ML19317G568
| ML19317G568 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/04/1974 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | Knuth D US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19317G567 | List: |
| References | |
| NUDOCS 8003191141 | |
| Download: ML19317G568 (2) | |
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") sy,i.yY Florida February 4, 1974 Power coano..
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1 Donald F. Knuth, Director j
The Directorate of Regulatory Operations U. S. Atomic Energy Commission Washington, D. C.
20545
Subject:
Crystal River Plant Unit #3
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Docket 50-302
Dear Mr. Knuth:
On Wednesday, January 30, 1974, we advised the Director of Regulatory Operations, Region II in Atlanta by telephone, that we had been notified by B&W Company that certain revisions were required in Fuel as utilized in some of their the Specific Heat Curve for UO2 transient Computer Codes. This change will be reflected in a higher value of the specific heet for elevated fuel temperatures.
Florida Power Corporation has determined that in our opinion this change constitutes a significant deficiency in that, had it remained unchanged, Crystal River Unit #3 could have been operated in such a manner that safety limitations would have been exceeded. Therefore, we are filing this report pursuant to the requirements of AEC 10CFR50.55e.
The studies necessary to quantify the impact that this revision The may have on the safety analyses reported in the SAR are underway.
general effect will be a change in the level of stored energy in the Based on B&W?.s fuel as well as in the time response of some transients.
present evaluation, this revision will not affect the steady-state analysis because the basic data from which the curve is derived are valid; it is these basic data that are used for the steady-state calcu-e lations. The particular effect on kinetic behavior can be determined only by an evaluation of the safety analyses. To indicate the magnitude of this revision, preliminary calculations en Oconee 2 show that'a reduction in the maximum linear heat-rate of less than 1.0 KW/ft should offset the effects of this change in specific heat.
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w Donald F. Knuth February 4, 1974 Page.
We have been advised that the correction of this deficiency will not require any physical component design changes. The result of lowering the maximum allowable linear heat rate will result in modifications to the Technical Specifications with regard to operating restrictions.
In addition to this change in B&W's transient computer codes, the recently published AEC Final Acceptance Criterion for ECCS will require that considerable re-analyses be performed which also have a bearing on the maximum allowable linear heat rates. Both of these
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considerations will be fully taken into account and documented in a timelf fashion prior to finalization of the Crystal River Unit #3 Technical Specifications.
We will keep you advised on the status of B&W's continuing investigation. We understand that B&W will be discussing this infor-nation with you on a generic basis in an effort to keep you fully informed of further developments.
If you require any further information regarding this matter, please advise us.
Very truly yours, f
idh Joel T. Rodgers' Assistant Vice President cc: Norman C. Moseley Director, Region II O
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F!cdda Power February 1, 1974 coaeouvio=
Donald F. Knuth, Director The Directorate of Regulatory Operations U. S. Atomic Energy Commission Washington, D. C.
20545 i
Subject:
Crystal River Plant Unit #3 Docket 50-302
Dear Mr. Knuth:
In order to provide you with the necessary data to evaluate Florida Power Corporation's actions regarding the reported non-conformance discussed in our letter to you of December 27, 1973 we are enclosing copies of the following data:
1.
GAI letter #FPC-9738, dated January 23, 1974.
2.
GAI letter #FPC-9093, dated October 8, 1973.
3.
FPC letter, dated November 5, 1973.
4.
Crystal River Unit #3 Construction Procedure #JAJ-W52, Revision 2.
5.
Signed Quality Control Checklist (Form #JAJ-132).
6.
Field Changes 1 - 8 to Crystal River #3 Construction Procedure JAJ-W52.
These documents are the documentation referenced in our December 27th letter. The GAI letter #FPC-9738, dated January 23, 1974, is a formal transnittal of documentation that was originally at the site in the form of a telecopier communication to Florida Power Corporation.
This is the reason for this letter being dated subsequent to the issuance of our final report on December 27th.
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,.. Petersburg. Flor:da 33733 e 813--866-5151 e
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