ML031970448
ML031970448 | |
Person / Time | |
---|---|
Site: | Wolf Creek |
Issue date: | 07/08/2003 |
From: | Moles K Wolf Creek |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
RA 03-0085 | |
Download: ML031970448 (14) | |
Text
WEOLF CREEK'NUCLEAR OPERATING CORPORATION Kevin J. Moles Manager Regulatory Affairs JUL 0 8 2003 RA 03-0085 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
References:
- 1) Letter ET 95-0112, dated October 31, 1995, from Robert C.
- 2) Letter WO 95-0189, dated December 27, 1995, from Otto L.
Subject:
Docket 50-482: Inservice Inspection Program Second Interval, Second Period Owner's Activity Reports Gentlemen:
In References I and 2, Wolf Creek Nuclear Operating Corporation (WCNOC) requested use of ASME Code Case N-532 aAlternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000" in lieu of current ASME Section Xl reporting requirements.
In Reference 3, the USNRC concluded that the proposed alternative to use Code Case N-532 and the clarifications contained within References 1 and 2 provide an acceptable level of quality and safety and approved the use of Code Case N-532 for use at Wolf Creek Generating Station. Code Case N-532 requires that an Owner's Activity Report (Form OAR-1) be prepared and certified upon completion of each refueling outage. Each Form OAR-1 prepared during an inspection period shall be submitted following the end of the inspection period. The enclosures provide the Owner's Activity Reports for the period October 4, 1999 through December 31, 2002. This timeframe constitutes the second period of the second interval of the WCNOC Inservice Inspection Program. Within this period, Refueling Outages 11 and 12 occurred. The enclosed Forms OAR-1 (Reports WCRE-10, 12-P2-RF-11 and WCRE-10, 12-P2-RF-12) correspond to these outages.
P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equaf Opportunity Employer M/F/HC4VET
RA 03-0085 Page 2 of 2 There are no commitments in this letter.
If you have any questions concerning this matter, please contact me at (620) 364-4126, or Ms.
Jennifer Yunk at (620) 364-4272.
Very truly yours, KJM/rIg Enclosures cc: J. N. Donohew (NRC), wle D. N. Graves (NRC), wle T. P. Gwynn (NRC), wle Senior Resident Inspector (NRC), wle
FORM OAR-I OWNER'S ACTIVITY REPORT Report Number WCRE-10. 12-P2-RF-l I Owner Wolf Creek Nuclear Operatine Corporation (Name and Address of Owner)
Plant Wolf Creek Generating Station. 1550 Oxen Lane Northeast. Burlington. Kansas 66839 (Name and Address of Plant)
Unit No. I Commercial service date 9-3-85 , Refueling outage no. II (If applicable)
Current inspection interval 2nd (1st. 2nd. 3rd. 4th. other)
Current inspection period 2nd (1st. 2nd. 3rd)
Edition and Addenda of Section Xi applicable to the inspection plan 1989 edition with no addenda Date and revision of inspection plan WCRE-10 Rev. 2. dated 10-1-2000 Edition and Addenda of Section Xi applicable to repairs and replacements. if different than the inspection plan same CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct. and that the examinations. tests. repairs, replacements, evaluations, and cottective measures represented by this report conform to the requirements of Section Xl.
Certificate of Authorization No. N/A Expiration Dat Dt N/I (If saplicable)
Signed Dennis E.Touawa -PM,,L" 'Ene.
0 wner or Owner's Designee, TitlE 5Jr Eneineer s9-/ - IO Date _5Z/ / /°/0 CERTIFICATE OF INSERVICE INSPECTION (lliSiJ}/
1.the undersigned, holding avalid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Provinceof Kansas andemployed by .L...bI..r.l.....1......h .......
