ML19308D093
| ML19308D093 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/02/1977 |
| From: | Stewart W FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML19308D085 | List: |
| References | |
| NUDOCS 8002270589 | |
| Download: ML19308D093 (3) | |
Text
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LICENSEE EVENT REPORT d
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[PLCASE PRINT ALL RE'_UinED INFCL iATON]
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6 LCENSEE LCENSE EVENT t ^
NAMC LCIP.SE NUMBER TYPE TYPE
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LJ 9 14 15 25 26 30 31 32 hf[J CATICoAY t
L DOCKET fJuvetR EVENT DATE '
REPOAT DATE
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@l The f ailure of Westinghouse Pressure Transmitter 59PH to demonstrate the post l
7 Us LD EE l accident (LOCA) performance capability was determined by the B&W Power Generation l
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rio Rroup. This event has not occurred to this date.
A qualified instrument is to be l
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installed as a renlacement.
Administrative control has been initiated should this l
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event occur before replacement.
(77-18) l 7 89 rm.tr 60 C
Coos COMPONENT CCDE M
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,1, 7 89 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION
[@ l The Westinghouse 59PH Pressure Transmitter used in the Decay Heat Interlock System l
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$l did not cualify for post accident (LOCA) reliabil'ity as per B&W test report. The __ _)
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h ttE ED LASC AMOUNT Of ACTMTV h
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7 as cu g ADOtttONAL FACTORS OOU k_SeeSuDDiementary Data Attached.
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'bl NAME:
W..'P. Stewart SIl pgggg; (813) 866-4159 CPO net.
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SUPPLEMENTARY INFORMATION 1.
Report No:
50-302/77-18 2.
Facility:
Crystal River Unit 3 i
3a.
Report Date:
2 March 1977 3b.
Occurrence Date:
16 February 1977 4.
Identification' of Occurrence:
The failure of the' Westinghouse 59PH Pressure Transmitters to qualify the performance required in case of a post accident condition (LOCA).
5.
Conditions Prior to Occurrence:
There has been no occurrence to this date although the deficiency has been
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identified by the B&W Power Generation Test Report of 30 December 1976.
6.
Description of Occurrence:
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A significant deficiency as defined by 10CFR50.55(e) regarding Westinghouse 59PH Pressure Transmitters used at CR-3 as RC-3A-PT1 & 2, RC-3B-PT1 & 2, and RC-132-PT which provide RCS pressure signal to the Decay Heat System high pressure isolation valve automatic closure and Interlock System (DRI) was j
reported by the B&W Power Generation group in that the pressure transmitters would not maintain the necessary accuracy over the required time period following a post accident condition (LOCA).
3 Numerous B&W tests indicated that the 59PH Transmitter would not qualify for this condition and that the test results were inconclusive.
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Designation of Apparent Cause of Occurrence:
j The cause of this occurrence was due to failure of the unit due to moisture leakage in the terminal box, and the fact that the instrument did not demon-strate the required post-accident performance.
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Analysis:
Failure of these instruments, should the event occur, could prevent the opening of a Decay Heat System isolation valve within the Reactor Building when the RCS pressure reaches the operating pressure of the Decay Heat System.
Manual bypass capability exists to open this valve.
9.
Corrective Action:
The 59PH Pressure Transmitters for the Decay Heat Interlock application are to be replaced with pressure transmitters that have met the environmental 7
qualification required for this application. Installation is expected to be complete by 1 April 1977.
In the interim, Administrative Procedures have i
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i Supplementary Information Page 2 been established to permit bypassing the Decay Heat Interl'ock System in order to open the Decay Heat System drop line isolation valves.
10.
Failure Data:
No failure of this type has occurred to this date.
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