ML19289F506
| ML19289F506 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/22/1979 |
| From: | Stewart W FLORIDA POWER CORP. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 7906110064 | |
| Download: ML19289F506 (2) | |
Text
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April 22, 1979 Mr. James P. O'Reilly, Director U.S. Nuclear Regulatory Comission Office of Inspection and Enforcement 101 Marietta Street, Suite 3100
' Atlanta, GA 30303
Subject:
Crystal River Unit No. 3 Docket No. 50-302 Operating License No. DPR-72 IE Bulletin 79-05B
Dear Mr. O'Reilly:
This letter is to advise you of the action taken by Florida Power Corporation in response to Item 3 of IE Bulletin 79-05B dated April 21, 1979. Specifically, this action includes:
1)
On Saturfay, April 21, 1979, the Plant Review Committee (PRC) met and reviewed IE Bulletin 79-05B As a result andmeeting, of this the B&WSP-112, recomendations received April 21, 1979.
Calibration of the Reactor Protection System, has been revised and implemented lowering the high pressure reactor trip setpoint from 2355 psig to 2300 psig.
2)
In lieu of raising the setpoint of the PORV from 2255 psig to 2450 psig as discussed in the subject bulletin and B&W 1etter, Florida Power Corporation has isolated the PORV by closing the This action was discussed PORV isolation valve (block valve).
with Mr. Reid, Mr. Grimes and Mr. Moseley of the NRC and found acceptable as an interim action by Florida Power Corporation, as we are scheduled to shut down Crystal River #3 on Monday morning, April 23, 1979, for normal plant refueling. Prior to startup following this refueling outage, the setpoint of the PORV will be changed from 2255 psig to 2450 psig.
2230 259 P7dcA55 OFFICIAL COPY 790611 0064 General Othee 32ot inney.iourth sr i sovin.r.o som 14o42. m Pete<seurg Fwes 337 nn.
.. . .. . ~ .. . .
1 Mr. James P. O'Reilly Page 2 April 22, 1979 This action has been reviewed and analyzed by B&W and does not constitute an unreviewed safety question as no credit was taken for PORV actu during the transients analyzed. PORV to decrease the likelihood of automatic actuation of the operation during these anticipated transients.
Florida Power Corporation is continuing its review of the overall pres-surizer operation during various transients and will advise you of our findings once this review is complete.
If you require any clarification of the actions taken by Florida Power Corporation, please contact this office.
Very truly yours, FLORIDA POWER CORPORATION
. b W. P. Stewart WPS:ddw cc: Director Office of Inspection & Enforcement Division of Reactor Operations Inspection U.S. Nuclear Regulatory Commission Washington, D.C. 20555 File: 3-0-3-a-3 2230 260
.