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Category:PRESERVICE & INSERVICE INSPECTION & TEST REPTS
MONTHYEARML20210J3851999-07-28028 July 1999 Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval ML20198P0951997-12-22022 December 1997 ISI Summary Rept,Results for Outage 6 (1997) Third Period, First Interval for Pnpp ML20115D6961996-06-20020 June 1996 ISI Summary Rept for Pnpp ML20078B7981994-10-0505 October 1994 ISI Summary Rept NP0059-0004 ML20070S1521991-03-26026 March 1991 Inservice Insp Summary Rept NP0059-0002,Results for Outage 2(1990),First Period,First Interval PY-CEI-NRR-1264, Summary Technical Rept,Evaluation of Indications in Perry Feedwater to Safe-End Welds1990-11-21021 November 1990 Summary Technical Rept,Evaluation of Indications in Perry Feedwater to Safe-End Welds ML20058D8261990-10-0202 October 1990 Temporary Change 1 to, Inservice Exam Program 1999-07-28
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico PY-CEI-NRR-2437, Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With PY-CEI-NRR-2429, Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With PY-CEI-NRR-2424, Monthly Operating Rept for July 1999 for Perry Npp.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Perry Npp.With ML20210J3851999-07-28028 July 1999 Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval PY-CEI-NRR-2416, Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 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Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2313, Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2306, Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 1 ML20249A1891998-06-11011 June 1998 SER on Moderate Energy Line Pipe Break Criteria for Perry Nuclear Power Plant,Unit 1 & Requests Addl Info to Demonstrate That Plant & FSAR in Compliance W/Staff Position & GDC as Discussed in SER PY-CEI-NRR-2289, Monthly Operating Rept for May 1998 for Perry,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Perry,Unit 1 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted PY-CEI-NRR-2282, Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D2051998-04-20020 April 1998 SER Authorizing Licensee to Use Code Case N-524 Until Such Time as Code Case Included in Future Rev of RG 1.147 PY-CEI-NRR-2277, Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20216G3901998-03-11011 March 1998 SER on Proposed Merger Between Duquesne Light Co & Allegheny Power Sys,Inc ML20216J1401998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2258, Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 11998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 1 1999-09-30
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- PY-CEI/NRR-1264 L Attachment 2 u
SUMMARY
TECHNICAL REPORT EVALUATION OF THE INDICATION (S)
IN THE PERRY FEEDWATER TO SAFE-END WELDS November 21, 1990 Cleveland Electric Illuminating Company l
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,i s 0017040060 901126 PDR ADOCK 05000440 0 PDC
4 PY-CEI/NRR-1264 L g Attachment 2 As part of Perry's Inserw ;e Inspection (ISI) Program, all six reed-water (rW) nozzle to sa: and welds were ultrasonically examined (UT) during the second refuel outage (RFO-2). Flaws were detected in nozzles N4E and N4C that were outside of the acceptance criteria of IWB 3514.3 of ASME XI (reference Nonconformance Reports 490-S-270 and 90-S-277 dated November 9, 1990 and November 13, 1990, respectively).
Both flaws were 0.15" deep, with the flaw in nozzle N4C being 2.9" long, versus 1.6" long for nozzle N4E. Since both flaws are the same depth, and very nearly the same location (although one was oriented at 6:00 0' Clock and the other 012:00 o' clock - see Figure
- 1), justification for the larger flaw will serve as *.e :hnical justification for both.
The UT indications were not identifiable as characterit. tic of IGSCC.
L However, the current limited size of the irdications maf de such
! that IGSCC charactettstics would not be sufficiently pronounced 3 be apparent. Consequently, CEI has taken a conservative appecach and included an appropriate IGSCC contribution in conjunction with cyclic fatigue growth when determining the " final" flaw size. The
'inal flaw size is fully acceptable within the criteria of ASME XI, Tables IWB 3641-5 and 3641-6 for the full duration af operating cycle 3 for Perry (nominal 18 month cycle).
l The subject nozzles will be UT re-inspected during 'efueling Outage 43 (RF1-3) and further engineering evaluation will be performed at that time. The current conservative projected results, however, l
indicate that some additional action (i.e., other than a "use-as-is" l condition) would be required beyond RFO-3. '
l
PY-CEI/Niut-1264 L Attachant 2 STRESS HISTORY The stress hissory for this location was taken from CBIN Stress Report #4,(L4, T4, S4 and F4), as analyzed for the modified sparger configuration. (GE had changed the sparger attachment from being welded to a " freeze fit" configuration to remove a " cyclic" fatigue weld problem in the attachment weld). A residual stress .as added to the stress profile. The value of residual stress added was a function of percentage of crack depth (a/t). The equation used was i taken from NUROG-0313/ Revision 2 with a suggested value for Sy of 30 kai, which closely approximates the value for Inconel 182 of 28.4 ksi at temperature.
