ML20113D536

Application for Amend to Licenses DPR-71 & DPR-62,revising Tech Specs to Increase Number of Fuel Bundles Loaded Around Source Range Monitor During Refueling Operations.Fee Paid

ML20113D536
Person / Time
Site:	Brunswick
Issue date:	04/09/1985
From:	Cutter A CAROLINA POWER & LIGHT CO.
To:	Vassallo D Office of Nuclear Reactor Regulation
Shared Package
ML20113D539	List: ML20113D536 ML20113D549
References
NLS-85-114, NUDOCS 8504150349
Download: ML20113D536 (2)

Text

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d CD&L SERIAL: NLS-85-i l4 Carolina Power * '.lght Company

~APR 0 9 385 Director of Nuclear Reactor Regulation Attention:

Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMEni REFUELING OPERATIONS

SUMMARY

In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, Carolina Power & Light Company (CP&L) hereby requests a revision to the Technical Specifications (TS) for the Brunswick Steam Electric Plant, Unit Nos. I and 2. The proposed TS change to Section 3/4.9.2 will increase the number of fuel bundles that may be loaded around each source range monitor (SRM) during refueling operations.

DISCUSSION The current Brunswick-1 and 2 TS permit loading of up to two fuel bundles around each SRM before a minimum count rate of three counts per second (cps) is required. The proposed amendment would permit four fuel bundles to be loaded around each SRM if needed in order to obtain the required minimum count rate 3 cps.

Under the revised procedure, refueling would begin by loading two exposed fuel bundles around each SRM and then verifying at least 3 cps on the SRM. These bundles would be those scheduled to occupy those locations during the next fuel cycle. If an acceptable e

oEE count rate is then observed, spiral loading of the core would proceed as usual. If 08A insufficient counts are observed, additional high exposure fuel bundles would be inserted oo to complete the 2 x 2 array around each SRM. These fuel bundles would normally not be

' loaded in these locations for the next fuel cycle and would be inserted only to assist in the SRM instrumentation check.

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$g If at this point the minimum 3 cps is not obtained, refueling would be halted until the operability of the SRM instrumentation is verified. If the required count rate is obtained, then spiral loading would proceed. When the spiral loading is complete, the e

extra bundles will be moved to their proper locations and replaced with fuel bundles

LL assigned to the SRM adjacent positions.

Q w c% LL # %8H27 p@.00 m rayett.w ne street

• P. o. Box 1551

• Raleigh. N C. 27602 i[i

Mr. D. B. Vassallo

. P: git 2 -

SIGNIFICANT HAZARDS ANALYSIS-h~

General Electric has performed fuel reactivity (k-effective) calculations which i

demonstrate that any four GE fuel bundles arranged in a square (2 x 2) array, with a 4

- minimum of 12 inches between them and any surrounding bundles, at their maximum reactivity exposure, and in an uncontrolled state, will have a k-effective of less than

- 0.95. Thus,' loading any combinction of four GE fuel bundles around each SRM does not constitute a safety concern since inadvertent criticality with four bundles is not possible. For these reasons, Carolina Power & Light Company believes that operation of

- the facility in accordance with the proposed amendment does not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) created the possibility of a new or different kind of accident from any 4

accident previously evaluated; or (3) involve a significant reduction in a margin of f

safety. As such, this revision does not in :olve a significant hazards consideration.

ADMINISTRATIVE INFORMATION The proposed Brunswick-1 and Brunswick-2 TS pages, along with a summary list of changes made to each page, are included in F.nclosures 1 and 2 respectively. In order to facilitate reloading operations for the current Brunswick-1 refueling outage, issuance of this amendment is required by August 6,1985. A similar request has been granted for Georgia Power Company in Amendment No. 39 to the Hatch Unit No. 2 Technical Specifications.

Carolina Power & Light Company has evaluated this request in accordance with the 1

provisions of 10 CFR 170.12 and determined that a license amendment application fee is required. A check for $150.00 is enclosed in payment of this fee.

Should you have any questions concerning this submittal, please contact Mr. Sherwood R.

Zim. merman at (919) 836-6242.

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Yours very truly

' /r W A. B. Cutter - Vigce r sident Nuclear Engineering & Licensing MAT /crs (1348 MAT)

I Enclosure cc:-

Mr. L. W. Garner (NRC-BNP)

Dr. 3. Nelson Grace (NRC-RII) j Mr. M. Grotenhuis ' (NRC)

A. B. Cutter, having been first duly sworn, did depose and say that the information f

contairied herein is true and correct to tne best of his information, knowledge and belief; and the sources of his information are officers, employees, contractors, and agents o,,,,,,,,,,*

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Carolina Power & Light Company.

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