ML19296B837
| ML19296B837 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/31/1979 |
| From: | Moore G FLORIDA POWER & LIGHT CO. |
| To: | Ross D NRC - TMI-2 BULLETINS & ORDERS TASK FORCE |
| Shared Package | |
| ML19296B831 | List: |
| References | |
| FOIA-81-149 NUDOCS 8002220225 | |
| Download: ML19296B837 (3) | |
Text
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August 31, 1979 d
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Mr. D. F. Ross, "Jr.
Director Bulletins and Orders Task Force Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Cocsission 17ashington, DC 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72
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Identification and Resolution of Long-Tern Generic Issues Related to the Commission Orders of May 1979
Dear lir. Ross:
Florida Power Cor;cration received your letter of August 21, On August 23, 1979, 1979, identifying eight long-term issues related to the Order which must be re-solved for Crystal River Unit 3 and the other PAU Cperating Plants.
These eight (8) ite=s were identified and briefly ciscussed in Enclosure 1 of
/, and 8, you requested your letter.
In your discussion of Ite=s 1, 4,
..:cr:ation and our schedule for Florida Power Corporation to provide additional resolution of these five (5) ice =s by August.'.'.
In that regard, Florida Power Corporation heret -
. :::its, as Attachment I to this letter,,our response to your August 21, L...
aquest for additional information.
If you require further discussion concerning out
- rponse, please contact us.
Very truly yours, FLORIDA POTTER CORPORATION 8
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C. C. Ifoore Assistant Vice President Power Production 8'
CCMekcF06(DS) 8 2220 9
2 '2 Attachment 14n47 St Petersburg.Florda 33733 813-866 5151
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t t ATTAC MENT 1
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Response to Ross Letter of August 21, 1979 Item 1 - Failure Hode and Affects Analysis of the Integrated Control System On August 17, 1979,- B&W submitted to you for your review, copicis of the report entitled "BAW--1564,- Integrate'd Control System (ICS) Reliability Analysin*'.
This letter is to advise you that,this report is applicabic to Crystal River Unit 3.
Although this was a generic report developed by B&W,. and. there arc dif-ferences in the secondary system designs at, the various B&W plants, we feel that the conclusions reached in this report can be applied to, Crystal River Unit 3.
Florida Power Corporation is presently reviewing the recommendations listed in Section 3 of this report to determine what possible changes are necessary at Crystal River Unit 3 to' enhance reliability and safety.
Ited - Auxiliary / Emergency Feedwater System Reliability Upgrade This letter is to inform you of Florida Power Corporation's cocmitment to the AFW/EFW System Reliab(11ty Study penposed by B&W and discussed with you and your
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staff on July 19, 1979', and August 9, 1979.
The dra f t report for Crystal River Unit 3 will be submitted by October 22, 1979, and the first report will bc submitted by December 3, 1979.
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Item 5 - Detailed Analysis of the Thermal-Mechanical Conditions in the Reactor Vessel During Recovery. f rom Small Breaks With Exteaded 1,oss of All Feedwater
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The above analysis will be submitted by Lecember 21, 1979.
Item 7 - Small Break :1,0CA Analysis The following is our schedule of response to the six items contained in Attachment A of your letter:
1)
A.
Report will be submitted on December !
.ci9.
3.
Report will be submitted on Septemba.
'979.
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979.
2)
A.
Report will be submitted on Septemte-B.
In response to this request, we are pm-sing three (3) options i
in preference of order:
I)
Provide a statement by September **
1979, that swa small break with. auxiliary feedWter will pressurize tin-system to*.
the PORV setpoint.
2).
Provide by December 30, 1979, a qualitative anneanment of the transient.
2 3)
Provide core analysis by February 1,1980, using 0.01 f t break with no AFV available.
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Ve are presently proceeding with option #1, unless otherwise notified by the NRC.by September 7,1979.
CCMekcF06(DS)
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Table 4-5.
(Cont'dl FAltuPE MODULE NO.
M00utt ilAl1C h)DE tif tCT (na H55 RfACTOR 1 RIP RtMARK5 Functlanal: 2 Hodified Turbine High The 105 pulser util send a continuous increase lingh RC Pressure IC5:
4-2-13 Ikader Pressure demand to the turbine tilC causing a throttle g
Error pressure decrease. The large pressure error detector transfers the turbine [ilC to sunual
.Mo problem after in s5 seconds. The ICS assumes the tracking reactor trip moda and the feeduater and reactor increase to seet tne s41 load increase. The erroneous andlfied throttle pressure error causes a mis-satch between tl,e 1855 stean production and the tuihine operatis.n.
15e pressure decrease is almited at s100 psf by the turbine initial oressure reoulator. Reactnr trin on hioh Af.
pressure is possible.
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issan'.lally the same response as Failure flode til9h RC Pressure "High" escept ps essure rises and is terminated if power es401.
by turbine ley-pass valve action.
-l;o problem af ter reactor trip su e
IS e'
Functional: 3 Turbine Control Fallure is very simil r to failure of functional 105:
3-6-1 block 2. above.
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