05000302/LER-1977-104, Forwards Rev 1 to LER 77-104 Re Four RCS Flow Instruments Exceeding Calibr Tolerances.Util Revising Commitment to Agree W/Tech Specs to Calibr Transmitters Every 18 Months

Forwards Rev 1 to LER 77-104 Re Four RCS Flow Instruments Exceeding Calibr Tolerances.Util Revising Commitment to Agree W/Tech Specs to Calibr Transmitters Every 18 Months

ML20214P931
Person / Time
Site:	Crystal River
Issue date:	05/29/1987
From:	Wilgus W FLORIDA POWER CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20214P933	List: 05000302/LER-1977-104, Forwards Rev 1 to LER 77-104 Re Four RCS Flow Instruments Exceeding Calibr Tolerances.Util Revising Commitment to Agree W/Tech Specs to Calibr Transmitters Every 18 Months
References
3F0587-18, 3F587-18, NUDOCS 8706040172
Download: ML20214P931 (2)

LER-2077-104, Forwards Rev 1 to LER 77-104 Re Four RCS Flow Instruments Exceeding Calibr Tolerances.Util Revising Commitment to Agree W/Tech Specs to Calibr Transmitters Every 18 Months

Event date:
Report date:
3022077104R00 - NRC Website

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• UPDATED REPORT - LAST REPORT DATED 9/9/77 LICENSEE EVENT REPORT CONTROL BLOCK:l - l l l l l l (pLEAsa palNT ALL REOUIRED INFORMATION)

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[TJ59 W60 l 0l 510 l-[0 l 3 l0 l2 l l0 l 9 [0 l 2 l7 l 7l l0 l 5 l2 l 9 l'8 l7 l 61 68 69 74 75 80 EVENT OESCAPPTION B5 l In mode 5 (cold shutdown) while reviewing completed Surveillance l 7 89 80 EE l Procedure, Calibration of the Reactor Protection System, SP-ll2, it was l 7 89 80

@ l discovered that four_RCS flow instruments were out of calibration l gg f contrary to Table 3.3-1 of Tech Spec 3.3.1.1. Redundancy N/A. First 8]

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@ l timo occurrence. Thedifferentialpressuretransmitterswerecalibrated$

7 89 a r ggored operable. ,

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7 89 80 Q l pressure transmitters. The instruments will be calibrated at least l 7 89 80 D2 l once per 18 months. .l

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NAME: pHONC-

c. .. e SUPPLEMENTARY INFORMATION

1. Report No.: 50-302/77-104

2. Facility: Crystal River Unit #3

3. Report Date: 29 May 1987. (first reported 9 September 1977)

4. Occurrence Date: 18-22 August 1977 (discovered 2 September 1977) m

5. . Identification of Occurrence:

Four Reactor Coolant System flow instruments exceeded calibration tolerances contrary to Table 3.3-1 of Technical Specifications-3.3.1.1.

6. Conditions Prior to Occurrence:

Mode 5 (cold shutdown)' operation.

7. Description of Occurrence:

While reviewing the compl eted Surveillance Procedure on Calibration of the Reactor Protection System, SP-112, it was discovered that four differential pressure transmitters in the Reactor Coolant flow system were found to be out of calibration

. tolerances. The maximum out of tolerance figure was .37%. The differential . pressure transmitters were calibrated and restored operable.

8. Designation of Apparent Cause:

The cause of this occurrence is attributed to instrument drift.

9. Analysis of Occurrence:

There was no safety hazard to the plant or public as the plant was in cold shutdown condition.

10. Corrective Action:

The original Bailey BY transmitters were replaced with Rosemount 1153D transmitters during the 1985 refueling outage. This replacanent upgraded the transmitters to meet equipment qualification requirements and should resolve the instrument drif t problem.

11. Failure Data:

This is the first occurrence of this event.