ML20059A763
| ML20059A763 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 10/15/1993 |
| From: | Gordon N NEBRASKA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20059A756 | List: |
| References | |
| NUDOCS 9310270113 | |
| Download: ML20059A763 (225) | |
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L ENCLOSURE 1 to Nebraska Public Power District Letter CNSS937262
+~ OWNER'S' DATA REPORT FOR INSERVICE INSPECTIONS FORM NIS-1 Cooper Nuclear Station NRC Docket No. 50-298, DPR-46 p L.
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I i 4 Pags 1 of 1 NPPD Cooper Nuclear Station Urdt #1 Commercial Service Date: July 1974 National Board Number: 20762 NIS-1 FORM OWNER'S DATA REPORT FOR INSERVICE INSPECTION As Required by the Provisions of the ASME Code Rules
- 1. OWNER: Nebraska Public Power District, PO Box 499, Columbus, NE 68601
- 2. PLANT: Cooper Nuclear Station #1, PO Box 98, Brownville, NE 68321
- 3. PLAN 1 '! NIT: #1 4. OWNER CERTIFICATE OF AUTHORIZATION (If Requirad): N/A
- 5. COttiERCIAL SERVICE DATE: 07/74 6. NATIONAL BOARD NUMBER FOR UNIT: #20762
- 7. COMPONENTS INSPECTED: See Attached Exam Component ID Index
- 8. EXAMINATION DATES: 1 16-92 to 8-01-93 9. INSPECTION INTERVAL: From 1985 to E
- 10. ABSTRACT OF EXAMINATIONS: For a list of examinations, see attached Exam Component ID Index. Current status or work required for current interval is 732 complete this date.
- 11. ABSTRACT OF CONDITIONS NOTED: See Attached Report Sununary
- 12. ABSTRACT OF CORRECTIVE MEASURES RECOff4 ENDED AND TAKEN: See Attached Report Sunrnary We certify that the statement.s made in this report are correct and the examinations and ce ective measures taken conform to the rules of the ASME Code, Section XI.
Date C O M l5 , 1993 Signed /
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(Plant Manager) Certificate of Authorisation No. (If Applicable): bb Expiration Date: M CERTIFICATE OF INSERVICE INSPECTION If the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of A D/5 l'4 and eroployed by N. L O. T
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of //44 I 4< 4 ^ fT have inspected the components described in this Owner's Data Report during the period O * /6 ' D to Y - O / ~ 91 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures deacribed in this Owreer's Data Report in accordance with the requir ements of the ASME Code, Section XI. By the signing of 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 Data Report.. Furthermore, neither the Inspector nor his empicyer 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: /O ~ / f ' N of sr dh ' Conrnis sions : d r$ IM b b i 4-(Inspector's Signature) (National Board, State, Province, and No,) 7
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& GE Nuclear Energy PACE 1 of 4 NPPD Cooper Nuclear s1aton Commercial Servce Date Juy 1974 Natonal Board Numbst 20762 NDE INSPECTION SERVICES REPORT
SUMMARY
10 INTRODUCTION . Nondestructive Examinations were performed by GE Inspection Services of GE Nuclear Energy at Cooper Nuclear Station Unit 1 under contract No. 86A-MS2 Task 305 of Nebraska Public Power District. The examinations were performed from February 16,1992 through August 1,1993. A total of 591 components were examined during this period. The total includes ASME Section XI inservice , inspection Components and Augmented Inservice Inspections. 2.0
SUMMARY
OF COMPONENTS INSPECTED The following table lists the components examined and describes indications and/or deficiencies which were recorded. 4 ASME Number of CategoDf G9!DP9flen!# QescD ftou G9 Adit!90sEpted B-A 15 Vessel Welds No Recordable Indications (NRI) } Fifteen (15) Components examined for Section Xl ISI credit. I B-D 6 Nozzle to Vessel Wolds (NRI) NVE-BD-N9 Exan. 'imited to 7016% - coverage. Vessel Nozzle Blend Radius (NRI) NVIR-BD-N9 Exam limited to 70.16% coverage. Four (4) components examined for Section XI ISI credit. B-E 9 Pressure Rotaining Par 1ial (NRI)
- Performed by CNS Personnol' Penetration Wolds in Vessel Nino (9) components examined for Section XI ISI creut.
BF 7 Class 1 Pressure Rotatning JPB-BF 10 Counterbore recorded. Ref. , Dissimilar Motal Wolds DM-300. RCA BF-1 -ID Surface Goomotry and Root Goometry recorded Ref. DM-304, DM 305, and DM-306. i RRF-BF-1 -ID Root Geometry, Acoustic Interiaco and spot lack of fusion recorded Ref. Data Shocts DA-013 and DA-014. RRG-BF-1 -ID Root Geomotry. Acoustic Interface and spot lack of fusion Ref. Data Shoots DA-010, DA-011 and DA4)12. RBD-BF-7 re-examined due to scheduling error in period 2. Remaining Components (NRI) Six (G) components examined for Section Xi ISI crodit. t
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l O GE Nuclear Energy l t PAGE 2 of 4 NPPo Cooper Nuclear Station I Commercal SeMce cate July 1974 Nahonal Board Number. 20762 i ASME Number of Categgy Ggmponents DesAri2tigD QQndi.tions.119 ted i B-G-2 79 Pressure Retaining Bolling NRI > less than 2"in diameter Thirty-One (31) compr.,nonts examined for Section X:ISI cred:t. Forty-Eight (48) components examined for Section XI Pre-service inspection (PSI) ! B-H 6 Integral Attachments for I Three (3) welds examined for Section XI ISI Vessels credit. HNC-C1 Two Rejectable Unear indications recorded Ref. Data Sheet D-118 Indications were removed Ref. D-477. Component had limited examinatbn coverage of 50% HNC-C1-2: Component had limited examination coverage of 50%. Score expansion due to indication in HNC-C1-1. HNC-C1-3 Component had limited examination coverage of 50% Original - scheduled weld, indication observed in HNC-C1-1, first identifed as located in this component. RPV-BH-1 and RPV BH-4: Completed hmited examinahons, originally begun in penod 1 (Spnng 1989 Outage). Remaining Components (NRI). B-J 61 Pressure Retaining Welds in FWD-BJ-10 had hmited Examination Piping coverage of 50%. Examined FWB-BJ-25 for Section XI code credit. FWA-BJ-20: Examined limited to 50% coverage; examined FBA-BJ-44 for Section XI code credit. FWD-BJ Root Geometry Recorded, Ref. DM-241 FWD-BJ-25 OD Georr,etry and ID Root Geometry Recorded Ref. DM-243 FWD-BJ ID and OD Geometry , Recorded, Ref. DM-230 - PWA-BJ-1 + 2 Spot Laminar and ID Geometry Recorded Ref. DM-419 and DM-420 PWA-BJ ID Geometry Recorded. Ref. DM-417 RHA-BJ-11. Root Geometry Recorded Ref. DM-279 RHB-BJ 1 - ID Root Geometry Recorded. Ref. DM-281 RHB-BJ Surfaco Exam (NRI), but hmited to 84.23% coverage, volur';etric exam recorded OD Geometry and Root Geometry, Exam limited to 78.94% coverage. Examined RHB-BJ-11 for Section XI code credit. i I
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GE Nuclear Energy , PAGE 3 of 4 NPPD Cooper Nucleat Station Commercial sonnee cate July 1974 Nstional Board Number. 20762 i ASME Number of Qateggry Co_mpgneilts Description ConditJ!gnqEptej , B-J Presssure Retaining Welds RHB-BJ OD Geometry Recorded. Ref. in Piping DM-364 (Cont'd) RHB-BJ 2 - Root Geometry Recorded. Rofc DM 443 RWA-BJ OD Geometry Recorded. Ref. ; DM-(XiG Remaining Components - (NRI) . Fifty-Nine (59) welds examined for Section XI ISI credit. . The following welds are longitudinal welds l associated with circumferential wolds - no seeparate code credit will be taken for these l welds: RHA-BJ-11 A, RHA-BJ-11B. RHA-BJ-12A, RHA-BJ-14A, RHA-BJ-9A, a RHB-BJ-10A, RHB-BJ-100, RHB-BJ-11 A. RHB-BJ-17A, RHB-BJ-18A, RAD-BJ-40A, RBD-BJ-40A, RHB-BJ-1 A. RHB-BJ-1B, 'i RHB-BJ-2A, RHB-BJ-7A, RHB-BJ-78. i B-K-1 4 Class 1 integral Attachments (NRI) FWD-BKi-35 Exam limited to 60% coverage ; MSA-BKi Exam limited to 62% coverage. Two (2) welds examined for Section XI ISI , credit. l B-M-2 2 Class i Valve Body (NRI) , Two (2) components examined for Section -' XI ISI credit. i B-N 1 8 Interior of Vessel (NRI) . Eight (8) examinations completed for Section XI ISI credit. B-N-2 4 Intenor Attachments to (NRI) Vessel Four (4) examinations completed for Section XI tSi credit. . i B-O 3 Pressure Retaining welds 6n (NRI) ', Control Rod Housing CRD-02-271 - Umited to 50% coverage CRD-26-51 1 - Umited to 50% coverage CRD-30-03 Umikx! to 50% coverage i B-P 2 Class 1 Pressure Retalning Class 1 system feakage test. Components Performod by CNS Personnel * , i I-
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, GE Nuclear Energy PAoE 4 of 4 NPPD Cooper Nuclear Station commercial Service Date July 1974 National Board Numter 20762 ASME Number of Cat _e. gory Components DescilgtloD Conditions Noted C-A 2 Class 11 Welds in Pressure RHR-CA-3A - OD Geometry Recorded, Ref.
Vessol DM-404, Exam limited to 88.20% coverage . RHR-CA-6A - (NRI) Exam limited to 86.50% coverage. C-B 2 Class 11 Nozzle Wolds in (NRI) . Vessel Two (2) welds examined for Section XI ISI cre'll C-C 16 Class 11 Integral Attachments CS-PB-A1 - Rejectable Unear Indication, Ref. D-048, repaired and acceptable, Ref. D-478 i Remaining Components -(NRI) Sixteen (16) welds examined for Section XI ISI credit. C-F 27 Class 11 Welds in Piping (NRI) Twenty-Seven (27) welds examined for Section XI ISI credit. D-A 3 Systems in Support of (NRI) Reactor Shutdown Function Three (3) welds examined for Section XI ISI credit. F-A 21 Plate and Shell Type (NRI) Supports Twenty-One (21) supports examined for Section XIISI credit. F-B 15 Linear Type Supports (NRI) Fifteen (15) supports examined for Section XI ISI credit. F-C 52 Component Standard NRI Supports Fifty-Two (52) supports examined for - Section Xi ISI credit.
GE Nuclear Energy COO 5TR NUCLEAR STATION PAGE 1 of 29 EXAM COMPONENT INDEX REYtSION No. O SPRING 1993 FRR CAL + ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT- DRAWING LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS B-A HMA-BB-1 R-227 SR-102 0' DM-340 CM448 GE.BA-3,4 L-025 218" VESSEL GE-U T-300 2 91-12 15 NRI 1 45'S DM-341 CM-049 L-024 BHD-M GE-UT-300 2 91-12 15 NRI 60*S DM-342 DM-050 L-023 GE UT-300 2 91-12 15 - NRi B-A HMA-BB-2 R-227 SR-102 0' DM-334 CM448 GE.BA-3,4 L-025 218" VESSEL GE-UT-300 2 91-12 15 NRI 45'S DM-335 CM-049 L-024 BHD-M GE-UT-300 2 91-12 15 NRI 6(TS DM-336 DM-050 L-023 GE-UT-300 2 91-12 15 NRI B-A HMA-BB-3 R-227 SR-102 0' DM-337 CM-048 GE BA-3,4 L-025 218" VESSEL GE-UT-300 2 91-12 15 - NRI 45'S DM-338 CM-049 L-024 BHD-M GE-UT-300 2 91-12 15 NRI 6T S DM-339 CM-050 L-023 GE-UT-300 2 91-12 15 NRI B-A HMA-BB-4 R-227 SR-102 0' DM-331 CM-048 GE BA-3.4 L-025 218' VESSEL CE-UT-300 2 91-12 15 NR.I 45'S DM-332 CM-049 L-024 BHD-M GE-UT-300 2 91-12 15 NRl 60'S DM-333 DM450 L-023 GE-UT-300 2 91-12 15 NRI B-A HMA-BB-5 R-227 SR-102 0' DM-328 CM-048 GE.BA-3,4 L-025 218' VESSEL GE-UT-300 2 91-12 15 NR! 45'S DM-329 CM-049 L-024 BHD-M GE-UT-300 2 91-12 15 NRI 60'S DM-330 DM-050 L-023 GE-U T-300 2 91-12 15 NRI B-A HMA-BB-6 R-227 SR-102 0' DM-325 CM-048 GE. BA-3,4 L-025 218' VESSEL GE-UT-300 2 91-12 .15 NRI 45'S DM-326 CM449 L-024 BHD-M GE-UT-300 2 91-12 15 NRI 60 S DM-327 ~ DM-050 LO23 GE-UT-300 2 91-12 15 NRI B-A HMA-BB-7 R-227 SR-102 0' DM-322 CM-048 GE.BA-3,4 L-025 218' VESSEL GE-UT-300 2 91-12 15 NRI 45'S DM-323 CM-049 L-024 BHD-M GE-UT-300 2 91-12 15 NRI 60'S DM-324 CM-050 L-023 GE-UT-300 2 91-12 15 NRI B-A HMA-BB-8 R-227 SR-102 0' DM-319 CM-048 GE BA-3.4 L-025 218" VESSEL GE-UT-300 2 91-12 15 NRI l 45'S DM-320 CM449 L-024 BHD-M GE-UT-300 2 91-12 15 NRI -{ 60'S DM-321 - CM-050 L423 GE-UT-300 2 91-12 ~ 15 NRI B-A HMB-BB-5 R-226 SR-101 0' DM-313 CM-045 GE.BA-3,4 15 218" VESSEL GE-UT-300 2 91-12 16 NRI
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45'S DM-314 CM-046 vv24 BHD-M GE-UT-300 2 91-12 16 NRI .l GO'S DM-315 CM-047 L-023 GE-UT-300 2 91-12 16 NRI
. SCANNED 5' REF. Rl-06 B-A HMB-BB-6 R-226 SR-101 0' DM-316 CM-045 GE.BA-3.4 L-025 218" VESSEL GE-UT-300 2 91-12 16 NRI 45'S DM-317 CM-046 L-024 BHD-M GE-UT.300 2 91-12 16 NRI 60'S DM-318 CM447 L-023 GE-UT-300 2 91-12' 16 NRI SCANNED 5' REF. RI-06 B-A HMC-BB-1 R-228 SR-103 0' DM-343 CM-048 GE.BA-3,4 L-025 218'- VESSEL GE-UT-300 2 91-12 15 NRl :
45'S DM-344 CM-049 L-024 BHD-C GE-UT-300 2 91-12 15 NRI _, 60'S DM-345 CM-050 L-023 GE-UT-300 2 91-12 15 NRI ,i B-A HMD-BB-2 - R-257 SR-117 0' DM-387 CM-053 GE.BA-3,4 L-026 218" THD-M GE-UT-300 2 91-12 15 NRI 45'S DM-385 . CM454 L-027 , GE-UT-300 2- 91-12 .15 NRI - 6O'S DM-386 CM-055 L-028 GE-UT-300 2 91-12 15 NRI -
GE Nuclear Energy COOPER NUCLEAR STATION PAGE 2 of 28 Ex AM COMPONENT INDEx REVISION No. O SPRING 1993 FRR CAL ASMti COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS B-A HME-BB-7 R-255 SR-115 0' DM-375 CM-053 GE.BA3.4 L-026 218" THD-M GE-UT-300 2 91-12 15 NRI 45'S DM-376 CM-054 L-027 GE-U T-300 2 91-12 15 NRI 60'S DM-377 CM-055 L-028 GE-UT-300 2 91-12 15 NRI B-A HME-BB-8 R-254 SR-114 0' DM-372 CM-053 GE.BA3.4 L-026 218" THD-M GE-UT-300 2 91-12 15 NRI 45'S DM-373 CM-054 L-027 GE-UT-300 2 91-12 15 NRI 60'S DM-374 CM-055 L-028 GE-UT-300 2 91-12 15 NRI B-A VCB-BC6-3 R-246 SR-113 MT D-370 N/A GE.BA3,4 N/A 218' THD-FL GE-MT-100 0 91-25 N/A NRI 0' DM-381 CM-053 L-026 GE-U T-300 2 91-12 15 NRI 45'S DM-382 CM-054 L-027 GE-UT-300 2 91-12 15 NRI EXAM. 240' TO 360' B-D NVE-BD-N6A R-256 SR-116 0' DM-378 CM-053 GE.DA3.4 L-026 6" N-VES GE-U T-300 2 91-12 15 NRI 45'S DM-379 CM454 L 027 GE-U T-300 2 91-12 15 NRI 60'S DM-380 CM-055 L-028 GE-UT-300 2 91-12 15 NRI B-D NVE-BD-N8B R-259 SR-122 0* DM-412 CM-063 CE.232-242 L-029 5- NOZ-VES GE-UT-M0 2 91-12 16 NRI 45'S DM-413 CM-0G4 L-029 GE-UT-300 2 91-12 16 NRI 60'S DM-414 - CM465 L-030 GE-UT-300 2 91-12 16 NRI B-D NVE-BD-N9 R-258 SR-121 0' DM-409 CM463 CE.232-242 L-029 5' N-VES GE-UT-300 2 91-12 16 NRI 45'S DM410 CM-064 L-029 GE-UT-300 2 91-12 16 NRI 60'S DM-411 - CM465 L-030 GE-UT-300 2 91-12 16 NRI EXAM LIMITED TO - 70.16% COVERAGE. B-G ' NVIR-BD-NGA R-232 SR-107 PT D-350 N/A CE.232-244 N/A 6' NIR GE-PT-100 0 91-27 N/A NRl (REF. R1-06) B-D NVIR-BD-N8B R-211 SR-091 60'S DM-284 ' CM-029 CE232-241 L-004 5" NIR GE-UT-305 2 93-01 16 NRI 70'RL DM-285 CM-030 L-004 GE-UT-305 2 93-01 16 NRI B-D NVIR-BD-N9 R-210 SR-092 GO'S DM-283 CM-029 CE232-242 L-004 5" NtR GE-UT-305 2 93-01 16 NRI 70* RL DM-282 CM-030 L-004 GE-UT-305 2 93-01 16 NRI. EXAM LIMITED TO 70.16% COVERAGE. B-E CRD 34-03 93-737 NM VT-2 93-737 N/A GE197R576 N/A N/A N/A CNS 6 3.10 28 4 N/A N/A CNS 7.0 8.1 5 EXAMINED BY CNS B-E CRD 34-19 93-737 N/A VT-2 93-737 N/A GE197R576 N/A N/A N/A CNS 6.3.10.28 4 N/A - N/A CNS 7.0.8.1 5 EXAMINED BY CNS B-E CRD 34-35 93-737 NIA VT-2 93-737 N/A GE197R576 N/A N/A N/A CNS 6.3.10.28 4 N/A - N/A CNS 7.0.8.1 5 EXAMINED BY CNS B-E CRD 38-07 93-737 N/A VT-2 93-737 N/A GE197R576 N/A. N/A N/A CNS 6.3.10.28 4 N/A N/A CNS 7.0.8.1 5 EXAMINED BY CNS - b__ . __ _ .____ _ _ _. _ _ _ _ _ _ __ ~. - . - . - . - - . _ - _ _ _ . , - - - . _ . _ ~ - .- . - - - , - - . - - - . - .
L GE Nuclear Energy COOPER NUCLEAR STATION PAGE 3 of 28 EX AM COMPONENT INDEX REVISON No. O SPRING 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARITY PROC.. REV. NO. STD. . CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET St2E CONF. NUMBER NO. NPPD NO. COMMENTS I B-E CRD 38-27 93-737 N/A VT-2 93-737 N/A GE197R576 N/A N/A N/A CNS 6.3.10.28 4 N!A N/A ! CNS 7.0 8.1 5 EXAMINED BY CNS ; B-E CRO 38-47 93-737 N!A VT-2 93-737 ftA GE197R576 N/A N/A N/A CNS 6.3.10.28 4 N/A N/A CNS 7.0 8.1 5 EXAMINED BY CNS B-E INCORE 20-45 93-737 N/A VT-2 93-737 N/A GE197R576 N/A N/A N/A CNS 6.3.10.28 4 N/A N/A CNS 7.0.8.1 5 EXAMINED BY CNS B-E INCORE 28-05 93-737 N/A VT-2 93-737 N/A GE197R576 N/A N/A N!A CNS 6.3.10.28 4 N/A N/A CNS 7.0 8.1 5 EXAMINED BY CNS ' ! B-E NVE-BE-N10 93-737 N/A VT-2 93-737 N/A CE.232-242 N/A N/A N/A CNS 6.3.10.28 4 N/A N/A CNS 7.0.8.1 5 EXAMINED BY CNS t3-F CSA-BF-1 R-278 SR-137 PT D-458 N/A CNS-CS-4 N/A 13.4* SE NOZ GE-PT-100 0 93-27 N/A NRt ~ 45'S DA-016 CA-015 L-021 GE-UT209 1 93-03 51 ID GEOMETRY CA-016 L-021 GE-UT209 1 93-03 61 NRI 45'RL DA-017 CA-017 L-021 GE-UT209 1 93-03 121 ACCUSTIC INTERFACE & ID GEOMETRY 60'RL DA418 CA-018 L-021 GE-UT209 1 93-03 121 ACOUSTIC INTERFACE & "! ID GEOMETRY B-F JPB-BF-1 R-220 SR-097 PT D-302 ~N/A CE232-241 N/A 6* SE-N GE-PT-100 0 91-27 N/A NRI 45'S DM-299 CM-034 L-004 GE-UT-105 2 91-07 109 NRI CM-035 L-004 GE-UT-105 2 91 107 NRI ' .l 45'RL DM-300 CM-036 L-004 GE-UT-105 2 91-07 109 ID COUNTERBORE - 1 CM-037 L-004 GE-UT-105 2 91-07 107 ID COUNTERBORE 60'RL DM-301 CM-038 L-004 GE-UT-105 2 91-07 109 NRI CM-039 L-004 GE-UT-105 2 91-07 107 NRI -B-F RAD-BF-7 R-171 SR-062 PT. D-215 N/A CNS-RR-37 N/A 24' P-P GE-PT-100 0 91-27 N/A . NRI .l O' DM-216 CM-018 L-009 GE-UT-106 1 91-08,-37 106 NRt - 45'S DM-217 CM-017 L-009 GE-UT-106 1 91-08, 106 NRI - 45'S DM-218 CM-015 L-009 - GE-UT-102 2 91-05 55 NRI 45'RL DM-219 CM-016 L-009 GE-UT-102 2 .91-05 55 NRI B-F~ RBD-8F-7 R-169 SR-060 PT D-209 N/A CNS-RR-38 24' P" GE-PT-100 0 91-27 N/A NRI 0" DM-210 CM418 L-009 GE-UT-106 1 91-08.-37 106 NRI , 45'S DM-211 CM-017 L-009 GE-UT-106 1 91-08 -37~ 106 NRI, NOTE: NO NIS-1 l CODE CREDIT TO BE TAKEN TH!S OUTAGE . .
9 GE Nuclear Energy COOPER NOCLEAR STATION PAGE 4 c4 28 EXAM COMPONENT INDEX REVISION No. 0 SPRING 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO- NPPD NO. COMMENTS B-F RCA-BF-1 R-221 SR-098 PT D-303 N/A CE232-241 N/A 5' N-CAP GE-PT-100 0 91-27 N/A NRI 45'S DM-304 CM-040 L-004 GE-UT-105 2 91-07 20 INSIDE SURFACE AND ROOT GEOMETRY 45' RL DM-305 CM-041 L-004 GE-UT105 2 91-07 20 10 ROOT GEOMETRY 06 RL DM-306 CM-042 L-004 GE-UT 105 2 91-07 20 ID SURFACE GEOMETRY B-F RRF-DF-1 R-244 SR-136 PT D-368 N/A CNSRR37 N!A 14" SE-N0Z GE-PT-100 0 91-27 N/A NRI 45'S DA-013 CA-012 L-021 GE-UT-209 1 93-03 52 ID ROOT GEOMETRY 45'RL DA-014 CA-013 L-021 GE-UT-209 1 93-03 121 ACOUSTIC !NTERFACE & 60 SPOT LACK OF FUSION 60'RL DA-015 CA-014 L-021 GE-UT-209 1 93-03 121 NRI B-F RRG-BF-1 R-245 SR-135 PT D-369 N/A CNSRR37 N/A 14" SE-NOZ GE-PT-100 0 91-27 N/A NRI 45'S DA-010 CA-009 L-021 GE-UT-209 1 93-03 52/60 ID ROOT GEOMETRY 45' RL DA-011 CA-010 L-021 GE-UT-209 1 93-03 121 ACOUSTIC INTERFACE 60'RL DA-012 CA-011 L-021 GE-UT-209 1 93-03 121 SPOT LACK OF FUSION B-G-2 2* BULKHEAD R-311 N/A VT-1 DOH92001 N/A 232-230 N/A N/A BOLT IV1-W812 3 1 N/A NRI SEAL FLANGE B-G-2 BAG 1 R-022 N/A VT-1 D-022 N/A N!A N/A N/A BOLT N1-W812 3 1 N/A PSt SAT;!N WAREHOUSE CRD 42-15 R-022 N!A VT-1 D-022 N/A N/A N/A MA BOLT N1-W812 3 1 N/A PSI SAT;IN WAREHOUSE CRD 22-03 R-022 N/A V G1 D422 N/A N/A N/A N/A BOLT N1-W812 3 1 N/A PSI SAT; IN WAREHOUSE CRO 42-19 R-022 N/A VT-1 D-022 N/A N/A N/A N/A BOLT IV1-W812 3 1 N/A Pst SAT; IN WAREHOUSE CRD 38-27 R-022 N/A VT-1 D-022 N/A N/A N/A N/A BOLT IV1-W812 3 1 N/A PSI SAT;IN WAREHOUSE CRD 46-27 R-022 N/A VT-1 D-022 N!A N/A N/A N/A BOLT IV1-W812 3 1 N/A PSI SAT;IN WAREHOUSE CRD 38-23 R-022 N/A VT-1 D422 N/A N/A N/A N/A BOLT - IV1-W812 3 i N/A PSI SAT; IN WAREHOUSE CRD 26-27 R-022 N/A VT-1 D-022 N/A N/A WA N/A BOLT N1-W812 3 1 N/A PSI SAT; IN WAREHOUSE CRD 30-07 R-022 N/A VT-1 D-022 N/A N'A N/A N/A BOLT IV1-WS12 3 1 N/A PSI SAT; IN WAREHOUSE CRO 30-31 R-022 N/A VT-1 D-022 MA N/A N/A N/A BOLT IV1-W812 3 1 N/A PS! SAT;IN WAREHOUSE B-G-2 CRD22-19 R-023 N/A VT-1 0-023 N/A N/A N/A N/A BOLT IV1-W812 3 1 N/A PSISAT
- BAG 12 R423 N/A VT-1 D-023 N/A N/A N/A N/A BOLT IV1-W812 3 1 N/A PSI SAT;IN WAREHOUSE CRD 22-27 R-023 N/A VT-1 D C23 N/A N/A N/A N/A BOLT IV1-W812 3 1 N/A PSISAT CRD 34-11 R-023 N/A VT-1 D 023 N/A N/A N/A N/A - BOLT IV1-W812 3 1 N/A PSISAT CRD 50-35 R-023 N/A VT-1 0-023 N/A N/A N/A - N/A BOLT IV14V812 3 1 N/A PSISAT CRD 18-15 R-023 N/A- VT-1 (LO23 N/A N/A N/A N/A BOLT IV1-W812 3 1 N/A PSISAT CRD d6-31 R-023 N/A VT-1 11-023 . N< A N/A N/A N/A BOLT IV1 W812 3 1 N/A PSISAT CRD 22-11 R-023 N/A VT1 D-023 N/A N/A N/A N/A BOLT N1-WB12 3 1 N/A PSI SAT CRD 42-07 R-023 N/A VT- 4 D-023 N'A WA N/A N!A BOLT IV14V812 3 1 N/A PS! SAT CRD 14-43 R-023 N/A VT-1 l 0423 N/A N/A N/A N/A BOLT N1-W812 3 1 N/A PStSAT-
)
@ GE Nuclear Energy COOPER NUCLEAR STATION PAGE 5 of 28 EX AM COMPONENT INDEx REVtSION No. O SPR!NG 1993 FRR CAL.
ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET StzE CONF. NUMBER NO. NPPD NO. COMMENTS B-G-2 CRD 34-39 R-025 N/A VT-1 0-025 N/A MA N/A N/A BOLT IV1-W812 3 1 N/A PSl; SAT CRD 38-43 R-025 N/A VT-1 D-025 N/A N/A N/A N/A BOLT N1-W812 3 1 N/A PSl; SAT CRD 14-11 R-025 N/A VT-1 D-025 N/A N/A N/A N/A BOLT N1-W812 3 1 N/A PS1; SAT - CRD 14-11 R-268 N/A VT-1 D-432 N/A N/A N/A N/A BOLT IV1-W812 3 i N/A ISI SAT, REMOVED FROM SVS, NEW STYLE BOLTS CRD 14-15 R425 N/A VT-1 D425 N/A N/A WA N/A BOLT N1-W812 3 1 N/A PS!; SAT CRD 14-15 R-268 N/A VT-1 D-432 N/A N/A N/A N/A BOLT N1-W812 3 1 N/A ISl SAT, REMOVED FROM SVS, NEW STYLE BOLTS CRD 38-11 R-025 WA VT-1 D-025 N/A N/A N/A N/A BOLT IV1-W812 3 i N/A PSl; SAT CRD 38-11 R-268 N/A VT-1 D-432 N/A N/A N/A N/A BOLT IV1-W812 3 1 N/A ISI SAT, REMOVED FROM j SVS, NEW STYLE BOLTS CRD 10-11 R-025 N!A VT-1 D-025 N/A N/A N/A N/A BOLT IV1 W8*2 3 i N/A PSl; SAT.' CRD 10-11 R-268 N/A VT-1 D-432 N/A N/A N!A N!A BOLT N1-W812 3 1 N/A ISI SAT, REMOVED FROM SVS, NEW STYLE BOLTS CRD 14-39 R-025 N/A VT-1 0-025 N/A N/A N/A N/A BOLT N1-W812 3 1 N/A PSl; SAT CRD 14-39 R-268 N/A VT-1 D-432 N/A N/A N/A N/A BOLT IV1-W812 3 1 N/A ISt SAT, REMOVED FROM SVS. NEW STYLE BOLTS CRD 18-39 R-025 N/A VT-1 D-025 N/A N/A N/A N/A BOLT N1-W812 3 1 N/A PSl; SAT. . CRD 18-39 R-268 N/A VT-1 D-432 N/A N/A N/A N/A BOLT N1-W812 3 1 N/A ISI SAT, REMOVED FROM SVS, NEW STYLE BOLTS s CRD 26-3i R425 NA VT-1 D-025 N/A N/A . N/A N/A BOLT IV1-W812 3 .1 N/A psi; EAT CRD 38-39 R-025 N!A VT-1 D-025 N/A N/A N/A N/A BOLT IV1-W812 3 1 N/A PSl; SAT - i B-G-2 CRD 34-27 R-026 N/A VT-1 D-026 N/A N/A N/A N/A BOLT IV1-W812 3 1 N/A PSl; SAT CRO 34-27 R-268 N/A VT-1 D-432 N/A N/A N/A N/A BOLT N1-W812 3 1 N/A ISI SAT, REMOVED FROM SVS, NEW STYLE BOLTS ! N/A D-026 N/A N/A N/A N'A BOLT IV1-W812 3 - WA PSl; SAT CRD 30-27 R-026 VT-1 1 CRD 18-19 R-026 N/A VT-1 D-026 N/A N/A N/A N/A BOLT IV1-W812 3 1 r!A PSl; SAT CRD 34-43 R-026 N/A VT-1 D-026 N/A N/A N/A N!A BOLT N1-W812 3 1 N/A PSl; SAT CRD 26 R-026' N/A VT-1 D-026 - N/A N/A N/A N/A BOLT N1-W812 3 1 N/A PSl; SAT ! CRD 42-11 R-026 N/A VT-1 D-026 N/A N/A N/A N/A BOLT N1-W812 3 1 N/A PSl; SAT i CRD 46-35 R-026 N/A VT-1 D-026 N/A N/A N/A N/A . BOLT N1-W812 3 ? N/A PSl; SAT l CRD 46-23 R-026 N/A VT-1 D-026 N/A N/A N/A N/A BOLT N1-W812 3 1 N/A PSl; SAT CRD 38-35 R-026 N/A VT-1 D-026 N/A N/A N/A N/A BOLT N1-W812 3 1 N/A PSl; SAT B-G-2 CRD 42-35 R-024 N/A VT-1 D-024 N/A N/A N/A N/A BOLT IV1-W812 3 1 N/A PSl; SAT , CRD 10-39 R-024 N/A VT-1 D-024 N/A' N/A N/A N/A BOLT IV1-WB12 3 i N/A PSl; SAT l CRD 10-39 R-268 N!A VT-1 D-432 N/A N/A N/A N/A BOLT N1-W812 3 1 N/A ISI SAT; REMOVED FROM l SVS; NEW STYLE BOLT CRO 18-03 R-024 N/A VT-1 . D-024 N/A N/A N/A N/A BOLT IV1-W812 -3 1 N/A PSl; SAT CRD 18-03 R-268 N/A VT-1 D-432 . N/A N/A N/A N/A BOLT - IV1-W812 3 1 N/A ISI SAT; REMOVED FROM
' SVS; NEW STYLE BOLT CRD 26-23 R-024 N/A VT-1 D-024 N/A N/A N/A N/A BOLT IV1-W812 3 1 N/A psf; SAT
_ __ _ - - _ - _ _ _ _ _ _ _ - . . _ - _ _ = = _ - _ . _ _ - _ - _ _ - _ - _ - _ - - _ _ _ - - _ - _ - _ _ _ _ _ _ -
@ GE Nuclear Energy COOPER NUCLEAR ST ATION PAGE 6 of 28 EXAM COMPONENT INDEX REVISION No. O SPRING 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARITY PROC REV. No. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS B-G-2 CRO 18-43 R-024 N/A VT-1 D-024 N/A N/A N/A N/A BOLT IV1-W812 3 1 N/A PSl; SAT CRD 18-43 R-268 N/A VT-1 D-432 N/A N/A N/A N/A BOLT IV1-W812 3 1 N/A ISI SAT,SIX (6) NEW STYLE BOLTS REMOVED FROM SVS CRD 30-43 R-024 N/A VT-1 D424 N/A N!A N/A N/A BOLT N1-W812 3 i N/A PSl; SAT CRD 26-35 R-024 N/A VT-1 D-024 N/A N/A N/A N/A BOLT N1-W812 3 1 N/A PSl; SAT CRD 22-15 R-024 N/A VT-1 D424 N/A N/A N/A N/A BOLT IV1-W812 3 1 N/A PSl; SAT CRD 42-27 R-024 N/A VT-1 D-024 N/A N/A N/A N/A BOLT N1-W812 3 1 N/A PSl; SAT CRD 30-15 R-024 N/A VT-1 D-024 N/A N/A N/A N/A BOLT IV1-W812 3 1 N/A PSl; SAT B-G-2 CS-14A R-121 N/A - VT-1 D-157 N/A 2501-1 N/A N/A BOLT IV1-W812 3 1 N/A SAT B-G-2 CS-CV-18CV R-123 N/A VT-1 D-159 N/A 2501-1 N/A 10* BOLT N1-W812 3 1 N/A SAT B-G-2 CS-CV-19CV R-123 N/A VT-1 D-159 N/A 2501-1 N/A 10" BOLT N1-W812 3 1 N!A SAT . B-G-2 HPCI-CV-29CV R-047 N/A VT-1 D-057 N/A 2509-2 N/A N/A BOLT N1-W812 3 1 N/A SAT B-G-2 MS-AO-86A R-047 N/A VT-1 D-057 N/A 2506-4 N/A N/A BOLT IV1-W812 3 1 N!A SAT B-G-2 MS-A066B R-047 N/A VT-1 D-057 N/A 2506-4 N/A N/A BOLT IV1-W812 3 1 N/A SAT B-G-2 MS-A0-86C R-047 N/A VT-1 D-057 N/A 2506-4 N/A N/A BOLT N1-W812 3 1 N/A SAT B-G-2 MS-RV (OCRV R-294 N/A VT-1 D-47G N/A N!A N/A N/A STUD IV1-W812 3 1 N/A PSI EXAM; SAT BOLT (REF; MSD-BG2-17) B-G-2 MS-RV-71F R-285 N/A VT-1 D-465 N/A N/A N/A N/A BOLTS IV1-W812 3 1 N/A SAT B-G-2 MSH-132 R-237 N/A VT-3 D-355 N!A 2506-1 N/A -N/A HANGER GE-VT-100 0 . 91-29.-36 N/A SAT VT-4 N4-W812 2 91-31,-34 EXAMINED DUE TO FALSE SAMPLE EXPANSION FOR MSH-133 B-G-2 MS-V-71G R-188 N!A VT-1 D-252 N/A fCA N/A N/A N/A N1-W812 3 1 N/A 12 BOLTS; NRI PSI EXAM S/N 382 B-G-2 MS-RV-71G R-189 N/A VT-1 D-253 N!A N/A N/A N/A N/A IV1-W812 3 1 N/A 12 NUTS; NRI S/N 382 B-G-2 MS-RV-71G R-190 N/A VT-1 D-254 N!A N/A N/A N/A N/A IV1-W812 3 1 N/A 12 STUDS; NRI PSI EXAM, S/N 382 B-G-2 N6A R-311 N/A VT-1 DOH92001 NfA 232-230 N/A N/A BOLT IV1-W812 3 i N/A NRI B-G-2 NGB R-311 N/A VT-1 DOH92001 N/A 232-230 N/A N/A BOLT IV1-W812 3 1 N/A NRI B-G-2 N7 R-311 N/A VT-1 DOH92001 N/A 232 230 N/A N/A BOLT N1-W812 3 1 N!A - NRI B-G-2 RF-16-CV R-275 N/A VT-1 D-455 N/A 2509-1 N/A N/A BOLT N1-W812 3 1 N/A -SAT
- _. - - - - _ _ - _ - _ _ _ _ _ _ _ _ - - - _ - _ - -- 2 - .. - . . _ . . _. _ _ . . . - - , - . , . - . . - .
