ML19344B383
| ML19344B383 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 08/03/1977 |
| From: | Bolger R COMMONWEALTH EDISON CO. |
| To: | Case E Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19344B371 | List: |
| References | |
| NUDOCS 8010080742 | |
| Download: ML19344B383 (2) | |
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N. CommonwJ'- 7 Edison
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Mr. Edson G. Case, Deputy-Director k
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-11 U.S. Nuclear Regulatory Commission
.A. h Washington, DC 20555
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Subject:
Dresden Station Unit 1
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\\c N NRC Docket'No. 50-10 Reference (a) :
D. K. Davis letter to R. L. Bolger,
' dated May 11, 1977.
1
Dear Mr. Case:
This letter is written in response to Reference (a),
which contained a request for additional information regarding the Dresden Station Unit 1 Fuel Cycle 11 licensing report.
Attachment I to this letter contains responses to questions (1) and (2) of Reference (a).
These are interim responses for use prior to the availability of the final transient analysis I
for Dresden-1.
A conservative margin is added to the current MCFHR limits based on the Janssen-Levy correlation until a final MCPR limit can be established from the transient analysis based on XN-2 correlation.
Responses to questions (3) through (6) are in their final version.
Responses to questions (7) and (8) - are interim responses pri~or to the sensitivity study of the, Maximum system pressure on the initial operating pressure.
Responses to questions - (9). through (17) are final versions.
Transient analyses of the Dresden 1 Unit 1 reactor by using the approved XN-2 correlations are to be completed by November 1, 1977.
The results will be submitted to the NRC immedi-ately following the completion of the analyses.
Attachment II to this letter are proposed Technical Specification changes to conservatively limit the operation of the Unit within required safety margins for Cycle 11.
The proposed Technical Specification change.on MCHFR adds an additional margin of 0.4 to the existing MCFHR limit of 1.5 at 125 percent overpower.
The section on Partial Core Flow Operation limits the reactor operation to at least two pumps to preclude the possibility of flow instability under natural circulation conditions and to preclude reactivity insertion under recirculation pump startup.
The change on reactor
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Mr. Edson G. Case 2.-
August 3,-1977 4
pressure bounds..the initial operating pressure within the initial conditions.used:in-. Anticipated Transient.Without. Scram.
The
.: change' for ECCS fuel operating limits now include's Type-XN-1 and~ deletes Types-7Pu and 3.
These changes are to ensure the safe operation of.the coming cycle.
The Type XN-1 heatup analysis supplement sas performed as a-followup.to'the 1975 Plant As-Is analysis submitted July 31, 1975,. and is included as Attachment III to this letter.
2 on-site and off-site' review have reviewea a.;l crproved the proposed Technical Specification changes.
i
. Please refer any additional questions to this office.
Three (3) signed originals and 37 copies of this letter are provided for.your-use.
Very truly yours,
}
R. L. Bolg Assistant Vice President i
Attachments 1
SUBSCRIBED and SWO to befo me this M day i
of '-
, 1977.
du, Notary Public 4
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