code ASME III CL. 1 1968 Edition 68 Addenda Code Case No (b) Applicable Edition of Section XlUtilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N-41i 6-3 (c) Design Responsibilities FirstEnergy Corp., Welding Services Inc.(WSI), Structuial Integrity Associates Inc;

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 Pressurizer Babcock & Wilcox 620-0014-59 N-157 DB-I002 1972 Repaired Yes

7. Description of Work The existing 10 pressurizer hot le.-nozzle to surge line weld was weld overlayed by WSI.

All phyical work was performed by WSI per PO# 103571 and WSI traveler# 10357 1-TR-005 All work completed by WSI is documented on "NR-22 Report of Repairs. FirstEnergy Corp. (DB) performed a:VT-2 initial inservice leakage test. Test was 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 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 l X 11 in. (2) Information in items 1 through 6 on this report is included on each shreet, and (30 each sheet is numbered and the number of sheets is recorded at the top of this form.

15 RFO Inservice Inspection Summary Page 187 of 238 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/NuRA-Amnn ýwmrnfca, Dal-P~ofl wah A~

9. REMARKS Welding Services Inc..

CERTIFICATE OF COMPLIANCE 1, 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" star,"xpires 07/17/10 Date O2-6&-oa FENOC (flar,,aa,l~a. o~la~g~daJ Signed " C ( ,AhoIaaraamaQt~alv)

                                                                                                                          . gc.                     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 r%. 'Js5,* and state that to - the best of my knowledge and belief, this repair, modification or replacement has been completed inaccordance with Section6" 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 inany manner for any personal injury, property damage or loss of any kind arising from of connected with this inspection, Date 2_ 6f be Signed -lo* .. 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 12113/10 1 National Board Certificate of Authorization'No. 20 to use the "NR" stamp expires 07/17/10 Date FENOC Signed O.C.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 CI. of Hartfbod, 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 'VP" 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 beifer 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

15 RFO Inservice Inspection Summary Page 188 of 238 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 ~12 FORM NR-I REPORI OF REPAIR' IO NUCLEAR COMPONIFNTSAND SYSTEMS 1NN MODIFICAIION!I] NUCLEAR POWER PLANTS ORREP ACEMENCE-] e I Wortrapefna.by Welding Sevires Inc. I03571 "NR-22" 2225 SkyAandCowl, Norcross, GA 30071 2 Dser First Energy Corp. 76 S Main, Akron. OH 3 Nam, aldd- solof nlmetrpower or Davis-Besse, 5501 N. State Rte. 2, Oak Harbor, Oito 43449

                . Systm                                                                   Reactor Cooling System "RCS-501tm Wbic-RcqoirdlRtepai,MtliOaem,,1 ReIacrtmanAriitks Ideosl[oiw                                                                   cammeanio   Code                        Aodiei oName               sw NIO              No        lan. No.       Otiher Year Oath            nEao               c      CeeCIass       Ridhod1Rpl 7I          ROS               B9W      A-214               NIA            NIA              1 1972             11/11       1971       NIA       1              Repair Hot-Legto97 RCMKltZ-FW54                                                                                                      1 summer 5b. iRtymIm       Dw         tvled et Ao~Oihfet Rph-em Idesdfioion                                                                                Coon       Code Typeof     itLm   tooled ortlrced        mr1.           M4                                 i       Oti
                                                                                                                       'her.,   Year     N        e/ Md..,         Code 5aiharaNo       Nome            SN.0.         NastlRI    No. Not                            Seto        Addenda Case()                 .Co W     eldContoy        #11-12          W tI            WA                 N/A          N/A         N/A       2007    ASMEXI        95/0        N-740 ENICr e-7A                                                                                                                                   "seet11" Heat#

NXOTBOTK 5 ASMECode SemanvlaptplieubtOre.i~ i-aes olr 90 Me5 WA 7 ASMEECodeneed= XI sd Ertepairs.roededori ana or 1995 1i96 N-740. See fineIt

              &Commatý Codemd for e*. imodifd.r.n                or, rploems:                              A-SME   1.1171        . Suminer1971                               NIA-9 Dfma rsoponsibilites                                                                   FENOC Flrst Energy Nuclear Operating Co.

10 TeScordrd: hydomnon []-- [ L]ornai degepsasae [. esmsare a CodeC*a() Psi NIA

                                                                 *Pressure Test to be performed by owner, 31     epaneat work (l of pmoptlyidemled .4oOOdis.Ks)     ,      skeWers)is aeptab-o)

Hot-Leg to sorrge pipingSlnjctut Wed Overlay was perforreed in ocortdocer wth WSI Traveler 103571-TR-005 Rev. 0 which incorporates Davis Besse SAP womkorder number 200249952. This implements a one time NRC accepted repair ptan in accordance with Relief Request RR-A30 and for amend code case N-740

12. Rematrks WraseedfPeeWId0flesayQ ateeT.90-fttma aWtu105( wmeUed £IIN1~0f-A COTA 514 .030BearVNXO0OT~r CERTIFICATE OF COMPL lANCE I, James E. Hertz , ncstifytbe to tin beatofmy bmikdgo endbetiefthe statoents made in this report om Commraonddet epain.modificeatm reptaeraneat ana-rtn dn*ernbed abo coalbrmto Seo X1vf the ASMECode m*d the Neuonal Board Itspecion Code "NNRsoles National BoardCeflicate of Auodrinatio No NR-69 tI soethe 'liR stampetesra,Nov. 6 2010 NR Cersifimte HoRder ,, , Welding Services Inc.

Date 1/10/2008 Signed QOJQC Inspector RFCAEOF INSPECTION I. "irn1i' G

holdeng. valid-ammasiwon isoedby The.Notoel Board of Boiler andPr- Vevse lotaelore -d omtdifite afroapeten.y issued by the jurisdietio of E)W 0 and employed by mtPantad theiya'-t om r reacemeot

                                                    " l craud tim          p          desnehbed   t this repart                           0              a"d toneai to tr best fmy knotda.e andbelie4 this repir, modifiation or rept                  e ativiAryh.         en       ed oacordanee widh SectionXI of the ASMECode andthe NationalBoard Inspection Code 'NR"ndea By signing tts certificatte,neithir tie undersigned nor myempteye ma my                           e-rty-aved or implied, coneneting th -eork denaeibedin thisreport FPsthearom. neither the undersigaed normy empltoyrr aIt be liable i                   "nyorerefo anypersonal injury, Propertydamage or a loss ofany kind a               biee*

r or nncetet olh this inspection Doe jiop Siaead __ Cem iornes teem.Ors tA osr C oe eO5 r CIUS ccA

15 RFO Inservice Inspection Summary Page 189 of 238 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/V-R4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section X1

1. Owner FirstEnergy Corp. Date February 6, 2008 76 South Main St., Akron, OH 44308 Sheet 1 of 2 2 Plant Da-vs-Besse NucleaT Powter Station Unit #1 5501 N. SR. 2, Oak Harbor', OH 43449 Order# 200249953.

ReAPOgraqz-fl P.O.NP.,ob Ne. . 3 Work Performed by FirstEnergy Nuclear Opecrating Co. Type Code Stamp NR' 9qfl N q1? 2- Oak -nrhnr. 'TT 41419 .Authorization No. 20 Expiration Date 07/17/10 4 Identification of Systems Pressurizer DB-T002 (Subsys 064-04)

5. (a) Applicable Construction Code ASME III CL.1 1968 Edition 68 Addenda Code Case No (b) Applicable Edition of Section Xt Utilized for Repairs or Replacements 19 9.5 Edition 96 Addenda Code case N-416-3 (c) Design Responsibilities FirstEner Igy Corp., Welding Sertvices Inc.(WS!), Structural Inte*rity Associates Inc.

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 Pressurizer . Babcock & Wilcox 620-0014-59 N-157 DB-T002 1972 Repaired Yes-

7. Description of Work The existing 12" decay heat nozzle to hot leg nozzle weld was weld overlayed by WSI.

All phyical work was performed by WSI per PO# 103571 and WSI traveler# 10357 1-TR-006 All work completed by WSI is documented on "NR-32 Report of Repairs. FirstEnergy Corp. (DB) perfoimed a-V-T--2 initial inservice leakage test. Test was satisfactory.

8. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure NOP osi 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 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 1/2 X 11 in (2) Information InItems 1 through &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.

15 RFO Inservice Inspection Summary Page 190 of 238 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-1f..R-.

9. REMARKS App~b0l Mon.4,o-o,.DIU ~flr00 Aac Welding Services Inc.

CERTIFICATE OF COMPLIANCE Richard R. Cockrell , certify that the statements made inthis report are correct and therepair, 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" sta~rp-xpires 07/17/10 bate Z--aA FENOC (*04 twoasorgafrulzmn) Signed

                                                                                     "       7lspJbelzdrepr~eFmlV¢ Q.c.      . -

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 Hai tford, CT have inspected the work described inthis report on &.., U and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Sectibdh-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 11--7i " Signed-"1M.2pt. :A'),- Commissions t%&3'3,'*"." &*&Lk 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 .1 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 CI of Hartford, Cf 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 beotq 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 *__.. (or(N

                                                                                                                            - 1Joo B     (  r

15 RFO Inservice Inspection Summary Page 191 of 238 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 NPRI REPORT0f REFAIRE)- MODIFICAIONHE OR REPLACEMENT El] ~ 2~Z 10OF97CLEFAR COWpONERTSAND SYSTEMS IN NUlCLEARFOWR1~. PLAN/TS. . . . . I Wo.k rerlbrd by Welding Services Inc. 103571 "NR-32" 2225 Skyland Court, Norncoss, GA 3C071 20ao First Energy Corp. Q-) 76 S Main Akron. OH 3 Na edd Idtinicara, of nooort pW eat Davis-Besoa, 5501AN. State Rte. 2, Oak Herb", Ohio 43449

4. Syms Reactor Ceolttg System "RCS" "

5. Itt i:bi Reqied RepaioModifi.niar.,eoReýplasoee Aaireaa.

Identfona Constnoo Cod. A1tivty [N *m rti o Otlr e a/ Smdan/ Cd eed d No 1h.[benf N- I M4fg : Sena bit No N.1I*ad Jouds No O Y_~Bl Da '*" NFa Adens Sdk/sal Caa(S CateCod.Cl, eai a Nears iSsc/strItotRn RCS _ 1W /1A N/A N/A N/A 1:9:73 ASM Ut 1971 N/A IRaep/f Decay Heat n.l 1971 _D-33-GCA-4-1-FWl 5b.laer* lneatliedDulag Rnepleaeonsn Antivm___ tderifeae.d Convtuofio Cod. Typeof b toneadtdlrep"lae Md8. Mr. Raned Othe Maned Edlnoor Cod. SoReenNa NHm Se'*al sed o No Na.t Scda D i,,tir Aldend, Cle(s) c& cles wdid -0o/yV -e Ael"& WSI N/A HtA W/A N/A 2OU7 AS/ X t95E 96 N-740 12011//is arm 6 ,1M/ CodeSea/jo M apfai/ioLefueinsrvices iepecton7 11995 1998 N/A (.,*) (=rear 00*d

                                                                                                                                                                                       .0cr 7 AS-,aCode Secton 30ese fzr    rda~paxn1neodifiesfia,rops.

re -ou 1995 1N01-740, Sas finSelII 8 Coearoe Cod,ueadfor pean aodiatio.. er rptsoms:

                                                               ...                                             ASME1t. 1971               Swrmer 1971                               N/A 9 Demign  reeoneabiSi/es                                                                     FENOC First Energy NuHcearOperating Co.

10 TtmOeardn~d. bodisnaln C] X.seard M dodgsnieas. M one _t__ mi Cod.Caaebs/ N/A

                                                                     *,PressureTest to be performed by owner.
               /1 lsc-*ip1ofesarl-                       During the application of the first weld over/ay tayer,WSt inadvertently welded over an unknown d/soont oinlty                             in the

__ tan ofrpmplyi od~d/i/nalshssr/,/ uiides/d asdosidrsý0 11amlb dissimilar weld metal zone causing a breach into the interiotwail of/be piping system. The discontinuity was repaired under the guidelines of WSt's supporting traveler number 103571 -TR-021 Rev,./0S& and NCR # 08-148. The Decay Heat Structural Weld Overlay was Derformed in accordance Wth WSI Traveler 103571-TR-00 latest Rev. which incorporates Davis Besse SAP work order number 200290832. This implements a one time NRC accepted repair p/anin accordance with Reioef Reqdst RR-A30andfor amendcode Cae N1-740.

12. Remarks WPSusedfor WeldDverlay 01-08-T-804-BSoriom Rtev.It, Weld wi/n reed ERNiCrtos.7ASPA 5.14.0315 WSt Field Weld Numtber:Denny Heat-WOL: Davis Besse Field Weld Naraber DH-33A-CCA-4-1 -F.Vt 1*21lES masedfordorcenrisnoy rapoir- 08-43-S-010 RV'/aSdWrc-/dr/- .1mW/Cr-Fr-?7 SF4 5,113V'3205Seeppor-/iogNCR 08-141 and08-i8fror inorf.

CERTIFICATE OF COMpIP IANCE I. James E. HerU , ooilithra* to tde boa of my knowledgeand belie/ the s/aomon made in thisreport are Caornet andtie repair, modiboaanonar nephaeaaott iis demseibedabove coeform to SSefio 22 of the ASMECods and the NationalBaard otp .iob Cods 'W 9. rid National *owd Cedficat ofAuthaoization " NR-69 t edth.eNRstamp expio NOv.6 2010 NR Crtifimte Holddr -Weling S* s Inc. Date 1/22/20a8 Signeved ___ Q inspector C ICATE OF INSPECTION L, 1. %&s G.. LPrý .holdikg evatidoatnausiaon issued by The NatlionalBoard of/Ba/erand PressareVVesot berroninrs and cerificate ofmoropctereayissued by thelbneatona of mid ernpl/yedby impeo/od ote pe/ar,modfiorationor eplaronet dsenoobodia repor.'t "Q3* and s/atl that tothe best of my knowledgeandbelief, t1,s repair, medifioationorreplaemenr activity bha been coapt e oaieo e /doth Section Xt of the ASME Cods and the Ntional Boardtspeotion Cod 'NR' rules By signng thdisceroificate,neither dm unedsigp normy employermakes any warranty expressed or implied. naernina the nok denoribodie this report Fohe/b nonrn,neither the n-designed noemy employ." shall be Liablein asy -mor faor soy perosaol jAei-y. propertydamage orean ofany lbrdarising fiam or-c neersod rnth tho diapol/se Date isd23(6 Irgned.- Si/ V _o

15 RFO Inservice Inspection Summary Page 192 of 238 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-1fNVR4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 owner FirstEnergy Corp. rDat February 4, 2008 76~South Main St. Akron. OH 44308t Sheet 1 of 3 76 South Main SL Akron OH 44308 2, Plant Davis-Besse Nuclear Power' Station Unit #1 5501 N. SR. 2, Oak Hiarbor, OH 43449 Order# 200249954 Nev.,rOg*,rosn P.O.No..Je No., ft, 3 Work Performed by FirstEnergy Nuclear- Operating Co. Type Code Stamp NR Nam 5501 N. SR. 2. Oak Harbor, OH 43449 Authorization No 20 Expiration Date 07/17/10

4. Identification of Systems Psessuiizer Sencing Line DB-RC14A (Subsys 064-04)

5. (a) Applicable Construction Code ASME III CL. 1 t968 Edition 68 Addenda Code Case No (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N-41l6-3 (c) Design Responsibilities . FirstEnergy Corp, Welding Services Inc.(WSI), Structnral Integrity Associates Inc.

