ML19325F272

Special Rept 89-13:on 891028,upper & Lower containment,high- range,post-accident Radiation Monitors Declared Inoperable. Caused by Channel Calibr Surveillance Interval Being Exceeded.Alternative Method to Monitor Bldg Provided

ML19325F272
Person / Time
Site:	Sequoyah
Issue date:	11/13/1989
From:	Shell R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8911200048
Download: ML19325F272 (2)

Text

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• TENNESSEE VALLEY AUTHORITY p CH ATTANOOGA. TENNESSEE 37401 SN 157B Lookout Place c NOV.181988

.U.S. Nuclear Regulatory Commission ,

'ATIN: Document Control Desk.

Hashington,.D.C. 20555 Gentlemen:

'In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - TECHNICAL SPECIFICATION (TS) 3.3.3.7 - SPECIAL i

REPORT 89-13

'The enclosed special report provides details concerning Unit I upper and lower -

containment, high-range, postaccident radiation moni brs that were declared ~

inoperable when the channel calibration surveillance in'.erval was exceeded.

This report is being made in accordance with TS Action Statement 3.3.3.7.d.  ;

If you have any questions concerning this submittal, please telephone M. A. Cooper at (615) 843-6651.

Very truly yours, TENNESSEE VALLEY AUTHORITY H. AM i kanager,'NuclearLicensingand Regulatory Affairs Enclosure 3- cc (Enclosure):

., Ms. S. C. Black, Assistant Director  ;

for Projects TVA Projects Division  ;

U.S. Nuclear Regulatory Commission 1 One White Flint, North l liS55 Rockville Pike Rockville, Maryland 20852 i Mr. B. A. Wilson, Assistant Director for Inspection Programs j TVA Projects Division j U.S. Nuclear Regulatory Commission l Region II 101 Marietta Street, NW, Suite 2900 g Atlanta, Georgia 30323 NRC Resident Inspector l Sequoyah Nuclear Plant fj/ l 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 q/ tP l 8911200048 891113 DR An Equal opportunity Cmployer 3 ADOCK0500g7

' ~

r-Enclosure l ,,

SQN Special Report 89-13  !

i At 0001 Eastern daylight time on October 28, 1989, SQN Unit i entered Action Statement d of Limiting Condition for Operation (LCO) 3.3.3.7 when the upper and lower containment, high-range, postaccident radiation monitors (1-RM-90-271, 272, 273, and 274) were declared inoperable because the channel calibration surveillance'intervtl was exceeded. The channel calibrations had been scheduled to be performed.during the Unit 1 ice weighing outage, which was to have been held in mid-October. However, because of a successful ice flow blockage inspection at power, the ice weighing outage was deferred. In view of ALARA (as low as reasonably achievable) considerations, the subject radiation monitors were not calibrated with the reactor at power. '

Consequently, the surveillance interval has been exceeded, and in accordance with TS 4.0.3, the radiation monitors are considered inoperable. .

In accordance with Action Statement d of LC0 3.3.3.7, an alternate method to monitor the containment building was provided within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The alternate method of monitoring high-range radiation is through the use of the postaccident sampling system.

The plan and the schedule for restoring the operability of the 1-RM-90-271, 272, 273, and 274 monitors are to conduct the channel calibration surveillance during the upcoming Unit 1 Cycle 4 refueling outage. An additional repair wil1 be accomplished at the same time on the 1-RM-90-272 monitor by installing a new output signal cable.

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