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A total of 46 ASME, Augmented or Owner Elected components were examined. The examinations for these components consisted of 19 VT's, 18 PT's, 8 MT's, 17 UT's and 4 RT's. A total of 66 examinations were performed on Class 1 Components.
A total of 46 ASME, Augmented or Owner Elected components were examined. The examinations for these components consisted of 19 VT's, 18 PT's, 8 MT's, 17 UT's and 4 RT's. A total of 66 examinations were performed on Class 1 Components.


R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)
                        -
1990 1999 Interval, Second Period, Fourth Outage (1996)
CLASS    1 COMPONENTS:        Cont.
CLASS    1 COMPONENTS:        Cont.
Class    1 examinations  were  performed  on the  following items/systems and/or plant lines/component:
Class    1 examinations  were  performed  on the  following items/systems and/or plant lines/component:
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Auxiliary Feedwater System:                  3A -FW7-900-1A 3A -FW7-900-1B 3J -FW7-900-1 3K -FW7-900-1 Diesel Generator System:                    5C-DG-B
Auxiliary Feedwater System:                  3A -FW7-900-1A 3A -FW7-900-1B 3J -FW7-900-1 3K -FW7-900-1 Diesel Generator System:                    5C-DG-B


R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)
                          -
1990 1999 Interval, Second Period, Fourth Outage (1996)
HIGH ENERGY COMPONENTS:
HIGH ENERGY COMPONENTS:
Five (5) Augmented or Owner Elected items associated with the High Energy Program were examined during the 1996 Outage. The examinations    for these items consisted of 3 VT's, 3 MT's and 1 UT for a total of 7 examinations.
Five (5) Augmented or Owner Elected items associated with the High Energy Program were examined during the 1996 Outage. The examinations    for these items consisted of 3 VT's, 3 MT's and 1 UT for a total of 7 examinations.
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R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)
                        -
1990 1999 Interval, Second Period, Fourth Outage (1996)
SNUBBER PROGRAM: Cont.
SNUBBER PROGRAM: Cont.
Visual Examinations:
Visual Examinations:
Item  /S stem Descri tion                  Plant Line Main Steam Lines:                          30A-MS-600-1A 30B-MS-600-1B 6A-MS-600-1A 6B-MS-600-1A 6B-MS-600-1B 6A-MS-600-1 6B-MS-600-1 Safety Injection Lines:                    10A-SI2-2501-A 10A-SI2-2501-B 10 -SI -151 8J-SI -151 4 -SI -301 Residual Heat Removal Lines:                10  -AC -601 10A -AC7-2501-B 10A -AC7-2501-A 10D -AC -601 10E -AC -601 10G -AC -601 10GG-AC -151 8B -AC -601 6  -AC -601 6D -AC -601 6K -AC -151 Service Water Lines:                        10B-SWO-125-1 8A-SWO-125-1 8L-SW -125
Item  /S stem Descri tion                  Plant Line Main Steam Lines:                          30A-MS-600-1A 30B-MS-600-1B 6A-MS-600-1A 6B-MS-600-1A 6B-MS-600-1B 6A-MS-600-1 6B-MS-600-1 Safety Injection Lines:                    10A-SI2-2501-A 10A-SI2-2501-B 10 -SI -151 8J-SI -151 4 -SI -301 Residual Heat Removal Lines:                10  -AC -601 10A -AC7-2501-B 10A -AC7-2501-A 10D -AC -601 10E -AC -601 10G -AC -601 10GG-AC -151 8B -AC -601 6  -AC -601 6D -AC -601 6K -AC -151 Service Water Lines:                        10B-SWO-125-1 8A-SWO-125-1 8L-SW -125


R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)
                        -
1990 1999 Interval, Second Period, Fourth Outage (1996)
SNUBBER PROGRAM: Cont.
SNUBBER PROGRAM: Cont.
Visual Examinations:
Visual Examinations:
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Com onent T e                  TAHITI Pipes                        45 Elbows                        39 Reducers                      12 Tees                            2 10
Com onent T e                  TAHITI Pipes                        45 Elbows                        39 Reducers                      12 Tees                            2 10


R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)
                    -
1990 1999 Interval, Second Period, Fourth Outage (1996)
EROSION/CORROSION MINWALLPROGRAM:                    Cont.
EROSION/CORROSION MINWALLPROGRAM:                    Cont.
Component thickness measurements were performed on the following systems:
Component thickness measurements were performed on the following systems:
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IVc ccttify that statements made in this report arc correct and the examinations and corrective measures taken conform to the rules      of the ASME Code,    Section XI.
IVc ccttify that statements made in this report arc correct and the examinations and corrective measures taken conform to the rules      of the ASME Code,    Section XI.
CertiTicate of Authorization No. (ifapplicable)                          N/A                        Expiration Date                      N/A Date            13      Se member                  19 96          Signed Rochester GaB A Flectric Cn        mtion GNtter                                  ISI Engineer CERTIFICATE OF INSERVICE INSPECTION I, Ibe undesigned, holding a vsgd conunisdon issn d by tbc Na lion st Board of Boiler and Presto o Vessel Inspcdora and the State or Province Zgdt                andonptoy dby a
CertiTicate of Authorization No. (ifapplicable)                          N/A                        Expiration Date                      N/A Date            13      Se member                  19 96          Signed Rochester GaB A Flectric Cn        mtion GNtter                                  ISI Engineer CERTIFICATE OF INSERVICE INSPECTION I, Ibe undesigned, holding a vsgd conunisdon issn d by tbc Na lion st Board of Boiler and Presto o Vessel Inspcdora and the State or Province Zgdt                andonptoy dby a
                                                              '
                                                                                       . c        ~          of a of~
                                                                                       . c        ~          of a of~
have inspected the components described in this Ohhltei's Report during the period df          a          M                to                                  and state that to thc best of my hlowledge and belief, thc Ohvncr llas perfomled examinations and taken corrective measures described in this Ohvnei's Report in accordance with the inspection plan and as required by the ASME Code, Section Xl.
have inspected the components described in this Ohhltei's Report during the period df          a          M                to                                  and state that to thc best of my hlowledge and belief, thc Ohvncr llas perfomled examinations and taken corrective measures described in this Ohvnei's Report in accordance with the inspection plan and as required by the ASME Code, Section Xl.
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96 -PT; NO RECORDABLE INDICATIONS  ACCEPTABLE.
96 -PT; NO RECORDABLE INDICATIONS  ACCEPTABLE.


'
R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Znterval, Second Period, Fourth Outage (1996)
R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Znterval, Second Period, Fourth Outage (1996)
: 1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
: 1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
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R. E. GINNA NUCLEAR          POWER PLANT Znservice Inspection Report 1990-1999  Interval, Second Period, Fourth Outage (1996)
R. E. GINNA NUCLEAR          POWER PLANT Znservice Inspection Report 1990-1999  Interval, Second Period, Fourth Outage (1996)
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R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999  Interval, Second Period, Fourth Outage (1996)
R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999  Interval, Second Period, Fourth Outage (1996)
: 1. Owner Rochester Gas & Electric Cor .,89 East Ave.;Rochester NY 14649
: 1. Owner Rochester Gas & Electric Cor .,89 East Ave.;Rochester NY 14649
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G12.      2" CVCS RELZEF      LINE      TO PRT                                      DRAWINGS:  B-32 Summary                  Item Number        Categ        Number      Component                          Component Type 600940      SN-VT                    CVU-80                              AUG                VT MECHANICAL SNUBBER 96  VTr SETTING 1 1/2          9  S/N    2 35 1 8 9 NO RECORDABLE  INDICATIONS    ACCEPTABLE G13.      SEAL WATER TO RCP-B                                                        DRAWINGS'-32 Summary      Exam        Item Number        Categ        Number      Component                          Component Type 600960      SN-VT                    CVU-103                            AUG                  VT MECHANICAL SNUBBER 96  VTe SETTING 2        1/8    9  S/N    244509      NO RECORDABLE &  INSIGNIFICANT ACCE PTABLE .
G12.      2" CVCS RELZEF      LINE      TO PRT                                      DRAWINGS:  B-32 Summary                  Item Number        Categ        Number      Component                          Component Type 600940      SN-VT                    CVU-80                              AUG                VT MECHANICAL SNUBBER 96  VTr SETTING 1 1/2          9  S/N    2 35 1 8 9 NO RECORDABLE  INDICATIONS    ACCEPTABLE G13.      SEAL WATER TO RCP-B                                                        DRAWINGS'-32 Summary      Exam        Item Number        Categ        Number      Component                          Component Type 600960      SN-VT                    CVU-103                            AUG                  VT MECHANICAL SNUBBER 96  VTe SETTING 2        1/8    9  S/N    244509      NO RECORDABLE &  INSIGNIFICANT ACCE PTABLE .
600980      SN-VT        ----        CVU-104                            AUG                  VT MECHANICAL SNUBBER 96  VTa    SETTING 2      9  S/N      24499    NO RECORDABLE    INDICATIONS    ACCEPTABLE ~
600980      SN-VT        ----        CVU-104                            AUG                  VT MECHANICAL SNUBBER 96  VTa    SETTING 2      9  S/N      24499    NO RECORDABLE    INDICATIONS    ACCEPTABLE ~
G14.      SEAL WATER RETURN FROM RCP-A                                              DRAWINGS:  B-34 Summary      Exam        Item                                                                  NDE Number        Categ        Number      Component                          Component Type      Exam 9  OC  SBB    RRBBBBBSBSBB K%  R  BB  9  K    D K  R    mt        BBBBK
G14.      SEAL WATER RETURN FROM RCP-A                                              DRAWINGS:  B-34 Summary      Exam        Item                                                                  NDE Number        Categ        Number      Component                          Component Type      Exam 9  OC  SBB    RRBBBBBSBSBB K%  R  BB  9  K    D K  R    mt        BBBBK 9
                          ----
601000        SN-VT                    CVU-186                            AUG                  VT MECHANICAL SNUBBER 96  VTe SETTING 1            4  9  S/N'    654 1 9  NO RECORDABLE  INDICATZONS    ACCEPTABLE ~
9 601000        SN-VT                    CVU-186                            AUG                  VT MECHANICAL SNUBBER 96  VTe SETTING 1            4  9  S/N'    654 1 9  NO RECORDABLE  INDICATZONS    ACCEPTABLE ~
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R. E  ~  GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990"1999 Znterval, Second Period, Fourth Outage            (1996)
R. E  ~  GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990"1999 Znterval, Second Period, Fourth Outage            (1996)
: l. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
: l. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
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56


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R. E. GINNA NUCLEAR POWER PLANT Inservice Znspection Report 1990-1999  Interval, Second Period, Fourth Outage (1996)
R. E. GINNA NUCLEAR POWER PLANT Inservice Znspection Report 1990-1999  Interval, Second Period, Fourth Outage (1996)
: l. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
: l. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
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INSIGNIFZCANTS FLUID LEVEL 1/2 FULL                      ACCEPTABLE'ETTINGS HOT 3 5/8 COLD 3 1/4            9
INSIGNIFZCANTS FLUID LEVEL 1/2 FULL                      ACCEPTABLE'ETTINGS HOT 3 5/8 COLD 3 1/4            9
                                     'S/N    18193 'NUBBER PROGRAM REQUIREMENTS APPLY'02081 SN-FT              ----      N616                          AUG                        FT HYDRAULIC SNUBBER 96 -FT;  FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM. TESTED OPERABLE, SNUBBER WAS REPLACED'52.
                                     'S/N    18193 'NUBBER PROGRAM REQUIREMENTS APPLY'02081 SN-FT              ----      N616                          AUG                        FT HYDRAULIC SNUBBER 96 -FT;  FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM. TESTED OPERABLE, SNUBBER WAS REPLACED'52.
POWER PRESS.            RELIEF LINE                                      DRAWINGS:        S-1 Summary                      Item Number    Categ              Number    Component                      Component Type BB 602090    SN-VT                          PS-2                          AUG                        VT HYDRAULIC SNUBBER 96  VT  SETTING 4            i/8  9  S/N,  PD  87239 12449
POWER PRESS.            RELIEF LINE                                      DRAWINGS:        S-1 Summary                      Item Number    Categ              Number    Component                      Component Type BB 602090    SN-VT                          PS-2                          AUG                        VT HYDRAULIC SNUBBER 96  VT  SETTING 4            i/8  9  S/N,  PD  87239 12449 NO RECORDABLE &        INSIGNIFICANTr FLUID LEVEL              1/8"  RED SHOWING        ACCEPTABLE.
                                                          -
NO RECORDABLE &        INSIGNIFICANTr FLUID LEVEL              1/8"  RED SHOWING        ACCEPTABLE.
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(-)  Repair, Replacement or Modification as identified within "ATTACHMENT II"
(-)  Repair, Replacement or Modification as identified within "ATTACHMENT II"


R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)
                        -
1990 1999 Interval, Second Period, Fourth Outage (1996)
: l. Oavner:                                                V            4 4
: l. Oavner:                                                V            4 4
: 2. Plant: R,E, Ginna Nuclear Popover Plant 1503 Lake Rd. Ontario .      14519
: 2. Plant: R,E, Ginna Nuclear Popover Plant 1503 Lake Rd. Ontario .      14519
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A "Code Rejectable Indication" occurs when a component under the RR&M Program contains an indication that is beyond ASME Section XI Code acceptable standards and was determined to be not "Service Induced". This category includes but is not limited to items such as welding discontinuities from a modification identified during ISI preservice examinations or component damage caused by human involvement.
A "Code Rejectable Indication" occurs when a component under the RR&M Program contains an indication that is beyond ASME Section XI Code acceptable standards and was determined to be not "Service Induced". This category includes but is not limited to items such as welding discontinuities from a modification identified during ISI preservice examinations or component damage caused by human involvement.


R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)
                          -
1990 1999 Interval, Second Period, Fourth Outage (1996)
: l. Owner:              ~    . e                V                      4
: l. Owner:              ~    . e                V                      4
: 2. Plant: R E Ginna Nuclear Power lant 1503 La! e Rd.      ntario    . 45 9
: 2. Plant: R E Ginna Nuclear Power lant 1503 La! e Rd.      ntario    . 45 9
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: 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519
: 2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519
: 3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:
: 3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:
* The      following information will report applicable Repairs, Replacements          or Modifications performed at R. E. Ginna Nuclear Power    Plant during this reporting period as required by ASME Section XI Code.
The      following information will report applicable Repairs, Replacements          or Modifications performed at R. E. Ginna Nuclear Power    Plant during this reporting period as required by ASME Section XI Code.
ASME      Class:      1    ~Sstem:        Pressurizer                  GORR    Mo.: 96-E-001 3A-RC8-2501 Construction Code:                  ASME      Section        III '86; Work Performed              B :      2 Name      of  Com onent:            V430, V431C Plugs & Cages Work        Descri tion/Remarks:                        A Replacement                activity was initiated for plugs & cages associated with Valves 430 & 431C.
ASME      Class:      1    ~Sstem:        Pressurizer                  GORR    Mo.: 96-E-001 3A-RC8-2501 Construction Code:                  ASME      Section        III '86; Work Performed              B :      2 Name      of  Com onent:            V430, V431C Plugs & Cages Work        Descri tion/Remarks:                        A Replacement                activity was initiated for plugs & cages associated with Valves 430 & 431C.
This activity was controlled by WO ¹'s 19504164 ,19503981; and PCR      96-032. Upon activity conclusion,                                    a VT-2 Leakage Examination was performed & acceptable under PT-7 (01.1).
This activity was controlled by WO ¹'s 19504164 ,19503981; and PCR      96-032. Upon activity conclusion,                                    a VT-2 Leakage Examination was performed & acceptable under PT-7 (01.1).
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: 8. ASME    Class:      3    ~S stem:      AFW                          GORR    No.: 96-006 Construction Code: ASME                      III    NF '74, SP-5291, ME-318 Work Performed B : 1 Name of Com onent:                  AFU-34 Snubber Replacement Work Descri tion/Remarks: A Snubber Replacement activity was initiated for support AFU-34. This activity was controlled by WO      ¹ 19404236. Upon reinstallation, a VT-3 Preservice (Baseline) exam'.nation was performed and acceptable.
: 8. ASME    Class:      3    ~S stem:      AFW                          GORR    No.: 96-006 Construction Code: ASME                      III    NF '74, SP-5291, ME-318 Work Performed B : 1 Name of Com onent:                  AFU-34 Snubber Replacement Work Descri tion/Remarks: A Snubber Replacement activity was initiated for support AFU-34. This activity was controlled by WO      ¹ 19404236. Upon reinstallation, a VT-3 Preservice (Baseline) exam'.nation was performed and acceptable.


R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)
                          -
1990 1999 Interval, Second Period, Fourth Outage (1996)
: l. Owner:                                          ve
: l. Owner:                                          ve
: 2. Plant: R,F. Ginna Nuclear Power Plant 150      ake Rd, Ontario N Y 14519
: 2. Plant: R,F. Ginna Nuclear Power Plant 150      ake Rd, Ontario N Y 14519
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       ¹ 19501745. Construction Code VT examinations were performed and acceptable                      on ESW09A  West Base                                Support. Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.
       ¹ 19501745. Construction Code VT examinations were performed and acceptable                      on ESW09A  West Base                                Support. Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.


R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)
                          -
1990 1999 Interval, Second Period, Fourth Outage (1996)
: l. Owner:                                        v        e          4 4
: l. Owner:                                        v        e          4 4
: 2. Plant: R.E. Ginna Nuclear Power Plant 15031 ake Rd. Ontario N.Y, 14519
: 2. Plant: R.E. Ginna Nuclear Power Plant 15031 ake Rd. Ontario N.Y, 14519
Line 1,216: Line 1,185:
                                               ~
                                               ~
ASME 1
ASME 1
AFW VIII, B31.1
AFW VIII, B31.1 onent: EAF02A, EAF02B Tube Ass'y Replacement Work Descri tion/Remarks: A Replacement activity was initiated
                                                                    "'
onent: EAF02A, EAF02B Tube Ass'y Replacement Work Descri tion/Remarks: A Replacement activity was initiated
                                                                           '55 GORR    No.: 96-029 y
                                                                           '55 GORR    No.: 96-029 y
for the Shell and Tube Assembly associated with EAF02A &
for the Shell and Tube Assembly associated with EAF02A &
Line 1,252: Line 1,219:
       ¹ 19503972, Action Report 96-0621 and EWR 10204. Upon reinstallation, a VT-3 Preservice                              (Baseline) examination          was performed and acceptable.
       ¹ 19503972, Action Report 96-0621 and EWR 10204. Upon reinstallation, a VT-3 Preservice                              (Baseline) examination          was performed and acceptable.


e R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report
e R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)
                          -
1990 1999 Interval, Second Period, Fourth Outage (1996)
: 1. Owner:      es e  as                                              4 4
: 1. Owner:      es e  as                                              4 4
: 2. Plant: R.F. Oinna Nuclear Power Plant 1503 I al;e Rd. Ontario N Y 14519
: 2. Plant: R.F. Oinna Nuclear Power Plant 1503 I al;e Rd. Ontario N Y 14519
Line 1,268: Line 1,233:
15
15


i R. E. GINNA NUCLEAR POWER PLANT Inserv ice Inspection Report
i R. E. GINNA NUCLEAR POWER PLANT Inserv ice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)
                            -
1990 1999 Interval, Second Period, Fourth Outage (1996)
: 1. Owner:          t                c            V                    4
: 1. Owner:          t                c            V                    4
: 2. Plant: R,F.. Crinna Nuclear Power Plant 150 Lake Rd. Ontario N.Y 14519
: 2. Plant: R,F.. Crinna Nuclear Power Plant 150 Lake Rd. Ontario N.Y 14519
Line 1,283: Line 1,246:


R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Fourth Outage (1996)
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Fourth Outage (1996)
                                          '
: 1. Osvner:            i~        c                          e.
: 1. Osvner:            i~        c                          e.
: 2. Plant: R.F. Ciinna Nuclear Power Plant 1503 I.ai'e Rd. Ontario N.Y. 1451
: 2. Plant: R.F. Ciinna Nuclear Power Plant 1503 I.ai'e Rd. Ontario N.Y. 1451
Line 1,304: Line 1,266:
: 2. Plant: R.F. Oinna Nuclear Power Plant 1503 Lake Rd. Ontario Y. 145 9
: 2. Plant: R.F. Oinna Nuclear Power Plant 1503 Lake Rd. Ontario Y. 145 9
: 3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:
: 3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:
: 35. ASME      Class:      2    ~S stem: CVCS-Charging                      GORR
: 35. ASME      Class:      2    ~S stem: CVCS-Charging                      GORR No.: 96-044 d
                                                                                '
No.: 96-044 d
Construction Code:                    B31.1 '55, G-676262,                ASME      III '86 Work Performed              B :      lA Name      of  Com onent:            8" CVCS Weld ¹1 Repair Work        Descri tion/Remarks:                      During an Owner Elected PT examination on weld                  8A-CH-2502          ¹1, a 3/4" linear indication was identified. A .Code Repair by metal removal was initiated.
Construction Code:                    B31.1 '55, G-676262,                ASME      III '86 Work Performed              B :      lA Name      of  Com onent:            8" CVCS Weld ¹1 Repair Work        Descri tion/Remarks:                      During an Owner Elected PT examination on weld                  8A-CH-2502          ¹1, a 3/4" linear indication was identified. A .Code Repair by metal removal was initiated.
This activity was controlled by WO ¹'s 19601798, 19502368, Action Report 96-0412 and PCR 96-061. Upon completion of the Repair Cycle by metal removal, a PT examination was reperformed and acceptable. UT thickness readings were -also performed and acceptable.
This activity was controlled by WO ¹'s 19601798, 19502368, Action Report 96-0412 and PCR 96-061. Upon completion of the Repair Cycle by metal removal, a PT examination was reperformed and acceptable. UT thickness readings were -also performed and acceptable.
Line 1,313: Line 1,273:
18
18


R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)
                          -
1990 1999 Interval, Second Period, Fourth Outage (1996)
: l. Owner:                                          v        ete      . 44
: l. Owner:                                          v        ete      . 44
: 2. Plant: R.E. Ginna Nuclea Power lant 150'1 .al'e Rd, Ontar'o .Y 14519
: 2. Plant: R.E. Ginna Nuclea Power lant 150'1 .al'e Rd, Ontar'o .Y 14519
Line 1,328: Line 1,286:
19
19


,
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report
                            -
1990 1999 Interval, Second Period, Fourth Outage (1996)
: l. Owner:          ~      ~E        'c            V                    4 4
: l. Owner:          ~      ~E        'c            V                    4 4
: 2. Plant: R.F.. Csinna Nuclear Power Plant 150 I.al e Rd. Onta 'o N.Y. 14519
: 2. Plant: R.F.. Csinna Nuclear Power Plant 150 I.al e Rd. Onta 'o N.Y. 14519
Line 1,368: Line 1,323:
                                             ~.
                                             ~.
ASME RCS G-676496 3
ASME RCS G-676496 3
III '86;
III '86; GORR B31.1 '55, G-676343, Noet 96-058 "I'onstruction Name      of    Com  onent: S/G "A & B", RCS Hot & Cold Leg Repairs Work Descri tion/Remarks: A Repair activity by metal removal was initiated for Steam Generators "A" and "B" RCS Hot and Cold Legs on identified piping locations to remove original construction defects, arc strikes, and gouges. This activity was controlled by WO ¹'s 19601418, 19601419, and Action Report 96-0272. Upon completion of the Repair Cycle, PT examinations as well as UT thickness                                readings were performed and acceptable.
                                                                          "
GORR
                                                                                        "
B31.1 '55, G-676343, Noet 96-058
                                                                                                "
                                                                                                    "I'onstruction Name      of    Com  onent: S/G "A & B", RCS Hot & Cold Leg Repairs Work Descri tion/Remarks: A Repair activity by metal removal was initiated for Steam Generators "A" and "B" RCS Hot and Cold Legs on identified piping locations to remove original construction defects, arc strikes, and gouges. This activity was controlled by WO ¹'s 19601418, 19601419, and Action Report 96-0272. Upon completion of the Repair Cycle, PT examinations as well as UT thickness                                readings were performed and acceptable.
22
22


R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)
                            -
1990 1999 Interval, Second Period, Fourth Outage (1996)
: l. Owner:          s              c              V                      4
: l. Owner:          s              c              V                      4
: 2. Plant: R,E, Cr nna Nuclear Power Plant 1503 I.al'e Rd, Ontario N, Y, 14519
: 2. Plant: R,E, Cr nna Nuclear Power Plant 1503 I.al'e Rd, Ontario N, Y, 14519
Line 1,412: Line 1,359:
25
25


,
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report
                          -
1990 1999 Interval, Second Period, Fourth Outage (1996)
   . l. Owner:      e    sa A        t'                        ete        44
   . l. Owner:      e    sa A        t'                        ete        44
: 2. Plant: R.E. Ginna Nuclear ower Plant 1503 Lake Rd, Ontario N.Y. 4519
: 2. Plant: R.E. Ginna Nuclear ower Plant 1503 Lake Rd, Ontario N.Y. 4519
Line 1,432: Line 1,376:
2.
2.
3.
3.
                            -
vas        'eInserv ice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996) cste          e t                          st Plant: R.F.. Ginna Nuclear Power Plant 150 Lake Rd Ontario N.Y 14519 4 4 Applicable Edition of Section Xl Utilized for Repairs, Replacements or Modifications:
vas        'eInserv ice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996) cste          e t                          st Plant: R.F.. Ginna Nuclear Power Plant 150 Lake Rd Ontario N.Y 14519 4 4 Applicable Edition of Section Xl Utilized for Repairs, Replacements or Modifications:
1986 No Addenda ATTACHMENT II
1986 No Addenda ATTACHMENT II
Line 1,514: Line 1,457:
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)
ATTACHMENTIII Com onent Result Details(CONTINUED)
ATTACHMENTIII Com onent Result Details(CONTINUED)
M-19  1A, 2A, & 3A L.P. HEATER DRAINS TO CONDENSER Summary Comp. Comp. Nominal Nominal Minimum            Minimum    Percent    NDE N m er ID      T      Will      Wll2 All w l            R    in    N min  1  Meth d 234010    01    R      0.594    0.500    0.207,0.174  0.567,0.522      >88        UT 234030    03    E      0.500              0.176        0.495          >88        UT 234040    04    P      0.500              0.173        0.484          >88        UT 234070    07    E      0.500              0.174        0.604          >88        UT 234075    07A  E      0.500              0.173        0.505          >88        UT 234080    08    E      0.500              0.174        0.517          >88        UT 234090    09    P      0.500              0.173        0.484          >88        UT 234280    28    P      0.500              0.175        0.463          >88        UT 234290    29    E      0.500              0.177        0.460          >88        UT M-21    STEAM EXT. TO PRESEP. TANKB & 4B L.P. HEATER Summary Comp. Comp. Nominal Nominal Minimum            Minimum      Percent    NDE Number ID      T e Wall 1 Wall 2 Allowable              Readin      Nominal    Method
M-19  1A, 2A, & 3A L.P. HEATER DRAINS TO CONDENSER Summary Comp. Comp. Nominal Nominal Minimum            Minimum    Percent    NDE N m er ID      T      Will      Wll2 All w l            R    in    N min  1  Meth d 234010    01    R      0.594    0.500    0.207,0.174  0.567,0.522      >88        UT 234030    03    E      0.500              0.176        0.495          >88        UT 234040    04    P      0.500              0.173        0.484          >88        UT 234070    07    E      0.500              0.174        0.604          >88        UT 234075    07A  E      0.500              0.173        0.505          >88        UT 234080    08    E      0.500              0.174        0.517          >88        UT 234090    09    P      0.500              0.173        0.484          >88        UT 234280    28    P      0.500              0.175        0.463          >88        UT 234290    29    E      0.500              0.177        0.460          >88        UT M-21    STEAM EXT. TO PRESEP. TANKB & 4B L.P. HEATER Summary Comp. Comp. Nominal Nominal Minimum            Minimum      Percent    NDE Number ID      T e Wall 1 Wall 2 Allowable              Readin      Nominal    Method 301382    36B    P      0 375              0.184        0.347          >88      UT 301383  36C      P      0.375              0.184        0.363          >88      UT 301384  36D      P      0.37'5              0.184        0.365          >88        UT
                                                '
301382    36B    P      0 375              0.184        0.347          >88      UT 301383  36C      P      0.375              0.184        0.363          >88      UT 301384  36D      P      0.37'5              0.184        0.365          >88        UT


R. E. GINNA NUCLEAR PO%ER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)
R. E. GINNA NUCLEAR PO%ER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)
Line 1,551: Line 1,492:
                               '75503 0.181          0.143      <65      UT 375504    50D    E      0.258                    0.181          0.122      <65      UT 13
                               '75503 0.181          0.143      <65      UT 375504    50D    E      0.258                    0.181          0.122      <65      UT 13