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 Pressurizer Babcock & Wilcox 620-0014-59 N-157 DB-T002 1972 Repaired Yes

7. Description of Work The existing level sensing nozzle RC14A was replaced with a new nozzle and a weld overlay added.

All phyical work was performed by WSI pet P0# 103571 and WSI traveler# 103571-TR-016-4. All work completed by WSI is documented on "NR-23" and "NR-30" Report of Repairs. Firstenergy Corp (DB) performed a VT-2 initial inservice leakage test. Test was satisfactory. 8 Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure NOP *sip 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 Blowdown Adjustments Made Using N/A (r- Medium) 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 ranrort is included on each sheet, and i30 each sheet is numbered and the number of sheets is recorded at ter ton of this torm. this recort Is included on each sheet, and (30 each sheet is numbered and the number of sheets is recorded at the ton of this form

15 RFO Inservice Inspection Summary Page 193 of 238 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 Macatnan.l Datatitht to healcle A lpptcatia

9. REMARKS Welding Service Inc NR-23 &30 report of repairs.'

CERTIFICATE OF COMPLIANCE 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" st,-1p"expires 07/17/10 Date tJ2-o0-na FENOC Signed\ 5Z 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 R. -, Ueb 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 ?4 Signed _____ _____ Commissions A-CERTIFICATE OF COMPLIANCE 1, N/A , certify that to the best of my knowledge and belief the statements made inthis 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 7/10 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, CI 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

15 RFO Inservice Inspection Summary . Page 194 of 238 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 r FORM *R.I RFPORIOF REPAIR[" MOoIFICAIION[ OR REPIACENIENI L] FO NUCLEARCOMPONENTSAND SYSTEMSIN NUCLEARPOWER PLANTS I Workp*orofd by WveldingSerices Inc. 103571 *NR-23" 2225 SkyWandCo.,t Norross. GA 30071 ___0 ___________________ir__ tst Enoery Carp, 2 0-1 76 S Main, Akron, OH 3 Neto, eddome. (deeatiao oftcdel=s po#r pln Davis-Benon, 5501 N. State Rte. 5, Oak Haibo¢. Ohio 43449 4 $Sl"n Reactor Cooling System "RCS" 5e, ltorn Whkh aqinralRepair,Modltcaiar, or RMAo Amiose ldeotdpt Wi C-.t enotCod. A.i0y N _ MA AA MNd L .1 Te rosa 3 p14 er B"w 6200 L14-59 N-i 57 N/A MA 1972 ASM 11I1 1 Repair 5b. Ir Cose-o9a, Xl .Ppa er e po166i51 no"a -Difsin 6, ~ s Ty.,..f I,= [aml.t t.Pbd M4 W& Ndm .:To3&7 FYe . Nm

ý. ode Coetn 5.-Ieol S-1 N, No Cue-s)

                 ,Temperbe"I*                                 WSI            NIA                 NIA...NA         NIA                2(o      ASMGYJ 95196              _t-83&-tr                1 Pad                "Zsee      "i A~n                                                                    ...

12 of ifis fonme'

                '"3/4Nozzle                                 -WSl        lSN-1.2,45A7,            NJA                      /A         20 I/ ASME XI           95196      N-638-1                  I

od *X]zpS¢J*

rr *1195 " t996 NJA 7 ASMEco C.& Se1.Qed iorrepadlýrmnnedf e-.-moo: - 1995 1966 N,18.-I, S-eeie 11 (_1Oo A.0-. (000.00 8 Comeoenrso Cods ned for ears ord~b'e, 7ep,0-od& ASUEIII,1560 Wsoe 158 WA 9 Daot -rnpiot*,i FENOC_Fst Energy Nuclear OpewrIngCo. ' _" 10T" eorodoold: tooosooi idnepeneLM]osnspose.' pit CodeCmoe) MIA

PressureTest to beperformed by owner It Iopin of Level Sensing Nozzle RC14A-F' repiaCement included a pressure boundary change rnm the Interior to the e)dedor tueeofpoopoeyidootnfed eddtifr. ohoa(s) orobneto(m*) aoeerapnble) of the Pmsturlz'. This change was 6 a10 posible by instating an arnbient temperaturm Temperbead inconel weld pad petforred in aco:rfdafCB with the cotrois specilied In Code Case N-638-1 as modified by Relief Request RR-A31. in conj unction with WSrs Traveler # 103571-TR-016-1-6 latest Rev. This implements a one lUmeNRC accepted reoir DlanIna=cordance with Relief Reo(est RR A31 and for amend Code Case N-638-1.

INn renoIr neorlorrneststod teenene.e~Ao.1.O *...o. t..... o Oee.M. ... ~. 0I0 .... 1 0.~

                                                                                      =rep         aY.0   meO                1:1310 -a -13 lowIio~ntII,-0.t4A MOUr n-e10 t000000ioof New Nozzle: SIN # LSN.1,2,4,6,e &7 'See suppwio                           form N-2" LSN-i Component #1 SB-166 Rotud Bar tUNS) N06690; HT. #ASS683                                       Component #2 SA-376 Pipe Type 316 Sob. 160; HT. #37680 LSN-2 Component #1 SB-168 Round Bar (UNS) N06690; HT. IAS583                                        Component #2 SA-376 Pipe Type 316 Sch. 160; HT. #37680 LSN-4 Component #1 SB-166 Round Bar (UNS) N06690; HT. #AS5683                                       Component #2 SA-376 Pipe Type 316.Sch. 160; HT. #37680 LSN-5 Component #1 SB-166 Round Bar (UNS) N06690; HT. #RS7?56                                       Component #2 SA-376 Pipe Type 316 Sch. 160; HT. #37680 LSN-8 Component #1 SB-166 Round Bar (UNS) N06690; HT. #RS7756                                       Component#2 SA-376 Pipe Type 316 Sch. 160: HT. #37680 LSN-7 Component #1 SO-166 Round Bar (UNS) N06690; HT.#RS7756                                        Component #2 SA-376 Pipe Type 316 SECh.160; HT. #37680

12. Re*ars: Pad Weld WPS; Oi-43-T-653-102M36 RIO;Weld Wre ERNiCrFe-TA SFA 5.14; ,035 "GTAW Machlile" Nozzle to Pad Weld WPS; 43-43-T-001 Rt3; Weld Wre ERNICrFe-7A SFA 5-14; 3132 "GTAW Manual" CERTIFICATE OF COMPLIANCE 1, Jazes B Hertz rerttify duat tothe bt of mlylaowlede aedbltef the stozltenw meti n this report m Cmeowl*l the repairr modfctm h ý~cm~laaitra dwcibedl above cmonf= twSection)U of the ASME Code end heinlBm'~riiaeo~~zto NR-69 to=toq.mpx*sNov. 9 2WI0 N gCert~ffimelolde" ,,* ek f Services Iric. -

Daie 111612Q001Si4* '*.( '- QA/QC lnspector

                                                                                    -ýCERTIFICATE OF INSPECTION 1Ih.i                                                   ýM                  med by rhn NwotInl wiaidoenon                        Bond of    Bode.need   Prea Vesnd topeome and eftsiate oftoopaeey mire by thn jauiitodin of                                                                      neod eoeployd   by W6*'15 CCo                                                                                        va.ý iupected the repair.Oooddiftio ne-eephtotentdmnbnd1this r-epan-                                                               and sll" ImsO entte   h beg of my aenoowlodg       and1,li64 ths Topai,en*edadon or repl~ mt artivity haobeer,                      p         ne so-ordýooewith SecOtonXI of tn ASME Code and dteNaiQW Board tnmpeotion                 Co&INl" mTle By signing thil Oet'fi:el, neohbetheLudmsi*en*t.               s y eredoper nekhe, e e nty.       --'y, us         or indaliee, orreeming the workdescribed ie tbis repet. Fhlne-ore aneihfethe W-doeig..doneroy -ployor obtI be liable in ary mar                            fbo anyypeeeoat inir*-y Ppeprty d          -oareralose ofanyki.        isilne fi   .o-o       td Mthiniop       -p--                                ,,"

Date ~~fz~if. 7y)n CIa~~eIBCO3 ~A~~~o

15 RFO Inservice Inspection Summary Page 195 of 238 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Uniit #1, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 0 ,s FOWNRI I*URI OFRlEPATR[ MOyTACATIONCE O R.E P3ACM9pLANT TO. CLEARCOMPONENTS ANDSYSTEjSI3 N NUCLEAR p0,V4ERLNNCS iro1.,oi, Widig 97oc~o o.103571 "NR-302 ... "~z-.:o* 2225Skyi0d Coo,.50,.00, GA 30071 10-no FirmEnergy Corp. 76SN1rL Ako.n,OK 3 It-o96 Tdroarofad6st-re34 Da0v1so-9~.9301N. StateRta.2.09100,533r.ON. 43449 0s, R6 R-t00 Coafi96 eyatee. 11C5

5. hoAeboq66Maoli3006o3 iof0Ai1oa ____________

1-9101 lreai MS. N_ W.1&,W566 14. I 1 100 1-Io

                                                                                                      -I Ioo--      I ME
                                                                                                                             * '~ I6AM499 C-0 60        I      C01--d apifOý I
                                         'IVW,1                               WA            ý A1                _07 WAa         ý             ý     /

1119AA a.2 Kah 3610 WA IV, 1_1 Cr91t bee fltali n 12 sanOllo,.PS/0 lWA 9393 WA 197 2 3 1393 1996WA 7 Sfll9 0o1ojr.,toE0 qtO o 0 A 6.I1711 &a-05 1913 W/A

                                                                                                    ...      =_            -     -

N T~d06'P-W001dao

                                                              =P       ar Te to ]QlirforFe ed                                    __       ,'a   codoCed,1)

PressureTest to beperformed byoweer 11D~tiod'bor Atthe time of remo~ngfie exdothrg tLenl SeotsiogNozfeo 3939renmovd 6, Sinal bore 9e We00.TinS mpreltlW1 address fte reattactrro,6 of dese Hots W 8o 1 nwilfoltoothe easionog viel u~tb.tot field4 are,Idnife30409960,691 art m-unfadeeso N-5data repoit All994msWO abcordance with ffwordrul spcified! i Code Case N6.38-1 es modifiedby Refid Request RR-A3I. in ortinctim wit1 ro me in60198 WV~fsTraelerc V 103571-TR-016.-8.faotetRev. Tris implemrentsa63 Wonee NRC accepted repair pltien aocEordaoreold, Relief RequestRR A31 end for amend Code CueON-638-9. Field Weld fdotrber Modi~e& (RC-14-AO99.40 & 18B (RC-14.,6) FW. 6 & 72Z (C1C)9.16&70 (RC-14-fl) FIN. 14B & 73 (RC-14.E) 99.22 &72 (RC-14-F)FIN. 2&70_____________________ ______

                                 - S3*16ftoe PiPf WPS; 098-t-T-M1 RM19           Weld Wie ER306L SFA, S9; 3(32' "GTAWMeonod1 CERI"rWCALTEOF CONaIE'IANCE L                 ow   F009.60 PA              cutily 911to thebeoafrooIeoe4od     0 W0 betialte earoope i.n9     66.opoV C-       aad 0.opaft, .odiliotio      pla-amiria.0663, 1609,0 91ofba Woot             Secto 2a06035161966   Code  cad
                          -900060. Board   68d. 00MVod=NUrode Notioi6!0BoarCoO9096     ofAhoflrot03NO  M,.0                                         91-             0309         0.6 NfetE       2010 NR Cr96000,. Hold.                AC.                                     do               t03690..-

D~o. imm si 96.1hseco 13090 do~foow9~e~odby

                                                                                        ~ ~~~~~~~a holdcog~

00916009 rhajorouikhortof srl.o1 01 VW149'1 Co~~d an1Preasroe Vved aadmployd by iotrooodMeorapao. roodroafiroorroyaoor mt odeodbod i ft rpon saooatoh

d. o.t described 696911W,.0. Fotre0.~0.MW- 1h. -de.god noro, np.,.1)01911 bo W1.01i.*aes- for aaop-eeralhury. Wp.Wor doroOor. -of anyUWolohrno zi 04oihtsnapaoopreO

okja4(o018 0 _S? Coooorep13dA~ AS

15 RFO Inservice Inspection Summary Page 196 of 238 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-.kR-4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner FirstEnergy Corp. nDat February 4, 2008 Name 76 South Main St.. Akron, OH 44308 Sheet 1 of 3 76 South Main St Akron OH 44308 2 Plant Davis-Besse Nuclear Power Station Unit #1

                       ~01 N 5Th 2 flak TThrhnr OfT 434411                                                       Order# 200249955 3   Work Performed by        FirstEnergy Nuclear Operating Co.                                      Type Code Stamp              NR N5 .o 5501 N. SR. 21 Oak Harbor, OH 43449                                                   Authorization No            20 Expiration. Date          07/17/10

4. Identification of Systems Pt essurizes Sencing Line DB-RC14B (Subsys 064-04)

5. (a) Applicable Construction Code ASME III CL. 1 1968 Edition 68 Addenda Code Case No (b) Applicable Edition of Section XAUtilized for Repairs or Replacements 19

95 Edition . 96. Addenda Code Case N-416-3 (c) Design Responslbllltles FirstEnergy Corp, WeldingServices Inc.(WSI), Souctural Integuity Associates Inc.

6. Identification of Comoonents Repaired or Renlaced and Renlacement Components Id.. niic

                                                  .. to...  . C... m o......e t    R. par e  o..
                                                                                             . Replaced
                                                                                                  . .r         an    ..  ................         ........

Manufacturer's National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No Built Replacad or Code, Replacement Stamped Pressurizer Babcock & Wilcox 620-0014-59 N-157 DB-T002 1972 Repaired Yes

7. Description of Work The existing level sensing nozzle RC 14B was replaced with a new nozzle and a weld overlay added.

All phyical work was performed by WSI per PO# 103571 and WSI traveler # 103571-TR-016-1. All work completed by WSI is documented on "NR-23" and "NR-30" Repoit of Repairs. Firstenergy Corp (DB) performed a VT-2 initial inservice leakage test. Test was satisfactory. 8 Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure NOP psi Test Temperature N T 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 1/2/2 X 11 in (2) Information in items 1 through 6 on this reoort is included on each sheet, and (30 each sheet is numbered and the number of sheets is recorded at the too of this form.

15 RFO Inservice Inspection Summary Page 197 of 238 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/?WVR-+

9. REMARKS Welding Service Inc NR-23 & 30 report of repairs.

CERTIFICATE OF COMPLIANCE I, Richard R. Cockrell , certify that the statements made in this report are correct and the repair, modifibation, 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" sta,, xpires 07/17/10 Date 62 .- D 1 -Dg FENOC 01rep~ay (naillo ogaitnt Signed (..AhoIz~ ,c P ,ab ) 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 CI of Hanford, CT have inspected the work described in this report on C-I5. -1, 3,OV 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. Signed t ,.n~l 4 Commissions ,ql. . "" "A - Date 11._ 108_ ______________________C16LC U Thl-W*10 (NI~aiPdka o d a(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 _ _ _. (nameol,.pak*o~gin.1c5 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, C' 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 bev.*t 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 p.0015 ~~(Nanl o015

15 RFO Inservice Inspection Summary Page 198 of 238 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 POEM NR-1 MEORI OF REPAI7 10 NUCLEAR COMPONENPTS hiOOT1'TckToNE] AND SYSTEMS IN NUCLEARPOWER PLANTS ORuRPtAcEmE/o [ cJ ;, 1- 3 SWodperford by Wefl ngServices Inc. - 103571 'NR-23 "

                                                                                            -  (_

2225 Skylavd Court, NoZoss, GA 30071 00.. .-. 2 Oe,. P80s Brgy Corp. 76 S Mail, Akron, OH 3 NEaoe, add- Teak*fiaco of* eploo, "Davis-Besse.Oa.a. 5501 N. State Rte. 2, Oak Harbor, Ohio 43449 4 S-m Reactor Cooling System "RC5-

5. 5I0teWhich dRl*/.ored ap, Modoifioado, "R eptfca-fl AOVibon Mattawancoooua_

                                                                    !ditreod       f&

Code4.. Z iIII AalTZ Cod ,C eol dROI . No~Cyon NMora ~ ~N ...~o~ Ado~l~d 0.001, Best 12G-0014-591 N-157 NA WA 197-2 AXSMoERII EE 1 1~ Div.i tol1 5b.IS ocusmOed DeoriRlaeeRnenteAcoiviime 1Tprof heabntWret0 5 f Ms HdB&N O'a S... adid Code CodeCboe 5artarox, Nuar Ww~~o. No. DlAdnaC0 IT-erbeor0 WS WA5 A I WA NfN 07A-T-230XlIt5S/96 NfT I 66l Pad 'tee TmIE.& 12oftN!.fGW~l 314"P 50zd -,,. A A 207Z_ AE m l

6. A516 CodesactioneS Sypplialefa in-vcmoenbpeuoooo

7. 6351 Cod. eeiXd -d hrepaus. o-doe-ao aroep*oeee N400-1, See Tee 11 ASE,1968 1596 N/A 9 Desip eneb/ /g Co.