m . ~~- = c- - GE Nuclear Energy COOPER NUCLEAR ST ATtON PAGE 7 of 28 EX AM COMPONENT INDEM REVISION No. 0
- SPRING 1993 1
FRR CAL l ASME COMPONENT
SUMMARY
EXAM DATA CAL SH T. DRAWING LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS B-G-2 RF-13-CV R-191 N/A VT-1 D-255 N/A N/A N/A N/A (8) STUDS IV1-W812 3 1 N/A PSl; SAT ; B-G-2 RF-13-CV R-191 N/A VT-1 D-255 N'A N/A N/A N/A (8) NUTS IV1-W812 3 1 N/A PSl; SAT ' B-G-2 RF-14-CV R-191 N/A VT-1 D-255 N/A N/A N/A N/A (S) STUDS IV1-W812 3 1 N/A PSl; SAT B-G-2 RF-14-CV R-191 N/A VT-1 D-255 N/A N/A N/A N/A (8) NUTS IVI-W812 3 1 N/A PSl; SAT I' B-G-2 RF-15-CV R-191 N/A VT-1 D-255 N/A N/A N/A N/A (8) STUDS IV1-W812 3 1 N/A PSl; SAT . B-G-2 RF-15-CV R-191 N/A VT-1 D-255 N/A N/A N/A N!A (8) NUTS N1-W812 3 1 N/A PStSAT j B-G-2 RF-16-CV R-191 N/A VT-1 D-255 N/A N/A N/A N/A (8) STUDS IV1-W812 3 1 N/A PSl; SAT , B-G-2 RF-16-CV R *,91 N/A VT-1 D-255 N!A N/A N/A N/A (8) NUTS IV1-W812 3 i N/A PSl; SAT , B-G-2 RHR-CV-20CV R-203 N/A VT-1 D-269 N/A 2510-4 N/A 24' BOLT IV1-W812 3 1 N/A SAT B-G-2 RHR-CV-27CV R-204 N/A VT-1 D-270 N/A 2510-3 N/A 24" BOLT IV1.W812 3 1 N/A SAT I B-G-? RHR-MO-18 R-146 N/A VT-1 D-182 N/A 2510-1 N/A N/A N/A IV1-W812 3 1 NA SAT B-G-2 RHR-V-81 A R-159 N!A VT-1 D-199 N/A 2510-4 NA N/A BOLT IV1-W812 3 i N/A SAT , B-G-2 RHR-V-818 R-092 N/A VT-1 D-128 N/A 2510-3 N/A N/A BOLT N1-W812 3 1 N/A j SAT B-G-2 RHR-V-88 R-123 N'A VT-1 D-159 N/A 2501-1 N/A 10" BOLT IV1-W812 3 1 N/Af -SAT P G-z QRF-BG2-A R-094 N/A VT-1 D-130 N/A CNS-RR-37 N/A 4' BOLT IV1-W812 3 1 N/A SAT B-G-2 RRF-2G2-8 R-093 N/A VT-1 D-129 N/A CNS-RR-38 N/A 4* BOLT N1-W812 3 i N/A SAT B-G-2 RWCU-CV-15CV R-047 N/A VT-1 0-057 N!A 2509-1 N/A N/A BOLT N1-W812 3 1 N/A SAT I B-G-2 NT R-317 N/A VT-1 DM-490 N/A 232-230 N/A N/A BOLT IV1-W812 3 1 N/A PSI-NEW BOLTING; SAT .j B-H HNC-C1-1 R-100 SR-049 MT D-136 N/A GE.BA-3 N/A N/A VES-SK GE-MT-100 0 91-25 N/A 2 REPORTABLE LINEAR - INDICATIONS, EXAM UMITED TO 50% COVERAGE i R-263 SR-126 0' DM-429 ' CM-070 L-032 MlUSK-W812 1 N'A 16 NRI 45'S DM-430 CM-071 L-032 MlUSK-W812 1 N/A 16 NRI 60'S DM-431 CM-072 L-031 MlUSK-W812 1 N/A 16 NRI R-295 SR-141 MT D-477 N/A N/A GE-MT-100 0 91-25 N/A NRI OF REPAIR AREA B-H HNC-C1-2 R-099 SR-048 MT D-135 N/A GE BA-3 N/A N/A VES-SK GE-MT-100 0 91-25 - N/A ' NRI. EXAM LIMITED TO - 50% COVERAGE R-263 3R-126 0' DM-429 CM-070 L-032 - MlUSK-W812 1 N/A 16 NRI 45'S DM-430 CM-071 L-032 MlUSK-W812 1. N/A 16 NRI
- 60'S DM-431 CM-072 - L-031 MlUSK-W812 1 N/A 16 NRI -
__ _ _ _ _ _ ___u__.__. ___. _ __ _ ______ _ __.__ _ - -. __ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ __ .________________.____r__________
GE Nuclear Energy COOPER NUCLEAR STATION PAGE 8 of 28 EXAM COMPONENT INDEX REV!SION Nw 0 SPHING 1993 FRR CAL , i ASME COMPONENT
SUMMARY
EXAM DATA CAL. SHT. DRAWING UNEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS B-H HNC-C1-3 R-082 SR-040 MT D-118 N/A GE BA-3 N/A 218" VES-SK GE-M1-100 0 91-25 N/A NRI. EXAM UMITED TO. 50% COVERAGE i R-263 SR-126 0' DM-429 CM-070 L-032 MiUSK-W812 1 N/A 16 NRI 45'S DM-430 CM-071 L-032 M!USK-W812 1 N/A 16 NRI ' i 60 S DM-431 CM4)72 L-031 MlUSK-W812 1 N/A 16 NRI , B-H RPV-BH-1 R-299 SR-143 PT D-481 WA CE 232-249 N/A R'A LUG GE-PT-100 0 91-27 N/A NRI. EXAM LIMITED TO ' 92%, FULL COVERAGE
' WITH N-460.
B-H RPV-BH-3 R-284 SR-138 PT D-464 N/A CE.232-249 N/A N/A LUG GE-PT-100 0 91-27 N/A NRI. EXAM LIMITED TO - 93%, FULL COVERAGE - WITH N-460. i B-H RPV-BH-4 R-305 SR-144 PT D-482 N/A CE.232-249 N/A N!A LUG GE-PT-100 0 91-27 N/A NRI, EXAM UMITED TO 92%. FULL COVERAGE W1TH N-460. i } B-J CWB-BJ-4 R-206 SR-087 MT D-273 N/A 2509-1 N/A 4" P-P GE-MT-100 0 91-25 N/A NRI i 45'S DM-274 CM-024 L-004 GE-UT-106 1 9148.-37 2 NRI B-J CWB-BJ-27 R-286 SR-139 MT D-467 N/A 2509-1 N/A 4" V-E GE41T-100 0 91-25 N/A NR1 0* DM-468 CM-081 L-004 GE-UT-106 1 91-08.-37 2 NRJ , 45*S DM-460 CM-080 L-004 GE-UT-10G 1 '1-08.-37 2 NRI
. B-J FWA-BJ-19 R-178 SR-069 MT D-234 N/A 2509-1 N/A 18" T-RED GE-MT-100 0 91-25 N/A NRI 0' DM-236 CM-021 L-008 GE-UT-106 1 91-08.-37 97 NRI -1 45'S DM-235 - CM423 L-008 GE-UT-106 1 91-08-37 97 NRI I B-J FWA-BJ-2 R 148 SR-055 MT D-185 N/A 2509-1 N/A 12" E-P GE-MT-100 0 91-25 N/A NRI ,
45'S DM-186 CM-012 L-008 GE-UT-106 1 91-08.-37 85 NRI B-J FWA-BJ-3 R-147 SR-054 MT D-183 N/A 2509-1 N/A 12" P-E GE-MT-100 0 91-25 N/A NRI . 45'S DM-184 CM-012 L-008 GE-UT-106 1 91-08.-37 85 NRI ! B-J FWA-BJ-20 R-179 SR-070 PT D-237 N/A 2509-1 N/A 18" V-T GE-PT-100 0 91-27 N/A NRI 0* DM-238 CM-021 L-008 GE-UT-106 1 91-08,-37 97 NRI ;
. 45'S : DM-239 CM-022 L-008 GE-UT-106 1 91-08.-37 97 NRL EXAM UMITED TO l*
50% COVERAGE-EXAMINED FWA-BJ-44 IN ' UEU OF THIS WELD FOR .; I SECTION XI CODE CREDIT 4 B-J FWA-BJ-44 R-222 SR-099 MT D-307 N/A 2509-1 N/A 1B* V-P GE-MT-100 0 91-25 N/A NRI 45'S DM-308 L CM-043 L-008 GE4JT-106 1 91-08.-37 97 NRt. EXAM UMITED TO 96% FULLCOVERAGE WITH CODE CASE N-460.. A
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@ ' GE Nuclear Energy COCPER NUCLE AR STATION PAGE 9 of 28 EXAM COMPONENT INDEX REVISION h 0 SPRING 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS B-J FWA-BJ-5 R-219 SR-096 MT D-297 N/A 2509-1 N/A 12" E-P GE-MT-100 0 91-25 N/A NRI 45"S DM-298 CM-033 L-000 GE-UT-10G 1 91-08 -37 85 NRI B-J FWA-BJ-6 R-262 SR-125 MT D-421 N/A 2509-1 N/A 12* P-E GE-MT-100 0 91-25 N/A NRI 45'S DM-422 CM-068 L-005 GE-UT-106 1 91-08,-37 85 NRI B-J FWB-BJ-2 R-173 SR-064 MT D-223 N/A 2509-1 N/A 12" E-P GE-MT-100 0 91-25 N/A NRI 45'S DM-224 CM-019 L-004 GE-UT-106 1 91-08 -37 85 NRI B-J FWB-BJ-3 R-174 SR-065 MT D-225 N/A 2509-1 N/A 12' P-E GE-MT-100 0 91-25 N/A NRI 45'S DM-226 CM419 L-004 GE-UT-10G 1 91-08.-37 85 NRI B4 FWC-BJ-10 R-175 SR-066 MT D-228 N/A 2509-2 N!A 12" T-P GE-MT-100 0 91-25 N/A NRI 45'S DM-227 CM420 L-008 GE-UT-106 1 91-08.-37 85 NRI l l B-J FWD-BJ-19 R-177 SR-068 PT D-233 N!A 2509-2 N/A 18" V-T GE-PT-100 0 91-27 N/A NRI l O' DM-232 CM-021 L-008 GE-UT-106 1 91-08.-37 97 NRI ) 45'S DM-231 CM-022 L-008 GE-U T-106 1 91-08.-37 97 NR1, EXAM LIMITED TO l 50% COVERAGE. EXAMINED FWD-BJ-25 IN LIEU OF THIS WELD FOR l SECTION XI CODE CREDIT i 18' 0 B4 FWD-BJ-24 R-180 SR-071 MT D-240 N/A 2509-2 NIA P-PB GE-MT-100 91-25 N!A NRI 45'S DM-241 CM483 L-008 GE-UT-106 1 91-08 -37 97 ROOT GEOMETRY B-J FWD-BJ-25 R-181 SR-072 MT D-242 N/A 2509-2 N!A 18" E-P GE-MT-100 0 91-25 N/A NRI 45'S DM-243 CM483 L-008 GE-UT-106 1 91-08.-37 97 OD GEOMETRY AND 10 ROOT GEOMETRY . B-J FWD-BJ-9 R-176 SR-067 MT D-229 N/A 2509-2 N/A 12' E-PB GE-MT-100 0 91-25 N/A NRI 45'S DM-230 CM-020 L-008 GE-UT-106 1 91-08-37 85 ID, OD GEOMETRY RECORDED B4 MSC-BJ-8 R-207 SR-088 MT D-275 N/A GE731E611- N/A 24" P-WOL GE-MT-100 0 91-25 N/A NRI 45"S DM-276 CM425 4 L-008 GE-UT-106 1 91-08.-37 106 NRI B4 MSD-BJ-51 R-225 SR-100 MT D-311 N/A GE731E611 N/A 24* P-P GE44T-100 0 91-25 N/A NRI 45'S DM-312 CM-044 L-008 GE-UT-106 1 91-08.-37 106' NRI B-J MSDR-BJ-11 R-056 SR-029 MT D 469 N/A 2506-3 N/A 3' S OL-P GE-MT-100 0 91-25 N/A NRI B4 MSDR-BJ-24 R-056 SR-029 MT D-070 N/A X2506-201 N/A 2" V-COU GE-MT-100 0 91-25 WA NRI B-J MSDR-BJ-26 R-056 SR-029 MT D-071 N/A X2506-201 N/A - 2" P-SOL GE-MT-100 0 91-25 N/A NRI B-J MSDR-BJ-33 R-056 SR-029 MT D-072 N/A X2506-201 N/A 2" EP GE-MT-100 0 91-25 N/A NRI B4 MSDR-BJ-34 R-056 SR-029 MT D-073 N/A X2506-201 N/A 2" P-E GE-MT-100 0 91-25 N/A NRl B4 MSDR-BJ-39 R-056 SR-029 . MT: D-074 N/A 2506-3 N/A 3* SOL-P GE-MT-100 0 91 N/A NRI _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ - _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ - - . - - - _ - - - - -
a
@ GE Nuclear Energy COCPER NtJCt.E AR ST ATION PAGE 10 of 28 -
EX AM COMPONENT INDE4 REVtSION Mo. O SPRING 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARITY PROC, REV, NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS B-J MSDR-BJ-43 R-056 SR-029 MT D-075 N/A X2506-201 N/A 2" E-P GE-MT-100 0 91-25 N/A NRI B-J MSDR-BJ-44 R-056 SR-029 Mr D-076 N/A X2506-201 N/A 2" P-E GE-MT-100 0 91-25 N/A ' NRI B-J MSDR-BJ-M R-057 SR-030 MT D-077 N/A X2506-201 N/A 2" V-COU GE-MT-100 0 91-25 N/A NRI B-J MSDR-BJ-56 R-057 SR-030 MT D-078 N/A X2506-201 N/A 2" P-SOL GE-MT-100 0 91-25 N/A NRI B-J MSDR-BJ-61 R-057 SR-030 MT D-079 N/A X2506 201 N/A 2" E-P GE-MT-100 0 91-25 N/A NRl B-J MSDR-BJ-62 R-057 SR-030 MT D-080 N/A X2506-201 N #A 2" P-E GE-MT-100 0 91 N/A NRI B-J MSDR-BJ-63 R-057 SR-030 MT D-081 N/A X2506-201 N/A 2" E-P GE-MT-100 0 91-25 N/A NRI B-J MSDR-BJ-67 R-057 SR-030 MT D-082 N/A X2506-201 N/A 2" E-P GE-MT-100 0 01-25 N/A NRI B-J MSDR-BJ-68 R-057 SR-030 MT D-083 N/A X2506-201 N/A 2" P-E GE-MT-100 0 91-25 N/A NRI B-J MSDR-BJ-69 R-057 SR-030 MT D-084 N/A X2506-201 N/A 2" COO-P GE-MT-100 0 91-25 N/A NRI B-J PSA-BJ-17 R-264 SR-127 MT D-423 N/A 2506-1 N/A 10" P-E GE-MT-100 0 91-25 N/A NRI 45'S DM-424 CM-069 L-007 GE-U T-106 1 91-08,-37 78 NRI B-J PSA-BJ-18 R-265 SR-128 MT D-425 N/A 2506-1 N/A 10" E-P GE-MT-100 0 91-25 N/A NRI 45'S DM-426 CM469 L-007 GE-UT-106 1 91-08.-37 78 NRI B-J PWA-BJ-1 R-261 SR-124 MT D-418 N/A 2509-2 N/A 14" E-T GE-MT-100 0 91-25. N/A NRI l O' DM-419 CM-066 L-008 GE-UT-106 1 91-08.-37 14 2-SPOTINDICATIONS 45"S - DM-420 CM-067 L-005 GE-UT-106 1 91-08.-37 14 ID GEOMETRY
' B-J PWA-BJ-2 R-200 SR-123 MT D-415 N/A ' 2509-2 N/A 14" E-E GE-MT-100 0 91-25 N/A NRI 0* DM-416 . CM-066 L-008 GE-UT-106 1 91-08,-37 14 NRI 45'S DM-417 CM-067 L-005 GE-UT-106 1 91-08.-37 - 14 10 GEOMETRY B-J RAD-BJ-40A R-172 SR-063 PT D-220 N/A CNS-RR-37 - N/A 3.5" LS GE-PT-100 0 91-27 N/A NRI 0' DM-221 CM-018 L-009 GE-UT-106 1 91-08 -37 106 .NRI 45'S DM-222 CM-017 L-009 GE-UT-106 1 91-08.-37 106 NRI 3 5" LS OF RAD-BF-7 NOTE: NO N!S-1 CODE CREDIT FOR THIS WELD TAKEN SEPERATELY.
PART OF RAD-BF B-J RBD-BJ-40A R-170 SR-061 PT D-212 ' N/A CNS-RR-38 N/A ?? US GE-PT-100 0 91 N/A NRI 0' DM-213 ~ CM-018 L-009 GE-UT-106 1 91-08-37 106 NRI
-45*S DM-214 CM-017 L-009 GE-UT 106 1 91-08,-37 106 .
NRI - NOTE: NO NIS-1 CODE CREDIT FOR THIS WELD TAKEN SEPERATELY. 3.5* i L/S WELD PART OF RBD-BF-7.
.u _ _ _ _ _.___ _ _ _ - ,- _.. . _ _ _._--- _. -
2 _ _ _ _ _ _ _ _ . _~.. -.._ . -_a.. _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ __m
_ m . - . GE Nuclear Energy COOPER NUCLEAR ST ATION PAGE 11 of .28 EX AM COMPONENT INDEx REVISION No. 0 SPRING 1993 , FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS t B-J RHA-BJ-11 R-208 SR-089 MT D-277 N/A 2510-1 N/A 20" P-E GE-MT-100 0 91-25 N/A NRi O' DM-278 CM-026 L-008 GE-UT-106 1 91-08,-37 103 . NRI 45'S DM-279 CM-027 L-008 GE-UT-106 1 91-08.-37 103 ROOT GEOMETRY r B-J RHA-BJ-11 A R-208 SR-089 MT D-277 N/A 2510-1 N/A 12" US GE-MT-100 0 91-25 N/A NRI L! 0' DM-295 CM-026 L-008 GE-UT-106 1 91-08.-37 103 NRI , 45'S DM-294 CM-027 L-008 GE-UT-106 1 91-08.-37 103 NRI ' NO NIS-1 CODE CREDIT FOR THIS WELD. . US PART OF RHA-BJ-11 B-J RHA-BJ-11 A R-251 SR-110 MT D-387 N/A 2510-1 N/A 12' US GE-MT-100 0 91-25 NIA NRI 0" DM-392 CM-056 L-008 GE-UT-106 1 91-08.-37 103 f4RI ! 45'S DM-393 CM-057 L-008 GE-UT-106 1 91-08.-37 103 NRI NO NIS-1 CODE CREDIT FOR THIS WELD.. US PART OF RHA-BJ B-J RHA-BJ-11B R-208 SR-089 MT D-277 N/A 2510-1 N/A 12" US GE-M T-100 0 91-25 N/A NRI 0" DM-295 CM-026 L-008 GE-UT-106 1 91-08.-37 103 NRI j- 45'S DM 294 CM427 L-008 GE-UT-106 1 91-08,-37 103 NRl ' NO NIS-1 CODE CREDIT
- FOR THIS WELD.
US PART OF RHA-BJ-11 B-J RHA-BJ-118 R-251 SR-110 MT D-387 N/A 2510-1 N/A 12" US GE-MT-100 0 91-25 N/A NRI 0' DM-392 CM-056 L-008 GE-UT-106 1 91-08.-37 103 NRI 45'S DM-393 CM-057 L-008 GE-UT-106 1 91-08.-37 103 NRI NO NIS-1 CODE CREDIT , FOR THis WELD. US PART OF RHA-BJ-12 B-J RHA BJ-12 R-251 SR-110 MT D-387 N/A 2510-1 N/A 20* E-P GE-MT-100 0 91-25 N/A NRI . 'I 0' DM-388 CM-056 L-008 GE-UT-106 .1 91-08.-37 103 NRI 45'S DM-389 CM-057 L-008 GE-UT-106 1 9148,-37 103 NRI B-J RHA-BJ-12A R-251 SR-110 MT D-387 N/A 2510-1 N/A 12" . US GE-MT-100 0 91-25 N/A NRI 0'. DM-390 CM-056 L-008 GE-UT-106 1 91-08,-37 103 NRI '; 45'S DM-391 CM-057 L-008 GE-UT-106 - 1 91-08.-37 103 NRI . NO NIS-1 CODE CREDIT , FOR THIS WELD.. US PART OF RHA-BJ-12
-_m..m.____... ..m_._ _ . _ . . . _ _. . _ _ .mm_, m.__m_m__.__.___._____m._...___._.m.._____ . _ , , . . . , . _ , _ _ _ . _ _ . . . _ _ . _ _ .,r_ .
- m. ,.w..,- .m.,n. _ , , ,, .a _ . . +.- . , - , ,' m , ., m...
O GE Nuclear Energy COOPER NUCLEAR STATION PAGE 12 of 25 EX AM COMPONENT INDEX REVf5fCN No O ~ SPRING 1993 4 FRR CAL , ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT, DRAW 1NG LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS B-J RHA-BJ-12A R-252 SR-ti t MT D-394 N/A 2510-1 N/A 12" US GE-MT-100 0 91-25 N/A NRI 0' DM-397 CM-056 L-006 GE-U T-10G 1 91-08.-37 103 NRI 45'S DM-398 'CM-057 L408 GE-UT-106 1 91-08.-37 103 NRJ NO NIS-1 CODE CREDIT' FOR THIS WELD. . US PART OF RHA-BJ-14 EXAM UMITED TO 94.24%. R , FULL COVERAGE WTTH ~
' CODE CASE N-460.
B-J. RHA-BJ-14 R-252 SR-111 MT D-394 N/A 2510-1 NIA 20" P-P GE-M T-100 0 91-25 N/A - NRI , O' DM-395 CM-056 L-006 GE-UT-106 1 91-08.-37 103 . NRI 45'S DM-39G CM457 . L-008 GE-UT-106 1 91-08,-37 103 NRI B-J RHA-BJ-14A R-252 SR-111 MT D-394 ' N/A 2510-1 N/A 12" US GE-MT-100 0 91-25 N/A NRI 0' DM-399 CM-056 L-008 GE-UT-106 1 9t 08,-37 103 NR1 , 45'S DM-400 CM-057 L-008 GE-UT-106 1 91-08.-37 103 NRI ' NO NIS-1 CODE CREDIT FOR THIS WELD. US PART OF RHA-BJ-14 B-J RHA-BJ-9A R-208 SR-089 MT D-277 r N/A 2510-1 N/A 12" US GE-MT-100 0 91-25 N/A NRI 0' DM-296 . CM-026 L-008 GE-UT-106 1 91-08.-37 103 NRI 45'S DM-293 CM-027 L408 GE-UT-106 1 91-08 -37 103 NRI -
.NO NIS-1 CODE CREDIT .
FOR THIS WELD. US PART OF RHA-BJ B-J RHB-BJ-1 R-209 SR-090 MT D-280 N/A 2510-4 N/A 24" E-V GE-MT-100 0 91-25 N/A NRI 45'S DM-281 CM428 L-009 GE-UT-106 1 91-08.-37 113 ID ROOT GEOMETRY , B-J RHB-BJ-10A R-253 SR-112 MT D-378 N/A 2510-4 N/A 12" US GE-MT-100 0 91-25 N/A NRI O' DM-384 CM-059 L-008 GE-UT-106 1 91-08.-37 114 NRI 45'S DM-383 CM-058 L-008 GE-UT-106 1 91-08.-37 114 NRl .
- NO N!S-1 CODE CREDIT '
FOR THIS WELD. US PART OF RHB-BJ-11 B4 RHB-BJ-10B R-253 SR-112 MT D-378 N/A 2510-4 N/A 12" .US GE-MT-100 0 91-25 N/A NRI 0" . DM-384 CM-059 - L-008_ GE-UT-106 1 91-08,-37: '114 NRI - 45'S DM-383 CM458 L-008 GE-UT-106 1 91-08,-37 114 NRI .
- j. NO NIS-1 CODE - ,
COVERAGE FOR THIS !
- WELD.
d US PART OF RHB-BJdi
4 1 GE Nuclear Energy t COOPER NUCLEAR STATION PAGE 13 of 28 s ' EXAM COMPONENT INDEX REVISION No. O * ' SPRING 1993 ' FRR CAL. ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING UNEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO- COMMENTS B-J RHB-BJ-11 R-253 SR-112 MT D-378 N/A 2510-4 N/A 24' P-E GE-MT-100 0 91-25 N/A NRI 0' DM-380 CM-059 L-008 GE-UT+10G 1 91-08 -37 114 NRI 45'S DM-379 CM458 L-008 GE-UT-106 1 91-08,-37 114 NRf B-J RHB-BJ-11 A R-242 SR-108 MT D-360 N/A 251(M N/A 12" US GE-MT-100 0 91-25 N/A NRI 45'S DM-363 . CM-052 L-008 GE-UT-106 1 91-08,-37 114 NRI. NO NIS-1 CODE CREDIT FOR THIS WELD. US PART OF RHB-BJ-17 4 B-J RHB-BJ-11 A R-253 SR-112 MT D-378 N/A 2510-4 N/A 12" US GE-MT-100 0 91-25 N/A NRI 0' DM-382 CM-059 L-008 GE-UT-106 1 91-08.-37 114 . NRI '! 45'S DM-381 - CM458 L-008 GE-UT-106 1 91-08.-37 114 NRI NO NIS-1 CODE CREDIT FOR THIS WELD. US PART OF RHB-BJ-11 B4 RHB-6J-17 R-242 SR-108 Mr D-360 N/A 2510-4 N/A 24" P-P GE-MT-100 0 91-25 N/A ' NRI, EXAM UMITED TO 84.23% COVERAGE 45'S DM-361 CM-052 L-008 GE-UT-106 1 9148.-37 114- ROOT AND OD , GEOMETRY EXAM UMITED TO 78.94% COVERAGE. L EXAMINED RHB-BJ-11 IN UEU OF THIS WELD FOR SECTION XI CODE ' CREDIT. B-J RHB-BJ-17A R-242 SR it ~4 MT D-360 N/A 2510-4 N/A 7.5* US GE-MT-106 0 91-25 N/A NRI ' 45'S DNO362 CM-052 L-006 ' GE-MT-106 1- 91-08.-37 114 . NRI NO NIS-1 CODE CREDIT i FOR THIS WELD. B-J RHB-BJ-17A R-243 SR-109 MT D-365 N/A ' 2510-4 N/A 7.5' US GE-MT-100 0 91-25 N/A NRI 45'S DM-366 CM452 L-008 GE-tJT-106 1 91-08,-37 114' NRf , NO NIS-1 CODE CREDIT , FOR THIS WELD.
. US PART OF RHB-BJ-18 B-J 52HB-BJ-18 R-243 SR-109 MT- D-365 N/A 2510 4 ' N/A 24* P-P GE-MT-100 0 91-25 . N/A NRI 45*S DM-364 CM452 L408 GE-UT-106 1 91-08,-37 114 OD GEOMETRY - _ . . ._ _ - - _ _ _ . . _ - - - . _ _ _ - - . . - ~ _ _ _ _ - - - - - _ - - . _ _ _ _ _ _ - _ - - - . _ _ - _ . . _ _ - - _ _ _ ._ _ _ - -
~
@ GE Nuclear Energy COOPER NUCLE AR $t ATION PAGE 14 of 28 .
EXAM COMPONENT INDEX REVISION No. 0 SPRING 1993 I FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARITY PROC. R EV. . NO. STD. CAT. NUMBER REPORT ' RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS ' B-J RHB-BJ-18A R-243 SR-109 MT D-365 N/A 2510-4 N/A 17 US GE-MT-100 0 91-25 N/A NRI 45'S DM-367 CM-052 L-008 GE-UT-106 1 91-08,-37 114 NRl NO NIS-1 CODE CREDIT FOR THS! EXAM, US PART OF RHB-BJ-18 B-J RHB-BJ-1 A R-209 SR 090 MT D-280 WA 2510-4 N/A 1T US GE-MT-100 0 91-25 N/A NRI 45'S DM-281A CM-028 L-009 GE.UT-106 1 91-08.-37 113 NRI NO NIS-1 CODE CREDIT FOR THIS EXAM, US PART OF RHB-BJ-1 '
'B-J RHB-BJ-1A R-272 SR-133 MT D-440 N/A 2510-4 N/A 17 US GE-MT-100 0 91-25 N/A NRI 0' DM-446 CM-077 L-004 GE-UT-106 1 91-08,-37 114 NRI 45'S DM-447 CM-078 L-004 GE-UT-106 1 91-08.-37 114 NRI NO NIS-1 CODE CREDIT .
FOR THIS EXAM US PART OF RHB-BJ-7 B-J RHB-BJ-18 R-209 SR-090 MT D-280 N/A 2510-4 N/A 1T LlS GE-MT-100 0 91-25 N/A NRI 45'S DM-281A CM4)28 L-009 GE-UT-106 1 91-08,-37 113 NRI _ NO NIS-1 CODE CREDIT FOR THIS EXAM, US PART OF RHB-BJ-1 B-J RHB-BJ-1B R-272 SR-133 PT D-441 ' N/A 2510-4 N!A 12' US GE-PT-100 0 91-27 N/A NRI 0' DM-448 CM-077 L-004 GE-UT-106 1 91-OR,-37 114 NRI 45'S DM-449 CM-078 L-004 GE-UT-106 1 91-03,-37 114 NRI NO NIS-1 CODE CREDIT - FOR THIS EXAM, US PART OF RHB-BJ-2 B-J RHB-BJ-2 R-272 SR-133 Mr D-440 N/A 2510-4 N/A 24" P-E GE-MT-100 0 91-25 - N/A NRI PT D-441 N/A - N/A GE-PT-100 0- 91-27 N/A NRI 0* DM-442 CM-077 L-004 GE-UT106 1 91-08 -37 114 - NRI 45'S DM-443 CM-078 L-004 GE-UT-106 1 91-08,-37 114 ROOT GEOMETRY B-J RHB BJ-2A R-272 SR-133 MT D-440 N/A 2510-1 N/A - 12' US GE-MT-100 .0 91-25 N/A NRI EXAM LIMITED TO 90.42%, FULL COVERAGE , WITH N-460 - O' DM-444 CM-077- L-004 GE-UT-106 1 91-08,-37 114 NRI 45"S DF4-445 CM-078 L-004 GE-UT-106 1 . 91-08.-37 114 NRI NO NIS-1 CODE CREDIT . .