.
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)
ATTACHMENTIII Com onent Result Details(CONTINUED)
ATTACHMENTIII Com onent Result Details(CONTINUED)
Line 1,560: Line 1,500:
C-381-358  Sh4              SW From Supply Header to Distribution Manifold C-381-358  Shs              SW  Return From SFPHX C-381-358  Sh9              SW  IB Above El. 253'6" From Pen. 308, 315, & 323 to Col. 7 C-381-358  Sh13            SW  IB Above El. 253'6" From 16" Header to Pen. 312, 316, &, 320 C'-381-358  Sh14            SW  IB Above El. 253'6" 16" & 20" Header C-381-358  Sh16            SW  IB From 14" Header to Pen. 201 & 209 C-381-358  Sh 1 7          SW  From 20" Header to MDAFW Pumps lA &. 1B C-381-358  Sh22            SW  Form Cont. Recirc. Unit 1-C to Pen. 315 C-381-358  Sh27            SW  to Cont. Recirc Cooling Unit 1C & 1D Motors C-381-358  Sh34            "A" & "B" SW pumps in Screenhouse
C-381-358  Sh4              SW From Supply Header to Distribution Manifold C-381-358  Shs              SW  Return From SFPHX C-381-358  Sh9              SW  IB Above El. 253'6" From Pen. 308, 315, & 323 to Col. 7 C-381-358  Sh13            SW  IB Above El. 253'6" From 16" Header to Pen. 312, 316, &, 320 C'-381-358  Sh14            SW  IB Above El. 253'6" 16" & 20" Header C-381-358  Sh16            SW  IB From 14" Header to Pen. 201 & 209 C-381-358  Sh 1 7          SW  From 20" Header to MDAFW Pumps lA &. 1B C-381-358  Sh22            SW  Form Cont. Recirc. Unit 1-C to Pen. 315 C-381-358  Sh27            SW  to Cont. Recirc Cooling Unit 1C & 1D Motors C-381-358  Sh34            "A" & "B" SW pumps in Screenhouse


'
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)
R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)
ATTACHMENTIII Additional lns ections: (Continued)
ATTACHMENTIII Additional lns ections: (Continued)
Line 1,590: Line 1,529:
Comp.      Comp.          Nominal      Minimum      Minimum      Percent  NDE ID        T  e          Waii        Allowable      Readin      Nominal Method WXX-02      P            0.065          0.046  ~      0.026      40      RT 33013-2027                Service Water Supply    & Return to SFPHX &#xb9;2 Comp.      Comp.          Nominal      Minimum      Minimum      Percent  NDE ID        T  e          Wall        Allowable      Readin      Nominal  Method SWXX-03      P            0.365          0.146          0.338      >88      UT 20
Comp.      Comp.          Nominal      Minimum      Minimum      Percent  NDE ID        T  e          Waii        Allowable      Readin      Nominal Method WXX-02      P            0.065          0.046  ~      0.026      40      RT 33013-2027                Service Water Supply    & Return to SFPHX &#xb9;2 Comp.      Comp.          Nominal      Minimum      Minimum      Percent  NDE ID        T  e          Wall        Allowable      Readin      Nominal  Method SWXX-03      P            0.365          0.146          0.338      >88      UT 20


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N}}
N}}

Latest revision as of 09:22, 4 February 2020

Rev 0 to Re Ginna Nuclear Power Plant 1996 ISI Program Rept.
ML17264A683
Person / Time
Site: Ginna Constellation icon.png
Issue date: 09/13/1996
From:
ROCHESTER GAS & ELECTRIC CORP.
To:
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ML17264A682 List:
References
NUDOCS 9610100113
Download: ML17264A683 (228)
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Text

ROCHESTER GAS AND ELECTRIC CORPORATION 89 EAST AVENUE, ROCHESTER, NY 14649 NUCLEAR REGULATORY COMMISSION INSERVICE INSPECTION REPORT FOR THE THIRD INTERVAL(1990 - 1999)

SECOND PERIOD, FOURTH OUTAGE (1996)

AT R. E. GINNA NUCLEAR POWER PLANT REVISION 0 SEPTEMBER 13, 1996 9610100113 960930

,'DR ADOCK 05000244 Q PDR

R. E. GINNA NUCLEAR POWER PLANT NUCLEAR REGULATORY COMMISSION INSERVICE INSPECTION REPORT THIRD INTERVAL (1990 - 1999)

SECOND PERIOD, FOURTH OUTAGE (1996)

OWNERS DATA SHEET Date: 13 September, 1996 Owner: Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649

~ ~

Plant Location and Unit No.: R. E. Ginna Nuclear Power Plant Unit One 1503 Lake Road Ontario, New York 14519 Commercial 0 eratin Date: Suly 1970 A licable Code: ASME Section XI, 1986 Edition, No Addenda

I R. E. GINNA NUCLEAR POWER PLANT Inserv ice Inspection Report 1990- 1999 Interval, Second Period, Fourth Outage (1996)

TABLE OF CONTENTS Introduction and Synopsis Summary of Work Accomplished Class 1 Components Class 2 Components Class 3 Components High Energy Components Design Break Weld Examinations Consequential Break Weld Examinations Component Support Examinations Steam Generators System Pressure Testing Hydrostatic Testing Leakage Testing Section XI, Service Induced Rejectable Components - Expanded Examinations Snubbers Visual Examinations Functional Testing Seismic Support Program Erosion/Corrosion (Minwall) Program Attachment I ISI Program Examination Summary Attachment II Repair, Replacement &, Modification Program Summary Attachment III Erosion/Corrosion (Minwall) Program Summary

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Fourth Outage (1996)

INTRODUCTION AND SYNOPSIS:

Inservice Inspection (ISI) activities for 1996 were performed on components within Class 1, 2, 3, High Energy Piping, Steam Generator Tubes, Seismic Supports and Snubbers. ISI examinations were concluded on July 2, 1996. Examination methods included Visual (VT), Liquid Penetrant (PT),

Magnetic Particle (MT), Ultrasonic (UT), Radiographic (RT), and Eddy Current (ET). Functional Testing (FT) and System Pressure Tests were also performed.

Erosion/Corrosion examinations were also performed during this time.

Personnel involved included RGAE Laboratory and Inspection Services, Sonic Systems Incorporated, Master Lee Services Corporation, ABB Combustion Engineering Corporation, Ginna Station Quality Control and the Ginna Station Results/Test Group. Additional Support Personnel included individuals from the followirig departments: Ginna Station Insulators, Maintenance, Electricians, Pipe Fitters, Health Physics, Turbine Maintenance, RG8'cE General Maintenance and the Mechanical Engineering Group of the Nuclear Engineering Services Department.

ASME SECTION XI

SUMMARY

OF WORK ACCOMPLISHED:

Upon conclusion of the 1996 Outage, 61.7% of ASME Section XI Code required examinations for the Third Interval ISI Program has been completed. A detailed component summary of all outage ISI activities with their associated results can be found within "Attachment I".

CLASS 1 COMPONENTS:

A total of 46 ASME, Augmented or Owner Elected components were examined. The examinations for these components consisted of 19 VT's, 18 PT's, 8 MT's, 17 UT's and 4 RT's. A total of 66 examinations were performed on Class 1 Components.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)

CLASS 1 COMPONENTS: Cont.

Class 1 examinations were performed on the following items/systems and/or plant lines/component:

Item/S stem Descri tion Plant Line

/Com onent CVCS-Charging System: 2C-CHS-2502 2A-CHS-2501 2-CHS-2501 2H-CHS-2501 CVCS-Letdown System: 2B-CH4-2501 High Pressure Safety Injection System: 10A-SI2-2501-B Pressurizer System: 10-RC8-2501 Reactor Coolant Pump A: PRCOl A (Studs)

Reactor Coolant Pump B: PRC01B (Bolts)

Reactor Coolant System: 29-RC -2501-A 2A-RCO-2501-A 2B-RCO-2501-B 2C-RC0-2501-B Residual Heat Removal System: 10A-AC7-2501-A 10A-AC7-2501-B Steam Generator A EMS01A (Items)

Steam Generator B EMS01B (Items)

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Fourth Outage (1996)

CLASS 2 COMPONENTS:

A total of 109 ASME or Owner Elected Components were examined. The examinations for these components consisted of 42 VT's, 26 PT's, 35 MT's, 11 RT's, and 28 UT's for a total of 142 examinations.

Class 2 examinations were performed on the following items/ systems and/or plant lines/components:

Item /S stem Descri tion Plant Line

/Com onent CVCS-Charging System: 2D-CH5-2501 8A-CH -2502 8B-CH -2502 8C-CH -2502 Feedwater System: 18A-FW-900-1A 18B-FW-900-1B 14A-FW-900-1A 14B-FW-900-1B High Pressure Safety Injection System: 2T-SI-2501 2U-SI-2501 3A-SI-1501 3C-SI-1501 4D-SI-1501 4E-SI-1501 8E-SI-301 8G-SI-301 4 -SI-301 4A-SI-301 Mainsteam System: 30A-MS-600-1A 30B-MS-600-1B Residual Heat Removal System: 6C-AC-601 6K-AC-151

R. E. GINNA NUCLEAR PO%ER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Fourth Outage (1996)

CLASS 2 COMPONENTS: Cont.

Item/S stem Descri tion Plant Line

/Com onent Steam Generator A EMS01A (Items)

Steam Generator B EMS01B (Items)

Service Water System: 6G-SW-125 8B-SW-125 8F-SW-125 8 J-SW-125 8N-SW-125 CLASS 3 COMPONENTS:

A total of 12 ASME or Owner Elected Components were examined utilizing the VT visual examination method.

Examinations were performed on the following items / systems and/or plant lines/components:

Item/S stem Descri tion Plant Line

~IC Auxiliary Cooling System: EACO I B (Integral Attachments & Supports)

Auxiliary Feedwater System: 3A -FW7-900-1A 3A -FW7-900-1B 3J -FW7-900-1 3K -FW7-900-1 Diesel Generator System: 5C-DG-B

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)

HIGH ENERGY COMPONENTS:

Five (5) Augmented or Owner Elected items associated with the High Energy Program were examined during the 1996 Outage. The examinations for these items consisted of 3 VT's, 3 MT's and 1 UT for a total of 7 examinations.

High Energy component examinations were performed on the following items / systems and/or plant lines:

Item/S stem Descri tion , Plant Line Feedwater System: 14A-FW-900-1 Mainsteam System: 24B-MS-600-1A STEAM GENERATOR TUBING:

Eddy Current ASME and Owner Elected Examinations were performed on tubes in the "A" and

'B" Steam Generators.

The following Eddy Current examinations were performed.

1. Preservice (Baseline) examinations.
2. Open Generator Tubes, Bobbin Coil, 100% Full Length.
3. Open Generator Tubes, Peripheral Tubes.

Steam Generator Eddy Current Examination details are documented in the Rochester Gas 8'c Electric 1996 Steam Generator Eddy Current Final Report.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990- 1999 Interval, Second Period, Fourth Outage (1996)

SYSTEM PRESSURE TESTS:

Leaka e Testin A total of five (5) ASME Leakage Examinations were performed. Leakage tests performed included one (1) Class 1, Reactor Coolant System (PT-7) examination and four(4) Class 2 or 3 examinations.

ASME Section XI Re uired Com onents Service Induced Re ectable - Ex anded Examinations:

There were no ASME Section XI required components that were classified as "Service Induced Rejectable" that needed Code expanded examinations.

SNUBBER PROGRAM:

Visual Examinations:

A total of 149 Snubber component supports were examined. These Augmented examinations were performed to satisfy Ginna Station Snubber Program commitment.

'nubber visual examinations were performed on the following items /systems and/or plant lines:

Item/S stem Descri tion Plant Line Steam Generator "A":

Steam Generator "B":

Auxiliary Feedwater Pump Discharge- 3K-FW7-900-1 Intermediate Building Lines: 3A-FW7-900-1A 3 J-FW7-900-1 3B-FW -900-1B 3A-FW7-900-1B 3A-FW -900-1A'B-FW

-900-1A

l, i

"R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990- 1999 Interval, Second Period, Fourth Outage (1996)

SNUBBER PROGRAM: Cont.

Visual Examinations:

Item/S stem Descri tion Plant Line Turbine Driven Auxiliary Feedwater 4A-CD-150-1C Pump Suction Line:

Steam Generator B, Blowdown Line: 2C-MS-600-1B Auxiliary Cooling Lines: 4S-AC6-152 3E-AC6-152 4T-AC6-152 2-IN. Letdown Lines: 2A-CH4-2501 2H-CH -601 2A-CH4-151 2-IN. Charging Line: 2G-CH5-2502 2-IN. Alternate Charging Line: 2F-CHS-2501 CVCS Relief Line: 2E-CH-601 Reactor Coolant Pump "1B" Seal 2H-CHS-2501 Water Line:

Reactor Coolant Pump "1A" Seal 2P-CH-2501 Water Line:

Feedwater Loop "A" & "B" Lines: 14A-FW-900-1A 14A-FW-900-1 14B-FW-900-1B 14B-FW-900-1

~ ~

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)

SNUBBER PROGRAM: Cont.

Visual Examinations:

Item /S stem Descri tion Plant Line Main Steam Lines: 30A-MS-600-1A 30B-MS-600-1B 6A-MS-600-1A 6B-MS-600-1A 6B-MS-600-1B 6A-MS-600-1 6B-MS-600-1 Safety Injection Lines: 10A-SI2-2501-A 10A-SI2-2501-B 10 -SI -151 8J-SI -151 4 -SI -301 Residual Heat Removal Lines: 10 -AC -601 10A -AC7-2501-B 10A -AC7-2501-A 10D -AC -601 10E -AC -601 10G -AC -601 10GG-AC -151 8B -AC -601 6 -AC -601 6D -AC -601 6K -AC -151 Service Water Lines: 10B-SWO-125-1 8A-SWO-125-1 8L-SW -125

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)

SNUBBER PROGRAM: Cont.

Visual Examinations:

Item /S stem Descri tion Plant Line Standby Auxiliary Feedwater Lines: 3C-FW-902S-1A 3C-FW-902S-1B Pressurizer Relief Lines: 6AP-RC -602 6BP-RC -602 3BP-RC -602 3B -RC8-2501 3A -RC8-2501 Seal, Water Return Lines: 2X-CH-2501 Functional Testin:

A total of twenty-one (21) snubbers were Functionally Tested (FT) during the 1996 outage. From the twenty (20) snubbers that were originally scheduled, fourteen (1 4) were mechanical snubbers and six (6) were hydraulic snubbers. Due to snubber failure, an expansion was performed that consisted of one (1) additional snubber that was Functionally Tested.

Snubber Functional Tests (FT) were performed on the following supports.

Mechanical Snubbers.

CVU-131 FWU-18 FWU-23 FWU-42 RHU-123 RHU-109 MSU-58 MSU-57 MSU-19(North) MSU-22 MSU-18(South) MSU-19(South) MSU-72 .AFU-227 H draulic Snubbers:

PS-6 N616 AFU-224 AFU-226(*) AFU-229 AFU-208 SGA-8 Note: (*) = Expanded Snubber Functional Test

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Fourth Outage (1996)

SEISMIC SUPPORT PROGRAM:

A total of seven (7) Augmented or Owner Elected Seismic Supports were inspected utilizing the visual (VT) examination technique.

Seismic Support examinations were performed on the following items/systems and/or plant lines:

Item/S stem Descri tion Plant Line CVCS-Letdown System: 3 -RC-601 High Pressure Safety Injection: 2H-SI-902 Mainsteam System: 6B-MS-600-1A 6C-MS-600-1B 6D-MS-600-1B Blowdown System: 2E-BD-600-1A 2E-BD-600-1B EROSION/CORROSION MINWALLPROGRAM:

A total of 98 items were examined during the 1996 Outage. The breakdown of this total is as follows:

Com onent T e TAHITI Pipes 45 Elbows 39 Reducers 12 Tees 2 10

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)

EROSION/CORROSION MINWALLPROGRAM: Cont.

Component thickness measurements were performed on the following systems:

DWG.

NO. SYSTEM M-12A MSR 1A &, 1B 2ND PASS TO SA HEATER AND CONDENSER M-12B MSR 2A &, 2B 2ND PASS TO 5B HEATER AND CONDENSER M-15B MSR 1B 4TH PASS TO SA HEATER M-19 1A, 2A, & 3A L.P. HEATER DRAINS TO CONDENSER M-21 STEAM EXT. TO PRESEP. TANKB & 4B L.P. HEATER M-22 STEAM EXT. TO PRESEP. TANK A Ec 4A L.P. HEATER M-75 STEAM EXTRACTION TO 5A 8c 5B HEATERS M-81 FEEDWATER DISCHARGE (TURBINE BUILDING)

M-84 FEEDWATER TO S/G 1A (CONTAINMENT)

M-85 FEEDWATER TO S/G.1B (CONTAINMENT)

M-88D S/G BLOWDOWN TO FLASH TANK (TURBINE BUILDING)

M-91 FEEDWATER CLEANUP (CV-19)

M-92 MAINFEEDWATER PUMP RECIRCULATION M-99 GLAND STEAM CONDENSER TO TURB. GEN. & GOV.

M-100 MAINGLAND STEAM TO TURB. GEN. & GOV. ENDS M-103 F.W. HTR. DRAIN SYS. FROM H.D PUMPS TO H.T. TANK

R. E. GINNANUCLEAR POWER PLANT Inservice Inspection Report 1990- 1999 Interval, Second Period, Fourth Outage (1996)

The statements made in this report and attachments are correct and the examinations and corrective measures taken conform to the Rules of the ASME Code,Section XI.

prepared By; ~ .

Frank A. Klepacki ISI Engineer

//3/Pd Date Approved y: >/~/~<

Michael J. Sa orito Date Manager, Laboratory and Inspection Services, Technical Performance and Field Inspections Certificate of Inservice Ins ection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspections and the State or Province of New York and employed by The Hartford Steam Boiler Ins ection and Insurance Com an have inspected and/or verified the components described within tl~s report and associated Attachments during the stated reporting time frame, and state to the best of my knowledge and belief, the Owner has performed examination and corrective measures described in this Report in accordance with the requirements of the ASME Code,Section XI.

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.

Reviewed By: +~~ ~i 8 Wl~~ s/za+es ANII's Signature Date 12

FORM NIS-1 OWNER'S REPORT FOR INSERVZCE INSPECTIONS As re uired bv the Provisions of the ASME Code Rules

l. Owner Rochester Gas 6 Electric Cor . 89 East Ave. Rochester N.Y. 14649 (Nante and Address of Quitter)
2. Plant R.E. Ginna Nuclear Power Plant 15 03 Lake Road Ontario NY 1 4 5 1 9 (Name and Address of Plant)
3. Plant Unit 4. (hvner Certificate of Authorization (ifrequired) N/A
5. Conunercial Service Date Jul 1970 6. National Board Number for Unit N/A
7. Components Inspected Manufacturer Component or hfanufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.

(*) SEE "ATTACHMENT I" FOR APPLICABLE INFORMATION Note: Supplemental siteets in form of lists, sketches, orArawings may be used, provided(1) size is 8-1/2 in. x I I in., (2) inforntatlon in items I tluou8It 6 on this report is included on each sheet, and (3) each sheet is numbered and thc number of sheets is recorded at thc top of this form.

(12/86) This form (E0029) may bc obtained from the Order D ~, ASh IE, 22 Law Drive, Box 2300, Fairfield, NJ07007-2300

0 FORM NIS-1 (Back)

8. Exainination Dates 11/27/95 to 7/02/96 9. hlspection Interval from 1990 to 1999
10. ApplicableEditionsofScctionXI 1986 Addenda No
11. Abstract of Examinations, Include a list of examinations and a statement concerning status of work required for current interval. (*)
12. Abstract of Conditions Noted. (*)
13. Abstract of Corrective Measures Recoiiunended and Taken. (*)

IVc ccttify that statements made in this report arc correct and the examinations and corrective measures taken conform to the rules of the ASME Code, Section XI.

CertiTicate of Authorization No. (ifapplicable) N/A Expiration Date N/A Date 13 Se member 19 96 Signed Rochester GaB A Flectric Cn mtion GNtter ISI Engineer CERTIFICATE OF INSERVICE INSPECTION I, Ibe undesigned, holding a vsgd conunisdon issn d by tbc Na lion st Board of Boiler and Presto o Vessel Inspcdora and the State or Province Zgdt andonptoy dby a

. c ~ of a of~

have inspected the components described in this Ohhltei's Report during the period df a M to and state that to thc best of my hlowledge and belief, thc Ohvncr llas perfomled examinations and taken corrective measures described in this Ohvnei's Report in accordance with the inspection plan and as required by the ASME Code, Section Xl.

By signing this certificate ncithcr thc Inspector nor his employer makes any warranty, expressed or implied, concenling the examinations and corrective measures described in this Ghvner's Rcport. Furthemiore, neither the hlspector nor his employer shall bc liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

~cz 8. W Inspector's Signature Conlillissions National Board, State, Province, and Endorsements 19 94

(*) SEE "ATTACHMENT I" FOR APPLICABLE INFORMATION 2

R. E. G1NNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 5970 S.National Board Number for Unit N/A ATTACHMENT I A. CLASS 1 COMPONENTS:

Al . STEAM GENERATOR A DRAWINGS: A-5 Summary Etiam Item Number Categ Number Component Component Type 005700 B-B B2.40 LHTSW-AR ASME UT LOWER HEAD-TO-TUBE SHEET WD 96 -UT: PERFORMED BY B&W, REF'EPORT ()7705-1-22: -ACCEPTABLE.

005900 B-D B3.140 INIR-AR OE UT INLET NOZZLE INSIDE RADIUS SECTION 96 -UT; NO RECORDABLE INDICATIONS ACCEPT. > 90% COVERAGE.

005990 B-F B5.70 NSE-1R ASME PT SAFE END-TO-NOZZLE UT (INLET) 96 -PT & UTr'O RECORDABLE INDICATIONS ACCEPTABLE.

PT & UT PERFORMED BY B&W UNDER REPORT () 7705-1-55.

006000 B-J B9.11 PL-FW-I-ASW-R OE PT ELBOW-TO-SAFE END RT 96 -PT & RT; PERFORMED BY BECHTEL (CONAM)- ACCEPTABLE.

006100 B-D B3.140 ONIR-AR UT OUTLET NOZZLE INSIDE RADIUS SECTION 96 -UT: NO RECORDABLE INDICATIONS ACCEPTABLE.

NOTE: "COMPONENT TYPE",ZS DEFINED AS FOLLOWS:

"ASME"= ITEM REQUIRED BY ASME SECTION XI CODE AUG99 = AUGMENTED PROGRAM ITEM REQUIRED BY NRC COMMITMENT "OE" = OWNER ELECTED NON MANDATORY EXAMINATIONS

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N1A S.Commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 1 COMPONENTS (CONT.)

Al. STEAM GENERATOR A (CONT.) DRAWINGS: A-5 Summary Exam Item Number Categ Number Component Component Type aa rara ararraaaaaararaaaraaar 006190 B-F B5.70 NSE-2R PT NOZZLE-TO-SAFE END UT (OUTLET) 96 PT & UT'ERFORMED BY B&Ws REPORT I 7705 1 566 ACCEPTABLE.

UT; PERFORMED BY RG&E NO RECORDABLE INDICATIONS ACCEPTABLE.

006200 B-J B9.11 PL-FW-ZX-ASW-R OE PT SAFE END-TO-ELBOW RT (OUTLET) 96 -PT & RT; PERFORMED BY BECHTEL (CONAM) - ACCEPTABLE.

006430 B-G-2 B7.30 ZMN-AR VT INLET MANWAY NUTS (20) MT

,96 -VT & MTS NO RECORDABLE INDICATIONS ACCEPTABLE.

006435 B-G-2 B7.30 IMS-AR OE VT INLET MANWAY STUDS (20) MT 96 -VT & MTS'O RECORDABLE INDZCATZONS ACCEPTABLE.

006530 B-G-2 B7.30 OMN-AR OE VT OUTLET MANWAY NUTS (20) MT 96 -VT & MT; NO RECORDABLE INDICATIONS ACCEPTABLE.

006535 B-G-2 B7.30 OMS-AR OE VT OUTLET 'MANWAY STUDS (20) MT 96 -VT & MTS'O RECORDABLE INDICATIONS - ACCEPTABLE.

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

l. Owner Rochester Gas & Electric Cor .,89 East Ave. Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/'A 5.Commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 1 COMPONENTS (CONT ~ ):

A1. STEAM GENERATOR A (CONT. ) DRAWINGS: A-5 Summary Exam Item NDE Number Categ Number Component Component Type Exam BSS 006609 F-A Fl.40 SGA-SL OE VT SUPPORT COMPONENT-LEGS A TO D 96 -VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

006641 F-A F1.40 SGA-MS VT MZD SUPPORT 96 -VT; NO RECORDABLE ZNDICATIONS - ACCEPTABLE.

006644 F-A F1.40 SGA-RS OE VT RING SUPPORT 96 -VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

A2. STEAM GENERATOR B DRAWINGS: A-5 Summary Exam Item Number Categ Number Component Component Type Exam SBSBRR SB BS RK BSR RBB R Nr SBBB Nf 006700 B-B B2.40 LHTSW-BR UT LOWER HEAD-TO-TUBE SHEET WELD 96 UT r PERFORMED BY B &W6 RE PORT I 77 05 2 "22 f ACCE PTABLE 006900 B-D B3.140 INIR-BR UT INLET NOZZLE INSIDE RADIUS SECTION 96 -UT; NO RECORDABLE INDICATIONS ACCEPTABLE.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road Ontario NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 1 COMPONENTS (CONT ~ )-

a A2. STEAM GENERATOR B (CONT. ) DRAWINGS: A-5 Summary Exam Item Number Categ Number Component Component Type Exam 006990 B-F B5.70 NSE-3R PT SAFE END-TO-NOZZLE UT (INLET) 96 PT & UTf'ERFORMED BY B&WS REPORT g 7705 2 55f ACCEPTABLE.

UT; NO RECORDABLE INDICATIONS ACCEPTABLE.

007000 B-J B9.11 PL-FW-III-R ASME PT ELBOW-TO-SAFE END RT (INLET) 96 -PT & RT; PERFORMED BY BECHTEL (CONAM) ACCEPTABLE.

007100 B-D B3.140 ONIR-BR UT OUTLET NOZZLE INSIDE RADIUS SECTION 96 -UT; NO RECORDABLE INDICATIONS ACCEPTABLE.

007190 B-F '5.70 NSE-4R NOZZLE-TO-SAFE END ASME PT UT

~

(OUTLET) 96 -PT & UT; PERFORMED BY B&W, REPORT )) 7705-2-56, ACCEPTABLE.

UTS'O RECORDABLE INDICATIONS - ACCEPTABLE.

007200 B-J B9.11 PL-FW-X-R ASME PT SAFE END-TO-ELBOW RT (OUTLET) 96 -PT & RT; PERFORMED BY BECHTEL (CONAM), ACCEPTABLE.

007430 B-G-2 B7.30 IMN-BR OE VT INLET MANWAY NUTS (20) 96 -VT & MT; NO RECORDABLE INDICATIONS - ACCEPTABLE.

i R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990"1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor . 89 East Ave. Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.Commercial Service Date ~cul 1970 6.National Board Number for Unit N/A ATTACHMENT CLASS 1 COMPONENTS (CONT.):

A2. STEAM GENERATOR B (CONT.) DRAWINGS: A-5 Summary Item Number Categ Number Component Component Type 007435 B-G-2 B7.30 IMS-BR OE VT INLET MANWAY STUDS (20) MT 96 -VT & MT; NO RECORDABLE INDICATIONS ACCEPTABLE.

007530 B-G-2 B7.30 OMN-BR OE VT OUTLET MANWAY NUTS (20) MT 96 -VT & MTa NO RECORDABLE INDICATIONS ACCEPTABLE.

007535 B-G-2 B7.30 OMS-BR OE VT OUTLET MANWAY STUDS(20) MT 96 -VT & MT; NO RECORDABLE INDICATIONS ACCEPTABLE.

007609 F-A F1.40 SGB-SL OE VT SUPPORT COMPONENT LEGS H TO K 96 -VTr NO RECORDABLE INDICATIONS ACCEPTABLE.

007641 F-A F1.40 SGB-MS OE VT MID SUPPORT 96 -VTr NO RECORDABLE INDICATIONS ACCEPTABLE ~

007644 F-A F1.40 SGB-RS OE VT RING SUPPORT 96 -VTr'O RECORDABLE INDICATIONS ACCEPTABLE.

0 R. E. GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.commercial Service Date ~cul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 1 COMPONENTS (CONT. )

A3. REACTOR COOLANT SYSTEM-LOOP A DRAWINGS: A-3A Summary Item Number Categ Number Component Component Type 011000 B9.31 PL-FW-II/10A-RCO-2501-A ASME PT 10" BRANCH WELD UT 96 -PT; ACCEPTABLE - 1 ROUNDED INDICATION.

UTf NO RECORDABLE INDICATIONS ACCEPTABLE.

A4. 10-1N. PRESSURIZER SURGE LINE DRAWINGS: A-3D Summary Item NDE Number Categ Number Component Component Type Exam 014000 B9.11 A ASME UT REDUCER"TO-PIPE PT (SURGE LINE) 96 -PT & UT; NO RECORDABLE INDICATIONS ACCEPTABLE.

014400 F-A F1.10V RCU-1 VT VARIABLE SPRING 96 VT -BP SI ZiE 1 4 9 SETTING 33 1 9 g S ACCEPTABLE ~

A5. 2-ZN. PRESSURIZER SPRAY LINE DRAWINGS: A-11 Summary Item Number Categ Number Component Component Type aaa a a aaaaaaa a aaaa aaaaaaaaaaa aaa 025100 B-J B9.40 19 ASME PT COUPLING- TO-PI PE a

96 -PT; NO RECORDABLE INDICATIONS ACCEPTABLE.