PENOC First EMWg Nldud-earpeati 10,Tem otd5c5d: hyd-oo~ Ej Po~ec ~laro-- opre-areE ve-oro po Col/c.,O)l NIA

                                                                   *PrecureTast to beperforined by owner It      eipda oonfo-k           Level Sensing Nozzle RC14A-F replacement                   included a pressure bounday doiange           from Theinterior to the exteoor (tmo prpely idmt*ioieddiboaWlTe)         =r etlle)bisaoepble1 oflite Pressurizer. This change was made possible by lnstlSi/n an ambient temperature, Temperboad incorel weld pad performed in accordance with the contooels sproead      in Code CasaN-&29-as modifid by Relif tRerrcest RR-A31. In ozolunoflEP vdE, wSrn TroVelort 103571-TR-016-1.6 latest Rev. This Implements a one UimeNRC eae-rled repair plan in accordanoe with Relief Request RR A31 and for amend Code Case N-638-1.

The repairwork OzersTOt of4end onepadweL- oneJ7prep. to aNtach the noze tothe pad/foreach location, RC1dAff/ F NewNozzle: SIN9 LSN-l .24,5,6 & 7 Soee supporting formN-?- LSN-I Component #1 SB-166 Round Bar (UNS) NOOSE; Kf. #ASS683 Component #2 SA-376 Pipe Type 316 Schb160; Hf.537680 LSN-2 Component#1 SB-166 Round Bar (UNS) K06690; HT. #AS5683 Compenent #2 SA-376 Pipe Type 316 SCh.160; HT. #37680 LSN-.4 Coneeroseet#1 RB-leO RoundBar IUN00P406590: 1ff 5AS5653 Comocoent #2 SA-376PipeTYPO 316SCh.150; NT. 537600 LSN4 Component #1 SB-166 Round Bar (UNS1K06690; HT. SctL 100; KT. 937680 LSN-SComponenrt #1 SB-1a RoundBar(UNS)N0600; HT.#RS,75. Component #2 SA-378 PipeType 316 Scl. 160;HT. 537600 LSN-7 Component #1 SB166 Round Bar LUNS) N06690; HT.#RS7756 Componen 2 SA-%376 Pipe Type 316 SOl. 160; HT. #37680 LSN-7ComiponentO 51 S0-166 RourndBlar(UNS)N400950;HT,#RS7756 Comeponent #2 SA-376 Pipe TYPe3IB Sorl.160;NT. #37680 12 Renarks: Pad Weld WPS; 01-43-T-803-102836 R/0;Weld Wire ERNICre-7A SFA 5.14; .035 "GTAW Machine" Nozzle to Pad Weld WPS: 43-43-T.001 R/3; Weld Wire ERMCrFe-7A SFA5.14; 3SS' "GTAW Manuatr CERTIFICATE OF COMPLIANCE 1, James E. Hertz , conifylth to the ba dfay knowtl*ad belief the stbtementsme" In thhLiron are Ceoroeed Tb. ON/or,eeofiaiflim or rap/areneeoe actbiviiesdoeeikd oboecIon ofoes 00.002 iu( f TheASTOICode -0 the Notional Board leoprodtooCod* ot.io Naional Board Cootift of AMoh NR-69 tos eNtR noop.eepires Non. 6 2010 NRCreoite H~old.eWl/r evcsIc Date 1/16/2060 Sipoo.t OAQR1C I1specToW

                                                                                        *FICATE OF INSPEMCTON I.   "Th*t1        j"    1        ,b odimra veid oaeaoomn leereby Tho 1a.0ousdBoardoefoEe/N                      rd Proesos mVed bopoononand certificoteof cornpoetenyeaod by doejo~diodoe of                                O       0't i Orod4                   employed by inspected ts repo., modificationor replaceeroat dowribed in this best of mykInowlldgoand    belief, s

report , t/isepaplo modification ot replacoooetoctivity hoe been o Loepto/od

                                                                                                                                           *oordoa With Section XI of the ASME Code ad the NationalBoard InmpecisACo&l 1(R roles By 3igncegthis ccTrifi-cot,*oeiber h* uondeigned wear       my employersookes   any vooareep eprood or irpliod, coeenose the work deocibed in this report Folthbeesorei. e donthe    tedmeignod nors" om=pb*T*" aeblbe liablob/e      ieao*oeofto an eronalmoinjory. propertydonoeco       or, too. eonyhtad.riso rroaxcrcanoso ditnom       i    xiok0/opectoona..

Doe ___ _ gred crononsr i OOSu- 2 C'L V^t

15 RFO Inservice Inspection Summary Page 199 of 238 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~A~

FORMNR-I REPORT OFREPAR[ MODIFICARIONE] OR ,R.ACE*i*IE[-] To NUCLEAR COMPONENTS AND SYSTEMSN*NUCLEAR POWERPLANTS I 0 ponoelyWelding Servicesno- 1R2571 '54R,3/i 2225S/eS/on/ CoA 0000,0. GA 210071 P~~onA PINEneOrgyCorp. I N_ mn/3 eee P0001WN DrAiN-N SO1 N. Sta/NRte.Z OaklHa/Erta0hin 4344/i 550 P n~~~oon OOnOCoo1.q Syotnnl 'RCSC 5n.100Si/RE/ ied.MSoEi-Rp Nnenn am W&.ROZ W& LSN-i2, 14 ASEI IN / I Np/ Sb1-0 hot/il Eunno 9 lenNSR nb b/N 140100,0000 C.-on/N Tn/i NWA P A NI WA I RS Aq 51110 W 2 eels/N ~ ~ ~ ~ 1 Ri/ Ol 3 OWO 197 ___________ 7 001 ninlnR0 ROOO O/50iI I/nnn 1905 1909 NA M AllelE1. 1071 /iený E19 W/A FEN00 Flint E-OO NRoraeo e/ISb- C. 5] /iPeo- r-- P- ____ p/i Cnl*, PEA

                                                              * .pressure Test/to beperformed byowner 1 0eN/orend               At the Re/Nof removing thNeOihstngLoel Sensing NozNlwWSI reenoved Sea. SmaBl bore pipe /On".This report OR addraes the reatfachmet of tie/i ines. WS/I willfollow the eodst* Niel weld numbers fhit nm identified on the oig/nal man ufactLres N-5 data report.

Allwork was pfon/nd inac/ordan/I with the ControlsapNcfied in Code Case N-638/ 1 on m- ,odedby Refoe Re*oest RR-A31. in RnjIunclion wilh wsrs Traoel"er 103571-TR'-016t-1, la/est Revn 11/is /mrlemoenten oe UmeNRC eczenisd reair oal in a-onrdance wit Relief Reunst RR A31 and re"annend Code Case N-638-1. FiN//iWeld Nuebonn Mod/i/ed: (RC-I 4-A)FW. 40& I BE (RC-I4-8) FW. B & 72 (RC-14-0i FW 148 & 7/i (RC-I 4-D) FW. 14B &'73 (RC-I4-E) FW. 22 &72 (RC-I-F) FW. 2& 70 BeSml Bore Mahin SYPS:i/B-ii-T-O0l RA:;WeldiV/ilr ER3/i8L SFA5.9: R/32ý GTAW Moonut' CERTIFICATE 0OFCOMPIPANCE L Jo/en.E.54rf nefihot W/iteeboo fnooN/olo/ontne/ib~f/ieoleeeeO no/="in th/isre/iNofto

                         /iTma       "~/no Oneirimeo/lon~i  CoepL  NR             vii darbdab         oeil       eoo MoteASECo NOCe//S..ct,tin//ion           o~o~   (nN.Ze                               Sp to,      i/no1         pinos N-
                                                                              ýS VA/NIýZiQ!TEOF       INSPECTION 5

agnpoloR, lopw, en Sodinoaho moplenon/ dawbed 1,dei mpon/IV 100/of mnkowtedg n on/ bn/loS. tisempai. modifnoonnxor epla-~en en//ily bee oo 00/0000 p.R M Ap/o/ Oeont- f/ thbe ASMiE Co/i. no/ide Nm10.1oe/i /ne Ipe/iomCode 'NRen/- By egnlo~odi, _iion/ooone/ituhoon/be ;. I/Ny .4r/ ON*IyO A.E/op/n/Nl neoend . 00010ie, oronenn ft -nkde.nd //eplz. fii ned.n enon/goon FnnoPneheennen.6f .- OREO yn

                                                                                                .. pS    4ob. 1inlom  toNnon/Ne/ for D_        M"COKI~'tirw

15 RFO Inservice Inspection Summary Page 200 of 238 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-V-4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI

1. Owner FirstEnergy Corp. Date February 4, 2008 76 South Main St.. Akron. OH 44308 Sheet 1 of 3

2. Plant Davis-Besse Nuclear Power Station Unit #1 N-e 5501 N. SR. 2, Oak Harbor, OH 43449 Order# 200249956

                                                                                                                     ,          amln ru. m.. Oeft., Ctc.

qwp~r~ 3 Work Performed by FhstEnergy Nuclear Operating Co. F Type Code Stamp Ng 5501 N. SR. 2. Oak Harbor, OH 43449 Authorization No 20 Expiration Date. 07/17/10

4. Identification of Systems Psessusizer Sencing Line DB-RC14C . (Subsys 064-04)

5. (a) Applicable Construction Code ASME III CL1 . 1968 Edition 68 Addenda Code Case No (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements 19 95 _ Edition 96 Addenda Code Case N-41(6-3 (c) Design Responsibilities FirstEnergy Corp; Welding Services Inc.(WSI), Structural Integrity Associates Inc.

6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identificationl Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No Jurisdictional No Built Replaced or Code Replacement Stamped Pressurizer Babcock & Wilcox 620-0014-59 N-157 DB-T0'2 1972 Repaired Yes

7. Description of Work The existing level sensing nozzle RC14C was replaced with anew nozzle and a weld Overlay added.

All phyical wotk was performed by WSI per P04 103571 and WSI traveler # 103571-TR-016-6. All work completed by WSI is documented on "NR-23" and "NR-30" Report of Repairs. Firstenergy Corp (DB) performed a VT-2 initial inservice leakage test. Test was satisfactosy. 8 Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure NOP !asi Test Temperature NQI '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 Y2X 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 too of this form.

15 RFO Inservice Inspection Summary Page 201 of 238 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-0070-5 FORM NIS-2/NR-1/NYR-,          .          -

Appcý,b Mwo -fn, D-mRepotm We bAmbe

9. REMARKS Welding Service Inc NR-23 &30 report of repairs.

CERTIFICATE OF COMPLIANCE I Richard R. Cockrell cer tify 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" stam pires 07/17/10 Date -0,1-O

                     -Z      8                          FENOC                  Signed              .                                         Q.C.

CERTIFICATE OF INSERVICE INSPECTION T, 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 Ci of Hartford, CT have inspected the work described in this report on f:1. ,,ý and state that to the best of my knowledge and belief, thisrepair, modification orreplacement 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 a-?b% Signed _T____________ Commissions .

                                                                   .'                                                 timfldbmi fl  andne)}

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 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 bet. 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 ._"_. ... (be~O,) (Nun O* Mmsee Seer,*m ) .

15 RFO Inservice Inspection Summary Page 202 of 238 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 Ps :2LA3 POEM MR- REPORT OP R OPAIR[SR. MODIS3CAQNUEA ORREP[ApEMEP/Ifl TO NUCLEARCOMPONENTSAND)SYSILMSIN NU1CLEARO POWERPLANTS I ~W.Uosten/by Welding Services Inc. W03571 'NR.23' 2225Skýao CrtlNorss, GA 30071 2 Ow-n _________s,______ FiLst On Cr. 76$8Main.Akron,OH 3 N-o ed&ooWrfcaolod.4 p Pnnt.I10 ODol5-Besse 5501N.910.1Rte.2,OakIVoW, ONO11 43449 4Sry ReactorCoolingSysterm "RCS' ____ tdeo/ficsto, CofiorrsoCod Anoo NT& /No Nat BR No Jot/sdNo Me,5 YeneBa Sea/W/ " Cf Codie a esporMW PO..ooo pB&nror6W 620-001459l .-167 W/A INWA 1972 AME 1968 1/ Repair 5b.h- IrsoflotD-3kooLstsrArdo~en T ypeof . oso h.a/edoweep/wed M0 M1 No. en vm Y No0~ I e d No C--(.ro Teoperboad__ _ _ ANA N/ WA 200ASdI Pad Soel/e i NA 1 A NA 34" No21 i Jfti WS1 L89.1,2_,4.5.,e,7 ./A -.A A XI wa1 ic A 4CO//C lS 1,/or 3.pphbobts thein-sac-nsSeperin 1!6 195 N/A 7 A&%M2 Cedeo/t~ 06.01

                                             - Floo0.,w enitiotions,.ornposom                                         ISO5                  1996                     N.3-1,Seoe  IelIl a Coooeooo/entCtde     o        tops/orotod/Ost..oro etvhloenoe                                'ASMEML1966              oenenoerl68                        W/A 9 Sen/gtoempaoextt/o                                                                         P614CC     FosS  EneoWmudNaro  Oneratbra Co.

ISto-r_ thoste p CodeC-0o) N/A

                                                                      *PressureTast to beperforoeed by owner
                 /5 nero/penno/.0     -               5.ve Sen/sing    Nozzle SC V.A-F replacemnent             insu//ed a presscre boundary ch~angefrom tire SIrefiorto Sihe    extedOt
                 .r UW "Iesw-               I.. cnarni's -    -

ssore

                                                                               /56       1-t, Isikanh         oso ntteis atr        loenetuse Toor50.,toad inrtewl weld oacl peelorned Inaccordance with the controls soecified InCode Case N-638-1 as modified by Relief Request RR-A31,in coJuencon wilh WSI's Traveter # 103571-TR-016-1-6 latest Rev. This Implements a one lime NRC accepted repair plan in accordance wivt ReobelRequest RR A31 and for amend Code CaSe N-638-1.

The repair work consited of one pad weld, and one J-prep. to attach the nozzle to the pad for each location, RCI4A thru F New Nozzl: S/N # LsN-1,2,4,5,6 & 7 "See supporling form N-2" LSN-1 Component #1 SB-166 Round Bar (UNS) N06890; HT. #AS5683 Componert #2 SA-378 Pipe Type 316 Sch. 1608.HT. #37680 I CoLrer'..mn0.",ae,o al -nelion Ogoil Ror. rtl*' IM~t,.J005/'I"I *Ato /i',_rsen enot dOS A-78 P/noTerr 16 Sdlr. 160: HT. #37866 LSN-4 Comporent#1 SB-166 Round Bar (UNS) N06690; HT. #ASS683 Component #2 SA-376 Pipe Type 316-Sch. 160; HT. 937680 LSN-5 Component #1 SB-166 Round Bar (JNS) N06690; HT. #RS7756 Component #2 SA-376 PipeType 31 Sch. 160;HT. #37680 LSN-0 Component#1 SB-106 Round Bar (UNS) N06690; HT. #RS7756 Component #2 SA-376 Pipe Type 316 Sch. 160e: T. #37880 LSN-7 Component #1 S-166 Round Bar (UNS) N06890; HT. #RS7756 Component #2 SA-376 Pipe Type 316 Sch. 160; HT. #37680 12.Remarks: Pad Weld WPS; 01-43-T-603-102838 R/0 Weld Wre ERNjCe--e-7A SFA 5.14; .035 "GTAW Machoine' Nozzle to Pad Weld WPS; 43-43-T-001 R13;Weld Wire ERNiCrFe-7A SFA 5.14; 3132" "GTAW Manuar CERTIFICATE OF COMPLIANCE I Janes I. Herlz , ctift that w the bot ofoy knoowled andbelif rt/ staentenots o ade in hisrepor ose Cored woddenrewr. noddtoietm or rnpl.ceeoo te-toie dor/oibedabort confoem to Seet/on)a of//e ASME Code mid te N.lEmeleBoard Inspection, C.&/ 'me/e. NatioQd Bonrd Certficrto of . NR-69 tota, the eNSstap expirest Nnv. 6 2010 NE Ct0ortiw Ho/d. WoNta Soe.seYIr.* Bae 1/161Z.n8 Signed OPlCC cor StTIFICATE OF INSPECTION L ~5A% C.(-M holdi.Sngs i i/tese byTvNhe1/oitB=4i ofdC/len W.Peston Yowl tospetrtsooonfr/noeptoyoebttt~dern _ ta C*_____ mloyd by inter thedtrepnsi.coodofot/oen sorbreoroota dtenibedeinthis repent 0S1 o 60/t e e bentof sty lor-iedge sodbde/inthinrepair, morod/cotinonorsop/tene pecteity hasbweoenp/;;M jobroedanr, wide Setint/S of thoASME C.od, od wNotoonslBotdtonpsenionCodeN/'ue/e t& work deso/ibod in this repot Pou eo, aneitherthe w//tdn/rtd oor my mploer shall be libe in try tmteorrfor eroyp-erotl injiay peopentydmawoewe lossOf msy*id riins b o ml withthis inpertior-00o ~ ~ ýý - ý2~C~ e=nd~W'O Csorosoooont ttaoese.O/OO.Osoocomb&05

15 RFO Inservice Inspection Summary Page 203 of 238 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
                                                                                                                                                                             .P)

F - TO 100 CE-ok TONUC[5AO 90or 0AED COM.IONFEMANDC SIONlEM SYSTEMS MO$I OD INN/UCLErAR P1609 P6 O*SPNCACESWpNI LANTS E I wor61/9*0b7 WeldingSo0ces 910. 103571 9NR30" 2225 SkyloodCo=ot 1/01/oo.1 CA 30071 to- First ErmrgyCorp. 76 S Mai, AkIrn, Ott 6 4 211O. 9n 90.Idod po[*pl' 0111Dr is-liesSe. 5501 N.State Eta-. , Oak Ha54 r,Ohio 42449 y.$0 R.Cto" Comung syste6 =RCS' 5, t= V6ke Rv0w6Rgl1r, 5i0406s19 060W6A0/.0i I 'U5" 1 ... SN-. 4.5.6.7 NA A A 200 ASMEMI I/9 NWA I Repa0 5,.b-650 164k160691RepU0l60o 045*6 169. N /A 1CA NI/A ~ i 19711* N/A 2. 0011Boo16/N hNA IJ N/A iAl/A 197N/ 7 A1501166&506195lorb0 , 0* 64.&00. 06619166o 1G955 1ins WA

                                                                                                    .;;71."               .=1       I.                       1.6WA 19 00000pI960no             *.~      0w.46.N                                       55/919591
                                                                                                        =                  10,617        C.