- FOR THIS EXAM, US PART OF RHB-BJ-2 .t b
m _. . _ - - . . . _ _ _ . . < . _ , ..__.m._._,__mm __.______.m___.I..u_______m_...___.__ _ _ o = ., _2m_m __.,__m.r._.___u_u___m.e -,.+..4v. --,---wm-v+-w-m.+. -~--=+wrsn---- - v .es*-w- w -.r- w v e
1 a GE Nuclear Energy COOPER NUCLE AR $7ATION PAGE 15 of 28 i EKAM COMPONENT INDEX REVISION No- O - SPlHNG 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING - UNEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS B-J RHB-BJ-2A R-250 SR-120 MT D-405 N/A 2510-1 N!A 12" US GE-MT-100 0 91-25 N/A NRI 45'S DM-407 CM462 L-008 GE-UT-106 1 91-08.-37 114 ' NRI R-273 SR-134 0' DM-451 CM-0 T7 L OO4 GE-UT-106 1 91-08,-37 114 NRI NO NIS-1 CODE CREDIT FOR THIS EXAM, US FART OF RHB-BJ D-J : RHB-BJ-7 R-250 SR-120 MT D-405 N/A 2510-1 N/A 24" E-P GE-MT-100 0 91-25 N/A NRf SR-134 45'S DM-406 CM-062 L408 GE-UT-106 1 91-08.-37 114 NRI R-273 0' DM-450 CM477 L-004 GE-UT-106 1 91-08.-37 114 NRI B-J RHB-BJ-7A R-250 SR-120 MT D-405 N/A 2510-1 N/A 12" US GE-MT-100 0 91-25 N/A NRI 45'S DM-408 CM462 L-008 GE-UT-106 1 91-08.-37 114. NRI R-273 SR-134 0' DM-452 CM-077 L-004 GE-UT-106 1 91-08.-37 114 NRI NO NIS-1 CODE CRED? T FOR THIS EXAM, US PART OF RHB-BJ-7 B-J RHB-BJ-78 R-250 SR-120 MT D-405 N/A 2510-4 N/A 12" US GE-MT-100 0 91-25 N/A NRI - R-273 SR-134 0' DM-453 CM-077 L-004 GE-UT-106 1 91-08,-37 114 NRI 45'S DM-408 CM462 L-008 GE-UT-106 1 91 08,-37 114 N RI - NO NIS-1 CODE CREDIT FOR THIS EXAM, US PART OF RHB-BJ-7. - i B-J RSA-BJ-1 R-097 SR-046 MT D-133 N/A 2506-2 N/A 3" WF-P GE-MT-100 0 91-25 N/A NRI , B-J RSA-BJ-15 R-231 SR-106 MT D-348 N/A 2506-2 N/A 3* P-E GE-MT-100 0 91-25 .N/A NRf B-J RSA-BJ-7 R-098 SR-047 MT D-134 N/A - 2506-2 N/A 3" P-E GE-MT-100 0 91-25 N/A NRI B-J RVD-BJ-23 R-062 SR-036 PT D-089 N/A X2512-200 N/A' 2' P-V GE-PT-100 0 91 N/A NRI , B-J RVD-BJ-25 R-060 SR-034 e)T D-087 N/A X2512-200 N/A 2* P-V GE-PT-100 0 91-27 N/A NRI B.J RVD-BJ-26 R-081 SR-035 PT- D-088 N/A X2512-200 N/A - 2* T-P GE-PT-100 0 91-27 N/A NRI B-J RVD-BJ-31 R-059 SR-033 PT D-086 N/A X2512-200 N/A 2* T-P GE-PT-100 0 91-27 N/A NRI B-J RVD-BJ-32 R-058 SR-032 PT D-085 N/A - X2512-200 N/A 2" P-V GE-PT-100 0 91-27 N/A NRf , B-J RWA-BJ-G R-054 SR-028 MT D-065 N/A 2509-1 N/A 4* T-P GE-MT-100 0 91-25 NRI 45'S DM-066 ' CM-003 L-008 GE-UT-106 .1 91-08.-37 2 OD GEOMETRY i t
.I - m m_ . . _ _ _ __.__..o .___.___-__m_ . _ - - _ _ _ _ . . . _ _ . _ _ _ _ m.._ m_mm____m___ _u_a_______.._______.__._.___m ______m._m_-.__m___,a _m- ,_ _ _ _ _ _ -swa _ ___ rs._a,n_ _ _ _ _ _ _
GE Nuclear Energy
- COOPER NUCLEAR STATION PAGE 16 of 28 EXAM COMPONENT INDEX REVISION % 0 '
SPRING 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING UNEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET St2E CONF. NUMBER NO. NPPD NO. COMMENTS B-J RWA-BJ-8 R-205 SR-086 MT D-271 N/A 2509-1 N/A 4" P-P GE-MT-100 0 91-25 N/A NRI 45'S DM-272 CM-024 L4)04 GE-UT-10G 1 91-08.-37 2 NRI B-J SLC-BJ-16 R-119 SR-052 PT D-155 N/A X2504-200 N/A 1.5* P-V GE-PT-100 0 91-27 N/A NRI B-J SLC-BJ-17 R-120 SR-053 PT D-15G N'A X2504-200 N/A 1.5" T-P GE-PT-100 0 91-27 N/A NRI B-J SLC-BJ-8 R-095 SR-044 PT D-131 N/A X2504-200 N/A 1 5" P-T GE-PT-100 0 91-27 N/A NRI B-J SLC-BJ-9 R-096 SR-045 PT D-132 N/A X2504-200 N/A 1.5' E-P GE-PT-100 0 91-27 N/A NRI B-K-1 FWD-BK1-35 R-230 SR-105 MT D-347 N!A 2509-2 N/A N/A ATTACH GE-MT-100 0 91-25 N/A NR1, EXAM LIMITED TO 60% COVERAGE. B-K-1 MSA-BK1-44 R-066 SR-037 MT D-093 N/A GE731E611 N/A N/A SP-FH GE-MT-100 0 91-25 N/A NRI. EXAM UMITED TO 4 62% COVERAGE B-K-1 RR-BK1-3A R-111 SR-051 PT D-14 7 N/A ISO-RL-A N/A N/A LUG GE-PT-100 0 91-27 N/A NRI BJ-1 RR-BK1-3B R-110 SR4)50 PT D-146 N/A ISO-RL-B N/A N/A LUG GE-PT-100 0 91-27 N/A NRI i , B-M-2 HPCI-CV-29CV. R-271 N/A VT-3 D-439 N/A 2509-2 N/A 14' VALVE GE-VT-100 0 91-29 -36 N/A SAT UM2 BJA-2 RHR-MO R-247 N/A VT-3 D-371 N/A 2510-1 N/A 20" VALVE GE-VT-100 0 91-29.-36 N/A SAT BM2 BODY B-N-1 CS PIPING R-302 N/A VT-1 VTD-07 N/A N/A N/A N/A VES. INT. VT-06 0 93-05 N/A NRI
- VTD-10 NRI B-N-1 CS SPARGERS R-302 N/A VT-1 VTD-83 N/A N/A N/A N/A VES. INT. VT-06 0 93-05 N/A NRI VTD-85 VT-06 0 93-05 NRI VTD-87 VT-06 0 93-05 NRI +
VTD-89 VT-06 0 93-05 NRI B-N-1 FW SPARGERS R-302 N/A VT-1 VTD-64 N/A N/A N/A N/A VES INT. VT-06 0 93-05 N/A NRI i VTD-70 VT-06 0 93-05 NRI VTD-73 VT-06 0 93-05 ~ NRI B-N-1 GUIDE RODS R-302 N/A VT-1 VTD-05 N/A N/A N/A N/A VES. INT. VT-06 0 93-05 N/A NRI + e t _m_ _._ ____._m-______._____.m.___.______.---_m..._.-.__.-.__m__m___ _~.___-a--_____._m__.__.________________________.___.______w -._m. _m___.___.__m_ _ ___. ._____s.-
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y G GE Nuclear Enstgy COOPER NUCLEAR STATION PAGE 18 of 28 ' , txAM COMPONENT INDEX REVISION No. O i SPRfNO 1993 i FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARl1Y Pm V3 REV. NO. STD. { CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMdtR NO. NPPD NO. COMMENTS B-N-2 JET PUMP R-302 N/A VT-1 VTD-14 N/A N/A N/A N/A VES. INT. VT-06 0 93-05 N/A NRI J RISER VTD-19 VT-06 0 93-05 ' NRI ; BRACKETS VTD-24 VT-06 0 93-05 NRI VTD-29 VT-06 0 93-05 NRI VTD-34 VT-06 0 93-05 NRI VTD-39 VT-0G 0 93-05 NRI VTD-44 VT-06 0 93-05 NRI VT D-49 VT-06 0 93-05 ' NRI VTD-54 VT-06 0 9345 NRI VTD-59 VT-M J 9305 NRI B-O CRD-02-27-1 R-032 SR-024 PT D-032 N/A GE197R576 N/A N/A CRD GE-P T-100 0 91-27 N/A NRI, EXAM LIMITED TO 50% COVERAGE B-O CRD-26-51-1 R-034 SR-026 PT D4)34 N/A GE197R576 N/A N/A CRD GE-P T-100 0 91-27 N/A NRI. EXAM LIMITED TO 50% COVERAGE 2 B-O CRD-30-03-1 R-033 SR-025 PT D-033 N/A GE197R576 N/A N/A CRD GE.PT-100 0 91-27 N/A NRI, EXAM LIMITED TO 50% COVERAGE B-P Rx FEEDWATER 93-744 N/A VT-2 93-744 N/A N/A N/A N/A N/A CNS 7.0.8.1 5 N/A N/A CNS 6 3.10.28 4 N/A N/A EXAMINED BY CNS B-P Rx FEEDWATER 93-745 N/A VT-2 93-745 N/A N/A N/A N/A N/A CNS 7.0.8.1 5 N/A N/A CNS 6.3.10.28 4 N/A N/A EXAMINED BY CNS ' B-P Rx COOLAN T 93-737 N/A VT-2 93-737 N/A N/A N/A N/A N/A CNS 7.0 8.1 5 N/A N/A CNS 6.3.10.28 4 EXAMINED BY CNS - . B-P Rx COOLANT 93-738 N/A VT-2 93-738 N/A N/A N/A N/A N/A CNS 7.0 8.1 5 N/A N/A CNS 6.3.10.28 4' EXAMINED BY CNS
, B-P Rx COOLANT 93-739 N/A VT-2 93-739 N/A N/A N!A N/A N/A CNS 7.0 8.1 5 N/A N/A CNS 6.3.10 28 -4 EXAMINED BY CNS B-P Rx COOLANT 93-740 N/A VT-2 93-740 N/A N/A N.'A N/A N/A CNS 7.0.8.1 -5 N/A - N/A CNS 6 3.10.28 4 EXAMINED BY CNS B-P Rx COOLANT 93-741 N/A VT-2 93-741 N/A N/A N/A N'A N/A CNS 7.0.8.1 5 N/A' N/A
, CNS 6.3.10.28 4 EXAMINED BY CNS 4 B-P Rx COOLANT 93-742 N/A VT-2 93-742 N!A N/A N/A N!A N!A CNS 7.0.8.1 5 , N/A N/A CNS 6 3.10.28 4 EXAMINED BY CNS _ . _ _ . . . . _ . . _ _ _ _ . _ . . _ _ _ m_ _ _ _ _ _ _ . _ _ _ _ _ _ _ .__;__m. . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ - _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . - . - - . - - . - . - ___~,-m____ __..___-_._._m =
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GE Nuclear Energy COOfYR NUCLE AR 5T Af TON PAGE 19 of 25 - EXANI COMPONENT INDEX REVISION No. O
' SF' RING 1993 FRR. CAL i ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT, DRAWING LINEARITY PROC. REV. NO. STD. l CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC . SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS B-P Rx COOLANT 93-743 N/A VT 2 93-743 N/A N/A N/A N/A N/A CNS 7.0.8.1 5 N/A N/A CNS 6.3.10.28 4 EXAMINED BY CNS
- B-P Rx COOLANT 93-746 N/A VT-2 93-746 N/A N/A N/A N/A N/A CNS 7.0.8.1 5 N/A N/A CNS 6.3.10.28 4 EXAMINED BY CNS B-P Rx COOLANT 93-747 N/A VT-2 93-747 N/A N/A N/A N/A N/A CNS 7.0 8.1 5 N/A N/A
! CNS 6 3.10.28 4 EXAMINED BY CNS B-P Rx COOLANT 93-748 N/A VT-2 93-748 N/A N/A N/A N/A N/A CNS 7.0 8.1 5 N/A N/A CNS 6.3.10.28 4 EXAMINED BY CNS B-P Rx COOLANT 93-749 N/A VT-2 93-749 N/A N/A N/A N/A N/A CNS 7.0.81 5 N/A N/A CNS 6.3.10.28 4 EXAMINED BY CNS ts. P Rx COOLANT 93-750 N/A VT-2 93-750 N/A N/A N/A N/A N!A CNS 7.0 81 5 N/A N/A CNS 6.3.10.28 4 EXAMINED BY CNS l B-P Rx COOLANT 93-751 N/A VT-2 93-751 N/A N/A N/A N/A N/A CNS 7.0 81 5 N/A N/A CNS 6.3.10.28 4 EXAMINED BY CNS - B-P Rx COOLANT 93-752 N/A VT-2 93-752 N/A N/A N/A N/A N/A CNS 7.0.8.1 5 N/A NTA CNS 6.3.10.28 4 EXAMINED BY CNS ' B-P - Rx COOLANT 93-753 N/A VT-2 93-753 N/A N/A N/A N/A N/A CNS 7.0.8.1 5 N/A N/A CNS 6.3.10.28 4 EXAMINED BY CNS B-P Rx COOLANT 93-754 N!A VT-2 93-754 N/A N/A N/A N/A N/A CNS 7.0.8.1 5 N/A N/A
- - CNS 6.3.10.28 4 EXAMINED BY CNS B-P Rx COOLANT 93-755 N/A VT-2 93-755 N/A N/A N/A N/A N/A CNS 7.0.8.1 5 N/A N/A CNS 6.3.10.28 4 EXAMINED BY CNS B-P Rx COOLANT 93-756 N/A VT-2 93-756 N/A N/A N/A N/A N/A CNS T.0 8.1 5 N/A N/A CNS 6.3.10 28 4 EXAMINED BY CNS B-P Rx COOtANT 93-757 N/A VT-2 . 93-757 N/A N/A N/A N/A N/A CNS 7.0.8.1 5 N/A N/A CNS 6.3.10.28 4 EXAMINED BY CNS B-P Rx COOLANT 93-758 N!A VT-2 93-758 - N/A N/A N/A N!A N/A CNS 7.0.8.1 5 N/A N/A CNS 6.3.10.28 4 EXAMINED BY CNS B-P Rx COOLANT 93-759 N'A VT-2 93-759 N/A N/A - N!A N!A N/A CNS 7.0 8.1 5 N/A N/A CNS 6.3.10.28 4 EXAMINED BY CNS '
B-P Rx COOLANT 93-760 N/A VT-2 93-760 N/A N/A N/A N/A N/A CNS 7.0.8.1 5 N/A N/A CNS 6.3.10.28 4 EXAMINED BY CNS B-P Rx COOLANT 93-761 N/A VT-2 93-761 N/A N/A N/A N/A N/A CNS 7.0.8.1 5 N/A N/A CNS 6.3.10 28 4 EXAMINED BY CNS i l
... __ _ _ _ _ _ _ _ _ . _ . . - _ _ -_ __ _ _ _ _ _ ~. ~ . . - . _ _ _ . . . _ _ _ _ . _ _ . . _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ ___.__._w
GE Nuclear Energy COOPER NUCLEAR STATION PAGE 20 of 28 EXAM COMFONENT INDEx REVi$ ION No. O - SPRING 1993 FRR CAL l ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARITY PROC. REV. NO. STD. CAT. ~ NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS - B-P Rx COOLANT 93-762 N/A VT-2 93-762 N/A N/A N/A N/A N/A CNS 7.0.8.1 5 N;A N/A CNS 6.3.10.28 4 EXAMINED BY CNS B-P Rx COOL. ANT 93-763 N!A VT-2 93-763 N/A N/A N/A N/A N/A CNS 7.0.8.1 5 N/A N/A CNS 6 3.10.28 4 EXAMINED BY CNS B-P Rx COOLANT 93-764 N/A VT-2 93-764 N/A N/A N/A N/A N/A CNS 7.0.8.1 5 N/A N/A CNS 6.3.10.28 4 EXAMINED BY CNS B-P Rx COOLANT 93-765 N'A VT-2 93-765 rJ/A N/A N/A N/A N/A CNS 7.0 8.1 5 N/A N/A CNS 6.3.10 28 4 EXAMINED BY CNS B-P Rx COOLANT 93-899 N/A VT-2 9 S 899 N/A N/A N/A N/A N/A CNS 7.0.8.1 5 N/A N/A CNS 6.110.28 4 EXAMINED BY CNS B-P Rx COOLANT 9'>900 N/A VT-2 93-900 N/A N!A N/A N/A CNS 7.0.8.1 5 N/A N/A CNS 6 3.10.28 4 EXAM!NED BY CNS B-P Rx COOLANT 93-901 N/A VT-2 93-901 N/A N/A N/A N/A N/A CNS 7.0 8.1 5 N/A N/A CNS 6.3.10.28 4 EXAMINED BY CNS - B-P Rx COOLANT 93-902 N/A VT-2 93-902 N/A N/A N!A N/A N/A CNS 7.0.8.1 5 N/A N!A i CNS 6.3.10 28 4 EXA. MINED BY CNS B-P Rx COOLANT 93-903 N/A VT-2 93-903 N/A N/A N/A N/A N/A CNS 7.0 8.1 5 N!A NIA i CNS 6.3.10.28 4 EXAMINED BY CNS B-P Rx COOLANT 93-904 N/A VT-2 93-904 N/A N/A N!A N/A N!A CNS 7.0.8.1 5 N/A N/A CNS 6.3.10.28 4 EXAMINED BY CNS , BD Rr COOLANT. 93-905 N/A VT-2 93-905 . N/A N/A N/A N/A N/A CNS 7.0.8.1 5 N/A N/A .; CNS 6.3.10.28 4 EXAMINED BY CNS C-A RHR-CA-3A R-249 SR-119 0' DM-403 CM-060 M-82454 L-004 62" DR-DREB GE-UT-301 0 91-13 106 NRI - 45'S DM-404 CM-061 L-004 GE-UT-301 0 91-13 '106 OD GEOMETRY EXAM UMITED TO 88.20% CO'KRAGE C-A RHR-CA-6A R-248 SR-118 0' DM-401 CM-060 M-82454 L-004 46' TS-CHS GE-UT-301 0 91-13 106 NRI .; 45'S DM-402 CM461 L-004 GE-UT-301 0 91-13 106 NRI. EXAM LIMITED TO . 86.5% e *ARAGE. C-B RHR-CB-3A R-266 SR-129 -MT D-427 N/A M-82454 N!A 20' - NOZ-RP GE-MT-100 0 91-25 N/A %RI C-8 RHR-CB-4A R-167 SR-058 MT D-207 N/A SWECO.M-8 N/A 20- RP-DR - GE-MT-100 0 91-25 . N/A NRl i 2454 I w.___ _ _ _ . . _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . , . . . , _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ . _ _ . . . . . . _ _ _ _ . _ _ _ _ . _ _ . _ _ _ _ _ . . _ . , . _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
GE Nuclear . Energy COOPE54 NUCLEAR STATION PAGE 21 of 28 - EXAM COMPONENT 1NDEX REVISION No. O SPRING 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWit(G LINEARITY PROC. REV. i NO. STD, CAT. NUMDER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER 40. NPPD NO. COMMENTS C-C CS-PA-A1 R-048 SR-031 MT D-058 N!A 2002-2 N'A N/A SUPPORT GE-MT-100 0 91-25 N/A NRL PT D-059 GE-PT-100 0 27 NRl, EXAM UMITED TO - 98.55% FULL COVERAGE WITH CODE CASE N-460. C-C CS-PB-A1 R-038 SR-022 MT D-048 N/A 2602-1 N/A N!A SPRT GE-MT-100 0 91-25 N/A REPORTABLE UNEAR IND, EXAM LIMITED TO 98.55% FULL COVERAGE WITH CODE GASE N-400. R-296 SR-142 MT D-478 N/A GE-M T-100 0 91-25 POST REPAIR.NRt PT D-049 N/A GE-PT-100 0 91-27 NRI C-C CSA-CC-1 A R-012 SR-012 MT D-012 N'A CB&f49 N/A 16* PC-P GE-MT-100 0 91-25 N/A NRI C-C CSB-CC-1A R-015 SR-015 MT D-015 N/A CB&l49 N/A 16" PC-P GE-MT-100 0 91-26 N/A NRI C-C CSB-CC-WR2 R414 SR-014 MT D-014 N/A KE 110.01 N/A 16" S-P GE-MT-100 0 91-25 N/A NRI C-C HPIS-CC-1A R-007 SR 007 MT D-007 N/A CB&l49 N/A 16" . P-PC GE-MT-100 0- 91-25 N/A NRI C-C RHB-CE1-2 R-166 SR-077 MT D-250 N/A 2624-1 N/A 16" EL GE-MT-100 0 91-25 N/A NRI C-C RHR-PA-A1 R-197 . SR-080 MT D-261 . N/A 2624-1 N!A N/A SUPPORT GE-MT-100 0 91-25 N/A NRI PT D-262 - N/A GE-PT-100 0 91-27 C-C RHR-PB-A1 R-184 SR-075 MT D-247 N/A 2624-3C N/A N!A SUPPO1T GE-MT-100 0 01-25 N/A NRI PT D-248 ~ N/A GE-PT-100 0 91-27 NRI C-C RHR-PC-A1 R-198 SR-081 MT D-263 N/A 2624-1 N/A N/A SUPPORT GE-M T-100 0 91-25 N/A NRI PT D-264 N/A GE-PT-100 0 91-27 C-C RHR-PD-A1 R-183 SR-074 MT D-245 N/A 2624-3C N/A N/A SUPPOPT . GE-VT-100 0 91-25 N!A NR1 PT D-246 N/A GE-PT-100 0 _ 91-27 NRI C-C RPA-CC-1 A R-009 SR-009 MT D-009 N/A CB&l-69 N/A - 20* P-PC GE-MT-100 0 91-25 N.'A ' NRI C-C RPB-CC-1A R-010 SR-010 MT D410 N/A CB&l49 N/A 20* P-PC GE-MT-100 0 91-25 N> A NRI C-C RPC-CC-1A R-011 SR411 MT D-011 N/A CB&l-69 N/A 20* P-PC GE-MT-100 0 31-25 N'A NRI C-C RPD-CC-1A . R-008 SR-008 MT D-008 N/A CB&l49 N/A 20" P-PC GE-M T-100 0 i)1-25 N/A NRI l C-C RWA-CC-13 R-013 - SR-013 MT D-013 N/A CB&l49 N/A 6' ' P-et GE-MT-100 0 91-25 N/A NRI C-F CSA-CF-13 R-016 SR-016 MT- D-016 . N/A 2603-1 N/A 14* V-P GE-MT-100 0 91-25 N/A NRI C-F CSA-CF-28 R-018 SR-018 Mr D-018 N/A 2602 N/A 12' E-V CE-M T-100 0 91-25 N/A NRI C-F CSA-CF-29 R-017 SR-017 MT D-017 N/A 2602-2 N//, 12" V-P GE-MT-100 0 91-25 N/A NRl C-F CSB-CF-t2 R-006 SR-006 MT D-006 N'A 2603 N/A 16" P-RE GE-MT-100 0- 91-25 N!A NRi
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O GE Nuclear Energy i COOPER NUCLEAR STADON P/GE 22 W 28 EXAM COMPONENT INDEX REVIStDN No. O SPRING 1993 i
! FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS C-F. CSB-CF-15 R-001 SR-001 MT D-001 N/A 2603-2 N/A 14' V-P GE-M T-100 0 91-25 N/A NRI C-F CSB-CF-16 R-002 SR-002 MT D-002 N/A 2003-2 N/A 14' P-V GE-MT-100 0 91-25 N/A NRt C-F CSB-CF-17 R405 SR-005 MT D-005 N/A 2603-2 N/A 14" V-P GE-MT-100 0 91-25 N/A NRI C-F CSB-CF-33 R-004 SR 004 MT D-004 N/A 2602-1 N!A 12" E-V CF.-MT-100 0 91-25 N/A NRI C-F CSB-CF-34 R-003 SR-003 MT D-003 N/A 2002-1 N/A 12" V-P GE-MT-100 0 91-25 N/A NRJ C-F PSA-CF-10 R-075 SR-110 MT D-111 N/A 2629-1 WA 10" E-P GE-MT-100 0 91-25 N/A NRI 0* DM-113 CM410 L-004 GE-UT-10G 1 91-08 -37 78 NM: 45'S DM-373 CM-011 L-004 GE-UT-106 1 91-08,-37 78 NRI C-F PSA-CF-15 R-269 SR-131 MT D-433 N/A 2629-1 N'A 10" P-T GE-MT-100 0 91-25 N!A NRI 0' DM-434 CM-073 L-008 GE-UT-106 1 91-08,-37 78 NRI 45'S DM-435 C M-074 L-008 GE-UT-106 1 91-08,-37 78 NRI C-F PSA-CF-6 P-074 SR 039 MT D-110 N/A 2629-1 N!A 10' T-R GE-M T-100 0 91-25 N/A NRI 0' DM-112 CM-010 L-004 GE-UT-106 1 91-08.-37 78 NRI 45'S DM-372 CM-011 L-004 CE-U T-106 1 91-08.-37 78 NRI C-F RAS-CF-13 R-085 SR-042 PT D-121 N/A 2629-1 8" P-E GE-PT-100 0 91-27 N/A NRI 0' DM-187 CM-013 L-009 GE-UT-106 1 91-08.-37 73 NRI 45'S DM-188 CM-014 L-009 GE-UT106 1 91-08.-37 73 NRI C-F RAS-CF-36 R-270 SR-132 MT D-438 N/A 2629-1 N/A 8* R-P GE-MT-100 0 91-25 N/A NRI 0' DM-436 CM-075 L-006 GE-UT-106 1 91-08.-37 73 NRI 45'S DM 437 CM-076 L-008 GE-UT-106 1 91 08-37 73 NRl C-F RAW-CF-1 R-202 SR-085 MT D-268 N/A 2625-2 N/A 20* P-T GE-MT-100 0 91-25 N/A NRI C-F RAW-CF-41 ' R-185 SR-076 . MT D-249 N/A 2624-2 N/A 18' E-E GE-MT-100 0 91-25 N/A NRI C-F RAW-CF-5 R-201 SR-084 MT D-267 N/A 2625-2 N/A 20* P-E GE-MT-100 0 91-25 N/A . NRI C-F RAW-CF-69 R-083 SR-041 PT D-119 N/A 2624-3A N/A 16' P-E GE-PT-100 0 91-27 N/A NRI C-F RHB-CF-10 R-196 SR-079 MT D-260 N/A 2624-1 N/A 16" E-P GE-MT-100 0 91-25 N/A NRI -l C-F- RHG-CF-19 R-046 SR-023 MT D-056 N/A 2624-2 N/A 10' E-V - vE-MT-100 0 91-25 N/A NRI - C-F RHG-CF-5 R-086 SR-043 Mr D-122 - N/A 2624-2 N/A 10" E-V GE-MT-100 0 91-25 N/A NRI j C-F RPC-CF-22 R-199 SR-082 MT D-265 N/A 2624-1 N/A - 16' V-P GE-MT-100 0 P1-25 N/A NRt C-F RSA-CF-1 R-037 SR-021 PT D-047. N/A 2614-1 N!A 8' T-F GE-PT-100 0 91-27 N/A NRI C-F RWA-CF-1 R-055 SR-027 MT D-067 N/A 2629-2 N/A 8* CAP-P GE-MT-100 0 91-25 N/A NRI 0" DM-349 CM-004 L-004 - GE-UT-106 1 91-08,-37 73 NRI 45'S . DM-068 CM-005 L-004 GE-UT-106 1 91-08.-37 73 NRI C-F SDN-CF-11 R-267 SR-130 MT D-428 N/A 19-EP-1 A-2 N/A 8" P-P GE-MT-100 0 91-25 N/A NRI C-F SDN-CF-9 R-200 SR-083 MT D-266 N/A S-W13095 N/A 8* CAP-P GE-MT-100 0 91-25 N/A NRI
@ GE Nuclear Energy COCPER NUCLEAR STATION PAGE 23 of 28 EKAM COMPONENT INDEY REVISION No. O 5PRING 1993 FRR CAL i ASME. COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING UNEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS C-F SDS-CF-6 R-182 SR-073 MT D-244 N/A S-W13095 N/A 8* P-T GE-MT-100 0 91-25 N/A NRI D-A SLC 92-305 C2-3422 VT-2 92-305 N/A N/A N/A N/A N/A CNS 7.0.8.1 4 N/A N/A SAT; NON4AFETY RELATED PORTIONS OF SYSTEM, NO LONGER IN ISI PROGRAM D-A VR-DA-1 R-128 N!A VT-3 D-164 '?A 2628-1 N/A N/A LUG GE-VT-100 0 91-29,-36 N/A SAT D-A VR-DA-2 R-128 N/A VT-3 D-164 N!A 2628-1 N/A N/A LUG GE-VT-100 0 91-29.-36 N/A SAT D-A VR-DA-3 R-140 N/A VT-3 D-176 N/A 2628-1 N/A N/A PLATE GE-VT-100 0 91-29.-36 N/A SAT D-B HPCI 93-304 92-3421 VT-2 92-304 N/A N'A N/A N/A N/A CNS 7.0.8.1 4 N!A N/A SAT; INTERVAL 2 PERIOD 2 REQUIRED PRESSURE TEST; REF.: NCR 92-133 AND LER 92-18 D-C FPC 92-310 92-3440 VT-2 92-310 N'A N/A N/A N/A N/A CNS 7.0.8.1 4 N/A N/A SAT; NON-SAFETY RELATED PORTIONS GF SYSTEM, NO LONGER IN '
. ISI PROGRAM
-. .y 4 _ . __.
F-A CS-PB-Si R-019 N/A VT .> ' 4 19 N/A 2602-2 N/A N/A PUMP GE-BG-100 0 91-29 -36 N/A SAT F-A CS-PB-S1 R-029 N/A VT-3 s-029 N'A 2602-1 N/A N/A PUMP GE-VT-100 0 91-29.-36 N/A SAT SUPPORT F-A CSA-X-227A R-084 N/A VT-3 D-120 N/A . CBal-69 N/A N!A PENT. GE-VT-100 0 91-29,-36 N/A SAT F-A CSB-WR-2 R-020 N'A VT-3 D-020 N/A KE-110.01 N/A N/A TORUS GE-VT-100 0 91-29.-36 N/A SAT PENT. i F-A CSB-X-2278 R-084 N/A VT-3 D-120 N/A CB&l-69 N/A N/A PENT. GE-VT-100 0 91-29,-36 N/A SAT F-A HPCI-BP-Si R-021 N/A VT-3 D-021 N/A 2611-6 N/A N/A PUMP GE-VT-100 0 91-29 -36 N/A SAT F-A HPCl41P-S1 R-028 N/A VT-3 0-028 N/A 26041 N/A N/A PUMP GE-VT-100 0 91-29,-36 N/A SAT . F-A ~ HPIS-X-226 R-084 N/A l VT-3 D-120 N!A CB&l-69 N'A N/A PENT. GE-VT-100 0 91-29,-36 N/A SAT F-A RCIC-MP-Si R427 N/A ' VT-3 D-027 'N/A 2621-1 N!A N/A PUMP GE-VT-100 ' O 91-29.-36 N/A SAT F-A RHH-5A R-063 N/A ' VT-3 0-090 N/A RH-H5A N/A N/A RESTRNT GE-VT-100 0 91-29.-36 ~ N/A SAT F-A RHR-PA-S1 R-194 N/A VT-3 D-258 N/A 2624 N/A N/A SUPPORT GE-VT-100 0 91-29.-36 N/A SAT - s
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'h GE Nuclear Energy COOPER NUCLEAR STADON PAGE 24 et 28 EXAM COMPONENT INDfX REYeslON No, O SPRING 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL. SH T. DRAWING UNEARITY PROC. REV, NO. STD. CA1. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS F-A RHR-PB-Si R-102 N/A VT-3 D-138 N/A 2624-3C N/A N/A SUPPORT GE-VT-100 0 91-29 -36 N/A SAT F-A RHR-PC-S1 R-195 N!A VT-3 D-259 N/A 2624-1 N/A N/A SUPPORT GE-VT-100 0 91-29,-36 N/A SAT F-A RHR-PD-S1 R-102 N/A VT-3 D-138 N!A 2624-3C N/A NA SUPPORT GE-VT-100 0 91-29,-36 N/A SAT F-A RHR-X-225A R-084 N/A VT-3 D-120 N/A CB&W9 N/A N/A PENT. GE-VT-100 0 91-29.-36 N/A SAT F-A RHR-X-225B R-084 N/A VT-3 D-120 N/A CB&l-69 N/A N/A PENT. GE-VT-100 0 91-29.-36 N/A SAT F-A RHR-X-225C R-084 N/A VT-3 D-120 N!A CB&l-69 N/A N/A PENT. GE-VT-100 0 91-29.-36 N/A SAT F-A RHR-X-22SD R-084 N/A VT-3 D-120 N/A CB&l-69 N/A N/A PENT. GE-VT-100 0 91-29.-36 N/A SAT F-A RWA-X-224 R-084 N/A VT-3 D-120 N/A CB&l-69 N/A N/A PENT. GE-VT-100 0 91-29 -36 NA SAT F-A SLC-PA-Si R-080 N/A VT-3 D-116 N/A 2712-1 N 'A N/A SUPPORT GE-VT-100 0 91-29.-36 N/A SAT F-A SLC-PB-Si R-081 N/A VT-3 D-117 N/A 2712-1 N/A N/A SUPPORT GE-VT-103 0 91-29.-36 N!A SAT F-B MSH-107 R-041 N/A VT-3 D-051 N/A 2629-1 N!A N/A STRUT GE-VT-100 0 91-29,-36 N/A SAT F-B MSH-107A R-040 N/A VT-3 D-050 N/A 2629-1 WA N/A STRUT GE-VT-100 0 91-29.-36 N/A SAT F-B MSH-111 R-106 N/A VT-3 D-142 N/A 2629-1 WA N/A SWAY GE-VT-100 0 91-29,-36 N/A SAT
- BRACE F-B MSH-151 R-043 N/A VT-3 D-053 NA MSH-151 N/A N/A STN GE-VT-100 0- 91-29.-36 N/A SAT F-B MSS-17 R-108 N/A VT-3 0-144 N!A 2629-1 N/A N/A RlGID GE-VT-100 0 91-29.-36 N/A SAT STRUT F-B MSS-18 R-109 N/A VT-3 D-145 N/A 2629-1 N/A N/A STRUT GE-VT-100 0 91-29 -36 N/A SAT F-B RHH-4B R-104 N/A VT-3 D-140 N/A 2625-1 N!A N/A BRACE GE-VT-100 0 91-29.-36 N/A SAT F-B RHH-6 R-053 N/A VT-3 D-064 N/A 2626-1 N/A N/A SUPPORT GE-VT-100 0 91-29.-36 N/A SAT F-8 RHH-93 R-217 N/A VT-3 D-291 N/A 2624-2 N/A N'A RESTRNT GE-VT-100 0 91-29-36 N/A SAT F-B RHH-938 R-107 N/A VT-3 D-143 N/A 2624-2 N/A N!A SWAY GE-VT-100 0 91-29,-36 N/A SAT BRACE F-B RHS-81 R-104 N!A VT-3 D-140 N/A 2625-1 N/A N/A STRUT GE-VT-100 0 91-29,-36 N/A SAT F-B RPV-STB-1A R-301 N/A VT-3 D-483 N/A 731E306 N/A N'A STAB. GE-VT-100 0 91-29,-36 N/A SAT BRACKET F-8 RPV-ST B-3A R-277 N/A VT-3 D-457 N/A 731E306 P4/A N/A STAB. GE-VT-100 0 91-29,-36 N/A SAT BRACKET F-B RPV-STB-4A R-306 N/A VT-3 D-484 N/A 731E306 N/A N/A ' STAB, GE-VT-100 0 91-29.-30 N!A SAT BRACKET F-B VRH-51A R-134 N/A VT-3 D-170 N/A 2628-1 KA MA- BRACE GE-VT-100 0 91-29,-36' N/A SAT-
GE Nuclear Energy COOPER NUCLEAR STArtON PAGE 25 of 28 EXAM COMPONENT INDEA REVISION No. O SPRING 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT, DRAWING LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO NPPD NO. COMMENTS F-C MSH-133 R-145 N/A VT-3 D-181 N/A 2506-1 N/A N/A VARI. GE-VT-100 0 91-29,-36 N/A SAT, SEE MWR 93-1231 VT-4 SUPPORT IV4-W812 2 91-31,-34 F-C MSH-140 R-274 N/A VT-3 D-454 N/A 2614-2 N/A N/A VARI. GE-VT-100 0 91-29,-36 N/A SAT VT-4 SPRING IV4-W812 2 91-31 -34 F-C- MSH-147 R-223 N/A VT-3 D-309 N/A 2506-2 N/A N/A HANGER GE-VT-100 0 91-29,-36 N/A SAT VT-4 IV4-W812 2 91-31.-34 F-C MSH-152 R-044 N/A VT-3 D-054 N/A MS-H152 N/A N/A SUPPORT GE-VT-100 0 91-29.-36 N/A SAT VT-4 IV4-W812 2 91-31,-34 , F-C MSH-98 R-216 N/A VT-3 D-290 N/A 2629-1 N/A N/A HANGER GE-VT-100 0 91-29.-36 N/A SAT VT-4 IV4-W812 2 91-31 -34 F-C MSS-6 R4)45 N/A VT-3 D-055 N/A MS-S6 N/A N/A RESTRNT GE-VT-100 0 91-29.-36 N/A SAT. F-C MSS-8 R-218 N/A VT-3 D-292 N/A 2629-1 N/A N/A STRUT GE-VT 100 0 91-29.-36 N/A SAT F-C RFH-54A R-031 N/A VT-3 D-031 N/A RF-H54A N/A N/A HANGER GE-VT-100 0 91-29.-36 N/A SAT VT-4 IV4-W812 2 91-31,-34 F-C RFH-56 R-030 N/A VT-3 D-030 N/A RF-H56 N'A N/A SUPPORT GE-VT-100 0 91-29.-36 N!A SAT F-C RFH-62A R-224 N/A VT-3 D-310 N/A 2509-2 N/A N/A HANGER GE-VT-100 0 91-29 -36 N/A SAT VT-4 IV4-WB12 2 91-31.-34 i F-C RFH-64 R-0G4 N/A VT-3 D-091 N/A RF-H64 N/A N!A SUPPORT GE-VT-100 0 91-29-36 N/A SAT VT-4 IV4-W812 2 91-31,-34 F-C RFH-64A R-065 N/A VT-3 D-092 N/A RF-HG4A N/A N/A SUPPORT GE-VT-100 0 91-29 -36 N/A SAT ' VT-4 IV4-W812 2 91-31 -34 i I F-C RFS-10 R-072 N/A VT-3 D-109 N/A RF-S10 N/A N/A SHOCK GE-VT-100 0 91-29,-36 N/A SAT VT-4 ARRESTR IV4-W812 2 91-31,-34 F-C RHH-120 R-154 N/A VT-3 0-194 N/A 2510-4 N/A N/A HANGER GE-VT-100 0 91-29.-36 N/A SAT VT-4 IV4-W812 2 91-31,-34 F-C RHH-120A R-118 N/A VT-3 D-154 N/A 2510-4 N/A N/A VARI. GE-VT-100 0 91-29,-36 . N/A SAT VT-4 SUPPORT IV4-W812 2 91-31 -34 F-C RHH-122 R-114 N/A VT-3 D-150 N/A 2510-4 N/A N/A SUPPORT GE-VT-100 0 91-29,-36 N/A SAT-R-297 VT-4 D-479 IV4-W812 2 91-31.-34 2 SAT F-C RHH-26 R-105 N/A VT-3 D-141 N/A 2624 1 N/A N/A SUPPORT GE-VT-100 0 91-29,-36 N/A SAT VT-4 IV4-W812 2 91-31 -34 i i W_.- ..-_._a-.a__--.. _ . - - - - - - _ _ ..a.-u__---.___---_ _ _ _ _ _ _ _ _ _ _ - - -,rr . , ,
i GE Nuclear Energy i l COO 8'fR NUCLEAR ST ATLON PAGE 26 of 28 EXAM COMPONENT INDEX REVISION No. 0 SFHING 1993 l l FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING UNEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO COMMENTS
- F-C RHH-28 R-193 N/A VT-3 D-257 N/A 2624-1 N/A N/A VARI. GE-VT-100 0 91-29.-36 N/A SAT i
R-298 VT-4 D-480 SUPPORT IV4-W812 2 91-31,-34 SAT F-C RHH-32A R-155 N/A VT-3 D-195 N/A 2510-1 N/A NJA SUPPORf GE-VT-100 0 91-29,-36 N/A SAT V T-4 IV4-W812 2 91-31.-34 F-C RHH-33 R-162 N/A VT-3 D-202 N/A 2510-1 N/A N/A HANGER GE-VT-100 0 91-29,-36 N/A SAT VT-4 IV4-W812 2 91-31,-34 F-C RHH-35 R-153 N/A VT-3 D-193 N/A 2510-1 N!A N/A HANGER GE-VT-100 0 91-29,-36 N/A SAT VT-4 IV4-W812 2 91-31,-34 , F-C RHS-10 R-152 N/A VT-3 D-192 N/A 2510-4 N/A N/A HANGER GE-VT-100 0 91-29,-36 N/A SAT VT-4 IV4-W812 2 91-31,-34 + F-C RHS-3A R-141 N/A VT-3 D-177 WA 262G-1 N 'A N/A MECH. GE-VT-100 0 91-29.-36 N/A SAT VT-4 SNUBBER N4 W812 2 91-31,-34 F-C RHS-5 R-113 NTA VT-3 D-149 N/A 2510-4 N/A N/A SUPPORT GE-VT-100 0 91-29.-36 N/A SAT VT-4 IV4-WB12 2 91-31,-34 F-C RHS-67 R-156 N/A VT-3 D-196 N/A 2510-1 MA N/A SHOCK GE-VT-10G 0 91-29,-36 N/A SAT VT-4 ARRESTR N4-W812 2 91-31 -34 F-C RHS-68 R-157 N/A VT-3 D-197 N'A 2510-1 N/A N!A SHOCK GE-VT-100 0 91-29.-36 N/A SAT VT-4 ARRESTR IV4-W812 2 91-31,-34 F-C RHS-7 R-112 N/A VT-3 D-148 N *A 2510-4 N/A N/A SUPPORT GE-VT-100 0 91-29 -36 MA SAT F-C RHS-70 R-158 N/A VT-3 D-198 N/A 2510-1 N/A N/A SHOCK GE-VT-100 0 91-29.-36 N/A SAT VT-4 ARRESTR IV4-W812 2 91-31,-34 F-C RHS-71 R-160 N/A VT-3 D-200 N/A 2510-1 N/A N/A SHOCK GE-VT-100 0 91-29,-36 N/A SAT VT-4 ARESSTR IV4-W812 2 91-31,-34 F-C RHS-73 R-161 N/A VT-3 D-201 N/A 2510-1 N/A NA SHOCK GE-VT-100 0 91-29,-36 N/A SAT VT-4 ARESSTR IV4-W812 2 91-31,-34 F-C RHS-8 R-150 N/A VT-3 D-190 N/A 2510-4 N/A N/A SHOCK GE-VT-100 0 91-29 -36 N/A SAT VT-4 ARRESTR IV4-W812 2 91-31,-34 F-C RHS-80 R-101 N/A VT-3 D-137 N/A 2625-1 N/A N/A MECH GE-VT-100 0 91-29,-36 N/A SAT VT-4 SNUBBER N4-W812 2 91-31 -34 F-C RHS-8C R-149 WA VT-3 D-189 N/A 2510-4 N/A N/A SHOCK GE-VT-100 0 91-29,-36 N/A SAT VT-4 ARRESTR IV4-W812 2 91-31,-34 F-C RHS-9 R-151 N/A VT-3 D-191 N/A 2510-4 N/A N/A MECH- GE-VT-100 0 91-29,-36 N/A SAT VT-4 SNUBBER IV4-W812 2 91-31,-34 _ _ _ _ _ _ _ ~ _ _ _ _ _ _ . _ , ~. _ _ ._ _ _ _ _ . . . - , , ,- - . . _ __ .-._ . _ . _ _ _ - _ _ _ . _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _
@ GE Nuclear Energy COOPER NUCLEAR STATION PAGE 27 of 28 EXAM COMPONENT INDEX REVISON No. O SPRING 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO, - COMMENTS F-C RR-H6-A R-126 N/A VT-3 D-162 N/A ISO-RL-A N/A N/A SUPPORT GE-VT-100 0 91-29,-36 N/A' SAT VT-4 N4-W812 2 91-31,-34 F-C RR-H6-B R-126 N/A VT-3 D-162 N/A ISO-RL-B N/A N/A SUPPORT GE-VT-100 0 91-29,-36 N/A SAT VT-4 IV4-W812 2 91-31,-34 FC RR-SSS-A R-117 N/A VT-3 D-153 N/A ISO-RL-A N/A N/A MECH. GE-VT-100 0 91-29,-36 N/A SAT VT-4 SNUBBER N4-W812 2 91-31,-34 F-C RR-SS5-B R-116 N/A VT-3 D-152 N/A ISO-RL-B N/A N/A MECH. GE-VT-100 0 91-29.-36 N/A SAT VT-4 SNUBBER N4-W812 2 91-31,-34 F-C VR-61-17X R-130 N/A VT D-166 N/A 2628-1 N/A N/A MECH. GE-VT-100 0 91-29.-36 N/A SAT VT-4 SNUBBER IV4-W812 2 91-31,-34 F-C VR-61-8X R-135 N/A VT-3 D-171 N!A 2628-1 N/A N/A MECH. GE-VT-100 0 91-29 -36 N/A SAT VT-4 SNUBBER IV4-W812 2 91-31 -34 F-C VR-61-82 R-142 N/A VT-3 D-178 . N/A 2G28-1 MA N/A MECH. GE-VT-100 0 91-29.-36 N/A SAT VT-4 SNU9BER IV4-W812 2 91-31,-34 F-C VRH-49 R-136 N/A VT-3 D-172 N/A 2628-1 N/A N/A CONST. GE-VT-100 0 91-29,-36 N/A SAT VT-4 SUPPORT IV4-W812 2 91-31,-34 F-C VRH-49A R-125 N/A VT-3 D-161 N/A 2628-1 N/A N/A VARI. GE-UT-100 0 91-29 -36 N/A SAT VT-4 SUPPORT N44V812 2 91-31,-34 SAT R-289 VT-4 D-471 N4-W812 ~ 2 91-31,-34 SAT F-C VRH-50 R-137 N/A VT-3 D-173 N/A 2628-1 N/A N/A VARI. GE-UT-100 0 91-29,-36 N/A SAT R-290 VT-4 D-472 SUPPORT IV4-W812 2 91-31,-34 SAT F-C VRH-51 R-138 N/A VT-3 D-174 N/A 2628-1 N/A N/A- SUPPORT GE-VT-100 0 91-29.-36 N/A SAT R-291 VT-4 D-473 IV4-W812 2 91-31,-34 SAT F-C VRS-7 R-129 N/A VT-3 0-165 N/A 2628-1 N/A N/A MECH. GE-VT-100 0' 91-29.-36 N/A SAT VT-4 SNUBBER IV4-W812 2 91-31,-34 F-C VRS-70 R-131 N/A VT-3 D-167 N/A 2628-1 N!A N/A MECH- GE-VT-100 0 91-29,-36 N/A SAT VT-4 SNUBBER IV4-W812 2 91-31,-34 F-C VRS-71 R-132 N/A VT-3 D-168 N/A 2628-1 N/A N/A MECH. GE-VT-100 0 91-29.-36 N/A SAT VT-4 SNUBBER IV4-W812 2 91-31,-34 i' i' I
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' GE Nuclear Energy COOPER NUCLEAR STATON PAGE 2S of 28 -
EKAM COMPONENT INDEX REVtS!ON No O ' SPRING 1933 CAL SHT. FRR- CAL ASME COMPONENT
SUMMARY
EXAM DATA RECORD DRAWING LINEARITY PROC. REV NO. STD. CAT. NUMBER REPORT -RECORD TYPE SHEET ISOMETRIC SHEET St2E CONF. NUMBER NO. NPPD NO. COMMENTS F-C VRS-72 R-133 N/A VT-3 D-169 N/A 2628-1 N/A N/A MECH. GE-VT-100 0 91-29-36 N.'A SAT VT-4 SNUBBER IV4-W812 2 91-31.-34 F-C VRS-73 R-144 N!A VT-3 D-1BO N/A 2628-1 N/A N/A MECH. GE-VT- 100 0 91-29.-36 N/A SAT VT-4 SNUBBER IV4-WB12 2 91 31,-34 F-C VRS-74 . R-143 N/A VT-3 D-179 . N/A 2628-1 N/A N/A MECH. GE-VT-100 0_ 91-29,-3G N/A SAT VT-4 SNUBBER IV4-W812 2 91-31,44 F-C VRS-8 R-127 ' N/A VT-3 0-163 N/A 2628 1 N/A N/A MECH. GE-VT-100 0 91-29. 4 N/A SAT VT-4 SNUBBER IV4-W812 2 91-31,-34 a._...______..______ _ . _ . . ________....:._ ___________...____._.u_______2__________.. ~ __.____._-___m.. . . _ . .