- L.....,
C
...... of Johnston. Rhode Island have inspected the items described in this Owner's Activity Report. during the period October 4,1999 to November 7, 2000 ,and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requiremtents of Section Xl.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations. tests, repairs, replacements, evaluations and corrective measures described in this 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.
iyv ,ll~live, Cormrnissions KS#299 Inspector's Signature National Board. State. Province. and Endorsements Date /'l>X)/
L//S Factory Mutual Insurance Company This form (E00127) may be obtained from the Order Dept.. ASME. 22 Law Drive. Box 2300. Fairfield. NJ 07007-2300 OAR-I 12-P2-RF l I Page I of 5
FI TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Completion of RF-1 1 (1-2, P-2)
Examinations Examinations Examinations Credited (%/e) to Examination Required For Credited for This Credited (%S) for Date for the Categoxy The Interval Perlod* The Perlod** Interval Remarks B-A 24 2 8 21 B-B 5 2 40 60 B-D 36 4 11 53 B-E 113 0 0 33 B-F 14 2 14 57 B-G-l 219 36 16 47 Note I B-G-2 15 7 60 Note 2 B-H 2 0 0 5O Note I I B-1A 170 0 0 26 B-K Note I I B-L-2 0 0 100 Note 3 B-M-2 7 0 0 57 Note 4 B-N-I 3 0 0 33 B-N-2 6 B-N-3 1 B-O 4 0 0 100 B-P Note 5 Note 5 Note 5 Note 5 Note 5 C-A 9 0 0 33 C-B 7 0 0 13 Note 9 C-C 19 5 37 C-D 1 0 0 100 C-F-1 84 0 0 33 Note 6 C-F-2 28 8 29 57 Notes 6, 10 C-G 4 0 0 25 C-H Note 5 Note 5 Note 5 Note 5 Note 5 AUG 500 117 23 56 Notes 7, 10 D-A 44 13 30 61 Note 8 D-B Note 8 F-A
___________ .7 293 .1.
87 &
30 60 4 This column is interpreted to represent the cumulative number oJ exams performred to date in this period.
This column is interpretedto represent the cumulative percentage of scheduled examsrfor the interval which have completed in this period to date.
OAR-I 12-P2-RF-I I Page 2 o5
Note 1: 216 of the 219 examinations for category B-G-I are comprised of the reactor vessel studs, nuts, washers, and flange ligaments. The other three examinations are performed on the studs, nuts and washers, and flange surfaces of a reactor coolant pump. In RFO-9, RCP-D was disassembled, and the flange face surfahces were examined.
Note 2: For pumps and valves, examinations are limited to components selected for examination under Examination Categories B-L-2 and B-M-2.
Note 3: Examination is required only when a pump is disassembled for maintenance, repair or examination.
Examination is required only once during the inspection interval, thus completed percentages indicated may not be consistent with Table IWB-2412-1 schedule. In RFO-9, RCP-D was disassembled, and the pump casing surfaces were examined.
Note 4: Examination is required only when a valve is disassembled for maintenance, repair or examination.
Examination is required only once during the inspection interval, thus completed percentages indicated may not be consistent with Table IWB-2412-1 schedule.
Note 5: Visual Examinations (VT-2) are performed as required for a fuel cycle, 40-month, and 10-year system hydrostatic testing basis. All required exams have been performed for this fuel cycle.
Note 6: For simplicity, numbers and percentages are based only on circumferential welds selected for examination. When a circumferential weld is intersected by a longitudinal weld, that longitudinal weld is selected by default in the WCNOC Program. This approach results in greater than the 7.5% sample of longitudinal seam welds being inspected, exceeding the ASME Code requirements.
Note 7: Includes augmented exams required by NUREG 0800 and RCP Flywheel Exams.
Note 8: Numbers do not include Visual Examinations (VT-2) as required for 40-month and 10-year system hydrostatic testing basis. AU required exams have been performed for this fuel cycle.
Note 9: Relief Request 12R-23 is being submitted to approve an incomplete examination for Category C-B. Per WCNOC program protocol, this incomplete exam has not been counted in Table 1. Thus, the total exams credited percentage is shown as being below the 16% minimum. Following NRC approval of Relief Request 12R-23, Table 1 will be updated to reflect that exam as complete, and the Category percentage will be 25%.
Note 10: A Relief Request is being prepared to approve one incomplete examination for Category C-F-2 and 13 incomplete examinations in the Augmented Category. Per WCNOC program protocol, these incomplete exams have not been counted in Table 1. Following NRC approval of the Relief Request. Table I will be updated to reflect those exam as complete, and the Category percentage will be adjusted accordingly.
Note 1: During the last revision of WCRE-1 0, the pressurizer integral attachments were correctly reclassified as category B-H instead of B-K.
