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Requests info re splices inside Monticello containment w/o environ qualification documentation (PN-78-91) & industry- wide implications.
Accession Number: ML19289B550
Date Released: Saturday, November 7, 2020
Package Contents
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- ML20086D461 - Requests info re splices inside Monticello containment w/o environ qualification documentation (PN-78-91) & industry- wide implications. (2 page(s), 4/26/1978)
- ML20086D472 - Discusses LER 77-12 re change in GE analysis of facility max critical power ratio.Proposed Tech Spec change approved & issued as Amend 30,raising max critical power ratio limits by increment of 0.08. (1 page(s), 4/4/1978)
- ML20086D476 - Requests review of encl LER 50-263/77-12 re change in max critical power ratio limits.Util preparing application to amend Tech Specs. (1 page(s), 7/19/1977)
- ML20086D481 - Advises that addl conservatism being administratively added to Tech Specs for max critical power ratio limits,in light of GE 770620 ltr. (1 page(s), 6/20/1977)
- ML20086D496 - LER 77-012:on 770620,during investigation of Cycle 5 max critical power ratio limits,GE found that pump trip delay time assumed in original Cycle 5 transient analysis not appropriate.Amend request will be submitted.W/770620 ltr. (2 page(s), 6/27/1977)
- ML20086D499 - Forwards Amend 30 to License DPR-22,safety evaluation & notice of issuance & availability.Amend incorporates increased max critical power ratio requirements.W/o encls. (1 page(s), 9/28/1977)
- ML20086D514 - Telecopy RO:on 780105,discovered that one of two Nuclear Engineering Co Model B3-1 shipping casks provided w/1-inch diameter lid bolts rather than 1-1/4 inch size specified in Certificate of Compliance 6058. (2 page(s), 1/6/1978)
- ML20086D520 - Telecopy RO:heating steam coil leak in reactor bldg ventilation supply unit V-AH-4A resulted in freezing of condensate at inlet to unit & subsequent inoperability of associated secondary containment isolation dampers. (2 page(s), 12/14/1977)
- ML20086D537 - Telecopy RO:insp of internal torus catwalk support structure revealed that catwalk mitered sections not all attached to horizontal catwalk support plates in some manner.Attachment locations will be upgraded. (2 page(s), 10/14/1977)
- ML20086D550 - Telecopy RO:on 771012,local leak rate testing of MSIV AO-2-80A & nitrogen instrument air sys isolation valve CV-7436 indicated that leakage exceeded Tech Spec acceptance criteria.Cause under investigation. (2 page(s), 10/13/1977)
- ML20086D554 - Telecopy RO:on 771004,local leak rate testing of HPCI sys discharge isolation check valve HPCI-9 indicated that leakage exceeded Tech Spec acceptance criteria.Cause under investigation. (1 page(s), 10/5/1977)
- ML20086D557 - Telecopy RO:on 770929,local leak rate testing of core spray inboard isolation check valve AO-14-13A indicated that leakage exceeded Tech Spec acceptance criteria.Cause under investigation. (1 page(s), 9/29/1977)
- ML20086D561 - Telecopy RO:on 770913,local leak rate testing of core spray inboard isolation check valve AO 14-13B indicated that leakage exceeded Tech Spec acceptance criteria.Related event on 770914. (1 page(s), 9/14/1977)
- ML20086D567 - Telecopy RO:main steam drain isolation valve MD 2373 & main steam outboard isolation valve AO 2-86A exceeded Tech Spec acceptance criteria for local leak rate tests. (1 page(s), 9/12/1977)
- ML20086D570 - Responds to 770719 ltr requesting info re shutdowns of facility due to coolant water leaks from valves. (3 page(s), 8/8/1977)
- ML20086D575 - LER 77-020/03L:on 770404,RCS leakage determined to be greater than 10 gpm.Caused by packing leakage past stems on RTD bypass throttle valves 13RC20 & 14RC20.Valves placed on backseat & stem leakage decreased. (3 page(s), 4/5/1977)
- ML20086D579 - LER 77-038/03L:on 770519,RCS leakage determined to be greater than 10 gpm from stem leakoff on manual isolation valves 1PS24 & 1PS28 for pressurizer spray valves.Caused by packing leakage.Valves will be repacked at next outage. (1 page(s), 5/23/1977)
- ML20086D606 - Requests info re 770710 shutdown due to leaky valves & nature of radioactive matls pumped into Delaware River as result of incident. (3 page(s), 7/19/1977)
- ML20086D642 - Telecopy RO:on 770709,determined that recombiner sys A offgas flow control valve PCV 7489A could be opened w/ controlling solenoid valve deenergized.Valve held from svc pending investigation. (2 page(s), 7/11/1977)
- ML20086D681 - Responds to 770608 telegram re electrical cable failures at plant on 770604. (2 page(s), 6/9/1977)
- ML20086D691 - Telecopy RO:on 770301,torus water vol found to be slightly below min vol established by Tech Specs.Water vol restored to normal operating level. (1 page(s), 3/2/1977)
- ML20086D703 - Telecopy RO:on 770223,while withdrawing in-sequence control rod to bring reactor critical,reactor period of less than 5 s obtained. (1 page(s), 2/24/1977)
- ML20086D760 - Forwards LER re torus water vol below limit.W/o encl. (1 page(s), 9/22/1976)
- ML20086D779 - PNO-76-156:on 760915,steam generator tube leak of approx 80 gpm developed in steam generator 2A.Incident did not result in radiation releases in excess of limits.Outage to plug generator tube expected to last approx 5 days. (1 page(s), 9/16/1976)
- ML20086D788 - Telecopy RO:on 760909,discovered that torus water vol several hundred cubic ft below 68,000 cubic ft min required by Tech Specs.Caused by failure to correct for vol vs level correlation. (1 page(s), 9/10/1976)
- ML20086D799 - Recommends issuance of encl preliminary notification re 760714 bomb threat. (1 page(s), 7/16/1976)
- ML20086D811 - PNO-III-76-048:on 760714,general bomb threat received by load dispatcher.All plants placed in security alert. (1 page(s), 7/15/1976)
- ML20086D818 - Responds to 760520 inquiry re potential design deficiency concerning LPCI pump cavitation & motor overload.Pumps not subj to damage due to cavitation or motor overload in runout condition. (1 page(s), 6/7/1976)
- ML20086D823 - Telecopy RO:on 760504,during routine surveillance test, primary containment oxygen concentration found to be in excess of Tech Spec limit.Caused by leakage from drywell instrument air sys into containment nitrogen supply line. (2 page(s), 5/5/1976)