ML20127P248
| ML20127P248 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/22/1985 |
| From: | Domer J TENNESSEE VALLEY AUTHORITY |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20127P198 | List: |
| References | |
| NUDOCS 8505230732 | |
| Download: ML20127P248 (3) | |
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TENNESSEE VALLEY AUTHORITY CHATTANOOGA, TENNESSEE 557401 400 C$$ MAR 27 AfD : 59 '
tnut Street Tower II March 22, 1985
-U.S. Nuclear Regulatory Commission Region:II~
ATTN:
Dr. J. Nelson Grace, Regional-Administrator
.101 Marietta Street, NW, Suite 2900
-Atlanta, Georgia 30323
Dear Dr. Grace:
SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 - NRC-0IE REGION II INSPECTION REPORT 50-327/85-06 AND 50-328/85 RESPONSE TO VIOLATION Enclosed is our response to D. M Verrelli's March-1, 1985 letter to
.to H. G.'Parris transmitting IE Inspection Report Nos. 50-327/85-06 and
~50-328/85-06 for our Sequoyah Nuclear Plant which cited TVA with one. Severity Level V Violation.
- If-you have any questions, please get in touch with R. E. Alsup at FTS-858-2725.
To the best of.'my knowledge, I-declare the statements contained herein are
' complete and true.
Very truly yours,.
TENNESSEE VALLEY AUTHORITY
}J.A.DomerL
.0 Nuclear Engineer Enclosure' cc (Enclosure):
Mr. James Taylor,' Director Office of Inspection and Enforcement U.S. Nuclear Regulatory-Commission Washington, D.C.
20555 Records Center Institute'of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 8505230732 850405 PDR ADOCK 05000327 G
PDR An Equal Opportunity Employer s
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v ENCLOSURE
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' RESPONSE NRC-01E INSPECTION REPORT NOS.
U T50-327/85-06 AND 50-328/85-06.
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- D.~M. VERRELLI'S LETTER TO H.iG.-PARRIS
- DATED MARCH
- 1,1985 7-L CItem-328/85-06-011 E10 CFR 50.72(b)(2)(ii) requires the' licensee to notify the NRC operations
-center as soonLas practicable and in a11' cases, within four hours of any u
- eventior condition that results in manual or automatic actuation of the-b Reactor-Protection System (RPS). 10 CFR 50.72(.c) "Foll'owup Notification" l-
- trequires'that :the results of ensuing evaluations or assessments of. plant -
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conditions and'information related to plant behavior that is not' understood be immediately reported.'.
.: Contrary to the above, on' January 12, 1985, notification of the NRC opera-ltions center.of an RPS. actuation within the four hour requirement was made,-
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'however the licensee failed to report that the'RPS train A trip breaker-had f
' failed _to automatically open and was manually tripped. No follow-up notification to the operations center.was made when licensee personnels
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determined that'the initia1' report was incomplete.-
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fThis is a Severity Level V violation (Supplement I).
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Admission or Denial'of~the Alleged Violation lTVA'admitsLthe violation occurred as stated.
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Reasons for.the Violation'if Admitted-
'The NRC notification required by 10 CFR 50.72 was made by the onshift shif t -technical. advisor -(STA) who, at the time 'of.the phone call, was.
unaware of.the failure of the 'A' train reactor trip breaker to open automatically. At the. time 'of - the trip, tihe reactor operator (RO)
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immediately noted that the breaker did not open automatically and,
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' within five seconds of the trip, manually opened.the breaker using.a handswitch on the main control board. However, this information was
.not known to the'STA at the time of the phone call.
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.Later,_on the day =of the trip, the malfunction'was learned by the STAS Lon' shift; however, following some. time of discussion and evaluation on the-need for further reporting to the NRC operations center, it-was concluded that it was not.necessary. This decision was based on the sfact'that a.icensee event report (LER) would be written on the event
- and would describe; fully the malfunction, and that the NRC Resident.
p' LInspector had.been notified of the event. The cause of the failure to provide followup notification to the NRC operations center on this event was 'a misinterpretation of the reporting criteria. This is the'first:
, event of. this nature and is considered an isolated case and not a generic problem of reporting events at Sequoyah.
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.3.
-Corrective Steps Which Have Been Taken and Results Achieved
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Several-discussions were held between Sequoyah management and NRC personne1~concerning this event, including the reporting aspect. It
-was agreed'that events of this naturefwhich were not included as part g-of -the initial phone. call would be included in a followup call as the
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information is known.- This clarification of policy was verbally.-
' transmitted to onshift personnel who would-be responsible--for 10.CFR
- 50.72 ~ notifications, including the STA.. Further, a memorandum from.
the Operations Section manager to all licensed personnel.and' STAS is-
'being sent to. provide written clarification on NRC phone calls..These actions will preclude similar misunderstandings in the future..
42 ' Corrective Steps Taken To Avoid Further Violations See item'3.
.5[ Date'When Full Compliance Will Be Achieved
' Full compliance was achieved on January 14, 1985.
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