BSEP-96-0390, Application for Amend to License DPR-71,revising Minimum Critical Power Ratio Safety Limit Ref in TS 2.1.2 from 1.07 to 1.10 for Unit 1 Cycle 11 Operation & Revises TS 5.3.1 to Reflect New Fuel Type Being Added to Unit 1 Reactor Core
| ML20129F518 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/16/1996 |
| From: | Campbell W CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20129F523 | List: |
| References | |
| BSEP-96-0390, BSEP-96-390, TAC-M95263, NUDOCS 9610290152 | |
| Download: ML20129F518 (5) | |
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C_P &. _L Carolina Power & Light Company William R. Campbell PO Box 10429 Vice President Southport NC 28461-o429 Brunswick Nuclear Plant October 16,1996 SERIAL: BSEP 96-0390 10 CFR 50.90 TSC 95TSB32 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO.1 DOCKET NOS. 50-325/ LICENSE NOS. DPR-71 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT FUEL CYCLE 11 RELOAD LICENSING (NRC TAC NO. M95263)
Gentlemen:
By letters dated April 8,1996 (Serial: BSEP 96-0061) and July 30,1996 (Serial: BSEP 96-0271),
Carolina Power & Light Company submitted a license amendment request for revisions to the Technical Specifications for the Brunswick Steam Electric Plant (BSEP), Unit No.1. The proposed license amendment revises the Minimum Critical Power Ratio (MCPR) Safety Limit referenced in Technical Specification 2.1.2 from 1.07 to 1.10 for Unit 1 Cycle 11 operation and revises Technical Specification 5.3.1 to reflect the new fuel type (GE13) being added to the Unit 1 reactor core beginning with Cycle 11 operation. In addition, the proposed license amendment revises the acceptable range of sodium pentaborate concentration for the standby liquid control system to reflect changes to poison material concentration needed to achieve reactor shutdown based on the planned use of the new GE13 fuel type. Subsequently, by letters dated October 4,1996 (BSEP 96-0366) and October 8,1996 (BSEP 96-0376), CP&L responded to NRC requests for additional information regarding the proposed license amendment.
During telephone discussions on October 15,1996, the NRC staff noted that because the proposed safety limit MCPR value of 1.10 for Brunswick 1 Cycle 11 operation is based on an NRC-approved methodology that uses cycle-specific input parameters, the proposed safety limit MCPR value should be restricted to use only during Brunswick 1 Cycle 11. To accommodate the NRC staff, CP&L is providing the enclosed revision to the proposed license amendment. The Company proposes to add a footnote to the safety limit MCPR value of 1.10 in Technical Specification 2.1.2 and its associated ACTION statement that indicates the stated MCPR values are applicable only for Unit 1 Cycle 11 operation. In addition, CP&L proposes to add a reference in Technical Specification 6.9.3.2 to the NRC Safety Evaluation approving this proposed license amendment. Adding this reference will document NRC acceptance of the General Electric methods used for determination of the Unit 1 Cycle 11 safety limit MCPR value, including the use of NEDC-32505P, "R-Factor Calculation Method for GE11, GE12, and GE13 Fuel, Tg /, f November 1995."
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9610290152 961016 0
PDR ADOCK 05000325 4-P, PDR Tel 910 457 2496 Fox 910 457 2803 i
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t Document Control Desk BSEP 96-0390 / Page 2 Carolina Power & Light Company has reviewed the proposed license amendment request, as revised by the footnote restricting applicability of the safety limit MCPR value to only Unit 1 Cycle 11 operation and as revised by the addition of the NRC Safety Evaluation reference in Specification 6.9.3.2, and has determined that adoption of the proposed license amendment does not impact the conclusions of the no significant hazards notice published in the Federal Register on August 14,1996 (61 FR 42276). This conclusion is based on the fact the proposed footnote restricts the use of the 1.10 safety limit MCPR value to an operational period less than originally evaluated through the 10 CFR 50.92 evaluation (e.g., to only Unit 1 Cycle 11 operation rather than for an indefinite period of time). This conclusion is also based on the fact that adding a reference in Specification 6.9.3.2 to the NRC Safety Evaluation approving this license amendment request is an administrative change that provides additional documentation of the methods found acceptable to the NRC staff in approving this license amendment request.
Carolina Power & Light Company has concluded that the proposed license amendment meets the eligibility requirements for categorical exclusion set forth in 10 CFR 51.22(c)(9); therefore, the proposed license amendment does not require the preparation of an environmental assessment.
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' provides the revised page change instructions for incorporating the proposed revisions. provides the revised typed Technical Specification pages for Unit 1. provides the revised marked-up Technical Specification pages for Unit 1.
Carolina Power & Light Company is providing, in accordance with 10 CFR 50.91(b), Mr. Dayne H.
Brown of the State of North Carolina with a copy of the proposed license amendments.
As previously discussed with the NRR Project Manager, Unit 1 core reloading operations are expected to commence by October 22,1996. Since NRC approval and issuance of this proposed license amendment is needed to allow core reloading operations to commence, and in order to allow time for procedure revision and orderly incorporation into copies of the Technical Specifications, CP&L requests that the proposed license amendment be issued no later than the close of business on Friday, October 18,1996.
Please refer any questions regarding this submittal to Mr. Mark A. Turkal at (910) 457-3066.
Sincerely, William R. Campbell WRM/wrm
1 Document Control Desk BSEP 96-0390 / Page 3
Enclosures:
1.
Revised Page Change Instructions 2.
Typed Technical Specification Pages - Unit 1 3.
Marked-up Technical Specification Pages - Unit 1 William R. Campbell, having been first duly sworn, did depose and say that the infonnation contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, and agents of Carolina Power & Light
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U. S. Nuclear Regulatory Commission ATTN.: Mr. Stewart D. Ebneter, Regional Administrator 101 Marietta Street, N.W., Suite 2900 Atlanta, GA 30323-0199 Mr. C. A. Patterson NRC Senior Resident Inspector - Brunswick Units 1 and 2:
l U.S. Nuclear Regulatory Commission ATTN.: Mr. David C. Trimble, Jr. (Mail Stop OWFN 14H22) 11555 Rockville Pike Rockville, MD 20852-2738 The Honorable H. Wells Chairman - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510 Mr. Dayne H. Brown Director-Division of Radiation Protection North Carolina Department of Environment, Health, and Natural Resources P.O. Box 27687 Raleigh, NC 27611-7687
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ENCLOSURE 1 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO.1 NRC DOCKET NO. 50-325 4
OPERATING LICENSE NO. DPR-71 REQUEST FOR LICENSE AMENDMENT FUEL CYCLE 11 RELOAD LICENSING (NRC TAC NO. M95263) 4 j
PAGE CHANGE INSTRUCTIONS UNIT 1 l
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3/4 1-20 3/4 1-20 5-1 5-1 6-23 6-23 6-23a
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ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO.1 NRC DOCKET NO. 50-325 OPERATING LICENSE NO. DPR-71 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT FUEL CYCLE 11 RELOAD LICENSING (NRC TAC NO. M95263)
TYPED TEQbNICAL SPECIFICATION PAGES - UNIT 1 e,
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