ML20037A571
| ML20037A571 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/23/1977 |
| From: | Long F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Sniezek J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8003160002 | |
| Download: ML20037A571 (2) | |
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March 23, 1977 MEMORANDUM FOR:
J. H. Snie:ek, Chief, Light Water Reactor Programs Branch, Office of Inspection and Enforcement, Headquarters Ad N. C. Moseley, Director, Office of Inspection and THRU:
Enforcement, Region II FROM:
. J. Long, Chief, Reactor Operations and Nuclear Support Branch, Region II
SUBJECT:
FLORIDA POWER CORT 0EATION, CRYSTAL RIVER 3, DOCKET NO.
50-302 - LOSS OF CFFSITE POWER TEST (F21h3hH1)
Loss of offsite power testing performed at Crystal River 3 <*oes not meet the intent of RG 1.68, paragraph D.l.k.
FSAR 13.1.1 states that the test program is structured in.accordance with RG 1.68.
FSAR 14.1.2.0.1 states that the facility is designed to withstand a complete Ices of all system and unit power except the station batteries.
Item 11 of FSAR Table 13 h, titled " Loss of Offsite Pover," states that the 1surpose of the test is to demonstrate operation of the diesel generators (DG), turbine driven W pumps and engineered safeguard (ES) buses in the event of a total loca of offsite power.
The test was performed on March 9,1977, at a power level of about h0". generator output. The test was conducted with the unit generator supplying the facilit/ auxiliary load, ES bus 3A vas energized by an emergency DG and E bus 3B was energized by the offsite power source through the startup transformer. Loss of offsite power was simulated by opening the breaker to ES bus 33. The remaining DG automatically started and reenergized ES bus 3L.
No interruption in reactor operation was experienced, as the unit generator continued to supply the auxiliary loads and ES bus M was being energized from an uninterrupted DG.
ES bus 3A was similarily tested by energizing E bus 3B with a DG and interrupting the offsite power supply to ES bus 3A.- Same results were experienced.
FPC corporate manag2 ment takes the position that they have met their testing cor:mitment r.nd supports their position on the bases that a BW facility has ever conducbed testicc. tat involved loss of off. site j
po'rer coincident with loss of unit generator. A review of the th*ee BW Oconee units reveals that testics simila" to Crystal River 3 we.s conducted. Also, FPC stated they w eld Le reluctant to subject the reactor coolart pumps to loss of seel water flov for testing purpcacs.
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Region II does not concur that the loss of offsite power testing
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conducted at Crystal River 3 meets the intent of RG 1.68; therefore, j
the test does not demonstrate that the plant rerpense vill be as predicted for a loss of offsite power coincident with a loss of unit generator. If you concur with our position, ve request that action be taken to require that retestir3 be accomplished in accordance with the intent of RG 1.68.
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F. J.,Lons, Chief Reactor Operations and Nuclear Support Branch cc:
G. Gower, II:HQ R. C. Lewis, IZ:II CONTACT:
R. C. LEWIS 221-6068 l
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