ML20126K178
| 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) | |
Text
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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:
. f JJ nbbril 1ts.
Leo J. K6rton/ Investigator 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 that ad misint preted co mean that said that h
that it Technical Specifications were be ng intentionally v o a ed, a question of how you interpreted the. Technic pec fications. h) onsidered it a poor practice to be outside of the rod d %
it was rea11 n ertion li for even 10 3r 15 inutes, even though s was permitted by said tha the Technical Specification.l said that as far as there nad ad no knowl-never been a chart recorder f ar tracking rod insertions, a o conceal edge of anyone intentionally turning off plant instrumentation data.
Closure Information The results of the
\\nterviewwerediscussedatanallegationpanel 985.
(Exhibit 2)
Based upon the information provided meeting on August 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
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nsertio its was being intentionally violated.- On the following day,-
(f ]y-).-
f 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 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 knewofconcerningthematt)er also said h t the limits asl as furnished to by nfodnation Interview of was interviewed by Investigator Leo J.
h NORT0h in the presence of_ Senior.
sident inspector Paul LAN
-(Exhibit 3)
L 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.
Y in actuality a violation of the Technical S ecif cation.
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