ML19341C389

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Forwards Suppl 5 to IE Bulletin 80-17, Failure of Control Rods to Insert During Scram at Bwr. No Written Response Required
ML19341C389
Person / Time
Site: Zimmer
Issue date: 02/13/1981
From: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Borgmann E
CINCINNATI GAS & ELECTRIC CO.
References
NUDOCS 8103030283
Download: ML19341C389 (2)


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UNITED STATES 5

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799 ROOSEVELT ROAD e

CLEN ELLYN, ILLINOIS 60137

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February 13, 1981 Gentlemen:

Enclosed is IE Bulletin No. 80-17, Supplement 5, which is transmitted for information with regard to your nuclear power facility.

Should you have any questions regarding this bulletin supplement, please contact this office.

Sincerely h4

/ James G. Keppler Director

Enclosure:

IE Bulletin No. 80-17, Supplement 5 9103 080 R$3

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Cincinnati Gas and Electric Company.

ATTN: Mr. Earl A. Borgmann 4

Senior Vice President Engineering Services I

and Electric Production

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J. R. Schott, Plant Y

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AEOD Resident Inspector, RIII PDR Local PDR i

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liarold W. Kohn, Power Siting Commission Citizens Against a Radioactive Environment liclen W. Evans, State of Ohio 3

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SSINS No.: 6820 Accession No.:

801104259 IEB 80-17, Supp. 5 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C.

20555 February 13, 1981 IE BULLETIN NO. 80-17, SUPPLEMENT 5:

FAILURE OF CONTROL RODS TO INSERT DURING A SCRAM AT A BWR Description of Circumstances:

On July 3, 1980, the NRC issued IE Bulletin No. 80-17, that required actions to be taken by licensees of all operating GE BWRs.

Among the actions required, Item 6(a) required a prompt notification report by telephone to the appropriate Regional Office followed by a telecopy or other written submittal.

These reports were required in the event that any of the systems (HPCI, RCIC, SLCS, RPT, RHR/ pool cooling, and main steam bypass) were found to be less than fully operable.

These reports have served the purpose of notifying NRC of cases of potential reduction in operability of systems important to the mitigation of consequences of an anticipated transient without scram (ATWS) event.

These reports are no longer necessary since improvements have been accomplished to increase the reliability of control rod scram.

l Actions No Longer Necessary by Licensees:

Further reporting is not required in response to Item 6(a) of IE Bulletin 4

No. 80-17.

This does not change the reporting requirements set forth in your license technical specificctions.

No written response to IE Bulletin 80-17, Supplement 5, is required.

If you have any questions regarding this matter, please contact the appropriate NRC Regional Office.

Attachment:

Recently issued IE Bulletins l

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Attachment

, e' IEB 80-17, Supp. 5 February 13, 1981 RECENTLY ISSUED IE BULLETINS Bulletin No.

Subject Date Issued Issued To l

81-01 Surveillance of 1/27/81 All power reactor Mechanical Snubbers facilities with an OL i

& to specified i

facilities with CP 1

80-25 Operating Problems with 12/19/80 All BWR facilities Target Rock Safety-Relief with an OL & specified t-Valves at BWRs near term OL BWR j

facilities & all BWRs with a CP Supplement 4 Failure of Control Rods 12/18/80 To specified BWRs t

to 80-17 to Insert During a Scram with an OL & All at a BWR BWRs with a CP 80-24 Prevention of Damage 11/21/80 All power reactor Due to Water Leakage facilities w*th an Inside Containment OL or CP (October 17, 1980 Indian Point 2 Event) 80-23 Failures of Solenoid 11/14/80 All power reactor i

Valves Manufactured by facilities with Valcor Engineering OL or CP Corporation 80-22 Automation Industries, 9/11/80 All radiography Model 200-520-008 Sealed-licensees Source Connectors

.l 80-21 Valve yokes supplied by 11/6/80 All light water

^

Malcolm Foundry Company, Inc.

reactor facilities with Ols or cps Supplement 3 Environmental Qualification 10/24/80 All power reactor to 79-01B of Class 1E Equipment facilities with an OL Supplement 2 Environmental Qualification 9/30/80 All power reactor to 79-01B of Class 1E Equipment facilities with an OL i

OL = Operating License 1

CP = Construction Permit i

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