ML20212D898
| ML20212D898 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/14/1999 |
| From: | Abbott R NIAGARA MOHAWK POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17059C778 | List: |
| References | |
| GL-88-01, NMP1L-1467, NUDOCS 9909240108 | |
| Download: ML20212D898 (2) | |
Text
o NiagprahMohawk' nichard s. Abbon September 14,1999 Phone: 315.3491812 vice President NMPIL 1467 rex: 315.349.4417
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NuclearEngineering U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 RE:
Nine Mile Point Unit 1 Docket No. 50-220 DPR-63
Subject:
Submittal of1999 Inservice Inspection Summary Report and Flaw Indication Evaluations Gentlemen:
In accordance with the requirements of the ASME Boiler and Pressure Vessel Code,Section XI (1983 edition with Summer 1983 Addenda), Niagara Mohawk Power Corporation (NMPC) conducted nondestmetive examinations of selected components of Nine Mile Point Unit 1 (NMPI) during refueling outage number 15 (RFO15), which ended on June 16,1999. Enclosure I provides the inservice inspection (ISI) summary report for RFO15, as required by subsection IWA-6230 of Section XI of the ASME Code. With the five exceptions noted in the summary report, this repon constitutes a close-out of the ASME Code required examinations for the second ten-year ISI interval, which ends on December 25,1999.
During RFO15, NMPC also performed augmented examinations on the reactor pressure vessel (RPV) shell welds, as required on a one time basis by 10 CFR 50.55a(g)(6)(ii)(A)(2). These examinations identified flaw indications in two RPV shcll welds. Enclosure 2 summarizes NMPC's evaluation of the flaw indications c-concludes that the flawed welds are acceptable for continued service for twenty eight (28) effective full power years (EFPY). Enclosure 2 contains other supporting information (see Attachments 2A and 2B) and is being submitted for NRC review and approval.
Finally, during RF015, NMPC performed ultrasonic inspections on reactor recirculation system welds in accordance with Generic Letter 88-01 and ASME Code Section XI (1983 edition with Summer 1983 Addenda). These inspections identified four welds with rejectable indications, based on the ASME Code Section XI acceptance criteria. However, the indication sizes are less than those determined to be acceptable by calculation. Therefore, the indications are considered I
acceptable for continued service through the present plant operating cycle. Enclosure 3 provides
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NMPC's evaluation of the flaw indications and the supponing calculation (see Attachment 3 A). is also being submitted for NRC review and approval.
Very tmly yc,urs, b
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PDR Richard B. Abbott Vice President Nuclear Engineering RBA/IAA/ kap Enclosures N n. Ma. Point Nuci r st. tion eo. Box s3. Lycoming. Wew York 13093-0063
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Mr. H. J. Miller, NRC Regional Administrator, Region I Mr. S, S. Bajwa, Section Chief PD-I, Section 1, NRR Mr. G. K. Hunegs, NRC Senior Resident Inspector I
Mr. D. S. Hood, Senior Project Manager, NRR Records Management j
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