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@ GE Nuclear Energy COOPER NUC' E AR ST ATION PAGE 1 of 12 AUGMENTED EXA M COMFOdNT INDEx REVtSION No. O
$PRING 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS AUG CSA-BF-1 R-278 SR-137 PT D-458 N/A CNS-CS-4 N/A 13.4" SE-NOZ GE-PT-100 0 93-27 N/A NRt 45'S DA-016 CA-015 L-021 GE-UT-209 1 93-03 51 ID GEOMETRY CA-016 L-021 GE-UT-209 1 9M3\ 61 NRI 45'RL DA-017 CA4)17 L-021 GE-UT-209 1 93-03 121 ACOUSTIC INTERFACE & ID GEOMETRY 60' RL DA-018 CA-018 L-021 GE-UT-209 1 93-03 121 ACOUSTIC INTERFACE & ID GEOMETRY FOR GL8841 AND ASME SECTION XI CREDIT. AUG CSA-PIPE R-302 N/A VT-1 VTD-107 N/A N/A N/A N!A VES. INT. VT-06 0 93-05 N/A NRI AUG CSA-SPARGER R-302 N/A VT-1 VTD-83 N/A N/A N/A N/A VES INT. VT-06 0 93-05 N/A NRI VTD-87 VT-06 0 9M5 NR. AUG CSB-PIPE R-302 N/A VT-1 VT D-10 N/A N/A N/A N/A VES. INT. VT-06 0 93-05 N/A NRL AUG CSB-SPARGER R-302 N/A VT-1 VTD-85 N/A N/A N/A N/A VES. INT. VT-06 0 9M5 N/A NRI VfD-89 VT-06 0 93-05 NRI AUG CWA-CF-54 R-214 SR-095 45'S DM-288 CM-031 2605-4 L-009 6' P-E GE-UT-102 2 91-05 48 NRI AUG FWD-BK1-42 ' R-168 SR-059 MT D-208 N/A' 2849-4 N/A 18' E-L GE-MT-100 0 91-25 N/A NRI AUG FWD-BK1-50 R-229 - SR-104 MT' D-346 N/A - 2849-4 N/A 18" E-LUG GE MT-100 0 91-25 -N/A NRI AUG JET PUMP RISER R-302 N/A VT-1 VTD-14 N/A N/A N/A N/A VES. INT. VT-06 0 9%5 N/A NRI - SIL 551 BRACKETS VTD-19 VT-06 0 93-05 VTD-24 VT46 0 93-05 VTD-29 VT-06 0 93-05 VTD-34 VT-06 0 93-05 VTD-39 VT-06 0 93-05 VTD-44 VT-06 0 9%5
, VTD-49 VT-06 0 ESOS -
VTD-54 VT-06 0 93-05 VTD-59 VT-06 0 93-05 AUG JPB-01 R-300 N/A 55'S D-488 CM48? N/A L-020 N/A JPB GE-tr.-500 0 9M7 119 NRI THROUGH JET PUMP BEAMS JPB-20 i _ _ . _ . _ _ . . _._.m _...m_. ._____-____-__.____________.___m__._______m___- .- - w., -- -,---v -
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GE Nuclear Energy COOPER NUCl. EAR STATION PAGE 2 of 12 AUGMENTED EKAM COMPONENT INDEX REVISf0N No. O SPRING 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARITY PROC. RFV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMElRIC SHEET SIZE CONF. NUMBER NPPD NO. COMMENTS t AUG JPB-BF-1 R-220 SR-097 PT D-302 N/A CE232-241 N/A 6' SE-NOZ GE-PT-100 0 91-27 N/A NRI 45'S DM-299 CM-034 L-004 GE-UT-105 2 91-07 109 NRI CM-035 L-004 GE-UT-105 2 91-07 107 NRI 45'RL DM-300 CM-036 L-004 GE-UT-105 2 91-07 109 ID COUNTEP. BORE CM-037 L-004 GE-UT-105 2 91-07 107 ID COUNTERBORE 60'RL DM-301 CM-038 L-004 GE-U T-105 2 91-07 109 NRI CM-039 L-004 GE-U T-105 2 91-07 107 NRI FOR GL88-01 AND ASME SECTION Xi CREDIT. ! AUG MSA-AB R-051 N/A VT-1 D-062 N/A GE731E671 N/A N/A BOLT IV1-W812 3 1 N/A SAT AUG MSB-AB R-050 N/A VT-1 D-061 N/A GE731E671 N/A N/A BOLT N1-W812 3 i N/A SAT AUG MSC-AB R-049 N.A VT 1 D-060 N/A GE731E671 N/A N/A BOLT IV1-W812 3 1 N/A SAT AUG MSD-AB R452 N/A VT-1 D-063 N/A GE731E671 N/A N/A BOLT N1-W812 3 1 N/A SAT AUG MSH-104 R-235 N/A VT-3 D-353 N/A 2629-1 N/A N/A CONSTNT GE-VT-100 0 91-29,-36 N/A SAT VT-4 SUPPORT N4-W812 2 91-31,-34 EXAMINED DUE TO FALSE SAMPLE EXPANS!ON FOR MSH-133 AUG MSH-132 R-237 N/A VT-3 D-355 N/A 2506-1 N/A N/A HANGER GE-VT-100 0 91-29.-36 N/A SAT VT-4 IV4-W812 2 91-31,-34 AUG MSS-22 R-236 N/A VT-3 D-354 N/A 2506-1 N/A N/A SHOCK GE-VT-100 0 91-29.-36 N/A SAT VT-4 ARRESTR N4-W812 2 91-31,-34 , AUG PRF-102 R-070 SR-038 VT-1 D-104 N/A 730E878 N/A 32_5' RGB-PED IV1-W812 3 i N/A SAT ! R-069 0' DM496 CM409 L-009 MulB-NX12 1 N/A PRF-3 NRI AUG PRF-103 R-070 SR-038 VT-1 D-104 N/A 730E878 N/A 32.5" RGB-PED N1-W812 3 1 N/A SAT R-069 0* DM-096 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-104 R-070 SR-038 VT-1 0-104 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-069 0' DM-099 CM-009 L-009 MulB-NX12 1 N/A PRF-3 NRI AUG PRF-108 ' R-070 SR-038 VT-1 D-104 N/A 730E878 . N/A 32.5" RGB-PED N1-W812 3 1 N/A SAT R-069 0' DM-099 CM-009 L-009 MulB-NX12 1 N/A PRF-3 NRI AUG PRF-109 R-070 SR-038 VT-1 D-104 NIA 730E878 N/A 32.5" RGB-PED N1-W812 3 1 N/A SAT R-069 0' DM-099 CM-009 L-009 MUlB-NX12 1 WA PRF-3 NRI AUG PRF-11 R-070 SR-038 VT-1 D-100 N/A 730E878 N/A 32.5* RGB-PED N1-W812 3 1 N/A SAT R-069 0' DM-098 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-110 R-070 SR-038 VT-1 D-104 N/A 730E878 N/A 32.5" RGB-PED N1-W812 3 i N/A SAT R-069 O' DM-099 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI
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@ GE Nuclear Energy COOPER NUCLEAR STATION PAGE 3 of 12 AUGMENTED EXAM COMPONENT INDEX , REVISION No. O SPRING 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT, DRAWING LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET StZE CONF NUMBER NO. NPPD NO. COMMENTS AUG PRF-111 R470 SR-038 VT-1 0-104 N/A 730E878 N/A 32.5* RGB-PED IV1-W812 3 1 N/A SAT R-069 0' DM499 CM-009 L-009 MUIB-NX12 1 N/A PRF-3 NRt AUG PRF-112 R-070 SR-038 VT-1 D-104 N/A 730E878 N/A 32.5" RGB-PED N1-W812 3 i N/A SAT
- f. " O' DM-099 CM-009 L-009 MulB-NX12 1 N/A PRF-3 NRI AUG PRF-115 R-070 SR-038 VT-1 D-104 N/A 730E878 N/A 32.5" RGB-PED N1-W812 3 1 N/A SAT R-069 0' DM-099 CM409 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-116 R-070 SR-038 VT-1 D-104 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-069 0' DM-099 CM-009 L-009 MulB-NX12 1 N/A PRF-3 NRI AUG PRF-117 R470 SR-038 VT-1 D-105 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-069 0' DM-099 CM-009 L-009 MUtB-NX12 1 N/A PRF-3 NRI AUG PRF-118 R-070 SR-038 VT-1 D-105 N/A 730E878 N/A 32.5* RGB-PED N1-WB12 3 1 N/A SAT R-0G9 0" DM-099 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-119 R-070 SR-038 VT-1 D-105 N/A 730E878 N/A 32 5* RGB-PED IV1-W812 3 1 N!A SAT R-069 0' DM-099 CM409 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-12 R-070 SR-038 VT-1 D-100 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-069 0' DM-098 CM-009 L-009 MU'IB-NX12 1 N/A PRF-3 NRI AUG PRF-120 R-070 SR-038 VT-1 D-105 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-069 0' DM-099 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-13 R-070 SR-038 VT-1 0-100 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-069 0' DM-098 CM409 L-009 MUlB-NX12 1 N/A PRF-3 NRJ
;AUG PRF-14 R-070 SR-038 . VT-1 D-100 N/A 730E878 N/A 32.5" RGB-PED N1-WB12 3 1 N/A SAT R-069 0' DM-098 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-16 R470 SR-038 VT-1 D-100 N/A 730E878 N'A 32.5" RGB-PED N1-W812 3 1 N'A SAT R-069 0' DM-098 CM409 L-009 MUiB-NX12 1 N/A PRF-3 NRI AUG PRF-20 R-070 SR-038 VT-1 D-100 ' N/A 730EB78 N/A 32 5" RGB-PED N1-W812 3 1 N/A SAT
. R-069 0' DM-098 CM-009 L-009 MUIB-NX12 1 N/A PR'-3 NRI
GE Nuclear Energy COOPER NUCtJAR ST ADON PAGE 4 of 12 1 AUGMENTED EXAM COMPONENT INDEX REvtSION No. O SPRfNG 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM UATA CAL SHT. DRAWING LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SilE CONF. NUMBER NO. NPPD NO. COMMENTS AUG PRF-22 R-070 SR-038 VT-1 D-101 N/A 730E878 N/A . 32.5" RGB-PED N1-W812 3 1 N/A SAT R-069 0' DM-098 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRt AUG PRF-24 R-070 SR-038 VT-1 D-101 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-069 O' DM-098 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-27 R-070 SR-038 VT-1 D-101 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-069 0* DM498 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-28 R-070 SR-038 VT-1 D-101 N/A 730E878 N/A 32 5" RGB-PED IV1-W812 3 1 N!A SAT R-009 0' DM-098 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-3 R-070 SR-038 VT-1 D-100 N/A 730E878 N/A 32.5* RGB-PED IV1-WB12 3 1 N/A SAT R-069 0' DM-098 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-30 R-070 SR-038 VT-1 D-101 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 FCA SAT R-069 , O' DM-097 CM-009 L-009 MulB-NX12 1 N/A PRF-3 NRI AUG PRF-32 R-070 SR-038 VT-1 D-101 N/A 730E878 N/A 32.5" RGB-PED N1-W812 3 1 N/A SAT R-069 0' DM-097 C M-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-36 R-070 SR438 VT-1 D-101 F#A 730E878 FCA 32.5* RGB-PED N1-W812 3 1 N/A SAT R-009 0' DM-097 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI ' AUG PRF-38 R-070 SR-038 VT-1 D-101 N/A 730E878 N/A 32.5* RGB-PED N1-W812 3 1 PUA SAT R-069 0' DM-097 CM-009 L-009 MUlB-NX12 1 tvA PRF-3 NRI AUG PRF-4 R-070 SR-038 VT-1 D-100 N/A 730E878 N/A 32 5" RC P . PED IV1-WB12 3 1 N/A SAT R-069 0' DM-098 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI
- AUG PRF-40 R-070 SR-038 VT-1 D-101 N/A 730E878 N/A 32.5' RGB-PED IV1-W812 3 1 N/A SAT R-069 0' DM-097 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-44 R-070 SR-038 VT-1 D-101 N/A 730E878 N/A 32.5" RGB-PED N1-W812 3 1 N/A SAT R-069 0" DM-097 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-46 R-070 SR-038 VT-1 D-102 N/A 730E878 N/A 32.5" RGB-PED N1-W812 3 1 N/A SAT R-069 0' DM-097 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-48 R-070 SR-038 VT-1 D-102 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-009 0' DM-097 CM-009 L-009 MUiB-NX12 1 tea PRF-3 NRI AUG PRF-51 R-070 SR-038 VT-1 D-1C2 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-069 0' DM-097 CM-009 L-009 MulB-NX12 1 N/A PRF-3 NRI AUG PRF-53 R-070 SR-038 V7-1 D-102 N/A 730E878 N/A 32.5" RGB-PED N1-W812 3 1 N/A SAT R-009 0' DM-097 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-55 R-070 SR-038 VT-1 D-102 PUA 730E878- N/A 32.5" RGB-PED IV1-W812 3 1 t#A SAT R-069 ~ O' DM-097 CM-009 L-009 MulB-NX12 1 t#A l PRF-3 NR!
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O GE Nuclear Energy i COOPER NUCLEAR ST ATION . PAGE 5 of 12 AUGMENTED EXAM COMPONENT INDEX REYlSION No.C - SPRtNG 1993 5 l FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARITY PROC. REV. NO. STD. j CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETR!C SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS AUG PRF-59 R-070 SR-038 VT-1 D-102 N/A 730E878 N'A 32 5' RGB-PED N1-W812 3 1 N/A SAT R-069 0' DM-097 CM-009 L-009 MU!B-NX12 1 N/A PRF-3 NRI ! AUG PRF-6 R-070 SR438 VT-1 D 100 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-069 0' DM-098 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI ! AUG PRF-62 R-070 SR-038 VT-1 D-102 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-069 0' DM-097 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-CA R-070 SR-038 VT-1 D-102 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-069 0' DM-097 CM-009 L-009 MUlB-NX12 1 N'A PRF-3 NRI AUG PRF-67 R-070 SR-038 VT-1 D-102 N/A 730E878 N/A 32.5" RGB-PED !V1-W812 3 1 N/A SAI R-069 0' DM-096 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-70 R-070 SR-038 VT-1 0-102 N/A 730E378 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-069 0* DM-096 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-76 R-070 SR-038 VT-1 - D-103 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-069 0' DM-096 CM-009 L-009 MulB-NX12 1 N 'A PRF-3 NRI , AUG PRF-78 R-070 SR-038 VT-1 D-103 N/A 730EB78 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-069 0' DM-096 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI l AUG PRF-8 R-070 SR-038 VT-1 D-100 - -N/A 730E8T8 N/A 32.5* RGB-PED IV1-W812 3 1 N/A SAT R-069 0' DM-098 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-80 R-070 SR-038 VT-1 D-103 N!A 730E878 N/A 32.5* RGB-PED IV1-WB12 3 1 N/A SAT R-069 0' DM-096 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-84 R-070 SR-038 VT-1 D-103 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT d-069 0' DM-096 CM-009 L-009 MUtB-NX12 1 N/A PRF-3 NRI ! AUG PRF-86 R-070 SR-038 VT-1 D-103 N/A 730E878 N/A 32.5* RGB-PED IV1-W812 3 1 N/A SAT R-069 0' DM-096 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-88 R-070 SR-038 VT-1 0-103 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-069 0' DM-096 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-92 R-070 SR-038 VT-1 .D-103 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 NIA - SAT R-069 0' DM-096 C M-009 ' L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-B4 R-070 SR-CG8 VT-1 D-103 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-069 0" DM-096 CM-009 L-009 MUlB-NX12 1 N/A - PRF-3 NRI AUG PRF-96 R-070 SR-038 VT-1 D-103 ~ N/A 730E878 N/A 32.5* RGB-PED IV1-W812 3 1. N/A SAT R-069 0' . DM-096 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI AUG PRF-99 R-070 SR-038 VT-1 D-103 N/A 730E878 N/A 32.5" RGB-PED IV1-W812 3 1 N/A SAT R-069 0* DM-096 CM-009 L-009 MUlB-NX12 1 N/A PRF-3 NRI
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GE Nuclear Energy COOPER NUCLEAR STATON PAGE 6 o' 12 AUGMENTED EXAM COMPONENT INDEX REVISION No.O SPANG 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS AUG PRG-11 R-071 SR-038 VT-1 D-106 N/A 733E878 N/A 11* RGB-PED IV14V812 3 1 N/A SAT R-067 0' DM-094 CM-008 L409 MulB-NX12 1 N/A PRG-3 NRI AUG PRG-14 R-071 SR-038 VT-1 0-106 N/A 730E878 N/A it' RGB-PED IV1-W812 3 1 N'A SAT R-067 0' DM-094 CM-008 L-009 MUlB-NX12 1 N/A PRG-3 NRI AUG PRG-16 R-071 SR438 VT-1 0-106 N/A 730E878 N/A 11" RGB-PED IV14V812 3 1 N/A SAT R-067 0' DM-094 CM-008 L-009 MUlB-NX12 1 N/A PRG-3 NRI AUG PRG-19 R-071 SR-038 VT-1 0-106 N/A 730E878 N/A 11* RGB-PED N1-W812 3 1 N/A SAT R-067 0' DM-094 CM-008 L-009 MUlB-NX12 1 N/A PRG-3 NRI AUG PRG-22 R-071 SR-038 VT-1 D-106 N/A 730E878 N/A 11" RGB-PED IV1-W812 3 1 N/A' SAT R-067 0' DM-094 CM-008 L-009 MUlB-NX12 1 NA PRG-3 NRI AUG PRG-24 R-071 SR-038 VT-1 D-106 N 'A 730E878 N/A 11' RGB-PED N1-W812 3 1 N/A SAT R-067 0' DM-OQ4 CM-006 L-009 MUlB-NX12 1 N/A PRG-3 NRI AUG PRG-27 R-071 SR-038 VT-1 D-10G MA 730E878 N/A 11" RGB-PED N1-W812 3 1 N/A SAT R-067 0' DM-094 CM-006 L-009 MUlB-NX12 1 N/A PRG-3 NRI AUG PRG-3 R-071 SR-038 VT-1 D-106 N/A 730E878 N/A 11* RGB-PED N1-W812 3 1 N/A SAT R-067 0' DM-094 CM-008 L-009 MUiB-NX12 1 N/A PRG-3 NRI AUG PRG-30 R-071 SR-038 VT-1 0-107 N/A 730E878 N/A 11* RGB-PED IV1-W812 3 1 N/A SAT R467 0* DM-094 CM-008 L-009 MulB-NX12 1 N/A PRG-3 NRI AUG PRG-32 R-071 SR438 VT-1 D-107 N/A 730E878 N/A 11" RGB-PED N1-WB12 3 1 N/A SAT R-067 0' DM-094 CM-008 L-009 MUlB-NX12 1 N/A PRG-3 NRI AUG PRG-35 R-071 SR-038 VT-1 D-107 N/A 730E878 N/A 11* RGB-PED IV1-W812 3 1 N/A SAT R-067 0' DM-094 CM-008 L-009 MU!B-NX12 1 N/A PRG-3 NRI AUG PRG-39 R-071 SR-038 VT-1 D-107 N/A 730E878 N/A 11' RGB-PED IV1-WB12 3 1 NA SAT R-067 0' DM-094 CM-008 L-009 MulB-NX12 1 N/A PRG-3 NRI AUG PRG-42 R-071 SR438 VT-1 D-107 N/A 730E878 N/A 11* RGB-PED IV1-W812 3 1 N/A SAT R-067 0' DM-095 C M-008 L-009 MUlB-NX12 1 N!A PRG-3 NRI AUG PRG-44 R-071 SR438 VT-1 D-107 N/A 730E878 N/A 11" RGB-PED IV1-W812 3 1 WA SAT R-067 0" DM495 CM-008 L-009 MUiB-NX12 1 N/A PRG-3 NRI AUG PRG-47 R-071 SR-038 VT-1 0-107 N/A 730E878 N/A 11* RGB PED IV1-W812 3 1 N/A SAT R 067 0* DM-095 CM-008 L-009 MulB-NX12 1 N/A PRG-3 NRI AUG PRG-50 R-071 SR-038 VT-1 D-107 N/A 730E878 N/A 11' RGB-PED N1-W812 3 1 N/A SAT R-067 0' DM495 CM-008 L-009 MUlB-NX12 1 NA PRG-3 NRl AUG PRG-52 R-071 SR-038 VT-1 D-107 N/A 730E878 N/A it' RGB-PED N1-W812 3 1 N/A SAT R-067 0' DM-095 CM-008 L-009 MulB-NX12 1 N'A PRG-3 NRI
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i COO 8TR NOCLEAR STATION PAGE 7 of 12 4 AUGMENTED EX AM COMPONENT INDEX REVISION. No. O SPRING 1993 FRR CAL. ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARITY PROC. REV. NO. STD. I l CAT. NUMBER REPORT RECORD TYPE SHEET RECOPD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS l ! AUG PRG-54 R-071 SR-038 VT-1 D-107 N/A 730E878 N/A 11" RGB-PED IV1-W812 3 1 N/A SAT ! R467 0' DM-095 CM-008 L-000 MUlB-NX12 1 N/A PRG-3 NRI , i AUG PRG-55 R 471 SR-038 VT-1 D-108 N/A 730E878 N/A 11" RGB-PED IV1-W812 3 i N/A SAT R-067 0* DM-095 CM-008 L-009 MUlB-NX12 1 N/A PRG-3 NRI i AUG PRG-58 Ro71 SR-038 VT-1 D-108 N!A 730E878 N/A 11" RGB-PE D IV14v812 3 1 N/A SAT R-067 0' DM-095 CM-008 L-009 MulB-NX12 1 N/A PRG-3 NRI AUG PRG-59 R-071 SR-038 VT-1 D-108 N/A 730E878 N/A 11" RGB-PED IV1-W812 3 1 N/A SAT R467 0' DM-095 CM-008 L-009 MUiB-NX12 1 N/A PRG-3 NRI AUG PRG-6 R-071 SR-038 VT-1 D-106 N/A 730E878 N/A 11" RGB-PED IV1-W812 3 i N/A SAT R-067 0' DM-094 CM408 L-009 MulB-NX12 1 N/A PRG-3 NRI AUG PRG-60 R-071 SR-038 VT-1 D-108 N/A 730E878 N/A 11" RGB-PED IV1-W812 3 1 N/A SAT R-067 0' DM-095 CM-008 L-009 MulB-NX12 1 N/A PRG-3 NRI l AUG PRG-8 R-071 SR-038 VT-1 D-106 N/A 730E878 N!A 11" RGB-PED IV1-W812 3 1 N/A SAT R-067 0' DM-094 CM-000 L-009 MIJIB-NX12 1 N/A PRG-3 NRI AUG RAD-BF-7 R-171 SR-0G2 PT D-215 N/A CNS-RR-37 N/A 24" P-P GE-PT-100 0 91-27 N/A NRI 0' DM-216 CM-018 L-009 GE-UT-106 1 91-08.-37 106 NRI 45'S DM-217 CM-017 L-009 GE-UT-106 1 91-08.-37 106 NRI , 45'S DM-218 CM-015 L-009 GE-UT-102 2 91-05 55 NRI 1 45'RL DM-219 CM-016 L-009 GE-UT-102 2 91-05 55 NRI FOR GL88-01 AND ASME SECTION XI CREDIT AUG RCA-BF-1 R-211 SR-098 PT D-303 N/A CE232-241 N/A 5" N-CAP GE-PT-100 0 91-27 N/A NRI 45'S DM-304 CM-040 L-004 GE-U T-105 2 91-07 20 INSIDE SURFACE AND ROOT GEOMETRY 45'RL DM-305 CM-041 L-004 GE-UT-105 2 91-07 20 10 ROOT GEOMETRY 60'RL DM-306 CM-042 L-004 GE-UT-105 2 91-07 20 ID SURFACE GEOMETRY & FOR GL88-01 AND ASME t SECTION XI CREDIT AUG RCC-H-111 R-124 N/A VT-3 D-160 N/A 2848-6 N/A N/A SUPPORi GE-VT-100 0 91-29,-36 N/A SAT AUG RCC-H-144 R-122 N/A VT-3 D-158 N/A '2848-8 N/A N/A BRACE GE-VT-100 0 91-29.-36 N/A SAT ! AUG RCC-H-164 R-215 N/A VT-3 D-289 N/A 2848-1 N/A N/A HANGER GE-VT-100 0 91-29,-36 N/A SAT VT-4 IV4-W812 2 91-31,-34 AUG RCC-H-LEF R-091 N/A VT-3 D-127 N/A X2848-220 N/A N/A BRACE GE-VT-100 0 91-29,-36 N/A SAT AUG RCC-H-LEFT R-087 N/A VT-3 D-123 N/A X2848-220 N/A ' N/A BRACE GE-VT-100 0 91-29,-36 N/A SAT AUG RCC-H-RIGHT R-088 N/A VT-3 D-124 N/A X2848-220 N/A N/A BRACE- GE-VT-100 0 91-29,-36 N/A SAT AUG RCC-S-26 R-124 N/A VT-3 D-160 N1A 2848-6 N/A N/A STRUT GE-VT-100 0 91-29,-36 N/A SAT e_ . _ _ _ _ _ _ . _ - . _ _ _ _ _ - - _ _ - _ _ _ - - _ - - . . _ _ - - _ _ . _ _ _ - - _ . _ _ _ _ - _ _ _ _ _ - _ _ _ _ - _ _ _ - _ _ _ _ _ _ - . . _ _ _ _ _ - ____ -- - _ _ - _ _ _ - -. ._~- _ _ _ . - - _ - - _ _ _ _ - _ - -
i COOPER NUCLEAR STATION PAGE 8 of 12 AUGMENTED EXAM COMPONE NT INDEX REYtSION No. O ! SPRING 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL. SHT. DRAWING LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS I AUG RFH-63A R-238 N/A VT-3 D-356 N/A 2509-2 N/A N/A VARI. GE-VT-100 0 91-29,-36 N/A SAT VT-4 SUPPORT IV4 W812 2 91-31,-34 EXAMINED DUE TO FALSE SAMPLE EX-PANSION FOR MSH-133 AUG RFH-70A R-241 N/A VT-3 D-359 N!A 2509-1 N/A N/A CONSTNT GE-VT-100 0 91-29.-36 N'A SAT
- VT-4 SUPPORT IV4-W812 2 91-31,-34 EXAMINED DUE TO FALSE SAMPLE EXPANSION FOR j MSH-133 AUG RFH-71 R-239 N/A VT-3 0-357 N/A 2509-1 N/A N/A CONSTNT GE-VT-100 0 91-29.-36 N/A UNSAT, REF.
