ML20236L416

Special Rept 87-03:on 870927,during Channel Check of Triaxial Peak,Monitor SI-005-MEI Found Inoperable.Cause Undetermined.Replacement Monitor to Be Installed After Refueling & Engineering Design Evaluation to Be Made

ML20236L416
Person / Time
Site:	Crystal River
Issue date:	11/05/1987
From:	Eric Simpson FLORIDA POWER CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
3F118705, 87-03, 87-3, NUDOCS 8711100327
Download: ML20236L416 (2)

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    .C O R P O R AT IO N November 5,I1987                                                               ,

3F118705 I q 1 U. S. Nuclear Regulatory Cammission i Attention: M w nt Control Desk , .j l Washington, D. C.' 20555 1

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Subject:

Crystal River Unit 3 1 Docket No. 50-302 I Operating License No. DPR-72 Special Report 87

Dear S'r:

Enclosed is 'Special Report 87-03 which .is submitted in acmrdance with Technical Specification 6.9.2.b. Should there be any questions, please contact this office. .

                        ' Sincerely,
                                         ~

l l 1 E. C. Simpson, Director .l Nuclear Operations Site Support J l WIR: mag ') 1 Enclosure j xc: Dr. J. Nelson Grace Regional Administrator, Region II

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Mr. T. F. Stetka . Senior Resident Inspector l 1 l l 1 j M 9 g\ 8711100327 071105 PDR ADOCK 05000302

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                                                                                                     .l' Soecial prenrt 87-03 On September 27, 1987 at approximately 0400, Crystal River Unit 3 was in Mode 5 (cold shutdown) 'in preparation for refueling operations.        During the performance of SP-155 " Channel Check of the Triaxial Peak Accelograptus",

Inonitor SI-005-MEI for the top of "A" steam generator at 176'6" elevation was found to be inoperable. This accelograph is required to be operable in all Modes per section 3.3.3.3 of the Technical Specifications. As of October 27, 1987, Inonitor SI-005-MEI still had not been returned to operable status. This necessitates s*ninnion of this report pursuant to sections 3.3.3.3 and 6.9.2.b of the Technical Specifications. 'l l After discovering that the SI-005-MEI accelograph was inoperable, a l replacement was obtained frcn the warehouse ard calibrated on September 28, 1987. This replacement was not installed at that time, due to the extensive outage work being performed in that area. A water slap of the steam generator was scheduled to be performed (and has already been performed), which would have resultai in increased worker activity in the area of the monitor. It was decided to install the accelograph at some time later in the outage in order to prevent any needless damage to the monitor. This monitor is scheduled to be , l installed after completion of refueling operations and prior to ascension into l Mode 4 (hot shutdown) . l The cause of this accelograph failure could'not be readily determined. It I should be noted that the triaxial peak accelograph for the reactor vessel head I at 140 ' elevation was also fourd inoperable, yet it is not required to be operable in Modes 5 or 6 (cold shutdown or refueling) . A review of . past failures irdicates that there have been several previous cases where the triaxial peak accelographs have been found out of tolerance and inoperable. Based on these previous failures, Engineering has been requested to perform an evaluation of this type of seismic monitor to determine if a different design  ; monitor is required for the application. j i i i l 1 i 1 1. j l I \ u_____________}}