ML19254F768

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Forwards IE Bulletin 79-06A, Review of Operational Errors & Sys Misalignments Identified During TMI Incident, & Draft Ltrs
ML19254F768
Person / Time
Issue date: 04/13/1979
From: Moseley N
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: Grier B, James Keppler, James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19254F764 List:
References
NUDOCS 7911160549
Download: ML19254F768 (3)
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NUCt. EAR R5GULATORY COMMcsE5?i~ AR o

UNITED STATES 7g,

wAsHIN GToN. D. C. 20555

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w MEMORANDUM FOR:

B. H. Grier, Director, Region I J. P. O'Reilly, Director, Regicn II J. G. Keppier, :irector, Regien III K. V. Seyfrit, 'irector, Regior IV R. H. Engelken, Director, Region V Nornan C. Mcseiey, Director, Divisicr. of :eac:cr

ROM:

Operations Inspection, IE IE Bulletin No.79-05A, REVIEh 0F 0.:E:.ATI^:,c'. E :.0.5

SUBJECT:

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The subject Bulletin should be dispatched for acticn en April 14, 1979, Oc all pressurized water power reactor facilities of

estinghouse design with an cperatinc license.

Facilities with a constructicn permit, Ft. St. Vrair.,

E'..','s and the Combustion Engineering and the B&W facilities with an Operating license should receive the subject Bulletin for informatien only.

The text of the Bulletin and draft letters to licensees are enclosed for this purpose.

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Norman C. eseley[ Directo'r Division of Reactor Operations Inspection Office of Inspection and Enforce ent

Enclosure:

1.

Draft Transmittal Letter to Westinghouse designed PWR Operating Licensees 2.

Draf: Transmittal Letter to Operating Licensees of GE, CE and BEW plants, l 3 4 /

._Q 4 F. St. Vrain and all Construction Permit Holders 3.

IE Bulletin I:o.79-06A c.

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(Oraft letter to Westinghouse desigr.ed pressurized water power reactor facilitics.!ith an cperatin; license. )

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Addressee:

Enciesed is :E Sulletin i;o.79-05A, which recuires ac-ion by you..'--

recard to.vcu,r Westinchcuse desicned cressurized water rea::cr raci,alty(1es; w1:n an operating license.

Eased on our current uncerstanding or tne.nree.. lie ;slanc a :1:e -

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reac r,.;e tave reason to believe that pressurizer level ird'ea-i:n.

j i n.v c u r r a c 1,.1 :.v Ta.v n o t p ro v i e e re ).1 a b3ie int 0rmation rec. arc,. n c. ;e.e.

in -he react:r coolant syster under certain transient er accicen condi-icns.

You should ir.ediately instru:: your cperating pers:rre a c co r d i n c.i.v.

In addition ycu shoulc cnsicer nis possibilit.y it rescending to the enclosed bulletin.

Snculd you have any c estiens regarding this Eulletin or :ne ac:'ers rec.uired by jeu, please centac this office.

Sincerely, Sicnature (c.egicnal v1 rector)

Encicsure:

IE Sulletin No.79-06A 1347 226

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_s 1::icns :: de aker oy Licensees:

cr all..'es-inchouse pressurized '..ater react:r facilities witn an o;erating licer.se (the actions s?e:ified bei:s recia:e :ncss iden-ifie:

in IE Bulletin 79-C6 on an item by item basis):

1.

Review'tne description of circumstances described in Enciosure i ui

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letin / e.-05 and the oreliminary chronciogy or :.ne

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Inis review should be directed toward understancin3 (1) J..e extreme sericusness and consequences cf the simultaneous Diccking or co:n auxi,iiary feecaater trains at the _inree,,,11e Islar.d Unit 2 plant and other a:ticns taken during the early phases of_the accident; (2) the apparent c;erational errcrs wnich led to the eventual core damage; (3) that the potential exists, under certain accident or transient conditions, to have a water level in the pressurizer simultaneously with the reactor vessel not full of water; and (a) the necessity to systematically analyze plant conditions and carameters and take appropriate corrective action.

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3 coeratior cf engineered p'. ant conditions (see S' DUPLICATE DOCUMENT ti nal decisions based i.:i:a-icr wqen one Or Entire document previously a cE' '

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entered into system under:

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