19 I0 boo-Ot P.. .**,e0Tesato beperfortu~dby otoner. I 0od1 = At 91 ti1e of tre101g ow9e Level Sensirg Nozz0ee WSJ removed1 e1 . Smal0 bofe pipe 9W10s. 110 1106 01 addm186the ret0t0ad n9 of Miaseline. NSI 1 the9 WS1 follow 9,1fieldweld nmbers 9t1t are Identified on 9s olifnrli 1o9t9ctunresN-5 data report All*mrk wm1performed in 091o04an00 v the coml*6s990010.111n Code Cane N-638-1 a9 9111 by Reif Request RR-A31, Incon6urnon wiN wro Travelerif 10;3571.1"R-016 LatestR.e=,"Tifsimole~nwta a or lirm NRC aceas repair I* in amordartm with Relief Reguest RR A31

                 .Wdfor anwW Code Case N-V39-1.

(RC-14-.A 1*W.40 & 18B (RC-14,B) FW. 6 & 72 (RC-14-0) FW. 140 &73 (RC-14-91 FW. 22 & 72 (RC-14-F)PW.2&70-

12. Remarks:

Smal 9El Pilling WPS; 59-09-T-001R1i: Weld WiMeER30BL SFA 5.9; 3132 WTAWManuar CERTWPICATEOF COMPLIANCE "L Janic E.14009 , 1h9e tily fd W theb /ofoV Od 9. 4 id , 0ef t9n d 66906 p 1im theNclwIa 966.4Wpecien Code-WI90-16

                            .Nit0oe0/

B9d Cv6040tio f A ' " 1R4J9 Wall .t61NR-15699 o, 9.0..e 2010 NRCaet:ific HoW0 w/4li 5d-eo I-Dale 1=20-2006 Or d-\-N * -- QQCC.._6p0 -1 r IL oe MRTlS(CATE OF INSPECTIION 5 -~5V6.B~9

                                                                   .9090.614
                                                                         '4 6.111419666 6

000190 121/6006906..019 4100166106..00 7 4 SactiooV d d.92590 Cod.andd. N1/6410.6411lewd.40 Code 1W 64.. 00 ___[F .. 0146 t4l A

15 RFO Inservice Inspection Summary Page 204 of 238 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- 4 OWNER'S REPORT FOR REPAIRS.OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI I Owner FirstEnergy Cotp. Data February 4,2008 7~ Smith Main N...ArnO 40 Sheet 1 of 3 76 Soutb Main St. Akmn OH 44308 2, Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, OH 43449 Order# 200249957 3 Work Performed by FirstEnesay Nuclear Operating Co. Type Code Stamp N 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No 20 Expiration Date 07/17/10 4 Identification of Systems Pressurizer Sencing Line DB-RC14D (Subsys 064-04)

5. (a) Applicable Construction Code ASME m CL. 1 1968 Edition 68 Addenda Code Case No (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N-416-3 (c) Design Responsibilities FirstEnergy Corp, Welding Services Inc.(WSI), Structural Integrity Associates Inc.

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 Pressurizer Babcock & ,Wilcox 620-0014-59 N-157 DB-T002 1972 Repaired Yes

7. Description of Work The existing level sensing nozzle RCI4D was replaced with a new nozzle and a weld overlay added.

All phyical work was performed by WSI per PO# 103571 and WSI traveler # 103571-TR-016-3. All work completed by WSI is documented on "NR-23" and "NR-30" Report of Repairs. Firstenergy Corp (DB) performed a VT-2 initial inset vice leakage test. Test was 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 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 1hX 11 in (2) Information in items 1 ttrough 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.

15 RFO Inservice Inspection Summary Page 205 of 238 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-R-1

9. REMARKS Welding Service Inc NR-23 & 30 report of repairs.

CERTIFICATE OF COMPLIANCE RichaTd P. 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 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" st"'rTexpires 07/17110 Date 02.-'Ot-Di FENOC Signed 0 Q.C. 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 Hartford, CI have inspected the work described in this report on F0e6- r. tB 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..

                                                                                                                                              -  o

(-. U.W" 0*~ Date -I oj9, Signed ~i~~ Commissions LQ9! -1pid W A es-CERTIFICATE OF COMPUANCE 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 'Ell 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, CI 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 berf"' liable in any manner for any personal injury, property damage or loss of any kind arising from or connected with this inspection Date Signed Com missions (1ýr) CJUMýA_ li,,d -.- ),

                                                                                                                  .M Jdwcli-   d .. ))

15 RFO Inservice Inspection Summary Page 206 of 238 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 EPAMI-r MOOI.CA1oN[__ OR R ,LACEMENT'" G 2-q.

                            .TO                                NUCLEAR        COMPONENTS          ANDSYSTEMS          INNUCLEAR       POWERPLANTS I Workperforled     by                                              Wed" Services          Irr-                                                          103571         "NR-23' 2225 SkylladCourt,Norcross, GA 30071 2.0-                                                                                         First Energy Corp.

W-) 76 SMal.~ Ai'or. ON 3 Ne, .addIrcmuwd otoroe1 r pbt Davts-Besse. 5501N.State Rte.2. Oak Harbof, Ohio 43449

4. Syote Reactor Coolinlg System "RCS"

5. fftrs "-t Rd.p., r or.

Mod. .ORW-p-toor A=eaioros tdm~~~fioaC .. t.to fee Code oey No. irob No. "YooE M W CodC. Rp.al Ma )aOploa r It h No Neeoee~ Soa NorgaO Addoda Cow*) t r B&W f 14-591 1157 I WA ! NN AA 72 ASMEI 19 1W AI IpI Sb Iwo oe _tot =dr 5b. eurms b..W Dnl Re,'jp.ouan~ A.,,W IdentifieiooC..U Codb 51iteo No Nv. NO1T54. N.,*NO B Sooer) *a4,or Ce) C.ode&CI soot N. N. Add-, Temperbead NA NIA 2007 ASMEXI 5 Pad It1 Isee 1z or I N/A 2 7MIX- 9or

                     /4d                        Nozl I                    t.

S12.4,5.6. -A -WA- NIWW -A 719 1995 low0

                                                                                                                                                                             ~ SeetOne111
                                                                                                                                                                         ~ N-638-T, 7ASMEC.&ooationtazod                                  lrov.
                                                                       -ph-aoo I-                   ,~W-00.           .        -.

ICoswo Co.&rod faorpqoo..moffod.aioo. orrqtorvor ASMEtL1095 sinnrirert68 WSA 5-.)) t- O5

9. Daito Viaoa P03400First Eneru Nuclear OtarafinoCo.

100Tvý ooodrtevd b~oe-rd En Vftlror C dpveo V pd 00C.d(,)y NIA

                                                                 *PrmtureTat to be performed by owner.e II Ovoipeoofvvok        LavelSensingNozzle RCT4A-Freptaoernent hiduded a pressure boundary changiefrom theItotetlorto fthepdenor (re f popeh caifd          Mi~t.WS~ed-0et . okeabivo. dokprb)*

of the Pressurizer. This change was madeerissibiolv, instaingrv antornilerrl terenrahMtrr Temom,netradInconeelweld pad pereotoned in accrdance with fte couflois speciied in Code Case N-928-1 as modified by Relief Request RR-A31. In conjunction with WSrs Traveleri# 103571-TR-0t6-1-6 latest Rev. This Implerents a one timeNRC accepted rYepab plan in accordance with Rel Request RR A31 and for antend Code Case N-638-1. The repair work consisted of one pad weld,'and ott J-prep. to atach fte nozzle tothe padfor eCachtoRI* , RCI 4A thi F New Noze: SIN# LSN-i.2.4,5.6 & 7 'See supporting form N-2' t.SH-1 Component #1 S8_16e Round Ber(UNS) N06eMf.HT. #ASSM8 Component #2 SA-376P"p Type 318Sch-160;MY.#V5850 ISN-2 Component #1 S84-16 RoundBar (I4NS)N06690;NfT.#AS5663 Comrponlent #2 SA-376 PipeType 316Sch.1M0 HT.#37680 LSN-5Comnponent #1 SB-168 Round Bar (UNS)N06690; NT. #AS56= Component #2 SA-376 PIpe Type316-S&t.160; HT.#37680 LSN-5Component #1 SB-lee RoundBar (UNS)N06590;NT. #RS7758 Comnponen~t#2 SA-2TM Pipe Type 316Solo.160;HT. #37880

                  -140-      mpon -Jr-             66-               t. ýu                ;      66               -ponent                 -      pe=                      160 W #37-LSK-7 Componentu             81BMW    RoundBr (tJS) NOsO; HT. SRST756                              Corspenerrit   #2 SA-376 Pipe Type 316 BIlt. 1W0NT. #.7680

12. Remarks: Pad Weld WPS; 01.43-T-803-102836 R10;Weld Wtre ERNiCrFe-7A SFA 5.14; .035 *GTAW Machinme' Nozzle to Pad Weld WPS; 43-43-T-00i R13:Weld Wire ERNICrFe-7A SFA 5.14: 3320 'GTAW Manualr CERTIFICATE OF COMPFIA IACE L James E. HeNmz , oeotr thoy to tlr bot ofawe noboede r*d beief Ithe made ind rtharvot are naeor Con-ect erdtherepi-r.raodifi*ti*oorr*oplao airirio t m de*;oeOhd aboveredeeim to $Soioe XIoftheASMECodeord theNational BoardTlopeottio Code-W dmire NationalEeoeCmntficao ofAu NR-69 Nte the'FR.aVomptrm P40.6 , 2010 NRcelitfioaoe Iboldor b eriemsIN.

Dor. l1l6rzlYm Slod ____ NQCIropector ___-'R CATE OF INSPECTION

1. ltA10*ArS ro LM'S , WhW a vao~lidrtonoterunioei ismodb hyobiatiorvalBaoo.ofBoilar adrciPoum oo sdov loporr ted o=oifiatt of ooopemi.yiswod bythejurimsicioe of eWtQO 00dOOpIoyeiby o.mrod ft4-a e vodfloesa

                                                     -la        orcphvungntoe      d.-norhe . bl-po   reportedttebato Sectionoa of theAStdECodearidtheNaoaratBoardIiepmtiooCode'NRO                                                                                            .d..

fte "rh do-orb 0- rop.W eh e. -9h.*ho andosiovd nor a opevploy shalt bo,,d n e e for .r

                               .anypsoool rojry.property    diraep oroalow      of anybkind   rasingr Boororcoartvomedorih     SrioaeperiNm 1501         t~iQj.       51004                                    ooor          oss           .~3        ~     j~

15 RFO Inservice Inspection Summary Page 207 of 238 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 1 -e4f FOOSINR-1 "REPORT OF URPAI1J MOODIICATION[_] OILRA~c0 r TO NUCLOEAR COJPONOMAND SYSTIE IN NUCLEAR POWERPLANTS I Wkplpfo by WeldingServies ha 10571 *NRO-30 2225Sky0 Coort Ooo.=9. GA 3O71 2 O,. Plot EnergyC,,p. 20- Z,.A.0-I.- 76 S MAft Amo. OH 3 -db Mm01oern. r-0 Devhi*s-&. 5501 N StoaeRo. 2, Oak H11tw,Ohio 43449 4 . ReaCtor Cooing SysteM -RCS" IO N Di_ .6d." Co. 0000 I YC No0*. WS LSN-.A5.6. IA A A . 2001 AS.E IX 5196 1A 1 ROt V0. U.0000 WAA j 1m NA, NO0to1 WA_ NIA 1 1977 I 1A tO 1971 I NA 2

                                 $0. VIM11       12                                                                      ASME9       PoolrnI I'* owoNFOlneT! "                    WAI             WA N*AI                     ttA       iA        1To 1995 I,1                  9                               NGrA 40100. t971           Banooo,1973                            N/A 00190ICFirt n100,901.dotO~ra1.l.lmCOn
                                                           'PrembWO     Tev to be pe'foried by owner..

0100.1.0 Ve 09At Simeof renynV ft enos~ftgLoeve Seonoq Nozzles WSI osnioved642. SMORbm pe Iet_ This neerQ[ oddl fe reatt*dment of 019M00n. WMI1M]ow19 tile 9fid weld nuo10 001t arel ed 00019 nllantrtaCles N-6 N-lo5t data 0ep09L Al! 1 VMSp rMedin aor0dar*e w1thM1e 0 c190010qpew90ed&ICode Case "-036-1 9 mo=lfedby ReobefRequest RR-A31, in conjuntoion 1th WMrs Tnaeser

103571-TR-01 G-" late10 Rev, Tb Itplement a one t90e NFC ac0epted repair p i a hlan norafC9e

                                                                                                                                                %fthRegef Reest RR A31 01 ror amend Code Case 14-638-1 ReW"Weld Numbers Modied:

(RC-14-A)FW. 40 6 18B (RC-14-5 FW. 6 &72 (RC,114-qFWA148&70 (RO-i4-O) OW. 140 &73 (RC-14-E) FW. 22 &72 (RC-14-F)FW.2&70

12. 14emrl90 Sma09Bo pVo5 WPS; O8-09-T=1I R/; Weld M.

P ER308L SFA 5.9; 3Mi- "GTAWMauoa_ _ CERTIFICATE OF COMP1ONACE

1. Jameso H.199 .ooloo d.tb9torep .0db1e0

                                                                                                    -0oo10d.0fa-*a          of-ap*Op mt. i. the NabmW1  990    .- 19 d lwh-!!:ooNR-do 8 d C-fi                                                                    on to~a dao ýo      V pi       Nov90  6        2010 NOCaO¢lla0HolV-              SW--    \.j"--o---..M.M                  1      Seo' s In0.                      ...

D 10000 lr sOog "ad OAJOC 0190901r _-*TEMC.=OF IMSPECrION

                                       ;*v F~onalt*,

r~lm* *mll *" ]o 90919019od00107fro 1 10 NehlooeIr 0oa..... P..o eOoo , X By~ AS

                               -ko.       ~ M~ dii90.~oo
                                          , .             ~t-.b FCd,.0       -d- ft         ft1901909,4Oe91.0997 701.

O..iP N00ow1WE 0001.1 M 0 NF~blaf 9001.,090 do 001ddfaoedad 490101 0 110 opotee np alblas.. nylop alI11..1Co0opP14.to

15 RFO Inservice Inspection Summary Page 208 of 238 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/NR4-. OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI I Owner FirstEnergy Corp. Date February 4, 2008 N. H4 76 South Main SL. Akron. OH 44308 Sheet 1 of 3 2 Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2, Oak Harbor, oH 43449 Order# 200249958 Rewo wp-awo P.O. KID-G. 3, Work Performed by FistEnergy Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No. 2 Expiration Date 07/1 7[10 4 Identification of Systems Pressurizer Sencing Line DB-RCI4E (Subsys 064-04) 5 (a) Applicable Construction Code ASME HI CL.) 1968 Edition 68 Addenda Code Case No (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements .19 95 Edition 96.. Addenda Code Case N-4166-3 (c) Design Responsibilities FirstEnergy Corp, Welding Services Inc.(WSII. Structural Integyity Associates Inc.