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Znterval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~oui 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 1 COMPONENTS (CONT.)

A6. RESIDUAL HEAT REMOVAL FROM LOOP A HOT LEG DRAWINGS: A-15 Summary Item Number Categ Number Component Component Type 031125 F-A F1.10S RHU-33 OE VT MECHANICAL SNUBBER 96 VTr S/N 70649 SETTING 3 1/4 r'O RECORDABLE INDICATIONS ACCEPTABLE.

A7. 2" LETDOWN FROM REGEN HTX DRAWINGS: A-24 Summary Exam Item Number Categ Number Component Component Type 048200 B-J B9.40 1 PT NOZZLE-TO-PIPE 96 -PTr'O RECORDABLE INDICATIONS ACCEPTABLE'8.

SEAL WATER TO RCP-B DRAWINGS: A-32 Summary Exam Item NDE Number Categ Number Component Component Type Exam RSBS CBB C QR C R BB CC C BB ms cBBQ 049370 F-A F1.10S CVU-104 OE VT MECHANICAL SNUBBER 96 VTr PSA 1 9 S/N 24499 SETTING 2 9 NO RECORDABLE INDICATIONS ACCEPTABLE ~

A9. 2" CHARGING TO LOOP B COLD LEG DRAWINGS: A-25 Summary Exam Item Number Categ Number Component Component Type 051300 B-J B9.40 28 ASME PT PIPE-TO-NOZZLE 96 -PT; NO RECORDABLE INDICATIONS ACCEPTABLE.

R. E. GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Oui 1970 6.National Board Number for Unit N/A ATTACHMENT I CLASS 1 COMPONENTS (CONT. )

A10. 2" ALTERNATE CHARGING TO LOOP A COLD LEG DRAWINGS: A-26 Summary Item Number Categ Number Component Component Type Exam 051600 B-J B9.40 21 ASME PT PIPE-TO-ELBOW 96 -PT; NO RECORDABLE INDICATIONS ACCEPTABLE.

052300 B-J B9.40 28 ASME PT ELBOW-TO-PIPE 96 -PT; NO RECORDABLE INDICATIONS ACCEPTABLE.

053300 B-J B9.40 38 AUG PT VALVE(383A)-TO-PIPE UT 96 -PT & UT; NO RECORDABLE INDICATIONS - ACCEPTABLE.

A11. 2" ALTERNATE CHARGING TO LOOP B HOT LEG DRAWINGS: A-27 Summary Exam Z tern Number Categ Number Component Component Type 054980 B-J B9.40 9E ASME PT TEE-TO-PIPE 96 -PT; NO RECORDABLE INDZCATZONS - ACCEPTABLE.

055100 B-J B9.40 11 AUG PT VALVE(393)-TO-PIPE UT 96 -PT & UT; NO RECORDABLE INDICATIONS - ACCEPTABLE.

10

0 R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Znterval,, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave. Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A B.commercial Service Date ~Jul 1970 B.National Board Number for Unit N/A ATTACHMENT I CLASS 1 COMPONENTS (CONT.):

A12. REACTOR COOLANT PUMP A DRAWINGS: A-7 Summary Ztem Number Categ Number Component Component Type 056812 B-G-1 B6.180 STUD $ 12 OE UT BOLTINGf INPLACE 96 -UT; NO RECORDABLE INDICATIONS ACCEPTABLE.

056818 B-G-1 B6.180 STUD ()18 OE UT BOLTING, INPLACE 96 -UT; NO RECORDABLE INDICATIONS ACCEPTABLE.

A13. REACTOR COOLANT PUMP B DRAWINGS'-6 Summary Item Number Categ Number Component Component Type 058120 BOLT RCP-B ANCHOR BOLTS OE UT BOLTS 96 -UT; INSIGNIFICANT; INDICATION STILL SEEN ON STUD N2.

NO CHANGE SINCE LAST EXAMINATION IN 1995 ACCEPTABLE.

A14. H.P. SAFETY INJECTION LINE TO LOOP B COLD LEG DRAWINGS: A-16 Summary Exam Item Number Categ Number Component Component Type BB~BBBBB BBBBBBBBBBBBBB~BBBBBBMBBBBMMBB 058300 B-G-2 B7.70 V-842A (BOLTING) ASME VT 10" DARLING CHECK VALVE 96 -VT; TAKING CODE CREDIT THIS OUTAGE ACCEPTABLE.

R. E. GINNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas a Electric Cor . 89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 1 COMPONENTS (CONT. ):

A15. RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG DRAWINGS: A-14 Summary Exam Item Number Categ Number Component Component Type 059300 B-G-2 B7.70 V-720 ( BOLTING) ASME VT 10" VELAN MOTOR OPER.

GATE VALVE 1500N 96 -VT; TAKING CODE CREDIT THIS OUTAGE ACCEPTABLE.

B. CLASS 2 COMPONENTS:

Bl. 2" CHARGING FROM REGEN HTX DRAWINGS: A-29 Summary Exam item Number Categ Number Component Component Type Exam 050930 C3.20 CVU-54 (IA) PT INTEGRAL ATTACHMENT 96 -PT; NO RECORDABLE INDICATIONS ACCEPTABLE.

050933 F1.20R CVU-'54 VT RIGID RESTRAINT (IA) 96 -VT; DRAWING DOES NOT SHOW MISSING EDGE WELDS, ACTION REPORT 96-0433 GENERATED. ACCEPT AS IS-DWG TO BE CHANGED. NO RECORDABLE INDICATIONS ACCEPTABLE.

12

8 R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649

'2. Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road Ontario, NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~cul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.):

B2. STEAM GENERATOR A DRAWINGS: B-1 Summary Item Number Categ Number Component Component Type 070700 C1.30 TSSW-AR OE UT TUBE SHEET-TO-SHELL WELD 96 -UT: PERFORMED BY B&W, REPORT I 7705-1-77 - ACCEPTABLE.

070900 C-A C1.10 LST-AR OE UT LOWER SHELL-TO-TRANSITION CIRC WELD 96 -UT; PERFORMED BY B&W, REPORT () 7705-1-80, - ACCEPTABLE.

071000 C-A C1.10 TUS-AR OE UT TRANSITION-TO-UPPER SHELL CIRC WELD 96 UT PERFORMED BY B&WS REPORT g 7705 1 1 60/ 1 59 f ACCEPTABLE 071100 C-A C1.20 USH-AR OE UT UPPER SHELL-TO-HEAD CIRC WELD 96 UTa PERFORMED BY B&WS REPORT () 7705 1 1629 ACCEPTABLE.

071200 C-B C2.21 FWIN-AR MT FEEDWATER INLET NOZZLE UT TO VESSEL WELD 96 -MT & UT; PERFORMED BY B&W, REPORT I 'S 17 & 7705-1-169, - ACCEPTABLE.

071250 C-B C2.22 FWIN-AR OE UT FEEDWATER INLET NOZZLE INSIDE RADIUS 96 -UT; NO RECORDABLE INDICATIONS - ACCEPTABLE.

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor ., 89 East Ave., Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.):

B2. STEAM GENERATOR A (CONT.) DRAWINGS'-1 Summary Exam Item NDE Number Categ Number Component Component Type Exam 071360 C-C C3.10 AB1R OE MT EARTHQUAKE BRACKET IA 96 MTa PERFORMED BY B&WS REPORT ¹ 1 8f ACCEPTABLE ~

071362 C-C C3.10 AB2R OE MT EARTHQUAKE BRACKET IA 96 MT r'ERFORMED BY B &W9 REPORT ¹ 18f ACCEPTABLE ~

071364 C-C C3.10 AB3R OE MT EARTHQUAKE BRACKET IA 96 MTr PERFORMED BY B&WS REPORT ¹ 18 9 ACCEPTABLE 071366 C-C C3.10 AB4R MT EARTHQUAKE BRACKET IA 96 MT PERFORMED BY B&WS REPORT ¹ 18f ACCEPTABLE ~

B3., STEAM GENERATOR B DRAWINGS B-1 Summary Exam Item Number Categ Number Component Component Type m m 071400 C-A C1.30 TSSW-BR ASME UT TUBE SHEET-TO-SHELL WELD 96 -UT; PERFORMED PY B&W, REPORT ¹ 7705-2-77, ACCEPTABLE.

14

R. E. GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT Z CLASS 2 COMPONENTS (CONT. )

B3. STEAM GENERATOR B (CONT.) DRAWINGS: B-1 Summary Exam Item NDE Number Categ Number Component Component Type Exam 071600 C-A C1.10 LST-BR OE UT LOWER SHELL-TO-TRANSITION CIRC WELD 96 -UT; PERFORMED BY B&W, REPORT N 7705-2-80, ACCEPTABLE.

071700 C-A C1.10 TUS-BR OE UT TRANSITION-TO-UPPER SHELL CIRC WELD 96 UTS PERFORMED BY B&WS REPORT g 7705 2 160/159, ACCEPTABLE.

071800 C-A C1.20 USH-BR OE UT UPPER SHELL-TO-HEAD CIRC WELD 96 -UTa PERFORMED BY B&W, REPORT () 7705-2-162, - ACCEPTABLE.

071900 C-B C2.21 FWIN-BR OE MT FEEDWATER INLET NOZZLE UT TO VESSEL WELD 96 -MT & UT; PERFORMED BY B&W, REPORT O'S 18 & 7705-2-169, - ACCEPTABLE.

071950 C-B C2.22 FWIN-BR OE UT FEEDWATER INLET NOZZLE INSIDE RADIUS 96 -UTS'O RECORDABLE INDICATIONS - ACCEPTABLE.

a 072080 C-C C3.10 'BB1R OE EARTHQUAKE BRACKET - IA 96 MTS PERFORMED BY B&WS REPORT () 18 9 ACCEPTABLE ~

15

l R. E. GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave. Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.Commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.)

B3. STEAM GENERATOR B (CONT.) DRAWINGS: B-1 Summary Exam Item Number Categ Number Component Component Type 072082 C-C C3.10 BB2R OE MT EARTHQUAKE BRACKET - IA 96 -MT; PERFORMED BY B&W, REPORT ¹ 18, ACCEPTABLE.

072084 C-C C3. 10 BB3R OE EARTHQUAKE BRACKET IA 96 -MTr'ERFORMED BY B&W, REPORT ¹ 18, ACCEPTABLE.

072086 C-C C3.10 BB4R MT EARTHQUAKE BRACKET IA 96 -MT; PERFORMED BY B&W, REPORT ¹ 18, - ACCEPTABLE.

B4. CHARGING PUMP A TO PULSE DAMPENER DRAWINGS: B-6 Summary Exam Item Number Categ Number Component Component Type Exam 075700 C-F-1 C5.11 1 VT CAP-TO-PIPE PT 96 -PTa REJECTf'/4" LONG INDICATION WITHIN ARC STRIKE, CONSTRUCTION, NOT SERVICE INDUCED. ACTION .REPORT 96-0412 GENERATED, CODE REPAIR MADE. RE-EXAM ACCEPTABLE. VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

075900 C-F-1 C5.11 3 ASME PT ELBOW-TO-PIPE UT 96 -PT & UTf'O RECORDABLE INDICATIONS ACCEPTABLE.

16

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.commercial Service Date ~Jul 1970 6.National Board Number for Unit N/JL ATTACHMENT I CLASS 2 COMPONENTS (CONT.):

B4. CHARGING PUMP A TO PULSE DAMPENER (CONT) DRAWINGS B-6 Summary Exam Item Number Categ Number Component. Component Type m

077400 F1.20R CVU-410 OE VT RIGID RESTRAINT (IA) 96 VT r RE JECT SELF LOCK1NG NUTS LOOSE (4 THREADS ) f ACTION REPORT 96-0411 GENERATED. RE-EXAM AFTER TIGHTENING ACCEPTABLE.

NOT SERVICE INDUCED.

077401 C-C C3.20 CVU-410 (IA) ASME PT INTEGRAL ATTACHMENT 96 -PTr REJECT; POOR ORIGINAL CONSTRUCTION WELD QUALITY. ACTION REPORT 96-0411 GENERATED. WELD REWORKED. RE-EXAM ACCEPTABLE.

NOT SERVICE INDUCED.

B5. CHARGING PUMP C TO PULSE DAMPENER DRAWINGS'-6 Summary Exam Item Number Categ Number Component Component Type 076800 C-F-1 C5.11 2 ASME PT PIPE-TO-ELBOW UT 96 -PT & UT; NO RECORDABLE INDICATIONS ACCEPTABLE.

17

R. E. GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A B.commercial Service Date ~Jul 1970 6.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.):

B6. CHARGING PUMP B TO PULSE DAMPENER DRAWINGS B-6 Summary Exam Item Number Categ Number Component Component Type 077600 F-A F1.20R CVU-412 OE VT RIGID RESTRAINT (IA) 96 -VT; REJECT; INTEGRAL ATTACHMENT ORIGINAL CONSTRUCTION POOR WELD QUALITY ACTION REPORT 96 0411 GENERATED'ELD REWORKEDf RE-EXAM - ACCEPTABLE. NOT SERVICE INDUCED.

077601 C-C C3.20 CVU-412 (IA) PT INTEGRAL ATTACHMENT 96 -PTr'EJECTr'NTEGRAL ATTACHMENT ORIGIONAL CONSTRUCTION POOR WELD QUALITY. ACTION REPORT 96-0411 GENERATED. WELD REWORKED, RE-EXAM ACCEPTABLE. NOT SERVICE INDUCED.

B7. MAIN STEAM LOOP A INSIDE CV DRAWINGS: B-8 Summary Exam Item Number Ca'teg Number Component Component Type 079000 C-F-2 C5.51 A-R OE MT NOZZLE-TO"ELBOW UT (S/G-A) 96 '-MTr'XAM PERFORMED BY BECHTEL (CONAM) ACCEPTABLE. UT; NO RECORDABLE

& INSZGNIFZCANT; GEOMETRY ACCEPTABLE.

079175 C-F-2 C5. 51 A1Z OE MT PI PE- TO- PI PE RT 96 -MT & RT; PERFORMED BY BECHTEL (CONAM) - ACCEPTABLE.

079200 C-F-2 C5. 51 A1-R OE MT PI PE- TO- PI PE RT 96 -MT & RT; PERFORMED BY BECHTEL (CONAM) ACCEPTABLE.

18

R. E. GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric'Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.Commercial service Date ~oui 1970 B.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT. ) "

B7. MAIN STEAM LOOP A INSIDE CV (CONT) DRAWINGS: B-8 Summary Item Number Categ Number Component Component Type 079500 '1.20V MSU-1 OE VT VARIABLE SPRING 96 -VTf'ETTING 3 1/2" = 11123 O'S, NO RECORDABLE INDICATIONS - ACCEPTABLE.

079600 F-A F1.20S MSU-2 OE VT MECHANICAL SNUBBER 96 -VT; SETTING 3 3/4", NO RECORDABLE ZNDICATIONS ACCEPTABLE.

079700 F-A F1.20S MSU-3 VT MECHANICAL SNUBBER (ZA) 96 VT SETTING 3 9 NO RECORDABLE INDICATIONS ACCEPTABLE 079750 C-C C3.20 MSU-3 (IA) MT INTEGRAL ATTACHMENT 96 -MTr'O RECORDABLE INDICATIONS ACCEPTABLE.

080000" F-A F1.20V MSU-4 OE VT VARIABLE SPRING 96 VTa SETTING 1 1/4 = >7989 g Sf NO RECORDABLE INDICATIONS ACCEPTABLE.

080100 F-A F1.20V MSU-5 ASME VT VARIABLE SPRING 96 -VT: REJECT; LACK OF THREAD ENGAGEMENT. ACTION REPORT 96-0489 GENERATED.

BECHTEL PERFORMED REWORK. RE-EXAM ACCEPTABLE. NOT SERVICE INDUCED.

19

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor ., 89 East Ave., Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.):

B8. MAIN STEAM LOOP A OUTSIDE CV DRAWINGS B-9 Summary Exam Item NDE Number Categ Number Component Component Type Exam 081550 C-F-2 C5.52 E1L1 ASME VT ELBOW LONGITUDINAL MT WELD UT 96 -VT & MT; NO RECORDABLE 1NDZCATIONS ACCEPTABLE. UT; NO RECORDABLE

& INSIGNIFICANT; NO CHANGE SINCE LAST EXAM ACCEPTABLE.

081650 C-F-2 C5.51 E1A VT PIPE-TO-ELBOW MT UT 96 -VT & MT; NO RECORDABLE INDICATIONS - ACCEPTABLE. UT; NO RECORDABLE

& COUNTERBORE GEOMETRYa ACCEPTABLE.

B9. MAIN STEAM LOOP B INSIDE CV 6 DRAWINGS '-8 Summary Exam Item NDE Number Categ Number Component Component Type Exam 084400 C-F-2 C5.51 A-R MT NOZZLE-TO-ELBOW UT (S/G-B) 96 -MTa PERFORMED BY BECHTEL (CONAM) ACCEPTABLE. UT; NO RECORDABLE ID GEOMETRY - ACCEPTABLE.

084600 C-F-2 C5.51 Al-R MT PIPE-TO-ELBOW RT 96 -MT & RT; PERFORMED BY BECHTEL (CONAM) ACCEPTABLE.

v 084700 F-A F1.20V MSU-6 VT

'ARIABLE SPRING 96 -VT; SETTING 7900 ))'S, NO RECORDABLE INDICATIONS - ACCEPTABLE.

20

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~cul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.)

B9. MAIN STEAM LOOP B ZNSZDE CV (CONT.) DRAWINGS: B-8 Summary Exam Item Number Categ Number Component Component Type Exam 084900 F-A'1.20S MSU-7 ASME VT MECHANICAL SNUBBER 96 -VT; SETTING 3" & 2 3/4". NO RECORDABLE INDICATIONS ACCEPTABLE.

085200 F-A F1.20S MSU-8 OE VT HYDRAULIC SNUBBER 96 -VT; REJECTa INCORRECT SETTING & NUT/BOLT TURNS AS ONE. ACTION REPORT 96-0465 GENERATED. RE-EXAM AFTER ADJUSTMENTS ACCEPTABLE. NOT SERVICE INDUCED.

085300 F-A F1.20V MSU-9 OE VT VARIABLE SPRING 96 -VTa SETTING = 7400 O'S, INSIGNIFICANT; LACK OF THREAD ENGAGEMENT BY ONE THREAD OK PER MECH. ENG. LETTER ACCEPTABLE.

085400 F-A F1.20V MSU-10 OE VT VARIABLE SPRING 96 VT. SETTING ~ 8554 gfS NO RECORDABLE INDICATZONS ACCEPTABLE B10. MAIN STEAM LOOP B OUTSIDE CV DRAWINGS '-10A Summary Number 087625 Exam Categ Item Number F1 '0S

'omponent Component MSU-25 m

OE Type Exam VT I

MECHANICAL SNUBBER (IA) 96 -VT; SETTING 1 3/4", NO RECORDABLE INDICATZONS ACCEPTABLE.

21

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649 2'. Plant R.E.Ginna Nuclear Power Plant,'1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.Commercial Service Date ~Jul '970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.):

B10. MAIN STEAM LOOP B OUTSIDE CV (cont.) DRAWINGS: B-10A Summary Exam Item Number Categ Number Component Component Type 087630 C-C C3. 20 MSU-25 (IA) ASME INTEGRAL ATTACHMENT 96 -MT: NO RECORDABLE INDICATIONS ACCEPTABLE.

Bll. FEEDWATER LOOP A OUTSIDE CV DRAWINGS: B-ll Summary Exam Item Number Categ Number Component Component Type 091225 F-A F1.20S FWU-15 VT MECHANICAL SNUBBER (ZA) 96 -VT; SETTING 2 5/8", NO RECORDABLE INDICATIONS ACCEPTABLE.

091226 C-C C3.20 FWU-15 (ZA) ASME INTEGRAL ATTACHMENT 96 -MT; NO RECORDABLE INDICATIONS - ACCEPTABLE.

B12. FEEDWATER LOOP A INSIDE CV DRAWINGS: B-12 Summary Exam Item Number Categ Number Component Component Type KKRRRRBS BS QSB RRRRRRRBSSS RR ~~RRBSR 092300 F-A F1. 20V FWU-6 OE VT VARIABLE S PRING 96 -VT: SETTING = 2556 O'S, NO RECORDABLE INDICATIONS ACCEPTABLE.

22

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report t

1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.)

B12. FEEDWATER LOOP A INSIDE CV (CONT.) DRAWINGS: B-12 Summary Item Number Categ Number Component Component Type 092600 F1.20V FWU-4 OE VT VARIABLE SPRING 96 -.VTl SETTING = 2797 O'S. NO RECORDABLE INDICATIONS ACCEPTABLE.

093100 F-A F1.20V FWU-2 VT VARIABLE SPRING 96 VT a SETTING 2 1 04 g S 6 NO RECORDABLE INDICATIONS ACCEPTABLE 093400 C-F-2 C5.51 DD3-R OE MT PIPE-TO-ELBOW RT 96 -MT & RTf PERFORMED BY BECHTEL (CONAM) ACCEPTABLE.

093500 F-A F1.20V FWU-1 OE VT VARIABLE SPRING (IA) 96 VTr SETTING 2617 g Sf NO RECORDABLE INDICATIONS ACCEPTABLE 093505 C-C C3.20 FWU-1 (IA) OE MT INTEGRAL ATTACHMENT 96 -MTS NO RECORDABLE INDICATIONS ACCEPTABLE.

093800 C-F-2 C5.51 DD6-R OE MT ELBOW-TO-PIPE RT 96 -MT & RT; PERFORMED BY BECHTEL (CONAM) - ACCEPTABLE.

R. E. GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.Commercial Service Date ~Jul 1970 B.National Board Number for Unit N/JL ATTACHMENT I CLASS 2 COMPONENTS (CONT.)'12.

FEEDWATER LOOP A INSIDE CV (CONT,) DRAWINGS: B-12 Summary Exam Item NDE Number Categ Number Component Component Type Exam 093900 C-F-2 C5.51 DD7-R OE MT PIPE-TO-ELBOW RT 96 -MT & RT; PERFORMED BY BECHTEL (CONAM) ACCEPTABLE.

094000 C-F-2 C5.51 DDS-R MT ELBOW-TO-PIPE RT 96 -MT & RT a PERFORMED BY BECHTEL (CONAM) ACCEPTABLE .

094200 C-F-2 C5.51 DD10-R OE MT REDUCER-TO-ELBOW RT 96 -MT & RT; PERFORMED BY BECHTEL (CONAM) ACCEPTABLE.

094300 C-F-2 C5.51 EE-R OE UT ELBOW-TO-SAFE END PT (S/G-A) 96 -PT; PERFORMED BY BECHTEL (CONAM) ACCEPTABLE. UT; NO RECORDABLE

& INS IGNI FI CANT ROOT f METALLURGICAL INTER FACE & COUNTERBORE ACCEPTABLE.

094310 C-F-2 C5.51 E-R OE UT SAFE END-TO-NOZZLE PT (S/G-A) 96 -PT & UT; PERFORMED BY B&W, REPORT O'S 16 & 7705-1-140; - ACCEPTABLE.

24

R. E. GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.):

B13. FEEDWATER LOOP B OUTSIDE CV DRAWINGS: B-14 Summary Exam Item NDE Number Categ Number Component Component Type Exam 094850 F-A F1.20R FWU-43 OE VT RIGID RESTRAINT 96 -VTa NO RECORDABLE & INSIGNIFICANT ACCEPTABLE.

B14. FEEDWATER LOOP B INSIDE CV DRAWINGS: B-13 Summary Exam Item Number Categ Number Component Component Type 097700 F-A F1.20V FWU-13 OE VT VARIABLE SPRING (IA) 96 -VT: SETTING = 3880 ()'S, NO RECORDABLE INDICATIONS ACCEPTABLE.

098100 F-A Fl.20V FWU-11 OE VT VARIABLE SPRING 96 -VT; SETTING 2199 OSS. NO RECORDABLE INDICATIONS ACCEPTABLE.

098600 F-A F1.20V FWU-10 VT VARIABLE SPRING 96 VTS SETTING 23 15 (t S 9 NO RECORDABLE & INSZGNI FICANTJ LACK OF ONE THREAD FULL ENGAGEMENT AT LOWER CLAMPS OK PER MECH ENG LETTERS ~

NOT SERVICE INDUCED ACCEPTABLE.

098825 F-A Fl.20V FWU-9 OE VT VARIABLE SPRING 96 VTS SETTING 2 8 56 g S 9 NO RECORDABLE INDICATIONS ACCEPTABLE 25

R. E. GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990"1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave. Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.):

B14. FEEDWATER LOOP B ZNSZDE CV (CONT.) DRAWINGS: B-13 Summary Exam Item NDE Number Categ Number Component Component Type Exam 098900 C-F-2 C5.51 AA-R MT PIPE-TO-ELBOW RT 96 -MT & RT; PERFORMED BY BECHTEL (CONAM) ACCEPTABLE.

099000 F-A F1.20V FWU-7 OE VT VARIABLE SPRING (IA) 96 -VT; SETTING = 2856 O'S, NO RECORDABLE INDICATIONS ACCEPTABLE.

099005 C-C C3.20 FWU-.7 (IA) OE INTEGRAL ATTACHMENT 96 -MT; NO RECORDABLE INDICATIONS ACCEPTABLE.

099500 C-F-2 C5.51 AA4-R OE MT PIPE-TO-ELBOW RT 96 -MT & RT; PERFORMED BY BECHTEL (CONAM) ACCEPTABLE.

099800 C-F-2 C5.51 AA7-R OE RT REDUCER-TO-ELBOW MT 96 -MT & RT; PERFORMED BY BECHTEL (CONAM) - ACCEPTABLE.

099900 C-F-2 C5.51 BB-R OE UT ELBOW-TO-SAFE END PT (S/G-B) VT 96 -PT; PERFORMED BY BECHTEL (CONAM) - ACCEPTABLE. UT; NO RECORDABLE

& INSIGNIFICANTa GEOMETRY & METALLURGICAL INTERFACE - ACCEPTABLE.

VTa NO RECORDABLE INDICATIONS - ACCEPTABLE.

26

n' R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.Commercial Service Date ~Jul 1970 B.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT. ):

B14. FEEDWATER LOOP B INSIDE CV (CONT. ) DRAWINGS: B-13 Summary Item NDE Number Categ Number Component Component Type Exam 099910 C-F-2 C5.51 B-R OE UT SAFE END-TO-NOZZLE PT (S/G-B) 96 PT & UTa PERFORMED BY B&Wf REPORT f) S 17 & 7705 2 1409 ACCEPTABLE.

B15. H. P. SAFETY INJECTION LINE 8E-SZ-301 DRAWINGS: B-1 6 Summary Exam Item Number Categ Number Component Component Type mfa KBBBB D Km Rt RK RK R&rmrm a 9 at aaaaaa 104200 F1.20R SZU-104 VT RIGID SUPPORT (IA) 96 -VT; NO RECORDABLE INDICATIONS - ACCEPTABLE.

104210 C-C C3.'20 SIU-104 (ZA) PT INTEGRAL ATTACHMENT 96 -PTr'O RECORDABLE INDICATIONS - 'ACCEPTABLE.

B16 ~ H.P. SAFETY INJECTION LINE 8G-SZ-301 DRAWINGS: B-19 Summary Exam Item Number Categ Number Component Component Type me 122600 F1.20R RHU-112 OE VT RIGID SUPPORT (IA) 96 -VTa NO RECORDABLE INDICATZONS - ACCEPTABLE.

122602 C-C C3. 20 RHU-112 (IA) PT INTEGRAL ATTACHMENT 96 -PT; NO RECORDABLE INDICATIONS << ACCEPTABLE.

27

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990"1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor ., 89 East Ave., Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~cul 1970 S.National Board Number for Unit N/A ATTACHMENT Z CLASS 2 COMPONENTS (CONT.):

B17. RESIDUAL HEAT REMOVAL LINE 6K-AC-151 DRAWINGS: B-21 Summary Exam Item Number Categ Number Component Component Type Exam 130050 F1.20V RHU-93 OE VT VARIABLE SPRING (IA) 96 -VT/'ETTING = 1755 LIGHT RUST &

(( ', NO RECORDABLE & INSIGNIFICANT; PEELING PAINT. BASE CHANNEL HAS HEAVY BA RESIDUE, CAN BODY HAS RE-EXAM AFTER CLEANING - NO RECORDABLE - ACCEPTABLE.

130055 ---- C3.20 RHU-93 (IA) PT INTEGRAL ATTACHMENT 96 -PT; NO RECORDABLE INDICATIONS ACCEPTABLE.

B18. RESIDUAL HEAT REMOVAL LINE 6C-AC-601 DRAWINGS: B-1 9 Summary Item NDE Number Categ Number Component Component Type Exam RRDRBBRXRSNNS NS MSN MBBBB MNS 157400 C-F-1 17 OE PT PI PE- TO-VALVE( 857C) UT 96 -PT & UT; NO RECORDABLE INDICATIONS ACCEPTABLE.

B19. H.P. SAFETY INJECTION PUMP B SUCTZON LINE DRAWINGS: B-16B Summary Exam Item NDE Number Categ Number Component Component Type Exam 160500 C-F-1 C5.21, 1 PT 8X8X4 TEE-TO-PIPE UT r

96 -PT & UT/'O RECORDABLE INDZCATIONS - ACCEPTABLE.

