ML20078G932
| ML20078G932 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 01/30/1995 |
| From: | Schwartz G COMMONWEALTH EDISON CO. |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML17332B027 | List: |
| References | |
| BYRON-95-043, BYRON-95-43, NUDOCS 9502030343 | |
| Download: ML20078G932 (2) | |
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January 30, 199" LTR BYRON-95-0043 FILE:
3.11.0320 Mr. John B. MaTtin Regional Administrator U.S. Nuclear Regulatory Commission (Region III) 801 Warrenville Road i
'f Lisle, Illinois 60L '2-4351
Subject:
Byron Station Unit 1 Steam Generator Interim Plugging Criteria 90 Day Report NPF-37; NRC Docket No. 50-454
-1 Referencea:
1.
October 24,-1994, Letter from George F. Dick (NRR) to D.
L.
Farrar (Corm.:d) Issuing Amendment No. 66 to Facility Operating Licenses NPF-37 and 66, Docket Nos. STN 50-454 and STN 50-455.
2.
Draft Generic Letter, " Voltage-Based Repair Criteria For The Repair Of Westinghouse Steam Generator Tubes Affected By Outside Diameter Stress Corrosion Cracking," issued for public comment on August 12, 1994.
J, 3.
October 17, 1994, letter from D. M. Saccomando to Office of Nuclear Reactor'Regulaticn, U.S. Nuclear Regulatory Commission, transmitting additional information regarding Byron Station IPC submittals and supplements.
4.
September 30, 1!s94, letter from D. M. Saccomando to W. T.
Russell, transmitting additional information regarding Byron Station IPC nubmittals and supplements.
In Reference 1, NRC approved a license amendment for Byron Station to implement a voltage-based Interim Plugging Criteria (IPC) for Unit 1, Cycle 7.
g As part of IPC implementation, Technical Specification 4.4.5.5.d.2 requires:
"The final results of the inapection and tube integrity evaluation shall be
. reported to the <taff pursuant to Specification 6.9.2 within 90 days following restart."
Pursuant to thin requiremenc, Comed is submitting the enclosed report of results from the Byron Unit 1 End-of-Cycle (EOC) 6 steam generr. tor inspection.
Startup from refueling outage 6 - (B1R06) was conducted on November 2.
1994.
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Byron Ltr: 95-0043 January 30, 1995 Page 2 1
Attachment A to this letter contains the 90 day report for Byron Unit 1.
The following information is included in the report, as required by the SER of Reference 1 and the draf t Generic Letter (Reference 2) :
1.
The metallurgical results of the examinations performed on tubes pulled during B1R06.
2.
The inspection results in tabular and graphical form for each of the j
following:
a.
EOC voltage distribution of all indications regardless of I
motorized rotating pancake coil (MRPC) confirmation, b.
Beginning-of-Cycle (BOC) to EOC cycle growth rate distribution, c.
Voltage distribution for EOC repaired !Tdications (from population in item a that were repaired by plugging).
d.
Voltage distribution for BOC left in service - regardless of MRPC
- results, e.
Voltage distribution for BOC left in service - confirmed by MRPC or not MRPC inspected.
f.
NDE uncertainly distribution for predicting next EOC voltage distribution.
3.
The results of the tube integrity evaluation, including the conditional burst probability and main steam line break leak rate (preliminary results were provided in Reference 3 prior to resumption of power operations from B1R06).
In References 3 and 4, Comed was required to provide a detailed description of the methods used to evaluate the IPC inspection data.
Attachment B contains WCAP-14277, Class 3, "SLB Leak Rate and Tube Burst Probability Analysis Methods for ODSCC at TSP Intersections," which satisfies this commitment.
This WCAP is non-proprietary.
Please address any comments or questions regarding this matter to Mr. Jay Smith at (815)234-5441, extension 2604.
Sincerely,
/
G.K.
chwartz Station Manager Byron Nuclear Po r ant Attachments l
cc:
Document Control Desk - NRR G. Dick, Byron Project Manager - NRR H.
Peterson, Senior Resident Inspector - Byron Office of Nuclear Facility Safety - IDNS (9215ZZ/012795)