6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identif-catiorn Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No.. Built Replaced or Code Replacement Stamped Pressurizer Babcock & Wilcox 620-0014-59 N-157 DB-T002 1972 Rpaied Yes I

7. Description of Work The existing level sensing nozzle RC14E was replaced with anew nozzle and a weld overlay added.

All phyical work was performed by WSI per PO# 103571 and WSI traveler # 103571-TR-016-5. All work completed by WSI is documented on "NR-23" and "NR-30" Report of Repairs. Firstenergy Corp (DB) performed a VT-2 initial inservice leakage test. Test was 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 (ifapplicable) N/A Set Pressure and Blowdown 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 81/2 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 top of this form.

15 RFO Inservice Inspection Summary Page 209 of 238 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-1/NVR-4 Ap- f=..*-.pt

                                                                                                                                 - W~ot

At-W*=

9. REMARKS Welding Service Inc NR-23 & 30 report of repairs.

CERTIFICATE OF COMPLIANCE 1, 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 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" sta7O"*xpires 07/1 7/10 Date e12..-04-Ds FENOC Signed \ S)7 Z 17 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 C" of Hartford, CI have inspected the work described in this report on (.,, X.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 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 . ýJf L Signed _7er~, .f Commissions a~~d ccM4io IMd¢,* k am Of3 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 "NFl" stamp expires 07/1 7/10 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 O-IO and employed by HSB CI 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, conceming 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

15 RFO Inservice Inspection Summary Page 210 of 238 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

                                                                                                                                                                -)   2~3 FORMNtR-1       aRt'OR oF RvAa[o                       MODImCArsONJ              ORREAt3PAOZer[

TrbtIM.XU COMP'45t'ANT)S AurV~raIN N UEI.FOAI7yRPLANTS I Wotysfead by NeN S=I0 1,7 -__1071 'MR-.23 2 On- Z~t nrgy Cop. 76SIMalf, AIM,0OR 3 Meak hdpopN/ Pa--Pae 0= 0 N.StateRte.2,OakHa-ba. 0- 444 4 SYMes ReactraColinq System"RCS' NO L Isslv an hm S. m,. Iaesoa 55W 620-50145 N-157 N. t& [do8r17ie

                                                                                ~        N          Yrolk N/A 197 2/A

__"WA11198 9.06d CosooCde AM.,& Code 94 I WAI ESME C1. RI-W* Aei C. Cd 6.A5OE.od4.sisGdia WA 5 14rWAEa9 99 1 ASWECod 8ý=321m qM oeo-taa Ieyt~odaoe 1996 19W6 N-5313-1. see&WIl1 ASMEIn,19M8 Sra171999 .. FNO~CFlr FnaW Nwcteroeerads CO. W-0f dJ 0 fr]&P- I- P- Ps rDOIC-4) _ N/A _

                                                             *P~sre 7g     ratto eIperformed 17 owner.
                            ~isooota~n   ~ LeveBenstttlan ozei ROM4A,+                srhmnwttkxhtded a pressmsboundoey vksnp            ethenteft f tor f0teurerlor of ft~Pressuizer Ths . hag was moade osil byIs~telng an aemb~eAtapwpisr8Tempetea kscomilWeldpad petsrfamid                           Insscodanoe

__ - ,t- .a 1, A. - uaqe.., -- ýtneI, ReWOoO RR5, in , nlen4L~nAth WSqN TrvavLtIM#1 71-TR-OI6~ latest Rev. This iplemeo*la one VimeNRC acoeptedmeqp plan Inaecordanoe MMtRelef R es RA 1and for amend Code Case N,-638-I. The reprwuk cwnWsd oroe padweld."and onm ,-prp.to aach the nozzleto the pad for act Ilo . RC14A hm F New N~ac2e:SIN# LSN-1.24,5,6 &7 -SeeruppWUM form N-2 2 [SN-I Cynpont#1 SB-le Roun B (IS N0 ; KT. A56 Cornp-# SA-376Pipe Te 318 .83, LsN.2 Csttleoettt#1 Ba-lee Round Bar(IJNS) NOBOW. HT. #ASSe C~monipee#2 SA~-376 P"p Type316 Scln.160;HT. 537060 LSN-ACwqrpne#fl SB3-leeRoundSaW(Ut/ Ko889 NT.#9.Z98 ConRponrt*2 Sik-376PipeType 316 Selt. 1W0, HT. 93166 LSN-_CCnp t#1 38-198 Round Bar (UNS)P10689;,NT.#RS77M Componertl#2 SA-376 Pipe Type 316 Sh.16H,T. 037680 LSN.-6Coernnowm;tl SB-166 Round Bar (UN P166o; OS NT.#RS7756 Com~pofte.#2 SA-37BPipeType 316 SI- 190;HT, #37680 LSINI-ICmnor-At #1 38-lee Resot aRw IUN61N06M,0 HT.#RS775e Coranonat 02 S"-76 Plirt Type 310 Scdt16%,HT.#3768D0

12. Remark Pad Weld WPS; 01-43-T-803-0283e R/I; Wl Wire ERNICtFe-7A SFA 6.14; .035 "GTAW Madti,,e Nozfl to Pad Weld WPS; 43-43-T-001 RP3A Weld Wire ERNiCrF-7A SFA 5.14; 3W32 -GTAW Manual" CE~rT5CATE OFCOMPLLA4NCE

1. JornmEH6.N ia , certify hataft benQl nWAW andbclioftm sWcarn matade inth rcanss0 Noml-oR~d CaUrent.e~f NR-ea touftcedetksaw-ep-n Nme, 2010 Ulm Si-W0 =1 MQChwspectrn aWCATS OPIMSPECTON wdeer b m~peoed Tle apw, M aesd.Se .W..noleanesdma s.tm mth~pw atet bl bestofm akras*Wpc anadbelie&thdnrrpne. aedffiatimo onrcloea-a .oeovityhasbea- isepab

                                                                                                                          .soazweas o Secifm M.7wASINE Codend dbo        Noliwo lBesd bnped-s Cod.'W nden.

Syeip 'boooeoaoz, -9b.9 theondoiurdna= mw awtoya nmy tassn. Wsp=.mdo- hpled. --nonje toeeekdeoeoe id~i aesPitbmoe~nldr~andaied oeepedmptohaStetebeisrynreer Date aiirppy olnneybe o~e e li Ciospsiss

15 RFO Inservice Inspection Summary Page 211 of 238 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 (~:) '3S1 3 FORMNR-1 REPORT of M2AIRE] mot54CAT¶ON] Qotkmosnoos2 (L) -4 6-1x0NUC2LEAR COMPONE2000 ANDSYSTEMS(N NUCLIEAR PO54 PLANTS I Wl wfi5b W .V S.,0roe Im 190071 .14R. 2225 019l ~f.N,,~ A3D071 20~FV F1Ergy C.,p. 79 S M2OO, Moo OH 0 3 *eMOoo/e9poI O5ws.vsBeoa, 55015N5. RtMShe2,0OakHatt=,. 01*0 43449

              ,.s,-                                                                     Retor CoolingSystem 9RCS" ii               or                               N/A=                                ASMEX        91          9/aa 51
                  ,    o::              SP W "A"!

N..2o;aA 9091 NO "A 4 39 A wTAs' N 1"A 0A bOSwI.ýW WIfl* Y A9S5 199 NUA

               &C-Cod.k/.yo'                   od      o~oo F09CC FRO E..~.ogyNooe&opr   *ot,      Ca.

9 D0/p_&lb

               .0 tMOdo                         I19d,                                D        Pp-' E.-           P-       __          pd                      .      NIA.,

fleg to beperformed hy mm~er. it D tadý& Ae 9t9e

9. of E!M2!Loyfte edsf Leval r SewtidNeSI (W oed 6M. S,,ed bore Pl.ý m r t, TM Dy addrm et99reaffdnheredof V%99 ,39. WS1w8IfboIw [he exsgno fied weld nmabers M,30, ldeotofed w M moeulSta~o N-5dat m9wrL boOaid ADwolk was pOt d In ae rd e 043he. 3 09 9 epeoafld In Code Caen N-638-1 as moaede by ReW Requag RR-ASI. in m*r fim wfth wSrSTmveT r# 1071-TR-0161- Wlest Rev. This bmnplat a w0e9ime NRC accepled ,pairplin in acovdanme wft Refie Reqet RR A31 Raid Weld919990, Modifid:

(RC-14-A) FW.40 &199 (R0-14,B)FW.6 1&72 (RC-44-C) FW. 1489&70 (RC,-14-OFW.14B &73 (O1-)W22&72 (RO-14-P) SJI2 & 70

12. R901aI1I: _ _ _ _ _ _ _ _ _ _ _ _ _

Smale 8ore Pio0'a WPS; 0l--T-001 Ru: Weld 'l ER30WLSFA 5.9; 3/32" GTAW Mauar CERTIFICATE OF COMYLIANCE 4 I. Je'eeS E al , eH*d.Wdo thbwofoW knoIedp md bobafd59,.,,.,o.,o inthis R omee Cone9,lae'rng,

                                       &a           9d      a 9q1modd9amm I&M         a0v19=te de0 ab3 cmtm ft     3 S9t93 X)oft1 AS*E Co&d        w Noi.9 Bo-udC~ffiat of A~lht '.i                                    NR-89        f     dn'Ta
                                                                                                                  . anp"           N.v. 6        2010
                                                                             , .     ,.,  ',^c,    EvoFIoPEsrCToO S0=9, 70 oft      ASMdE Coe nd1b. NledNa=   BmudIaspel Cod"WR ned.

fty*d-n15hnt1.So 9W.d09 &do mýW d.99a9909 wd,npo.,e =pea,y %doy Aa j~b. H" pd ft

                            .Mnod, Weoyed.          doo.po l~eo,
                                                              ..       01. 0     .,d         a 0 3o39,US 1099909 d      gls                                         Wdl,0frpck.odo,9eOyca 90799001          yW            atorl.

616 Syepo0

15 RFO Inservice Inspection Summary Page 212 of 238 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/NWR-4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 17 Owner Date February 4,2008 FiMstOEne4gy Corp. 76 South Main St.. Akron, OH 44308 Sheet 1 of 3 2aPe 2Plant Davis-Besse Nuclear Power Station Unit #O 5501 N. SR. 2, Oak Harbor, OH 43449 Order# 200249959 3 Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp N 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No 20i Expiration Date 07/17/10 4 Identification of Systems Pressmizer Sencing Line DB-RC14F (Subsys 064-04)

5. (a) Applicable Construction Code ASME Itt CL.I 1968 Edition 68 Addenda Code Case No (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19

95 Edition 96 Addenda Code Case N-41t i-3 "4 (c) Design Responsibilities FirstEnergyCoirp, Welding Services Inc.(WSI), Structural Integrity Associates Inc.

6. Identification of Comnonents Renaired or Renlaced and Renlacement Components Manufacturerfs National Other Identification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped Pressurizer Babcock & Wilcox 620-0014-59 N-15/ DB-1002 1972 Repaired Yes

7. Description of Work The existing level sensing nozzle RC14F was replaced with a new nozzle and a weld overlay added.

All phyical work was performed by WSI per PO# 103571 and WSI traveler # 103571-TR-016-2. All work completed by WSI is documented on "NR-23" and "NR-30" Report of Repairs. Firstenergy Corp (DB) performed a VT-2 initial inservice leakage test. Test was 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 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 'AX I11 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.

15 RFO Inservice Inspection Summary Page 213 of 238 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'V "I"....... ....... Alpp l Ma,*, n

                                                                                                                         =mD-ataRan = be Machad

9. REMARKS Welding Service Inc NR-23 &30 report of repairs.

CERTIFICATE OF COMPLIANCE I, Richaid R. Cockrell , certify that the statements made inthis 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" stFnrp'Lexpires 07/17/10 Date . - D2 L FENOC Signed 0 &,1 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 emp!oyed by HSB CI . of Haitford, C1 have inspected the work described in this report on 1ýj*. 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 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 111Jg Signed Commissions A~jý ý- 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 OH[O and employed by HSB CI of Hantford. C1 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 inthis report Furthermore, neither the undersigned nor my employer shall bea* -" liable in any manner for any personal injury, property damage or loss of any kind arising fromor connected with this inspection Date Signed Commissions bo(NW (adonatB

                                                                                                                            ,  d (d .ro,'a,.a).
                                                                                                                     "  Jdý'      "  .))

15 RFO Inservice Inspection Summary Page 214 of 238 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 o2 *. 6 FOR REPORT NNUCL OFPONPAN[S MODIFICATION[] ORUEP-ACEPWPNIES TONLJCLEAR COMPONENTS ANDSYS TEMSINNUCLEAR POWER PLANTS I WI performedby . Weldtng Services Inc. 103571 "NR-23" 2225 Skyland Count. Norcrss, GA 30071 2Ora First Energy Corp. 76 S Main, Alron, OH 3 Name,cdden.Id/ati/mmn of=* powe plat Oavis-Betse. 5501 N. S/ate Rte. 2, Oan Harbor, Ohio 43449

4. syrom Reactor Cooling System "RCS" 5%.ItameWhichR6oepzfd Rir, om teor Acvit*es Mo.ifuenkfoono, Identification Caonsios Code Arh*hy Nasl dtln Cede 5/0 o Tpre ~ 0sdaNo am o ithtYse// "'6'NoWed IWbion deroi Atn i/ o t Dpe tpoe I presurizer MBW 620-0014-591 N-157 . N/A 1972- ,ME NI Repair -

Di, to 968 5b. It-emnstalledDuainoRItoncnemo Am/vilih, tdentifio*mon C oioorueo/de Teepe.beod Pad lasa No seee 1l & Name Mr W t 1' PA I No ISI Nitns WEA NO WEA I NPA r yj 2007 Ni/a SN EaleSeial ASMESH A Mdr/at 95/16 code C..4(s) N-63811 C. ClaNto Cu/nOc_ 12 ofthis 7 Mo 8 34' Nozz WS L-1.2.,4,5.6.7 N/A I/A N/A 2007 ASH XI 9.5/0" N-063-l 1 inOSkISCo/s Sooioan*a=pphm~lo oatr n-sant*mopaut 1995 NA

                                                                                                                                                                             '00 7 ASMECodesecton 2 noedfor ropes. modifcatiooaor rep/roarcenr                                     1905                  1090                          N."8-      Seefint 1t
               & CronorucroeCodena f/orpainr medniofioo-onrnepltaooomn

ASME IiItt snnnna-1968 N/A 9 fie nmep tabiltso FENOCFirst Energy NodearOperaltigGo. _____

10 itnts ondutd: Ityd-- alr7 P- Mnooedratiaena poED pmes-o pit Co/eCeoit) NWA

                                                                   *Pressure Iiost tobe performned by owner..

tt nPtamf ,pnen Level Sensing Nozzle RC14A-F replacement Included a pressure boundari change from the interior to the enherior (th n eof i.oas nt entel n/mperatTeona/ oroheel irsnoiine0wt ap r c d of itre Pressujrizer. Thisc/hangewas madepossible byInrstallingan ambient temperature, Teenperbead inconel weld pad performedin acmodance with the controls specified in Code Case N-638-1as modified by Relief Request RR-A31, in conjunction with WSI's Traveler 6 103571-TR-016-1.-6 latest Rev. This implements a one time NRC accepted repair plan In accordance with Relief Request RR A31 and for amend Code Case N-631-1. The repair work consisted of one pad weld,and one J-prep. to attach the nozzte to the pad for each location, RC14A thru F New Nozn:zleSIN# LSN-1.2,4.5,6 & T "See supporting form N-2" LSN-1Component #1 S13-166Round Bar (UNS)N06690; HT. #AS5683 Component #2 SA-376 Pipe Type 316 Sch. 160; HT. #37680 LSN-2 Component #1 SB-16 Round Bar (UNS)N06gM, HT. #AS5683 Component #2 SA-376 Pipe Type 316 Scb. 160; HT.#37680 LSN-4 Component #1 SB-166 Round Bar (UNS) N06090; HT. #AS5883 Component #2 SA-378 Pipe Type 316-Sch. 160; HT. #37680 LSN-SComponent #1 SB-166 Round Bar (UNS) N08690; NT. ORS7756 Compenentd 2 SA376 Pipe Type 316 Soh. 160; HT. #37680 LSN-6 Component #1 SB-A66 Round Bar (UNS) N06690; HT. #RS7756 Comptoent #2 SA-376 Pipe Type 316 Sch. 160; HT. #37680 LSN-7 Component #1 SB-168 Round Bar (UNS) N06690; HT. #RS7756 Component #2 SA-376 Pipe Type 319 Sch. 160; HT. #37680

12. Remarks: Pad Weld WPS; 01-43-T-803-102836 R/O;Weld Wire ERNiCrFe-7A SFA 5.14; .035 "GTAW Machine" Nozzle to Pad Weld WPS; 43-43-T-001 RI3; Weld Wire ERNiCrFe-7A SFA5,14; 3/32" GTAW ManuaO CERTIFICATE OF COMPI lANCE I, James l.E7.Heitz c.r* dataea thts o best of my krowmted0and bhnl thd stasee mAta this treport ame Co-rect and the repair, modificotir cni/it described bo- oore/a to Scatt Xl of the ASNMCode ted thdNational Board C R'Rtnpee/nor mien NationalBoardC=riiat ofAc - No NR-69 to-tshe'NRasumpoptres NoV.6 . 2010 NR Catifcal Holder , .g Services Inc.