O4R-l 12-P2-RF-/ I PageS of 5
TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Flaw Flaw or Relevant Condition Found Examination Item Item Description Characterization During Scheduled Section XI Category Number (IWA-3300) Examination or Test (Yes or No)
D-A D.1 10 EF-080-HBC-24" Through Wall No Component EF03-SO05 ESW System Note A Note A: On 10/16/99, a through wall leak was discovered in the ESW return piping. In accordance with NRC GL 91-018 for class 3 piping (moderate energy), the evaluation and acceptance criteria from GL 90-S05 and Code Case N-513 was used to determine that the system was suitable for continued service. On 3/312000, it was determined that the degradation had progressed to the point that the piping no longer had structural integrity as defined by Code Case N-513. The degraded
- components were then replaced per Repair/Replacement Plan 2000-004.
04R-I 12-P2-RF-I1 Page 4 of i
.Iq 41 TABLE 3 I ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Flaw or Relevant Condition Found Repair, During Scheduled Repair/
Replacement, Section XI Replacement Code or Corrective Item Description Examination or Date Plan Class Measure Description of Work Test (Yes/No) Complete Number 3 Replace Carrier Corporation Type 28NW Cut and cap Cooling Coil tube and replace No 01/07/2000 1999-048 Room Cooler leaking tube nuts. Hex nuts have through Component SGL I2B wall leakage located near the base of the hex Aux Building HVAC System head of the nut. Cause of defect appears to be erosion/corrosion.
3 Replace Spool Piece Replace Cooling Coil in SGLI2B with new No 04/05/2000 1999-063 Component SGL12B Aerofin Type 'R" Coil due to continuing Aux Building HVAC System problems with leakage at tubing fittings.
3 Replace ESW RETURN PIPE SPOOL Replace flange, reducer and tee on spool No 05/16/2000 2000-004 Component EF03-S005 EF03-S005 located on EFO8OHBC-24" due ESW System to through-wall leakage.
3 Replace Piping and Fittings Remove and replace cracked welds on each No 08/04/2000 2000-073 Component BG-034-HBC-6" side ofBGV0021 per original design CCW system requirements per SWO 00-218249-002.
3 Replace Piping and Fittings Repair through wall cracks in CCW piping No 03/27/2001 2000-099 Components 034-HBC-6" welds downstream ofEBG01 by removing 052-HBC-6, 472-HBC-6", and and replacing welds and installation of 101-HBC-14" replacement piping.
CCW System 3 Repair/Replace Piping and Fittings Repair/replace by welding a section of Pipe No 12/08/2000 2000-105 Components BB-149-HBC-4" and Spool EG13-S017/242 and E1303-S018/242 BB-145-HBC-4" and cut out and reweld existing field weld CCW System between EG13-SO15/242 and S016/242.
2 Repair/Replace HX Shell Outlet Nozzle Modify the heat exchanger shell side outlet No 01/03/01 2000-107 Component EBG0I nozzle by changing from 8* to 12" diameter.
Letdown Heat Exchanger Add a 12"x8" reducer to the pipe line, between the nozzle and the 8"x6" reducer.
2 Repair/Replace HX Shell Attachment Repair crack in the vessel shell at the toe of a No 01/03/01 2000-108 Component EBG0l permanent attachment weld. Modification of Letdown Heat Exchanger the attachment was performed per CCP 09642.
OAR-I 12-P2-RF-II Page 5 of 5
FORM OAR-I OWNER'S ACTIVITY REPORT Report Number WCRE-I 0. [2-P2-RF-l 2 Owner Wolf Creek Nuclear Operatine Corporation. 1550 Oxen Lane Northeast. Burlington. Kansas 66839 (Name and Address of Owner)
Plant Wolf Creek Generating Station. 1550 Oxen Lane Northeast. Burlington. Kansas 66839 tName and Address ot Plant)
Unit No. I Commercial service date 9-3-85 Refueling outage no. 12 (If applicable)
Current inspection interval 2nd (I st. 2nd. 3rd. 4th. other)
Current inspection period 2nd i Ist. 2nd. 3rd)
Edition and Addenda of Section Xl applicable to the inspection plan 1989 edition with no addenda Date and revision of inspection plan WCRE- 0 Rev. 3. dated 3-22-2002 Edition and Addenda of Section Xi applicable to repairs and replacements. if different than the inspection plan same CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct. and that the examinations. tests, repairs, replacements, evaluations, and corrective measures represented by this report conform to the requirements of Section XI.