28

i e

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor ., 89 East Ave. Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.commercial Beruice Date ~Jul 1970 6.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.)

B20. H.P. SAFETY INJECTION PUMP A SUCTZON LZNE DRAWINGS: B-1 6B Summary Exam Item Number Categ Number Component Component Type 160850 F1. 20R RHU-120 OE VT RIGID SUPPORT (IA) 96 -VT; NO RECORDABLE & INSIGNIFICANT; HEAT TRACE CLAMPED TO SUPPORT, WELL NOT INTERFERE WITH SUPPORT FUNCTION - ACCEPTABLE.

160851 C-C C3.20 RHU-120 (IA) ASME PT INTEGRAL ATTACHMENT 96 -PTr'O RECORDABLE INDICATIONS - ACCEPTABLE.

B21. H.P. SAFETY INJECTION LINE 3A-SZ-1501 DRAWINGS: B-37 Summary Exam Item NDE Number Categ Number Component Component Type Exam 161140 C5.21 12 PT ELBOW-TO-PIPE UT 96 -PT & UT; NO RECORDABLE INDICATIONS ACCEPTABLE.

B22. H.P. SAFETY INJECTION LZNE 4D-SZ-1501 DRAWINGS: B-37 Summary Exam Item Number Categ Number Component Component Type 161425 F-A F1.20A PEN 113 ANCHOR OE VT ANCHOR ( IA) 96 -VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

161426 C-C C3.20 PEN 113 ANCHOR (IA) ASME PT INTEGRAL ATTACHMENT 96 -PT; NO RECORDABLE INDICATIONS ACCEPTABLE.

29

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.Commercial Service Date ~Jul 1970 B.National Board Number fo r'Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.):

B22. H. P. SAFETY ZNJECTZONj'LINE 4D-SZ-1501 (CONT. ) DRAWINGS: B-37 Summary Exam Item Number Categ Number Component Component Type 161530 F-A F1.20R SIU-39 OE VT RIGID RESTRAINT (IA) 96 -VT; ACTION REPORT 96-0434 GENERATED DUE TO 0 DEG. STRUT AT 19 DEG. OK AS IS DRAWING TO BE REVISED. NOT SERVICE INDUCED - CONSTRUCTION.

NO RECORDABLE INDICATIONS ACCEPTABLE.

161531 C-C C3.20 SZU-39 (IA) PT INTEGRAL ATTACHMENT 96 - PT: NO RECORDABLE INDICATIONS ACCEPTABLE.

B23. H. P. SAFETY INJECTION LINE 2T-SZ-2501 DRAWZNGS: B-39 Summary Exam Item Number Categ Number Component Component Type 161760 C-F-1 C5.30 6 ASME PT PIPE-TO-TEE 96 -PT; NO RECORDABLE INDICATIONS - ACCEPTABLE.

B24. H.P. SAFETY INJECTZON LINE 2U-SZ-2501 DRAWINGS: B-39 Summary Z tern NDE Number Categ Number Component Component Type Exam 162180 F1.20A SZU-30 OE VT ANCHOR ( IA) 96 -VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

30

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT Z CLASS 2 COMPONENTS (CONT.):

B24. H.P. SAFETY INJECTION, LINE 2U-SZ-2501 (CONT.) DRAWZNGS: B-39 Summary Exam Item Number Categ Number Component Component Type Exam 162181 C-C C3.20 SIU-30 (IA) ASME PT INTEGRAL ATTACHMENT 96 -PT; NO RECORDABLE & 1NSIGNIFICANT; SEVERAL ROUNDED INDICATIONS THAT WERE 3/16" OR LESS ACCEPTABLE.

162220 C-F-1 C5. 30 38 ASME PT PIPE-TO-VALVE (878F) 96 -PTr'O RECORDABLE INDICATIONS ACCEPTABLE.

B25. H.P. SAFETY INJECTION LINE 3C-SZ-1501 DRAWINGS: B-41 Summary Exam Item Number Categ Number Component Component Type 163030 C-F-1 C5.21 3 ASME PT ELBOW-TO-PIPE UT 96 -PT & UTr NO RECORDABLE INDICATIONS - ACCEPTABLE.

B26. H. P. SAFETY INJECTION LINE 4E-SI-1501 DRAWINGS: B-42 Summary Exam Item Number Categ Number Component Component Type Exam 163935 F-A F1.20A PEN 101 ANCHOR OE VT ANCHOR ( IA) v 96 -VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

31

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear. Power Plant,1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.Commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.)

B26. H.P. SAFETY ZNJECTZONNLZNE 4E-SZ-1501 (CONT.) DRAWINGS: B-42 Summary Etiam Item Number Categ Number Component Component Type 163936 C-C C3.20 PEN 101 ANCHOR (IA) ASME PT INTEGRAL ATTACHMENT 96 -PT; NO RECORDABLE INDICATIONS ACCEPTABLE.

164000 C-F-1 C5.21 38 ASME PT ELBOW-TO-PIPE UT 96 -PT & UT; NO RECORDABLE INDICATIONS ACCEPTABLE.

164360 C-F-1 C5.21 60 ASME PT TEE-TO-REDUCER UT 96 -PT & UT; NO RECORDABLE INDICATIONS ACCEPTABLE.

B27. SERVICE WATER LINE 6G-SW-125 DRAWZNGS'-50 Summary Etiam 1 tern Number Categ Number Component Component Type 173035 F1.20A PEN 319 ANCHOR OE VT ANCHOR (IA) 96 -VT: NO RECORDABLE INDICATIONS ACCEPTABLE.

173036 C3.20 PEN 319 ANCHOR (IA) OE INTEGRAL ATTACHMENT 96 -MT: NO RECORDABLE INDICATIONS ACCEPTABLE.

32

R. E. GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A B.commercial Service Date ~Jul 1970 6.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT. ):

B28. SERVICE WATER LZNE 8N-SW-125. DRAWINGS: B-50 Summary Exam Item Number Categ Number 'omponent Component Type Exam 173160 C3.20 SWU-81 (IA) OE MT INTEGRAL ATTACHMENT

'6 -MT; NO RECORDABLE INDICATIONS ACCEPTABLE.

173170 ---- F1.20R SWU-81 OE VT GUIDE (IA) 96 -VT; NO RECORDABLE & INSIGNIFICANT; PAINT BU1LD-UP IN GAP ACCEPTABLE.

B29. SERVICE WATER LINE 88-SW-125 DRAWZNGS: B-51 Summary Exam Item Number Categ Number Component Component Type 173860 C3.20 SWU-88 (IA) OE MT INTEGRAL ATTACHMENT 96 -MT; NO RECORDABLE INDICATIONS '- ACCEPTABLE.

173870 F1.20R SWU-88 VT GUIDE (IA) 96 -VTJ'O RECORDABLE INDICATZONS - ACCEPTABLE.

B30. SERVICE WATER LZNE 8F-SW-125 DRAWINGS: B-52 Summary Item Number Categ Number COmponent Component Type 174460 C3. 20 SWU-89 (ZA) OE INTEGRAL ATTACHMENT 96 -MT; NO RECORDABLE INDICATIONS ACCEPTABLE.

33

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 1nterval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.Commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 2 COMPONENTS (CONT.):

B30. SERVICE WATER LZNE 8F-SW-125 (CONT.) DRAWINGS: B-52 Summary Item NDE Number Categ Number Component Component Type Exam 174470 F1.20R SWU-89 OE VT RIGID RESTRAINT (IA) 96 -VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

B31. SERVICE WATER LINE 8B-SW-125 DRAWINGS: B-53 Summary Item Number Categ Number Component Component Type 175460 C3. 20 SWU-42 (IA) OE MT INTEGRAL ATTACHMENT 96 -MTS NO RECORDABLE 1NDICATZONS ACCEPTABLE.

175470 -;-- F1. 20R SWU-42 VT RIGID RESTRAINT (ZA) 96 -VT; NO RECORDABLE INDICATIONS - ACCEPTABLE.

C. CLASS 3 COMPONENTS:

Cl. DIESEL GENERATOR B Z. W. COOLING RETURN DRAWINGS: C-36 Summary Exam Item Number Categ Number Component Component Type 500140 D-B D2. 20 DG-1B (IA) VT INTEGRAL ATTACHMENT 96 -VT; REJECTS'RIGINAL CONSTRUCTION UNDERCUT WITHIN INTEGRAL ATTACHMENT.

OK PER MECH. ENG. MEMO. NOT SERVICE INDUCED. NO RECORDABLE &

INSIGNIFICANT; GAP IN PLATE - ACCEPTABLE.

34

R. E. GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor ., 89 East Ave. Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.Commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I CLASS 3 COMPONENTS (CONT.)

Cl. DIESEL GENERATOR B tT.W. COOLING RETURN (CONT.) DRAWINGS: C-36 Summary Item Number Categ Number Component Component Type Exam 500145 F1.30R DG-1B OE VT RIGID SUPPORT (ZA) 96 -REJECT; ORIGINAL CONSTRUCTION UNDERCUT WITHIN INTEGRAL ATTACHMENT.

OK PER MECH. ENG. MEMO. NOT SERVICE INDUCED. NO RECORDABLE &

INSIGNIFICANT; GAP IN PLATE ACCEPTABLE.

500150 D-B D2.20 DG-2B (IA) ASME VT INTEGRAL ATTACHMENT 96 -VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

500155 F-A F1.30R DG-2B OE VT RIGID SUPPORT (IA) 96 -VT; NO RECORDABLE'INDICATIONS ACCEPTABLE.

a C2. AUX. FW PUMPS DZSCH - ZNTERMED. BLDG. DRAWINGS C-1C Summary Exam Item 'DE Number Categ Number Component Component Type BBQLSC'RRD BB CS RC ZRZZZRS R BBR 505260 F1.30S AFU-103 OE VT MECHANICAL SNUBBER 96 -VT; NO RECORDABLE INDICATIONS ACCEPTABLE. SETTINGS: EAST 3" S/N 18184, WEST 3 1/2" S/N 18185.

505320 F-A F1.30S AFU-34 OE VT

~ MECHANICAL SNUBBER 96 -VTS'O RECORDABLE INDICATIONS - ACCEPTABLE. SETTING = 2 3/4".

35

p ~ t R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.commercial Service Date ~Jul 1970 6.National Board Number for Unit N/A ATTACHMENT I CLASS 3 COMPONENTS (CONT.)

C2. AUX. FW PUMPS DZSCH -. ~ ZNTERMED. BLDG. (CONT. ) DRAWINGS: C-1C Summary Item Number Categ Number Component Component Type NB Qc R Rc 505500 F-A F1.30S AFU-52 OE VT MECHANICAL SNUBBER 96 -VTr NO RECORDABLE 1NDICATIONS ACCEPTABLE. SETTZNG = 1 3/4" 505750 F-A F1.30S AFU-75 OE VT MECHANICAL SNUBBER 96 -VT'O RECORDABLE ZNDICATIONS ACCEPTABLE. SETTING = 2 1/8".

C3. COMPONENT COOLING HEAT EXCHANGER B DRAWINGS C-41 Summary Item NDE Number Categ Number Component Component Type Exam 555200 D-B D2.20 CCW1B-W (IA) ASME VT INTEGRAL ATTACHMENT 96 -VT; NO RECORDABLE & INSIGNIFICANT; LIGHT RUST ACCEPTABLE.

555250 F-A F1.40 . CCW1B-W VT SUPPORT WEST (IA) 96 -VTr NO RECORDABLE INDICATIONS - ACCEPTABLE.

555300 D-B D2.20 CCWlB-E (IA) ASME VT INTEGRAL ATTACHMENT 96 -VT; NO RECORDABLE INDICATIONS - ACCEPTABLE.

9 555350 F-A F1.40 CCW1B-E VT SUPPORT EAST (IA) 96 -VT; NO RECORDABLE INDZCATIONS ACCEPTABLE.

36

I, R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I D. HIGH ENERGY COMPONENTS:

D1. MAIN STEAM TURBINE BUILDING DRAWINGS: HE-7A Summary Item Number Categ Number Component Component Type 200265 HE-CB B AUG UT PIPE-TO-ELBOW MT VT 96 -MT & VT; REJECT ARC STRIKES, GOUGES & LUG STUBS. NOT SERVICE INDUCED CONSTRUCTION. INDICATIONS REMOVED BY GRINDING. MT & VT RE-EXAM AFTER REPAIRS-ACCEPT. UT THICKNESS READINGS-ACCEPT. UT; NO RECORDABLE INDICATIONS ACCEPTABLE.

D2. FEEDWATER LOOP A OUTSIDE CV DRAWINGS: HE-5 Summary Exam Item Number Categ Number Component Component Type 201700 HE-CS *F1.20S FWU-26 OE VT MECHANICAL SNUBBER (IA) 96 -VT; NO RECORDABLE INDZCATIONS ACCEPTABLE.

201701 HE-IA *C3. 20 FWU-26 (IA) AUG MT INTEGRAL ATTACHMENT 96 -MTr NO RECORDABLE INDICATIONS ACCEPTABLE.

201720 HE-CS *F1. 20R FWU-27 OE VT RIGID SUPPORT (IA) 96 -VT: NO RECORDABLE & INSIGNIFICANT; 2 ADDITIONAL STANCHION LUGS HAVE BEEN ADDED, DRAWING TO BE REVISED ACCEPTABLE.

201721 HE-IA *C3. 20 FWU-27 (IA) AUG MT INTEGRAL ATTACHMENT 96 -MT; NO RECORDABLE INDICATIONS - ACCEPTABLE.

37

e R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

l. Owner Rochester Gas & Electric Cor ., 89 East Ave., Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.Commeccial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I E. LEAKAGE TESTING:

E1 LEAKAGE EXAMZNATIONS CLASS 1 9 2 9 3 DRAWINGS L-1 Summary Etiam Item Number Categ Number Component Component Type 411000 B-P IWB5221 PT-7 LEAKAGE TEST OF ASME VT REACTOR COOLANT SYSTEM 96 -VT; NO EVIDENCE OF LEAKAGE AT FINAL PLATEAU. LAST PLATEAU WAS HELD FOR 4 HRS AT OPERATING TEMPERATURE & PRESSURE BEFORE WALKDOWN.

ACCEPTABLE.

412100 D-B IWD5221 STANDBY AUXILIARY ASME VT FEEDWATER PUMP "D" 96 -VTr NO EVIDENCE OF LEAKAGE. COMPLETED BOUNDARY THIS OUTAGE - ACCEPTABLE.

414000 D-A IWD5221 SERVICE WATER ASME VT OUTSIDE CONTAINMENT 96 -VT; NO EVIDENCE OF LEAKAGE. COMPLETED BOUNDARY THIS OUTAGE. ACCEPTABLE.

415600 C-H, IWC5221 PRESSURIZER (TRC01) ASME VT CLASS 2 INSTRUMENTATION 96 -VTf - ACCEPTABLE.

415650 C-H IWC5221 RPV (RPC01) ASME VT CLASS 2 INSTRUMENTATION 96 -VT; ACCEPTABLE.

38

0

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Znterval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I F. STEAM GENERATOR EDDY CURRENT EXAMINATIONS:

Fl. STEAM GENERATOR A DRAWINGS: N/A Summary Exam Item NDE Number Categ Number Component Component Type Exam 802500 B-Q B16.20 OPEN GENERATOR TUBES ASME ET BOBBIN COIL 100% ET FULL LENGTH 96 -ET; SEE 1996 S/G EDDY CURRENT FINAL REPORT & BWZ FINAL REPORT FOR DETAILS, ACCEPTABLE.

802600 SG-ET ---- OPEN GENERATOR TUBES OE ET PERIPHERAL TUBES ET 96 -ET'EE 1996 S/G EDDY CURRENT FINAL REPORT & BWI FINAL REPORT FOR DETAILS, - ACCEPTABLE.

F2. STEAM GENERATOR B DRAWINGS: N/A Summary Item NDE Number Categ Number Component Component Type Exam 803500 B-Q B16.20 OPEN GENERATOR TUBES ET BOBBIN COIL 100'8 ET FULL LENGTH 96 -ET SEE 1996 S/G EDDY CURRENT FINAL REPORT & BWI FINAL REPORT FOR DETAZLS, ACCEPTABLE.

803600 SG-ET ---- OPEN GENERATOR TUBES OE ET PERIPHERAL TUBES ET 96 -ET; SEE 1996 S/G EDDY CURRENT FINAL REPORT & BWI FINAL REPORT FOR DETAILS, - ACCEPTABLE.

39

S

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Gi.nna Nuclear Power Plant 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.Commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I G. SNUBBER PROGRAM COMPONENTS:

Gl. STEAM GENERATOR A DRAWINGS: A-7F Summary Item Number Categ Number Component Component Type Exam 600080 SN-VT SGA-7 AUG VT HYDRAULIC SNUBBER 96 VTS SETTING 38 1/8 f S/N 7728073 A NO RECORDABLE 1NDICATIONS ACCEPTABLE.

600090 SN-VT ---- SGA-8 AUG VT HYDRAULIC SNUBBER 96 VTS SETTING 38 1/4 9 S/N 7728073 A NO RECORDABLE INDICATIONS ACCE PTABLE .

a 600091 SN-FT ---- SGA-8 a

AUG FT HYDRAULIC SNUBBER 96 -FT; FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM. TESTED OPERABLE.

G2. STEAM GENERATOR B DRAWINGS: A-7F Summary Exam Item NDE Number Categ Number Component Component Type Exam 600120., SN-VT SGB-3 AUG VT HYDRAULIC SNUBBER 96 VT SETTING 38 1/2 f S/N 7728073 A NO RECORDABLE INDICATIONS ACCEPTABLE.

600130 SN-VT ---- SGB-4 AUG VT HYDRAULIC SNUBBER 96 -VT; SETTING 38 3/8", S/N = 7728073-A. NO RECORDABLE INDICATIONS ACCEPTABLE.

a 40

J

R. E. GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.Commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)

G3. TURBINE DRIVEN AUX. FW PUMP SUCTION DRAWINGS: C-16 Summary Exam Item Number Categ Number Component Component Type Exam 600200 SN-VT AFU-3 AUG VT MECHANICAL SNUBBER 96 VT r SETTING 2 9 S/ N 2 0 925 9 NO RECORDABLE INDICATIONS ACCEPTABLE G4. AUX. FW PUMPS DZSCH ZNTERMED ~ BLDG. DRAWINGS: C-1E Summary Exam Item NDE Number Categ Number Component Component Type Exam 600220 SN-VT AFU-31 AUG VT MECHANICAL SNUBBER 96 VTS'ETTING 2 3/4 9 S/N 244529 NO RECORDABLE INDICATIONS ACCEPTABLE ~

600240 SN-VT ---- AFU-34 AUG VT MECHANZCAL SNUBBER 96 VT SETTING 2 3/4 9

'/N 144489 NO RECORDABLE INDICATIONS ACCEPTABLE ~

600260 SN-VT ---- AFU-52 AUG VT MECHANICAL SNUBBER 96 VTS SETTING 1 3/4 9 S/N 244539 NO RECORDABLE INDICATIONS ACCEPTABLE ~

600280 SN-VT ---- AFU-75 AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 2 1/8", S/N = 20924, NO RECORDABLE INDICATIONS ACCEPTABLE.

r

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.;Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.):

G4. AUX. FW PUMPS DZSCH - ZNTERMED. BLDG. (CONT.) DRAWINGS: C-1E Summary Etiam Item Number Categ Number Component Component Type 600300 SN-VT ---- AFU-98 AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 1 9/16", S/N = 24454, NO RECORDABLE INDICATIONS ACCEPTABLE'00320 SN-VT AFU-101 AUG VT MECHANICAL SNUBBER 96 VTS SETTING 3 3/ 8 f S/N 1 575 1 9 NO RECORDABLE INDICATIONS ACCEPTABLE ~

600339 SN-VT ---- AFU-103 (EAST) AUG VT MECHANICAL SNUBBER 96 VT SETTING 3 f S/N 1 8 1 84 f NO RECORDABLE INDZCATIONS ACCEPTABLE ~

600340 SN-VT ---- AFU-103 (WEST) AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 3 1/2", S/N = 18185, NO RECORDABLE INDICATIONS ACCEPTABLE.

600360 SN-VT ---- AFU-109 AUG VT HYDRAULIC SNUBBER 96 VTJ SETTING 2 1/4 f S/N 30986 NO RECORDABLE INDICATIONS ACCEPTABLE ~

600380 SN-VT ---- AFU-111 AUG VT MECHANICAL SNUBBER 96 VT SETTING 2 1/16 f S/N 1 6377 f NO RECORDABLE INDICATIONS ACCEPTABLE 600400 SN-VT ---- AFU-123 AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 1 5/8", S/N = 22485, NO RECORDABLE INDICATIONS ACCEPTABLE.

42

0

- R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~cul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)

G4. AUX. FW PUMPS DISCH - 1NTERMED. BLDG. (CONT. ) DRAWZNGS: C-1E Summary Exam Item Number Categ Number Component Component Type 600420 SN-VT AFU-124 AUG VT MECHANICAL SNUBBER 96 VTa SETTING 2 f S/N 24451 f NO RECORDABLE INDICATIONS ACCEPTABLE G5. STEAM GENERATOR B BLOWDOWN LINE DRAWINGS: B-31 Summary Exam Item Number Categ Number Component Component Type CSS ZXNCS CBSNS 600460 SN-VT BDU-16 AUG VT MECHANICAL SNUBBER VTa RE J LOOSE NUTS f MZSALIGNMENT ACTION REPORTS 96 02469 0345 9 0426

& 0 5 3 5 GENERATED I DI S POS T ION OF ACTION REPORTS & MECH ENGS MEMO ACCEPT. SETTING=2 3/4" HOT, 1 1/2" COLD. S/N =10182. VT-ACCEPT. SERVICE INDUCED-SNUBBER PROGRAM REQUIREMENTS.

G6. AUX.COOL LINE 4S-AC6-152 DRAWINGS: B-29 Summary Exam Item NDE Number Categ Number Component Component Type Exam RRRRR SS R  %%%ASS MSS 600530 SN-VT CCU-43 AUG VT MECHANICAL SNUBBER 96 -VT'ETTING 1 5/8", S/N = 11462, NO RECORDABLE INDICATIONS - ACCEPTABLE.

G7. AUX.COOL SYS.FRM.PUMP COOL OUT.TO PEN126 DRAWINGS'-34 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600610 SN-VT ---- CCU-57 AUG VT MECHANICAL SNUBBER 96 VT a'ETTING 2 1/2 9 S/N 1 8 1 94 9 NO RECORDABLE INDICATIONS ACCEPTABLE .

43

0 R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT Z SNUBBER PROGRAM COMPONENTS (CONT.)

G8 . AUX. COOL L1NE 4T-AC6-152 DRAWINGS: B-30 Summary Exam Item Number Categ Number Component Component Type 600710 SN-VT CCU-71 AUG VT MECHANICAL SNUBBER 96 VTr SETTING 2 1/2 f S/N 181939 NO RECORDABLE INDICATIONS ACCEPTABLE G9. 2" LETDOWN TO REGEN HTX DRAWINGS: A-23 Summary Exam Item Number Categ Number Component Component Type 600880 SN-VT CVU-26 AUG VT MECHANICAL SNUBBER 96 VT SETTING 2 9 S/N 208 80 f NO RECORDABLE INDICATIONS ACCEPTABLE G10 ~ 2" CHARGING TO REGEN HTX DRAWINGS: A-30 Summary Exam Item NDE Number Categ Number Component Component Type Exam 600900 SN-VT CVU-46 AUG. VT MECHANICAL SNUBBER 96 VT r SETT ZNG 2 9 S/N 3 8 555 9 NO RECORDABLE INDICATIONS ACCEPTABLE G11. 2" ALTERNATE CHARGING TO LOOP B HOT LEG DRAWINGS'-27 Summary Exam Item Number Categ Number Component Component Type 600920 SN-VT ---- CVU-49 AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 1 1/2", S/N = 9483, NO RECORDABLE INDICATIONS ACCEPTABLE.

i 4

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~oui 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)

G12. 2" CVCS RELZEF LINE TO PRT DRAWINGS: B-32 Summary Item Number Categ Number Component Component Type 600940 SN-VT CVU-80 AUG VT MECHANICAL SNUBBER 96 VTr SETTING 1 1/2 9 S/N 2 35 1 8 9 NO RECORDABLE INDICATIONS ACCEPTABLE G13. SEAL WATER TO RCP-B DRAWINGS'-32 Summary Exam Item Number Categ Number Component Component Type 600960 SN-VT CVU-103 AUG VT MECHANICAL SNUBBER 96 VTe SETTING 2 1/8 9 S/N 244509 NO RECORDABLE & INSIGNIFICANT ACCE PTABLE .

600980 SN-VT ---- CVU-104 AUG VT MECHANICAL SNUBBER 96 VTa SETTING 2 9 S/N 24499 NO RECORDABLE INDICATIONS ACCEPTABLE ~

G14. SEAL WATER RETURN FROM RCP-A DRAWINGS: B-34 Summary Exam Item NDE Number Categ Number Component Component Type Exam 9 OC SBB RRBBBBBSBSBB K% R BB 9 K D K R mt BBBBK 9

601000 SN-VT CVU-186 AUG VT MECHANICAL SNUBBER 96 VTe SETTING 1 4 9 S/N' 654 1 9 NO RECORDABLE INDICATZONS ACCEPTABLE ~

45

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.Commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.):

G15. 2" LETDOWN LINE TO NON-REGEN HTX DRAWINGS: B-35 Summary Item Number Categ Number Component Component Type 601040 SN-VT CVU-345 AUG VT MECHANICAL SNUBBER 96 VT SETTING 1 1 4 / 9 S/N 94919 NO RECORDABLE INDICATIONS ACCEPTABLE 601060 SN-VT ---- CVU-351 AUG VT MECHANICAL SNUBBER 96 VT SETTING 3/4 9 S/N 9472 9 NO RECORDABLE INDICATIONS ACCEPTABLE G16. CVCS LETDOWN LINE TO MZX BED DEMZN DRAWZNGS: B-36 Summary Exam Item Number Categ Number Component Component Type Exam SN 601080 SN-VT CVU-372 AUG VT MECHANZCAL SNUBBER 96 VTr'ETTING 3/4 9 S/N 94789 NO RECORDABLE INDICATIONS ACCEPTABLE ~

G17. FEEDWATER LOOP A INSIDE CV DRAWZNGS: B-12 Summary Exam Z tern Number Categ Number Component Component Type 601100 SN-VT FWU-3 AUG VT HYDRAULIC SNUBBER 96 -VT; SETTING 4 1/8", S/N 438629 REJECTr'EAVY OIL RESIDUES ACTION REPORT 96-0466 GENERA/ED. RE-EXAM - NO RECORDABLE INDICATIONS ACCEPTABLE.

SNUBBER WAS REPLACED. SNUBBER PROGRAM REQUIREMENTS APPLY.

46

I l

lt

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas 6 Electric Cor ., 89 East Ave., Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~cul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT. ):

G17. FEEDWATER LOOP A INSIDE CV (CONT.) DRAWZNGS: B-12 Summary Exam Z tern

'umber Categ Number Component Component Type 601110 SN-VT FWU-5 AUG VT HYDRAULIC SNUBBER 96 -VT; REJECT; IMPROPER SETTING. ACTION REPORT 96-0590 GENERATED. SETTING ACCEPTED BY MECH'NG MEMOS SETTING 3 7/8 9 S/N 2500 10 1529 NO RECORDABLE INDICATIONS -,ACCEPTABLE. SNUBBER PROGRAM REQUIREMENTS APPLY.

G18. FEEDWATER LOOP B INSIDE CV DRAWINGS: B-13 Summary Exam Item Number Categ Number Component Component Type 601120 SN-VT FWU-8 AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 2 1/4", S/N = 8033, NO RECORDABLE INDICATZONS - ACCEPTABLE.

601130 SN-VT ---- FWU-12 AUG VT MECHANICAL SNUBBER 96 VTr SETTING 3 1/4 9 S/N 80349 NO RECORDABLE INDICATIONS ACCEPTABLE.

G19. FEEDWATER LOOP A OUTSIDE CV DRAWINGS: B-11 Summary Exam Item Number Categ Number Component Component Type 601140 SN-VT FWU-15 AUG VT

~ MECHANICAL SNUBBER 96 VTa SETTING 2 5/8 9 S/N 9358 9 NO RECORDABLE INDICATIONS ACCEPTABLE ~

li R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649 2 ~ Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (Zf Req.) N/A B.Commercial Service Date ~Jul 1970 6.National Board Number for Unit N/R ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT. )

G19 ~ FEEDWATER LOOP A OUTSIDE CV (CONT )

~ DRAWINGS B-11 Summary Exam Item Number Categ Number Component Component Type Exam 601150 SN-VT FWU-17 AUG VT MECHANICAL SNUBBER 96 VTr'ETTING 4 3/4 9 S/N 93929 NO RECORDABLE & INSZGNZFICANTf CORROSION STAINS ON PAINTED SURFACE - ACCEPTABLE.