Date 111W250011 Sigred QAI/CtIIIto

                                                                                        ýtERTIFICATE OF INSPECrION li.iroitg-firicamatisior     . isrlrd by The Nationl Board/Boilrad PressueVeanl Jr. o     do       ears of eapatencytissed bytheiyoi.dictior o/f                          0,V, 1S                 andempoyed     by inaprcted thi repair. modifiantion orrpiatcotnt demobed in thi/      repon                        D                     a     te   ttathe ot of rmykrowlaedgoardt lit this enpair,mo/dicatineon orrcploarrmacrtity hosttan crmted ohnacrerdenoc                  with Section Xt of ahe  AStIE Code andthe National Board lsrpoctire Code'NRi at/r By siiting this certnficAot.mit/er the undorsigned nor my employeremoh amywarranty epeamsed or implied. conrersnin the work de*imited in thieps rt Firrhrumoe sit=r hr andrrsignrdnar my employer litallbe liable maymannerfor any personal inpy. property daomagea a Its of mmyk/ed areiing fromeor conr*ted with d/is improtion_

0'1 Da. s(2.od7NW'L Cromrissinsr 3 ~ i~ .h C5ef~,

15 RFO Inservice Inspection Summary Page 215 of 238 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.,c-p 9/-I To SFiN

                                                                  /ORTR   OPFR*PAYR[]                  MODRIFCAnIoNJ ORORREP AC94ENTE]

TONUCLEAR CO/{PONS/7?A//S SYSTO9.09 9/NUCLEARpOWERftNASTS I k~b eldingScrsAmssc. 103571 'NR-W9 2225 S /oSCo1,ol N-,1,. GA 2297i 2000- z"lefgCo1.. 76S Mon. AkS99sCN 09 3 N-9ý 7 l,90 a.o/ Dos/sn., 5951N.State Rt..2. OokHerber. /Ont42.90 k Ste- R-orsa Coolin Sybe9n "RCS N_ w109/19a .ý t,9N Ir A~t . /0Y,yk N.-. N.3.. WAW71910 T =i ISfl IFU 00 1995 199 W/A 7 AS/n,C 9 a.oWno b0,oa -Joa&mm ob,/ ODIAEM1.1971 4- 1973./ W/A tCo, 0.0a/n~. mO0o ,0m.. FEP/CCIS/S 90sN//r

                                                                                                               ,            090.0/91 Co.

D-f 90a__ 0CdC9, . A.WA Tat to beperoantd b owner 11DVdmalft At 1Owime . removing91ft0 an~dslg 199. Sensin; Nou191 VlS1 rem/99 6e R &nA bore pipe lives.Thisreport will address ft0 reaftodned of Mass9fiesf. Ml5 wil folo. ew exisng field weld rut/imb90.0, dud ae.9k,/SW rth or9igin/1907000d100N- data ropoLt ANWorkwas1perfomnedi1 acoodw19R99ft/1119al 910s pecfled in CodeCawe N438-1 asmodlflid by Relief Reques1 RR-Mi 91,E91*oN//000191 9590/Toveler # 103571J-Th-19--O " kleoRev. Pusimplennents a one timeNRC acoeptod rpir oplan In e00,d009oed91 9.99/9900991 RR A31 and for emend0 Code CaseN4138-1. (RC-1"-A2W.40 & 188 (RC-`14-B)FW. 9 &72 (F.-t14-C) FW. 148 &70 (R.C-14-01F9I. 149 & 72 (RtC~l-4F) W. 2 &70 12.900/09/11: Small Boes!Mft1 WS1; 08-OT-001~R11:WeldV/S. ER3I99L SPA59; 3132' GTAW Monoar CERIFIWCATE OFCOWL LANCE9

1. Jemerl 9.9F Hm 949oO9.

                                                                        *dMt          b=eoof awwIpM~d beha/o     r    o       0-Mde s,9 dis,      1,.

C- d0f.00.90...,/oa,0 dweib/Sel

                                                                                             .o-f- if. lto              ASMS/

M./s U.alS COd& and ft NWOsloB-oi lhp..tio. Co.6-NR d.

                                             /40~ 0f,&o~ooJo.

Rod o91,o~ NR89 fto 9. 74R0 K..9 80,190 2919 NR/I/Co/w.0Fut/er

                                            !M" 0129           Si~snd                                                              09/0CC/yso
                                                                                     'C-nrCATE OF ENSPECTION L. -mtAAzk                G,                                      n90n1e9o/oio99.6-0--~ovosd   mA9099/09 Eoys~oo00.e5~otoo~aMCI
                                                                   ..odbySoj"ooio                                                                    by 910009    909/dol                                        ,eya.e rep0.                                          .0199009001 WAih9 to ft 11~992U050, ASNIECo& 3, dftNutood RoodI0.pn,9 Cod.7/'Wndn.

byOn-8f Fo/isuelempw dfld-o,, d9,eo - /. -. 09/p'eloomya.,p/s9demm q.-W1 V on--e f 0d900/9, dsrie 6. 9099010910thsyk99 p ooe9s my 919,0, b/0909999y -f 000 ait -2 (Le EI l i0 & C..o.lwn V4 A C004

15 RFO Inservice Inspection Summary Page 216 of 238 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-C070-5 FORM NIS-2INR-1/NVR-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section X1

1. Owner FirstEner gy Corp. Date February 6, 2008 N-m 76 South Main St.. Akron, OH 44308 Sheet 1 of 3

2. Plant Davis-Besse Nuclear Power Station Unit #1 Name 5501 N. SR. 2, Oak Harborý, OH 43449 Order# 200249960 R". OManla. P.. N*,

3 Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp - _NR N-am Authorization No, 20 55011 N- SR 2 Qak bor OH 4-UAQ Expiration Date 07/17/10 4 Identification of Systems Pressurizer DB-T002 (Subsvs 064-04* DB-7'002 (Subsys 064ý041 5 (a) Applicable Construction Code ASME ]II CL.1 1968 Edition 68 Addenda Code Case No (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 ...5 Edition 96. Addenda Code Case N-416-3 (c) Design Responsibilities FirstEnergy Corp., Welding Services Inc.(WST), Structural Integrity Associates Inc.

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 Pressurizer

Babcock & Wilcox 620-0014-59 N-157 DB-T002 1972 Repaired Yes 7.. Description of Work The top vent nozzle replacement included cutting the existing nozzle flush with the outside diamenter of the pressurizer, installing a sacrificial plug in the nozzle bore and depositing a weld pad around the existing nozzle bore. The nozzle bore and sacrificial plug were machined out 1/2 the thickness of the pressurizer shell, a new replacement nozzle was installed into the newly machine bore and welded to the new weld pad.

All phvical work was performed by WSI per P0# 103571 and WSI traveler# 10357 I-TR-014 All work completed by WSI is documented on "NR-33 & 34" Report of Repairs. FirstEnergy Corp. (DB) performed a VT-2 initial inservice leakage test. Test was 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 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.% 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.

15 RFO Inservice Inspection Summary Page 217 of 238 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/IWR4t-

9. REMARKS Welding Services Inc.

CERTIFICATE OF COMPLIANCE 1, Richard R. Cockrel, 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" sta pxpires _ 07/17/10 Date 6 0- 0,51 FENOC (rani ohnrptorlmizato~*- Signed ad

                                                                                                        &     p*n~la
                                                                                                                      *         ,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 Fpea. -1, 7,8tP and state that to-- the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance witi Secti6"- Xl of the ASME Code and the National Board Inspection Code 'NR" rules. "n 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 a,1:- 19 Signed TW 4 Commissions 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 "VR" and "NR" rules. National Board Certificate of Authorization No.. 316 to use the "VR" stamp expires 12/13/10 ;1 National Board Certificate of Authorization No.. 20 to use the "NR" stamp expires 07/17/10 Date FENOC naed rgevaorgarnaaho

Signed IsIronzs ,oprsontaurw). 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, conceming the repair, modification or replacement described in this report. Furthermore, neither the undersigned nor my employer shall beri. liable in any manner for any personalinjury, property damage or loss of any kind arising from or connected with this inspection, Date Signed Commissions M.-W,. 8-nd m ,inw.f)

15 RFO Inservice Inspection Summary Page 218 of 238 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. 3 FOWR] NR-I           REPORT    OFREPATRIE                   MODIFICATIOOJ                 ORKEPLACERMRNI TONUCLEAR      COoMPONENTS     ANDSYS100oS     INNIUCLEAR     POWERPLO./TS IW/'kpf(/oOO                      _______                 WeldingServiceslo-                                                     103571        "NR-33 2225RStylarel CouNo-.059/, GA 30071 760SMhm Akr/on. OR 3 lOneoo 0l05    Mkor_.9.ovdee0/o-'eA0                                                 Davie-8cee. &5W1     N.StateRte.2.0OakHa000,0Ohio43449 4.Sono                                                             Reacotor Cooling System,1RCS" Is b-Wo-Ao1       Ropoiroojt,t5 m       MotoOOtoboerk        ,Aodit,5 54F0                             -                                  .I I          NCR           M&W        020.00145                               _N0 I- IIJ7 I                 6 10                                    Repair tod/ibo/9                                                                          C-doo/oCo TSmoo     E~.        Code0 Ver
                            . Nealne 11adINA                                                                   2      07AM01.1 2003I           W
             & 010.09 (00054w,10005 4.toboe ,o 0.FOon                                                                                                     N/A I 49000  Cod./0000 o.odtroo.o.eoAhenote0o~d.osm0                                      1095                   19%6                     N0.03-1. See 1l/ 11 0 CneA/6iooColeoodO,.,qedrs  004.00/55/o/r5.I.oooooo                                                                                         NIA Fie-EC -NcerOneafn 0 0/o05~                      _____
              /0 005,,O/t                  ktdos.0o                       50      . denepn-/~o

Plvsmre roo to he perfonned by wir m- ve P__

0 ooCoe4R* NIA 1;/400005-t The TopVerit /4022 replacemen0t brdoded a/06591 R605daychange from0/e0inter/or(t1the6exterio

                                                                                              .A1-ifedA00Aod-    r/0oe0,ie-Vubk/

wOOh the cont/oe specified InCode Case N-638-1 os modified by Rief R est RRtA31. in conjunction with WrSI's Traveler # 103571-'1-014 lateft Rev. "Thislmnldements a ote time NRC cceoted reoer Man hi accordan/ e witP R Roest eefu RR A31 and for amend Code Caw N-35-1. The repoirFwoW consted of ne pad weld. and o0e J-1pp. to attach the nozzle to the pad Iocalol RC-PZR-VENT WSI fielldtd nmr Ve.ar.-W 'Pad Weld" Verd-JW *J-pep Weld" Davs BeRssefield i number

                                                                                                                        /ld RC-PZR-Vent

12. Renledto: Pad Weld WPS; O T-8039102836 R0/; Weld WireERMCrFe-7A SFA 5.14; .030 "GTAW Machinel Nozle fo Pad Weld WPS; 43-43-T-001 003; Weld WVe ERNiCrFa-TA SFA 5.14; 3/32 "GTAWManyar' CEI*CTInCATE OF COMPLIANCE

                         .             JRms 6-1,ertz Her          .       0,0
                                                                     " to . boo 0.of my lofee . ndbO* de otoMoemo         ,made be toio M    te CoeadteMo            odla.         pa           h i 0.50,0,54bth      dms .ototOefS'.6 X(10
                                                                                                                  .10,.4      Code etd ONsiomotBo..d RopetionCode Neti*edoaodCmfi-tnIooffh       "N-69                                          to-thn'6ttmpe4ot            N40.6         2010 NF.LC.t/*mAf Holdoer                                                               lt.

960/See* Dole V/19=085 Signed OM0 0sptoor

                                                                                              ý    tVF NSPECTION en"OO/tOttpet~ooOeeoodby Copso                            /bsolndatoiO                                                    d emtployed an0          by oeyottda 61 R A4~

ther.ee, n/oddieotonorroploocos dM0/.h(od / repo. n t h beefat mykowetdge andbefbs/,dos pnoi.594400/0/0/o pieemem050/t bee0/O Owempt 00/5,to 0 S/oeEX ofthem 45/40 CodeodW lbNelieBoralrod Inspenid/Cede "/W0.I-By00 oo dole os/Rot6ý, t.o wdereigned et y7employer-dk. arke,t-1yp,.. o hpite. .t.. i rpeso io d/o.o-1 domil00in/Ohitqe0. Fnhebo,et oodw ft udteriplor o,00p/ltyerol/l te lia06101. enyman.f coppsoo oom -sy ooep eoe rioc /4oior St0506 witdue inepeohoo. . . . . . Dole /umn/on AmO~.

15 RFO Inservice Inspection Summary Page 219 of 238 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 .S-3. FORMNR-I REPORTOF REPAIRrn MODIFICAI[ON*-] . ORREPTACEMENT[r TONUCLEAR COMPONENTS ANDSYSrMt IN NUCLEARpOW'ERPLAN3s VWorrorr S-Aces Mo 103571 Iid 2225 SkY~edýCR11.Nor--.e GA 30071 9 O10e~~ Fost Ene057 Corp.____ 76 S Meain.0109 OHf S N~ore1oe 0orcoeorkorCorpieRoe sw.cr5501N. StateRte.2. OakHarbor,Ohio 43449 a~~ e Rato,

                                                                                      .. Coo1oe syoteme"tS Io~eOC0       TN1               NAA                                          0 Noze 1/W1 W                             004 St.                             SowLtN.l                                    noIkow-1.)                               .       CoO&Ml-0 lret. lre,              0e          PYA ASPd           'V            M                                   !*6     111 A;9         Ode 9
                .at    .orprcoe         1j 1-           ASand ik        NrA           N/A     I AOI      NA       90      AS          159111 I N/A moe                                                                                                    ma            - -

7 ASNICSkC ýerpee m=l&ea,or90err

                                  ] weel~ad                                                                     159588A  19N.See                                 I.. I a-COmo       Co" odcrm-c        MA.rror -rplro                                                          JlTt1071
                                                                                                                        -9r                                 W/A FENOC FirndEMMrYNuclearOperatiigCa W.DeToe-AA-e                     _______________

Cede .05e) NVA.

                                                             .P1e&=1a1"     TEstto bEp efo rmed bypon or.

It D*- oFwoo Atthe the of remroovi the exiostrr Voot Noziles WSI removed lea. Small bore pipe loie. This repea M1 address tre reatrachment of thLsline. WS1 will followthe ords;rnfoeldweld nomobc that are Identifiedon the origina[ menufactare N-5 data report. An work was performed Inaoorode~s wAththe cotoatosspecltled inCode Case N-838-1 as modified by Ret Request RR-A31, Is .rerl ýft WSVs TravelerO 103579-TR-Of4 latest Reo. This Implemmteea one Tor NRC accepted repair platn n occordace aWrh Refif Reqouest RR A31 cnd fom ameed Code Case N-638-1. Small Bore Pll5n Weld Nocrbero:FW. 23b. 23X 23d.23e See attachred

12. Reerarko:

S-et90 DrleoPla- PS: S8-S8T-00l R1l Weld V4re ER3O8LSPA 5.9: 3(2"GTAW maceat

                                                    -                          ~CERTIFCATE       OF CONWLIAR4CE L        Jarr. E.HerO           .ff orfrlvr to0 dm     oat of larooredorAmid ef OreMtr-o =A&etoadusraeereorr      er C.ere '"d dr ee. -~difttono ., Td-eorer e.,Mdr doroibed           eh or.-

eoo.o ro trodo Mto ASrd Co.&ed A.6-o1s RoodNeycorror CodewKR"rot. Naleod BoardCeddoielof Aodrorfieoýo NO-OS to do,, W rormprefc No. 6 2010 CERTFCATE OF INSPECTON

1. EymehedeN

heporeore ~ ~ h.Uisevodd-o

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ikoeroo..d orreAhrertaerrioiiod. BoeW olo00 rrrr~ec PvErjroeareo SoudeEloo7UASdECode Ore od AeNerae eoerdbrperoo CedeTR" ok.. Ire., oortdeobed t addyrpo. Frepoeror,herraro rordardped.,., v.Tyr,rr "reo be rhdes i.r -r -11.

