ML20126K178

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Sanitized Version of Investigation Rept Q-1-85-017 Re Alleged Willful Violation of TS Concerning Rod Insertion Limits
ML20126K178
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 11/12/1985
From: Christopher R, Norton L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20126J928 List:
References
FOIA-92-163 Q-1-85-017, Q-1-85-17, NUDOCS 9301070057
Download: ML20126K178 (3)
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Title:

Haddam Neck Nuclear Generating Station Alleged Willful Violation of Technical Specifications Concerning Rod Insertion Limits i

Licensee:

Case Number: Q-1-85-017 Connecticut Yankee Atomic Power Report Date: November 12, 1985 Company Control Office: 01:RI ,

Status: Closed Inquiry Reported By: Approved By:

Leo J. K6rton/ Investigator

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R. Keith Christoph6r, Directc/r Office of Investigations Office of Investigations Field Office, Region 1 Field Office, Region I f

Information in this record was dMetej in accordance with jhe freedom of Informatior Act, cxemations ..MAlC .tJ 31 F0\A. JJ A .I M.. 3..

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z ai tha ad mentioned this in a te phone cc,nyersat ,

ad misint preted co mean that that it that said that h Technical Specifications were be ng intentionally v o a ed, it was rea11 a question said tha of how you interpreted the. Technic pec fications.

onsidered it a poor practice to be outside of the rod s was permitted by h)d%

n ertion li for even 10 3r 15 inutes, even though there nad the Technical Specification.l said that as far as ar tracking rod insertions, a ad no knowl-never been a chart recorder f o conceal edge of anyone intentionally turning off plant instrumentation data.

Closure Information The results of the \nterviewwerediscussedatanallegationpanel meeting on August , 985. (Exhibit 2) Based upon the information provided Since this Inquiry failed by 01, the panel decided to close this allegation.to develop any eviden violation of Technical Specifications at Haddam Neck, this matter is closed.

No further investigative effort will be expended by this office.

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DETAILS OF INQUIRY Purpose of Inquiry This Inquiry was initiated based upon a recuest from Thomas MURLEY, Regional Administrator, Region I to interview an-incividual who was reported to have knowledge of the willful violation of Technical Specifications at the Haddam Neck Nuclear Power Station. (Exhibit 1) The willful violations allegedly involved the intentional disregarding of the control rod insertion limits .

(RIL) during power descension.

Background

0 sst 1 1985, Kenneth FERL1 r et En neer e on I, was told by at-Maine Yankee luc ear Gen rating Station, that an individua w refuse ~to identify had informed that the Haddam Neck Technical Specift on governing rod nsertio its was being intentionally violated.- On the following day,- f (,4 -

reiterated the same allegation to FERLIC and added that chart recorders in e control room were being turned off in order to hide the fact that the (f ]y-).-

rod insertion imits were being exceeded. In a telephone conversation on j wit Region I and Ol-personnel,; q identified the mdividuat who told about the intentional vio 'l10 f the rod insertion limits asl also said h t the nfodnation knewofconcerningthematt)er as furnished to by Interview of was interviewed by Investigator Leo J.

NORT0h in the presence of_ Senior. sident inspector Paul

-(Exhibit 3)

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. lstated that had no knowledge of any willful-violations of Technic peci ications or operating procedures and did not have any knowl-edge _of any attempts to conceal information by turning off chart recorders or any other plant instrumentation, was told that some information had come to the NRC's attention tha ad knowledge of the intentional violation of Technical Specif cations in '%

relation t exceeding the control rod group insertion limits. acknowl-edged that ad heard from some operator trainees that one shift supervisor would ignore he " elbow" (Exhibit 4) in the rod insertion limits and, instead of borating, would " drive through" the elbow. This would result in the rods-being inserted beyond the Technical Specifications for that power level for anywhere from 10 to 15 minutes. However, since the Technical Specification itself permitted the control rod group to be inserted beyond the insertion .

limits for up to two hours without takina compensatory me sures thi t.

in actuality a violation of the Technical S ecif cation. Y Q(f i T

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