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{{#Wiki_filter:(I vP 41 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION P-/7 7 7 CONTROLLED COPY NUMBER /~yeah'( | |||
/F-7 | |||
~Q H/W~4 PROCEDURE NOo REV. ZO. ~7 Cg, GP Pc.U '29M ll53 PORC REVIEW DATE Pc.v P''l T'l55 pc. w ir'l T',l 'i 5 7 J= | |||
Pc U. 8'0 l ll 5) | |||
P,c.& R'9~ 1'l 4k PLANT SUPERINTENDENT qcu 'Fj ~ ll 45' EPFECTIVE DATE 9707310iSB'970725 PDR ADQCK 05000244 P PDR NON-QA CATEGORY 1.0 aZVXZWED >Y: | |||
mIS FOR | |||
'TART: | |||
PROCEDORE CONTAINS 8 &T USEONLY~ | |||
~ PAGES G)NNA STATlON pAT2 VlMa ~~', | |||
C{) A) Q+ | |||
. | |||
FE" iED. | |||
~ootoOro rO Qnp v lEOOQZZ ~ gATE yS Treading TlME'- | |||
ae! guet RecooE | |||
N V1 | |||
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PZ-7: 25 | |||
@ +~w- '7-P'T C~ay y-r A VT-2 Visual Examination of the Reactor Coolant zypfzz and items listed herein shall be completed at the pressure indicated. No leakage shall be allowed ~+augh pipe, vessels, or valve bodies Lea3cage through packing, flange gasketing, etc., shall be noted and gmmtified, evaluation by operations or Plant Supervision. If if possible, for test performance is not fox. 10 year hydro, mark N/A in 2352 psig inspection completed column. | |||
INSPECTION 929XZZK 2352 ps'. | |||
RCS Loop A Hot Leg to Steam Ganarator 2 ~ RCS Loop A Hot Leg Safety In]ection Line to V878H 3 ~ RCS Znop A Hat Leg RHR Line to KV 701 4 ~ RCS Inop A Hat Leg Sample Line to V998 5~ RCS Loop B Hot Leg to Steam Generator 6~ -RCS Loop B Hat Leg Safety Infection Line to V878P 7~ RCS Loop B Hot Leg Sample Line to AOV 955 8 ~ RCS Znop B Hot Leg Ctmxging Line to V9315 9~ RCS Loop A Crossaver Pipe | |||
: 10. Loop A Crossover Pipe Instrumentation Lines | |||
~tt RCS | |||
: 11. RCS Loop A Crossaver Pipe Drain to V523 and V541 | |||
: 12. RCS Loop A Crossaver Pipe Excess Letdown Line to HCV 123 1 Inop B Crossover Pipe 3 C tp Lt RCS Loop B Crossover Pipe Drain to V540 RCS Loop=8 Crossaver PiPe Letdown Line to AOV 200A, B, 202 17 RCS XDOP A Cold Leg to Reactor Coolant Pump | |||
'8. | |||
RCS Loop A Cold Leg Safety Xn)ection Line to MV 8408, V842 878B | |||
: 19. RCS Loop A Cold Leg Alternate Charging Line to MV 392B | |||
: 20. RCS Loop B Cold Leg to Reactor Coolant Puxp Cold Leg Safety In)ection Line to MV 839B, V842A 878D | |||
~tl | |||
: 21. RCS Loop B 22 RCS Loop B Cold Leg RHR Line to MV 720 | |||
'3 RCS Loop B Cold Leg Charging Line to V9314 | |||
'4 Pressurizer | |||
'5. | |||
P i* LI | |||
: 26. Pressurizer Surge Line to RCS Zoop B Hot Leg | |||
: 27. Pressurizer Spray Line to RCS Loop A Cold Leg | |||
: 28. Pressurizer Spray Line to RCS Loop B |
Revision as of 17:56, 29 October 2019
ML17264A962 | |
Person / Time | |
---|---|
Site: | Ginna ![]() |
Issue date: | 05/22/1989 |
From: | Marlow T ROCHESTER GAS & ELECTRIC CORP. |
To: | |
Shared Package | |
ML17264A963 | List: |
References | |
PT-7, NUDOCS 9707310158 | |
Download: ML17264A962 (52) | |
Text
(I vP 41 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION P-/7 7 7 CONTROLLED COPY NUMBER /~yeah'(
/F-7
~Q H/W~4 PROCEDURE NOo REV. ZO. ~7 Cg, GP Pc.U '29M ll53 PORC REVIEW DATE Pc.v Pl T'l55 pc. w ir'l T',l 'i 5 7 J=
Pc U. 8'0 l ll 5)
P,c.& R'9~ 1'l 4k PLANT SUPERINTENDENT qcu 'Fj ~ ll 45' EPFECTIVE DATE 9707310iSB'970725 PDR ADQCK 05000244 P PDR NON-QA CATEGORY 1.0 aZVXZWED >Y:
mIS FOR
'TART:
PROCEDORE CONTAINS 8 &T USEONLY~
~ PAGES G)NNA STATlON pAT2 VlMa ~~',
C{) A) Q+
.