                         .w preo.Wotla p.orpy doorore 1-17.W     oe        (Add oe      oer oroed rithrrio irpefioro.9 D. 41%              Sit~edM .                                                __j~.                                        Cý1AA

15 RFO Inservice Inspection Summary Page 220 of 238 FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #l, 5501 N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 D05O070-5 FORM NIS-2/NR-1AINR-4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl

1. Owner FirstEnergy Corp. Date Februaiy 6, 2008 76 South Main St.. Akron. OH 44308 Sheet 1 of 3 2 Plant Davis-Besse Nuclear Power Station Unit #1 5501 N..SR. 2. Oak Harbor. OH 43449 Order# 200249961 RPlvrOrgýnn P.O.Ný..*b Na...el 3 Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR S501 TN.SR. 2. Oak Harhbr. OH 43449 Authorization No. 20 Expiratlon Date 07117/10 4 Identification of Svstems i .......

Piessurizer DB-r0O02 (Subsvs 064-04) DB-I'002 5, (a) Applicable Construction Code ASME IIl CL.I 1968 Edition 68 Addenda Code Case No (b) Applicable Edition of Section XIUtilized for Repairs or Replacements - 19 95 Edition. 96 Addenda Code Case N-416-3 . (c) Design Responsibilities FirstEnergy Corp.. Welding Services Inc.(WSI), Stiuctural Inteety Assbciates Inc: R . Identifiretion. nf rnrnnnent* Ransird nr Renntar.ed and Rnnlsnnmant Cnmnonnentsq 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 Pressurizer Babcock & Wilcox 620-0014-59 N-157 DB-T002 1972 Repaired Yes

7. Description of Work The sample nozzle replacement included cutting the existing nozzle flush with the outside diamenter of the pressurizer, installing a sacrificial plug in the nozzle bore and depositing a weld pad aroundthe existing nozzle bore. The nozzle bore and sacrificial plug were machined out 1/2 the thickness of the pressurizer shell, a new replacement nozzle was installed into the newly machine bore and welded to the new weld pad.

All phyical work was performed by WSI per PO# 103571 and WSI Uaveler# 10357 1-TR-015 .......... All work completed by WSI is documented on "NR-28 & 29" Report of Repairs. FirstEnergy Corp. (D1) performed a VT-2 initial inservice leakage test. Test was satisfactory. Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure NOP *sl Test Temperature NOI °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 (T.,Mdot, ) at N/A (Lonlea* NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size Is 8 112X 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.

15 RFO Inservice Inspection Summary Page 221 of 238 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 De-S070-5 FORM NIS-2/N R-I/N-Ve---

9. REMARKS .Apl~l~u~tr~DLaeotb~~~d ..

Welding Services Inc .. CERTIFICATE OF COMPLIANCE I, Richard R. Cockr'ell 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" starpp..xpires 07/17/10 Date 02-106-0)8 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 CI , of Hartford,C' C .. . haveinspected thework described in this report on . F*n-r 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 17-T &B Signed

Commissions 'f 2 ',B et(O

                        ...                                   d&                                                                              VAT IN- Cb       "      ...

andl,1do~ndl O0no.5) 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 FENOC Signed Q.C, at+. Date (name000q0 repai 04ron0) rop'oeOawe) (a01toooe4 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 CI of Hartford, CTl 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 bai Z 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.N o B_) (040 0 m.,0.), 7ý,-

15 RFO Inservice Inspection Summary Page 222 of 238 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=%4 NR-I REPORT OF REPAM D NMODIF0CALOO*[EI OkREPLACEAENTEIý to NUCLEAR CONPONENTAND SYSTEMS 17740JCLEAR POWERPLANTS 0.W9900003o/byWelding9 S.Mri 1- 103571 TIR-20 ___ 2225Sly'd Coop,.K0 - GA 3G071

                                                                                                              .099 799SoN AjoLan.OHf N-2 9ooo     d   00ne d-      f           pWooo                                            Dii93-90190.5501Ni.St-l R~te.2, 00k Hill-0. 0hio 43449 osyoose                                                               RoadeRPCoaling    Sytenm"RCS' N.         Mg 1-ite we 1.,

ee en ft 0of 00N.0059, Yo-oRW O61o/l ~ mk c CodeI9 Ro0MORL 012 A0 NIA 1-72 ASOIEin9 19W9 A o Th

                                                   ~on~oSO..O~oonu
                                              . flosto                    S~loo IRoo

0. Io0.o35/oo 90090e0o j 000 SileloRd Ro,0lele 20.7ýMe 20 N/

1 -]50/O100XS3.biesooooo.033ooo 1995 l9ow H/A 7 Ask'L00 (e& 009.op5 500.00,0396,0000

                                                                 -M.                                                1999     1990N-6W0-.                       SeeVneII 59                                                                       -m                 im                              05-WA-5eeo,,ed8o0 Code       fi  9      0500000 oOqt-~oO 1999C                5999                             0.990~..tWC SDooopootoobd/oo Prezsor Test to be performed by ownoer.

II Ds V-oros The9SampleNo551 replacoomont irdouded a pristonir bounodary chansgefoi the3101109 tiolS 919019 the to of die P093509/Rter. ThIt change ms9901d8 pRsS0tre by iritsiOnbgan59101900/Sttemperatuore, 19stperbead 00000091 wId pad p01101019In35991019leR withthe 0001004specfed inCR8e Case N-63B.1as niodified by HekRIReooooesl RR-A31. InconbrisionR WitlhWS~sTmOler # 103571-TRI-015 The 059011003301901990313of0Me9990dP0910.00100we J -O5 to29109091the 522001to0the5tie Ooooton. IC-PZR-SAMPLE WSI91 field somnarbRetSarrigg.PW 'Pad WRI1Se opeJ/"-rp 0t1 0,9001999999 helidmld e bohoRC-PZR-Saeple

12. Remelts9: PadWeld8WPS: 01-43.T-R03-1028301 R/O:Weld Wine ERNIoCOre7A SPA 5.14,.035 'GTAW Machine' Nozzle to Pad Weld WPS: 43-43-TC001R/3; Weld Wire ERNICrF`-TA SFA 5.14:3/M2 "GTAWManualr I, 193r930.0 E. Herat ,rowidy09d9tho099 e o o l.iod Ibefid 0.0 re33e5 i3&I report3 Co t "99f9*0Z05i0, 3odifiwd0a0 9 o, pk - ,a9iitie ee099 d0159i8 b-oedcen5fo00 0 S3e5 XI tf0.

to t AS1,MCode90d 01999503990 90oardhapienionCodoNsH10 013 Nation ed Cei of Atiho- NR-69 to o0netdin'NR3M0e0q3 / N93.8 2010

                                                                                  *'Trrf-WICA TE OF I*NSPECTION I,       IWO          Gi. Lt.AB,  Nodina voted3       o3000 300o0de         byTb9n,5009.9oDod   of 90100sd Pne-o   0Viene 000091~   ~o ~ ~                by010/9009 o                             .01310090 531009000the090-,    nen"Mionce0,9090305 0993i100199t d-M       oof930E;0                                                      f.f 000 f309hiooR01dtend0elof ft3095    mp , -iito      n-0       -o 00(9M50.10310519 o 05500503100t cti                  %           03330 Section  22 f0,011.1AW   Cdeode eel 009N&, 90end o0     o d900Cod9'NR 000 By3000 brRllso             90019 ned-neened095510150 eoitw     .03 -W m-kne   F      o- . 31P099                10303
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15 RFO Inservice Inspection Summary Page 223 of 238 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 F0R REPORT NU1-1 OFREPAIS.[AD MODIFICATIONE OR EPIACEMsIO14[A 3. (-c 3 TONUCLEAR rOM7ON7NT jnD 91 -- INIIA

                                                                                                                    -          -   P131. PLAN-v 0./ose/pW.ODnlO                                             So'ew/e I                                                            103571       "11-291 222 Sy/asOCosI.Noreo.,GA        30071                           ____________

2 0-o PhIL nEmryCorp. 3 KIs 3W0-ID/lppw avh-00b. 5501N. S~ale RNt 2,00k Hobe, Oh/o 43449 t

4. S/ad ReactorCoalingSys em -RCS-9wIkh 30ool PXP-i.

So.U- MaI.ww sI-aasoo dW IN sooptobs H-1 WG N-i L NIA ' A 2007 A .11 10 201 A RePaiF 50~ ~ ~ ~ od180o/20033woo/i ~ W 1o D.,iv so&sd T/t/w~ss0sss3A~./0Nos .ý I, 11 0- Y_ '- Edkkalo s , -A-Coud SP NiA N-A N I A 11989 AA NO _ __ft 0Se0s Ina 1 nd 14 . I

lallBo*P oI 0*/A ' toA NA N/A 19 AWEW 71 WA

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               /0 1o0,sw0oosA                    0/M*-             ]                             deePmo-                     00.0___1              M     Cý.aso)~                 N0IA
                                                                    'Pressare Teot to beperformedby owner.

o1)1D-"oo00S Mi~lelimnfe o w otgiao0 eo/o1/o9SampleNzes l woas lea. 50/00 hose ppe Rle. TI/N report\0ll RddOlrs0/ rea/ollwanessof this 1100e. 90S1WElfallow the oN/NOfield weld son betstiat p ~nI/d00ao/la aoalw - aarpl lwd a performed in acoordaoce0111,09 theool/vs sPecifed in Code Case N-838-1as modifiedbysRellNtRequestlRR-A31,in eonjuwoooe Y0013557 Traaeler# 103571-TR-015lateatRev. This/wplemoolo a oe 0010NRC aooeptcdtepoa/rldan in1ac0ordasrce wi/h Rellef Rwgoet RR AS1 andOWo 01/10101 Code CamitN-638-1. Snell Bor Field Weld N0wh8T-00: FIN 28a, 28b. 28C. 28Sd.See attac/ed

12. Roorsiai:

SmelalBos PI'/no WI'S: 06-08-T-001N/I Weld Wire ER308L SPA009:3/32"GTAW ManoaT-CERTIFICATE OFCOMPLIANCE

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                                             =              A;        N                             NR-110            N=lhsaNR spo         1p01     N-6.1          201/0 NRlCeoflaled0/aWde   .Srle s,        E OF INSPECTION TI~
                         *wotý 1.~

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15 RFO Inservice Inspection Summary Page 224 of 238 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-11NR-'I OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section X1 1 Owner FirstEnergy Corp. Date February 6, 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 Hartbor. OH 43449 Ordei# 200249962 Rep,.rOrgranUoneRo. No. jobNo. .t

3. Work Performed by FirstEner:y Nuclear Operating Co. Type Code Stamp Ng 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No 20 Expiration Date 07/1 7/10

4. Identification of Systems Pressurizer DB-1002 (Subsys 064-04) 5 (a) Applicable Construction Code ASME In CL.1 1968 Edition 68 Addenda Code Case No (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N-41i6-3 (c) Design Responsibilities FirstEneig Corp., Welding Services Inc.(WSI), Structural Integrity Associates Inc.

6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other ldentiflcation/ Year Repaired ASME Name of component Name of Manufacturer Serial No. Board No. Jurisdictional No.. Built Replaced or Code Replacement Stamped Pressurizer Babcock & Wilcox 620-0014-59 N-157 DB-ID02 1972 Repaihed Yes

7. Description of Work The thermowell nozzle replacement included depositing a weld pad around the existing thermowell bore and one J-plep to attach the nozzle to the weld pad location.

All phyical work was performed by WSI per PO# 103571 and WSI traveler# 10357 I-TR-009 All woik completed by WSI is documented on "NR-3 1" Report of Repairs. FirstEnergy Corp. (DB) performed a VT-2 initial inservice leakage test. Test was satisfactory. 8 Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure NOP psi Test Temperatu re NOI TF Pressure Relief Valves: Service N/A Size N/A Opening Pressure N/A Blowdown (Ifapplicable) NIA Set Pressure and Blowdown Adjustments Made Using N/A (T. ,-. . at N/A NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (11size is 8 V/ 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 too of this form.-

15 RFO Inservice Inspection Summary Page 225 of 238 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 3 1, 1978 DB-0070-5 FORM NIS-2/NR-1I4N-R 4 A*ppfl~bln Man~fldu,,, DatsDp~onjob.'ADa.hdd ""::

9. REMARKS Welding Services Inc.

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 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" stq expires 07/17/10 Date b2*.4-, FENOC Signed Q.C. CERTIFICATE OF INSERVICE INSPECTION I, 1homas 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 OH1O and employed by ... HSB CT of Hartford, CI have inspected the work described in this report on Fe.-[, oP, and state that to3 the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Sectile-n XI of the ASME Code and the National Board Inspection Code "NR" rules.. By signing thiscertificate, 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 *,7T!r)g Signed Wm-'m . Commissions K 5 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 "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 Hanrford, 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 ba.ire 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 _ _ _. and1adýiona..ýMnj)

                                                                                                                                                    -iýZ

15 RFO Inservice Inspection Summary Page 226 of 238 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 FORM14R98-1 8/9/08/ Of /FEPA/RIE1 MO/3IR/CAT/ONF- ORREPIAC9EMENT[D 0 -4 TONUCLEAR COMPONENTS A3ND SYSTEMS /N NUCLEAR POWER PLANTS I WoOp.88/by W e/ing Se9ees Inc. 1/3571t NR-31V 2220 S0kY/d Court NoPCao*,GA 30071 2 First EnergyCop. 76 S Mab, Akro0n, OH 3N- Wftf/do/olpag" /C O es MA.N.St/At Rt.. 2. Oak H/rbo, Ohl. 43449 3,- Ructor CoOfng Sysltm RC

              ;,                                         S    ,J,.Ao.      o lb.      /f    beo                                                                                 Div.I     ol N41 Bd. Kl                                Seý                                  colftý T.0N*.0*NI                                                            A          WA       NIAN/A        200     ASM*I                /-1                  16 tASAC CO/I10090 b1199e/oo          la

1599 109* N/A

              /      .O/Ca*590111/CO/Naa/OomadOiaoa11              a/all,                                   1995                  NOS0                     N-*30-1,SeekI1e11 4
               /1CaaoCoaCoO/(aa/.oo                     Caa11 11l/a/8/1111/88                            AUEME/  198         Sunc/108                              WA 9 Diseeqeon1býi0 FE.-    R-st Lý-W NucleerOý-MttrtgCý
               /0     0.,i                        /Poeres                               [obe./p                   e                        .o[_ed                        N/Ab PressureTast 1 be performed by ome1r, 1 Do-1/pbodo                   The ThermF vea Nom01ereplacement included a Pressure boundary change from the hterlor to the exteftt of Fle Pressurzer. Thi'scha/8/5 w8smade p0                  .e by /I         an /mblenltepe11ature. Temperaeed k/Carl/l -0/d pad performed In accordance vlbththe co/Fs speified in Code Case N-638-1 w9mode by R/R1elRequest RR-A31, Ln =j/clfon wi/h MSI'sTraveler* 103571.TR-009 WarestR/0, Th.saimolements 0onelImeNRC a0te/tnd mo0or atn hIraccordance w8thRe//f Re/C.ol AR A31 ind for mend Code C                                    54-.38-I.