Certificate of Authorization No. NIA Expisation Date NIA I If aimilicatbic)
Signed Dennis E. Toucaw Engineer D 6120/2003 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE 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 Kansas and employed by Factory Mutual Insurance Company of Johnston, Rhode Island have inspected the items described in this Owner's Activity Report. during the period October4, 1999 to December 31, 2002 and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section Xl.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations. tests. repairs. replacements. evaluations and corrective measures described in this 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 ansing trom or connected with this inspection.
gWl I Il~ll i Commissions KS#299
/ Inspector's Signature National Board. State. Province. and Endorsements Date i fo m This form (E0O127) may be obtained from the Order Dept., ASME. 22 Law Drive. Bdox 2300. Fairfield. NJ 07007-2300 OAR., per 7.-o-12-P2.RF..Wg Page I of 7
TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Completion of RF-12 (I-2, P-2)
Total Total Total Total Examinations Examination E i os Examinatfons Examinaons Credited (%) to Examination Required For Credited for This Credited (nai) for Date for the Category The Interval Period* The Period** Interval Remarks B-A 24 2 8 21 B-B 5 2 40 60 B-D 36 7 19 61 B-E 113 38 34 66 B-F 14 2 14 57 Note 10 B-l-I 219 79 36 66 B--2 15 0 7 60 Note I B-H 2 0 0 50 B-i 170 0 26 Note 10 B-K 0 B-L-2 0 100 Note 2 B-M-2 7 I 14 71 Note 3 I
B-N-I 3 33 67 B-N-2 6 B-N-3 l B-0 4 0 0 100 B-P Note 4 Note 4 Note 4 Note 4 Note 4 C-A 9 4 44 78 C-B 7 3 43 71 Note 8 C-C 19 5 26 58 C-D l 0 0 100 C-F-I 84 0 0 33 Note 5, 10 C-F-2 28 8 29 57 Note 10 C-G 4 I 25 SO C-H Note 4 Note 4 Note 4 Note 4 Note 4 AUG 500 152 30 63 Note 6 D-A 44 15 34 66 Note 7 D-B Note 7 F-A 277 97 35 64 Note 9 RI-IS! 121 30 25 25 Note 10 S
This column is interpretedto represent the cumulative number ofexams performedto date in this period This column is interpretedto represent the cumulative percentage ofscheduled examsfor the interval which have completed in this periodto date.
OAR-I 12-P2-RF-12 Page 2 of 7
Note 1: For pumps and valves, examinations are limited to components selected for examination under Examination Categories B-L-2 and B-M-2.
Note 2: Examination is required only when a pump is disassembled for maintenance, repair or examination.
Examination is required only once during the inspection interval, thus completed percentages indicated may not be consistent with Table IWB-2412-1 schedule. In RFO-9, RCP-D was disassembled, and the pump casing surfaces were examined.
Note 3: Examination is required only when a valve is disassembled for maintenance, repair or examination.
Examination is required only once during the inspection interval, thus completed percentages indicated may not be consistent with Table IWB-2412-1 schedule.
Note 4: Visual Examinations (VT-2) are performed as required for a fuel cycle, 40-month, and 10-year system hydrostatic testing basis. All required exams have been performed for this fuel cycle.
Note 5: For simplicity, numbers and percentages are based only on circumferential welds selected for examination. When a circumferential weld is intersected by a longitudinal weld, that longitudinal weld is selected by default in the WCNOC Program. This approach results in greater than the 7.5% sample of longitudinal seam welds being inspected, exceeding the ASME Code requirements.
Note 6: Includes augmented exams required by NUREG 0800 and RCP Flywheel Exams.
Note 7: Numbers do not include Visual Examinations (VT-2) as required for 40-month and 10-year system hydrostatic testing basis. All required exams have been performed for this fuel cycle and period.