FE" iED.
~ootoOro rO Qnp v lEOOQZZ ~ gATE yS Treading TlME'-
ae! guet RecooE
N V1
',
PZ-7: 25
@ +~w- '7-P'T C~ay y-r A VT-2 Visual Examination of the Reactor Coolant zypfzz and items listed herein shall be completed at the pressure indicated. No leakage shall be allowed ~+augh pipe, vessels, or valve bodies Lea3cage through packing, flange gasketing, etc., shall be noted and gmmtified, evaluation by operations or Plant Supervision. If if possible, for test performance is not fox. 10 year hydro, mark N/A in 2352 psig inspection completed column.
INSPECTION 929XZZK 2352 ps'.
RCS Loop A Hot Leg to Steam Ganarator 2 ~ RCS Loop A Hot Leg Safety In]ection Line to V878H 3 ~ RCS Znop A Hat Leg RHR Line to KV 701 4 ~ RCS Inop A Hat Leg Sample Line to V998 5~ RCS Loop B Hot Leg to Steam Generator 6~ -RCS Loop B Hat Leg Safety Infection Line to V878P 7~ RCS Loop B Hot Leg Sample Line to AOV 955 8 ~ RCS Znop B Hot Leg Ctmxging Line to V9315 9~ RCS Loop A Crossaver Pipe
- 10. Loop A Crossover Pipe Instrumentation Lines
~tt RCS
- 11. RCS Loop A Crossaver Pipe Drain to V523 and V541
- 12. RCS Loop A Crossaver Pipe Excess Letdown Line to HCV 123 1 Inop B Crossover Pipe 3 C tp Lt RCS Loop B Crossover Pipe Drain to V540 RCS Loop=8 Crossaver PiPe Letdown Line to AOV 200A, B, 202 17 RCS XDOP A Cold Leg to Reactor Coolant Pump
'8.
RCS Loop A Cold Leg Safety Xn)ection Line to MV 8408, V842 878B
- 19. RCS Loop A Cold Leg Alternate Charging Line to MV 392B
- 20. RCS Loop B Cold Leg to Reactor Coolant Puxp Cold Leg Safety In)ection Line to MV 839B, V842A 878D
~tl
'3 RCS Loop B Cold Leg Charging Line to V9314
'4 Pressurizer
'5.
P i* LI
- 26. Pressurizer Surge Line to RCS Zoop B Hot Leg
- 27. Pressurizer Spray Line to RCS Loop A Cold Leg
- 28. Pressurizer Spray Line to RCS Loop B Cold Leg
- 29. Pressurizer Mini Spray Line araund PCV 431A
- 30. Pressurizer Hixd. Spray Line around PCV 431B 31.
32 ~
Pressurizer Pressurizer
~liary Spray Line to V9313 Stoaa Space Sample Line to AOV 951 33 ~ Pressurizer Liquid Space Sample Line to MV 953 34 Reactor Vessel to NK 852A
'5, Reactor Vessel to KN 852B
- 36. Reactor Vessel Head Vent Line to SV 590, 591 37 Reactor Vessel Level Instrumentation Line to V599 ctor Vessel Head Closure Seal Lealcoff Connections
0 rr-7:26
. /0> &~
pd. y+'7 X8 A VT-2 Visual Examinatj.on of the Reactor Coolant, and items 1 isted herein, shal 1 be completed at the pressure indicated No S'r pac~,
,
e shall be all~ through pipe, vessels, or valve bodies. Leakage through flange gasketing, etc., shall be noted and quantified, if possible, for urther evaluation by Operations or Plant S~~ision. If not for 10 year hydro, mark N/A in 2352 psig inspection completed column.
test performance is INSPECTION QSHIZe 2352 QSSQ
- 39. Accessible surfaces on the Reactor Vessel Head
- 40. Reactor Vessel Incore Penetrations in Sump A,
- 41. Check all accessible ma)or components for leakage (i.e. Reactor Vessel, Steam Generators, etc.) within the Reactor Coolant System Boonhey, which wer~eot mentioned in preceding steps.
