05000302/LER-1979-006-01, /01T-0 on 790201:figures for Transient Limits on Rapid Depressurizations & High Pressure Injection Tests in Disagreement W/Cycle 2 Reload Rept.Tech Specs Will Be Revised

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/01T-0 on 790201:figures for Transient Limits on Rapid Depressurizations & High Pressure Injection Tests in Disagreement W/Cycle 2 Reload Rept.Tech Specs Will Be Revised
ML19269C721
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 02/06/1979
From: Cooper J
FLORIDA POWER CORP.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19269C718 List:
References
LER-79-006-01T, LER-79-6-1T, NUDOCS 7902120125
Download: ML19269C721 (2)


LER-1979-006, /01T-0 on 790201:figures for Transient Limits on Rapid Depressurizations & High Pressure Injection Tests in Disagreement W/Cycle 2 Reload Rept.Tech Specs Will Be Revised
Event date:
Report date:
3021979006R01 - NRC Website

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2 IAs a result of Florida Power's review of the Cveln Tun Roln,d Ronnrt-fe J

has been determined'that the present Technical Specification 5.7, figure 4 ITTT1 i or transient limits on Rapid Depressurizations. and hich oressure iniectici f

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Those areas affected in Tech. Spec's will be revised and submitted to licensing for approval.

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C.,.E, An a (SEE TTACHED SUPPLEMENTARY INFORMATION S'dEZT)

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SUPPLEMENTARY INFORMATION Report No.:

50-302/79-006/0lT-0 Facility:

Crystal River Unit #3 Report Date:

2 February 1979 Occurrence Date:

1 February 1979 Identification of Occurrence:

Revised component cyclic or Transient Limits based on " State of the Art" data and reported under Technical Specification 6.9.1.8.h.

Conditions Prior to Occurrence:

Mode 1 power operation (76%?

Description of Occurrence:

As a result of Florida Power's review of the Cycle Two Reload Report, submitted b; B&W, it was determined that items 11 and 15 in Table 5.7-1 of Technical Specification 5.7 were in disagreement with the report figures.

Item 11, Rapid Depressurizations, according to the Report should now read 40 and the number of test transients for the high pressure injection test, should also read 40.

This information was discussed with NRC Region II and per their request is being reported under Technical Specification 6.9.1.8.h.Through communication with B&W it has been determined that the 80 Rapid Depressurizations (item 11) presently addressed in the Technical Specification was based on the initial Reactor Coolant Stress Analysis and is valid. As a result of the " State of the Art" this figure has now been re-tabulated.

Similarly, the new figures for test transients, involving the high pressure injection test, were derived.

Analysis of Occurrence:

There is no hazard to the health and safety of the plant or general pub-lic.

The number of transients in both cases have not exceeded the revised figures as submitted by B&W.

Corrective Action

Those areas affected within the Technical Specification will be sub-mitted as a Technical Speciffaation change to NRC licensing for ap-proval.

Failure Data:

No previous occurrences.

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