Note 8: Eight Category C-B components were originally scheduled for examination in Interval 2, two in Period 1, three in Period 2, and three in Period 3. Two Category C-B exams were performed for ISI credit in Period I (Relief Request 12R-23 was submitted to the NRC for approval of an incomplete exam in Period I and was approved by the NRC in a letter dated April 23, 2003). Three Category C-B examinations were completed for ISI credit in RF12, which brought the number of exams completed for the Interval to five. One of the components originally scheduled for examination in Period 3 was discovered to be a solid forging with holes drilled, thus no inner radius exists for this component. Removal of one of the exams scheduled for Period 3 has resulted in 71% completion of the exams required for the Interval.
Note 9: Wolf Creek has implemented changes that has removed many snubbers and associated supports from plant configuration. Thus the number in the "Total Examinations Required For The Intervarl column for category F-A is less than that shown in the RF-I I report. The sample percentage requirements of Code Case N491-1 continue to be met.
Note 10: Categories B-F, B-J, C-F-1, and C-F-2 welds are now examined under the RI-ISI program In the safety evaluation of the WCNOC RI-ISI program, the NRC approved WCNOC's proposal that since 33 percent of the ASME Section Xl exams had been performed in Period 1 and the first part of Period 2, then 67 percent of the RI-ISI scope would be examined during the remainder of Period 2 and Period 3, so that 100% of selected exams are completed during the interval.
OAR-I 12-P2-RF-12 Page 3 of 7
TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Flaw Flaw or Relevant Condition Found Examination Item Item Description Characterization During Scheduled Section XI Category Number (IWA-3300) Examination or Test (Yes or No)
There were no components containing flaws or relevant conditions that required an evaluation to determine acceptability for continued service.
OAR-I 12-P2-RF-12 Page 4 of 7
S I TABLE 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Flaw or Relevant Condition Found Repair, During Scheduled Repair/
Replacement, Section XI Replacement Code or Corrective Item Description Examination or Date Plan Class Measure Description Of Work Test (Yes/No) Complete Number 3 Repair/ 3" DRAVO Pipe Spools: EGI I- Replace all of the welds in line BB-138- No 05/06/2003 2002-031 Replacement S013/231, EGI I-S014/241, EGI I- CBC-3 with reportable indications found as S015/241, EGI -S016/241,EGI I- part of the corrective action to PIR 2000-SO17/241 2899. For ALARA and scheduling Pipe Anchor, PipeEGIEG 1I-A006/231 nchor
-A00/231 considerations, most of the piping material will also be replaced.
3" Velan Globe Valve, BBV0261 3" Velan Gate Valve, BBHV0013 3 Repair/ 3" DRAVO Carbon Steel Pipe Replace all of the welds in line BB-206- No 02/11/2003 2002-034 Replacement Spools: EG17-SOOI/231, EG17- CBC-3 with reportable indications found as S002/231, EG I7-S003/241, EG 17- part of the corrective action to PIR 2000-S004/241, EG 17-SO05/241, EG 17- 2899. For ALARA and scheduling S006/241, EG17-S007/241 considerations, most of the piping material 3" CORNER & LADA Pipe Anchor, will also be replaced.
EG I 7-A007/231 3" Velan Globe Valve, BBV0264 Velan 3" Motor Operated Gate Valve, BBHV0016 3 Replacement Carrier Room Cooler Replace leaking tube nut with new part. No 10/11/2001 2001-018 Component SGL13B I Replacement Reactor Vessel Penetration # 10 Install ABB Canopy Seal Clamp Assembly No 03/21/2003 2002-030 Canopy Seal Weld over seal weld on spare penetration # 10.
I Replacement Reactor Vessel Penetration # 22 Install ABB Canopy Seal Clamp Assembly No 03/24/2003 2002-029 Canopy Seal Weld over seal weld on spare penetration # 22.
2 Repair Richmond Engineering Horizontal Grind the head to shell girth weld flush in No 05/20/2002 2002-023 Heat Exchanger, EBGOI two areas to facilitate flaw evaluation by ultrasonic testing.
3 Replacement Tube side drain line from EEGO IA Replace drain line between EGV0029 and No 09/10/2002 2002-007 south waterbox, EG-HBC-2" EEGOIA.
3 Repair/ Carrier Corporation Type 28NW Install tube jumper between tube I and tube No 08/14/2001 2001-026 Replacement Room Cooler, SGLIOA 4 in row 17 to bypass a tube which has a through wall leak.