REMARKS:
Inspecteti By: @ Date: 5 P I~
2, Level I Inspector Personnel 'perations Date: o 8 /2 Materials Engineering Supervision S'ate:
Reviewed By: 0 2 8 QC S~~ision
~ 's ~
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Enclosure 3 ISI UT/PT Inspection on Bi-Metalic Wleds 1979 = Penetration 26, 27, 34 1988 = Penetration 16, 32
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ROCHESTER GAS AND EL ~IC GINNA STATION gv w 1979 INSERVICE NONDESTRUC AMINATIONS SUGARY REPORT t Ppl Examination Area Page Examination Procedure Examination Calibration Indications Identification Number Method Number/Revision Sheet Number Sheet Number No Recordable Insignificant Geometric Other Remarks 826-27 & 34 104 UT SWRI 800-57/0 45'-1012 01293 SS Side 45 -1011 01292 45'T-1011 Inc. Side 0010 0005 X 0011 OLS60 0012 Attn PL-FW-XI-PR 105 NDE 100-1 20061 RC-1000-LSW-1-PH 106 VT NDE 100-1 20066 RC-1000k-PR 107 NDE 100-1 20064 AS-1001-23-PR 108 VT NDE 100-1 20067 RC-1000-HSW-1-PR 109 NDE 100-1 20065 PL-FW-XII-PR 110 NDE 100>>1 20060 RC-1001&-PH 111 NDE 100-1 340136 X Pipehanger Half Installed per Drawing QCN $ 14 AS-1001-13-PR 112 NDE 100-1 340168 AS-1001-9-PR-1 113 NDE 100-1 340177 RC-FWW-PH-I 114 NDE 100-1 340147 X Pipehanger not in location shown on Drawing QCNE13 SI-100SKSW-I-PH 115 NDE 100-1 340134 X Pipehanger not built per Drawing QCN815
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.... INSTRUMENT CALIBRATIONRECORD - - Shoot, No. 1293 hlaint.. Proc. No.
Examiner I
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Date:
Q
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Time:
CALI'BRATIOH VERIFICATION 0
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-,St... 98~. I > a
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Nominal Angle Z Q-G hfeasured Angle: (("~ JQQQ Og))~ QrCJ /Jg AQ.
hleasured Angle Signal Anplitude:,'D Sl Oi htanufacturer I Se rial Numbor I (Screen Divisions)
'i Signal Distance (in): n, . v e5 t/e Screen Divisions O I d. bJd Coarse llangel Sleet db coarse:
Nominal db fine:
Ai e uency(htlIZ)
IHSTRUHENT S ETT IHGS Remarks:
100 Itejectl . AJ W/ X,r/ag g Q>Wg'AC ~a 80 ee Dcc: c/// c>
Fine db: 60 Coarse db: 40 Freqttencyl 20 Dolay I hlat'-I Cal: 7 Ctt g. 0 2 3 4 5 6 / 8 9 10 Itange Bep
'amping:
llatel g/
'screen Long division =
Shear ~4 in. of metal I" 'I.'-4 7X '
Video: Qii,'ct g w ' e r - ~
li l I t,er: Basic Cal. Block Nol (' .'
'ex
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I cflgt,h I, Type:
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ROCHESTER G&. AND ELECTRIC A JVD ULTRASONIC PIPE WELD EXAMINATIONRECORD Sheet No. 1013 Job No; Location. ~
C<<.tI*'~ 4 rA Date:
7-5=0 I Time (24 hr el~a System: Indentification.
(ov,Trz.'cw:,I(::) QPiiu-" Iq~ g,'g(.
