ML19220C539

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Forwards IE Bulletin, Review of Operational Errors & Sys Misalignments Identified During TMI Incident, & Draft Cover Letters
ML19220C539
Person / Time
Site: Crane 
Issue date: 04/11/1979
From: Moseley N
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: Engelken R, Grier B, James Keppler, James O'Reilly, Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
NUDOCS 7905110187
Download: ML19220C539 (3)


Text

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%, ' C'. f April 11, 1979 MEMORANDUM FOR: B. H. Grier, Director, Region I j J. P. O'Reilly, Director, Region II / J. G. Keppler, Director, Region III K. V. Seyfrit, Director, Region IV R. H. Engelken, Director, Region V FRCM: Norman C. Moseley, Director, Division of Reactor Operations Inspection, IE

SUBJECT:

IE BULLETIN NO. 79-06, REVIEW OF OPERAT:CNAL ERRORS AND SYSTEM MISALIGNMENTS IDENTIFIED DURING THE THREE MILE ISLAND INCIDENT The subject Bulletin should be dispatched for action on April 11, 1979, to all pressurized water pcwer reactor facilities with an operating license except B&W fr.cilities. Facilities with a construction permit, Ft. St. Vrain, EWR and the B&W facilities with an operating license should receive the subject Bulletin for information only. h The draft letters to licensees are enclosed for your use in expediting and dispatching the Sulletin. The Bulletin text will be placed on Wylbur later today, at which time your office will be notified by r telephone. >/$dR' Nomad v..noseley, Di rector D[disionofReactorCperaticns Inscection Office of Inspecticn and Enforcement

Enclosure:

1. Draft Transmittal Letter to all Operating Licensees less SWR and B&W plants 2. Draft Transmittal Letter to Operating Licensees of B&W plants, Ft. St. Vrain and all Construction Permit Holders 3. IE Bulletin No. 79-06 CONTACT: E. B. Blackwood, IE 49-28019 70051106 1 6 ) h c-

(Draft letter to all B&W power reactor facilities witn an operating license and all pcwer reactor facilities with a construction permit and Ft. St. Vrain.) IE Bulletin No. 79-06 Adcressee: The enclosed Bulletin 79-06, is forwarded to you for information. No written response is required. If you desi: e additional information regarding this matter, please contact this office. Sincerely, Sicnature (Regional Director)

Enclosure:

IE Bulletin No. 79-06 _ -{' with Enclosures h 1)\\ 5 ~ 90

(Or:'t letter to pressurized water power reactor facilities other than B&W ~ witn an operating license.) IE Sulletin Nc. 79-06 Addressee: Enclosed is IE Bulletin No. 79-06, which requires action by you with regard to your pressurized water reactor facility (ies) with an operating license. Based on our current understanding of the Three Mile Island accident saquence, and discussion with the designer of your pressurized water reactor, we have reason to believe that pressurizer le/el indication in your facility may not provide reliable infonnation regarding level in the reactor coolant system under certain transient or accident condition. You should immediately instruct your operating personnel accordingly. In addition you should consider this possibility in responding to the enclosed bulletin. Should you have any questions regarding this Bulletin or the actions required by you, please contact this office. Sincerely, Signature (Regional Director)

Enclosure:

IE Bulletin No. 79-06 with Enclosures

UNITED STATES NUCLEAR REGULATORY CCIOilSSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C. 20555 April 11, 1979 IE Bulletin No. 79-06 RE'/IEW 0F OPERATIONAL ERRORS AND SYSTEM MISAUGNMENTS IDENTIFIED DURING THE THREE MILE ISLAND INCIDENT As previously discussed in IE Bulletin 79-05 and 79-05A, the Three Mile Island Nuclear Power Plant, Unit 2 experienced significant core damage which resulted from a series of events initiated by a less of feedwater transient and apparently compounded by coerational errors. Several aspects of the incident have generic applicability to all light water pcwer reactor facilities, in addition to those previously identified as applicable to Babcock and Wilcox reactors. This bulletin is to identify certain actions to be taken by all other light, water power reactor facilities with an operating license. Actions previously have been required of licensees with B&W reactors. Action to be taken by licensees: For ali pressurized water pcwer reactor facilities with an operating license except Babcock and Wilcox reactors: 1. Review the cescciption of circumstances described in Enclosure 1 of IE Bulletin 7 3-05 and the preliminary chronology of the TMI-2 3/28/79 accident included in Enclosure 1 te IE Bulletin 79-05A. This review should be directed toward understanding: (1) the a. extreme seriousness and consequences of the simultaneous blocking of both auxiliary feedwater trains at the Three Mile Island Unit 2 plant and other actions taken during the early phases of the accident; (2) the apparent operational errors whicn led to the eventual core damage; and (3) the necessity to systematically analyze plant conditions and parameters and take appropriate corrective action. b. Operations personnel should be instructed to: (1) not ovecride automatic action of engineered safety features without careful review of plant conditicns; and (2) not make operational decisions based on a single plant parameter indication when a :enfir-atory indication is available. 7" - -_+-_n__ c. All licensed operator l DurLICATE DOCUMENT / }}D with operational res;n 0 review and such parti l Entire document previously entered records. into system under: j ANO 790 # 9'M d gg d h No. of pages: -/ ( 6 ( khNO/%D AN wew%%m r-}}