OAR-I 12-P2-RF-12 Page 5 of 7
3 Repair ESW Prclube Storage Tank, Perform base metal weld repair on TEFOIB No 08/02/2001 2001-019 TEFOIB tank shell.
3 Repair/ Velan Engineering 3" Gate Valve, Replace all of the welds in line BB1-164- No 01/08/2003 2002-036 Replacement BBHV0014 CBC-3" with reportable indications found Velan Enginecring 3" Globe Valve, per PIR 2000-2899. Most of the piping BBV0262 material will also be replaced. REV. I -
Replace wrapper plate on EG I 3-A002 and 3" Dravo Carbon Steel Pipe Spools: repair any gouges in the tube steel.
EG 13-SO09/232, EG 13-SO 10/232, EG13-SOI 1/232, EG13-S008/232 3 Repair/ 4" Dravo Corporation pipe Spool, Repair by replacing downstream weld on 90 No 07/19/2002 2002-049 Replacement EGI I -S020/241 degree elbow of spool EGI I -S020/241.
2 Repair 4" Dravo Corporation pipe Spool, Replaced vendor weld "B" on spool EGO9- No 01/08/2003 2002-047 EGO9-S023/231 S023/231. In addition to this replacement, replaced vendor weld 'A" and the piece of pipe between the two welds.
2 Replacement Horizontal Heat Exchanger, EBGOI Perform weld repairs on EBGOI heat No 05/06/2003 2002-044 exchanger by installing nozzle encapsulations.
2 Repair 14" Anchor Darling Pressure Seal Remove the defect from the body of valve No 07/30/2002 2002-042 Tilting Disc Check Valve, AEVOI23. Defect was reduced to an AEV0123 acceptable condition by buffing/grinding only, no welding was performed.
3 Replacement 3" Dravo Pipe Spool, EG17-S020 Replace the upstream elbow in pipe spool No 01/10/2003 2002-040 EGI 7-S020 and its welds.
3 Repair/ Pipe Anchor, EG15-AOOI/232 Replace all of the welds in line BB-185- No 05/06/2003 2002-035 Replacement 3" Carbon Steel Pipe Spools: CBC-3 with reportable indications found as EG15-S001/232, EGI5-S002/232, part of the corrective action to PIR 2000-EG I5-SO03/242, EG I5-S004/242, 2899. For ALARA and scheduling EG 15-SO05/242, EGI 5-S006/242 considerations, most of the piping material will also be replaced.
Velan 3" Globe Valve, BBV0263 Velan 3" Gate Valve, BBHVOO15 3 Replacement Containment Cooler, SGNOID Remove one leaking cooling coil from No 03/13/2003 2002-053 service by cutting off nozzles and blind flanging the supply and return header connections.
3 Replacement Carrier Corporation 28NW Heat Repair/replace leaking tube nut on cooling No 01/1 5/2003 2002-051 Exchanger, SGL15A coil row 27, tube 1. Remove circuits containing row 10 tube 8 and row 35 tube I from service by capping each circuit at it's connection to it's header.
OAR-I 12-P2-RF-12 Page 6 of 7
o 6/020 20-3 3 Repair/ 3" DRAVO Pipe Spools: Replace all of the welds in lines EG-297- No 6/20/2003 2002-033 Replacement EG13-S007/232, EG15-S007/242, CBC-3, EG-299-CBC-4, EG-300-CBC-3, EG I 5-S008/242, EG I3-SOO 1/242, EG-302-CBC-4 with reportable indications EG13-SO02/232, EG13-S003/232, found as part of the corrective action to PIR EG I 3-S004/232, EG 13-S006/232, 2000-2899. For ALARA and scheduling EG09-SO1 7/231, EG I7-SO08/24 1, considerations, most of the piping material EG I 7-S009/241, EGI 7-S010/241, will also be replaced.
EG17-S0 11/241, EGI3-S005/232, EG09-S024/231, EG09-S018/231, EGI I-S012/241 BERGEN-PATERSON/DANIEL INTERNATIONAL PIPE SUPPORT, EG17HO02/241 DANIEL INTERNATIONAL PIPE SUPPORT, EG09-RS02/231 3" Velan Globe Valve, BBV0264, BBV0262 4" VELAN PARALLEL SLIDE GATE VALVE, EGHV0132, EGV370 OAR-I 12-P2-RF-12 Page 7 of 7