ML20080A906
| ML20080A906 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 11/18/1994 |
| From: | Saccomando D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9411220399 | |
| Download: ML20080A906 (5) | |
Text
C:mmsnwealth Edison
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O 1400 Opus Place C
Downers Grove. Ilknots 60515
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November 18,1994 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn:
Document Control Desk
Subject:
Supplement to Byron Unit 2 Residual Heat Removal (RHR)
Heat Exchanger Inservice Inspection Results NRC Docket No. 50-455
References:
1)
Teleconference between Commonwealth Edison Company and the Nuclear Regulatory Comrnission dated November 10,1994, regarding Byron Unit 2 RHR Heat Exchanger Inservice Inspection Results 2)
D. Chrzanowski letter to T. Murley dated May 27,1992, transmitting Byron Unit 2 RHR Heat Exchanger Inservice Inspection Results Per the reference teleconforence, Commonwealth Edison Company (Comed) committed to provide the Nuclear Regulatory Commission (NRC) with updated information regarding the inspections results from the Byron Unit 2 Residual Heat Removal (RHR) Heat Exchanger Inservice Inspection. Byron has recalculated the results from the 1992 inspections (Reference 2) and is providing them in Attachment 1.
The original volumetric inspection data for a baseline on the nozzle indications was transmitted in Reference 2. The data in the report identified the indications in the pipe wall and those in the fillet material. In the original report, the calculations used the fillet reinforcement in the shear plane above the defect location. The updated calculations consider an effective fillet throat distance at the location of the indication as was done at Braidwood Station.
Byron has scheduled a volumetric examination to be conducted on the Unit 2 RHR Heat Exchanger nozzle to vessel welds in the upcoming refueling outage scheduled to begin in February,1995. This re-examination is being performed in accordance with IWC-2420(b) and wi!! be conducted during the next inspection period. The February outage for Unit 2 (B2R05) is the first outage for the third inspection period. The results of this examination will be submitted to the NRC.
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i Comed would be happy to address questions on this topic. Please address any questions concerning this correspondence to this office.
Sincerely, r
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Denise M. Saccomando Nuclear Licensing Administrator Attachment cc:
G. Dick, Byron Project Manager, NRR H. Peterson, Senior Resident inspector, Byron Station J. Martin, Regional Administrator, Rlli Office of Nuclear Safety, IDNS 4
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ATTACHMENT 1
BYRON UNIT 2
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ATTACHMENT 1 B'/RON UNIT 2 HEAT EXCHANGER NOZZLE WELD UT DATA flow EFFECTIVE N OZZLE length FILLET a/t a/t IND (1)
THICKNESS in THROAT W/O WITH LOCATION LENGTH o(2a)"
c/l t
fillet tc FILLET FILLET 2B RHR HEAT EXCHANGER INLET NOZZLE 11.12.13 10" to 13" 3.0"
(.144) 0.023
.4" n/a n/a 17.75%
n/a 30 35" to 36" 1.0"
(.094) 0.047
.4" n/c n/a 11.75%
n/a 31 36" to 37"
.5"
(.109) 0.0545
.4" n/a n/a 13.62%
n/a 32 37" to 38" 1.0"
(.125) 0.0625
.4" n/a n/a 15.62%
n/a 2B RHR HEAT EXCHANGER OUTLET NOZZLE 2
1" to 2"
.5"
(.078) 0.078
.4" n/a n/a 9.75%
n/a 3
2" to 3"
.5"
(.078) 0.078
.4" n/a n/a 9.75%
n/a 4
3" to 4"
.5"
(.140) 0.140
.4" n/a n/a 14.00%
n/a 6
5" to 6"
.5"
(.140) 0.140
.4" n/a n/a 17.50%
n/a 7
6" to 7"
.75"
(.062) 0.041
.4" n/a n/a 7.75%
n/a 10 9" to 10"
.5"
(.093) 0.093
.4" n/a n/a 11.63%
n/a 11 10" to 11"
.5"
(.078) 0.078
.4" n/a n/a 9.75%
n/a 16 16" to 17" 1.0"
(.062) 0.031
.4" n/a n/a 7.75%
n/a 25 to 28 25" to 30" 5.0" 0.341 0.0682
.4" 0.115"
.210" 56.5%(2) 55.9%(3) 29 31" to 32" l.0"
(.093) 0.0465
.4" n/o n/c 11.63%
n/o 30 32" to 33"
.5"
(.093) 0.093
.4" n/a n/a 11.63%
n/a 31 to 33 33" to 36" 3.0"
(.093) 0.0465
.4" n/a n/a 11 63%
n/a 35 37" to 38" 1.0"
(.062) 0.031
.4" n/a n/a 7.75%
n/a 36 38" to 39"
.75"
(.078) 0.052
.4" n/a n/a 9.75%
n/a 40 42" to 43" 1.0" 0.156 0.156
.4" n/a n/a 39.00%
n/a
" denotes ASME Section XI(Article IWA-3000) characterization (i.e. a= surface 2a= subsurface)
(1) the indication numbers reflect those on the original submitto of the Byron Unit 2 data-these numbers are those indications which are in excess of 100% DAC.
(2) the o/t value is based upon the flow in the base metal (.226" surface flow) without consideration for the flow in the fillet (3) the a/t value is based on the flow in the fillet and the nozzle with the fillet reinforcement.
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