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Responds to FOIA request for eight categories of info re steam generators.Forwards documents listed in Apps B & C.App A provides partial list of records available in PDR.
Accession Number: ML13319A640
Date Released: Sunday, November 8, 2020
Package Contents
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- ML20031F147 - Notifies that util discovered 11 row one tube plugs missing after completion of refueling & steam generator insp. Incident potentially problematic due to absence of onsite loose part monitoring sys. (1 page(s), 7/6/1977)
- ML20031F080 - Discusses proposed implementation of facility Tech Specs & associated bases for steam generator tube surveillance.Tech Specs should require prompt rept to NRC if more than three tubes exceed plugging limit.Related info encl. (5 page(s), 9/27/1976)
- ML20031F059 - Provides info re steam generator tube failures at facilities.Five tube leaks have resulted in shutdown for repairs. (2 page(s), 1/21/1976)
- ML20031F130 - Advises that util has shut down unit to repair leak in Steam Generator C.Leak will be repaired & facility operational by 770501. (1 page(s), 4/26/1977)
- ML20031F169 - Info Memo 5 re control of radioactivity in secondary sys of PWRs,precipitated by 770115 unmonitored release of 3 Ci I-131 at facility.Util requested to submit Tech Specs to include turbine bldg sump monitor w/alarm in control room. (3 page(s), 10/7/1977)
- ML20031F102 - Trip rept of 770217 visit to Westinghouse,Tampa Div to discuss steam generator tube leaks at facility.Agenda,list of attendees & schematic of facility layout encl. (1 page(s), 2/22/1977)
- ML20031F153 - Advises that Westinghouse has denied rumored use of lithium hydroxide in secondary coolant at facility.Occurrence of hydrogen in steam phase believed to be given off during formation of magnetite in tube/tube support plate annulus. (2 page(s), 7/26/1977)
- ML20031F128 - Trip rept of 770404 visit to B&W facilities at Mount Vernon, IN re differences in steam generator hardware designs between Oconee & other B&W operating units. (5 page(s), 4/19/1977)
- ML20031F180 - Advises that review & evaluation of util steam generator repair repts should carefully consider accidents inside as well as outside containment. (7 page(s), 10/25/1977)
- ML20031F215 - Forwards outline & assignment for branch input to rept on four steam generator tube rupture incidents. (2 page(s), 10/15/1979)
- ML20031F221 - Forwards notice of proposed issuance of amends to facility OL,approving steam generator replacement program. (2 page(s), 10/21/1977)
- ML20031F196 - Advises that util 790420 analysis of cause of denting at facility is satisfactory.Chemical cleaning recommended. Related info encl. (2 page(s), 5/16/1979)
- ML20031F193 - Responds to request re acquisition of replaced Westinghouse steam generator for research study.Primary candidates include Generator 2B of Surry Unit 2 & Generator 4B of Turkey Point Unit 4. (2 page(s), 3/11/1978)
- ML20031F224 - Notice of proposed issuance of amends to License DPR-32 & DPR-37,authorizing util to replace steam generators & return units to operation. (5 page(s), 10/21/1977)
- ML19273C366 - Responds to 800104 request re generic implications of recent eddy current testing experience.Preliminary conclusion finds multifrequency testing superior to single frequency.Planning trip to Ginna plant to review mockup. (3 page(s), 2/14/1980)
- ML17338A640 - Forwards "Radiological Considerations," & "Radiological Consequences of postulated Accidents." Concludes replacement steam generators have no effect on radiological consequences of postulated accidents. (34 page(s), 3/23/1979)
- ML13319A639 - Forwards 800520 summary of results of IE inquiry into steam generator tube support plate cracking at facility.Special team cannot unequivocally establish that licensee intentionally withheld safety info from NRC. (2 page(s), 6/9/1980)
- ML20031F234 - Responds to request for available info on role of secondary water chemistry at facility re type of corrosive degradation occurring on steam generator tubes.NRC should request info from util re current insp program. (4 page(s), 3/12/1981)
- ML17250A294 - Safety evaluation of licensee Apr 1980 steam generator insp. Plant is safe to return to power operation but proposed midcycle insp program should be made mandatory.Insp program should be submitted for comments 40 days prior to shutdown. (4 page(s), 5/19/1980)
- ML17340A761 - Forwards marked-up revised license conditions permitting return to power operation upon completion of insp & safety analysis & clear delineation of criteria used for insp, plugging & safety analysis.Comments requested by 810223. (10 page(s), 2/10/1981)
- ML20031F242 - Addresses concerns re proposed research study of replaced steam generator.Stress analysis of steam generator package for shipping is being performed.Instrumentation of steam generator during shipment under consideration. (3 page(s), 7/28/1981)
- ML13319A705 - Forwards summary of latest findings & addl actions to be taken by licensee from steam generator insp re development of caustic intergranular attack & circumferential cracking at top of tubesheet.Meeting w/licensee scheduled for 800706. (4 page(s), 6/30/1980)
- ML16138A447 - Operating Reactor Event Memo 80-18.Ultrasonic test technique recommended for use instead of ASME Section 5 for future bolts & studs examinations. (3 page(s), 8/19/1980)
- ML17258A950 - Forwards safety evaluation of facility inservice insp program for 1980-89 interval.Program is acceptable if plugging limit for 10 test sleeves is established & two typographical errors are corrected. (6 page(s), 4/4/1981)
- ML17250A292 - Forwards safety evaluation of licensee Apr 1980 steam generator insp.Licensee concluded that insp results, preventive tube plugging program & leakage rate limit support resumption of plant operation until next insp. (4 page(s), 5/19/1980)
- ML20030A306 - Discusses steam generator leak & concerns of detectability of defects. (3 page(s), 9/30/1980)