The mpg* work consisted /f one pad weld. and one J-prep. W ettac/ the naole to the pad location, RC-PZR-TWRC15

               +/-2      field weM num//0051Y-PW "015 Weal                   504 /-plrpaqvie      Davis Besse Wodweld/1nu/mber       RC-PZR/-IWC15

12. Remarks: Pad Weld WPS; 01-43-T-803-19/2836 PI. Wed VWreERNiCfFe-TA SFA 5.14; 035 "GTAW Ma.chh/e CERTIFICATE OF COMPL ANCE 8

Cooee ed* aý . W- -lid. de;.6W bovecoefb- t/ 9CaXl of theASMECode and tb iN R8.oo/d hpeeA.810 cCde.NRF nd 1/e88*8d/ Rd Cercate of t&//R0-9pfl/o//a /9/9.N.*48y/9d9 /9.19. p1 I NRC//ifitao/I0080dlC01/0 O88

111of 0yde 1opClnC

                                             -e-. 6.              ~CER tfATE                              OF INSPECIION 18pelal da/Ca111C~~o/ylo 1

Obheo//C/91Ca0 of ~ 0 11/ ood epla/d by 3180o9 X[ofd/ ASMCCode and ohe Ntion.8 Bo/ldhubpeo Code 8R' eld. 0/y18880/190 0119990/I, 1 8Cab1/l//8/d1r11 0 dfil11n/ y /a/1ploerran8/y 9 1

                                                                                                 -       -11y,   xplood C or /ed90phiL coo ,n1 the oo             i 8or "f repor FRlthcrmoze   Dei dw .d-Wed nor */ -lploy.           0 b. liableiany - for oij11 *W-                                                       ***,,*,                            . -- **. - "-                  t 'Akio"T

15 RFO Inservice Inspection Summary Page 227 of 238 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-VR4 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI t ..owner . F ir -stE ner -gYC o ll). Data January 3 1, 2008 N.O.. 76 South Main St, Akron, OH 44308 Sheet 1 of I

2. Plant Davis-Besse Nuclear- Power Station Unit #1 N5 5501 N. SR. 2, Oak Harbor-, OH. 43449 Order# 200261534 RopoirOueV'lb P.O.No..JobNo.,.

3 'Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp N 5501 N. SR. 2. Oak Harbor. OH 43449 Authorization No. 20 Expiration Date 07/17/10 4, Identification of Systems' Reactor Coolant Pump 2 Seal Injection Line -11/2" CCB-8-1 Piping - (Subsys 064-03) 5, (a) Applicable Construction Code ASME II CL.2 1971 Edition No Addenda Code Case No

          * (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements    .19    95      Edition       96          Addenda Code Case           N-416-3 (c)1 Design Responsibilities. FirstEnergy Corp.

6. Identification of Components Repalred or Renlaced and Replacement Components Manufacturer's National Other ldentification/ Year Repaired ASME Name of Component Name of Manufacturer Serial No. Board No, Jurisdictional No.. Built Replaced or Code Replacement Stamped I - 1 1/2" Coupling. Energy & Process Corp. HI S69060 N/A N/A 2006 Replacement No

    *18" x 1 1/2" Piping            Energy & Process Corp.              -T# 443566        N/A              N/A                       2002       Replacement       No*

7. Description of.Work Engineering Change Package (ECP) 06-0154-00 relocated drain valves MU247 & MU 247A down stream of MU 243 to allow piping to drain prior to the Local Leak Rate Test. (LLRT). Installed one new coupling & replaced 18" of piping, Code case N-416-3 NDE requirements were implemented during installation.

A VT-2 initial inservice leakage test was performed satisfactory. 8 Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure Yes Other Yes Pressure NOP psl Test Temperature NLO'I oF 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' (t"- mýii_ 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 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.

15 RFO Inservice Inspection Summary Page 228'of 238 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/N4'R-+ 4p~rtaO~e Idanl~aca,, DataP1ochai b. AnB.C,

9. REMARKS N/A CERTIFICATE OF COMPLIANCE Richard R. Cockretl , 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" starppexpires 07/17/10 Date O1-31-68 FENOC (nnm.of 1mt om0 on) Signed (*tnon..dt==n...b*a} 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 C1 of Hartford, C'I have inspected the work described in this report on &3,.. aý,o? and state that to the best of my knowledge and belief, this repair, modification or repla6ement has been completed in accordancewith Sectiorn 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 kj_, ps S VA A IM4 Commissions ,33* * - , ___________Signed w6 W34 t CERTIFICATE OF COMPLIANCE I, N/A , certify thatto 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 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 Hartford, CI 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 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 andI.01d~on..andnoD

15 RFO Inservice Inspection Summary Page 229 of 238 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/Nf---OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI I Owner Fib-stEnergy Corp. Date January 2, 2008 76 South Main 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 # 200266309 FPe OrgandzatsoP.O.No., .3 CO.

,t

3. Work Performed by FirstEner-gy Nuclear Operating Co. Type Code Stamp NR NO.

5501 N. SR. 2. Oak Harbor. OH 43449 AuthoriZation No 20 Exoiration Date 07/17/10 4 Identification of Systems High Pressure Line Flow Test Isolation Valve, DB-MU442 (Subsys065-01) 5 (a) Applicable Construction Code ASME III CL.2 1971 Edition No Addenda Code Case No (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements 19 95 Edition 96 Addenda Code Case N-416-3 (c) Design Responsibilities First Energy Corp

6. Identification of Components Repaired or Replaced and Replacement Components Manufacturer's National Other Identification/ Year Repaired ASWE Name of Component Name of Manufacturer Serial No Board No Jurisdictional No. Built Replaced or Codie Replacement Stamped 1- 1 1/2" Pipe Tee Tioga Pipe Supply Company HI# 702521 No TC PA 2007 Repaii No

7. Description of Work Installed new vent valve (DB-MU442) in Makeup Pump Test, Per ECP package 07-0094-00.

Code Case N-416-3 NDE requirements were implemented. A VT-2 Initial Inset vice Test was completed satisfactory.

,C.

8 Tests Conducted: fHydrostatic No Pneumatic No Nominal Operating Pressure Yes Other No Pressure 1502 psi 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 (TetMOeCSm) at N/A (LWo) NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2i 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 recorded at the too of this form.

15 RFO Inservice Inspection Summary Page 230 of 238 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 3 1, 1978 DB-0070-5 FORM NIS-2/NR-1/NYR-Appltcae bt .sl DaWRepofla

1. W,Alahd

9. REMARKS N/A CERTIFICATE OF COMPLIANCE I, Lynn R. Wagnei , 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 OI\-O -D- FENOC Signed 41 Q.C. CERTIFICATE OF INSERVICE INSPECTION I, T'homas G. Laps .holding a valid commission issued by tIe 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, CI have inspected the work described in this report on J_1&4. 5 ? e and state that to the best of my knowledge and belief, this repair, modification or replacement has been completed in accordance with Sectior. 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 1w, sr* JMldictianarMno5) CERTIFICATE OF COMPLIANCE j, N/A , certify that to the best of my knowledge and belief the statements made inthis 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 CI of Haitfoid, 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 with this inspection.. Date Signed Commissions (NationaDoa,,(Brd

                                                                                                                              . doaean.,, ),

Page 231 of 238 15 RFO Inservice Inspection Summary FirstEnergy Nuclear Operating Company, 76 South Main St., Akron, Ohio 44308 Davis-Besse Nuclear Power Station Unit #1, 550t N. St. Rt. 2, Oak Harbor, Ohio 43449 Commercial Service Date: July 31, 1978 DB-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 January 29, 2008 76 South Main St.. Akron. OR 44308 sheet 1 of I

2. Plant Davis-Besse Nuclear Power Station Unit #1 5501 N. SR. 2. Oak Harbor. OH 43449 Order# 200296303 Adý- Pp.,O Ngaon P.O .;* No.,

3 Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp NR N2ak P'141i'1N-. ;R. I- Onk THarbor. 014 43449) Authorization No 20 AOdt* Expiration Date 07117110

4. Identification of Systems Hanger EBB-I-SR9, DB-SNC178 (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 9..5 Edition .96 Addenda Code Case No (c) Design Responsibilities FirstEnergy Corp., Lisega Inc

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 Snubber Lisega Inc. 61222/29 N/A DB-SNC178 Unk. Replaced No Snubber Lisega Inc. 04616533/002 N/A DB-SNC178 2007 Replacement No

7. Description of Work Existing Lisega snubber (serial # 61222/29) was replaced with a new like for like replacement snubber (serial# 046165331002).

A VT-3 visual inspection was completed satisfactory. 5.(a) cont. ANSI B331.1 & 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 N/A Slowdown (ifapplicable) S.. 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 Yt 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 top of this form.

15 RFO Inservice Inspection Summary Page 232 of 238 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/NVRR4 AppclablaM=ndalue- DataMap Icb lh. d

9. REMARKS N/A CERTIFICATE OF COMPLIANCE I Richard .. 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" stapV~xpires 07/17/10 Date C>)-297-DE FENOC nfam, of moperowganzatm nm" Signed sg L.Q.C.

[IauII,no ,crI'mi.*)*'e 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 CM of Hartford, C" . have inspected the work described in this report on J.A.

2 and state that to the best of my..knowledge and belief, this repair, modification or replacement has been completed in accoidance 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, concerningt-he 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 o Signed Signed Commissions" WA II m~~an,,. B-n' o fanda Dr0.,.,J 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 Dat&* (-ad FENOC

                                                                ,v omg.'ma ga-ait ýo Signed (tafoh,,ad    rtm .latm,)

Q.C. CERTIFICATE OF INSERVICE INSPECTION t 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, CI 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 Sicned -Commissions (NaimnB.,d ow

                                                                                                                                 .1djwt*Como.ýa~M.

15 RFO Inservice Inspection Summary Page 233 of 238 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-1t+V-R4 OWNER'S REPORT FOR.REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section X1 I owner FitstEnet'gy Corp, Date Jauaty 2.2, 40UU8 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# 200296330, 3 Work Performed by FirstEnex y 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 EBB-1-SR9, DB-SNC234 (Subsys 083-01)

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 No (c) Design Responsibilities FirstEnergy Corp., Lisega Inc.

6. Identification of Components Repaired or Replaced and Replacement Components of Manufacturer Manufacturer's National Otter Identlficatlon/ Year Repaired ASME Name ot Component Name Serial No Board No. Jurisdictional No. Built Replaced or Code Replacement Stamped Snubber Lisega lnc- 61305/122 N/A DB-SNC234 Unk. Replaced , No Snubber Lisega Inc. 04616533/014 N/A DB-SNC234 2007 Replacement No

7. Description of Work Existing Lisega snubber (serial #61305/122) was replaced with a new like for like replacement snubber (seiial# 04616533/014).

A VT-3 visual inspection was completed satisfactoty. 5.(a) cont. ANSI B31.I & MSS-SP5S8 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 (ifapplicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A r-e, M~ediu} at N/A (Locationt NOTE: Supplemental sheets Inthe form of lists, sketches, or drawings may be used, provided (1) size is 8 YzX 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 too of this form.

15 RFO Inservice Inspection Summary Page 234 of 238 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 Athj - Ra.pi W.Anr D b. Macbe

9. 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" starnp;e pires 07/17/10 Date o FNOC SignedQ.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 CI of Hartford, CT ;have inspected the work described in this report on jJ4. 3c, amlB 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 k 1-3019e, Signed ~Commissions B 014 abd$uti=icem aben'.)i 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 CVR' 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. .n 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 CI 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 ....

15 RFO Inservice Inspection Summary Page 235 of 238 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/NIR4-OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI I Owner FirstEnergy Corp. Date July 24, 2006 Name "7t ,qouith Main St.. Akron. OH 44308 Sheet 1 of 1 2 Plant Davis-Besse Nudeat Power Station Unit #(1 5501 N. SR. 2, Oak Harbor, OH 43449 CR-05-05569 3 Work Performed by FirstEnergy Nuclear Operating Co. Type Code Stamp I N5k 5501 N. SR. 2. Oak Harbor. OH 4344*9 Authorization No. 20 Expiration Date 07/17/07 4 Identification of Systems DECAY HEAT REMOVAL SYSTEM (Subsys 049-02) 5 (a) Applicable Construction Code ASME mH CL.2 1971 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 Responsibilities ITI GRINNELL CORP., 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. Buit Replaced or Code Replacement Stamped DH REMOVAL SYS. III GRINNELL CORP, N/A N/A N/A 1977 REPAIRED YES

7. Description of Work Implementation of ECP 06-0039-00. ECP 06-0039-00 terrates the followint Decay Heat system oioinp to a desin piessure/temoerature of 320 psig and 350 degrees fahrenhiet, 12"-GCB-7, 10"-GCB-7, 8"-GCB-7, 4"-GCB-7, 2 1/2"-GrCB-7, I"-GCB-7, 3/4"-GCB-7, 18"-GCB-8 and 12"-GCB-8.

It should be noted that original piping code data plates did not contain design piessure/design temperature information so piping relate name plates were not attached. No physical work performed. 8 Tests Conducted: Hydrostatic No Pneumatic No Nominal Operating Pressure No Other No Pressure psi Test Temperature _F Pressure Relief Valves: Service N/A Size N/A Opening Pressure Blowdown (if applicable) Set Pressure and Blowdown Adjustments Made Using rr~t hwýo) at (Lc 6.) NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2hX 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.

15 RFO Inservice Inspection Summary Page 236 of 238 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-1INV#R4" App~aobln M dat8CW,- Oa- Roatratobe Arlt~dý

9. 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 ertificate of Authorization No. 20 to use the "NR" stamp expires 07/17/07 Date 7/.2-y'40.'__FENOC (n/.no .pt~.t n). 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 C1 of Hartford, C I have inspected the work described in this report on %X ýa 6 and state that to the best of my knowledge and belief, this repair, modification or replacement has been comp eted'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 ais 2U0 Signed t*'- Commissions O~.fonntnt) 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 12/13/07 National Board Certificate of Authorization No. 20 to use the "NR" stamp expires 07/17/07 Date ______ __FENOC Signed (oathnz torceaatatna) 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, CI 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

                                                                                                                    )flbtatflO 500,0(tOO.ta0~a~nana).

and o)e~at,0,o andno))

15 RFO Inservice Inspection Summary Page 237 of 238 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/NV-R-1 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

                                                   -As Required by the Provisions of the ASME Code Section Xl 1 Owner          FirstEnergy Corp.                                                          Date     May 29, 2007 76 South Main St., Akron. OH 44308                                                  Sheet I of I 2 Plant          Davis-Besse Nuclear Powere Station                                         Unit                              #1 Na-.

5501 N. SR. 2. Oak Harbor, OH 43449 ECP #06-0039-00 Add-,

3. Work Performed by FirstEnex-y Nuclear Operating Co. Type Code Stamp NR 5501 N. SR. 2. flak Harbor, OH 43449 Authorization No 20 N SR 2 1;901 Oa.kHabrO439 Expiration Date 07117107 4 Identification of Systems Decay Heat Piping (Spools GCB-7 & GCB -8) 5 (a) Applicable Construction Code ASME INlCL.2 1971 Edition N/A Addenda Code Case No (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements 19 95 Edition 96 Addenda: Code Case No (c). Design Responsibilities Fiist Energy Corp -

6. Identification 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 Jurisdictional No. Built Replaced or Code Replacement Stamped Decay Heat Piping IT" Grinnell Corp N/A N/A N/A 1977 Repaired Yes

7. Description of Work implementation of ECR 06-0039-00 shall re-rate line class GCB-7, "From Motorized Valve HV DH 11 to Decay Heat Pump Suction Piping " and GCB-8, "Decay Heat Pump Piping from and including Gate Valves DH 2733 and DH 2734" to a design pressure of 320 PStG and a design temperature of 350 degress F. The intent of this ECP is to document compliance with the provisions for re-eating activities in accordance with ASME Section Xi , " Inservice Inspection of Nuclear Power" 1995 Editon with 1996 Addenda, Article IWA-43 12. A re-rated nameplate was not installed on the existing piping.

a 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 Slowdown (if applicable) N/A Set Pressure and Blowdown Adjustments Made Using N/A FreerMeCCWf 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 I through 8 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.

15 RFO Inservice Inspection Summary Page 238 of 238 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-"070-4 FORM NISS-2/NR-11NVR-1

                                                                                                             -Appfi1 l M-9sno, Da Refto w b Aa*hed

9. REMARKS N/A CERTIFICATE OF COMPLIANCE I, Richard R. Cockrell , certify that the statements made in this report are correct and the repair, modificationor replacement of the items described above conforms to Section XI of the ASME Code and to the NationalBoard Inspectioh Code "NR" rules..

National Board Certificate of Authorization No. 20 to use the "NR" stane-expires 07/17/07 Date 0 5-2 91- o-7 FENOC Signed. .(.,. Q.C. CERTIFICATE OF INSERVICE INSPECTION I, Tom 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 CI ' of Haitford, C1. have inspected the work described in this report on MAI'.l 2%j "rnd state that to the best of my knowledge and belief, this fepair, modification or replacement has been compleed 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 5 Jq 01 Signed Commissions Z q-*33 " A 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 12/13/07 National Board Certificate of Authorization No. 20 to use the "NA" stamp expires 07/17/07 Date _FENOC {nameofmparwmc.,meli'.on~) Signed (.vtho.,ze rros~ntall¢) 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 Haitfoid, 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 a Jo04a,4.n..04 no4/}}

L-08-136, Cycle 15 and Refueling Outage 15 Inservice Inspection Summary Report

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L-08-136, Cycle 15 and Refueling Outage 15 Inservice Inspection Summary Report

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