VT-4 SUPPORT IV4-W812 2 91-31 -34 MWR 93-2435 EXAMINED DUE TO FALSE SAMPLE EXPANSION FOR MSH-133 AUG RFH-71A R-240 N/A VT-3 D-358 N/A 2509-1 N/A N/A CONSTNT GE-VT-100 0 91-29.-36 N/A SAT VT-4 SUPPORT IV4-W812 2 91-31,-34 EXAMINED DUE TO FALSE SAMPLE EXPANSION FOR MSH-133 AUG RH B-CF-3 R-187 SR478 MT D-251 N/A - 2624-1 N/A 16' P-E GE-M T-100 0 91-25 N/A NRI. EXAM LIMITED TO 66% COVERAGE. NOT COUNTED FOR SECTION XI CODE CREDIT AUG RHH-121 R-115 N/A VT-3 D-151 N/A 2510-4 N/A N/A N/A GE-VT-100 0 91-29.-36 N/A UNSAT, REF. VT-4 IV4-W812 2 91-31,-34 MWR 93-2395 R-310 VT-4 D-487 IV4-W812 2 91-31 -34 UNSAT, REF. INVAUD EXAM; NOT FOR SECTION XI CODE CREDIT. SUPPORT NOT PROPERLY SET DURING DESIGN CHANGE. AUG RHR-CV-26CV R-164 N/A VT-1 D-204 N/A 2510-4 - N/A N/A BOLT fV1-W812 3 1 N/A SAT; lNCLUDES CANOPY; BOLTING NOT-PRESSURE RETA!NING CAT. B-G-2 AUG RHR-CV-27CV R-163 - N/A VT-1 0-203 N/A 2510 N/A N/A BOLT ' IV1-W812 3 1 N/A SAT; INCLUDES CANOPY; BOLTING NOT PRESSURE RETAINING CAT. B-G-2 u _ _ _ ___ _ _ . a _ _ -- _ _ _ _ ---- - ~ - ._ .-~.;--.-- - -- _
@ GE Nuclear Energy COOPER NUCLEAR STATION PAGE 9 of 12 AUGMENTED EXAM COMPONENT INDEx REVISPON No. O SPRING 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAWING LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS AUG RRF-DF-1 R-244 SR-136 PT D-368 N/A CNSRR37 N/A 14' SE-NOZ GE-PT-100 0 91-27 N/A NRI 45'S DA-013 CA-012 L-021 GE-UT-209 1 93-03 52 ID ROOT GEOMETRY 45'RL DA-014 CA-013 L-021 GE-UT-209 1 93-03 121 ACOUSTIC INTERFACE & 60 SPOT LACK OF FUSION 60'RL DA-015 CA-014 L-021 GE-UT-209 1 93-03 121 NRI FOR GL88-01 AND ASME SECTION XI CREDIT AUG RRG-BF-1 R-245 SR-135 PT D-369 N/A CNSRR37 N/A 14' SE-NOZ GE-PT-100 0 91-27 N/A NRI - 45'S DA-010 CA-009 L-021 GE-UT-209 1 93-03 52/60 1D ROOT GEOMETRY 45'RL DA-011 CA-010 L-021 GE-UT-209 1 93-03 121 ACOUSTIC INTERFACE 60'RL DA-012 CA-011 L-021 GE-UT-209 1 93-03 121 SPOT LACK OF FUSION FOR GL88-01 AND ASME SECTION XI CREDIT AUG RWCU-28 R-035 SR-019 45'RL DM-035 CM-001 2005-1 L-008 4" P-E GE-UT-102 2 91-05 10 NRl; GL88-01 AUG RWCU-29 R-035 SR-019 45'S DM436 CM-001 2605-1 L-008 4* E-P GE-UT-102 2 91-05 10 NRl; GL88-01 AUG RWCU-29A R-035 SR-019 00'R DM-037 CM-001 2605-1 L-008 4" P-T GE-UT-102 2 91-05 10 NRl; GL88-01 AUG RWCU-30 R-035 SR-019 45'S DM-038 CM-001 2005-1 L-008 4" T-P GE-UT-102 2 91-05 10 NRl; GL88-01 AUG RWCU-31 R-035 SR-019 45'S DM-039 CM-001 2005-1 L-008 4* P-E GE-UT-102 2 91-05 10 NRl; GL88-01 AUG RWCU-32 R-035 SR-019 45'S DM-040 CM-001 2005-1 L-008 4* E-P GE-UT-102 2 91-05 10 NRl; GL88-01 AUG RWCU-33 R-036 SR-020 45 S DM-041 CM-002 2605-1 L-008 4" P-E GE-UT-102 2 91-05 10 NRI, GL88-01 AUG RWCU-34 R436 SR-020 45'S DM-042 CM-002 2005-1 L-008 4" E-P GE-UT-102 2 91-05 10 NRl; GL88-01 AUG RWCU-35 R-036 SRO20 45'S DM-043 CM-002 2005-1 L-008 4" P-E GE-UT-102 2 91-05 10 NRl; GL88-01 AUG RWCU-36 R-036 SR-020 45'S DM-044 CM-002 2605-1 L-008 4* E-P GE-U T-102 2 91-05 10 NRl; GL88-01 AUG RWCU-37 R-036 SR-020 45'S DM-045 CM402 2005-1 L-008 4* P-E GE-UT-102 2 91-05 10 NRl; GL88-01 AUG RWCU-38 R-036 SR-020 45'S DM-046 CM-002 2005-1 L-008 4' E-P GE-0T-102 2 91-05 10 ' NRl; GL88-01 AUG RWCU-63 R-213 SR-094 45'S DM-287 CM432 2005-2 L409 4- R-T GE-UT-102 2 91-05 110 NRl; GLB8-01 AUG RWCU-76 R-212 SR-093 45'S DM-2% CM-032 2005-2A L-009 4' P-N GE-UT-102 2 91-05 110 NRl; GL88-01 AUG RWCU-96 R-287 S.R-140 45'S DM-469 CM-082 2013-1 L-004 4' P-V GE-UT-102 2 91-05 18 PSl; NRl; GL8801 t
. . _ _ - _._ _ -_ -_ _- - _ _ - _ ____ - _-_ __-___-__-_2____- -
O GE Nuclear Energy COOPER NUCL. EAR ST ATION .PAGE 10 of 12 AUGMENTED EKAM COMPONENT INDEX REVISION No. 0 SPRING 1993 FRR CAL ASME COMPONENT l
SUMMARY
EXAM DATA CAL. SHT. DRAWING LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS AUG SHROUD HEAD R-307 N'A 0' DM-489 CM484 BN-18-1 L-020 N/A BOLTS GE-UT-501 0 91-22 120 NRI BOLTS NOS 2.25 NRI 1,4.5,6,7,8.9.12.13, MHz NRI 14.15.1S,17, NRI 18,19,20.21.22 NRI - 23.24.26,29.30, NRI 32,36, NRI 17,19 0' DM-489 CM-085 L-020 GE-UT-501 0 91-22 120 NRI 1 MHz AUG SIL 420 R-302 N/A VT-1 VTD-15 N/A N/A N/A N'A VES. INT, VT-06 0 93-05 N/A NRI VTD-20 VT-06 0 93-05 NRI VTD-25 VT.06 0 93-05 NRI VTD-30 VT-06 0 93-05 NRI VTD-35 VT-06 0 93-05 NRI VTD-40 VT-06 0 93-05 NRI VTD-45 VT-06 0 93-05 NRI VTD-50 VT-06 0 93-05 NRI VTD-55 VT-0G 0 93-05 NRI VTD-60 VT-06 0 93-05 NRI AUG SIL 462 R-302 N/A VT-1 VTD-01 N/A N/A N!A N/A AHC VT-06 0 93-05 N/A NRI0" COVER R-303 SR-303 45'S DA-002 CA-001 L-021 AHC GE-UT-211 3 N/A 117 NR1 45*S DA-003 CA-003 L-021 AHC GE-UT-211 3 N/A - 118 NRf 45'S DA-004 CA402 L-021 AHC GE-UT-211 3 N/A 118 NRI 60* RL DA-005 CA-004 L-021 AHC GE-UT-211 3 NA 117 NRI 45'S DA-006 CA408 L-021 AHC GE-UT-211 3 N/A 117 NRI GO'RL DA-007 CA-007 L-021 AHC GE-UT-211 3 N/A 117 NRI 60'RL DA-008 CA-005 L-021 AHC GE-UT-211 3 N/A 118 NRJ 60'RL DA-009 CA-006 L-021 AHC GE-UT-211 3 N/A 118 NRI VT-1 VTD-03 N/A N/A AHC VT-06 0 9}O5 N/A NRI 180' COVER R-304 SR-304 45'S DA-020 CAOO1 L-021 AHC GE-UT-211 3 N/A 117 NRI 45'S DA-021 CA-003 L-021 AHC GE-UT-211 3 N/A 118 NRI 45'S DA-022 CA-002 L-021 AHC GE-UT-211 3- N/A 118 NRI 60'RL DA-023 CA-007 L-021 AHC GE-UT-211 - 3- N/A 117 NRI 60'RL DA-024 CA-004 L-021 AHC GE-UT-211 3 N/A 117 NRI 60'R.L DA-025 CA-005 L-021 AHC GE-UT-211 3 N/A 118 NRI 60'RL DA-026 CA-006 ~ L-021 AHC GE-UT-211 3 N!A 118 NRI ~ _ _______.-_-_:._=_---_______.--________--___.___.______________-______...__._-
GE Nuclear Energy COOPER NUCLEAR STATION PAGE 11 of 12 AUGUENTED EXAM COMPONENT !NDEM REVISrON No. O . SPRING 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL. SHT. DRAWING LINEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMENTS AUG SIL 465 R-302 N/A VT-1 VTD-14 N/A N/A NTA N/A VESINT. VT-06 0 93-05 N/A NRI VTD-19 VT-06 0 93-05 NRI VTD-24 VT-06 0 93-05 NRI VTD-29 VT-06 0 93-05 NR1 VTD-34 VT-06 0 93-05 NRI VTD-39 VT-06 0 93-05 NRI VTD-44 VT-06 0 93-05 NRf VTD-49 VT-06 0 93-05 NRI VTD-54 VT-0G 0 93-05 NRI VTD-59 VT-06 0 9345 NRI AUG SIL 289 R-302 N/A VT-1 VTD-Of N/A N/A N/A N/A VES. INT. VT-06 0 93-05 N/A NRI VTD-10 VT-06 0 93 05 NRt AUG SIL 474 R-302 N/A VT-1 VTD-106 N/A N/A N/A N/A VES. INT. VT-06 0 93-05 N/A NR! AUG STEAM R-302 N/A VT-1 VTD-108 N/A N/A N/A N/A VES. INT. VT-06 0 93-05 N/A NRI SEPARATOR AUG SW-H-214 R-079 N!A VT-3 D-115 N/A SW-H214 N'A N/A HANGER GE-VT-100 0 91-29,-36 N/A SAT VT-4 IV4-W812 2 91-31 -34 AUG SW-H-223 RC78 N/A VT-3 D-114 N/A SW-H223 N/A N/A LUG GE-VT-100 0 91-29.-36 N/A SAT AUG SW-H-3 R-089 N/A VT-3 D-125 N!A 2852-1 N/A N/A LUG GE-VT-100 0 91-29.-36 N/A SAT AUG SW-H-4 R-090 N/A VT-3 D-126 N/A 2852-1 N/A N/A LUG GE-VT-100 0 91-29,-36 N/A SAT AUG SW-H-46 R-103 NIA VT-3 D-139 N/A 2851-6 N/A N/A BRACE GE-VT-100 0 91-29.-36 N/A SAT AUG- SW-S-178A R 442 N/A VT-3 D-052 N/A 2851-1 N/A N/A STRUT GE-VT-100 0 91-29 -36 N/A SAT AUG SW-S-33A R-192 N/A VT-3 D-256 N/A 2851-5 N 'A N/A STRUT GE-VT-100 0 91-29.-36 N/A SAT AUG SW-S-51A N/A N/A VT-3 N/A N/A SKE-SW277 N/A N/A SUPPORT 7.2.57 4 N/A N/A SAT, REF VT-4 N/A 7.2.57 4 N/A MWR 91-1294 EXAMINED BY CNS AUG SW-S-69 R-103 N/A VT-3 D-139 N/A 2852-19 N/A N/A RESTRNT GE-VT-100 0 91-29,-36 N/A SAT AUG VRH-45A R-279 N/A VT-3 D-459 N/A 2628-2 N/A N/A VARL GE-VT-100 0 91-29.-36 N/A UNSAT. REFERENCE VT-4 SUPPORT IV4-W812 2 91-31,-34 NCR 93-119 EXAMINED DUE TO FALSE SAMPLE EXPANSION FOR VRH-52. ~ . - . .- _ . ~ _ _ _ . ._ . _ - . _ . . . _ . - , . .. . . - - . - ~ _- . , . - . - . , _ . . . . . . . . . . , . . . . . - - . - , , . - - . .
@ GE Nuclear Energy COOPER NUCLEAR STATlON PAGE 12 et 12 AUGMENTED EXAM COMPONENT INDEX REVPSION No. C.
SPRING 1993 FRR CAL ASME COMPONENT
SUMMARY
EXAM DATA CAL SHT. DRAVANG UNEARITY PROC. REV. NO. STD. CAT. NUMBER REPORT RECORD TYPE SHEET RECORD ISOMETRIC SHEET SIZE CONF. NUMBER NO. NPPD NO. COMMEN TS AUG VRH-48 R-276 N/A VT-3 D456 N/A 2628-2 N/A N/A VARI. GE-UT-100 0 91-29,-36 N/A SAT VT-4 SUPPORT IV4-W812 2 91-31,-34 SAT-R-288 VT-4 D-470 IV4-W812 2 91-31,-34 SAT EXAMINED DUE TO FALSE SAMPLE EXPANSION FOR VRH-52 AUG VRH-52 R-139 N/A VT-3 D-175 N/A 2628-1 N/A N/A VARI. GE-VT-100 0 91-29.-36 N/A INVAllD EXAM - SUPPORT ADJACENT VALVE R-293 VT-4 D-475 IV4-W812 2 91-31,-34 REMOVED FROM SYSTEM UNSAT UNSAT SEE MWR 93-1372 AUG VRH R-280 N/A VT-3 D-460 N/A 2628-5 N/A N/A VARI. GE-VT-100 0 91-29,-36 N/A UNSAT, REFERENCE VT-4 SUPPORT IV4-W812 2 91-31.-34 NCR 93-111 EXAMINED DUE TO FALSE SAMPLE EXPANSION FOR VRH-43 AUG VRH-57 R-281 - N/A VT-3 D-461 N/A 2628 4 N/A N/A VARI. GE-VT-100 0 91-29,-36 N/A UNSAT, REFERENCE VT-4 SUPPORT IV4-W812 2 91-31,-34 NCR 93-118 EXAMINED DUE TO FALSE SAMPLE EXPANSION FOR VRH-48 AUG VRH-61 R-282 N/A VT-3 D-462 N/A 2628-3 N/A N/A VARI. GE-VT-100 0 91-29,-36 N/A SAT VT-4 SUPPORT IV4-W812 2 91-31,-34 EXAMINED DUE TO FALSE SAMPLE EXPANSION FOR VRH-48 AUG VRH-63 R-283 N/A VT-3 D-463 N/A 2628-4 N/A N!A VARL GE-VT-100 0 91-29 -36 N/A SAT VT-4 SUPPORT IV4-W812 2 91-31,-34 SAT R-292 VT-4 D-474 IV4-W812 2 91-31 -34 SAT EXAMINED DUE TO FALSE EXPANSION FOR VRH-48 L-
e
)
ENCLOSURE 2
- to Nebraska Public Power District Letter CNSS937262 i
i OWNER'S REPORT FOR REPAIRS AND REPLACEMENTS FORM NIS-2 Cooper Nuclear Station , NRC Docket No. 50-298, DPR-46 i i a i l N
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI i
~1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet ___. ___ o f 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: __
One (Name) P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: H/6 Same Authorization Date: N/A (Address) N/A Expiration Date:
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Work Repaired' ASME Code Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Replacement Number (Yes or No)
RHR-V-462 Velan 2 93-2260 Replaced No
- 7. Description of Work: Replaced valve.
- 8. Tests Conducted: Hydrostatic X Pneumatic Nominal Operating Pressure Other Pressure 565 psi Test Temp. Ambient'*P NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) Information in items 1 through 6 on this report is included on each. sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
- c. J
7-e
~9. Remarks: Code case N-308. " Documentation of Repairs and Replacements of Components in Nucicar Power Plants" is invoked through the us'e of Form NIS-2 for reportine.
(Applicable Manufacturer's Data heports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI, ! (repair or replacement) f Type Code Symbol Stamp: N/A Certification of Authorization No, N/A Expiration Date: N/A Signed: g( -
//4 V/ m . L ec .
7 Ennineerinz Manager Date: 10-12-93
// "(Owner p\ owner's Designee, Title) l f
CERTIFICATE OF INSERVICE INSPECTION -
.i I, the undersigned, holding a valid commission issued by the National Board of l Boiler and Pressure Vessel Inspectors and the State or Province of Nebraska and employed by. Hartford Steam Boiler I & I Company of Hartford. CT__ have-inspected the components described in this Owner's Report during the period . ,
January 1. 1992 to Aucust 31. 1993 , and state that to'the best of my knowledge. and belief, the Owner has performed examinations and taken corrective measures i described in this Owner's 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 measured described in this Owner's 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. , Inspector's Signature: ' ' /. aI ad 1 Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: /O- l'/ - f s 1 I l 4 l i 1
t FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 2 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: 826 Same Authorization Date: N/A (Address) N/A Expiration Date:
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) App icable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear
# *P" #* ^"
- Document Replaced, or Stamped Component Manufacturer Class Replacement Number (Yes or No)
RH-H58 N/A 2 93-2260 Repaired No l 1 l l l
- 7. Description of Work: Removed RH-H58 from the system.
l
- 8. Tests Conducted: Hydrostatic Pneumatic -
Nominal Operating Pressure l Other N/A Pressure psi Test Temp. "F. -NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
7 t 1 1
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throuth the use of Form NIS-2 for reportinn. l (Applicable Manufacturer's Data Reports to be Attached) i CERTIFICATE OF COMPLIANCE i Ue certify that the statements made in the report are correct and this repair conforms to the rules of the ASME Code, Section XI.
(repair or replacement) Type Code Symbol Stamp: N/A Certificacion of Authoriza ion No. N/A Expiration Date: N/A ngt I I .- Signed: Vile _- e t/- Engineerinn Mananer Date: 10-12-93
// (Owner r Owner's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I company of Hartford. CT have inspected the components described in this Owner's Report during the period January 1. 1992 to Aunust 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this Owner's 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. A Inspector's Signature: /2 u! t./ #- > _ Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements). Date: An - / V- f 3 L-
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI i
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name) ;
P.O. Box 499. Columbus. NE 68601 Sheet 3 of 89 (Address)
- 2. Plant: ____
Cooper Nuclear Station Unit: One (Name)
- P.O. Box 98. Brownville. NE 68321 N/A l (Address) (Repair Orgainzation, P.O.
No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: E/6 Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Main Steam (MS)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear rk Repaired ASME Code Document Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No)
MS-V-106 Dresser Ind. 1 92-0884 Replaced No j MS-V-107 Dresser Ind. 1 92-0884 Replaced No ! 0 0 N/A 1 92-0884 Replaced No M.9 I
- 7. Description of Work: Replaced both valves and piping between valves, t
- 8. Tests Conducted: Hydrostatic X Pneumatic
- Nominal Operating Pressure !
Other Pressure 1110 psi Test Temp. 72 *F e t NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this j report is included on each sheet, and (3) each sheet is numbered and the number of l sheets is recorded at the top of this form. I
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c
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked through the use of Form NIS-2 for reportinn.
(Applicabic Manufacturer's Data Reports to be Attached) i CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A CertificationofAuthoripationNo. N/A Expiration Date: N/A Signed: , a s Engineering Mananer Date: 10-12-93 9 "(Owner Owner's Designee, Title) CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford, CT have inspected the components described in this owner's Report during the period , January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this owner's 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 measured described in this Owner's 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, t-Inspector's Signature: -4 wtV Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: /d - N-f.T l l
l FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section II !
- 1. Owner: Nebraska Public Power District Date: October 5.1993 (Name) l P.O. Box 499 Columbus. NE 68601 Sheet 4 of 89 l (Address)
- 2. Plant: Cooper Nuclear Station Unit: One I (Name) l
___P.O. Box 98. Brownville. NE 68321 N/A ? (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A ;
(Address) Expiration Date: N/A
- 4. Identification of System: Main Steam (MS)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N71 Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear
# *E" # ^"
- Class Document Replaced, or Stamped Component Manufacturer Number Replacement (Yes or No)
MS-H242 N/A 2 93-0419 Replacement No MS-H261 N/A 2 93-0419 Replacement No MS-H241 N/A 2 93-0419 Replacement No
- 7. Description of Work: Installed new supports.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other N/A Pressure psi Test Temp. 'F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
1 J
r
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power plants" is invoked through the use of Form NIS-2 for reportine.
(Applicable Manufacturer's Data Reports to be Attached) i CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this
- t replacement conforms to the rules of the ASME Code, Section XI.
(repair or replacement) Type Code Symbol Stamp: N/A Certification of A.thorization No. N/A Expiration Date: N/A Signed: 3o ' Ennineering Manager Date: 10-12-93 *
// (Owne(orOwner'sDesignee, Title)
+
CERTIFICATE OF INS.",RVICE INSPECTION I, the undersigned, holding a valid commi sion issued by the National Board of -> Boiler and Pressure Vessel Inspectors and the State or Province of Nebraska and '
^
employed by Hartford Steam Boiler I & I Company __ of Hartford. CT have inspected the components described in this Owner's Report during the period : January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this owner's 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. Inspector's Signature: Y a. d w/d Commissions: NB #10352. Nebraska. N. I (National Board, State. Province, and Endorsements) Date: }() - / tl- 91 i
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FORM.NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As. Required by the Provisions of the ASME Code Section XI ,
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet- 5 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit One '
(Name) P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgain=ation, P.0. No . , J ob No . , Etc.)-
- 3. Work Performed By: Owner Type Code Symbol Stamp: EZ6 Same Authorization Date: N/A (Address) Expiration Date: N/A
- 4. Identification of System: Main Steam (MS)
- 5. (a) Applicable Construction Code: ASME Section III 19 68 Edition, Summer 1970 Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980,1 :er 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components ,
W rk Repaired ASME Code Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Replacement Number (Yes or No) MS-RV-71ARV (1) Target Rock 1 92-2738 Replacement No MS-RV-71FRV (2) Target Rock 1 92-2743 Replacement No-MS-RV-71GRV (3) Target Rock 1 92-2744 Replacement No MS-RV-71HRV (4) Target Rock 1 92-2745 Replacement No MS-RV-71CRV (3) Target Rock 1 92-2740 Replacement No 6
- 7. Description of Work: (1) Replaced one nut. (2) Replaced two studs and four nuts.
(3) Replaced one stud. (4) Replaced three studs.
- 8. Tests Conducted: Hydrostatic Pneumatic ,
Nominal Operating Pressure X Other Pressure 1020 psi Test Temp. Ambient *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets in recorded at the top of this form.
1 1 l l l F I L
- 9. . Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throunh the use of Form NIS-2 for ,
i reportinn. (Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE , We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authorization No. N/A Expiration Date: N/A Signed: . A / Engineerina Menazer Date: 10-12-93
/ (Owner ( r Owner's Designee, Title)
CERTIFICATE OF INSERVICE INSPECTION i I, the undersigned, holding a valid commission issued by the National. Board of Boiler and Pressure Vessel Inspectors and the State or Province of Nebraska- and-employed by Hartford Steam Boiler I & I Company of _. Hartford. CT have inspected the components described in this Owner's Report during the period' January 1. 1992 to Aunust 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this Owner's 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.
, k Inspector's Signature: a I- J p Commissions: NB #10352. Nebraska. N. I (National Board, State, Province,'and Endorsements)
Date: /$ /Uf3
l FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS
'As Required by the Provisions of-the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 ,
(Name) P.O. Box 499. Columbus. NE 68601 Sheet 6 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box _98. Brownville. NE 68321 N/A , (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: H/A-Same Authorization Date: N/A (Address) N/A Expiration Date:
- 4. Identification of System: Main Steam (MS)
- 5. (a) Applicable Construction Code: ASME Section III 19 68 Edition, Summer 1970 Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Work Repaired ASME Code Name of Name of Nuclear Class Document Replaced, or Stamped Component Manufacturer Number Replacement (Yes or No)
MS-RV-71DRV (1) Target Rock 1 92-2741 Replacement No MS-RV-71ERV (2) Target Rock 1 92-2742 Replacement No MS-RV-71BRV (3) Target Rock 1 92-2739 Replacement No MS-RV-71ARV (4) Target Rock 1 92-2738 Replacement No MS-RV-70CRV (5) Dresser 1 92-2779 Replacement No 7 Dascription of Work: (1) Replaced three studs. (2) Replaced one stud. (3) Replaced six studs. (4) Replaced seven studs. (5) Replaced one stud and two nuts.
'. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 1020 psi Test Temp. Ambient "F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
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a - - . . - -- ,
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throuch the use of Form NIS-2 for reportinn.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE L We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of A th rization No. N/A Expiration Date: N/A Signed: (},9
#A -
h A Ennineerine Manager Date: 10-12-93
+
[/ (OwndorOwner'sDesignee. Title) t CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford CT have inspected the components described in this owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures ! described in this owner's Report in accordance with the requirements of the ASME , Code, Section XI. By signing this certificate, neither the Inspector nor his employar makes any '; warranty, expressed or implied, concerning the examinations and corrective measured described in this Owner's 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. 1 Inspector's Signature: </- s Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: /8-/#/'NS A
, ,m .. . . . .. - ._.- > . .m _ .- - ,_, . _ . . . - . _
t i FORM NIS-2 OL'NER'S REPORT FOR~ REPAIRS OR REPLACEMENTS '
+
As Required by-the Provisions of the ASME Code Section XI G
~ 1'; : Owner: Nebraska Public Power District Date: October 5. 1993 (Name) {
P.O. Box'499. Columbus.'NE 68601 Sheet 7 of 89 . (Address) . 2; Plant: Cooper Nuclear Station Unit: One (Name) - P.O. Box 98. Br .mv111e . NE 68321 N/A [ (Address) (Repair Orgainzation, P.O. ; No. , Job No. , . Etc. ) {
- 3. Work Performed By: Owner Type Code Symbol Stamp:-E/.A i Same Authorization Date: N/A ~
(Address) - Expiration Date: N/A - i
- 4. Identification of System: Main Steam (MS)
- 5. (a) Applicable Construction Code: ASME Section III '
19 68 Edition,- Summer 1970 Addenda, N/A . Code Case , i (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components ,{
W rk Repaired : ASME Code - Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class { Number Replacement. (Yes or No) q MS-RV-71GRV Target Rock -1 92-2744 -Replacement- NoI
-i i
I l
- 7. Description of Work: Replaced einht bolts, four studs. and twelve nuts-. i
- )
1 o
- 8. Tests Conducted: ; Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 1020 psi Test Temp. Ambient "F I NOTE: Supplemental sheets in the' form of lists, sketches, or drawings may be used, provided (1) size-is 8-1/2" x 11", (2) information in items'1 throughj6 on this report is included on each sheet, and (3) each sheet is numbered and the' number of' sheets is recorded at the top of this form.
-I
[ :
1 l 1 ir 9. -Remarks: Code Case N-308. " Documentation of Renairs and Replacements of i Components in Nuclear Power Plants" is invoked throuch the use of Form'NIS-2 for ; i reportinn. .I I (Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI, (repair or replacement) Type Code Symbol Stamp: N/A Certification of Auth rigation No. N/A Expiration Date: N/A , 9 Signed: / Engineerine Mananer Date: 10-12-93 j/ (ownero(Owner'sDesignee, Title) CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a calid commission issued by the National Board of ' Boiler and Pressure Vessel In etors and the State or Province of Nebraska and employed by Hartford Steam siler I & I Comptny of Hartford. CT .have inspected the components described in this owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Omer has performed examinations and taken corrective measures described in this Owner's 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 measured described in this Owner's 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. Inspector's Signature: w! E tcJ Commissions: NB #10352. Nebraska, N. I (National Board, State, Province, and Endorsements) Date: lo-B/-93
FORM NZS-2 OUNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 8 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P,0. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.) 3 .. Work Performed By: Owner Type Code Symbol Stamp: EfA Same Authorization Date: N/A (Address) Expiration Date: N/A
- 4. Identification of System: Nuclear Boiler (NB)
- 5. (a) Applicable Construction Code: ASME Section III 19 65 Edition, Winter 1966 Addenda, N/A Code Case (b) Applicable Edition of Section X1 Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Stamped-Document Replaced, or Component Manufacturer Class Replacement Number (Yes or No)
" i" 93-2058 Repaired RPV Lower Head 1 No Eng ring
- 7. Description of Work: Crind out indications in the outer attachment weld between the RPV lower head and the support skirt.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other N/A Pressure psi Test Temp. 'F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) Information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
i
5
- 9. Remarks: Code Case N-308. " Documentation'of Repairs and Replacements of ,
t Components in Nuclear Power Plants" is invoked through the use of Form NIS-2 for reportinn. (Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE , We certify that the statements made in the report are correct and this repair conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Auth rization No. N/A Expiration Date: N/A Signed; w vu 2-l l11u 7 Engineering Mananer Date: 10-12-93 [/'(Ow'eror(wner'sDesignee, n Title) CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company' of Hartford.-CT have inspected the components described in this Owner's-Report during the period January 1. 1992 to Aucust 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective. measures described in this Owner's 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 measured described in this Owner's 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. Inspector's Signature:Y #~.) Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: N-/Uf3
FORM NIS-2 OWNER'S PJEPORT FOR REPAIRS OR REPLACEMENTS - As Required by the Provisions of the ASME Code Sectiun XI
- 1. 'Dwner: Nebraska Public Power District Date: October 5. 1993 ,
(Name) P.O. Box 499. Columbus. NE 68601 Sheet 9 of 89
-(Address)
- 2. Plant: ,
Cooper Nuclear Station Unit: One (Name) P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Peri rmed By: Owner Type Code Symbol Stamp: N/A ,.
Same Authorization Date: N/A
^ '""' '
Expiration Date: N/A-
- 4. Identification of System: Core Sprav (CS) -
- 5. (a) Applicable Construction Code: USAS B16.5 19 68 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Work Repaired ASME Code Name of Name of Nuclear Document Replaced or Stamped Component Manufacturer Class .
Number Replacement (Yes or No) CS-RV-13RV Consolidated 2 93-1924 Repaired No
,I
- 7. Description of Work: Rotated CS-RV-13RV inlet flanne by cuttinc and reweldine.
- 8. Tests Conducted: Ilydrostatic X Pneumatic Nominal Operating Pressure ;
other Pressure 625 psi Test Temp. 72 "F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this , report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top _of this form.
)
i
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of .!
Components in Nuclear Power Plants". is invoked throunh the use of Form NIS-2 for reportine. (Applicable Manufacturer's Data Reports to be Attached) , y CERTIFICATE OF COMPLIANCE I
- )
We certify that the statements made in the report are correct and this repair conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authoriz tion No. N/A Expiration Date: N/A Signed: 04) VA / ', ,
-k--
em4_3 Encineerinz Manager Date: 10-12-93
/ (Owner or er's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and' employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this Owner's Report during the period January 1. 1992 to Aunust 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures
~
described in this Owner's 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 measured described in this Owner's 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. Inspector's Signature: M )d Commissions: NB #10352. Nebraska. N. I (National Board, State, Province,.and Endorsements) Date: / / - W '-f_? L
!.x FORM NIS-2 OSNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE- 68601 Sheet 10 of 89 (Address) ,
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. ; No . , J ob No . , Etc . )
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address) Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components i
V rk Repaired ASME Code Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Replacement Number (Yes or No)
.RH-S76A Grinnell 2 93-1761 Repaired No
- 7. Description of Work: Restaked spherical bearinn on snubber upper paddle. ,
- 8. Tests Conducted: Hydrostatic Pneumatic j Nominal Operating Pressure Other N/A Pressure psi Test Temp. *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
i 9 Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throunh the use of Fonn NIS-2 for reportine. l (Applicable Manufacturer's Data Reports to be Attached) H CERTIFICATE OF COMPLIANCE - We certify that the statements made in the report are correct and this repair conforms to the rules of the ASME Code, Section XI. (repair or replacement) , Type Code Symbol Stamp: N/A Certification of Autho i tion No. N/A Expiration Date: N/A' - Signed: su o Ennineerinn Mananer Date: 10-12-93 l/ [0wner o p er's Designee, Title) CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I company of Hartford. CT have inspected the components described in this owner's Report during the period January 1. 1992 to Aunust 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this Owner's 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. Inspector's Signature: a / <e4 Commissions: NB #10352. Nebraska. N. I " (National Board, State, Province, and Endorsements) Date: MF/e f3
'l
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As' Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 11 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownv111e. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A' )
(Address) Expiration Date: N/A
- 4. Identification of System: Main Steam (MS)
- 5. (a) Applicable Construction Code: ASME Section III 19 68 Edition, Summer 1970 Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components
# *E*'#" ^
- Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Replacement Number (Yes or No)-
MS-RV-70CRV Dresser 1 92-2779 Repaired No MS-RV-70BRV Dresser 1 92-2779 Repaired No
- 7. Description of Work: Valves were refurbished.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 1020 psi Test Temp. Ambient "F-NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on.this report is included on each sheet, and (3) each sheet is numbered and the number of-sheets is recorded at the top of this form.
.i
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throuth the use of Form NIS-2 for-reportine.
(Applicable Manufacturer's Data Reports to be Attached)- CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair conforms to the rules of the ASME Code, Section XI, (repair or replacement) Type Code Symbol Stamp: N/A Certification of Auth rization No. N/A Expiration Date: N/A Signed: , s Engineering Manager Date: 10-12-93 [/ (OwnerffOwner'sDesignee, Title) j CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this owner's Report'during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this Owner's 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. l Inspector's Signature: / a - a40
- Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements)
Date: }O hl- f 3 l
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI , t
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 12 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name) ,
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job.No., Etc.)
- 3. Work Performed By: Owner Type Code Sym'bol Stamp: N/A Same Authorization Date: N/A (Address) Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B16.5 19 68 Edition, No Addenda, N/A Code Case ,
(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No) i RHR-MOV-M018 Anchor / Darling 1 93-1180 Repaired No
- 7. Description of Work: RHR-MOV-M018 had a scratch in pressure seal area repaired ~and 1
I pits removed. ! 1
- 8. Tests Conducted: Hydrostatic Pneumatic )
Nominal Operating Pressure X Other Pressure 1020 psi Test Temp. Ambient "F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, , I provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
;i
'I
'i g
i l
'9, Remarks: Code Case N-308. " Documentation of Repairs and Replacements of
[-
.i Components in Nuclear Power Plants" is invoked throuch the use of Form NIS-2 for l reportina.
(Applicable Manufacturer's Data Reports to be Attached) j CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair conforms to the rules of the ASME Code, Section XI. ; (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authori ation No. N/A Expiration Date: N/A Signed: o Ennineerinn Manager Date: 10-12-93 f' (Ownero(Owner'sDesignee, Title) CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I company of Hartford. CT have inspected the components described in this Owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures l described in this Owner's 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 measured described in this Owner's 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. Inspector's Signature: /Y 1 1- u J'-e ' Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: MN~ fd
L !. I I FORM NIS-2 OUNER'S REPORT FOR REPAIRS OR REPLACEMENTS i As Required by the Provisions of the ASME. Code Section XI ;
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name) I P.O. Box 499. Columbus. NE 68601 Sheet 13 of 89 ;
(Address)
- 2. Plant: Cooper Nuclear Station Unit: One' (Name)
P.O. Box 98. Brownville. NE 68321 N/A .
't (Address) (Repair Orgainzation, P.O.
No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address) Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B16.5 19 68 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components "P" #* ^ "
Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Replacement Number (Yes or No) RHR-MOV-M018 Anchor / Darling' 1 93-1180 Replacement No ;
- 7. Description of Work: Valve stem replaced.
8, Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 1020 psi Test Temp. Ambient *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used,' provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. j
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throuzh the use of Form NIS-2'for reportine. ,
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE : T We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authorfzation No. N/A Expiration Date: N/A Signed: / . 1 Engineerina Mananer Date: 10-12-93
/ (owner ( Owner's Designee, Title) i CERTIFICATE OF INSERVICE INSPECTION 1
I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of- Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this Owner's Report during the period January 1. 1992 to Aunust 31. 1993 , and state that to the best of_my knowledge and belief, the Owner has performed examinations and taken corrective measures ' described in this owner's 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 measured-described in this Owner's 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. Inspector's Signature: /b > we d.-s Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: /n-/<673
l FORM NIS-2 OUNER'S REPORT'FOR REPAIRS OR REPLACEMENTS ' As Required by the Provisions of the ASME Code Section.XI
- 1. Owner: Nebraska Public Power District Date: October S. 1993 (Name) q P.O. Box 499. Columbus. NE 68601 Sheet 14 of 89 )
(Address) ; 1
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A
]
Same Authorization Date: N/A I (Address) N/A l Expiration Date: j
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: ASME Section IIT 19 86 Edition, 1987 Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda ,
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code.
Name of Name of Nuclear Manufacturer Class Document Replaced,'or Stamped-
-Component Replacement Number (Yes or No)
RHR-MOV-M018 Anchor / Darling 1 93-1180 Replacement No )
)
i
'l
- 7. Description of Work: Valve's dise was replaced. .
.l
- 8. Tests Conducted: Hydrostatic Pneumatic ;
Nominal Operating Pressure X , Other Pressure 1020 psi Test Temp. Ambient "F l NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, ; provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this l report is included on each sheet, and (3) each sheet is numbered and the number of j sheets is recorded at the top of this form.
-9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throunh the use of Form NIS-2 for reportinn. (Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authorization No. N/A Expiration Date: N/A Signed: N.? Engineering Manager Date: 10-12-93
/ "(Ownerot( Owner's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and-employed by Hartford Steam Boiler I & I Company of Hartford CT have inspected the components described in this Owner's Report during the period ' January 1. 1992 to AuRust 31, 1993 , and state that to.the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Sect 1on XI. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measured described in this owner's Report. Furthermore, neither the Inspector no'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 connected with this inspection.
.n Inspector's Signature: a[ YAd Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements)
Date: " Yb 1
FORM NIS-3 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS-As Required by the Provisions of the ASME Code Section II
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 15 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One ;
(Name) P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No . , J ob No . , Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: E/A j same Authorization Date: N/A (Address) N/A Expiration Date:
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B16.5 19 68 Edition, No Addenda, N/A Code Case ,
(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda ,
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear W rk Repaired ASME Code ument Replaced, or Stamped :l Component. Manufacturer Class Number Replacement (Yes or No)
Anchor / Darling 1 93-1180 Repaired' No Ori nal Disc (1) Original Disc (2) An hor / Darling 1 93-1421 Repaired No
- 7. Description of Work: (1) Disc refaced and vits removed. (2) Disc refaced.
- 8. Tests Conducted: Hydrostatic Pneumatic !
Nominal Operating Pressure 1 Other N/A Pressure psi Test Temp. *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, . provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this. report is included on each sheet, and (3) each sheet is numbered and the number'of sheets is recorded at the top of this form. , i
1
-9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of ,
?
Components in Nuclear Power Plants"- is invoked throuth the use of Form NIS-2 for reportint. (Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE' We certify that the statements made in the' report are correct and this repair conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Author zation No. N/A Expiration Date: N/A ; Signed: 3 - Ennineerinn Mananer Date: 10-12-93
// ' (owner Owner's Designee, Title)
CERTIFICATE OF INSERVICE. 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this owner's Report during the period January 1. 1992 to Aunust 31. 1993 , and state that to the best of my knowledge , and belief, the Owner has performed examinations and taken corrective measures described in this owner's 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 measured described in this Owner's 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. - Inspector's Signature w M -J Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) i Date: /d-/V-f3 La . . _ - - _ _-
FORM NZS-2 OWEER'S REPORT FOR' REPAIRS OR REPLACEMENTS : As Required by the Provisions of the ASME Code Section XI t 1 1.. Owner: Nebraska Public Power District Date: October 5. 1993 ' (Name) P.O. Box 499. Columbus. NE 68601 Sheet 16 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name) ,
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.) !
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A
- Same Authorization Date: N/A (Address) Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B16.5 19 68 Edition, j No Addenda, N/A Code Case *
(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Work Repaired ASME Code Name of Name of Nuclear Manufacturer Class Document Replaced, or Stamped Component Replacement Number (Yes or No)
RHR-MOV-M017 (1) Anchor / Darling 1 93-1421 Replacement No i RHR-MOV-M013B (2) Anchor / Darling 2 93-0941 Replacemert -No
- 7. Description of Work. Replaced valve disc and stem.
.8. Tests Conducted: Hydrostatic Pneumatic . Nominal Operating Pressure X Other Pressure (1) 29/(2) 13 psi Test Temp. Ambient 'F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this j report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
[.
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throuth the use of Form NIS-2 for reporting.
