ML20053A668
| ML20053A668 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 05/12/1982 |
| From: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Jackson E VERMONT YANKEE NUCLEAR POWER CORP. |
| Shared Package | |
| ML20053A669 | List: |
| References | |
| NUDOCS 8205270101 | |
| Download: ML20053A668 (4) | |
See also: IR 05000271/1982007
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ENCLOSURES TRANSMITTED HEREWITH
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CONTAIN 10 CFR 2.790 INFORMATION
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MAY 121982
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H' a No. 50-271
Vemont Yankee Nuclear Powed f,orporation
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ATTN: Mr. E. W. Jackson
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Manager of Operations .
411 Western Avenue
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Drawer 2
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West Brattleboro, Vermont 0,5301.
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Gentlemen:
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Subject:
Inspection 50-271/82-07
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This refers to the special inspection conducted by a team of NRC inspectors on
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April 26-30, 1982 at the Yemont Yankee Huclear Power Station, Vernon Vermont
of activities authorized by NRC License No. DPR-28 and to the discussion of our
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findings held by Mr. Raymond with yourself, Mr. Warren Murphy and other members
of your staff at the conclusion of the inspection.
The NRC team examined the 15ss of feedwater event of April 24, 1982 to detemine
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the event sequence and cause;..to evaluate its consequences; and to assess the
actions of the plant staff during and subsequent to the event. The findings of
the team are discussed in the enclosed NRC Region I Inspection Report.
We have determined that the'perfomance of the shift crew during the event was a
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contributing factor to the delayed reporting of the event. Automatic initiation
and injection of the high pressure coolant injection (HPCI) system requires
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classification of the event as an Alert in accordance with the Yemont Yankee
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Emergency Plan. The HPCI initiation and . injection which occurred early in the
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event was not immediately recognized by the licensed staff. We are concerned
that it took about one hour.to recognize this fact. More importantly, we detemined
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that your Nuclear Safety Engineer (the STA) did recognize the HPCI initiation
and injection based on panel indications associated with HPCI initiation but
failed to communicate his observations to the licensed staff until later in the
event.
It appears that the, Nuclear Safety Engineer function has not been fully
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integrated into the operating crew and we believe that this area requires your
additional attention.
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An apparent violation of NRC requirements is discussed in the inspection report
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enclosed with this letter. We are considering this item for appropriate enforcement
action and will be addressing _this matter under separate correspondence at a
later time.
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Based on an analysis of the facts associated with this event, we find no physical
plant conditions which existed on April 24, 1982 that either constituted an
ENCLOSURES TRANSMITTED HEREWITH
CONTAIN 10 CFR 2.790 INFORMATION
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Ef CLOSURES TRANSMITTED HEREWITH
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CONTAIN 10 CFR 2.790 INFORMATION
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l AY 121382
Yer ont Yantae Nuc1 car Pouer corporation
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Alert or otherwise urranted offsite assessment action. The !.RC .;uidance
in SUREC-0054 differentiates betucc.n activation of ECCS due to transients and
those due to a loss of coolant accident. This difference provides a raticnale
for distinguishing between an Unusual Event and other classes of ec2rgencies.
In this Nrticular situation the loss of feeduater resultcd in an appropriate
syste., resrcnse; tc'cycr, the problens and delays associated with classification
anJ ar.alysis of the event, rcaffirm the need for you to upgrade your capabilities
related to errgency preparedness.
Specifically, the !:RC Energency Preparedness Appraisal team recently identified
the need for you to revise your procedures relating to Energency Action Levels
and to train your staff in the use of the revised procedures. The results of
this appraisal were comunicated to you on l' arch 24, 1932, and documented in a
letter dated April 28, 1982. These revisions were re';uested to to accomplished
no later than July 20, 1982.
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Infor ation contained within' the enclosed inspection report has been discussed
with Mr. E. W. Jackson by telephone en l'.ay 12, 1932. During this discussion, it
was detemined that paragraph five of the insocction report contained inforcation
' St you consider proprietary. Written application to withhold this inforr.ation
st culd te received in the Region I office within ten days of the date of this
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letter. Therefore, in accordance with 10 CFR 2.790 (b)(1), paragraph five of
the report will receive lin:ited distribution. A copy of this letter and its
enclosure, with paragraph five deleted, is being placed in the hRC's Public
Document Roca.
Your cooperation with us in this matter is appreciated.
Sincerely,
originai sisnod B78!
P.ichard W. Starostecki, Director.
Division of Project and Resident
Programs
Enclosure: HRC Region I Inspection Report Ihbor 50-271/82-07
cc w/eac1:
Mr. Warren P. ilurphy, Plant l'anager (w/o Para. 5 of Rpt)(w/o Para. 5 of Rpt)
I:r. W. F. Conway, President and Chief Operating Officer
Pr. L. H. Heider, Vice President (w/o Para. 5 of Rpt)
Mr. R. L. Smith, licensing Engincar (w/o' Para. 5 of Rpt)
Ps. l'adeltene Tunin, Lieutenant Governor, State of Yemont (w/o Para. 5 of Rpt)
l'r. Richard Saudek, Chaincan, Vermont Public Service Ecard (w/o Para. 5 of Rpt)
Public Docrent Room (PDR) (w/o Para. 5 of Rpt)
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local Public Document Rocru (LPDR)(w/o Para. 5 of Rpt)
Suc1 car Safety Information Center (NSIC) (w
State of He.t Haupshire (w/o Para. 5 of Rpt)/o Para. 5 of Rpt)
State of Vernont (w/o Para. 5 of Rpt)
- C Resident inspector (w/ Para. 5 of Rpt)
07?l01ALRECO3D COP
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ETLO9UnG TRANSMITTED HEREWITH
cou,dN 10 CFR 2.700 INFORMMlOM
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ENCLOFURES TRANSMITTED HEREVilTH
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CONTAIN 10 CFR 2.790 INFORMATION
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MAY 121982
'*crrnt Yankee ?;uclear Pc3.er Corporation
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bec w/ enc 1:
Region I Docket Room (tvith cor.currences) (w/o Para. 5 of Rpt)
Chief Operational Support Section (s:/o encl)
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1dC R 2.790 INFORMATt0N
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