601160 SN-VT ---- FWU-18 AUG VT MECHANICAL SNUBBER 96 VTr'ETTING 3 1/2 9 S/N 70679 NO RECORDABLE INDICATIONS ACCEPTABLE'01161 SN-FT ---- FWU-18 AUG FT MECHANICAL SNUBBER 96 -FT; FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM. TESTED OPERABLE'01170 SN-VT ---- FWU-20 AUG VT MECHANICAL SNUBBER 96 VTr SETTING 1 3/4 r S/N 70499 NO RECORDABLE ZNDICATZONS ACCEPTABLE 601180 SN-VT ---- FWU-21 AUG VT HYDRAULIC SNUBBER 96 -VTr SETTING 3 13/16", S/N = 2500-20-38, NO RECORDABLE & INSIGNIFICANT; FLUID LEVEL DOES NOT CORRESPOND WITH SNUBBER PISTON BY 1" ACCEPTABLE.

601190 SN-VT FWU-23 AUG VT MECHANICAL SNUBBER 96 VTr SETTING 4 f S/N 86309 NO RECORDABLE INDICATIONS ACCEPTABLE.

R. E. GZNNA NUCLEAR POWER PLANT Inservice Znspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas 6 Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.Commercial Service Date ~oui 1970 S.National Board Number for Unit N/R ATTACHMENT SNUBBER PROGRAM COMPONENTS (CONT.)

G19. FEEDWATER LOOP A OUTSIDE CV (CONT.) DRAWINGS: B-11 Summary Exam Item Number Categ Number Component Component Type Exam 601191 SN- FT FWU-23 AUG FT MECHANICAL SNUBBER 96 -FT'UNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM. TESTED OPERABLE.

601200 SN-VT ---- FWU-24 AUG VT MECHANICAL SNUBBER 96 -VT: SETTING 3 1/32", S/N = 10061, NO RECORDABLE INDICATIONS ACCEPTABLE.

601209 SN-VT ---- FWU-26 (EAST) AUG VT MECHANICAL'NUBBER 96 VT a SETTING 3 f S /N 1 8 1 7 9 f NO RECORDABLE ZNDZCATZONS ACCEPTABLE 601210 SN-VT ---- FWU-26 (WEST) AUG VT MECHANICAL SNUBBER 96 VTa SETTING 3 f S/N 1 8 1 80f NO RECORDABLE INDICATIONS ACCEPTABLE G20. FEEDWATER LOOP B OUTSIDE CV DRAWINGS: HE-5 Summary Exam Z tern Number Categ Number 'omponent Component Type 601220 SN-VT FWU-32 AUG VT MECHANICAL SNUBBER 96 VTr SETTING 3 1/4 f S/N = 7053 f NO RECORDABLE & ZNS IGNI FZCANTa ZD TAG BROKEN - ACCEPTABLE.

49

i tV

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor ., 89 East Ave., Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.):

G20. FEEDWATER LOOP B OUTSIDE CV (CONT. ) DRAWINGS: HE-5 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601230 SN-VT ---- FWU-38 AUG VT MECHANICAL SNUBBER 96 VT/ SETTING 3 9/16 / S/N 9395/ NO RECORDABLE INDICATIONS ACCEPTABLE 601240 SN-VT ---- FWU-39 AUG VT MECHANICAL SNUBBER 96 VT! SETTING 4 / S/N 9854 5 1 642 9 NO RECORDABLE INDICATZONS ACCEPTABLE 601250 SN-VT ---- FWU-40 AUG VT MECHANICAL SNUBBER 96 VT /'ETTING 3 1 /2 / S/N 7 0 66 9 NO RECORDABLE & INS ZGNZ FZ CANT f BROKEN ID TAG - ACCEPTABLE.

601260 SN-VT ---- FWU-42 AUG VT MECHANICAL SNUBBER 96 VT/ SETTING 4 1 /4 9 S /N 61599 NO RECORDABLE INDICAT IONS ACCEPTABLE 601261 SN-FT ---- FWU-42 AUG FT MECHANICAL SNUBBER 96 -FT; FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM. TESTED OPERABLE.

601270 SN-VT ---- FWU-44 AUG VT HYDRAULIC SNUBBER 96 -VT; SETTING 3 )/8"f S/N = G43864-02-20, NO RECORDABLE INDICATIONS ACCEPTABLE.

50

R. E. GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990"1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.Commercial Service Date ~Jul 1970 6.National Board Number for Unit N/A ATTACHMENT Z SNUBBER PROGRAM COMPONENTS (CONT.):

G20. FEEDWATER LOOP B OUTSIDE CV (CONT.) DRAWINGS: HE-5 Summary Item NDE Number Categ Number Component Component Type Exam 601280 = SN-VT FWU-47 AUG VT MECHANICAL SNUBBER a

96 VT SETTING 4 5/8 6 S/N 7474 INSIGNIFICANT ACTION REPORT 96 05 13 GENERATED FOR RIPPED BOOT - 9 ACCEPTABLE.

601290 SN-VT ---- FWU-48 AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 4 1/2", S/N 47856 REJECTa ACTION REPORT 96 0513 GENERATED

. TO ADDRESS RADIAL MOVEMENT OF SNUBBER. RE-EXAM AFTER CORRECTIONS ACCEPTABLE. NOT SERVICE INDUCED. SNUBBER PROGRAM REQUIREMENTS APPLY.

601300 SN-VT ---- FWU-51 AUG VT MECHANICAL SNUBBER 96 -VTv SETTING 4 1/2", S/N = 7483, NO RECORDABLE & INSIGNZFZCANTf'IGEON FECES ACCEPTABLE.

601310 SN-VT ---- FWU-52 AUG VT MECHANICAL SNUBBER 96 VTa SETTING 3 1/8 6 S/N 66079 NO RECORDABLE & INSIGNIFICANT! PIGEON FECES - ACCEPTABLE.

601320 SN-VT -"-- FWU-54 AUG VT MECHANICAL SNUBBER 96 VTa SETTING 4 6 S/N 7482 6 NO RECORDABLE & INS IGNI FICANT! PIGEON FECES ACCEPTABLE .

51

i R. E. GINNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.Commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.):

G20. FEEDWATER LOOP B OUTS1'DE CV (CONT.) DRAWINGS: HE-5 Summary Exam 1 tern Number Categ Number Component Component Type 601330 SN-VT FWU-57 AUG VT MECHANICAL SNUBBER 96 VTr SETTING 3 S/N 10064/ NO RECORDABLE & ZNSIGNIFICANT/ PIGEON FECES ACCEPTABLE.

G21. MAIN STEAM LOOP A INSIDE CV DRAWINGS: B-8 Summary Exam Item Number Categ Number Component Component Type 601350 SN-VT ---- MSU-2 AUG VT MECHANICAL SNUBBER 96 VT r SETTING 3 3/4 / S/N 7 0 87 9 NO RECORDABLE INDICATIONS ACCEPTABLE 601360 SN-VT ---- MSU-3 AUG VT MECHANICAL SNUBBER 96 VT/'ETTING 3 9 S/N 7060/ NO RECORDABLE INDICATIONS ACCEPTABLE.

G22. MAIN STEAM LOOP B INSIDE CV DRAWINGS: B-8 Summary Exam Item Number Categ Number Component Component Type SB 601369 SN-VT MSU-7 (TOP/WEST) AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 2 8/4", S/N = 7051, NO RECORDABLE ZNDICATIONS ACCEPTABLE.

52

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A B.commercial Bervice Date ~cul 1970 6.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)

G22. MAIN STEAM LOOP B INSIDE CV (CONT.) DRAWINGS: B-8 Summary Exam Item Number Categ Number Component Component Type 601370 SN-VT MSU-7 (BOTTOM/EAST) AUG VT MECHANICAL SNUBBER 96 VT! SETTING 3 r S/N 7 047 / NO RECORDABLE INDICATIONS ACCEPTABLE ~

601380 SN-VT ---- MSU-8 AUG VT HYDRAULIC SNUBBER 96 -VT'EJECT; ACTION REPORT 96-0465 GENERATED FOR INCORRECT SETTING & LACK OF 2 THREADS FOR FULL ENGAGEMENT. RE-EXAM AFTER CORRECTIONS. NO RECORDABLE INDICATIONS ACCEPTABLE. SETTING 3", S/N = G20968130. NOT SERVICE INDUCED. SNUBBER PROGRAM REQUIREMENTS APPLY.

G23. MAIN STEAM LOOP B OUTSIDE CV DRAWINGS: B-10A Summary Exam Item Number Categ Number Component Component Type 601390 SN-VT ---- MSU-12 VT MECHANICAL SNUBBER 96 VT/ SETTING 3 5/8 f S/N 9400/ NO RECORDABLE & INSIGNIFICANT/ PIGEON FECES - ACCEPTABLE.

601399 SN-VT ---- MSU-13 (EAST) AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 3 1/8", S/N = 1467, NO RECORDABLE & INSIGNIFICANT, PIGEON FECES ACCEPTABLE.

601400 SN-VT ---- MSU-13,(WEST) AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 3 3/8", S/N = 1464, NO RECORDABLE & INSIGNIFICANT, PIGEON FECES ACCEPTABLE.

53

i R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (Zf Req.) N/A S.commercial Service Date ~cul 1970 S.National Board Number foe Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.):

G23. MAIN STEAM LOOP B OUTSIDE CV (CONT.) DRAWZNGS: B-10A Summary Exam Item Number Categ Number Component Component Type 601409 SN-VT MSU-15 (NORTH) AUG VT MECHANICAL SNUBBER 96 VT SETTING 3 3/ 8 I S/N 7 47 6 I NO RECORDABLE & INS I GNI FZ CANT I PIGEON FECES - ACCEPTABLE.

601410 SN-VT ---- MSU-15 (SOUTH) AUG VT MECHANICAL SNUBBER 96 VTS SETTING 3 7/8 6 S/N 7477 9 NO RECORDABLE & INSIGNIFICANTs PIGEON FECES ACCEPTABLE.

601419 SN-VT ---- MSU-16 (NORTH) AUG VT MECHANICAL SNUBBER 96 -VT; REJECT; ACTION REPORT 96-0534 GENERATED FOR INCORRECT SETTING.

SETTINGS ACCEPTABLE PER ACTION REPORT & MECH ENG MEMO. SETTINGS HOT = 3 5/8", COLD = 3 1/8"; S/N = 7481. NO RECORDABLE & INSIGNZFZCANT-PIGEON FECES -ACCEPTABLE. SNUBBER PROGRAM REQUIREMENTS APPLY.

601420 SN-VT ---- MSU-16 (SOUTH) AUG VT MECHANICAL SNUBBER 96 -VTS REJECT: ACTION REPORT 96-0534 GENERATED TO ADDRESS SETTING. SETTINGS ACCEPTABLE PER ACTION REPORT & MECH ENG MEMO. SETTZNGSS'OT = 4

= 3 3/4". S/N = 7480. NO RECORDABLE & INSIGNIFICANT-PIGEON 3/16'OLD FECES-ACCEPT. SNUBBER PROGRAM REQUIREMENTS APPLY.

601429 SN-VT ---- MSU-18 (NORTH) VT MECHANICAL SNUBBER 96 VTS SETTING 2 1/4 6 S/N 7478 I NO RECORDABLE & INSZGNI FICANTs PIGEON FECES - ACCEPTABLE.

54

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Znterval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.):

G23. MAIN STEAM LOOP B OUTSIDE CV (CONT. ) DRAWINGS: B-10A Summary Item NDE Number Categ Number Component Component Type Exam 601430 SN-VT MSU-18 (SOUTH) AUG VT MECHANICAL SNUBBER 96 VT r SETTING 2 1/2 9 S/N 7 1 97 6 NO RECORDABLE & INSIGNIFICANT S PIGEON FECES ACCEPTABLE.

601432 SN-FT ---- , MSU-18 (SOUTH) AUG FT MECHANICAL SNUBBER 96 -FTr TEST REQUIRED DUE TO FUNCTIONAL TEST FAILURE IN 1996. SNUBBER TESTED OPERABLE.

601439 SN-VT ---- MSU-19 (NORTH) AUG VT MECHANICAL SNUBBER 96 VTr SETTING 3 6 S/N 9369f NO RECORDABLE & INSIGNIFICANTS PIGEON FECES ACCEPTABLE.

601440 SN-VT ---- MSU-19 (SOUTH) AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 2 7/8", S/N = 9372, NO RECORDABLE & INSIGNIFICANT PIGEON FECES ACCEPTABLE.

601441 SN-FT ---- MSU-19 (NORTH) AUG FT MECHANICAL SNUBBER 96 -FTr'UNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM. TESTED OPERABLE.

601442 SN-FT ---- MSU-19 (SOUTH) AUG FT MECHANICAL SNUBBER 96 -FT; FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM. TESTED OPERABLE.

55

R. E ~ GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990"1999 Znterval, Second Period, Fourth Outage (1996)

l. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road, Ontario NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (Zf Req. ) N/A 5.Commercial Service Date ~cul 1970 6.National Board Number for Unit N/A ATTACHMENT Z SNUBBER PROGRAM COMPONENTS (CONT.)

G23. MAZN STEAM LOOP B OUTSZDE CV (CONT.) DRAWINGS: B-10A Summary Item NDE Number Categ Number Component Component Type Exam 601450 SN-VT MSU-22 AUG VT MECHANICAL SNUBBER 96 VTa SETTING 2 1/8 f S/N 9357 9 NO RECORDABLE & INSZGNI FZCANTf PIGEON FECES ACCEPTABLE.

601451 SN-FT ---- MSU-22 AUG MECHANICAL SNUBBER 96 -FTr FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM. TESTED OPERABLE.

601460 SN-VT ---- MSU-25 VT MECHANICAL SNUBBER 96 -VT; SETTING 1 3/4", S/N = 1465, NO RECORDABLE & INSIGNIFICANT, PIGEON FECES ACCEPTABLE.

601469 SN-VT ---- MSU-26 (TOP) AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 5", S/N = 9355, NO RECORDABLE & INSIGNIFICANT, PIGEON FECES ACCEPTABLE..

601470 SN-VT ---- MSU-26 (BOTTOM) AUG VT MECHANICAL SNUBBER 96 VT r SETTING 4 3/4 f S/N 468 69 NO RECORDABLE & INS IGNI FZ CANT 9 PIGEON FECES ACCEPTABLE.

601480 SN-VT ---- MSU-27 AUG VT

~ MECHANICAL SNUBBER 96 -VT; SETTING 1", S/N = 9398, NO RECORDABLE & INSIGNIFICANT, PIGEON FECES ACCEPTABLE.

56

l

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990"1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~cul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)

G23. MAIN STEAM LOOP B OUTSIDE CV (CONT.) DRAWINGS: B-10A Summary Exam Item Number Categ Number Component Component Type 601490 SN-VT ---- MSU-29 AUG VT MECHANZCAL SNUBBER 96 -VT; SETTING 4 1/4", S/N = 1469, NO RECORDABLE INDICATIONS - ACCEPTABLE.

601500 SN"VT ---- MSU-31 AUG VT MECHANICAL SNUBBER 96 VTr'ETTING 2 1/2 9 S/N 93569 NO RECORDABLE INDICATIONS ACCEPTABLE 601510 SN-VT ---- MSU-32 AUG VT MECHANICAL SNUBBER 96 -VTr'ETTING 2 3/8", S/N = 1093, NO RECORDABLE INDICATIONS ACCEPTABLE.

G24. MAIN STEAM LOOP A OUTSIDE CV DRAWINGS: B-9A Summary Exam Ztem NDE Number Categ Number Component Component Type Exam 601520 SN-VT ---- MSU-38 AUG VT MECHANICAL SNUBBER 96 VTr SETTING 1 5/ 8 9 S /N 1 0 90 f NO RECORDABLE INDICAT IONS ACCEPTABLE 601530 SN-VT ---- MSU-39 AUG VT MECHANICAL SNUBBER 96 VT SETTING 4 3/4 9 S/N 10879 NO RECORDABLE INDICATIONS ACCEPTABLE ~

601540 SN-VT ---- MSU-40 AUG VT MECHANICAL SNUBBER 96 -VTa SETTING 4 5/8", S/N = 1080, NO RECORDABLE INDICATIONS ACCEPTABLE.

57

R. E. GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor ., 89 East Ave. Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT. )

G24. MAIN STEAM LOOP A OUTSIDE CV (CONT.) DRAWINGS: B-9A Summary Exam Item Number Categ Number Component Component Type Exam 601550 SN-VT MSU-44 AUG VT MECHANICAL SNUBBER 96 VT SETTING 3 1/8 9 S/N 1 4 68 f NO RECORDABLE & INSIGNIFICANTf SNUBBER SCALE HAS PAINT OVERSPRAY, ACCEPTABLE.

G25. MAIN STEAM LOOP B ATMOSPHERIC VENT DRAWINGS: B-10 Summary Exam Item Number Categ Number Component Component Type 601560 SN-VT MSU-55 AUG VT MECHANICAL SNUBBER 96 -VT; REJECT; ACTION REPORT 96-0518 GENERATED. SNUBBER INSTALLED BACKWARDS.

DCR'S 96-0146/0147 GENERATED, DRAWING TO BE CHANGED TO REFLECT CONFIGURATION. NO RECORDABLE INDICATIONS ACCEPTABLE. SETTING 2 3/4",

S/N = 18195.

601570 SN-VT ---- MSU-57 AUG VT MECHANICAL SNUBBER 96 VTa SETTING 3 1/4 f S/N 271829 NO RECORDABLE ZNDZCATIONS ACCEPTABLE.

601571 SN-FT ---- MSU-57 AUG FT MECHANICAL SNUBBER 96 -FT; FUNCTIONAL TEST REQUIRED DUE TO FAILURE IN 1995. SNUBBER TESTED OPERABLE.

58

I:

li 0

I

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor ., 89 East Ave., Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)

G26. MAIN STEAM LOOP A ATMOSPHERIC VENT DRAWINGS: B-9A Summary Exam Item Number Categ Number Component Component Type mar-ra KKKBBDKK BB BB BBR~Ã KRR R K RK BB 601580 SN-VT ---- MSU-58 AUG VT MECHANICAL SNUBBER 96 VTa SETTING 3 1/8 f S/N 181879 NO RECORDABLE INDICATIONS ACCE PTABLE .

601581 SN-FT ---- MSU-58 AUG FT MECHANICAL SNUBBER 96 -FT FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM. TESTED OPERABLE.

601590 SN-VT ---- MSU-60 AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 2 1/2", S/N = 18197, NO RECORDABLE INDICATIONS - ACCEPTABLE.

G27. MAIN STEAM LOOP B TO AUX FW PUMP TURBZNE DRAWINGS: C-32 Summary Exam Item NDE Number Categ Number Component Component Type Exam BB BBM MBB 601600 SN-VT ---- MSU-72 AUG VT MECHANICAL SNUBBER 96 VTa SETTING 1 5/ 8 f S /N 1 57 67 9 NO RECORDABLE INDICATIONS ACCEPTABLE ~

601601 SN-FT ---- MSU-72 AUG FT MECHANICAL SNUBBER 96 -FT'UNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM. TESTED OPERABLE.

59

j~

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor ., 89 East Ave., Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (Zf Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT Z SNUBBER PROGRAM COMPONENTS (CONT".)

G27. MAIN STEAM LOOP B TO AUX FW PUMP TURBINE (CONT.) DRAWINGS: C-32 Summary Exam Item Number Categ Number Component Component Type 601610 SN-VT MSU-74 AUG VT MECHANICAL SNUBBER 96 VT SETTING 3 1/4 f S/N 100669 NO RECORDABLE INDICATIONS ACCEPTABLE ~

G28. MAIN STEAM LOOP B ATMOSPHERIC VENT DRAWINGS '-10 Summary Item Number Categ Number Component Component Type 601620 SN-VT MSU-75 AUG VT MECHANICAL SNUBBER 96 VT r SETTZNG 2 9 S /N 8 030 9 NO RECORDABLE INDICATZONS ACCEPTABLE a

G29. MAIN STEAM LOOP A TO AUX FW PUMP TURBINE DRAWINGS: C-32 Summary Exam Item Number Categ Number Component Component Type

~BB MBBM 601630 SN-VT MSU-78 AUG VT MECHANICAL SNUBBER 96 VT e SETT ING 3 9 S /N 8 57 9 9 NO RECORDABLE INDICATIONS ACCEPTABLE 601640 SN-VT ---- MSU-80 AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 2 1416", S/N. = 18181, NO RECORDABLE INDICATIONS ACCEPTABLE.

60

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor ., 89 East Ave., Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT Z SNUBBER PROGRAM COMPONENTS (CONT.):

G29. MAIN STEAM LOOP A TO AUX FW PUMP TURBINE (CONT.) DRAW1NGS: C-32 Summary Exam Item NDE Number Categ Number Component Component Type Exam SN a ar a agama=am 601650 SN-VT MSU-82 VT MECHANICAL SNUBBER 96 VTa SETTING 2 7/8 f S/N 157689 NO RECORDABLE INDICATIONS ACCEPTABLE.

601659 SN-VT ---- MSU-84 (EAST) AUG VT MECHANICAL SNUBBER 96 VT SETTING 2 1/2 f S/N 101089 NO RECORDABLE INDICATIONS ACCEPTABLE.

601660 SN-VT ---- MSU-84 (WEST) AUG VT MECHANICAL SNUBBER 96 VTf SETTING 2 1/8 f S/N 101419 NO RECORDABLE INDICATIONS ACCEPTABLE.

601670 SN-VT ---- MSU-85 AUG VT MECHANICAL SNUBBER 96 -VTr'ETTING 3 1/4", S/N = 10074, NO RECORDABLE INDICATIONS ACCEPTABLE.

G30. 6-ZN. RESZD HT REMOVAL TO RPV (LHSZ) DRAWINGS: B-17 Summary Exam Item NDE Number Categ Number Component Component Type Exam

'RKKKKSSSN BBRSBS RBSR MSB 601680 SN-VT RHU-8 AUG VT MECHANICAL SNUBBER 96 -VT: SETTING 2 1/2", S/N = 15755, NO RECORDABLE INDICATIONS - ACCEPTABLE.

61

/

R. E. GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Znterval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519
3. Plant Unit 1 4. O~ner Certificate of Authorization (If Req.) N/A S.Commercial Service Date ~cul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.):

G31. RESIDUAL HEAT REMOVAL FROM LOOP A HOT LEG DRAWINGS: A-15 Summary Exam Item NDE Number Categ Number Component Component Type Exam 601690 SN-VT ---- RHU-30 AUG VT MECHANICAL SNUBBER 96 -VTf SETTING 1 1/16", S/N = 7065, NO RECORDABLE INDICATIONS ACCEPTABLE.

601700 SN-VT ---- RHU-33 AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 3 1/8". S/N = 7064, REJECT: SNUBBER LOCK NUT WRONG WIDTH ACCEPTABLE PER MECH ENG MEMO, NO RECORDABLE INDICATIONS ACCEPTABLE.

SNUBBER PROGRAM REQUIREMENTS APPLY.

G32. RESIDUAL HEAT REMOVAL LZNE 8B-AC-601 DRAWINGS: B-23 Summary Exam Item Number Ca teg Number Component Component Type 601710 SN-VT RHU-36 AUG VT MECHANICAL SNUBBER 96 VTr SETT ING 2 1 /2 9 S/N 1 57569 NO RECORDABLE INDICATIONS ACCEPTABLE ~

G33. RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG DRAWINGS '-25 Summary Exam Item Number Categ Number Component Component Type 601720 SN-VT ---- RHU-51 AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 2 3/8", S/N = 15752, NO RECORDABLE INDICATIONS ACCEPTABLE.

62

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.Commercial Service Date ~Jul 1970 B.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT. ):

G33. RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG (CONT. ) DRAWZNGS: '-25 Summary Exam Item Number Categ Number Component Component Type 601730 SN-VT ---- RHU-53 AUG VT MECHANICAL SNUBBER 96 VTa SETTING 2 5/8 f S/N 15754 f NO RECORDABLE INDICATIONS ACCEPTABLE G34. RESIDUAL HEAT REMOVAL LZNE 6D-AC-601 DRAWINGS: B-26 Summary Ztem NDE Number Categ Number Component Component Type Exam 601740 SN-VT ---- RHU-61 AUG VT MECHANICAL SNUBBER 96 VT SETTING 2 3/ 8 f S/N 1 5733 f NO RECORDABLE INDICATIONS ACCEPTABLE ~

G35. RESIDUAL HEAT REMOVAL LINE 10E-AC-601 DRAWINGS: B-20 Summary Exam Item NDE Number 'Categ Number Component Component Type Exam mt 601749 SN-VT RHU-63 (NORTH) AUG VT MECHANICAL SNUBBER 96 VTa SETTING 2 3/4 f S/N 16380f NO RECORDABLE INDICATIONS ACCEPTABLE 601750 SN-VT ---- RHU-63 (SOUTH) AUG VT MECHANICAL SNUBBER 96 -VT: SETTING 2 15/16", S/N = 16375, NO RECORDABLE INDICATIONS ACCEPTABLE.

63

R. E. GINNA NUCLEAR POWER PLANT Inservice Znspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

l. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.Commercial Service Date ~Jul 1970 6.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.):

G36. RESIDUAL HEAT REMOVAL LINE 10G-AC-601 DRAWINGS: B-20A Summary Exam Item NDE Number Categ Number Component Component Type Exam 601760 SN-VT ---- RHU-69 AUG VT MECHANICAL SNUBBER 96 VT SETTZNG 2 1 /4 / S/N 8 62 9/ NO RECORDABLE INDICATIONS ACCEPTABLE ~

601769 SN-VT ---- RHU<<71 (NORTH) AUG VT MECHANICAL SNUBBER 96 VT/ SETTING 2 7/16 / S/N 1 1466/ NO RECORDABLE INDICATIONS ACCEPTABLE ~

601770 SN-VT ---- RHU-71 (SOUTH) AUG VT MECHANICAL SNUBBER 96 -VT/ SETTING 2 1/2", S/N = 11465, NO RECORDABLE INDICATIONS ACCEPTABLE.

G37. RHR PUMP A SUCTION LINE DRAWINGS: B-20A Summary Exam Item Number Categ Number Component Component Type 601780 SN-VT RHU-72 AUG VT MECHANICAL SNUBBER 96 VTJ SETTING 3 1/8 / S/N 8606/ NO RECORDABLE INDICATIONS ACCEPTABLE 64

R. "E. GINNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor ., 89 East Ave., Rochester NY 14649

.2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario NY 14519

3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.Commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)

G38. RESIDUAL HEAT REMOVAL LINE 10D-AC-601 DRAWZNGS: B-20 Summary Item Number Categ Number Component Component Type Exam 601790 SN-VT RHU-75 AUG VT MECHANICAL SNUBBER 96 VTa SETTING 3 7/ 1 6 9 S/N 8632 9 NO RECORDABLE & INS IGNI FICANTS LIGHT CORROSION, MEDIUM TO HEAVY RUST ON BASE PLATE & FLOOR. T/C GENERATED AFTER CLEAN UP ACCEPTABLE'39.

RESIDUAL HEAT REMOVAL LINE 6K-AC-151 DRAWINGS: B-21 Summary Exam Item Number Categ Number Component Component Type SN 601800 SN-VT RHU-92 AUG VT MECHANICAL SNUBBER 96 VT SETTING 2 1/4 9 S/N 163769 NO RECORDABLE & INSIGNIFICANTS DRY BORIC ACID RESIDUE ON BASE PLATE ~ T/C GENERATED. AFTER CLEAN UP ACCEPTABLE.

G40. H.P. SAFETY INJECTION LINE FROM RWST DRAWINGS '-1 9 Summary Exam Item Number Categ Number Component Component Type 601810 SN-VT ---- RHU-109 AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 2 1/8", S/N = 11463, NO RECORDABLE INDICATIONS ACCEPTABLE'01811 SN-FT RHU-109 AUG FT MECHANiCAL SNUBBER 96 -FT; FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM. TESTED OPERABLE.

65

l R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

l. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A 5.Commercial Service Date ~cul 1970 B.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)

G40. H.P. SAFETY INJECTION LINE FROM RWST (CONT.) DRAWINGS: B-19 Summary Item NDE Number Categ Number Component Component Type Exam 601820 SN-VT RHU-110 AUG VT MECHANZCAL SNUBBER 96 -VTr SETTING 2 3/16", S/N = 16373, NO RECORDABLE INDICATIONS - ACCEPTABLE.

G41. H.P. SAFETY INJECTION PUMP A SUCTION LZNE DRAWZNGS: B-16B Summary Exam, Z tern Number Categ Number Component Component Type 601830 SN-VT  ;-- RHU-119 AUG VT MECHANICAL SNUBBER 96 VTr SETTING 1 3/4 9 S/N 1 57 66 9 NO RECORDABLE ZNDICAT IONS ACCEPTABLE ~

G42. H. P. SAFETY INJECTION LINE 8 J-SZ-151 DRAWINGS B-19 Summary Exam Item Number Categ Number Component Component Type SS SS SS SS SS rS rS SSRRSSSS SS MSSSSSS SS SS 601840 SN-VT RHU-123 AUG VT MECHANICAL SNUBBER 96 -VTr'ETTING 2 1/2", S/N = 15765, NO RECORDABLE INDICATIONS ACCEPTABLE.

'6 601841 SN-FT ---- RHU-123 AUG FT MECHANICAL SNUBBER 96 -FTr FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM. TESTED OPERABLE.

v

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (Zf Req.) N/A S.commercial Service Date ~Cul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.):

G43. H.P. SAFETY INJECTION LZNE TO LOOP A COLD LEG DRAWINGS: A-17 Summary Exam Item Number Categ Number Component Component Type 601850 SN-VT ---- SIU-3 AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 3 3/16", S/N = 8614, NO RECORDABLE & INSIGNIFICANT, NO ID TAG - ACCEPTABLE.