(Applicable Manufacturer's Data Reports to be Attached) j CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this q 1 replacement conforms to the rules of the ASME Code, Section XI. ! (repair or replacement) -l Type Code Symbol Stamp: N/A l Certification of Author zation No. N/A Expiration Date: N/A ] Signed: )N bJ n.En Engineerinn Manager Date: 10-12-93 l
/ ~(Owner 9 Owner's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and ! employed by Hartford Steam Boiler I & I company of Hartford. CT have , inspected the components described in this owner's Report during the period , January 1. 1992 to Aunust 31, 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME - r Code, Section XI. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measured described in this Owner's 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. Inspector's Signature: c/ dsd/ ' Commissions: NB #10352, Nebraska. N. I (National Board, State, Province, and Endorsements) Date: l0* N~YN
i FORM NZS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section II
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 i (Name) !
P.O. Box 499. Columbus. NE 68601 Sheet 17 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. t No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A Expiration Date: 'N/A
- 4. Identification of System: Hirh Pressure Coolant Iniection (HPCT)
- 5. (a) Applicable Construction Code: USAS B16.5 __ 19 68 Edition, ;
No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No) l HPCI-MOV-M015 Anchor Valve 1 93-1739 Replacement No
- 7. Description of Work: Replaced bonnet bolts. stem, and disc.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 1020 psi Test Temp. Ambient *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
-)
- 9. , Remarks: Ccde Case N-308. " Documentation of Repairs and Renlacements of Components in Nuclear Power Plants" is invoked throunh the use of Form NIS-2 for !
reportine. (Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE e We certify that the statements made in the report are correct and this , i replacement conforms to the rules of the ASME Code, Section XI. (repcir or replacement) Type Code Symbol Stamp: N/A
^
Certification of Authorizat on No. N/A Expiration Date: N/A Signed: b Ennineering Mananer Date: 10-12-93
/ ~(Owner o Owner's Designee, Title) :
i CERTIFICATE OF INSERVICE INSPECTION i I, the undersigned, holding a valid commission issued by the National Board of .i Boiler and Pressure Vessel Inspectors and the State or Province of Nebraska and- ! c; ployed by _ Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this owner's Report during the period January 1. 1992 to Aunust 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this owner's 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 co u euil. :seasured Furthermore, neither the Inspector nor his described in this owner's Report. 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. : Inspector's Signature: d (. uA 5) Commissions: NB #10352 Nebraska. N. I (National Board, State. Province, ard EE >rsements) j Date: /#','V-9Y
~l l
1 l l
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 18 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.) 3 Work Performed By: Owner Type Code Symbol Stamp: JJ/A Same Authorization Date: N/A (Address) Expiration Date: N/A
- 4. Identification of System: Hinh Pressure Coolant Iniection (HPCI)
- 5. (a) Applicable Construction Code: USAS B16.5 19 68 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear W rk Repaired ASME Code umen ep a e r Stamped Component Manufacturer Class ,
Number Replacement (Yes or No) HPCI-MOV-MOIS Anchor Valve 1 93-1739 Repaired ' No
- 7. Description of Work: Bored bonnet. cland. and nland flanne: removed pittinc from bonnet nressure seal area. stuffint box. and back seat.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 1020 psi Test Temp. Ambient "F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of ,
sheets is recorded at the top of this form.
i 1 l l
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of j Components in Nuclear Power Plants" is invoked throunh the use of Form NIS-2 for ,
l reportine. (Applicable Manufacturer's Data Reports to be. Attached) CERTIFICATE OF COMPLIANCE 8 We certify that the statements made in the report are correct and this . repair conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: _ N/A Certification of Auth ri.at on No. N/A Expiration Date: N/A Signed: Q $ . I 4- a= Ennineerina Mananer Date: 10-12-93
// '(Ownero{Dwner'sDesignee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I &-I Company of Hartford. CT have inspected the components described in this Owner's Report during the. period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this owner's 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 measured described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be Jiable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Inspector's Signature: 9[u! J / Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: /d -/4 -/ 9 7
l I
'l FORM NIS-2 OWNER'S REPORT FOR REPhRS OR REPIACEMENTS j As Required by the Provisien; cI the ASME Code Section XI j
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name) j P.O. Box 499. Columbus. NE 68601 Sheet 19 of 89 (Addrers) '
- 2. Plant: Cooper Nuclear Station Unit: One !
(Name) P.O. Box 98. Brownville. NE 68321 N/A I (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address)
Expiration Date: N /A ,
- 4. Identification of System: Main Steam (MS)
- 5. (a) Applicable Construction Code: ASME Section III 19 68 Edition, Summer 1970 Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components t
Name of Name of Nuclear W rk Repaired ASME Code Component Manufacturer Class umen ep aced, or Stamped Number Replacement (Yes or No). MS-RV-71FRV Target Rock 1 92-2743 Replaced No MS-RV-71ARV Target Rock 1 92-2738 Replaced No
- 7. Description of Work: MS-RV-71FRV replaced with new valve IS/N 381). MS-RV-71ARV [
replaced with new valve (S/N 379). ,
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 1020 psi Test Temp. Ambient *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this !
report-is included oa each sheet, and (3) each sheet is numbered and the number of" sheets is recorded at the top of this form.
f f '9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throunh the use of Form NIS-2 for reportine. (Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF. COMPLIANCE , t We certify that the statements made in the report are correct and this-replacement conforms to the rules of the ASME Code, Section XI. _; ' (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authprization No. N/A Expiration Date: N/A Signed: ), m _r[] i' Engineering Manager Date: 10-12-93
/ '(Owner o Owner's Designee, Title) i CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have :
inspected the components described in this Owner's Report during the period' January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this owner's 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 measured .i described in this Owner's Report. Furthermore, neither the Inspector nor his. employer shall' he liable in any manner for any personal injury or property damage - , or a loss of any kind arising from or connected with this inspection. . Inspector's Signature: / Mu Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: k"-/ M 5 i
r a i e ' 1
.l FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS !
As Required by the Provisions of the ASME Code Section XI j 1
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 )
(Name) P.O. Box 499. Columbus. NE 68601 Sheet 20 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One' 4 (Name) !
P.O. Box 98. Brownville. NE 68321 N/A l (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: H/6 :
Same Authorization Date: N/A
^ ' '" '
Expiration Date: N/A
- 4. Identification of System: Main Steam (MS)
- 5. (a) Applicable Construction Code: ASME Section III 19 68 Edition, Summer 1970 Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No)
MS-RV-71BRV Target Rock 1 92-2739 Repaired No MS-RV-71CRV Target Rock 1 92-2740 Repaired No j MS-RV-71DRV Target Rock 1 92-2741 Repaired No 3 MS-RV-71ERV Target Rock 1 92-2742 Repaired No I t
- 7. Description of Work: Valves were refurbished. ,
l
- 8. Test.s Conducted: Hydrostatic Pneumatic ,
Nominal Operating Pressure X Other Pressure 1020 psi Test Temp. Ambient 'F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
t I
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throuth the use of Form NIS-2 for reporting.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A N/A Expiration Date: _ N/A CertificationofAuthorpationNo. Signed: X/( /. .'e - Ennineering Manager Date: 10-12-93
# "(Owner Owner's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this owner's Report during the period January 1. 1992 to August 31. 193" and state that to the best of my knowledge and belief, the owner has performed .xaminations and taken corrective measures described in this Owner's 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 measured described in this Owner's 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.
- /)' / , A Inspector's Signature: f W v L 4 -
Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: O* r V- f T
l FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1, Owner: Nebraska Public Power District Date: October 5. 1993-(Name) P.O. Box 499. Columbus. NE 68601 Sheet 21 of 89 (Address) L2. Plant: Cooper Nuclear Station Unit: One (Name) P.O. Box 98. Brownville m_,Ny 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.) ,
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address) N/A Expiration Date:
- 4. Identification of System: Main Steam (MS)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case i
(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Component Manufacturer Class Document Replaced, or Stamped Number Replacement (Yes or No)
MS-MOV-M077 Anchor / Darling 1 93-0810 Replacement No L i
- 7. Description of Work: Replaced valve stem.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 1020 psi Test Temp. Ambient *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is nwnbered and the number of sheets is recorded at the top of this form.
s
1 { l 1 l
.9. Remarks: Code Case N-308. " Documentation of Repairs and Replacer 9nts of Components in Nuclear Power Plants" is invoked throuch the use'of Form NIS-2 for ;
reportine. (Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement c.onforms to the rules of the ASME Code, Section'XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authorization No. N/A Expiration Date: N/A Signed: - ) Engineering Mananer Date: 10-12-93
/ (Ownero(Owner's Designee, Title)
CERTIFICATE OF INSERVICE INSPdCTION - I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Nebraska and employed by Hartford Steem Boiler I & I company of Hartford. CT have : inspected the components described in this owner's Report during the period ' January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this Owner's 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.
'- A Inspector's Signature:
e
/ AU ,
i Commissions: NB #10352, Nebraska. N. I (National Board, State, Province, and Endorsements) Date: /0 fV-ff , 1 t
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPl.ACEMENTS , As Required'by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October S. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 22 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One '
(Name) P.O. Box 98. Brownville. NE 68321 ~ N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: ' N/A Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B16.5 19 68 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear W rk Repaired ASME Code Component Manufacturer Class Document Replaced, or Stamped Number Replacement (Yes or No)-
RHR-MOV-M013C Anchor / Darling 2 93-1440 Replacement No-l l
- 7. Description of Work: Replaced valve disc.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X
- Other Pressure 6.0 psi Test Temp. Ambient "F_ ,
NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of : sheets is recorded at the top of this form.
)
I- ..
I
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of ,
Components in Nuclear Power Plants". is invoked throurh the use of-Form NIS-2 for reportine. , (Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE , We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authorizat on No. N/A Expiration Date: N/A Signed: , - Eh Engineering Mananer Date: 10-12-93 t/ ~(Ownerog] Owner'sDesignee, Title) CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I company of Hartford, CT have , inspected the components described in this Owner's Report during the period January 1, 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this Owner's 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. Inspector's Signature: .Zs i Commissions: NB #10352 Nebraska. N. I (National Board, State. Province, and Endorsements) i Date: /O /vi f f , t 4 [
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 23 of 89 (Address)
- 2. Plant: Cooper Nuclear Station' Unit: One (Name)
P.O._hgx 48. Brownville. NE 68321 N/A ___ (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: H/6 same Authorization Date: __N/A (Address) N/A Expiration Date:
- 4. Identification of System: Reactor Water Cleanup (RWCU)
- 5. (a) Applicable Construction Code: ANSI B16.34 19 81 Edition, No Addenda, N/A Code Case ,
(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Nuclear rk Repaired ASME Code Name of Manufacturer Class Document Replaced, or Stamped Component Nuniber Replacement (Yes or No)
RWCU-CV-lSCV Anchor / Darling 1 93-1381- Replaced No
- 7. Description of Work: Valve was replaced.
- 8. Tests Conducted- liydrostatic X Pneumatic Nominal Operating Pressure ]
Other Pressure 1140 psi Test Temp. Ambient *F i NOTE: Supplemental sheets in the_ form of lists, sketches, or drawings may be used. provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. mu --
. _ _ _ _ . _ 2
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of' Components in Nuclear Power Plants" is invoked throuch the use of Form NIS-2-for reportinn.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE i o We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A ' i Certification of Au horiz tion No. N/A _ Expiration Date: N/A Signed: A Engineerinz Manager Date: 10-12-93
/ (Owner @rOwner'sDesignee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I' Company of Hartford. CT- have inspected the components described in this Owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best.of my knowledge ; and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured , described in this Owner's 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. I Inspector's Signature: r - veM , Commissions: NB #10352. Nebraska. N. I i (National Board, State, Province, and Endorsements) . a Date: /4?"/V-)CT t - - . .._._____. .-
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI. .l. Owner: Nebraska Public Power District Date: October 5. 1993 (Name) P.O. Box 499. Columbus. NE 68601 Sheet 24 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One ;
(Name) 1 P.O. Box 98. Brownville. NE 68321 ___ N/A (Address) (Repair Orgainzation, P.O. N o . , J ob No . , Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address) N/A Expiration Date:
'4. Identification of System: Hinh Pressure Coolant Iniection (HPCI)
- 5. (a) Applicable Construction Code: USAS B16.5 19 68 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Replacement Number (Yes or No)
HPCI-CV-29CV (1) Atwood & Morrill 1 93-0794 Repaired No HPCI-MOV-M014 (2) Anchot/ Darling 2 92-2555 Repaired No i
- 7. Description of Work: (1) Removed pitting on bonnet. (2) Machined bonnet. backinn !
rinn. and packinn pusher. '8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure (1) 1020 psi Test Temp. Ambient *F I (2) 928 NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded.at the top of this form.
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked through the use of Form NIS-2 for l
reportine. { (Applicable Manufacturer's Data Reports to be Attached) l CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authpri ation No. N/A Expiration Date: N/A Signed: [2 Engineering Mananer Date: 10-12-93
/ (Ownerogwner'sDesignee, Title) l l
) CERTIFICATE OF INSERVICE INSPECTION I I, the undersigr.ed, holding a valid commission issued by the National Board of i Boiler and Pressure Vessel Inspectors and the State or Province of Nebraska and employed by Hartford Steam Boiler I & I company of Hartford. CT have inspected the components described in this Ow:ter's Report during the period January 1. 1992 to Aunust 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures' described in this Owner's 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 measured i described in this Owner's Report. .Furthermore, neither the Inspector nor his i 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. Inspector's Signature: bX > Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: /o - /Yi < U- _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ __ _ _ _ _
FORM NIS-2 OUNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5,_1993 (Name)
P.O. Box 499. Columbus. NC 68601 Sheet 25 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownv111a. P.E 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address) Expiration Date: N/A
- 4. Identification of System: Hinh Pressure Coolant Iniection (HPCI)
- 5. (a) Applicable Construction Code: USAS B16.5 19 68 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear ument Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No).
HPCI-MOV-M014 Anchor / Darling 2 92-2555 Replacement No
- 7. Description of Work: Replaced valve disc.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 928 psi Test Temp. Ambient *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information_in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
. _ . . __ ________J
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of components in Nuclear Power Plants" is invoked throuch'the use of Form NIS-2 for reportin.gu__
(Applicable Manufacturer's Data Reports to be Attached) , CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Autho i tion No. N/A Expiration Date: N/A Signed: . .c. Engineerine Manager Date: 10-12-93
# Towner or vner's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this Owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this owner's 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. Inspector's Signature: 7e #> Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: /4 /0'-f5
FORM NIS-2 0"NER'S REPORT FOR REPAIRS OR REPIACEMENTS As Required by the Provisions of the ASME Code Section XI 1
- 1. Owner: Nebraska Public-Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 __, Sheet 26 of 89 ' (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No . , J ob No . , Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Core Spray (CS)
- 5. (a) Applicable Construction Code: USAS B16.5 19 68 Edition, No Addenda, N/A. Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of W rk Repaired ASME Code '
Name of Nuclear Component Manufacturer Class Document Replaced, or Stamped Number Replacement (Yes or No) CS-MOV-MOSA Anchor / Darling 2 93-0808 Replacement No
?
.7. Description of Work: Replaced valve disc and two seats. l
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 300 psi Test Temp. Ambient *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
- 9. Remarks: Code Case N-308. "Documtytation of Repairs and Replacements of Components in Nucleag Power Pinnts" is invoked throuth the use of Form NIS-2 for reportine. ;
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A certification of Authorization No. N/A Expiration Date: N/A Signed: d Engineerina ManaRer Date: 10-12-93
/ '(Owner o wner's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and - employed by Hartford Steam Boiler I & I company of Hartford. CT have inspected the components described in this owner's Report during the period- . January 1. 1992' to August 31. 1993 , and state that to the best of my knowledge and belief, the owner has performed examinations'and taken corrective measures described in this owner's 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 measured described in this Owner's 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.
/ l Inspector's Signature $ 7 / d e>
Commissions: NB #10352'. Nebraska. N. I , (National Board, State. Province, and Endorsements) Date.: /1^ - / 9'- fi
- P i
i FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS l As Required by the Provisions of the ASME Code Section XI
- 1. -Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 27 of 89 (Address) -
- 2. Plant: Conner Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Standby Liquid Control (SLC)
- 5. (a) Applicable Construction Code: USAS B16.5 19 68 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components F 4
r epaired A E Code-Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No) SLC-RV-10RV Dresser 2 92-3107 Replaced No , SLC-RV-11RV Dresser 2 92-3108 Replaced No
- 7. Description of Work: Replaced valve.
J
- 8. Tests Conducted: Hydrostatic _ Pneumatic 'l 1 Nominal Operating Pressure X i Other Pressure 1300 psi Test Temp. Ambient *F ]
NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
s
- 9. Remarks: Code Care N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throur.h the use of Form NIS-2 for reportine.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A
~
Certification of Author za ion No. N/A Expiration Date: N/A Signed: Ennineerine Mananer Date: 10-12-93
/ (Ownerfirjowner'sDesignee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this owner's Report during the period January 1. 1992 to August 31. 1993 ,_and state that to.the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this owner's 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 measured described in this Owner's 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. Inspector's Signature: u g. 3 Commissions: NB #10352 Nebraska N. I (National Board, State, Province, and Endorsements) Date: l0 ' AUSE
i FORM MIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI i
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Eox 499. Columbus. NE 68601 Sheet 28 of 89 l (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: Ela Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Component Manufacturer Class Document Replaced, or Stamped Number Replacement (Yes or No)
RER-RV-14RV (1) Consolidated 2 93-0751 Replacement No , RHR-RV-15RV (2) Consolidated 2 93-0751 Replacement No , RRR-RV-17RV (3) Consolidated 2 93-0751 Replacement. No RHR-RV-20RV (4) Consolidated 2 93-0751 Replacement ' No RHR-RV-21RV (2) Consolidated 2 93-0751 Replacement No I
.l
- 7. Description of Work: Replaced four bolts and einht nuts on each valve.
i
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X ,
Other Pressure _f1) 185 psi Test Temp. Ambient *F ) (2) 60 psi; (3) 50 psi; (4) 180_ psi ' NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, , provided (1) size is 8-1/2" x 11", (2) Information in items 1 through 6 on this l report.is included on each sheet, and (3) each sheet is numbered and the number of l sheets is recorded at the top of this form. 1
_. __ . m
-9. Remarks: Code Cane N-308. " Documentation of Repairs and Replacements of Componenty,_Ln Nu;Ll ear Power Plants" is invoked throuch the use of Forn NIS-2 for reportinv.
(Applicable Manufacturer's Data Reports to be Attached)- CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authogiz. tion No, N/A Expiration Date; N/A Signed: - - n 7 Engineerina Mananer Date: 10-12-93
/
~(Owneror(pner'sDesince, 6 Title) i CERTIFICATE OF INSERVICE INSPECTION i
I, the undersigned, holding a valid commission issued by the National Board of Boller and Pressure Vessel Inspectors and the State or Province of Nebraska and- - employed by Hartford Steam Boiler I & I Company of. Hartford. CT have inspected the components described in this Owner's Report during the period , January 1. 1992 to August 31. 1993 , and state that to the best of my _ knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured-described in this Owner's 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 inspections , Inspector's Signature: < a /.J Commissions: NB #10352. Nebraska. N; I (National Board, State, Province, and Endorsements)- Date: //1YIE
?
FORM HIS-2 OUNZR'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: __ Mebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 29 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: EZ6 Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RER)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda 6 Identification of Components Repaired or Replaced and Replacement Components Name of W rk Repaired ASME Code Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No)
RHR-RV-18RV Consolidated 2 93-0751 Replacement No
- 7. ' Description of Work: Replaced nine bolts and einht nuts.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 150 psi Test Temp. Ambient *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this-report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
a
a
- 9. Remarks: Code case N-308. " Documentation of Repairs and Replacemepts of ComEonents in Nuclear Power Plants" in invoked throunh the use of Form NIS-2 for i
reportinn. (Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. , (repair or replacement) Type Code Symbol Stamp: N/A Certification of Author zation No. N/A Expiration Date: N/A Signed: , - 1 Engineerine Mananer Date: 10-12-93 j' ' '(Ownerq{ owner'sDesignee, Title) CERTIFICATE OF INSERVICE 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 Nebraska and ' employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this Owner's Report during the period January 1. 1992 to Aunust 31. 1993 , and state that to the best of my. knowledge and belief, the Owner has performed examinations and taken corrective measures , described in this Owner's 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 measured described in this owner's Report. Furthermore,.neither the Inspector nor his employer shall be liable in any manner for anf personal injury or property damage or_a loss of any kind arising from or connected with this inspection: . Inspector's Signature: 4 r#~ # Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) i i Date: /O-/4 R r , I t l- { i e - w
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section II
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 30 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: El6 Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Core Spray (CS)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Nuclear W rk Repaired ASME Code Name of Document Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No)
CS-RV-11RV (1) Consolidated 2 93-0751 Replacement No CS-RV-13RV (2) Consolidated 2 93-0751 Replacement No
- 7. Description of Work: (1 ) Replaced einht bolts and sixteen nuts. (2) Replaced four bolts and einht nuts.
- 8. Tests Conducted: Hydrostatic Pneumatic j Nominal Operating Pressure X )
Other Pressure (1) 300 psi Test Temp. Ambient "F-(2) 307 psi NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of , sheets is recorded at the top of this form. !
i 1 l E9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of s Components in Nuclear' Power Plants" is invoked through the use of Form NIS-2 for reportine. (Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Auth ri~ation No. N/A Expiration Date: N/A Signed: 7 .2 m Ennineerinn Manager Date: 10-12-93 4/ (Ownero(Owner'sDesignee, Title) l i CERTIFICATE OF INSERVICE 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 Nebraska and' ,; employed by Hartford Steam Boiler I & I Company have of Hartford. CT inspected the components described in this Owner's Report during the period January 1. 1992 to Aunust 31. 1993 , and state that to the best of my knowledge , and belief, the Owner has performed examinations and taken corrective measures ' described in this Owner's 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 measured' ,. described in this Owner's 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. Inspector's Signature: Ye J b /~~$ \ c Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements)- Date: ' M-NE R i
1 l FORM NIS-2 OUNER'S REPORT FOR REPAIRS OR REPI). CEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 ;
(Name) P.O. Box 499. Columbus. NE 68601 Sheet 31 of 89 (Address)
- 2. Plant: Cooper Nuclear Station ' Unit: One (Name)
P.O. Box 98 Brownville. NE 68321 N/A l (Address) (Repair Orgainzation, P.O. j No., Job No., Etc.) l
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A
[ Same Authorization Date: N/A Expiration Date: N/A 4 Identification of System: Standby Liould Control (SLC)
- 5. (a) Applicable Construction Code: ASME Section III 19 77 Edition, Summer 1977 Addenda, N/A Code Case l l
(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear umen ep a ed, or Stamped Component Manufacturer Class Number Replacement (Yes or No)
SLC-SQBV-14B Conax Corp. 1 92-3106 Replacement No
.i l
- 7. Description of Work: _Ryplaced valve insert. including trirter body.
- 8. Tests Conducted: Hydrostatic Pneumatic .l Nominal Operating Pressure X Other Pressure 1300 psi Test Temp. _ Ambient "F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through'6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
i
- 9. Ren. arks : __Gode Case N-308. " Documentation of Repairs and Replacements of Components in !Nelear Power Plants" is invoked throunh the use of Form NIS 2 for reportine.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Au,thpri ation No. N/A Expiration Date: N/A Signed: Ennineering Manager Date: 10 12 ; [~ (Own or Owner's Designee, Title) I i
.1 CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this Owner's Report during the period January 1, 1992 to August 31, 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this Owner's 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. Inspector's Signature: Y ~M Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements)- Date: /A- 19-93
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS ; As Required by the Provisions of the ASME Code Section II l i l
- 1. Owner: Nebrasha Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 32 of 89 (Address) -2. Plant: Cooper Nuclear Station Unit: One : (Name) P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address)
Expiration Date: N/A i
- 4. Identification of System: Core Spray (CS) t
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, ,
No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda '6. Identification of Components Repaired or Replaced and Replacement Components C Name of Name of Nuclear W rk Repaired ASME Code Document Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No) CS-RV-11RV Consolidated 2 93-0751 Replacement No i
- 7. Description of Work: Replaced valve cuide pin. ;
'8. Tests Conducted: Hydrostatic Pneumatic ' Nominal Operating Pressure X Other Pressure 300 psi Test Temp. Ambient 'F NOTE:-Supplemental sheets lhi the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through-6 on this report is included on each sheet. and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
9 -Remarks: Code case N-308. " Documentation of Repairs and Replacements of
. Components in Nuclear Power Plants" is invoked throur.h the use of Form NIS-2 for reportinv.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE e We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authorization No. N/A Expiration Date: N/A Signed: t 2 Engineering Manager Date: 10-12-93 9 ' (Owner Owner's Designee, Title) CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford CT have inspected the components described in this Owner's Report during the period January 1. 1992 to August 31. 1993 ,- and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in thin Owner's Report. Furthermore, neither the Inspector nor his , employer shall he liable in any manner for any personal . injury or property damage or a loss of any kind arising from or connected with this inspection.
)
Inspector's Signature / 4 .i 4 Commissions: NB #10352, Nebraska. N. I
-(National Board, State, Province, and Endorsements)
Date: /6 - /V-17 l 8
FORM NIS-2 OUNER'S REPORT FOP. REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Powet District Date: October 5. 1993 ,
(Name) ' P.O. Box 499. Columbus. NE 68601 Sheet I of 89 (Address)-
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brovnville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job Wo., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: 'N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Primary Containment (PC)
- 5. (a) Applicable construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components paired or Replaced ara Replacement Components Name of r epaire ASME Code Name of Nuclear cumen eP 8 e r amPed Component Manufacturer Class ,
Number Replacement (Yes or No) ' ""* "" " ^
)
Tioga 2 93-0751. Replacement No PC-V-61 Flanges Tioga 2 93-0751 Replacement No Pene a " A dFag Tioga 2 93-0751 Replacement No
=
- 7. Description of Work: Replaced all bolts and nuts on the specified flannes.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 6.25_ psi Test Temp. Ambient 'F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, ,
provided (1) size is 8-1/2" x 11", (2) information in items 1 through'6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
1 i t
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throunh the use of Form NIS-2 for i reportine.
(Applicable Manufacturer's Data Reports to be Attached)
'i i
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ; t replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Aut o ization No. N/A Expiration Date: N/A I
/
Signed: LX/(O t . eca%) Engineering Manager Date: 10-12-93
// (OwnerfOwner'sDesignee, Title) i i
CERTIFICATE OF INSERVICE 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 Nebraska ~ and employed by Hartford Steam Boiler I & I Company of Hartford. CT have 1 inspected the components described in this Owner's Report during the period January 1. 1992 to Aug.ust 31. 1993 , and state that to the best-of my knowledge and belief, the owner has performed examinations and taken corrective measures ; described in this Owner's 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 measured described in this owner's 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. J. Inspector's Signature: <[/ 'b e 2) Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) , Date: /.^ - @ f ?
-e , _ .
FORM NIS-2 03NER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions-of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 34 of 89 (Address) -2. Plant: Cooper Nuclear Station Unit: One (Name) P.O. Box 98. Brovnville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: Nf6 Same Authorization Date: N/A (Address) ,
Expiration Date: N/A '
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: ASME Section III 19 83 Edition, Summer 1983 Addenda, N/A Code Case (b) Applicabi+ Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear U rk Repaired ASME Code Component Manufacturer Class Document Replaced, or Stamped Number Replacement (Yes or No)
RH-S8A Pacific Scientific 1 93-1173 Replaced No l
- 7. Description of Work: Replaced with snubber S/N 407.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other N/A Pressure psi Test Temp. *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throuph the use of Form NIS-2 for reportiny.
l l (Applicable Manufacturer's Data Reports to be Attached) l - CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A ion No. N/A Expiration Date: N/A CertificationofAuthorfza Signed: k. M Engineerinz Mananer Date: 10-12-93
/ (OwnerofOwner'sDesignee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this Owner's 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.
- As Inspector's Signature: L/ 2.fs M d Z ~
Commissions: NB #10352 Nebraska. N. I (National Board, State, Province, and Endorsements) Date: /? -/9 G r
t b FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1, Owner: Nebraska Public Power District Date: ___ October 5. 1993 (Name) P.O. Box 499. Columbus. NE 68601 Sheet 35 of 89 (Address) ,
- 2. Plant: Cooper Nuclear Station ~ Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address) N/A Expiration Date:
- 4. Identification of System: Reactor Feedwater (RF)
- 5. (a) Applicable Construction Code: USAS B31.7 9 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components V rk Repaired ASME Code Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Replacement Number (Yes or No)
RF-CV-13CV (1) Anchor Valve 1 92-2719 Replacement No RF-CV-14CV (2) Anchor Valve 1 92-2720 Replacement No RF-CV-15CV (3) Anchor Valve 1 92-2721 Replacement No RF-CV-16CV (2) Anchor Valve 1 92-2722 Replacement No
- 7. Description of Work: Replaced hinre nin cover studs and nuts and the hinne pin covers for each valve.
- 8. Tests Conducted: Ilydrostatic Pneumatic Nominal Operating Pressure X Other Pressure (1) 900 psi Test Temp. Ambient "F (2) 1020 psi (3) 1022 psi NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
- 9. Remarks: Code Case N-308; " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throunh the use of Form NIS-2 for reporting.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Autho izati n No. N/A Expiration Date: N/A Signed: bJ , Engineering Mananer Date: 10-12-93
/ (owner o owner's Designee, Title)
CERTIFICATE OF INSERVICE INSPECTION l I, the undersigned, holding a valid commission issued by the National Board of i- Boiler and Pressure Vessel Inspectors and the State or Province of Nebraska and employed by - Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this Owner's Report during the period-January 1. 1992 to _A,ugust 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificat:e, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measured described in this owner's Report. Furthermore, neither the Inspector nor his l 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. Inspector's Signature: [ n/[ d d Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: /d tv-? ?
7 FORM NIS-2 OWNER'S REPORT FOR REPAYRS OR REPLACEMENTS , As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993
^
(Name) P.O. Box 499. Columbus. NE 68601 Sheet 36 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address) N/A Expiration Date:
4 Identification of System: Control Rod Drive (CRD)
- 5. (a) Applicable Construction Code: ASME Section III 19 86 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No)-
14-11 A & G Eng. 1 93-0686 Replacement No , 26-23 A & G Eng. 1 93-0686 Replacement No ~ < 34-27 A & G Eng. 1 93-0686 Replacement No 18-39 A & G Eng. 1 93-0686 Replacement No 14-39 A & G Eng. 1 93-0686 Replacement No I
- 7. Description of Work: Peplaced einht bolts on each component, j
- 8. Tests Conducted: llydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 1020 psi Test Temp. Ambient *F !
NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, I provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this ~ l report is included on each sheet, and (3) each sheet is numbered and the number of - sheets is recorded at the top of this form. J
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacrnents of Components in Nuclear Power Plants" is invoked throuch the use of Form NIS-2 for reportine.
'(Applicable Manufacturer's Data Reports to be Attached)
CERTIFICATE OF COMPLIANCE' We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A N/A N/A Certification of Author ation No. Expiration Date: Signed: 0/(4n M
,9Lo emus Engineering Manager Date: 10-12-93
/ '(Owner Owner's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska- and: employed by Hartford Steam Beiler I & I Company of Hartford. CT have inspected the components described in this Owner's Report during the period i January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures ! described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. i By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measured described in this Owner's 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. t
/
Inspector's Signature: ~-~P / #V Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: <<^ ~ /Cl- 5' E
)
i l FORM NIS-2 OUNER'S P2 PORT FOR REPAIRS OR REPLACEMENTS
.As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 ,
(Name) P.O. Box 499. Columbus. NE 68601 Sheet 37 of 89 (Address)
- 2. Plant: Cooner Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) -(Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A .
(Address) Expiration Date: N/A
- 4. Identification of System: Control Rod Drive (CAD)
- 5. (a) Applicable Construction Code: ASME Section III 19 86 Edition, No Addenda, N/A __ Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear W rk Repaired ASME Code Document Replaced, or Stamped Component Manufacturer Class Number Peplacement (Yes or No) ;,
#9 9 38-11 A & G Eng. 1 93-0686 Replacement No 10-39 A & G Eng. 1 93-0686 Replacement No 14-15 A & C Eng. 1 93-0686 Replacement No 18-03 A & G Eng. 1 93-0686 Replacement No 42-35 A & G Eng. 1 93-0686 Replacement No
- 7. Description of Work: Renlaced eir_ht bolts on each component.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 1020 psi Test Temp. Ambient "F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this.
report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
i
- 9. Remarks: Code Case N-308. " Documentation of Renairs and Renlacements of Comnonents in Nuclear Power Plants" is invoked throunh the use of Form NIS-2 for renortina.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authorization No. N/A Expiration Date: N/A Signed: W3 ,T Engineerina Mananer Date: 10-12-93
/' ~ (Owner q Owner's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the compcnents described in this Owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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, concernin5 the examinations and corrective measured. described in this owner's 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. Inspector's Signature:'// / c+ 3 Commissions: NB #10352, Nebraska, N. I (National Board, State, Province, and Endorsements) Date: 9 h/- (T
{E ii
- j FORM.NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS' H As-Required by the Provisions of the.ASME Code Section XI 1
. i
- 1. Owner: Nebraska Public Power District Date: October 5.-1993 1
- (Name ) .
P.O. Box 499. Columbus. NE 68601 Sheet- ~38' of 89 : (Address)
- 2. Plant: Cooper Nuclear Station Unit: One' ,
(Name) ; P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. 1 No. , Job No. , Etc. ) _ i
- 3. ' Work Performed By: Owner Type Code Symbol Stamp: N/A j Same Authorization Date: N/A- .
Expiration Date: N/A
- 4. Identification of System: Control Rod Drive (CRD) !
- 5. (a) Applicable Construction Code: ASME Section III 19 86 Edition, No Addenda, N/A Code Case ,
-l (b) Applicable Edition of Section XI Utilized for Repairs or Replacements :
1980, Winter 1981 Addenda ,
- 6. Identification of Components Repaired or Replaced and Replacement Components j ,
Name of- Name of Nuclear W rk Repaired -ASME, Code l Component Manufacturer Class Document Replaced, or. Stamped l Number , Replacement .(Yes or No) ) 18-43 A & G Eng. 1 93-0686 Replacement .No: i 10-11 A & G Eng. 1 93-0686 Replacement No h
-I d
t i-
- 7. Description of Work: Replaced eithe bolts on each component. '
,t j
- 8. Tests Conducted: Hydrostatic ~ Pneumatic Nominal' Operating Pressure X' Other Pressure 1020 psi Test Temp. Ambient "F {
i NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used,' l provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this.
~
report is included on each sheet, and (3) each sheet is numbered and the number of l sheets is recorded at the: top of this form. {
- 9. . Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throunh the use or Form NIS-2 for reportinz. ,,
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) , Type Code Symbol Stamp: N/A Certification of Authoriyat on No. N/A Expiration Date: N/A Signed: ? Engineerine Mananer Date: 10-12-93
/ (ownerof0wner'sDesignee, Title)
CERTIFICATE OF INSERVICE INSPECTION 2 I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province-of Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this Owner's Report during the period January 1. 1992 to Aunust 31. 1993 ,.and state that-to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured , described in this owner's 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. . Inspector's Signature: Y h\ AJ ; Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) l Date: P -W P) t I i
0
]
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the. Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 39 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Control Rod Drive (CRD) 5 (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components rk Repaired ASME. Code Name of Name of Nuclear Component Manufacturer Class Document Replaced, or Stamped Number Replacement (Yes or No) 14-11 General Electric 1 93-0686 -Replaced No 26-23 General Electric 1 93-0686 Replaced No 34-27 General Electric 1 93-0686 Replaced No 18-39 General Electric 1 93-0686 Replaced No 14-39 General Electric 1 93-0686 Replaced No
- 7. Description of Work: Replaced Control Rod Drive mechanisms. )
l
- 8. Tests Conducted: Hydrostatic Pneumatic
- Nominal Operating Pressure X -
Other Pressure 1020 psi Test Temp. Ambient "F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report'is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. ; i j
- 9. Remad_. Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked through the use of Form NIS-2 for ;
reportine. (Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Author zation No. N/A Expiration Date: N/A ' IW Y b Signed: VK b , 2 . er4A Ennineering Mananer Date: 10-12-93
/ ' (ownerfOwner'sDesignee, Title)
CERTIFICATE OF INSERVICE INSPECTION i I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of- Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this Owner's Report during the period January 1. 1992 to Aunust 31. 1993 , and state that'to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this Owner's Report. Furthermore, neither the Inspector nor his l 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. Inspector's Signature: "/ b / 2 d e-l Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Datc: A* - A f7 l >
E FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 .
(Name) P.O. Box 499. Columbus. NE 68601 Sheet 40 of 89 (Address) ,
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orga'nzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: H/A Same Authorization Date: N/A (Address) N/A Expiration Date:
- 4. Identification of System: Control Rod Drive (CRD) ;
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components l W rk Repaired ASME Code Name of Name of Nuclear Class Document Replaced, or Stamped Component Manufacturer Number Replacement (Yes or No) 38-11 General Electric 1 93-0686 Replaced No 10-39 General Electric 1 93-0686 Replaced No 14-15 General Electric 1 93-0686 Replaced No 18-03 General Electric 1 93-0686 Replaced No 42-35 General Electric 1 93-0686 Replaced No r
- 7. Description of Work: Replaced Control Rod Drive mechanisms.
l
- 8. Tests Conducted: liydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 1020 psi Test Temp. Ambient *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of j sheets is recorded at the top of this form. l l
J
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of ;
Components in Nuclear Power Plants" is invoked throuth the use of Form NIS-2 for reportine. (Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE i i We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Aut orjzationNo. N/A Expiration Date: N/A Mg *. /_ [ Signed: VA / / .a- tecWL, Engineerinn Mananer Date: 10-12-93 [/ ' (Ownerof0wner'sDesignee, Title) CERTIFICATE OF INSERVICE 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 Nebraska 'and employed by Hartford Steam Boiler I & I company of Hartford. CT have inspected the components described in this owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this owner's 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. Inspector's Signature W N / .( -
. su Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements)
?
