ML20052E283
| ML20052E283 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/04/1982 |
| From: | Howe P CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8205100291 | |
| Download: ML20052E283 (3) | |
Text
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_y' 4'g'C 0 Office of Nuclear Reactor Regulation i
ATTN:
Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2
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United States Nuclear Regulatory Commission Washington, D.C.
20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 INTERPRETATION OF TECHNICAL SPECIFICATIONS Dee Mr. Vassallo:
SUMMARY
l In anticipation of the upcoming refueling operations on Brunswick Unit No. 2, Carolina Power & Light Company (CP&L) reviewed the applicable Technical Specifications (TS) regarding source range monitors (SRMs) and fuel l
loading chambers (FLCs) as set forth in TS 3 9.2 and 4.9.2.
We have discussed
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the interpretation of the TS with NRC as detailed below.
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DISCUSSION During a spiral unload, the core is unloaded by first removing the l
fuel from the outermost control cells (four bundles surrounding a control blade). Unloading continues in a spiral fashion by removing fuel from the l
outermost periphery to the interior of the core, symmetric about the SRMs, except for two diagonal fuel bundles around each of the four SRMs. Our interpretation of the aforementioned TS is that during spiral unloading the SRMs may drop below the TS count rate of three (3) counts per second (eps) when the eight remaining fuel bundles are removed from around the SRMs.
In a telephone conversation on April 30, 1982 with the Brunswick NRC Project Manager, CP&L discussed this interpretation of the current TS.
Agreement was reached that unloading the eight remaining fuel bundles from around the SRMs with the concomitant loss of three (3) cps was acceptable.
This is conservative since a General Electric analysis has demonstrated that sixteen or more uncontrolled fuel assemblies must be loaded together to achieve criticality. As there will be only two diagonal fuel assemblies in each array, with adequate water gap, criticality would be even more unlikely.
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During spiral core reloading, NFC and CP&L also agreed on the interpretation that current TS would allow a count rate below three (3) cps until two diagonally adjacent fuel assemblies are loaded around each SRM. A spiral reload is the reverse of a spiral unload. Except for two diagonal fuel bundles around each of the four SRMs, the fuel in the interior of the core, symmetric to the SRMs, is loaded first.
Should you have any questions regarding this interpretation of Technical Specifications, please contact our staff.
Yours very truly, s
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P. W. Howe Vice President Technical Services MSG /lr (n-46) cc: Messrs. C. Burger (NRC-RII)
L. W. Garner (NRC-BSEP)
C. Julian (NRC-RII)
J. P. O'Reilly (NRC-RII)
J. Van Vliet (NRC) i l
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Office of Nuclear Reactor Regulation 4
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1 Operating Reactors Branch No. 2 AITN:.
i U. S. Nuclear Regulatory Commission Washington, DC 20555
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