II~ 'Tp Thickness (Nominal) Diameter (Nominal) Examiner'. SNT Level Lo 'Location Wo Location
,$ g-C Wel Length: Examiner: SNT Level Angle
/2. c Flow~)
i8'~ iglircg.lioc/5 ~P Used 45" 45 T 60'eld Type: ( Procedure No: Rev.: Calib Sheet No: Scanning dB I~~' V '.MQ/ DC) -5 9 p> f2. Ir p Remarks:
Examination Area Limitations (If none, so state)
I ND. SQX DAC W MAX 50% DAC L L2 DAMPS tIF YES, EXPLAIN) REMARKS:
NO. of 50>> 100% . 50% IN.'I DAC WI Mf W2 MP MP MAX DAC DAC DAO DAC L/ II Ac d/+
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-INSTRUMENT CA BRATION RECORD hfaint. Proc. No. Location: Date: Time: (24 clock) ='CALI BRAT ION VER IF I CAT ION Q'I<tr4 C< Q IA R-.5-") '(.
Examiner I SN T I<evcl Instrument: Time: '
I ) I= Lc- (.7 Bronson 303 Q Sonic hfkl Initial Lxam incr: SNT Levol Serial Nor
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Pj.ocp~d other+~
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Nominal Anglo hfeasured Angled hfeasured Angle ' 'c.c Signal hiplitudd I 41/Ig.
hfanuf'acturer: rial'umber... (Screen DivSsions) nJ ztAE, Signal Distance C-
. -tL)di2 (in) I >>E Screen Divisions 'c, Vvc t..Rek Ho~a~A Pc eS t ~e.
Coarse Range: Bar '<<g.8. v ~'l d-Id Size: <fb coarse:
Nominal db fine:.
Fre uenc (hfllZ)
INSTRUMENT S ETTINGS Remarks I 100 Reject:
80
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Coarse db:
Frequency:
40 a.~ ~ Qc IOI I D 20 Delay:
hfat.'l Cal: 0
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'f> 'frgr Range: n r< ~ )t 'nt I'I I g' ~
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Cr'ys tcmIi Indentification.t s~PPCs(. 4<:(~ ~%.1~i. g. c<<> ~/'<<-"ct<<'Z<<0 ~e:">g '>~(j Thickness (Nominal) Diameter (Nomina I) SNT Level Lo Location Wo Location 5/
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dB Alr3P +c Remarks:
Examination Area Limitations (If none, so state) g'Qi'ND<<
50K DAC W MAX 50% DAC L2 DAMPS 1IF YES, EXPI AINI REMARKS:
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Rochester'Gas 'and ic Corporatiori R AIVD INSTRUMENT CALIBRATION RECORD FOR ATTENUATION/LAMINATIONEXAMINATION Sh.'. N.. 0005 Maint. Proc. Ho. Location:
r'"=rara<'w. i 'A Date: .
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SNT, Level Instrument<
Branson I ]
Serial,No<- .
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Enclosure 4 Ginna Strategic Plan The purpose of the Ginna Strategic plan was to provide crack initiation and growth predictions for Ginna CRDM nozzles and combine the results with a an economic analyses which could. be used as the basis for addressing the CRDM Alloy 600 issue at Ginna Station; The Strategic plan u'ses a combination of Finite element modeling (ANSYS 5.0), Statistical Analysis and a computer program which evaluates alternative strategies to address the CRDM issue, CIRSE (CRDM Nozzle Inspection and Repair Strategic Evaluation).
The finite elements analysis utilizes Ginna specific data supplied by BEW Nuclear Technologies, in 1994. This included Ginna specific list of materials, material certifications, list of welds, welds data-sheets; procedure qualifications, weld wire certifications, applicable fabrication drawings, as-built drawings and contract variations.
The statistical analysis using a Weibull distribution approach is performed using the industry inspection data provided by past inspection experience, including the sample plant inspection which included the same heats of material from the Ginna vessel head. Differences in material susceptibility, stress and temperature are addressed. Note that the analysis conservatively assumes a crack occurs in the sample plant inspected (which contained the same material heat numbers as Ginna) immediately following the inspection.
The CIRSE model utilizes the information developed in the finite element model, the statistical analysis and,others to evaluate the alternative scenarios for responding to the issue of CRDM nozzle cracking. The program input and output are processed using EXCEL. The analysis approach consists of: establishing the input parameters, predicting crack initiation and growth at each planned refueling outage, assessing the total number of nozzles requiring corrective action at each refueling outage, calculating the cost of any planned inspections and remedial measures plus any required repairs at each refueling outage. Present worth of the future costs are also tabulated.
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