ML19253C109
| ML19253C109 | |
| Person / Time | |
|---|---|
| Site: | Millstone |
| Issue date: | 11/05/1979 |
| From: | Counsil W NORTHEAST UTILITIES |
| To: | Harold Denton, Reid R Office of Nuclear Reactor Regulation |
| References | |
| TAC-11793, NUDOCS 7911280427 | |
| Download: ML19253C109 (12) | |
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9 03) 666-6911 L L J . ',. a :.':::' November 5, 1979 Docket No. 50-336 Director of Nuclear Reactor Regulation Attn: Mr. R. Reid, Chief Operating Reactors Branch #4 U. S. Nuc2 car Regulatory Commission Washington, D. C. 20555
References:
(1) R. Reid letter to W. G. Counsil dated August 25, 1979. (2) W. G. Counsil letter to R. Reid dated September 28, 1979. (3) W. G. Counsil letter to R. Reid dated August 22, 1979. (4) W. G. Counsil letter to R. Reid dated October 22, 1979. (5) W. G. Counsil letter to R. Reid dated October 24, 1979. Gentlemen: Millstone Nuclear Power Station, Unit No. 2 Feedwater System Piping In Reference (1), the NRC issued a Safety Evaluation documenting the acceptability of continued operation of Millstone Unit No. 2 until October 31, 1979, with feedwater piping crack indications. In Reference (2), Northeast Nuclear Energy Company (NNECO) submitted a detailed weld repair program with the intention of affecting the repair during the 1980 refueling outage. Plant operation after October 31, 1979 is contingent upon the issuance of a Safety Evaluation by the Staff af ter reexamination of the crack indications identified during examinations of the feedwater system piping required by I&E Bulletin No. 79-13. Reference (2) documented NNECO's acceptance criterion for the results of the re-examination of the feedwater crack indications. This acceptance criterion is that no confirmed crack growth in the through-thickness direction (depth) is permissible. This criterion has been fulfilled in response to Item (5) of Refere..cs (1) as described below. Thz ofe-end to pipe welds AC-G-1 and BC-G-1 have been reinspected using both radiographic and ultrasonic examination techniques. The ultrasonic examination was performed using the same methods, techniques, and conditions as was used to previously characterize the indications. The RT results for two selected circumferential areas of Weld AC-G-1, comparing the data from tne August,1979 inspection to the data from the November,1979 inspection, are provided in Figures 1 and 2. Similar data for three selected circumferential areas of Weld BC-G-1 are presented in Figures 3, 4, and 5. Based upon a comparison of the RT data of the two inspections, NNECO has con-3 &o .1 2011280 ? 14 G 341
. cluded that no measurable change in the size of the indications on either side of the safe-end to pipe welds has occurred. Subsequent to completion of the RT inspection, selected linear indications were ultrasonically examined. These UT results are presented in Figures 6 and 7. Based upon a comparison of the UT data from the August, 1979 and November, 1979 'xaminaticns, NNECG has conclitded that no measurable change in the length of the originally mapped reflectors has occurred. Furthermore, comparison of the amplitude profiles confirms that no measurable increase in indication depth has occurred. However, in the nine o' clock position of the number two reflector on t ae safe-end side of Weld BC-G-1, the amplitude has decreased as a result of a one-inch long parallel indication shadowing the original reflector. Regarding the pipe to elbow welds, AC-G-2 and BC-C-2, the following information is provided: (1) The larger indications at the safe-end to pipe welds, which are located in more critical temperature and stress regions, were determined to not propagate since the August, 1979 inspection. (2) As documented in Reference (3), the pipe to elbow welds were confirmed by UT to be so small is to be non-reportable as per the inspection procedure. Consequently, these smaller. indications were not mapped for the purposes of establishing baseline data. Ultrasonic examination of these welds at this time would, therefore, not be relevant in the absence of baseline data. (3) Ultrasonic examination of the pipe to elbow welds wculd require the dis-mantling of sophisticated, calibrated acoustic leak detection instrumen-tation without sufficient justification. In light of the above considerations, the pipe to elbow welds were not re-examinated using UT techniques during the current outage. Based upon the information presented above and the attached Figures, NNECO has fulfilled the previously established acceptance criterion documented in Reference (2). Confirmation that no growth has occurred during the interval between examinations lends additional credence and emphatically supports the applicability of the fracture mechanics analyses and supporting documenta-tion docketed in References (3), (4), and (5). The 1980 refueling outage repair program is, therefore, concluded to be technically defensible and appropriate. An interim ultrasonic examination, prior to March 1,1980, will be conducted to verify the continued absence of crack growth. The leak detection equipment will remain functional and be monitored without change from the current program until the issue is permanently resolved. )kkb b I
. We trust you find the above information sufficient to serve as the basis for a safety evaluation authorizing continued, safe plant operation of Millstone Unit No. 2. Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY E f41 W. G. Counsil Vice President Attachment
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