9 P
PY-CEI/NRR-1264 L Attacha nt 2 CRACK GROWTH The initial crack of 0.15" deep X 2.9" long was projected to grow for 1148 operating cycles, assuming worst case cycle combination to determine " Delta" K 7 From Figure C-3210-1 of ASME XI, the projected cyclic fatigue growth increased the flaw depth to only 0.16". The growth attributed to the '.GSCC contribution for the 12000 operational hours during operating cycle 3 is 0.29 This is based on a crack gravth rate of 2.41 x 10-5 in/hr, which came from EPRI NP-5882M, Project 1566-1 " Stress Corrosion Cracking Resistance of Alloy 600 and 690 and Compatible Weld Metals in BWRs". (In conversations with personnel at River Bend, this value is comparable to what was used in their evaluation).
The reported crack g;owth rate is associated with a K y value of 46.0 MPafm (41.9 ksifIn). This compares favorably with the actual K y expected for normal operating conditions (26.9 ksifIn). Since the crack growth rate is a function of K g, the actual rate would be expected to be less than the value used, and the calculated growth is conservative. Concurrent with the crack growth to a depth of 0.45" is the circumferential growth to 9". This growth was based on the 20:1 (maximum) aspect ratio (or circumferential growth) as specified in NUREG-0313/ Revision 2. See Figure 2 for the projected crack growth for operating cycle 3. TP: contribution of emergency or faulted conditions on the crack growth produced a negligible effect (on the final projected crack depth).
1 l
PY-CEI/NRR-1264 L Attachment 2 ACCEPTANCE CRITERIA Although the flaw location is at or close to the Inconel 182 butter-ing and the SA-508 Class 1 interface, it was assumed (as dictated by ASME XI) that the crack growth would occur in the buttering. The buttering was applied by using SMAW procedures; consequently rables IWB 3( '-5 and 3641-6 are the basis of the acceptance criteria.
Figure 2 shows the acceptance envelopes based on a stress ratio of 0.81. This value considers the Primary Membrane and Primary Bending contribution to be 13.0 kai as determined by CBIN in Repott D4, and an expansion stress (Pe) value of 16.0 ksi for RFE stress, based upon GE specified design thermal loads for the reedwater nozzle.
The acceptance criteria determines en allowable crack depth v.lue of 0.65", versus the projected (calculateci growth to 0.45". This difference of 0.20" supplies almost a 50% margin at the end of the next operational cycle for Perry.
l 1
l l
._._-._s s- 4 p
-d PY-CEI/NRR-1264 L Attachment 2 CONCLUSIONS l 1. The subject indications have been evaluated and shown to be l
acceptable as-is for continued full service operation during Perry's next operating cycle (Cycle #3).
l'
[ 2. Subsequent to UT inspection of the subject welds during RPO-3, an engineering evaluation will be performed to determine additional corrective actions (if any).
- 3. The subject nozzle welds will be treated as Category "r" weld-
! ments per Generic Letter 88-01/ Revision 0, Table 1 until such time as.further inspection / evaluation justifies otherwise.
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PY-CEI/NRR-1264 L Attachment 2 I
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A = 2.9" N0ZZLE N40 A = 1.6" N0ZZLE N4E SECTION "A-A" a = 0.15" 8OTH N0ZZLES
, A
, A J >
N0ZZLE
. SAFE END i a 3 4 FORGING SA-508 CL.i 1.20, SA-508 CL.2 o
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a = 0.15"
.A N0ZZLE:N4C AND FIGURE 1 N4E INDICATIONS' i
- 1. SAFE END 8 UTTERING
- INCONEL 182
- 2. FIELO WELD IN82 ROOT-PASS WITH INCONEL 82 HOT PASSESM AND INCONEL id2 FILL ,
PASSES
- 3. PORTION OF ORIGINAL FIELO WELD
- SAME AS #2 ABOVE
- 4. N0ZZLE BUTTERING
- INCONEL 182
- 5. ORIGINAL SAFE ENO INCONEL 600
- IN82 ANO IllCONEL 82 HAVE IDENTICAL 1 CHEMICAL COMPOSITION REQUIREMENTT AS SPECIFIED BY ASME SECTION II PART C SFA 5.30 +G SFA 5.14.RESPECTIVELY.
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PY-CEf/NRR-1364 L Attachment 2 90 - NORMAL AND UPSET "
LIMIT (SR=0 . 81)
(/) - . _ _ _ _ . EMERGENCY AND FAULTED (f) 80 - LIMIT (S A= 1. 46)
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L PERCENT-CIRCUMFERENCE O
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