Date: A'-h% 9 ? I l
I FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS l As Required by the Provisions of the ASME Code Section XI l 1.. Owner: Nebraska Public Power District Date: October 5. 1993 ) (Name) i l P.O. Box 499. Columbus. NE 68601 Sheet 41 of 89 1 (Address)
- 2. Plant: Cooner Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address) Expiration Date: N/A
- 4. Identification of System: Control Rod Drive (CRD)
- 5. (a) Applicable Construction Code: _ USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Class Document Replaced, or Stamped Component Manufacturer Number Replacement (Yes or No) 18-43 General Electric 1 93-0686 Replaced No 10-11 Ceneral Electric 1 93-0686 Replaced No
- 7. Description of Work: Replaced Control Rod Drive mechanisms.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Prescure X Other Pressure 1020 psi Test Temp. Ambient 'F -
NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of. sheets is recorded at the top of this form.
-9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throuch the use of Form NIS-2 for
'i reportinn.
(Applicable Manufacturer's Data Reports to be Attached) , i l i CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A CertificationcfAuthorpzationNo. N/A Expiration Date: N/A : Signed: A Engineerinz Mananer Date: 10-12-93
/ ' '(Owner ([ Owner's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and i employed by Hartford Steam Boiler I & I Com9any lof Hartford. CT have ! inspected the components described in this owner's Report during the period-January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this owner's 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.
< / >
Inspector's Signature:'S, MR Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: 4 JVD
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section II
- 1. -Owner: Nebraska Public Power District Date: October S. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 42 of 89 (Address)
- 2. Plant: Cooper Nuclear Station ? Unit: '
One (Name) P.O. Box 98. Brownville. NE 68321 N/A , (Address) (Repair Orgainzation, P.O. No., Job No., Etc.) ,
- 3. Work Performed By.: Ovner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address)
Expiration Date: __ N/A
- 4. Identification of System: Reactor Core Isolation Coolant (RCIC)
S. (a) Applicable Construction Code: ASME Section III 19 86 Edition, No Addenda, N/A Code Case . ( (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Component Manufacturer Class Document Replaced, or Stamped Number Replacement- (Yes or No)
RCIC-CV-12CV Rockwell 2 93-1002 Replacement No RCIC-CV-12CV Upstream and N/A 2 93-1002 Replacement No Downstream Piping i i l
- 7. Description of Work: Replaced valve and associated pipinn.
- 8. Tests Conducted: Hydrostatic X Pneumatic ,
Nominal Operating Pressure ! Other Pressure 190 psi Test Temp. Ambient 'F
.- 16 psi (RCIC-CV-12CV Upstream Pipe)
NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, ) provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this i report.is' included on each sheet, and (3) each sheet la numbered and the number of sheets is recorded at the top of this form. l i
_ m __ __.- ._. Code Case N-308. " Documentation of Repairs and Replacements of I
- 9. Remarks:
Components in Nuclear Power Plants" is invoked through the use of Form NIS-2 for reportine. (Applicable Manufacturer's Data Reports to be Attached) i CERTIFICATE OF COMPLIANCE Ve certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) . Type Code Symbol Stamp: N/A Certification of Aut o zation No. N/A Expiration Date: N/A Signed: /. A Engineerine Mananer Date: 10-12-93 P ~ (OwnerfrOwner'sDesignee, 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 Nebraska and ! employed by Hartford Steam Boiler I & I Company- of Hartford, CT have inspected the components described in this Owner's Report during the period . __ January 1, 1992 to August 31. 1993 , and state'that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in ace'ordance 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 measured described in this Owner's 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. Inspector's Signature: 7 . e/J Commissions: NB #10352. Nebraska, N. I (National Board, State, Province, and Endorsements) Date: /60~hl~) $ l L l c n
FORM NIS-2 OWWER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI l'. Owner: Nebraska Public Power District Date: October 5. 1993 (Name) P.O. Box 499. Columbus. NE 68601 Sheet 43 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: El6 Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Hir.h Pressure Coolant Iniection (HPCI)
- 5. (a) Applicable Construction Code: ASME Section III 19-83 Edition, Summer 1983 Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear ument Replaced, or Stamped Component Manufacturer Class Replacement Number (Yes or No)-
HPCI-CV-20CV Jenkins Brothers 2 93-1002 Replaced No
- 7. Description of Work: Replaced valve.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X !
Other Pressure 100 psi Test Temp. Ambient *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings.may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
t 1
- 9. . Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants". is invoked throunh the use of Form NIS-2 for reportina.
(Applicable Manufacturer's Data Reports to be Attached) i a CERTIFICATE OF COMPLIANCE' We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Augha ization No. N/A Expiration Date: N/A Signed: h7 h 4 sc. Engineerina Mananer Date: 10-12-93 g '(OwnerdrOwner'sDesignee, Title) CERTIFICATE OF INSERVICE INSPECTION : t I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors'and the State or Province of Nebraska and . employed by Hartford Steam Boiler I & I Company of Hartford. CT have-inspected the components described in this Owner's Report during the period. . January 1. 1992 to August 31. 1993 , and state that to the best of.my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME l Code, Section XI. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measured described in this owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for nr.y personal injury or property damage ) or a loss of any kind arising from or connected with this inspection, Inspector's Signature: Y/ub 4 4-) ' Commissions: NB #10352. Nebraska. N, I (National Board, State, Province, and Endorsements) Date: /6-IV-93 1
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section II
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus NE 68601 Sheet 44 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One ,
(Name) P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No. , Job No. , Etc . ) ~3. Work Performed By: Owner __ Type Code Symbol Stamp: j l f6 Same Authorization Date: N/A
^ '***
Expiration Date: N/A !
- 4. Identification of System: Core Sprav (CS)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section X1 Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Class Document Replaced, or Stamped Component Manufacturer Replacement Number (Yes or No)
Piping Between CS-R -13R and 93-0751 Repaired N/A 2 No Inlet Flange Repaired nouve in pipe. I
- 7. Description of Work:
- 8. Tests Conducted: llydrostatic X Pneumatic Nominal Operating Pressure Other Pressure 780 psi Test Temp. Ambient 'F
' NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, , provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
.)
1
. . -l
.9 '. . Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throuch the use of Form NIS-2 for reportine. (Applicable Manufacturer's Data Reports to be Attached)- CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authgri ftionNo. N/A Expiration Date: N/A Signed: / Engineerinn Manager Date: 10-12 #~ ' '(Owner or wner's Designee, Title) CERTIFICATE OF INSERVICE INSPECTION i I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have l inspected the components described in this Owner's Report during the period-January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures t described in this Owner's 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 measured described in this Owner's 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. t
- Inspector's Signature: ta b.y L.> ;
4 Commissions: NB #10352. Nebraska'. N. I - (National Board, State, Province, and Endorsements) l Date: /o - /V-f ? t'
i FORM NIS-2 OUNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI ,
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 45 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One ,
(Name) P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No.,~Etc.) >
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address)
Expiration Date: N/A i
- 4. Identification of System: Core Spray (CS)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case 1
(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk ' Repaired ASME Code Name of Name of Nuclear Class Document Replaced, or Stamped Component Manufacturer Number Replacement (Yes or No)
CS-RV-13RV Consolidated 2 93-0751 Replaced No
- 7. Description of Work: Replaced valve. Inlet side was cut and rewelded.
- 8. Tests Conducted: Hydrostatic (1) Pneumatic Nominal Operating Pressure X Other (2) Pressure Inlet-307 psi Test Temp. Ambient *F (1) Inlet: 780 psig Temperature: Ambient (2) Outlet tested via open flow path test, NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of ,
sheets is recorded at the top of this form.
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of
~ Components in Nuclear Power Plants" is invoked throur.h the use of Form NIS-2 for reporting.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI, 1 (repair or replacement) Type Code Symbol Stamp: N/A Certification of Aut;honization No. N/A Expiration Date: N/A Signed: . . .
~
/
x-ta_LJ Engineering Manager Owner's Designee, Title) Date: 10-12-93 I
/ ~ (Owner l CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I company of Hartford. CT have inspected the components described in this owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my. knowledge and belief, the Owner has performed examinations and taken! corrective measures described in this Owner's 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 measured described in this owner's 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. Inspector's Signature: / Nbd Commissions: NB #10352. Nebraska < N. I (Nationn1 Board, State, Province, and Endorsements) Date: h -/9-fr
t FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPI.ACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 46 of 89 (Address)
- 2. Plant: Cooper Nuclear Station ' Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 _ N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.) 3, Work Performed By: Owner Type Code Symbol Stamp: NZ6 Same Authorization Date: N/A
^
Expiration Date: N/A 4 Identification of System: Core Spray (CS) i
- 5. (a) Applicable Construction Code: USAS B31.7 19_69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda ,
s
- 6. Identification of Components Repaired or Replaced and Replacement Components '
W rk Repaired ASME Code Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Replacement Number (Yes or No) Tioga 2 93-0751 Replaced No Disc arge Flanges 1
- 7. Description of Work: Replaced flances by welding.
- 8. Tests Conducted: Hydrostatic (1) Pneumatic Nominal Operating Pressure X (Inlet)
Other (2) Pressure Inlet-307 psi Test Temp. Ambient *F (1) Open flow path test performed in lieu of hydro. (2) Outlet Pressure Test: 58 psig Temperature: Ambient NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6.cn1 this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
1 l
~I
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements'of components in Nuclear Power Plants" is invoked throuth the use of Form NIS-2 for reportine.
.(Applicable Manufacturer's Data Reports to be Attached)
CERTIFICATE OF COMPLIANCE , e We certify that the statements made in the report are correct and this , replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A a Certification of Aut or za ion No. N/A Expiration Date: N/A Signed: M/k / / . tv4J Enzineerine Mananer Date: 10-12-93
// ~ (Owner Owner's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and. employed by Hartford Steam Boiler I & I company of Hartford. CT have inspected the components described in this Owner's Report during the period January 1. 1992 to _AuRust 31. 1993 , and state that to the best of my knowledge, and belief, the owner has performed examinations and taken corrective measures described in this Owner's Report in accordence 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 measured described in this owner's 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.
/ )
Inspector's Signature:Vle[ dam Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: /s N-f?
,y . . -
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPIACEMENTS As Required by the Provisions of the ASME Code Section XI 1 Owner: Nebraska Public Power District Date: October 5. 1993 (Name) P.O. Box 499. Columbus. NE 68601 Sheet 47 of 89 (Address) -2. Plant: Cooper Nucicar Station Unit: One (Name) P.O. Box 98. Brownv111e. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: EZ6 Same Authorization Date: N/A (Address) Expiration Date: N/A
- 4. Identification of System: Core Spray (CS)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Work Repaired ASME Code Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Replacement Number (Yes or No)
CS-RV-11RV Tioga 2 93-0751 Repl as.ed No Discharge Flanges 7, Description of Work: Replaced flances by weldine. : '8. Tests Conducted: liydrostatic (1) Pneumatic Nominal Operating Pressure -X (Inlet) Other (2) Pressure Inlet-300 psi -Test Temp. Ambient *F ., (1) Open flow path test performed in lieu of hydro. (2)' Outlet Pressure Test: 58 psig Temperature: Ambient NOTE: Supplemental sheets in the' form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throuth the use of Form NIS-2 for reportine.
(Applicable Manufacturer's Data Reports to be Attached)- CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authori ation No. N/A Expiration Date: N/A Signed: N Engineering ManaRer Date: 10-12-93
# (Ownero{0wner'sDesignee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge ' and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage e or a loss of any kind arising from or connected with this inspection. Inspector's Signature:C y / b b h , . A3 Commissions: NB #10352. Nebraska. N. I *
-(National Board, State, Province, and Endorsements)
Date: A* - !V- Y !
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI , -1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name) P.O. Box 499. Columbus. NE 68601 Sheet 48 of 89 (Address)
- 2. Plant: Cooper Nuclear Station -Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Werk Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements.
1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of W rk Repaired ASME Code Name of Nuclear Document Component Manufacturer Class Replaced, or Stamped !
Number Replacement (Yes or No) q RHR-RV-10RV ! Tioga 2 93-0751 Replaced No Discharge Flange l l
.i
- 7. Description of Work: Replaced flanne by weldinst.
- 8. Tests Conducted: Hydrostatic (1) Pneumatic Nominal Operating Pressure X (Inlet)
Other (2) Pressure Inlet-4 psi Test Temp. Ambient "F (1) Open flow path test performed in lieu of hydro. (2) Outlet Pressure Test: 58 psig Temperature: Ambient NOTE: Supplemental. sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in iteas 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the. top of this form. i
T
- 9. Remarks: Code case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throuch the use of Form NIS-2 for reportinn.
(Applicable Manufacturer's Data Reports to be Attached) P i CERTIFICATE OF COMPLIANGE l i We certify that the statements made in the report are correct and this ; replacement conforms to the rules of the ASME Code, Section1XI. (repair or replacement) -; Type Code Symbol Stamp: N/A Certification of Authorization No. N/A Expiration'Date: N/A Signed: 7f )hh a /o > Ennineering Mananer Date: 10-12-93 M' Owner'sDesignee, Title)
~ (Ownero{
f CERTIFICATE OF INSERVICE INSPECTION i i I, the undersigned, holding a valid commission issued by the National Board of , Boiler and Pressure Vessel Inspectors and the State or Province of Nebraska and employed by Hartford Steam Boiler I & I company of Hartford. CT have , inspected the components described in this Owner's Report during the period January 1. 1992 to Aunust 31. 1993 , and state that to the best of my knowledge _ s and belief, the Owner has performed examinations and taken corrective measures described in this owner's 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 measured described in this Owner's Report. Furthermore, neither the Inspector nor his ,
- i 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. !
Inspector's Signaturd y? u!/ t /D Commissions: NB #10352. Nebraska.- N. I (National Board, State, Province, and Endorsements) '
/'e- 6%f s Date:
e
- - - - - - - - - - m -s - - - - - - -w - - e
i FORM NIS-3 OUNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI '
- 1. lDwner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 49 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A , (Address) (Repair Orgainzation, P.O. No., Job No., Etc.) -
- 3. Work Performed By: Owner Type Code Symbol Stamp: H/6 Same Authorization Date: N/A (Address) Expiration Date: N/A
~4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B31,7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components '
V rk Repaired ASME Code' l Name of Name of Nuclear Document Replaced, or Stamped Component. Manufacturer Class Replacement Number (Yes or No) Tioga 2 93-0751 Replaced No Dis harge Plange RHR-RV-13RV Tioga 2 93-0751 Replaced No-Discharge Flange
- 7. Description of Work: Replaced flannes by welding.
]
i
- 8. Tests Conducted: Hydrostatic (1) Pneumatic i Nominal Operating Pressure X (Inlet) .i Other (2) Pressure Inlet-6 psi Test Temp. Ambient _*F
~ ~
(1) Open flot path test performed in lieu of hydro. ; (2) Outlet Pressure ~ Test: 58 psig ={ Temperature: Ambient l NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. 1
t
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plantr,' is invoked throuch the use of Form NIS 2 for reportine.
(Applicable Manufacturer's Data Reports to be Attached) , CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this , replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Aut!;or za ion No, N/A Expiration Date: N/A Signed: oiA Engineering Mananer Date: 10-12-93 M' (Owner (Owner'sDesignee, Title) CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have , inspected the components described in this Owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measutor described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. I t By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measured described in this Owner's Report. Furthermore, neither the Inspector nor his i 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. , Inspector's Signature: q/_ /M)'l
/ aM Commissions: NB #10352. Nebraska. N. I (National Board, State. Province, and Endorsements)
Date: // - /f'- I_7 ; W
i FORM NIS-2 OWNER'S REPORT FOR REPAIRS-OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 50 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No . , J ob No . , Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address) Expiration Date: N/A 4 Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components. ,
W rk Repaired ASME Code I Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No) ; Tioga 2 93-0751 Replaced No Di a e F1 p ; J
- 7. Description of Work: Replaced flante by weldinn.
- 8. Tests Conducted: Hydrostatic (1) Pneumatic .
Nominal Operating Pressure X (Inlet) 'l other (2) Pressure Inlet-183 psi Test Temp. Ambient 'F (1) Open flow path test performed in lieu of hydro. (2) Outlet Pressure Test: 58 psig Temperature: Ambient l NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, I
- provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. !
- 9. ' Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throuch the use of Form NIS-2 for
- reportine.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Au.tho iz tion No. N/A Expiration Date: N/A Signed; h a- imWL Engineering Mananer Date: 10-12-93
/ (Owner (frOwner'sDesignee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and.taken corrective measures described in this owner's 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 measured described in this Owner's 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.
, s Inspector's Signature':h. U2A3 ,
i Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: /d-//'l3
i FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section II l
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 51 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR) j
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Nuclear rk Repaired ASME Code Name of Document Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No)
RRR-RV-14RV Discharge Flanges Tioga 2 93-0751 Replaced No P
- 7. Description of Work: Replaced flantes by weldine. ,
- 8. Tests Conducted: Hydrostatic (1) Pneumatic >
Nominal Operating Pressure X (Inlet) 1 Other (2) Pressure Inlet-185 psi Test Temp. Ambient *F (1) Open flow path test performed in lieu of hydro. (2) Outlet Pressure Test: 58 psig Temperature: Ambient ; NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, 1 provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of. . sheets is recorded at the top of this form. j
.9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of
.r Components in Nuclear Power Plants" is invoked throuch the use of Form NIS-2 for reporting. ,
(Applicable Manufacturer's Data Reports to be Attached). CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authori ation No. N/A Expiration Date: N/A Signed: 3 a Engineerinz Manager Date: 10-12-93 .,
/~ ~(Ownerorgowner'sDesignee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and , employed by Hartford Steam Boiler I & I Company of Hartford. CT have-inspected the components described in this Owner's Report during_the period January 1. 1992 to August 31. 1993 , and state.that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures o described in this Owner's 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 measured described in this Owner's 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. ! Inspector's Signature k 7 / LM Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) > Date: /C - bV f!
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the'ASME Code Section II
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 52 of 89 (Address)
- 2. Plant: Cooner Nuclear Station Unit: One (Name) >
P.O. Box 98. Brownv111e. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A ,
(Address) Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR) i
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components -
rk Repaired .ASME Code Name of Name of Nuclear Document Replaced, or Stamped Componeat Manufacturer Class Replacement Number (Yes or No) Dis "; ges Tioga 2 93-0751 Replaced No
- 7. Description of Work: Replaced flances by weldine.
- 8. Tests Conducted: Hydrostatic (1) Pneumatic :
Nominal Operating Pressure X (Inlet) Other (2) Pressure Inlet-60 psi Test Temp. Ambient "F i (1) Open flow path test and hydro test; 675 psig, temperature: ambient. (2) Outlet Pressure Test: 58 psig , Temperature: Ambient NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. t v _ _ .
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of components in Nuclear Power Plants" is invoked throuth the use of Form NIS-2 for reportinn.
(Applicable Manufacturer's Data Reports to be Attached) T CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this :; replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Au ho.ization No. N/A Expiration Date: N/A Signed: L Engineerinn ManaRer Date: 10-12-93 M' (Ownerej Owner's Designee, Title) s CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I company of Hartford. CT have i inspected the components described in this Owner's Report during the period January 1. 1992 to _ August 31. 1993 , and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures described in this owner's Report in accordance with the requirements of the ASME-Code, Section XI. L By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measured described in this owner's 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. p Inspector's Signature: L//w! A' i r Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Da t'e : '#" /6 85 [ I t I
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 53 of 89 , (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name) '
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A '
(Address) Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No)
Dis r F1 ges Tioga 2 93-0751 Replaced No
- 7. Description of Work: Replaced flances by weldinn.
- 8. Tests Conducted: Hydrostatic (1) Pneumatic Nominal Operating Pressure X (Inlet)
Other (2) Pressure Inlet-50 psi Test Temp. Ambient 'F (1) Open flow path test performed in lieu of hydro. (2) Outlet Pressure Test: 58 psig Temperature: Ambient NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
t
- 9. Remarks: Code Cane N-308. " Documentation of Repairs and Replacements of components in Nuclear Power Plants" is invoked throuch the use of Form NIS-2 for reportine.
(Applicable Manufacturer's Data Reports to be Attached) t CERTIFICATE OF COMPLIANCE Ve certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authorization No. N/A Expiration Date: N/A Signed: , z. Engineering Manager Date: 10-12-93
# [0wner o Owner's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and ; employed by Hartford Steam Boiler I & ! Company of Hartford. CT have inspected the components described in this Owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described-in this Owner's Report in accordance with -the requirements of the ASME Code, Section XI. By signing this certificate, reither the Inspector nor his employer makes any. k warranty, expressed or implied, concerning the examinations and corrective measured < described in this owner's 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, i .? Inspector's Signature: U;M Md'w f Commissions: NB #10352. Nebraska. N. I (National Board, State. Province, and Endorsements) Date: /d-/</-f) i
. ~ . ._. . _ _ _
FORM NIS-2 OSNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 54 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One ,
(Name) P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No . , Job No. . . Etc . )
- 3. Work Performed By: Owner Type Code Symbol Stamp: H/6 Same Authorization Date: N/A (Address) Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, i
No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired 'ASME Code Name c' Name of Nuclear Replaced, or Stamped ument Component Manufacturer Class Number Replacement (Yes or No)
Tioga 2 93-0751 Replaced No Dis harge Flange
- 7. Description of Work: Replaced flanne by welding.
- 8. Tests Conducted: Hydrostatic (1) Pneumatic Nominal Operating Pressure X (Inlet)
Other (2) Pressure Inlet-150 psi Test Temp. Ambient *F (1) Open flow path test performed in lieu of hydro. (2) Outlet Pressure Test: 58 psig Temperature: Ambient NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used,
. provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
F
- 9. Remarks: Code Case N-308. " Documentation 'of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throunh the use of Form NIS-2 for i reportinc.
(Applicable Manufacturer's Data Reports to be Attached) > CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A ' Certification of Authori at on No. N/A Expiration Date: N/A Signed: k k) 2- Shrd. Enzineerinn Manazer Date: 10-12-93
/ 70wnero[ Owner's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford.'CT have inspected the components described in this Owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured. described in this Owner's 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. Inspector's Signature: uAd ' Commissions: NB #10352. Nebraska. N. I 1 (National Board, State., Province, and Endorsements) Date: 'dfV-)5f 'I
FORM NIS-2 OSNER'S REPORT FOR REPAIRS OR P2 PLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 55 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type. Code Symbol Stamp: HZ6 Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B31.7 19_69_ Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of W rk Repaired ASME Code Name of Nuclear Component Manufacturer Class cument Replaced, or Stamped Number Replacement (Yes or No)'
RHR-RV-19RV Tioga 2 93-0751 Replaced No Discharge Flange Dis rg 1 ges Ti ga 2 93-0751 Replaced No
- 7. Description of Work: Replaced flannes by welding.
- 8. Tests Conducted: Hydrostatic 01 ) Pneumatic Nominal Operating Pressure X (Inlet)
Other (2) Pressure Inlet-60 psi Test Temp. Ambient *F (1) Open flow path test performed in lieu of hydro. (2) Outlet Pressure Test: 58 psig Temperature: Ambient NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at- the t op of- this form.
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked through the use of Form NIS-2 for reporting.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Aut or zation No. N/A Expiration Date: N/A Signed: - r Engineering Mananer Date: 10-12-93
/
(Owneror) Owner's Designee, Title) l CERTIFICATE OF INSERVICE INSPECTION l I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Nebraska and l employed by Hartford Steam Boiler I & I company of Hartford, CT have ; inspected the components described in this Owner's Report during the period January 1. 1992 to August 31, 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures ! described in this Owner's. 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 measured described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable. in any manner for any personal injury or property damage l or a loss of any kind arising from or connected with this inspection. Inspector's Signature W & d<~J Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: JO 'V f!
I i FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name) ,
P.O. Box 499. Columbus. NE 68601 Sheet 56 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: H/A Same Authorization Date: N/A (Address) Expiration Date: N/A
- 4. Identification of System: __ Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Replaced, or Stamped Document Component Manufacturer Class Replacement Number (Yes or No)
Tioga 2 93-0751 Replaced No Dis r F nges i
- 7. Description of Work: Replaced flances by weldine.
- 8. Tests Conducted: Hydrostatic (1) Pneumatic Nominal Operating Pressure X (Inlet)
Other (2) Pressure Inlet-180 psi Test Temp. Ambient 'F (1) Open flow path test performed.in lieu of hydro. (2) Outlet Pressure Test: 58 psig . Temperature: Ambient NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be.used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this-report is included on each sheet, and (3) each sheet is' numbered and the number of sheets is recorded at the top of this form. i
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants". is invoked throunh the use of Form NIS-2 for reportinn.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Autigor ation No. N/A Expiration Date: N/A , Signed:
/
I e, .M6 Engineering _ Manager Date: 10-12-93 (Owner or wner's Designee, Title) CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I company of Hartford CT have inspected the components described in this owner's Report during the period ) January 1. 1992 to Aunust 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures ~ , described in this Owner's Report in accordance with the requirementsoof the'ASME r Code, Section XI. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations'and corrective measured described in this Owner's Re~ port, 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. Inspector's Signature:' Wu . _ s' Commissions: NB #10352. Nebraska, N. I (National Board, State, Province, and Endorsements) Dato: se - / V G_1 e- -
, + m m _ - _ _ _ m _ +_. _ e ..w---- - - e-- r ? 4 +-r
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI ,
'1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 57 of 89 (Address) ,
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/n (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: H/6 Same Authorization Date: N/A (Address) Expiration Date: N/A
- 4. Identification of System: Primary Containment (PC)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements i 1980, Winter 1981 Addenda .
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code _
Name of Name of Nuclear , Component Manufacturer Class Document Replaced, or Stamped Number Replacement (Yes or No) Flanges on Pipe Spool Piece Between Replaced Tioga 2 93-0751 No Penetration X-213A ' and PC-V-61
- 7. Description of Work: Replaced flances by weldinn.
- 8. Tests Conducted: Hydrostatic (1) Pneumatic .
Nominal Operating Pressure X (Downstream of PC-V-61). Other (2) Pressure X-6.25 psi Test Temp. Ambient *F r (1) Pressure: 91 psig Temperature: Ambient (2) Flange Pressure Tests: 58 psig Temperature: Ambient NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through_6 on this-report is included on.each sheet, and (3) each sheet is numbered and the_ number of-sheets is recorded at the top of this form.
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throuch the use of Form NIS-2 for reportinR.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE Ve certify that the statements made in the report are correct and this , replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authori ation No. N/A Expiration Date: N/A Signed: 0- Engineering Mananer Date: 10-12-93 f '(Owner o 3wner's Designee, Title) CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this Owner's Report during the. period January 1. 1992 to AuRust 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this owner's 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' measured described in this owner's 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. Inspector's Signature: Ne/ .-n /id Commissions: NB #10352. Nebraska N. I (National Board, Stete, Province,.and Endorsements) Date: A46/f
Y FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEME23TS As Required by the Provisions of the ASME Code Section XI o
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 58 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name) :
t P.O. Box 98. Brownville. NE 68321 N/A ! (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: E/6 Same Authorization Date: N/A
(^ ' "" Expiration Date: N/A 4 Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired .ASME Code Name of Name of Nuclear Document Replaced, or Stamped Class Corapanent Manufacturer Number Replacement -(Yes or No)
RH-S22 ITT Grinnell 2 93-0970 Replacement No
- 7. Description of Work: Replaced reservoir clamp bolts and nuts. 1 1
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating. Pressure other N/A Pressure psi Test Temp. 'F
- NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, . provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this i report is included on each sheet, and (3) each sheet is numbered and the number of j sheets is recorded at the top of this form. -
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of l Components in Nuclear Power Plants" is invoked throuch the use of Form NIS-2 for reporting.
(Applicable Manufacturer's Data Reports to be Attached) 1 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certificaticn of Authorizptiop No. N/A Expiration Date: N/A
%9 / (I Signed: V/\ a si > < Le Engineerinn Mananer Date: 10-12-93
/ (Owner or dener's Designee, Title)
M CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I company of Hartford. CT have inspected the components described in this Owner's Report during the period January 1. 1992 to Aunust 31. 1993 , and state that to-the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures , described in this owner's 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 measured described in this owner's 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. Inspector's Signature: z/ a.4/C , Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) ! Date: /o -h/- 9 z
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
?
.l. Owner: Nebraska Public Power District Date: October 5. 1993 (Name) P.O. Box 499. Columbus. NE 68601 Sheet 59 of 89 I (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. ~ No.,-Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: E/6 Same Authorization Date: N/A-(Address) Expiration Date: N/A
- 4. Identification of System: Core Spray (CS)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, i No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Class Document Replaced, or Stamped Component Manufacturer Replacement Number (Yes or No)
CS-P-B Byron Jackson 2 93-0875 Repaired No
- 7. Description of Work: Indication on pump base was tround out and welded.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other N/A P. essure psi Test Temp. *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on-this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
- 9. Remarks: Code Case N-308. " Documentation of Renairs and Replacements of Components in Nuclear Power Plants" is invoked throur.h the use of Form NIS-2 for reportinn.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair' conforms to the rules of the ASME Code, Section XI. (repair or replacement) , Type Code Symbol Stamp: N/A Certification of Auth,ori ation No. N/A Expiration Date: N/A Signed: ,o Engineerine ManaRer Date: 10-12-93 ! [/ '(Owner o Owner's Designee, Title) CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this owner's Report during the period January 1. 1992 to -August 31, 1993 , and state that to the best of my knowledge and belief, the Dwner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this owner's 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. Inspector's Signature: N-<a - AJ Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: / / - l V- 9:t I
.5 i
FORM NIS-3 05NER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 60 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P,0. Box 98. Brownville. NE 68321 N/A (Address) (Repair-Orgainzation, P.O. No . , Job No . , Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A' (Address)
Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Casu
-(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components-W rk Repaired ASME Code Name of Name of Nuclear umen ep a d, or Stamped Component Manufacturer Class Rcplacement Number (Yes or No) ,
RHR-RO-250 N/A 2 93-0292 Replaced No RHR-RO-284 N/A 2 93-0292 Replaced No >
- 17. Description of Work: Restricting orifices were replaced. ;
- 8. Tests conducted: Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 200 psi Test Temp. Ambient *F
. NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size.is 8-1/2" x 11", (2) information in items 1 through 6 on this ,
report is included on'each sheet, and (3) each sheet is numbered and the number of ! sheets is recorded at the top of this form.
y l
- 9. -Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Corponents in Nuclear Power Plants" is invoked throuch the use of Form NIS-2 for reportinn.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI, (repair or replacement) Type Code Symbol Stamp: N/A Certification of Aut orization No. N/A Expiration Date: N/A Signed: 9 [_r Ennineering Manager Date: 10-12-93
"'(Ownero{0wner'sDesignee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford, CT have inspected the components described in this Owner's Report during the period January 1. 1992 to Aunust 31, 1993 , and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this owner's 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. Inspector's Signature: C/b ./ #O Commissions: NB #10352. Nebraska , JL I (National Board, State, Province, and Endorsements) Date: x - / 6 fr
i
'l FORM NIS-2 OTENER'S REPORT FOR REPAIRS OR REPLACEMENTS ]
As Required by the Provisions of the ASME Code Section XI l i
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name) l 1
P.O. Box 499. Calumbus. NE 68601 Sheet 61 of 89 j (Address) , i
- 2. Plant: Cooper Nuclear Station Unit: One !
(Name) I P.O. Box 98. Brownville. NE 68321 N/A , (Address) (Repair Orgainzation, P.O. No., Job No . Etc.) ;
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A j Same Authorization Date: N/A ,
(Address) Expiration Date: N/A 1
- 4. Identification of System: Residual Heat Removal (RHR) ;
- 5. (a) Applicable Construction Code: ASME Section III 19 86 Edition, l i
No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements , 1980, Winter 1981 Addenda l 1
- 6. Identification of Components Repaired or Replaced and Replacement Components Work Repaired ASME Code Name of Name of Nuclear Stamped Document Replaced, or Component Manufacturer Class Replacement Number (Yes or No)
RHR-MOV-M027A (1) Anchor / Darling 1 93-0292 Replacement No RHR-MOV-M027A (2) Anchor / Darling 1 93-0292 Replacement No i
- 7. Description of Work: (1) Replaced disc. stem, and seat rinn. (2) Replaced disc and stem a second time.
- 8. Tests Conducted: Hydrostatic Pneumatic ,
Nominal Operating Pressure X i Other Pressure 200 psi Test Temp. Ambient *F ; J NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in itea<s 1 through 6 on this ' report is included on each sheet, and (3) each sheet is nuesbered and the number of sheets is recorded at the top of this form. I 1 l j
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked through the use of Form NIS-2 for reportine.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Author Lat on No. N/A Expiration Date: N/A Signed: . N u<lu Ennineerinz Mananer Date: 10-12-93
// '(Owner or pwner's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and' employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this owner's Report during the period January 1. 1992 to Aunust 31. 1993 , and state that to the best of my knowledge ! and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this Owner's 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.
, I Inspector's Signature:
M M ~' . Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: M ^@H
FORM NIS-2 OUNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power Di. strict Date: October 5. 1993 f (Name).
P.O. Box 499. Columbus. NE 68601 Sheet 62 of 89 (Address) -2. Plant: Cooper Nuclear Station Unit: One (Name) P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: F/A Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR) t
- 5. (a) Applicable Construction Code: USAS B16.5 19 68 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear W rk Repaired ASME Code Document Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No)
RHR-MOV-M027A Anchor / Darling 1 93-0292 Repaired No
- 7. Description of Work: Ground out de fects in the sent rinn pocket and trim retaininn nroove. Machined sealine surface of honnet and back sent area. Added a weld to bottom of seat rinn. Scratches in pressure seal area on valve body and bonnet were machined / welded.
8' Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 200 psi Test Temp, Ambient "F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) infor tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
t
- 9. Remarks: Code Case N-30'8. " Documentation of Repairs and Replacements of
' Components in Nuclear Power Plants" is invoked throuth the use of Form NIS-2 for reportina.
(Applicable Manufacturer's Data Reports to be Attached) i CERTIFICATE OF COMPLIANCE ! r We certify that the statements made in the report are correct and this repair conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stam,i: N/A Certification of Aut or zation No. N/A Expiration Date: N/A Signed: , , / Engineerina Manager Date: 10-12-93 - V ~(Ownergy,0wner'sDesignee, Title) , CERTIFICATE OF INSERVICE 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' Nebraska and employed by. Hartford Steam Boiler I 6'I Company of Hartford.' CT have - inspected the components described in this owner's Report during the period r January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this Owner's Report. Furthermore, neither th e 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. ! Inspector's Signature [ -u M4 - ^ Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) i 5 Date: 'O - IV - 93
._J _ _ . _ _ _ _ _ _ _ , , _ , _ _ _ _ _ _ _ _ _ _ _ _ __+ m _._. _ . _ e.
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 63 of 89' (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: E/6 Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B16.5 19_68_ Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section X1 Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear V rk Repaired ASME Code Document Replaced, or Stamped Component Manufacturer Class Number Replacement (YesRor No)
RHR-V-132 Dragon 2 93-0855 Replaced No Pipin U stream of N/A 2 93-0855 Replaced No
- 7. Description of Work: Replaced pipinn and valve.
- 8. Tests Conducted: Hydrostatic X Pneumatic Nominal Operating Pressure Other Pressure 565 psi Test Temp. Ambient *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
._ J
. - ~ -. .
-\
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throunh the use of Form NIS-2 for ;
reporting. (Applicable Manufacturer's Data Reports to be Attached) , I ; CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. , (repair or replacement) [ Type Code Symbol Stamp: N/A i Certification of Authoris tion No. N/A Expiration Date: N/A-Signed: 5 5)$ (4 / Engineerinn Manager Date: 10-12-93
/ (Owneror(pwner'sDesignee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and ' employed by Hartford Steam Boiler I & I company of Hartford. CT ~have , inspected the components described in this owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge
- and belief, the owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this Owner's Report. Furthermore, neither the Inspector nor his ; employer shall be liable in any manner for any personal injury or property damage 9 or a loss of any kind arising from or connected with this inspection. Inspector's Signature: -rb.) Commissions: NB #10352. Nebraska. N. I , (National Board, State, Province, and Endorsements) Date: /6 -/ V- Lt l' l
O, 1 l 1 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS j As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 64 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Core Spray (CS)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear W rk Repaired ASME Code
"""*" *E"** #- ""E" Component Manufacturer Class Number Replacement (Yes or No)
CS-H205 N/A 2 93-0730 Replacement No
- 7. Description of Work: Replaced cotter pin on support.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other N/A Pressure psi Test Temp. *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
~
-f 1
I
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Pow 3r Plants" is invoked throunh the use of Form NIS-2 for reporting.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE
.e We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI.