G44. H.P. SAFETY ZNJECTZON LINE TO LOOP B COLD LEG DRAWINGS: A-1 6 Summary Exam Item Number Categ Number Component Component Type 601860 SN-VT SZU-47 AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 3", S/N = 15349, NO RECORDABLE INDZCATIONS ACCEPTABLE.

G45. RESIDUAL HEAT REMOVAL TO LOOP B COLD LEG DRAWINGS: A-14 Summary Item NDE Number Categ Number Component Component Type Exam aa a ann f a 601870 SN-VT ---- SIU-52 AUG VT MECHANICAL SNUBBER 96 VTa SETTING 2 1/2 f S/N 15348f NO RECORDABLE INDICATIONS ACCEPTABLE.

G46. SVC.WTR.-TO A & B DIESEL GEN.WTR.COOLERS DRAWINGS: C-13 Summary Item NDE Number Categ Number Component Component Type Exam 601890 SN-VT ~ SWU-254 AUG VT MECHANICAL SNUBBER 96 VTr SETTING 1 1/8 f S/N 12508 f NO RECORDABLE INDICATIONS ACCEPTABLE ~

67

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A B.commercial Service Date ~Jul 1970 6.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT ~ ):

G47. SERVICE WATER LZNE 8L-SW-125 DRAWZNGS: B-SOA Summary Item Number Categ Number Component Component Type 601900 SN-VT SWU-308 AUG VT MECHANICAL SNUBBER 96 VTr SETTING 2 7/8 9 S/N 803 1 f NO RECORDABLE INDICATIONS ACCEPTABLE 601910 SN-VT ---- SWU-309 AUG VT MECHANICAL SNUBBER 96 VTr SETTING 3 3/8 9 S/N 100739 NO RECORDABLE INDICATIONS ACCEPTABLE G48. SVC.WTR. -INTMD.BLDG.16" HD. TO PEN 312-320 DRAWZNGS: C-16B Summary Item Number Categ Number Component Component Type Exam 601920 SN-VT ---- SWU-370 AUG VT MECHANICAL SNUBBER 96 VTr SETTING 2 1/8 9 S/N 1 14649 NO RECORDABLE INDICATIONS ACCEPTABLE G49. STANDBY AUX FW THRU PEN 123 TO B S/G FWHD ZNCV DRAWZNGS: C-24 Summary Exam 1 tern Number Categ Number Component Component Type aaaBBaBB aaaaaaa aaaaa a aaanmaa anna aaaaaaaaaaa 601930 SN-VT ---- AFU-205 (AFW-10) AUG VT HYDRAULIC SNUBBER 96 VTr SETTING 3 3/ 1 6 9 S/N 154039 NO RECORDABLE & ZNSIGNZ FICANTf FLUID LEVEL APPROX. 70't ACCEPTABLE.

68

R. E. GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

l. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (Zf Req.) N/A 6.Commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)

G49. STANDBY AUX FW THRU PEN 123 TO B S/G FWHD INCV (CONT. ) DRAWINGS: C-24 Summary Exam Item Number Categ Number Component Component Type m

601940 SN-VT AFU-208 (AFW-13) AUG VT HYDRAULIC SNUBBER 96 VTS SETTING 1 25/32 f S/N 12902 9 NO RECORDABLE INDICATIONS ACCEPTABLE.

601941 SN-FT ---- AFU-208 (AFW-13) AUG FT HYDRAULIC SNUBBER 96 -FT; FUNCTIONAL TEST REQUIRED DUE TO FAILURE IN 1995. SNUBBER FAILED FUNCTIONAL TEST. SNUBBER REPLACED. SNUBBER TO BE TESTED IN 1997.

GSO. STANDBY AUX FW THRU PEN 119 TO A S/G FWHD INCV DRAW1NGS: C-20 Summary Exam Item Number Categ Number Component Component Type 601970 SN-VT AFU-224 (AFW-28) AUG VT HYDRAULIC SNUBBER 96 -VT; SETTING 2 1/2", S/N = 12906, NO RECORDABLE & INSIGNIFICANT, FLUID LEVEL 3/4 FULL ACCEPTABLE.

601971 SN-FT ---- AFU-224 (AFW-28) AUG FT HYDRAULIC SNUBBER 96 -FT; FUNCTIONAL TEST REQUIRED DUE TO FAILURE IN 1995. SNUBBER FAILED FUNCTIONAL TEST. SNUBBER WAS RE-BUILT. SNUBBER WILL BE TESTED IN 1997.

601980 SN-VT ---- AFU-226 (AFW-27) AUG VT HYDRAULIC SNUBBER

-VT; REJECT; ACTION f'6 REPORT 96-0443 GENERATED DUE TO SETTINGS. SETTINGS ACCEPTABLE PER ACTION REPORT & MECH ENG MEMO. SETTINGS HOT = 3

= 3 3/4", S/N = 12901, NO RECORDABLE INDICATIONS ACCEPTABLE.

5/16'OLD SNUBBER PROGRAM REQUIREMENTS APPLY.

69

R. E. GZNNA NUCLEAR POWER PLANT Znservice Znspection Report 1990-1999 Znterval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A B.Commercial service Date ~Jul 1970 6.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT. )

G50. STANDBY AUX FW THRU PEN 119 TO A S/G FWHD ZNCV (CONT.) DRAWINGS: C-20 Summary Item NDE Number Categ Number Component Component Type Exam 601981 SN-FT AFU-226 (AFW-27) AUG FT HYDRAULIC SNUBBER 96 -FTa FUNCTIONAL TEST REQUIRED DUE TO SCOPE EXPANSZON FUNCTZONAL TEST FAILURE OF AFU-229. SNUBBER TESTED OPERABLE.

, 601990 SN-VT ---- AFU-225 (AFW-29) AUG VT HYDRAULIC SNUBBER 96 VTt SETT1NG 1 3/4 6 S/N 129069 NO RECORDABLE & INSIGNIFICANTf FLUID LEVEL APPROX. 60% ACCEPTABLE.

602000 SN-VT ---- AFU-227 (AFW-31) AUG VT MECHANICAL SNUBBER 96 VTa SETTING 4 1/8 9 S/N 25594, NO RECORDABLE INDICATIONS - ACCEPTABLE ~

602001 SN-FT ---- AFU-227 (AFW-31) AUG FT MECHANICAL SNUBBER 96 -FTa FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM. TESTED OPERABLE.

G51. PRESS.RELIEF PM PRESS.TO RELIEF MANIFOLD DRAWINGS: S-2 Summary Exam Z tern Number Categ Number Component Component Type SOSSSS 602010 SN-VT ---- N601 AUG VT HYDRAULIC SNUBBER 96 -VT; REJECT; ACTION REPORT 96-0285 GENERATED FOR LEAKING OZL & LOOSE NUT.

ADJUSTMENTS MADE & OIL CLEANED.'E-EXAM; NO RECORDABLE INDICATIONS ACCEPTABLE. SETTING 3 9/16" S/N = 6565. SNUBBER PROGRAM REQUIREMENTS APPLY.

70

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road Ontario NY 14519
3. Plant Unit 1- 4. Owner Certificate of Authorization (Zf Req.) N/A 5.Commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.):

G51. PRESS.RELIEF FM PRESS.TO RELIEF MANIFOLD (CONT.) DRAWINGS: S-2 Summary Exam Ztem Number Categ Number Component Component Type 602020 SN-VT ---- N602 AUG VT HYDRAULIC SNUBBER 96 VTr SETTING 2 7/16 f S/N 65686 NO RECORDABLE & INSIGNIFICANTS FLUID LEVEL 3/4 FULL ACCEPTABLE.

602030 SN-VT ---- N604 AUG VT HYDRAULIC SNUBBER 96 VTa SETTING 1 3/4 6 S/N 65666 NO RECORDABLE & ZNSIGNZFICANTS FLUID LEVEL 1/2 FULL - ACCEPTABLE.

602040 SN-VT ---- N605 AUG VT HYDRAULIC SNUBBER T

96 VTr SETTING 2 3/4 f S/N 6561 6'O RECORDABLE & INSZGNI FICANTS FLUZD LEVEL AT LEAST 1/2 FULL ACCEPTABLE.

602050 SN-VT ---- N607 AUG VT HYDRAULIC SNUBBER 96 VTS SETTING 3 3/4 f S/N 65629 NO RECORDABLE & INSIGNIFICANTS FLUID LEVEL 1/2 FULL ACCEPTABLE.

602060 SN-VT ---- N608 AUG VT HYDRAULIC SNUBBER 96 -VTa RE JECTa ACTION REPORT 96-0287 GENERATED FOR LEAKING OIL. RE-EXAM AFTER REPAIRS. NO RECORDABLE INDICATIONS ACCEPTABLE. SNUBBER PROGRAM REQUIREMENTS APPLY.

71

P' R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report, 1990-1999 Interval, Second Period, Fourth Outage (1996)

l. Owner Rochester Gas & Electric Cor .,89 East Ave. Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.Commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.):

G51. PRESS.RELIEF FM PRESS.TO RELZEF MANIFOLD (CONT.) DRAWINGS: S-2 Summary Exam Item Number Categ Number Component Component Type 602070 SN-VT N615 AUG VT HYDRAULIC SNUBBER 96 -VT; REJECT; ACTION REPORT 96-0283 GENERATED TO ADDRESS LEAKING OIL. OIL COMING FROM VENT- USE AS IS. NO RECORDABLE & INSIGNIFICANT, FLUID LEVEL 1/2 FULL ACCEPTABLE. SETTING 2 3/8", S/N = 6564. SNUBBER PROGRAM REQUIREMENTS APPLY.

602080 SN-VT ---- N616 AUG VT HYDRAULIC SNUBBER 96 -VT; REJECT'CTZON REPORT 96-0621 GENERATED FOR SETTING. SETTINGS ACCEPTABLE PER ACTION REPORT & MECH ENG MEMO. NO RECORDABLE &

INSIGNIFZCANTS FLUID LEVEL 1/2 FULL ACCEPTABLE'ETTINGS HOT 3 5/8 COLD 3 1/4 9

'S/N 18193 'NUBBER PROGRAM REQUIREMENTS APPLY'02081 SN-FT ---- N616 AUG FT HYDRAULIC SNUBBER 96 -FT; FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM. TESTED OPERABLE, SNUBBER WAS REPLACED'52.

POWER PRESS. RELIEF LINE DRAWINGS: S-1 Summary Item Number Categ Number Component Component Type BB 602090 SN-VT PS-2 AUG VT HYDRAULIC SNUBBER 96 VT SETTING 4 i/8 9 S/N, PD 87239 12449 NO RECORDABLE & INSIGNIFICANTr FLUID LEVEL 1/8" RED SHOWING ACCEPTABLE.

72

R. E. GZNNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.)

G52. POWER PRESS.RELIEF LINE (CONT.) DRAWINGS: S-1 Summary Item Number Categ Number Component Component Type Exam 602100 SN-VT PS-4 AUG VT HYDRAULIC SNUBBER 96 VTS SETTING 1 3/16 9 S/N PD 86144 1 152 f NO RECORDABLE & ZNSZGNI FICANTS FLUID LEVEL 1/8 RED SHOWING 3/8 GREEN ACCEPTABLE.

G53. 3-IN. PRESSURIZER RELIEF LINE DRAWINGS: A-12 Summary Item NDE Number Categ Number Component Component Type Exam 602110 SN-VT PS-5 AUG VT HYDRAULIC SNUBBER 96 VTr SETTING 2 3/4 f S/N PD 87238 12469 NO RECORDABLE & INSIGNIFICANT/

FLUID LEVEL 3/16 RED 1/8 GREEN ACCEPTABLE.

602120 SN-VT ---- PS-6 AUG VT HYDRAULIC SNUBBER 96 VTS SETTING 3 1/2 f S/N PD 87767 1239f NO RECORDABLE & INSIGNZFICANTS FLUID LEVEL 5/8 RED 1/16 GREEN ACCEPTABLE.

602121 SN- FT ---- PS-6 AUG FT HYDRAULIC SNUBBER 96 -FT FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM. TESTED OPERABLE.

.602130 SN-VT ---- PS-8 AUG VT HYDRAULIC SNUBBER 96 VTS SETTING 2 7/8 f S/N PD 86144 1 1599 NO RECORDABLE & INSIGNIFICANTJ FLUID LEVEL 1/16 GREEN 1/4 RED - ACCEPTABLE.

73

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant,1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.Commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.):

G54. POWER PRESS.RELIEF LINE DRAWZNGS: S-1A Summary Exam Item Number Categ Number Component Component Type Exam 602140 SN-VT PS-9 AUG VT HYDRAULIC SNUBBER 96 -VT; REJECT; ACTION REPORTS 96-0282 & 96-0685 GENERATED FOR SETTINGS &

NOTIFICATION PROBLEM. RE-EXAM AFTER CORRECTION ACCEPTABLE. SETTINGS ACCEPTABLE PER MECH ENG MEMO. SETTING 3 3/4", S/N = PD 86144-1154.

SNUBBER PROGRAM REQUIREMENTS APPLY.

602150 SN-VT ---- PS-10 AUG VT HYDRAULIC SNUBBER 96 -VT; SETTING 3 7/8", S/N = PD 86144-1157, NO RECORDABLE & INSIGNIFICANT, FLUID LEVEL 1/32 GREEN 1/4 RED ACCEPTABLE.

602160 SN-VT ---- 'S-11 AUG VT HYDRAULIC SNUBBER 96 VTr'ETTING 2 3/8 9 S/N PD 86144 1 1569 NO RECORDABLE & INSZGNIFICANTS FLUID LEVEL 1/4 RED 1/8 GREEN ACCEPTABLE.

G55. SEAL WATER RETURN FROM RCP-B DRAWINGS: S-3 Summary Exam Item Number Categ Number Component Component Type 602200 SN-VT CVU-131 AUG VT MECHANICAL SNUBBER 96 VT SETTING 2 1 /2 9 S/N 25432 9 NO RECORDABLE INDICATIONS ACCE PTABLE 602201 SN-FT ---- CVU-131 AUG FT MECHANICAL SNUBBER 96 -FT; FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM. TESTED OPERABLE.

74

e R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.commercial Service Date ~cul 1970 S.National Board Number for Unit N/A ATTACHMENT I I

SNUBBER PROGRAM COMPONENTS (CONT. )

G55. SEAL WATER RETURN FROM RCP-B (CONT.) DRAWINGS: S-3 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602300 SN-VT ---- CVU-550 AUG VT MECHANICAL SNUBBER 96 -VT; SETTING 2 1/4", S/N = 18190, NO RECORDABLE INDICATIONS ACCEPTABLE.

G56. STANDBY AUX FW THRU PEN 123 TO B S/G FWHD ZNCV DRAWINGS: C-24 Summary Exam Item NDE Number Categ Number Component Component Type Exam 602400 SN-VT AFU-209 AUG VT HYDRAULIC SNUBBER 96 VTa SETTING 2 5/1 6 9 S/N 12904 9 NO RECORDABLE & INSZGNZ FICANTS FLUID LEVEL 20%, W/0 TO BE GENERATED TO ADD OIL TO RESERVOIR ACCEPTABLE.

G57. STANDBY AUX FW THRU PEN 119 TO A S/G FWHD ZNCV DRAWINGS C-20 Summary Exam Item Number Categ Number Component Component Type 602500 SN-VT AFU-229 AUG VT HYDRAULIC SNUBBER 96 -VT: REJECT; ACTION REPORT 96-0432 GENERATED DUE TO SETTING. SETTINGS OK PER ACTION REPORT. NO RECORDABLE & INSZGNZFICANT, FLUID LEVEL 1/2 FULL ACCEPTABLE'ETTINGSS HOT 4 1/8 f COLD 2 13/16 9 S/N 12900 SNUBBER PROGRAM REQUIREMENTS APPLY.

75

0' R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor ., 89 East Ave., Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road, Ontario NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (Zf Req.) N/A S.commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT I SNUBBER PROGRAM COMPONENTS (CONT.):

G58. STANDBY AUX FW THRU PEN 119 TO A S/G FWHD ZNCV DRAWINGS: C-20 Summary Exam Item Number Categ Number Component Component Type Exam 602501 SN-FT AFU-229 AUG FT HYDRAULIC SNUBBER 96 -FT; FUNCTIONAL TEST REQUIRED BY SNUBBER PROGRAM. SNUBBER FAILED FUNCTIONAL TESTS SCOPE EXPANSION REQUIRED TO INCLUDE AFU 2269 SNUBBER WAS REPLACED, SNUBBER WILL BE FUNCTIONAL TESTED IN 1997.

H. SEZSMZC SUPPORTS:

H1 CVCS LETDOWNS PEN 1 12 TO REG HT ~ EXCH ~ DRAWINGS: B-32 Summary Exam Item Number Categ Number Component Component Type 700100 SS-CS ~F1.20R CVU-84 OE VT GUIDE &

INTEGRAL ATTACHMENT 96 -VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

H2. MAZNSTEAM DRAWINGS: B-9A Summary Exam Ztem Number Categ Number Component Component Type 245SBRRBBQ 700450 SS-CS *F1.20R MSU-59 OE VT RIGID SUPPORT &

INTEGRAL ATTACHMENT 96 -VT; NO RECORDABLE INDICATIONS ACCEPTABLE.

76

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

1. Owner Rochester Gas & Electric Cor .,89 East Ave.,Rochester NY 14649
2. Plant R.E.Ginna Nuclear Power Plant 1503 Lake Road, Ontario NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.Commercial Service Date ~Jul 1970 S.National Board Number for Unit N/A ATTACHMENT Z SEISMIC SUPPORTS (Cont.)

H2. MAZNSTEAM (CONT. ) DRAWINGS: B-9A Summary Exam Item Number Categ Number Component Component Type Exam 700500 SS-CS *F1.20R MSU-54 VT RIGID SUPPORT &

INTEGRAL ATTACHMENT 96 VT f NO RECORDABLE & INSIGNE FZCANTf LOCKNUTS OBSERVED TO BE LOOSE 9 ADJUSTMENTS MADE 6 NOT SERVICE INDUCEDf SEE 1 994 RESULTS & NCR94 0606 ACCEPTABLE.

700530 SS-CS *F1.20R MSU-49 OE VT RIGID SUPPORT &

INTEGRAL ATTACHMENT 96 VTf I NO RECORDABLE & INS GNZ FI CANTf NE BASE PLATE IS LOOSE f IAW NCR9 4 0 64 9 ATTACHMENT 1 f ITEM 2 f LATERAL RESTRAINT IS NOT REQUIRED ACCEPTABLE ~

H3. S/G BLOWDOWN FROM PEN 322 & 321 TO N/C PIPING DRAWINGS: SS-3 Summary Item Number Categ Number Component Component Type 700680 SS-CS *F1.20A BDU-23 AUG VT ANCHOR &

INTEGRAL ATTACHMENT 96 -VTf'O RECORDABLE INDICATIONS ACCEPTABLE.

700700 SS-CS *F1.20A BDU-27 OE VT ANCHOR &

INTEGRAL ATTACHMENT 96 -VT; NO RECORDABLE INDICATIONS - ACCEPTABLE.

77

R. E. GZNNA NUCLEAR POWER PLANT Znservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

l. Owner Rochester Gas & Electric Cor . 89 East Ave.,Rochester NY 14649 "2. Plant R.E.Ginna Nuclear Power Plant, 1503 Lake Road, Ontario, NY 14519
3. Plant Unit 1 4. Owner Certificate of Authorization (If Req.) N/A S.Commercial Service Date ~Jul 1970 S.National Board Number for Unit NIA ATTACHMENT I SEISMIC SUPPORTS (Cont.):
84. SAFETY ZNJECTZON SYSTEM DRAWINGS: A-17 Summary Item Number Categ Number Component Component Type 700710 SS-CS *F1.20R SIU-8 AUG VT RIGID SUPPORT 96 -VT; REJECT, ACTION REPORT 96-0445 GENERATED FOR FOREIGN MATERIAL BETWEEN PIPE & SUPPORT USE AS IS PER ACTION REPORTS DRAWING TO BE REVISED TO INCLUDE THIS MATERIAL. NO RECORDABLE INDICATIONS ACCEPTABLE.

f 78

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As R uired b the Provisions of the ASME Code Section XI 1.0wnerRochester Gas & Electric Cor Date 13 Se tember 1996 89 East Ave., Rochester, NY 14649 Sheet 1 of 27

2. Plant R.E. Ginna Nuclear Power Plant Unit 1503 Lake Road, Ontario NY 14519 (*)

Address Repair Organization P.O. No. Job No., etc.

~

3. Work Performed by (*) Type Code Symbol Stamp N/A Name Authorization No. N/A

(*) Expiration Date N/A Address

4. Identification of System (*)

E. (a) Applioaeledonarrnoaon Code~19~ Edidon~ Addenda,~

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1 gpss Code dana

6. Identi%cation of Components Repaired or Replaced and Replacement Components ASME Repaired Code .

National Replaced Stamped Name of Name of Manufacturer Board Other Year or (Yes Com nent Manufacturer Serial No. No. Identification Build Re lacement or No

7. Description of Work
8. Tests Conducted:(') Hydrostatic C) Pneumatic 0 Nominal Operating Pressure 0 Other 0 Pressure psi Test Temp. 'F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8-1/2 In. x 11 in., (2) information in items 1 through 6 on this 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.

(') See "ATTACHMENT II" FOR APPLICABLE INFORMATION (12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N. Y. 10017 1

FORM NIS-2 (Back) 9.Remarks Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this " conforms to the rules of the ASME Code,Section XI. repair or replacement Type Code Symbol Stamp Certificate o Autho 'tion No. N/A Expiration Date NIA Signed FA Kle ki I I n in r Dae Se mb r Ovmer or Ovm r'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 and employed by of have inspected the components described in this Owner's Report during the period

  • xo 4

~M 9' to

, and state that to the best of my knowledge and belief, the Ovmer has performed examinations and taken corrective measures described in this Owner's Report in accordance viith the inspection plan and as required by the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's 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.

Commissions Inspector's Signature National Board, State, Province, and Endorsements Date tg 5'~

(') See "ATTACHMENT II" FOR APPLICABLE INFORMATION

(-) Repair, Replacement or Modification as identified within "ATTACHMENT II"

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)

l. Oavner: V 4 4
2. Plant: R,E, Ginna Nuclear Popover Plant 1503 Lake Rd. Ontario . 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

and MODIFICATION PROGRAM

  • "'EPAIR, REPLACEMENT The Repair, Replacement and Modification (RR&M) Program, as identified within the "Inservice Inspection (ISI) Program",

identifies component jurisdiction and associated requirements.

Applicable Repair, Replacement or Modification activities have been performed in accordance with ASME Section XI Code, 1986 edition, no addenda.

When an item under the rules and requirements of the "Inservice Inspection (ISI) Program" is found deficient, an Engineering "use-as-is" evaluation may result. This determination is indicated within the ISI Program Summary, "Attachment I", for the applicable component within this report.

results in a Code Repair, Replacement or Modification; the If the deficiency deficiency will be classified as one of three category types.

These category types shall consist of a "Code Service Induced Rejectable Indication", a "Code Rejectable Indication" and a "Corrective Action Activity".

A "Code Service Induced Rejectable Indication" occurs when a component under the RR&M Program contains an indication that is beyond ASME Section XI Code acceptable standards and was determined to be "Service Induced". "Service Induced" indications, stemming from Inservice Inspection Examinations (ISI), shall require additional expanded examinations. The associated expanded examinations shall be performed in accordance to the requirements of the ASME Section XI Code.

A "Code Rejectable Indication" occurs when a component under the RR&M Program contains an indication that is beyond ASME Section XI Code acceptable standards and was determined to be not "Service Induced". This category includes but is not limited to items such as welding discontinuities from a modification identified during ISI preservice examinations or component damage caused by human involvement.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)

l. Owner: ~ . e V 4
2. Plant: R E Ginna Nuclear Power lant 1503 La! e Rd. ntario . 45 9
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda'TTACHMFNT F

II A "Corrective Action Activity" may occur when a component under the RR&M Program requires corrective action. This corrective action may be a result from a maintenance operation that identifies a need to perform a Code Repair, Replacement or Modification. This category includes but is not limited to items such as machining a component to correct an identified problem or the removal and later reapplication of hardface material on pressure boundary surfaces.

The following groups have performed applicable Repair, Replacement and Modification activities during the 1996 Outage.

Each group has been identified by a number and will correspond to the groups'ame and address. Rochester Gas and Electric, Ginna Station departments will not be identified as like contractors but by generic name. In the below listing of Repairs, Replacements or Modifications; the work group will be identified by a number within the component discussion.

1. Rochester Gas & Electric, Ginna Station 1A. Rochester Gas & Electric, Laboratory & Inspection Services
2. NPS Energy Services 280 King of Prussia Road Radnor, Pa. 19087

'3. Bechtel Power Corporation 9801 Washington Boulevard Gaithersburg, Maryland 20878-5356

4. Team Leak, Inc.,

Syracuse, New York

5. Babcock & Wilcox Canada

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Fourth Outage (1996)

l. Owner: c i ~. ec 'c ve s 4
2. Plant: R.E. Ginna Nuclear Power Plant 1503 Lake Rd. Ontario N.Y. 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

The following information will report applicable Repairs, Replacements or Modifications performed at R. E. Ginna Nuclear Power Plant during this reporting period as required by ASME Section XI Code.

ASME Class: 1 ~Sstem: Pressurizer GORR Mo.: 96-E-001 3A-RC8-2501 Construction Code: ASME Section III '86; Work Performed B : 2 Name of Com onent: V430, V431C Plugs & Cages Work Descri tion/Remarks: A Replacement activity was initiated for plugs & cages associated with Valves 430 & 431C.

This activity was controlled by WO ¹'s 19504164 ,19503981; and PCR 96-032. Upon activity conclusion, a VT-2 Leakage Examination was performed & acceptable under PT-7 (01.1).

2. ASME Class: 2 ~S stem: SI GORR No  : 95-E-012 Construction Code: ASME Section III '86; Work Performed B : 1 Name of Com onent: V891C Weld Repair Work Descri tion/Remarks: An ASME Section XI Code Repair was performed on the upstream socket weld at Valve 891C that was found leaking. This activity was controlled by WO ¹ 19501520

& NCR 95-052. Construction Surface (PT) & Visual (VT) examinations were performed and acceptable. Upon conclusion of the Repair Cycle, a Hydrostatic Test and accompanying VT-2 Examination was performed & acceptable.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990- 1999 Interval, Second Period, Fourth Outage (1996)

l. Owner: R n v 4 4
2. Plant: R. Ginna uclear Power Plant 1503 Lake d. Ontario N.Y 145 9
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda TTACHMF.

