ML17254A523
| ML17254A523 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 08/19/1985 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8508230177 | |
| Download: ML17254A523 (8) | |
Text
REGULATORY IN
'MA'TION DISTRIBUTION SYSTF" (RIDS)
ACCESSION NBR: 8508230177 DOC ~ DATE,: 65/08/19 NOTARIZED:
NO DOCKET' FACIL:50-244 Robert Emmet Ginna Nuclear Plantr Unit lr Rochester G
05000244 AUTH BYNAME AUTHOR AFFILIATION KOBERiR,H, Rochester Gas 8 Electric Corp.
REC IP. fJAME RECIPIENT AFFILIATION ZHOLINSKI,J, A.
Operating Reactors Branch 5
SUBJECT; Forwards fluence vs operating time curve presented at 850717 meeting to support 821206 Tech Spec change re heatup 8
cooldown limits.Conclusions support capsule withdrawal schedule in proposed Tech Spec.
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///////N' Ill(IIIZl /I/ill/II/I ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.K 14649-0001 ROGER W. KOBER IIICE PRESIDENT EKECTRIC 6c STEAM PRODUCTION August 19'985 TKLKPIIONK AREA CODE 7le 546-2700 Director of Nuclear Reactor Regulation Attention:
Mr. John A. Zwolinski> Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washington>
D.C.
20555
Subject:
Proposed Technical Specification Heatup and Cooldown Limits R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Zwolinski:
At a meeting with the NRC Staff on July 17<
1985< additional plant specific information was presented which supports our proposed Technical Specification change for the heatup and cooldown limits dated December 8< 1982.
The additional informa-tion was in response to questions regarding the period of time (neutron fluence level) for which the proposed curves would remain valid.
Attached is the fluence vs. operating time curve that was presented.
Data is shown for the location of maximum fluence at the vessel inner radius (OT) as well as at the 1/4T position.
Also depicted are fluence vs.
time curves for surveillance capsules located at azimuthal locations of 13 and 23 relative to 0
0 the reactor core cardinal axes.
In regard to the attached figure> the solid portion of each curve represents plant-specific data through cycle 14 taken from a prior transmittal dated August 8< 1984.
The dashed portion of each curve represents a projection beyond cycle 14 to end of design life (32 EFPY).
These projections assume continued low leakage fuel management and are based on neutron flux levels equal to the linear average of those calculated for cycles 13 and 14.
In particular<
the following neutron flux levels were used for projection beyond 10.4 effective full power years.
13 capsule 9.46 x 10 n/cm -sec 10 2
23 capsule 0
6.25 x 10 n/cm -sec 10 2
vessel OT vessel 1/4T 3.08 x 10 n/cm -sec 2
2.03 x 10 n/cm -sec ( 8508230177 850819 PDR ADOCK 05000244 P
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ROCHESTER GAS AND ELECTRIC CORP.
August 19, 1985 Mr. John A. Zwolinski SHEET NO.
made:
Based on these projectionsi the following observations can be 1.
The 1/4T vessel location is estimated to reach an exposure level of 1.5 x 10 after 20.5 effective full power years of 19 operation.
2.
The estimated end of life fast neutron (E
> 1.0 MeV) exposure of the R.E. Ginna reactor vessel (OT) is 3.38 x 10 n/cm 19 2
3.
To simulate end of life conditionsi a surveillance capsule should be withdrawn from the 23 position after 15.4 effective full power years of operation.
Howeveri extension of the withdrawal time to 17 effective full power years would 19 2
increase the capsule exposure to only 3.70 x 10 n/cm approximately 10% greater than vessel EOI fluence.
Xt is anticipated that future fuel management practices will be consistent with those assumed for projections beyond Cycle 14.
The conclusions noted above support the capsule withdrawal schedule in the proposed Technical Specification.
V y truly yoursi R
er W. Kober
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