(repair or replacement) Type Code Symbol Stamp: N/A Certification of Autho ization No. _N/A Expiration Date: N/A Signed; h, N Engineering Manager Date: 10-12-93
/ ~ (ownerpowner'sDesignee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and , employed by Hartford Steam Boiler I & I company of Hartford.'CT have inspected the components described in this owner's Report during the period January 1. 1992 to Aunust 31, 1993 , and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures , described in this Owner's 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 measured described in this owner's 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. Inspector's Signature: /b j oA/ Commissions: NB #10352 Nebraska, N. I (National Board, State. Province, and Endorsements) Date: /H N/~ F >
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI-1, Owner: Nebraska Public Power District Date: October 5. 1993 (Name) P.O. Box 499. Columbus. NE 68601 Sheet 65 of 89 (Address)
- 2. Plant: Cooper Nuclear Station ' Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address) N/A Expiration Date:
- 4. Identification of System. Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Class ument Replaced, or Stamped Component Manufacturer Number Replacement (Yes or No)
RB-H42A Grinnell 2 93-0105 Replacement No
- 7. Description of Work: Replaced load stud. ,
l 1 l
- 8. Tests Conducted: Hydrostatic Pneumatic j Nominal Operating Pressure i Other N/A Pressure psi Test Temp. *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided-(1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throurh the use of Fonn NIS-2 for reportinn.
(Applicable Manufacturer's Data Reports'to be Attached) 4 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) ' Type Code Symbol Stamp: N/A Certification of Authocization No. N/A Expiration Date: N/A Signed: - r. Enzineering Mananer Date: 10-12-93 JI ~ (Owner Owner's Designee, Title) CZPTIFICATE OF INSERVICE 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 Nebraska and , employed by Hartford Stram Boiler I & I Company of Hartford. CT have inspected the componente described in this 0-cer's Report during the period . January 1, 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this Owner's 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.
Inspector's Signature: A/.2 o/M Commissions: NB #10352. Nebraska . N. I (National Board, State, Province, and Endorsements) Date: /O- ///- f ? s __ _ _ _ _ _ _ _ ~
7 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 66 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job'No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: Ef6 Same Authorization Date: N/A
^ ** '
Expiration Date: N/A
.4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda ,
.6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Nuclear Name of Name of Document Replaced, or Stamped Component Manufacturer Class Replacement Number (Yes or No)
RH-S78B Grinnell 2 92-3367 Replaced No RH SS9 Crinnell 2 92-3367 Replaced No RH-S52 Grinnell 2 92-3367 Replaced No-
- 7. Description of Work: Replaced snubbers listed.
t
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure other N/A Pressure psi Test Temp. 'F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11",-(2) information in items 1 through 6 on this report is' included on each sheet, and (3) each sheet is numbered and the. number of sheets is recorded at the top of this form.
i;s i
- 9. ' Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throuth the use of Form NIS-2 for reportina.
(Applicable Manufacturer's Data Reports to be Attached) t CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Aut ogiza ion No. N/A Expiration Date: N/A Signed: es'< Engineerine Manager Date: 10-12-93
// ~ (Owner o Owner's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this Owner's Report during.the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this owner's 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. Inspector's Signature , bu4.J Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements)- Date: /41- /ll' f3
g ! FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 67 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No . , Job No . , Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A' (Address) Expiration Date: N/A
- 4. Identification of System: Main Steam (MS)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, i No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Document Replaced, or . Stamped Component Manufacturer Class Number Replacement (Yes or No)
MS-S7A Grinnell 2 92-3367 Replaced No MS-S81 Grinnell 2 92-3367 Replaced No MS-S84 Grinnell 2 92-3367 Replaced No MS-S84B & R Grinnell 2 92-3367 Replaced No MS-S23 Grinnell 2 92-3367 Replaced No
-I
- 7. Description of Work: Replaced snubbers listed.
l I
- 8. Tests Conducted: Hydrostatic Pneumatic )
Nominal Operating Pressure l Other N/A Pressure psi Test Temp. *F j NOTE:-Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form, i l
- 9. Remarks: Code Case N-308. '" Documentation of Repairs and Replacements of Components in Nuclear-Power Plants". is invoked throuph the use of Form NIS-2 for l
reportinn. (Applicable Manufacturer's Data Reports to be Attached)- CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conform.= to the rules of the ASME Code, Section XI.. (repair or replacement) j Type Code Symbol Stamp: N/A Certification of Authorization No. N/A Expiration Date: N/A Signed: ( Engineering Mananer Date: 10-12-93
/ IOwner or wner's Designee, Title) i CERTIFICATE OF INSERVICE 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_. Nebraska and employed by Hartford Steam Boiler I & I company of Hartford. CT have inspected the components described in this Owner's Report during the period.
)
January 1. 1992 to August 31, 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this owner's Report in accordance with the requirements of the A9ME Code, Section XI. i By signin6 this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measured ' described in this Owner's 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. Inspector's Signature:
- X-Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements)
Date: I'd - M'~9 Y r r
FORM NIS-2 OVNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1; Owner: Nebraska Public Power District Date: October 5. 1993 (Name) P.O. Box 499. Columbus. NE 68601 Sheet 68 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One l (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. , No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: H/A Same Authorization Date: N/A (Address) Expiration Date: N/A
- 4. Identification of System: Reactor Water Cleanup (RWCU)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements-1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer- Class Number Replacement (Yes or No)
CU-S89 Grinnell 2 92-3367 Replaced No
- 7. Description of Work: Replaced snubber.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other N/A Pressure psi Test Temp. "F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on.this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
a
~9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements 'of- ; components in Nuclear Power Plants" is invoked throuch the use of Form NIS-2 for , reporting. (Applicable Manufacturer's Data Re;.>rts to be Attached) CERTIFICATE OF COMPLIANCE
+
We certify that the statements made in the report are correct and this-replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authorization No. N/A Expiration Date: N/A Signed: ,. Ennincerina Mananer Date: 10-12-93
/ (owner r Owner's Designee, Title) i CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province off Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described. in this Owner's Report during the . period January 1. 1992 tu August 31. 1993 , and state that to'the best of my knowledge and belief, the Owner has performed examinations'and taken corrective measures-described in this Owner's 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' measured described in this Owner's 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. Inspector's Signature: cM*# I Commissions: NB #10352. Nebraska. N, I (National Board, State, Province, and Endorsements) Date: /0-/Y-O i
FORM NIS-2 OWNER'S REPORT FOR REPAIRS.OR REPLACEMENTS An' Required by the Provisions of the ASME Code Section XI.
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 69 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: Nf6 Same Authorization Date: N/A (Address) N/A Expiration Date:
- 4. Identification of System: Core Spray (CS)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, ,
No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980. Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired- ASME Code Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Replacement Number (Yes or No)
CS-S6 Grinnell 2 92-3367' ' Replaced No-t
- 7. Description of Work: Replaced snubber.
- 8. Tests Conducted: Hydrostatic Pneumatic ,
Nominal Operating Pressure Other N/A Pressure psi Test Temp. *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, + provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this > report is included on each sheet, and (3) each sheet is numbered and-the number of~ sheets is recorded at the top of this form.
- 9. Remarks: Code-Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throuch the use of Form NIS-2 for reportine.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) _ Type Code Symbol Stamp: N/A Certification of Author zation No. N/A Expiration Dato: N/A Signed: . #g a,
- o. _ _G Engineering Mananer Date: 10-12-93
/ '(Owner o Owner's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I company of Hartford. CT have inspected the components described in this Owner's Report during the period January 1. 1992 to _AuRust 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this Owner's 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. Inspector's Signature: uI Au3
& i Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements)
Date: dNV-93
.=
FORM NIS-2 CVNER'S REPORT FOR REPAIRS OR REPLACEMElffS As Required by the Provisions of the ASME Code Section XI
. 1, owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 70 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: H/6 Same Authorization Date: N/A (Address) N/A Expiration Date:
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: ASME Section III 19 83 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda 6, Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No)
RH S65A Pacific Scientific 2 92-3388 Replaced No RH-S14 Pacific Scientific 1 92-3388 Replaced No
- 7. Description of Work: Replaced snubbers listed.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure other N/A Pressure psi Test Temp. *F i NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2)'information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
- - . . ~ . . . . ..
'l 9, Remarks: Code case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throunh the use of Form NIR-2 for reportinn.
(Applicable Manufacturer's Data Reports to be Attached) P' CERTIFICATE OF COMPLIANCE i We certify that the statements made in the report are correct and this ; replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) 1 Type Code Symbol Stamp: N/A-Certification of Authgr ation No. N/A Expiration Date: N/A Signed:
/
u n( y> /f,. -f-v 1.< ' , Engineerinn Manager Date: 10-12-93 i (Ownerog[0wner's Designee, Title) l 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 Nebraska and employed by Hartford Steam Boiler I & I company of Hartford CT have inspected the components described in this Owner's Report during the period January 1. 1992 to _ August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements ,0f 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 measured described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage 1 or a loss of any kind arising from or connected with this inspection. I Inspector'sSignature:j /' ! Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) i Date: M' M O t I L
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS I As Required by the Provisions of the ASME Code Section XI .l 'l-. Owner: Nebraska Public Power District Date: October 5. 1993 ~1 (Name) P.O. Box 499. Columbus. NE 68601 Sheet 71 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation,-P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: H/6 Same Authorization Date: N/A Expiration Date: N/A
- 4. .dentification of System: Main Steam (MS)
- 5. (a) Applicable Construction Code: ASME Section III 19 83 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear W rk Repaired ASME Code Component Manufacturer Class Document Replaced, or Stamped Number Replacement (Yes or No)
MS-S149B Grinnell 1 92-3388 Replaced 'No VR-S88 Grinnell 1 92-3388 Replaced No SS-B3 Grinnell 1 92-3388 Replaced No VR-58-12-Y Grinnell 1 92-3388 Replaced No VR-H64D Crinnell 1 93-3388 Replaced No
- 7. Description of Work: Replaced snubbers listed.
'8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other N/A Pressure psi Test Temp. *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, ; provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 onLthis report is. included on each sheet, and (3)-each sheet is numbered and the number of sheets is recorded at the top of this form.
9, Remarks: Code' Case N-308. " Documentation of Renairs and Replacements of Components in Nuclear Power Plants" is invoked through the use of Form NIS-2 for reportina. (Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement -conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Aut or zation No. N/A Expiration Date: N/A Sigried: . / Engineerinn Mananer Date: 10-12-93
/ ' (Ownero[ Owner'sDesignee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this Owner's Report during the period ; January 1. 1992 to Aunust 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this Owner's 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.
, / ?
Inspector's Signature: 9/ Swd Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: & /6 f/
i FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI ,
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 72 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: Ef6 Same Authorization Date: N/A (Address) N/A Expiration Date:
- 4. Identification of System: Main Steam (MS)
- 5. (a) Applicable Construction Code: ASME Section III 19 83 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Replaced, or cument Stamped .
Component Manufacturer Class Number Replacement (Yes or No) > VR-S70B Grinnell 1 92-3388 Replaced 'No VR-S10 Grinnell 1 92-3388 Replaced No VR-S4 Grinnell 1 92-3388 Replaced No BS-SIB & R Grinnell 2 92-3388 Replaced No VR-S7B Grinnell 1 92-3388 Replaced No
- 7. Description of Work: Replaced snubbers listed.
l
.l i
- 8. Tests Conducted: 11ydrostatic Pneumatic )
Nominal Operating Pressure ! Other N/A Pressure psi Test Temp. *F ,l NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this l report is included on each sheet, and (3) each sheet is numbered and the number of ) sheets is recorded at the top of this form. ! l l
- 9. . Remarks: Code Case N 308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throuth the use of Form NIS-2 for reporting.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Authpr ation No. N/A Expiration Date: N/A Signed: , / Engineerina Manager Date: 10-12-93
# '(Ownergowner'sDesignee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska 'and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this Owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures described in this owner's Report in accordance with the requirements of the ASME Co de ', Section XI. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measured-described in this Owner's 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.
, , t Inspector's Signature: '5I d/M Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements)
Date: /G' /Y ?$ i i
- - . - . _ - - - - _ - - ~ . . _ -
9
FORM-NIS-2 OUNER'S REPORT.FOR REPAIRS OR REPLACEMENTS' As Required by the Provisions e,f the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 73 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address) N/A Expiration Date:
- 4. Identification of System: Reactor Feedwater (RF) '
- 5. (a) Applicable Construction Code: ASME Section III 19 83 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired .ASME Code Name of Name of Nuclear ument Replaced, or Stamped Component Manufacturer Class Replacement Number (Yes or No)
RF-S14 Grinnell 1 92-3388 Replaced No RF S17 Grinnell 1 92-3388 Replaced No
- 7. Description of Work: Replaced snubbers listed.
l l 1
- 8. Tests Conducted: Hydrostatic Pneumatic j Nominal Operating Pressure !
Other N/A Pressure 1,s i Test Temp. *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, j provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this j report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. i
( _-
-9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throunh the use of Form NIS-2 for reportinn.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We_ certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,-Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Auth ri ation No. N/A Expiration Date: N/A A Signed: 7f s- e I) Enzineering Manager Date: 10-12-93 J7 (Owner or bwner's Designee, Title) l CERTIFICATE OF INSERVICE 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 Nebraska and employed by. Hartford Steam Boiler I & I Company of Hartford CT have inspected the components described in this Owner's Report during the period January 1. 1992 to August 31. 1993 ,- and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this Owner's 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. Inspector's Signature: N ElMu Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: /4-6'f7
7 FORM NIS-2 OL*NER'S REPORT FOR REPAYRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 74 of 89 (Address)
- 2. Plant; Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: H/6 Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Reactor Recirculation (RR)
- 5. (a) Applicable Construction Code: ASME Section III 19 83 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear rk Repaired ASME Code Component Manufacturer Class Document Replaced, or Stamped Number Replacement (Yes or No)
SS-1A Crinnell 1 92-3388 Replaced No SS-5B Grinnell 1 92-3388 Replaced- No SS-2A Crinnell 1 92-3388 Replaced No
- 7. Description of Work: Replaced snubbers listed.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other N/A Pressure psi Test Temp. *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
k 1
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of-Components in Nuclear Power Plants" is invoked throup.h the use of Form NIS-2 for reportinn.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Autior zation No. N/A Expiration Date: N/A Signed: ks i Engineering Manager Date: 10-12-93
/ ~ (Owner f 0wner's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford CT have inspected the components described in this owner's Report during the period January 1. 1992 to Aunust 31. 1993 , and state that to the best of my knowledge : and belief, the Owner has performed examinations and taken corrective measures ; described in this Owner's 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 measured described in this Owner's 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. Inspector's Signature: 9b / A7 Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: /0 * /V EJ ,
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions'of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 75 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B31.7 _ 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear Work Repaired- ASME Code Component Manufacturer Class Document Replaced, or Stamped Number Replacement (Yes or No)
RH-H42A Grinnell 2 92-3234 Repaired No
- 7. Description of Work: Re-installed assembiv nut.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other N/A Pressure -psi Test Temp. "F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
J
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of r
-Components in Nuclear Power Plants" is invoked throuch the use of Form NIS-2 for reportinn.
(Applicable Manufacturer's Data Reporcs to be Attached) i CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A j Certification of Authori ation No. N/A Expiration Date: N/A Signed: , Ennineerine Mananer Date: 10-12-93
/ (owner or er's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in'this Owner's Report during the period _ r January 1. 1992 to Aunust 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this' Owner's Report in accordance with the requirements of.the ASME j Code, Section XI. By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or in: plied, concerning the examinations and corrective measured
- described in this owner's 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. . Inspector's Signature: de < wd Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: M -/W O
r FORM NTS-2 OWNER'S REFORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 76 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No. , Job No. , Etc. )
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address) N/A-Expiration Date:
- 4. Identification of System: _ Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B31.1 19 67 Edition, No t.ddenda, N/A Code Case' (b) Applicable E11 tion of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired. ASME Code Name of Name of Nuclear ument Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No)
RH-H133 Burns & Roe 2 92-2411 Replaced No
- 7. Description of Work: Replaced support.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other N/A Pressure- psi Test Temp. 'F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at'the top of this form.
q
-l j
i
-9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of
]
Components in Nuclear Power Plants" is invoked throuch the use of Form NIS-2 for reportine. (Applicable Manufacturer's Data Reports to be Attached) ) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ; replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Autho, iz,tio No. N/A Expiration Date: N/A Signed: 7( 2 </. Ennineering Manager Date: 10-12-93
/ (Owner or wner's Designee, Title) t CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this owner's Report during the period ; January 1. 1992 to August 31, 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures , described in this Owner's Report in accordance with the requirements of the ASME: Code, Section XI. By signing this certificate, neither the Inspector nor his employer makes any 'l warranty, expressed or implied, concerning the examinations and corrective measured described in this Owner's 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. Inspector's Signature: u ld x[ A/q. O ddd i
, i >
l Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: /e-/f/-92
'i l
i l L _ _ _ _ - -.
FORM NIS-3 OUNER'S RZPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions'of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October S. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 77 of 89 (Address) ,
- 2. Plant: Cooper Nuclear Station Unit: One >
(Name) P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.) ,
- 3. Work Performed By: Owner Type Code Symbol Stamp: H/A
- Same Authorization Date: N/A-(Address)
Expiration Date: N/A
- 4. Identification of System: Reactor Water Cleanun (RWCU)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N-416 Code Case '
(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Document Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No) 3" Blind Flange Off RWCU 4" Cuyon Al'oys Inc. 2 92-1376 Replaced No Return Line ,
- 7. Description of Work: Replaced portion of RUCU pipe and blind flance that contained ,
an indication. ;
- 8. Tests Conducted: Hydrostatic (1) Pneumatic Nominal Operating Pressure X Other Pressure =1050 psi Test Temp. Ambient *F j (1) Hydrostatic test deferred per Code Case N-416.
NOTS: Supplemental sheets in the form of lists, sketches- or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
i
- 9. Remarks: Code Case N-308. " Documentation of Repairs' and Replacements of .
Components in' Nuclear Power Plants" -is invoked throuch the use of Form NIS-2 for reportinn. (Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Auth r ation No. N/A Expiration Date: N/A 1 Signed; hhk . - >[l$~ Engineering Mananer Date: 10-12-93
,7 - (Owner or wner's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this Owner's Re'p ort during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 meacured described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage ; i or a loss of any kind arising from or connected.with this inspection.
. Inspector's Signature: -0 m&
~ I Commissions: NB #10352, Nebraska, N. I (National Board, State, Province, and Endorsements) Date: // -W41 l l
=_.. ._ _______-_-_ ___ _______ _ - _ _ _ _ _ _ _ - _ -
FORM NIS-2 OUNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. -Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 78 of 89 (Address)
- 2. Plant: Cooner Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address) N/A Expiration Date:
- 4. Identification of System: Residual Heat Removal (RHR) '
- 5. (a) Applicable Construction Code: USAS B16.5 19 68 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear
# *E" * ^ * '
Document Replaced, or Stamped Component Manufacturer Class Replacement Number (Yes or No) RHR-CV-19CV Anchor Valve 2 92-2409 Replacement No i
- 7. Description of Work: Replaced valve bonnet bolts.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure =150 psi Test Temp. Ambient *F i
NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, i provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of , sheets is recorded at the top of this form. I I L- _ _ . . _ i
i
- 9. Remarks: Code Case N-308. " Documentation of-Repairs and Replacements of Components in Nuclear Power Plants". is invoked throuch the use of Form NIS-2 for reportine.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Auth rLaation No. N/A Expiration Date: N/A M' l Signed: M ,r.. L Engineerinn Mananer Date: 10-12-93
/ (Owner o Owner's Designee, Title) t CERTIFICATE OF INSERVICE INSFECTION .
i I, the undersigned, holding a valid commission issued by the National Board of- , Boiler and Pressure Vessel Inspectors and the State or Province of Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford CT have inspected the components described in this Owner's Report during the period i _ January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective, measures . described in this owner's Report in accordance with the. requirements of the ASME Code, Section XI.
=t By signing this certificate, neither the Inspector.nor his employer makes any warranty,-expressed or implied, concerning the examinations and corrective measured described in this owner's 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..
Inspector's Signature: u-/ Al Commissions: NB #10352. Nebraska. N. I l (National Board, State, Province, and Endorsements) ! Date: / c - / U-1.2 l l l l l i k b
F I b FORM NIS-3 05NER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 79 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name) t P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O.
No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A ess) N/A Expiration Date:
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: ASME Section III 19 86 Edition, I
1987 Addenda, N/A Code Case l (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 3 1980, Winter 1981 Addenda j
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Document Replaced, or Stamped !
Component Manufacturer Class Replacement Number (Yes or No) RHR-MOV-M025A or { M02 Anchor / Darling 1 93-2174 Replacement No S/N 7830-4-F-128X RHR-MOV-M027A or RHR-MOV-M027B Anchor / Darling 1 93-0292 Repaired No Spare Disc (2)
- 7. Description of Work: (1) Replaced base metal and stellite. (2) Welded stellite onto disc.
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure Other N/A Pressure' psi Test Temp. *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2" x 11", (2) information in items-1 through 6.on this report is included on each sheet, and (3) each sheet is numbered and-the number of sheets is recorded at the top of this form.
- c. __ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
9 Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throup.h the use of Form NIS-2 for reportinn. (Applicable Manufacturer's Data Reports to be Attached)' CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement / repair conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Auth r ation No. N/A Expiration Date: N/A Signed: [N W> Engineerinn Manager Date: 10-12-93'
// (Owner or Owner's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this 0wner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements af 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 measured ; described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property ramage , or a loss of any kind arising from or connected with this inspection. .3
. Inspector's Signature: - <~*d Commissions: NB #10352. Nebraska. N. I (National Board, State, Province,-and Endorsements)=
Date: /O - l'I' 93
+
_ _ _ . _ _ _ _ _ _ . _ _ _ _ _ m
r. FORM NIS-2 OUNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI I I
~
1
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 I (Name) l P.O. Box 499. Columbas, NE 68601 Sheet 80 of 89 (Address) 2 Plant: Cooper Nuclear Station Unit: One (Name) ;
P.0, Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: E/6 Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Nuclear Boiler (NB)
- 5. (a) Applicable Construction Code: ASME Section III 19 68 Edition,.
Summer 1970 Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear Work Repaired ASME Code Component Manufacturer Class Document Replaced, or Stamped Number Replacement (Yes or No)
Reactor Pressure Conbustion Vessel Nozzle N7 1 92-3098 Replacement No Flange Engineering
- 7. Description of Work: Replaced eicht studs and 16 nuts.
8, Tests conducted: Hydrostatic Pneumatic i Nominal Operating Pressure X , Other Pressure. 1020 psi Test Temp. 180 *F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, , provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of-sheets is recorded at the top of this form. c
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked through the use of Form NIS 2 for reporting.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Auth ri ation No. N/A Expiration Date: N/A Signed: ~
-b Engineerina Mananer Date: 10-12-93
# (Owner or Owner's Designee, Title)
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of 6 Boiler and Pressure Vessel Inspectors and the State or Province of Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures , described in this owner's 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 measured described in this Owner's 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. Inspector's Signaturo: -d Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) i Date: /o-/M3
-_.__-.____---____-.____._--_.___.-.__._.-----_-.----_--._.-.--._._.--_.-.-----.---.__-_._._.-----..-...._-Y
(: FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPIACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 81 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name) .
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation. P.O. No., Job No., Etc.) i
- 3. Work Performed By: Owner Type Code Symbol Stamp: EZA-Same Authorization Date: N/A (Address) Expiration Date: N/A
- 4. Identification of System: Main Steam (MS)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N-416 Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda 1
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear
# *E" #* ^
- unent Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No)
MS-V-105 Dresser Ind. 1 93-2505 Replaced No . Piping Downstream from MS-V-105 Up To N/A 1 93-2505- Replaced No The First Elbow I
- 7. Description of Work: Replaced valve and pipine. 2 i
- 8. Tests Conducted: Hydrostatic (1) Pneumatic Nominal Operating Pressure X (Downstream Weld)
Other Pressure X 1022 psi Test Temp. Ambient "F (1) Upstream Weld only: Pressure-1100 psig, Temperature-72*F ! Downstream weld hydro is deferred per Code Case N-416. NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet., and'(3) each sheet is numbered and the number of [ sheets is recorded at.the top of this form. I
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked through the use of Form NIS-2 for reportine.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Au to zation No. N/A Expiration Date: N/A Signed: - e Engineering Manager Date: 10-12-93
/ (Owner t Owner's Des.ignee. Title)
CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspec' tors and the State or Province of Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this owner's Report during.the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this owner's 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 measured' described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage y or a-loss of any kind arising from or connected with this inspection. l Inspector's Signature: A .. . Os> Commissions: NB #10352. Nebraska. N. I (National-Board, State, Province, and Endorsements) Date: r, - t y- 9 3
F FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section II l
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499 Col umbus . NE 68601 Sheet 82 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownv111e. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A -
Same Authorization Date: N/A (Address) N/A Expiration Date: 4 Identification of System: Main Steam (MS)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or. Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear ument Replaced, or Stamped Component Manufacturer Class Replacement Number (Yes or No)
MS-H270 N/A 1 93-2500 Replacement' No Piping Downstream From ' The First Elbow N/A 1 93-2500 Replaced No Downstream of MS-V-105 ;
- 7. Description of Work: Replaced pipinn and modified support.
- 8. Tests Conducted: Hydrostatic X Pneumatic Nominal Operating Pressure Other Pressure 1110 psi Test Temp. 72 *F ,
NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, ' provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of , sheets is recorded at the top of this form. : t
+:
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throuch the use of Form NIS-2 for_____
reportinn. (Applicable Manufacturer's Data Reports to be Attached)
)
i CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this 1 1 replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Autho iz tioi No. N/A Expiration Date: N/A Signed: & .) Engineering Manager Date: 10-12-93
/ '(Owneror(wner'sDesignee, Title) !
l CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in-this owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the-best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this owner's 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 measured described in this owner's 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. h Inspector's Signature Y m 4J Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements)- Date: /^ - F/~ f > s
p FORM NIS-2 OUNER'S REPORT ?OR REPAIRS OR REPLACEMENTS As Required by the Provisiots of the ASME Code Section XI 1, Owner: Nebraska Public Power District Date: October 5. 1993 (Name) P.O. Box 499. Columbus. NE 68601 St.eet 83 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A
'(Address) Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B16.5 19 68 Edition, No Addenda, M/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Component Manufacturer Class Document Replaced, or Stamped Number Replacement (Yes or No)
RHR-MOV-M025A Anchor / Darling 1 93-2181 Replacement No a f
- 7. Description of Work: Replaced valve disc.
l
'l
- 8. Tests Conducted: Hydrostatic Pneumatic 1 Nominal Operating Pressure X ;
other Pressure 200 psi Test Temp. Ambient *F ! I NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, l provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form, t
c 3
- 9. ' Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throup.h the use of Form NIS-2 for reportine.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) Type Code Symbol Stamp: N/A Certification of Aut or zat on No. N/A Expiration Date: N/A f l Signed: W /) . ns( . , r. - ) Ennineering Mananer Date: 10-12-93 [ ' (Owner o Owner's Designee, Title)- CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I company of Hartford. CT have inspected the components described in this owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this owner's 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 measured described in this owner's 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. 1 Inspector's Signature: e/ 2 JMd Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: 47 - /6/- f3
c. FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by.the Provisions of the ASME Code Section XI
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 84 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR) 5, (a) Applicable. Construction Code: USAS B16.5 19_j8_ Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear W rk Repaired' ASME Code Component Manufacturer Class Document Replaced, or Stamped Number Replacement (Yes or No)
RHR-MOV-M025A Anchor / Darling 1 93-2181 Repaired No-i
- 7. Description of Work: Machined bonnet. P.l a nd . stuffinn box back seat.'and stem to I remove pittinn and other indications.
1
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 200 psi Test Temp. _ Ambient "F- .
l NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, l provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
- 9. Remarks: Code case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked throuth the use of Form NIS-2 for reportine.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE Ve certify that the statements made in the report are correct and this repair conforms to the rules of the ASME Code, Section XI. (repair or replacement) _ Type Code Symbol Stamp: N/A Certification of Authori ati n No. N/A Expiration Date: N/A Signed; i) Ennineering Mananer Date: 10-12-93
/ ~(Owner o p er's Designee, Title)
CERTIFICATE OF INSERVICE 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 Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford, CT have inspected the components described in this owner's Report during the period January 1. 1992. to August 31, 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this owner's 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. Inspector's Signature:DYn v b 4> Commissions: NB #10352. Nebraska, N. I (National Board, State. Province, and Endorsements) Date: // - /Y~ ff
f. FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
'1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 85 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Reactor Core Isolation Coolant (RCIC)
- 5. (a) Applicable Construction Code: USAS B16.5 19 68 Edition, t
No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components W rk Repaired ASME Code Name of Name of Nuclear Component Manufacturer Class Document Replaced,.or Stamped Number Replacement (Yes or No)
RCIC-MOV-M0132 Crane Company 2 93-2386 Repaired No
- 7. Description of Work: Bonnet to body seal weld cut and rewelded. i
- 8. Tests Conducted: Hydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 1200 psi Test Temp. Ambient "F NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11",'(2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top _of this form. ,
t.
0
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked through the use of Form NIS-2 for reporting. i (Applicable Manufacturer's Data Reports to be Attached)
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair conforms to the rules of the ASME Code, Section XI.
-(repair or replacement)
Type Code Symbol Stamp: N/A Certification of Autho ization No. N/A Expiration Date: N/A Signed: Ai Engineerine Manager Date: 10-12-93
// (Owner or hmer's Designee, Title)
CERTIF,ICATE OF INSERVICE 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 Nebraska and.
employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this Owner's Report during the period January 1. 1992 to August 31. 1993 , and state that.to the best of my knowledge f and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this owner's 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. Inspector's Signature:I Ym ) Ms Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements)- Date: /0-/V-91
fl FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS ! As Required by the Provisions of the ASME Code Section II l
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 86 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: H/A Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, -
No Addenda, N/A ' Code Case (b) Applicable Edition of Section X1 Utilized for Repairs or Replacements t 1980, Winter 1981 Addenda ,
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear W rk Repaired ASME Code Document Replaced, or Stamped
- Component Manufacturer Class Number Replacement (Yes or No)
RH-S9 Pacific Scientific 1 93-1634 Repaired No RH-S10 Pacific Scientific 1 93-1634. Repaired No a
-l
- 7. Description of Work: Cut clamp stiffener plates and rewelded after adjustment.
- 8. Tests Conducted: Hydrostatic Pneumatic ,
Nominal Operating Pressure Other _F/A Pressure psi Test Temp. 'F i NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this ' report'is included on each sheet, and (3) each sheet is numbered and the number of
. sheets is recorded at the top of this form.
u
r A
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked through the use of Form NIS-2 for reportinc.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLlANCE r We certify that the statements made in the reporc are correct and this repair conforms to the rules of the ASME Code, Section X1. l (repair or replacement) Type Code Symbol Stamp: N/A Certification of Aut ortgation No. N/A Expiration Date: N/A
- Signed: Yk )) t. Engineerine Mananer Date: 10-12-93 '
/ ~ (Owner ov'0wner's Designee, Title)
( r CERTIFICATE OF INSERVICE INSPECTION r I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Nebraska and employed by Hartford Steam Boiler I & I Company of Hartford. CT have inspected the components described in this owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this owner's 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 measured
- described in this Owner's 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.
Inspector's Signature d kAs Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: n - N'-f3 l l l. i
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME. Code Section II _
- 1. Owner: Nebraska Public Power District Date: October 5. 1993 l (Name) I P.O. Box 499. Columbus. NE 68601 Sheet 87 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One i (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: N/A Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Reactor Core Isolation Coolant (RCIC)
- 5. (a) Applicable Construction Code: USAS B16.5 19 68 Edition, No Addenda, N/A Code Case ,
(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nuclear W rk Repaired ASME Code '
Document Replaced, or Stamped Component Manufacturer Class Number Replacement (Yes or No) RCIC-CV-21CV Rockwell 2 92-2610 Replacement No 5 i _b i
- 7. Description of Work: Replaced bonnet bolts.
b
- 8. Tests Conducted: liydrostatic Pneumatic Nominal Operating Pressure X Other Pressure 13 psi Test Temp. Ambient _*F !
NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, , provided (1) size is 8-1/2" x 11", (2) information in items 1 throu6h 6 on this report is included on each sheet, and (3) each sheet is numbered and the number'of sheets is recorded at the top of this form. e N'.. a
l i
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclear Power Plants" is invoked through the use of Form NIS-2 for I l
reportine. (Applicable Manufacturer's Data Reports to be Attached) , I CERTIFICATE OF COMPLIANCE ; i We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) 1 Type Code Symbol Stamp: N/A Certification of Aut or zation No. N/A Expiration Date: N/A Signed: W , Engineering Mananer Date: 10-12-93
$" ' (Owner o Owner's Designec, 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 Nebraska and ; employed by Hartford Steam Boiler I & I Company have of Hartford. CT inspected the components described in this owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of'my knowledge and belief, the Owner has performed examinations and taken corrective measures - described in this Owner's 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 measured described in this owner's Report. Furthermore, neither the Inspector nor his j cmployer shall be liable in any manner for any personal injury or property damage ' or a loss of.any kind arising from or connecte.d with this inspection. Inspector's Signature j e6C Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: le-/V-f5 s L
(I FORM NIS-2 OUNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
-1. Owner: Nebraska Public Power District Date: October 5. 1993 (Name) 4 P.O. Box 499. Columbus. NE 68601 Sheet 88 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box 98. Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: H/A Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Main Steam (MS)'
- 5. (a) Applicable Construction Code: ASME Section III 19 68 Edition, Summer 1970 Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced ar.i Replacement Components Name of Name of Nuclear W rk Repaired ASME Code Component Manufacturer Class Document Replaced, or Stamped Number Replacement (Yes or No) '
"*Y "
- gp 8 Target Rock 1 92-2738 Replacement' No
- 7. Description of Work: Valve seat replaced on spare valve.
'8. Tests Conducted: Hydrostatic Pneumatic '
Nominal Operating Pressure ! Other N/A Pressure psi Test Temp. 'F t NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form, s J t m_ _
r 7%
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of
' Components in Nuclear Power Plants" is invoked throunh the use of Form NIS-2 for reportine.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this > replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) > Type Code Symbol Stamp: N/A Certification of Aut or ation No. N/A Expiration Date: N/A n , ll Signed: ( - ti /D Engineering Mananer Date: 10-12-93
/ ' (Owner q Owner's Designee, Title) {
4 4 CERTIFICATE OF INSERVICE INSPECTION 1 1, the undersigned, holding a valid commission issued by the National Board of i Boiler and Pressure Vessel Inspectors and the State or Province of Nebraska and employed by Hartford Steam Boiler I & I company of Hartford. CT have inspected the components described in this Owner's Report during the period January 1. 1992 to August 31. 1993 , and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures described in this owner's 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 measured i described in this Owner's 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. Inspector's Signature: 7 -" m u? Commissions: NB #10352. Nebraska. N. I > (National Board, State. Province, and Endorsements) I l Date: l0~IV' U l-i i i i l' ) W - . _ . . ._ _ __ _ _____ _ __- - ___ _ O
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI ,
- 1. Owner: Nebraska Public Power District Date: October S. 1993 (Name)
P.O. Box 499. Columbus. NE 68601 Sheet 89 of 89 (Address)
- 2. Plant: Cooper Nuclear Station Unit: One (Name)
P.O. Box t% Brownville. NE 68321 N/A (Address) (Repair Orgainzation, P.O. No., Job No., Etc.)
- 3. Work Performed By: Owner Type Code Symbol Stamp: Nf6 Same Authorization Date: N/A (Address)
Expiration Date: N/A
- 4. Identification of System: Residual Heat Removal (RHR)
- 5. (a) Applicable Construction Code: USAS B31.7 19 69 Edition, No Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements ,
1980, Winter 1981 Addenda
- 6. Identification of Components Repaired or Replaced and Replacement Components k- ,
! Name of Name of Nuclear W rk Repaired ASME Code 4 Component Manufacturer Class cument Replaced, or Stamped Number Replacement (Yes or No)
RHR-RV-11RV Crosby Valve 2 93-0751 Replaced. No i
- 7. Description of Work: Replaced valve.
J
- 8. Tests Conducted: llydrostatic Pneumatic l Nominal. Operating Pressure X !
g Other Pressure 6 psi . Test Temp. Ambient *F l NOTE: Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2" x 11", (2) information in items 1 through 6 on'this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. i l 1
\: . . .
. . . .. . . . . . -- - _ = - _ _ _ - _ - - -
- 9. Remarks: Code Case N-308. " Documentation of Repairs and Replacements of Components in Nuclegr Power Plants" is invoked through the use of Form NIS-2 for reportinc.
(Applicable Manufacturer's Data Reports to be Attached) CERTIFICATE OF. COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code, Section XI. (repair or replacement) _ Type Code Symbol Stamp: N/A Certification of Au h rization No. N/A Expiration Date; N/A Signed: - J Ennineerine Mananer Date: 10-12-93
/ (owner r Owner's Designee, Title) i CERTIFICATE OF INSERVICE 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 Nebraska and - employed by Hartford Steam Boiler I & I Company of Hartford. CT have - inspected the components described in this owner's Report during the period 4 January 1. 1992 to Aunust 31. 1993 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's 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 measured described in this owner's 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. Inspector's Signature: 'N '
~O '
Commissions: NB #10352. Nebraska. N. I (National Board, State, Province, and Endorsements) Date: # "I U _ N' __ - _ . _ _ - _ . _ .
. ..}}