3. ASME Class: 2 ~Ss tern: RHR GORR No.: 96-001 Construction Code: B31.1 '55, SP-5291, ASME III '86 Work Performed B : 1 Name of Com onent: FE-673 Studs & Nuts Work Descri tion/Remarks: A Replacement activity was initiated for studs & nuts associated with FE-673. This activity was controlled by WO ¹ 19501415. Upon reinstallation, an ASME Section XI VT-2 Leakage examination was performed and acceptable.
4. ASME Class: 2 ~S stem: SAFW GORR No.: 96-002 Construction Code: ASME III, NF 1974 Work Performed B : 1 Name of Com onent: AFU-123 Snubber Replacement Work Descri tion/Remarks: A Snubber Replacement activity was initiated for support AFU-123. This activity was controlled by WO ¹ 19404238 and Action Report 95-0232. Upon reinstallation, a VT-3 Preservice (Baseline) examination was performed and acceptable.
5. ASME Class: l ~Sstem: Steam Generators GORR No.: 96-003 Line: N/A Construction Code: B31.1 '55, SP-5291 Work Performed B : 1 Name of Com onent: S/G "B" Snubber (SGB-3) Replacement Work Descri tion/Remarks: A Snubber Replacement activity was initiated for support SGB-3 on S/G "B". This activity was controlled by WO ¹ 19404251 and Action Report 95-0232. Upon reinstallation, a VT-3 Preservice (Baseline) examination was performed and acceptable.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Iriterval, Second Period, Fourth Outage (1996)

l. Owner: V 4
2. Plant: R.E Ginna Nuclear Power Plant 1503 I.ake Rd. ntario .Y. 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda TTACHME I

6. ASME Class: 2 ~S stem: CVCS-Letdown GORR No.: 96-004 Construction Code: ASME III NF '74 Work Performed B : 1 Name of Com onent: CVU-80 Snubber Replacement Work Descri tion/Remarks: A Snubber Replacement activity was initiated for support CVU-80. This activity was controlled by WO ¹ 19404240 and Action Report 95-0232. Upon reinstallation, a VT-3 Preservice (Baseline) examination was performed and acceptable.
7. ASME Class: 2 ~S stem: CVCS GORR No.: 96-005 Construction Code: ASME Work Performed B : 1 III NF '74, SP-5291, ME-318 Name of Com onent: CVU-372 Snubber Replacement Work Descri tion/Remarks: A Snubber Replacement activity was initiated for support CVU-372. This activity was controlled by WO ¹ 19404241 and Action Report 95-0232. Upon reinstallation, a VT-3 Preservice (Baseline) examination was performed and acceptable.
8. ASME Class: 3 ~S stem: AFW GORR No.: 96-006 Construction Code: ASME III NF '74, SP-5291, ME-318 Work Performed B : 1 Name of Com onent: AFU-34 Snubber Replacement Work Descri tion/Remarks: A Snubber Replacement activity was initiated for support AFU-34. This activity was controlled by WO ¹ 19404236. Upon reinstallation, a VT-3 Preservice (Baseline) exam'.nation was performed and acceptable.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)

l. Owner: ve
2. Plant: R,F. Ginna Nuclear Power Plant 150 ake Rd, Ontario N Y 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda

9. ASME Class: 2 ~S stem: MS GORR No.: 96-008 Construction Code: ASME III NF '74, SP-5291, ME-318 Work Performed B : 1 Name of Com onent: MSU-60 Snubber Replacement Work Descri tion/Remarks: A Snubber Replacement activity was initiated for support MSU-60. This activity was controlled by WO g 19501414 and NCR 95-039. Upon reinstallation, a VT-3 Preservice (Baseline) examination was performed and acceptable.
10. ASME Class: 3 ~S stem: SW GORR No 96-009

/

Construction Code: B31.1 '55, Gilbert Spec R0-2204, SP-5291 Work Performed B  : 1 Name of Com onent: PSW01D, SW Pump D Bowl Ass'y & Shaft Work Descri tion/Remarks: A Bowl assembly with shaft Replacement activity was initiated for Service Water Pump "D" with previously rebuilt items. This activity was controlled by WO 5 19500529, PCR 95-023 and NCR 95-061. Upon reinstallation, a VT-3 Preservice (Baseline) 'examination was performed and acceptable on the associated Rigid Restraint. Also, a VT-2 Leakage examination was performed and acceptable under PT-2.7.1 ASME Class: 2 ~S stem: MS GORR No.;96-010 "v

Construction Code: B31.1 '55, SP-5291 Work Performed B  : 4 Name of Com onent: V3517 Nuts Work Descri tion/Remarks: A Replacement activity was initiated for Valve 3517 Cap Nuts. This activity was controlled by WO 5 19503340 and TM 95-045. Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Fourth Outage (1996)

1. Owner: e ter ~ ~

c V e 4 4

2. Plant: R.E. Ginna Nuclear Power Plant 1503 I.ake Rd. Ontario N.Y. 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda TTACHMFNT I

12. ASME Class: 3 ~S stem: SW GORR No.: 96-011 Construction Code: B31.1 '55, SP-5291, ASME III '86 Work Performed B : 1 Name of Com onent: ACA05, Piping & Fittings Work Descri tion/Remarks: A Replacement activity was initiated for Penetration Cooler ACA05, Piping & Fittings. This activity was controlled by WO ¹ 19404349 and Action Report 96-0115.

Construction Code VT examinations were performed and acceptable on the Soldered Copper joints. Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

13. ASME Class: 3 ~Sstem: Aux. FW GORR No.: 96-013 "v

Construction Code:

Work Performed B31.1 '55, SP-5291, ASME III '86, B16.34 B : 1 Name of Com onent: V4009 Disc Replacement Work Descri tion/Remarks: A Replacement activity was initiated for the Disc associated with Valve 4009. This activity was controlled by WO ¹'s 19600808, 19600964. Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.'4.

ASME Class: 3 ~S stem: SW GORR No: 96-014

/

Construction Work Performed B :

Code: SP-5291, ASME III '86 1

Name of Com onent: ESW08A, ESW09A Bolting Work Descri tion/Remarks: A Replacement activity was initiated on bolting associated with D/G "A" Jacket Water and Lube Oil Heat Exchangers (Shell & Tube sides) as well as a 1/2" bolt on ESW09A West Base Support. This activity was controlled by WO

¹ 19501745. Construction Code VT examinations were performed and acceptable on ESW09A West Base Support. Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)

l. Owner: v e 4 4
2. Plant: R.E. Ginna Nuclear Power Plant 15031 ake Rd. Ontario N.Y, 14519
3. Applicable Edition of Section Xl Utilized for Repairs, Replaccmcnts or Modifications:

1986 No Addenda TT CHME I

15. ASME Class: 2 ~S stem: SI GORR No.: 96-015 Construction Code: B31.1 '55, SP-5291, ASME III '86 Work Performed B  : 1 Name of Com onent; Piping & Fittings upstream of V891C Relief Re uest: RR ¹31 (Code Case N-416-1)

Work Descri tion/Remarks: A Replacement activity was initiated for 1 1/2" piping & fittings upstream of Valve 891C to the 3" Header. This activity was controlled by WO ¹ 19501554 and Action Report 95-0394. Construction Code VT and PT examinations were performed and acceptable. Upon completion of this replacement activity, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance with RG&E Relief Request ¹31.

16. ASME Class: 2 ~S stem: MS GORR No.: 96-017 Construction Code: ASME III '77/'86 Work Performed B  : 2 Name of Com onent: V3504A; Disc, Stem & Bonnet Bolting Work Descri tion/Remarks: A Replacement activity was initiated for the Disc, Stem & Bonnet Bolting associated with Valve 3504A. This activity was controlled by WO ¹ 19504931. Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable..
17. ASME Class: 2 ~S stem: CVCS GORR No.: 96-019 Line: 3G-CH-151 Construction Code: B31.1 '5, G-676262, SP-5291 Work Performed B : 1 Name of Com onent: V313 Disc Work Descri tion/Remarks: A Replacement activity was initiated for the Disc associated. with Valve 313. This activity was controlled by WO ¹ 19502488. Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was .

performed and acceptable.

10

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Fourth Outage (1996)

l. Owner: e~ z s V
2. Plant: R.. Ginna Nuclear Power Plant 1503 Lake Rd, Ontario . Y 14519
3. Applicable Edition of Section Xl Utilized for Repairs, Replacements or Modifications:

ATTACHMENT II

18. ASME Class: 1 ~S stem: RCS GORR No.: 96-024 Construction Code: B31.1 '55, MSS-SP-69, ASME III '86 SP-5291 Work Performed B : 2 Name of Com onent: V431B Internals Work Descri tion/Remarks: A Replacement activity was initiated for Valve 431B Plug, Cage and Spacer. Also, the Bonnet gasket area was modified to allow for the installation of a thicker gasket. This activity was controlled by WO ¹ 19601119, Action Report 96-0375, PCR 96-041 and TE 91-515. Construction Code PT examinations were, performed and acceptable on the closure and seat surfaces, and Bonnet. Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance with PT-7 (01.1).
19. ASME Class: 3 ~S stem: Diesel Generators GORR No.: 96-026 Line: N/A Construction Code: B31.1 '55, SP-5291, ASME III '86 Work Performed B  : 1 Name of Com onent: ESW08B, ESW09B Bolting Replacement Work Descri tion/Remarks: A'olting Replacement activity was initiated on ESW08B & ESW09B Heat Exchangers. This activity was controlled by WO ¹ 19501746 and Action Report 96-0041.

Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

20. ASME Class: 1 ~S stem: RCS/Pressurizer GORR No.: 96-027 3A-RC8-2501-B Construction Code: ASME III '86 Work Performed B : 2 Name of Com onent: Valves 431A & 431B Gasket Seat Repairs Work Descri tion/Remarks: A Repair by metal removal was initiated on the Bonnet gasket seating surface for Valves 431A and 431B. This activity was controlled by WO ¹ 19601119 and PCR 96-041. Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance with PT-7 (01.1).

11

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Fourth Outage (1996)

l. Owner: t v e 4
2. Plant: R.E. Ginna Nuclear Powe Pla t l 3 ake d. Ontario Y 45 9
3. Applicable Edition of Section Xl Utilized for Repairs, Replacements or Modifications:

l986 No Addenda

21. ASME Class: 3 ~Sstem: CCW GORR No 96-028 Corrective Action Activity 3H-AC6-152 Construction Code: B31.1 '55, G-676262, ASME III '86/'92 Work Performed B : 1 Name of Com onent: FIC 609/613, Valves 762A/B & Piping Relief Re uest: RR ¹31 (Code Case N-416-1)

Work Descri tion/Remarks: A Replacement activity was initiated for FIC-609, FIC-613, Valves 762A & 762B, and associated piping. This activity was controlled by WO ¹ 19320707 and TE 94-552. Construction Code Final Surface (PT/MT) examinations were performed and acceptable. Root Pass Surface examinations were also performed and acceptable. Upon completion of this replacement activity, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance with RG&E Relief Request ¹31.

22. ASME Class:

Construction Code:

Work Performed Name of Com 1

3 ~S B :

stem:

~

ASME 1

AFW VIII, B31.1 onent: EAF02A, EAF02B Tube Ass'y Replacement Work Descri tion/Remarks: A Replacement activity was initiated

'55 GORR No.: 96-029 y

for the Shell and Tube Assembly associated with EAF02A &

EAF02B Aux. Feedwater Lube Oil Coolers. This activity was controlled by WO ¹ 19503511 and EWR ME-JEB-A. Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

12

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Fourth Outage (1996)

l. Owner: e e ras v e 4
2. Plant: R.E. Ginna Nuclearpower Plant 1503 1 ake Rd. Ontario .Y. 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda

23. ASME Class: 2 ~Sstem: MS GORR No.: 96-030 Construction Code:

Work Performed B :

B31.1 '55, SP-5291, ASME III '86 1

Name of Com onent: Valve 3516 Bolting Replacement & Flange Modification.

Work Descri tion/Remarks: A bolting Replacement activity was initiated on Valve 3516. Also, the valve body flange area was machined. This activity was controlled by WO ¹ 19502008. Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

24. ASME Class: 3 ~Sstem: CCW GORR No.: 96-031 Construction Code: B31.1 '55,, G-676262, SP-5291, B16.5 Work Performed B : 2 Name of Com onent: Valve 815A Replacement & Spacer Modification.

Work Descri tion/Remarks: A bolted Replacement activity was initiated on Valve 815A as well as the installation of a new spacer. This activity was controlled by WO ¹ 19400501 and TSR 96-563. A Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

25. ASME Class: 2 ~Sstem: MS GORR No.: 96-032 Construction Code: B31.1 '55, SP-5291, B16.5 '67 Work Performed B  : 2 Name of Com onent: Valve 3517 Bolt Modification.

Work Descri tion/Remarks: A Modification activity was initiated on Valve 3517 to replace an existing 1 3/4" Bonnet stud with a new "step stud. This activity was controlled by WO

¹ 19502007 and PCR 96-043. A Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

13

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Fourth Outage (1996)

l. Olvner: c V 4
2. Plant: R F. pinna Nuclear Power Plant 150 al'e Rd. Ontario N.Y, 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda ATTACHMFNT I

26. ASME Class: 2 ~S stem: Standby. Aux. FN GORR No.: 96-033 3C-FW-902S-1B Construction Code: ASME III NF '74/'86, SP-5291/ME-318 Work Performed B : 1 Name of Com onent: AFU-229 & AFU-208 Snubber Replacements Work Descri tion/Remarks: Snubber Replacement activities were initiated for support AFU-229 and AFU-208. These activities were controlled by WO ¹'s 19503968, 19503966 and Action Reports 96-0302, 96-0307. Upon reinstallation, a VT-3 Preservice (Baseline) examinations were per formed and acceptable.
27. ASME Class: 1 ~S stem: S/G GORR No.: 96-034 Line: N/A Construction Code; ASME III NF '86, SP-5291/ME-318, SP-5378 Work Performed B  : 3 Name of Com onent: SGB-4 Snubber Replacements Work Descri tion/Remarks: A Snubber Replacement activity was initiated for support SGB-4 on S/G "B" Ring Support Assembly.

This activity was controlled by WO ¹ 19505112 and SM-10034.4.17. Upon reinstallation, a VT-3 Preservice (Baseline) examination was performed and acceptable.

28. ASME Class: 1 ~Sstem: RCS GORR No.: 96-035 Construction Code: B31.1 '55, SP-5291, ME-121 Work Performed B : 1 Name of Com onent: N616 Snubber Replacements Work Descri tion/Remarks: A Snubber Replacement activity was initiated for support N616. This activity was controlled by WO

¹ 19503972, Action Report 96-0621 and EWR 10204. Upon reinstallation, a VT-3 Preservice (Baseline) examination was performed and acceptable.

e R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)

1. Owner: es e as 4 4
2. Plant: R.F. Oinna Nuclear Power Plant 1503 I al;e Rd. Ontario N Y 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda TTACHMFWT I

29. ASME Class: 3 ~S stem: Aux. FN GORR No.: 96-037 Construction Code: B31.1 '55, SP-5291, ASME III '86/'92, B16.34 '88.

Work Performed B  : 2 Name of Com onent: Valve 4007 Replacement Relief Re uest: RR ¹31 (Code Case N-416-1)

'ork Descri tion/Remarks: A Replacement activity was initiated for Valve 4007. This activity was controlled by WO ¹ 19601451.

Construction Code VT, PT and RT examinations were performed and acceptable. Root Pa'ss PT was also performed and acceptable. Upon completion of this replacement activity, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance with RG&E Relief Request ¹31.

30. ASME Class: 3 ~S stem: Aux. FN GORR No.': 96-038 Construction Code: B31.1 '55, SP-5291, ASME III '86/'92, B16.34 '88 Work Performed B  : 2 Name of Cpm onent: Valve 4008 Replacement Relief Re uest: RR ¹31 (Code Case N-416-1)

Work Descri tion/Remarks: A Replacement activity was initiated for Valve 4008. This activity was controlled by WO ¹ 19601452.

Construction Code VT, PT and RT examinations were performed and acceptable. Root Pass PT was also performed and acceptable. Upon completion of this replacement activity, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance'ith RG&E Relief Request ¹31.

15

i R. E. GINNA NUCLEAR POWER PLANT Inserv ice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)

1. Owner: t c V 4
2. Plant: R,F.. Crinna Nuclear Power Plant 150 Lake Rd. Ontario N.Y 14519
3. Applicable Edition of Section Xl Utilized for Repairs, Replacements or Modifications:

J

  • ATTACHMENT II
31. ASME Class: 2 ~S stem: Instrument Air GORR No.: 96-039 Construction Code: B31.1 '55, SP-5291 a

Work Performed B : 1 Name of Com onent: Valve 5393, Spring & Seat Replacement Work Descri tion/Remarks: A Replacement activity was initiated for the spring & seat associated with Valve 5393. This activity was controlled by WO ¹ 19601403. Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

32. ASME Class: 3 ~S stem: CCW GORR No.: 96-040 Construction Code: B31.1 '55, G-676262, SP-5291, ASME III '86/'92 Work Performed B : 1 Name of Com onent: New 2" Unions Modification Relief Re uest: RR ¹31 (Code Case N-416-1)

Work Descri tion/Remarks: A Modification activity was initiated to install new 2" Unions in CCW piping to & from the RHR Pumps. This activity was controlled by WO ¹'s 19504169, 19601679 and PCR 96-053. Construction Code VT and PT examinations were performed and acceptable. Upon completion of this activity, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance with RG&E Relief Request ¹31.

16

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Fourth Outage (1996)

1. Osvner: i~ c e.
2. Plant: R.F. Ciinna Nuclear Power Plant 1503 I.ai'e Rd. Ontario N.Y. 1451
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda ATTACHMENT ll

33. ASME Class: 2 ~S stem: Biowdown GORR Nowt 96-042 2B-MS-600-1A 2A-MS-600-1B 2B-MS-600-1B Construction Code:

'Work Performed B :

B31.1 '55, SP-5291, ASME III '86/'92 1

Name of Com onent: 2" Blowdown Piping for S/G "A" & "B" Relief Re uest: RR ¹31 (Code Case N-416-1)

Work Descri tion/Remarks: A Modification activity was initiated to replace existing 2" carbon steel piping with Crome Moly piping from both Steam Generators up to and including the downstream Tee connection. This activity was controlled by WO ¹ 19504580 and TSR 94-116. Construction Code RT, PT and VT examinations were performed and acceptable.

Upon completion of this activity, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance with RG&E Relief Request ¹31 and PT-7 (01.1) procedures.

34. ASME Class: 2/3 ~S stem: MS GORR No.: 96-043 30A-MS-600-1A 30B-MS-600-1 30A-MS-600-1 Construction Code: B31.1 '55, SP-5291, B16.6 '67 Work Performed B : 2 Name of Com onent: Valves 3516, 3517, 3518, 3519 Modification Work Descri tion/Remarks: A Modification activity was initiated to machine the body flange area of valves 3516, 3517, 3518 and 3519 to achieve proper gasket groove depth.

A 1 s o; on valve 3517, the retaining bar was reweldecLK Construction Code VT examination was performed and acceptable.

These activities were controlled by WO ¹'s 19501739, 19501765, 19502007 and 19502008; Action Reports 96-0417, 96-0590 and PCR 96-059. Upon completion of these activities, ASME Section XI

.Leakage Tests and associated VT-2 examinations were performed and acceptable.

17

R. E. GINNA'NUCLEARPOWER PLANT Inservice Inspection Report 1990 - 1999 Interval, Second Period, Fourth Outage (1996)

l. Owner: e V 4
2. Plant: R.F. Oinna Nuclear Power Plant 1503 Lake Rd. Ontario Y. 145 9
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:
35. ASME Class: 2 ~S stem: CVCS-Charging GORR No.: 96-044 d

Construction Code: B31.1 '55, G-676262, ASME III '86 Work Performed B : lA Name of Com onent: 8" CVCS Weld ¹1 Repair Work Descri tion/Remarks: During an Owner Elected PT examination on weld 8A-CH-2502 ¹1, a 3/4" linear indication was identified. A .Code Repair by metal removal was initiated.

This activity was controlled by WO ¹'s 19601798, 19502368, Action Report 96-0412 and PCR 96-061. Upon completion of the Repair Cycle by metal removal, a PT examination was reperformed and acceptable. UT thickness readings were -also performed and acceptable.

36. ASME Class: l ~S stem: RCS GORR No 96-045 4A-RC8-2501B Construction Code: B31.1 '55, G-676262 Work Performed B : 1 Name of Com onent: Valves 434, 435 Replacements Work Descri tion/Remarks: A Replacement activity was initiated on Valves 434 and 435 by mechanical means. This activity was controlled by WO ¹'s 19501724 and 19501725. Upon reinstallation; an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance with procedure PT-7(01.1).
37. ASME Class: 3 ~S stem: MS GORR No 96-046 Construction Code: B31.1 '55, SP-5291 Work Performed B : 1 Name of Com onent: Valve 3519, Items Replacement Work Descri tion/Remarks: A Replacement activity was initiated on Valve 3519 for the Shaft, Bushings, Keys and Studs. This activity was controlled by WO ¹ 19501765. Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

18

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)

l. Owner: v ete . 44
2. Plant: R.E. Ginna Nuclea Power lant 150'1 .al'e Rd, Ontar'o .Y 14519
3. Applicable Edition of Section Xl Utilized for Repairs, Replacements or Modifications:

1986 No Addenda

~*"'"

38. ASME Class: 2 ~S stem: MS GORR No.: 96-047 Constr'uction Code: B31;1 '55, SP-5291, ASME III '86/'92 Work Performed B : 1 Name of Com onent: Valve 3504C & Piping Replacement Relief Re uest: RR ¹31 (Code Case N-416-1)

Work Descri tion/Remarks: A Replacement activity was initiated for 1 1/2" piping and Valve 3504C. This activity was

.controlled by WO ¹ 19600032 and PCR 96-018. Construction Code VT and PT examinations were performed and acceptable. Upon completion of this replacement activity, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable in accordance with RG&E Relief Request ¹31.

39. ASME Class: 2 ~S stem: FN GORR No.: 96-048 Construction Code:.ASME III NF '74, SP-5291, ME-318 Work Performed B  : 1 Name of Com onent: FWU-3 Snubber Replacement Work Descri tion/Remarks: A Snubber Replacement activity was initiated for support FWU-3. This activity was controlled by WO ¹ 19601790 and Action Report 96-0466. Upon reinstallation, a VT-3 Preservice (Baseline) examination was performed and acceptable.
40. ASME Class: 2 ~S stem: MS GORR No.: 96-049 Construction Code: B31.1 / ASME III '77/'78 Work Performed B  : 2 Name of Com onent: Valve 3410, Items Replacement Work Descri tion/Remarks: A Replacement activity was initiated on Valve 3410 for the Pilot Plug and Stem. This activity was controlled by WO ¹ 19504890. Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.

19

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)

l. Owner: ~ ~E 'c V 4 4
2. Plant: R.F.. Csinna Nuclear Power Plant 150 I.al e Rd. Onta 'o N.Y. 14519
3. Applicable Edition of Section XI Utilized for Rep'airs, Replacements or Modifications:.
41. ASME Class: 3 ~Sstem: CCW GORR No 96-050 Construction Code: B31.1 '55, G-676262, ASME III '86 Work Performed B : 1 Name of Com onent: FE-651 Bolting Replacement Work Descri tion/Remarks: A Bolting Replacement activity was initiated on FE-651. This activity was controlled by WO ii 19500555 and Action Report 96-0626. Upon reinstallation, an ASME Section XI Leakage Test and associated VT-2 examination was performed and acceptable.
42. ASME Class: 2 ~S stem: EW GORR Noel 96-051 Construction Code: ASME III NF '74, SP-5291, ME-318 Work Performed B : 1 Name of Com onent: FWU-48 Snubber Replacement Work Descri tion/Remarks: A Snubber Replacement activity was initiated for support FWU-48. This activity was controlled by WO 8 19601937 and Action Report 96-0646. Upon reinstallation, a VT-3 Preservice (Baseline) examination was p'er formed and acceptable.
43. ASME Class: l ~S stem: Steam Generators GORR No.: 96-033

/

Construction Code: ASME III 1986 Work Performed B: 5 (Installation = 3) Code Stam ed: Yes Name of Com onent: S/G "A & B", EMS01A, EMS01B Relief Re uest: 8 31 (Code Case N-416-1)

Work Descri tion/Remarks: A Replacement activity was initiated for Steam Generators "A" and "Bue This activity was controlled by EWR'10034. Applicable Construction Code PT, MT, RT and UT examinations were performed and acceptable. Construction Code Hydrostatic Test was performed and acceptable. Applicable ASME Section XI Preservice (Baseline) examinations were performed and acceptable as documented within the 1996 NIS-1 "Attachment 1" section. These examinations included Surface, Volumetric and Eddy Current. Upon installation, ASME Section XI Leakage Test and accompanying VT-2 examination was performed and acceptable in accordance with RG&E Relief Request ii31 per procedure PT-7 (01.1) 20

R. E. GINNA NUCLEAR POPOVER PLANT Insetvice Inspection Report 1990- 1999 Interval, Second Period, Fourth Outage (1996)

l. Owner: los 4 4
2. Plant: .F. Ginna Nuclear Power Plant 1503 Lal e Rd. Ontario N.Y. 14519
3. Applicable Edition of Section Xl Utilized for Repairs, Replacements or Modifications:

1986 No Addenda I

44, ASME Class: 1 ~S stem: Steam Generators GORR No.: 96-054 Line: N/A Construction Code:

Work Performed AWS Dl.l, ASME III NF '74, SP-5378 B : 3 Name of Com onent: S/G "A & B", Lower Supports Work Descri tion/Remarks: A Replacement activity was initiated for Steam Generators "A", and "B" Lower Supports for the Steam Generator Replacement Project. This activity was controlled by WO ii's 19600798, 19600802, EWR 10034 and SM's 10034-4.23, 10034-4.15 . Construction Code MT examinations were performed and acceptable. ASME Section XI Preservice (Baseline) VT-3 examinations were performed and acceptable.

45. ASME Class: 1 ~Sstem: Steam Generators GORR No.: 96-055 Line: N/A Construction Code:

Work Performed AWS Dl.l, ASME III NF '74, SP-5378 B : 3 Name of Com onent: S/G "A & B", Intermediate Supports Work Descri tion/Remarks: A Replacement activity was initiated for Steam Generators "A" and "B" Intermediate Supports for the Steam Generator Replacement Project. This activity was controlled by WO I's 19600798, 19600802, EWR 10034 and SM's 10034-4.23, 10034-4.15 . Construction Code VT examinations were performed and acceptable. ASME Section XI Preservice (Baseline) VT-3 examinations were performed and acceptable.

46. ASME Class: 1 ~S stem: Steam Generators GORR No.: 96-056 Line: N/A Construction Code: AWS Dl.l, ASME III NF '74, SP-5378 Work Performed B  : 3 Name of Corn onent: S/G "A & B", Upper Restraint Rings Work Descri tion/Remarks: A Replacement activity was initiated for Steam Generators "A" and "B" Upper Restraint Rings for the Steam Generator Replacement Project. This activity was controlled by WO 5's 19600574, 19600575, EWR 10034 and SM's 10034-4.22, 10034-4.21 .,Construction Code MT examinations were performed and acceptable. ASME Section XI Preservice (Baseline) VT-3 examinations were performed and acceptable.

21

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report

  • 1990 - 1999 Interval, Second Period, Fourth Outage (1996)
l. Owticr: ~ e v 4 4
2. Plant: R.F. Ginna nclear Popover Plant 1503 Lake Rd,'ntario N.Y. 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

1986 No Addenda ATTACHMENT I

47. ASME Class: l ~S stem: RCS GORR No.: 9,6-057 Line: N/A Construction Code: ASME III '86/'92, B31.1 '55, G-676343, G-676496 Work Performed B  : 3 Name of Com onent: S/G "A & B" RCS Attachment Welds Relief Re uest: ¹ 31 (Code Case N-416-1)

Work Descri tion/Remarks: A Replacement activity was initiated for Steam Generators "A" and "B" RCS reattachment welds. This activity was controlled by WO ¹'s 19600794, 19600799, EWR 10034 and SM's 10034-7.12, 10034-7.13 . Construction Code PT and RT examinations were performed and acceptable. ASME Section XI Preservice (Baseline) PT, RT/UT examinations were performed and acceptable as documented within the 1996 NIS-1 "Attachment 1" section. ASME Section XI Leakage Test and accompanying VT-2 examination was performed and acceptable in accordance with RG&E Relief Request ¹31 per procedure PT-7 (01.1).

48. ASME Class:

Work Performed l

/.. Code: ~S B :

stem:

~.

ASME RCS G-676496 3

III '86; GORR B31.1 '55, G-676343, Noet 96-058 "I'onstruction Name of Com onent: S/G "A & B", RCS Hot & Cold Leg Repairs Work Descri tion/Remarks: A Repair activity by metal removal was initiated for Steam Generators "A" and "B" RCS Hot and Cold Legs on identified piping locations to remove original construction defects, arc strikes, and gouges. This activity was controlled by WO ¹'s 19601418, 19601419, and Action Report 96-0272. Upon completion of the Repair Cycle, PT examinations as well as UT thickness readings were performed and acceptable.

22

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)

l. Owner: s c V 4
2. Plant: R,E, Cr nna Nuclear Power Plant 1503 I.al'e Rd, Ontario N, Y, 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:
49. ASME Class: 2 ~S stem: FW GORR Noet 96-059 Line: N/A Construction Code: ASME IXI '86; B31.1 '55, SP-5291 Work Performed B : 3 Name of Com onent: S/G "A & B"; FW Loops "A & B" Repairs Work Descri tion/Remarks: A Repair activity by metal removal was initiated for Steam Generators "A" and "B" Feedwater Loops "A & B" on identified piping locations to remove original construction defects, arc strikes, and gouges. This activity was controlled by WO ¹'s 19601422, 19601423, and Action Report 96-0269. Upon completion of the Repair Cycle, MT examinations as well as UT thickness readings were performed and acceptable.
50. ASME Class: 2 ~S stem: FW GORR No.: 96-060 Line: N/A Construction Code: ASME ME-318 III '86/'92, B31.1 '55, SP-5291, Work Performed B  : 3 Name of Com onent: S/G "A & B" FW Attachment Welds

.Relief Re uest: ¹ 31 (Code Case N-416-1)

Work Descri tion/Remarks: A Replacement activity was initiated for. Steam Generators "A" and "B" Feedwater reattachment welds.

-This activity was controlled by WO ¹'s 19600849, 19600848, EWR 10034 and SM's 10034-7.06, 10034-7.07 . Construction Code PT/MT and RT examinations were performed and acceptable. ASME Section XI Preservice (Baseline) PT/MT, RT/UT examinations were performed and acceptable as documented within the 1996 NIS-1 "Attachment 1" section. ASME Section XI Leakage Test and accompanying VT-2 examination was performed and acceptable in accordance with RG&E Relief Request ¹31 per procedure PT-7 (01.1).

