ML19291C429
| ML19291C429 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/15/1980 |
| From: | Trimble D ARKANSAS POWER & LIGHT CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| 1-010-15, 1-10-15, NUDOCS 8001240413 | |
| Download: ML19291C429 (3) | |
Text
i ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK. ARKANSAS 72203 (501) 3714000 January 15, 1980 1-010-15 Director of Nuclear Reactor Regulation ATTN:
Mr. R. W. Reid, Chief Operating Reactors Branch #4 U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Subject:
Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 Reactor Vessel Surveillance Program (File:
0520.2, 1510)
Gentlemen:
Arkansas Power & Light Company is participating in the B&W integrated reactor vessel surveillance program (IRVSP) with Toledo Edison Company's Davis Besse Unit 1 (D.B.-1) serving as the host reactor.
The Technical Specifications of ANO-1 require the submittal of a report or an application for license amendment to the hTC any time (beginning one year after D.B.-l's attainment of commercial operation at 100% power) Davis Besse 1 fails to maintain a cummulative reactor utilization factor of greater than 65%. D.B.-1
' achieved 100% power on July 31, 1978.
One year later, D.B.-1 had failed to maintain a cummulative reactor utilization factor of greater than 65%. The objective of this report is to address the justification for the continued operation of ANO-1 with regard to the relatively low D.B.-1 cummulative reactor utilization factor.
Since the restart of D.B.-1 following the Three Mile Island incident, D.B.-1 has maintained a cummulative reactor utilization factor considerably higher than the 65% factor specified.
In the months following its restart, the operating history of D.B.-1 is similar to that of ANO-1.
Therefore, to assess the impact of the relatively low reactor utilization factor, one needs only to address the effects of the previous fourteen months of operation.
At the end of the current D.B.-1 fuel cycle a capsule from the RVSP of ANO-1 will be withdrawn and evaluated. Table 1 presents the irradiation history of the capsule and the reactor vessel of ANO-1, assuming a 0.8 reac-tor utilization factor for D.B.-1 and ANO-1 from the time of this report to the end of the current D.B.-1 cycle.
The accumulated neutron fluence of the capsule corresponds to 8.9 EFPY for the k thickness location of the reactor vessel of ANO-1.
At the time of withdrawal and evaluation of this capsule the total accumulated operation of ANO-1 will be 3.5 EFPY.
Obviously, the fluence of the capsule, as well as subsequent capsules, leads the reactor vessel by a sufficient margin to allow the modification of the Technical 1794 137 v1,mree e s19 e_f g
- _ _ eom1
Mr. R. W. Reid January 15, 1980 Specification pressure-temperature limit curves as necessary to account for irradiation induced changes to the material fracture toughness.
This will insure the continued safe operation of the ANO-1 plant.
Very truly yours, b& f.
David C. Trimble Manager, Licensing DCT: ERG:skm Attachment 1794 138
TABLE 1 IRRADIATION DATA FOR RV'S AND CAPSULES FOR IRVSP AT DAVIS BESSE UNIT I IDENTIFICATION ACCUMULATED CORRESPONDING APPROXIMATE OF CAPSULE TO NEUTRON FLUENCE NUMBER OF EFPY ACCUMULATED BE WITIIDRAWN OF CAPSULE FOR REACTOR NUMBER OF EFPY AT END OF VESSEL AT TIIE AT END OF D.B.-1 2
FIRST D.B.-1
- n/cm -
kT LOCATION FIRST CYCLE UNIT CYCLE
- EFPY -
- EFPY -
18 ANO-1 ANI-B 3.3X10 8.9 3.5 18 RS-1 RSI-E 3.3X10 8.9 3.0 18 DB-1 TEI-F 2.3X10 6.3 1.1 w
A wo 4
4