23

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990- 1999 Interval, Second Period, Fourth Outage (1996)

l. Owner: s ~ ~

V 4 4

2. Plant: .F. Ginna uclear Power Plant 1503 Lake Rd. Ontario .Y 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:
51. ASME Class: 2 ~Sstem: MS GORR No.: 96-061 30B-MS-600-1B Construction Code: ASME III NF 1974 Work Performed B : 3 Name of Com onent: MS Support Reinstallations Work Descri tion/Remarks: A Replacement activity was initiated for Steam Generators "A" and "B" Mainsteam Spring Can Support reinstallation. The reinstallation covers supports MSU-1, MSU-4, MSU-6 and MSU-9. This activity was controlled by WO ¹'s 19600800I 19600801I EWR 10034I and SM s 10034 7 10 10034 7.11. Up'on reinstallation, an ASME Section XI Preservice (Baseline) VT examinations were performed and acceptable.
52. ASME Class: 2 ~Sstem: MS GORR Noet 96-062 Line: N/A Construction Code: ASME I1I '86; B31.1 '55, SP-5291 Work Performed B  : 3 Name of Com onent: S/G "A & B"; MS Loops "A & B" Repairs Work Descri tion/Remarks: A Repair activity by metal removal was initiated for Steam Generators "A" and "B" Mainsteam Loops "A & B" on identified piping locations to remove original construction defects, arc strikes, and.gouges. This activity was controlled by WO ¹'s 19601420, 19601421, and Action Report 96-0270. Upon completion of the Repair Cycle, MT examinations as well as UT thickness readings were performed and acceptable.

24

0, R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990- 1999 Interval, Second Period, Fourth Outage (1996)

l. Osvner. este les v este 4
2. Plant: R F pinna ncle r ower la t 503 akc 1 d. tario . 14519
3. Applicable Edition of Section XI Utilized for Repairs, Replaccmcnts or Modifications:

1986 No Addenda ATTACHMENT I

53. ASME Class: 2 ~S stem: MS GORR No.: 96-063 Line: N/A Construction Code: ASME III '86/'92, B31.1 '55, SP-5291, ME-318 Work Performed B : 3 Name of Com onent: S/G "A & B" MS Attachment Welds Relief Re uest: ¹ 31 (Code Case N-416-1)

Work Descri tion/Remarks: A Replacement activity was initiated for Steam Generators "A" and "B" Mainsteam reattachment welds.

This activity was controlled by WO ¹'s 19600800, 19600801, EWR 10034 and SM's 10034-7.10, 10034-7.11 . Construction Code PT/MT and RT examinations were performed and acceptable. ASME Section XI Preservice (Baseline) MT, RT/UT examinations were performed and acceptable as documented within the 1996 NIS-1 "Attachment 1" section. ASME Section XI Leakage Test and accompanying VT-2 examination was performed and acceptable in accordance with RG&E Relief Request ¹31 per procedure PT-7 (01.1).

54. ASME Class: 2 ~S stem: Blowdown GORR No.: 96-064 Line: N/A Construction Code: ASME III '86/'92, B31.1 '55, SP-5291, ME-318 Work Performed B  : 3 Name of Com onent: S/G "A & B" Blowdown Attachment Welds Relief Re uest: ¹ 31 (Code Case N-416-1)

Work Descri tion/Remarks: A Replacement activity was initiated for Steam Generators "A" and "B" Blowdown reattachment welds.

This activity was controlled by WO ¹'s'9600355, 19600356, EWR 10034.and SM's 10034-6.01, 10034-6.02 . Construction Code MT and RT examinations were. performed and acceptable. ASME Section XI Leakage Test and accompanying VT-2 examination was performed and acceptable in accordance with RG&E Relief Request ¹31 per procedure PT-7 (01.1).

25

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996)

. l. Owner: e sa A t' ete 44

2. Plant: R.E. Ginna Nuclear ower Plant 1503 Lake Rd, Ontario N.Y. 4519
3. Applicable Edition of Section XI Utilized for Repairs, Replacements or Modifications:

ATTACHKTFNT II

55. ASME Class: 2 ~S stem: FN GORR No.: 96-065 Line: N/A Construction Code: ASME III '86/'92, B31.1 '55, SP-5291 Work Performed B : 3 Name of Com onent: S/G "A & B" Level & Instrumentation Lines, Condensate Pots.

Relief Re uest: ¹ 31 (Code Case N-416-1)

Work Descri tion/Remarks: A Replacement activity was initiated for Steam Generators "A" and "B" Level & Instrumentation Lines and Condensate Pots. Condensate Pots replaced include SFW01, SFW02, SFW03; SFW04, SFW05, SFW06, SFW07, and SFW08. This activity was controlled by WO ¹'s 19600728, 19600727, EWR 10034 and SM's 10034-7.08, 10034-7.09 . Applicable Construction Code MT and RT examinations were performed and acceptable. ASME Section XI Leakage Test and accompanying VT-2 examination was performed and acceptable in accordance with RG&E Relief Request ¹31 per procedure PT-7 (Ol.l).

56. ASME Class: 2 ~S stem: MS GORR No.: 96-066 Line: N/A Construction Code:

Work Performed ASME III '86/'92,'31.1 '55, SP-5291 B  : 3 Name of Com onent: S/G "A & B" Condensate Pots to Flow Transmitters Relief Re uest: ¹ 31 (Code Case N-416-1)

Work Descri tion/Remarks: A Replacement activity was initiated for Steam Generators "A" and "B" Condensate Pots to Flow Transmitters.'low Transmitters replaced included SMS03A, SMS04A, SMSOSA, SMS06A, SMS03B, SMS04B, SMS05B, and SMS06B.

This activity was controlled by WO ¹'s 19600728, 19600727, EWR 10034 and SM's 10034-7.08, 10034-7.09 . Applicable Construction Code MT and RT examinations were performed and acceptable. ASME Section XI Leakage Test and accompanying VT-2 examination was performed and acceptable in accordance with RG&E Relief Request ¹31 per procedure PT-7 (01.1).

0 R. E. GINNA NUCLEAR POWER PLANT

l. Owner:

2.

3.

vas 'eInserv ice Inspection Report 1990 1999 Interval, Second Period, Fourth Outage (1996) cste e t st Plant: R.F.. Ginna Nuclear Power Plant 150 Lake Rd Ontario N.Y 14519 4 4 Applicable Edition of Section Xl Utilized for Repairs, Replacements or Modifications:

1986 No Addenda ATTACHMENT II

57. ASME Class: 2 ~Sstem: CS GORR No.: 96-067 Line: N/A Construction Code: B31.1 '55, G-676262, ASME III '86; ME-318 Work Performed B  : 3 Name of Com onent: Containment Spray Attachment Welds &

Supports.

Work Descri tion/Remarks: .A Replacement activity was initiated to reinstall Containment Spray-piping welds and Supports that were removed for the Steam Generator Replacement Project.

This activity was controlled by WO 8 19600898, EWR 10034, SM 10034-4.01 and Action Report 96-0241. Construction Code PT examinations were performed on the Root/Final welds and were acceptable. Construction Code VT examinations were performed and acceptable on associated component supports. The supports examined included CSU-98, CSU-99, CSU-100, CSU-105, CSU-106, CSU 1071 CSU 108I CSU 109I CSU 110I CSU 111I CSU 112I CSU 117I CSU-118, CSU-119 and CSU-120. An ASME Section XI Flow Test and accompanying VT-2 examination was performed and acceptable.

58. ASME Class: 2 ~S stem: FW GORR No 96-068

/

Construction Code: ASME III '86 Work Performed B : 3 Name of Com onent: FW "B" Loop, Punch Mark Repairs to Welds/Piping.

Work Descri tion/Remarks; A Repair activity was initiated to remove Punch Marks on weld/base metal associated with Welds AA5 and AA4R. This activity was controlled by WO 8 19600848, SM 10034-7.07, Bechtel NCR 069 and Bechtel WP&IR/MTI No. P-FWB-01. Punch Marks on existing welds were removed by metal removal. Punch Marks on piping were removed by metal removal and rewelded. Upon completion of the Repair Cycle, Surface MT examinations were performed and acceptable on both welded and metal removal repairs. Repairs by metal removal were controlled to ensure that minimum wall thickness was maintained.

27

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTm EROSION/CORROSION (MINWALL)PROGRAM

SUMMARY

This section provides Erosion/Corrosion examination details and information corresponding to items inspected during the 1996 Outage.

A total of 98 items were examined. The breakdown of this total is as follows:

m onentT e Total Number Pipes 45 Elbows 39 Reducers 12 Tees 2 Total 98 The following lists identifies systems of examined components, system component result summaries, and component result details.

S stems of Examined Com onents:

Component thickness measurements were performed on the following systems.

DWG.

NO. SYSTEMS M-12A MSR 1A & 1B 2ND PASS TO SA HEATER AND CONDENSER M-12B MSR 2A & 2B 2ND PASS TO'5B HEATER AND CONDENSER M-15B MSR 1B 4TH PASS TO SA HEATER M-19 1A, 2A, & 3A L.P. HEATER DRAINS TO CONDENSER M-21 STEAM EXT. TO PRESEP. TANKB & 4B L.P. HEATER M-22 STEAM EXT. TO PRESEP. TANK A & 4A L.P. HEATER M-75 STEAM EXTRACTION TO 5A & 5B HEATERS M-81 FEEDWATER DISCHARGE (TURBINE BUILDING)

M-84 FEEDWATER TO S/G 1A (CONTAINMENT)

M-85 FEEDWATER TO S/G 1B (CONTAINMENT)

M-88D S/G BLOWDOWN TO FLASH TANK (TURBINE BUILDING)

-M-91 FEEDWATER CLEANUP (CV-19)

M-91 FEEDWATER CLEANUP (CV-19)

M-92 MAINFEEDWATER PUMP RECIRCULATION M-99 GLAND STEAM CONDENSER TO TURB. GEN. & GOV.

M-100 MAINGLAND STEAM TO TURB. GEN. & GOV. ENDS M-103 F.W. HTR. DRAIN SYS. FROM H.D PUMPS TO H.T. TANK

R. E. GINNA NUCLEAR POWER PLANT Inserv ice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTm S stem Com onent Result Summaries:

The following break down by system provides general results on the component types that were examined.

DWG.

NO. SYSTEM M-12A MSR 1A&1B 2ND PASS TO SA HEATER AND CONDENSER Components Examined: Results (% of Nominal):

4 Pipes 7 >88 2 Elbows 1 88-82 3 Reducers 1 70-65 M-12B MSR 2A & 2B 2ND PASS TO 5B HEATER AND CONDENSER Components Examined: Results (% of Nominal):

1 Elbow 1 70-65 M-15B MSR 1B 4TH PASS TO 5A HEATER Components Examined: Results (% of Nominal):

3 Pipes 3 >88 2 Elbows 2 88-82 M-19 IA, 2A, & 3A LP. HEATER DRAINS TO CONDENSER Components Examined: 'esults(%ofNominal):

4 Pipes 9 >88 4 Elbows 1 Reducer M-21 STEAM EXT. TO PRESEP. TANKB & 4B L.P. HEATER Components Examined: Results (% of Nominal):

3 Pipes 3 >88 M-22 STEAM EXT. TO PRESEP. TANKA & 4A L.P. HEATER Components Examined: Results (% of Nominal):

4 Pipes 1 >88 3 <65

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTIII SYSTEM STEAM EXTRACTION TO 5A & 5B HEATERS Components Examined: Results (% of Nominal):

4 Pipes 5 >88 2 Elbows 2 76-70 1 Tee FEEDWATER DISCHARGE (TURBINE BUILDING)

Components Examined: Results (% of Nominal):

1 Pipe 1 >88 1 Reducer 1 82-76 1 Tee 1 >88 FEEDWATER TO S/G IA (CONTAINMENT)

Components Examined: Results (% of Nominal):

1 Pipe 3 Acceptable 3 Elbows 2 >88 1 Reducer FEEDWATER TO S/G 1B (CONTAINMENT)

Components Examined: Results (% of Nominal):

1 Pipe 4 Acceptable 3 Elbows 1 >88 1 Reducer S/G BLOWDOWN TO FLASH TANK (TURBINE BUILDING) 3 Pipes 2 Elbows

'esults Components Examined:

3 1

(% of Nominal):

>88 88-82 1 Reducer 2 <65

0 R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTm

, SYSTEM FEEDWATER CLEANUP (CV-19)

Components Examined: Results (% of Nominal):

1 Reducer 1 >88 MAINFEEDWATER PUMP RECIRCULATION Components Examined: Results'% of Nominal):

6 Pipes 9 >88 3 Elbows 1 88-82 2 Reducers 1 76-70 GLAND STEAM CONDENSER TO TURB. GEN. & GOV.

Components Examined: Results (% of Nominal):

4 Pipes 7 >88 8 Elbows 3 88-82 1 76-70 1 <65 MAINGLAND STEAM TO TURB. GEN. & GOV. ENDS Components Examined: Results (% of Nominal):

4 Pipes 3 70-65 8 Elbows 9 <65 F.W. HTR. DRAIN SYS. FROM H.D PUMPS TO H.T. TANK Components Examined: Results (% of nominal):

3 Pipes 5 >88 1 Elbow 1 Reducer 4

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTIII Com onent Result Details:

The following list provides examination result details on components by drawing number and system description. The "Component Type" classification specified in the list below corresponds to the following:

P = Pipe E = Elbow T = Tee R = Reducer/Expander J = Expansion Joint M-12A MSR 1AA1B 2ND PASS TO 5A HEATER AND CONDENSER Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Method 222070 7 R 0.300 0.432 0.134,0.192 0.214,0.352 76-70 UT .

222075 7A P 0.432 0.192 0.415 >88 UT 222080 8 E 0.432 0.194 0.403 >88 UT 222090 9 0.432 0.193 0.413 >88 UT 222290 27 E 0.432 0.268 0.423 >88 UT 222310 29 R 0.432 0.437 0.274,0.203 0.482,0.440 >88 UT 222330 31 R 0.337 0.594 0.154,0.284 0.400,0.567 >88 UT

0 R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTIII Com onent Result Details(CONTINUED)

M-12B MSR 2A & 2B 2ND PASS TO 5B HEATER AND CONDENSER Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Num r ID T Will WII2 All w I R din N min l h 222890 87 E 0.432 0.198 0.290 70-65 UT 223090 106 P 0.432 0.207 0.271 76-70 UT M-15B MSR 1B 4TH PASS TO 5A HEATER Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Method 227220 74 P 0.300 0.168 0.291 >88 UT 227230 75 E 0.300 0.169 0.283 >88 UT 227240 76 P 0.300 0.168 0.260 88-82 UT 227320 84 E 0.300 0.171 0.270 >88 UT 227330 85 P 0.300 0.168 0.260 88-82 UT

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTIII Com onent Result Details(CONTINUED)

M-19 1A, 2A, & 3A L.P. HEATER DRAINS TO CONDENSER Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE N m er ID T Will Wll2 All w l R in N min 1 Meth d 234010 01 R 0.594 0.500 0.207,0.174 0.567,0.522 >88 UT 234030 03 E 0.500 0.176 0.495 >88 UT 234040 04 P 0.500 0.173 0.484 >88 UT 234070 07 E 0.500 0.174 0.604 >88 UT 234075 07A E 0.500 0.173 0.505 >88 UT 234080 08 E 0.500 0.174 0.517 >88 UT 234090 09 P 0.500 0.173 0.484 >88 UT 234280 28 P 0.500 0.175 0.463 >88 UT 234290 29 E 0.500 0.177 0.460 >88 UT M-21 STEAM EXT. TO PRESEP. TANKB & 4B L.P. HEATER Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Method 301382 36B P 0 375 0.184 0.347 >88 UT 301383 36C P 0.375 0.184 0.363 >88 UT 301384 36D P 0.37'5 0.184 0.365 >88 UT

R. E. GINNA NUCLEAR PO%ER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTIII Com onent Result Details(CONTINUED)

M-22 STEAM EXT. TO PRESEP. TANK A & 4A L.P. HEATER Summary Comp. Comp. Nominal Nominal Minimum Minimum 'ercent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Method 302121 37AA P 0.375 0.184 0.221 <65 UT 302122 37AB P 0.375 0.184 0.210 <65 UT 302123 37AC P 0.375 0.184 0.229 <65 UT 302124 37AD P 0.375 0.184 0.253 70-65 UT M-75 STEAM EXTRACTION TO 5A & 5B HEATERS Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Method 303080 08 0.375 0.225 0.336 >88 UT 303090 09 T 0.375 0.230 0.392 >88 UT 303100 10 P 0.375 0.225 0.265 76-70 UT

'303110 11 E 0.375 0.234 0.359 >88 UT 303120 12 P 0.375 0.232 0.263 76-70 UT 303140 14, E 0.375 0.225 0.363 >88 UT 8

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTIII Com onent Result Details(CONTINUED)

M-81 FEEDWATER DISCHARGE (TURBINE BUILDING)

Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE m r ID T e Will W112 All w 1 Re in N mini eh 390060 06 R 0.844 0.938 0.627,0.631 0.660,0.755 >88 UT 390065 6A P 0.938 0.697 0.877 >88 UT 390010 01 T 1.281 0.697 1.48 >88 UT M-84 FEEDWATER TO S/G 1A (CONTAINMENT)

Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 Allowable Readin Nominal Method 393110 11 E 0.938 0.705 N/A Acceptable VT 393120 0 938 0.606 0.849 >88 UT

'/A 12 P 393130 13 E 0 938 0.703 Acceptable VT 393150 15 R 0.938 1.156 0.929,1.146 N/A Acceptable VT 393160 16 E 1.156 0.773 1.026 >88 UT 9

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTIII Com onent Result Details(CONTINUED)

M-85 FEEDWATER TO S/G 1B (CONTAINMENT)

Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE r ID T e Will W112 11 w le Re in mini M h 393630 13 E 0.938 0.700 N/A Acceptable VT 393640 14 P 0.938 0.606 N/A Acceptable VT 393650 15 E 0 938 0.706 N/A Acceptable VT 393670 17 E 0.938 1.156 0.704,0.903 N/A Acceptable VT 393680 18 P 0 938 0.893 1.025 >88 N-88D S/G BLOWDOWN TO FLASH TANK (TURBINE BUILDING)

Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Number ID T e Wall 1 Wall 2 All w 1 Rea in N minal Me h 385770 77 P 0.337 0.143 0.308 >88 UT 385775 77A R 0.337 0.500 0.143,0.224 0.279,0.467 88-82 UT 385777 77B, P 0.500 0.224 0.476 >88 UT 385780 78 E 0500 0.224 0.238 UT 385790 79 P 0500 0.224 0.229 (65 UT 0.461'65 385820 82 E 0.500 0.224 >88 UT

1' R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENT III Com onent Result Details(CONTINUED)

M-91 FEEDWATER CLEANUP (CV-19)

Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Num er ID T e Wall 1 Wall 2 All wa 1 Readin N minal Meth d 300860 40 R 0.432 0.337 0.337,0.236 0.408,0.316 >88 UT M-92 MAINFEEDWATER PUMP RECIRCULATION Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE N m er ID T e Walll W112 All w l a in N minal M th 281040 04 E 0.594 0.448 0.523 >88 UT 281050 05 P 0.594 0.375 0.553 >88 UT 281060 06 E 0.594 0.337 0.466,0.267 0.612,0.612 >88 UT 281070 07 P 0.337 0.218 0.343 >88 UT 281110 11 P 0.337 0.145 0.286 88-82 UT 281130 13 R 0.337 0.322 0.113,0.169 0.499,0.338 >88 UT 281200 20B E 0.594 0.337 0.466,0.267 0.420,0.420 <65 UT 281210 21 P 0.337 0.218 0.307 >88 UT 281250 25 P 0337 0.112 0.307 >88 UT 281270 27 R 0.337 0.322 0.113,0.169 0.535,0.372 >88 UT 281280 28 P 0322 0.168 0.319 >88 UT 11

R E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTm Com onent Result Details(CONTINUED)

M-99 GLAND STEAM CONDENSER TO TURB. GE¹ 4 GOV.

Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE N m er ID T e Wall 1 Wall 2 All wa le R din N min l Meh 374426 43B E 0.258 0.181 0.103 <65 UT 374427 43A P 0.258 0.18'1 0.213 88-82 UT 374440 44 E 0258 0.181 0.241 >88 RT 374486 49B E 0 258 0.181 0.230 >88 UT 374487 49A P 0.258 0.181 0.221 88-82 UT 374500 50 E 0.258 0.181 0.236 >88 RT 374566 57B E 0.258 0.181 0.208 76-70 UT 374567 57A P 0 258 0.181 0.229 >88 UT 374580 58 E 0.258 0.181 0.267 >88 RT 374626 63B E 0 258 0.181 0.185 76-70 UT 374627 63 A P 0.258 0.181 0.253 >88 UT 374640 64 E 0.258 0.181 0.244 88-82 RT 12

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTm Com onent Result Details(CONTINUED)

M-100 MAINGLAND STEAM TO TURB. GEN. & GOV. ENDS Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE Nm r ID T e Walll Wll2 All w 1 R in N minal Me h 375222 22B E 0.258 0.181 0.096 <65 UT 375223 '2C P 0.258 0.181 0.175 70-65 UT 375224 22D E 0.258 0.181 0.129 <65 UT 375322 32B E 0.258 0.181 0.174 70-65 UT 375323 32C P 0.258 0.181 0.178 76-70 UT 375324 32D E 0.258 0.181 0.155 <65 UT 375412 41B E 0.258 0.181 0.067 <65 UT 375413 41C P 0.258 0.181 0.145 70-65 UT 375414 41D E 0.258 0.181 0.092 <65 UT 375502 50B E 0.258 0.181 0.064 <65 UT 50C P 0 258

'75503 0.181 0.143 <65 UT 375504 50D E 0.258 0.181 0.122 <65 UT 13

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTIII Com onent Result Details(CONTINUED)

M-103 F.W. HTR. DRAIN SYS. FROM H.D PUMPS TO H.T. TANK Summary Comp. Comp. Nominal Nominal Minimum Minimum Percent NDE m r ID T W111 W112 All w 1 R in min I eh 325010 01 P 0.216 0.072 0.204 >88 UT 325020 02 E 0.216 0.072 0.201 >88 UT 325030 03 P 0.216 0.072 0.202 >88. UT

, 325310 31 R 0.300 0.432 0.210,0.302 0.311,0.401 >88 UT 325305 30A P 0.300 0.210 0.294 >88 UT Additional Ins ections:

In addition to the Erosion/Corrosion program, Service Water components were selected to be surveyed from the following drawings; Related S stem C-381-025 Sh 1 SW Suction Line Loop A to Aux. Feedwater C-381-094 Sh 1 AHU-1B Cooling Coils From 4" SW to 20" Return C-381-358 Sh1 SW From CCHX to Anchor at Wall Col. Q C-381-024 Sh3 SW Suction Line Loop B AFW Pump Aux. Bldg & SBAFP Bldg.

C-381-358 Sh3 SW Return From CCWHX to Wall Col. Q C-381-025 Sh4 SW Suction Loop A to AFW Pump Aux Bldg. & SBAFP Bldg.

C-381-358 Sh4 SW From Supply Header to Distribution Manifold C-381-358 Shs SW Return From SFPHX C-381-358 Sh9 SW IB Above El. 253'6" From Pen. 308, 315, & 323 to Col. 7 C-381-358 Sh13 SW IB Above El. 253'6" From 16" Header to Pen. 312, 316, &, 320 C'-381-358 Sh14 SW IB Above El. 253'6" 16" & 20" Header C-381-358 Sh16 SW IB From 14" Header to Pen. 201 & 209 C-381-358 Sh 1 7 SW From 20" Header to MDAFW Pumps lA &. 1B C-381-358 Sh22 SW Form Cont. Recirc. Unit 1-C to Pen. 315 C-381-358 Sh27 SW to Cont. Recirc Cooling Unit 1C & 1D Motors C-381-358 Sh34 "A" & "B" SW pumps in Screenhouse

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTIII Additional lns ections: (Continued)

~Dw ¹ Related S stem C-381-358 Sh35 "C" k "D" SW Pumps in Screenhouse C-381-358 Sh37 SW D/G Bldg. "Room A" C-381-358 Sh38 SW D/G Bldg. "Room A 2 B C-381-358 Sh39 SW D/G Bldg. "Room B" D-304-695 Service Water (Auxiliary Building)

D-304-696 Service Water (Auxiliary Building) 33013-2027 Service Water Supply k Return to SFPHX 82 Service Water Result Details The following list provides examination'result details on service water components by drawing number and system description. The component ID was provided by engineering support. The "Component Type" classification specified in the list below corresponds to the following:

P=Pipe E=Elbow R=Reducer/Expander C-381-025 Sh1 SW Suction Line Loop A to Aux. Feedwater Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Wall Allowable Readin Nominal Method SW251-01 P 0.237 0.095 0.232 >88 RT C-381-094 Sh1 AHU-1B Cooling Coils From 4" SW to 20" Return Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Wall Allowable Readin Nominal Method SW941-01 P 0.145 0.064 0.151 >88 RT

~

l,

R E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTIII Service Water Result Details CONTINUED C-381-358 Sh1 SW From CCHX to Anchor at Wall Col. Q Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Wall Allowable Readin Nominal Method SW01-01 P 0.375 0.150 0.316 84 UT C-381-024 Sh3 SW Suction Line Loop B AFW Pump Aux. Bldg & SBAFP Bldg.

Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Wall Allowable Readin Nominal Method SW 243-01 P 0.237 0.095 0.231 >88 UT C-381-358 Sh3 SW Return From CCWHX to Wall Col. Q Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Wall Allowable Readin Nominal Method SW03-01 P 0.375 0.150 0.353 >88 UT SW03-02 P 0.375 0.150 0.328 87 UT C-381-025 Sh4 SW Suction Loop A to AFW Pump Aux Bldg. & SBAFP Bldg.

Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Wall Allowable Readin Nominal Method SW254-01 P 0.237 0.116 0.191 81 RT 16

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTIII Service Water Result Details CONTINUED C-381-358 Sh4 SW From Supply Header to Distribution Manifold Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e ~

Wall Allowable Readin Nominal Method SW04-01 P 0.216 0.086 0.149 70 RT SW04-02 P 0.216 0.086 0.204 >88 RT C-381-358 Shs SW Return From SFPHX Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Waii Allowable Readin Nominal Method SW05-01 P 0.280 0.242 0.202 72 RT C-3S1-358 Sh9 SW IB Above El. 253'6" From Pen. 308,315, & 323 to Col. 7 Comp. Comp. Nominal Minimum. Minimum Percent NDE ID T e Wail Allowable Readin Nominal Method SW09-01 . P 0.322 0.129 0.302 >88 UT SW09-02 P 0. 1'33 0.053 0.085 75 RT SW09-03 E 0.375 0.150 0.392 >88 UT C-381-358 Sh13 SW IB Above El. 253'6" From 16" Header to Pen. 312, 316, & 320 Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Wall Allowable Readin Nominal Method SW13-01 P 0.375 0.150 0.347 >88 UT SW13-02 P 0.280 0.112 0.270 >88 UT

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTIII Service Water Result Details CONTINUED C-381-358 Sh14 SW IB Above El. 253'6" 16" & 20" Header Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Wall Allowable Readin 'ominal Method SW14-01 E 0.237 0.096 0.190 80 RT C-381-358 Sh16 SW IB From 14" Header to Pen. 201 & 209 Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Wail Allowable Readin Nominal Method SW16-01 P 0.203 0.143 0.130 (65 RT C-381-358 Sh17 SW From 20" Header to MDAFW Pumps 1A & 1B Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Wail Allowable Readin Nominal Method SW17-01 E 0.237 0.130 0.206 87 RT SW17-02 P 0.237 0.133 0.177 75 RT C-381-358 Sh22 SW Form Cont. Recirc. Unit 1-C to Pen. 315 Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Waii Allowable Readin . Nominal Method SW22-01 P 0.237 0.095 0.184 78 RT

R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTm Service Water Result Details CONTINUED C-381-358 Sh27 SW to Cont. Recirc Cooling Unit 1C 4 1D Motors Comp. Comp. Nominal Minimum Percent NDE Minimum'llowable ID T e Wall Readin Nominal Method SW27-01 P 0.203 0.081 0.196 UT C-381-358 Sh34 "A" 4 "B" SW pumps in Screnhouse Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Wall Allowable Readin Nominal Method SW34-01 P 0.322 0.159 0.348 >88 UT SW34-02 P 0.375 0.185 0.358 >88 UT C-381-358 Sh35 "C" 4 "D" SW Pumps in Screenhouse Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Wall Allowable Readin Nominal Method SW35-01 P 0.237 0.117 0.383 >88 RT SW35-02 P 0.375 0.185 0.287 76 UT SW35-03 P 0.133 0.066 0.284 >88 UT C-381-358 Sh37 SW D/G Bldg. "Room A" Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Wall Allowable Readin Nominal Method SW37-01 P 0.237 0.095 0.148 (65 UT 19

i R. E. GINNA NUCLEAR POWER PLANT Inservice Inspection Report 1990-1999 Interval, Second Period, Fourth Outage (1996)

ATTACHMENTm Service Water Result Details CONTINUED C-381-358 Sh38 SW D/G Bldg. "Room A & B Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Watt Allowable Readin Nominal Method SW38-01 R 0.237 0.126 0.258 >88 RT C-381-358 Sh39 SW D/G Bldg. "Room B" Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Walt Allowable Readin Nominal Method SW39-01 P 0.237 0.101 0.229 >88 RT D-304-695 Service Water (Auxiliary Building)

Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Wait Allowable Readin Nominal Method SWXX-01 P 0.113 0.079 0.080 71 RT, D-304-696 Service Water (Auxiliary Building)

Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Waii Allowable Readin Nominal Method WXX-02 P 0.065 0.046 ~ 0.026 40 RT 33013-2027 Service Water Supply & Return to SFPHX ¹2 Comp. Comp. Nominal Minimum Minimum Percent NDE ID T e Wall Allowable Readin Nominal Method SWXX-03 P 0.365 0.146 0.338 >88 UT 20

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