ML060610071

Sixth Supplemental Letter Regarding License Amendment Application to Support Mark B-HTP Fuel Design for Cycle 15

ML060610071
Person / Time
Site:	Davis Besse
Issue date:	02/28/2006
From:	Bezilla M FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
3241, LAR 05-0002, TAC MC6888
Download: ML060610071 (5)

Text

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,ENOC vO 5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449 Mark B. Bezlla 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 Docket Number 50-346 10 CFR 50.90 License Number NPF-3 Serial Number 3241 February 28, 2006 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001

Subject:

Davis-Besse Nuclear Power Station Sixth Supplemental Letter Regarding License Amendment Application to Support Mark B-HTP Fuel Design for Cycle 15 (License Amendment Request (LAR) 05-0002; TAC No. MC6888)

Ladies and Gentlemen:

By letter dated May 2, 2005 (Serial Number 3131), as supplemented on August 28, 2005 (Serial Number 3166), September 15, 2005 (Serial Number 3183), January 12, 2006 (Serial Number 3213), January 13, 2006 (Serial Number 3214), and February 9, 2006 (Serial Number 3226), the FirstEnergy Nuclear Operating Company (FENOC) submitted License Amendment Request (LAR) 05-0002, an application for amendment of the Operating License, Appendix A, Technical Specifications (TS) for the Davis-Besse Nuclear Power Station (DBNPS). The proposed amendment would revise TS Section 2.1.1, "Safety Limits - Reactor Core," and TS Section 2.2.1, "Limiting Safety System Settings - Reactor Protection System Setpoints" to support use of the Framatome Mark B-HTP Fuel design for Cycle 15, which is scheduled to begin following refueling in March 2006.

As a result of recent discussions with the NRC staff, this letter provides a sixth supplement to the license amendment application, revising the proposed Table 4.3-1 footnote. Enclosure 1 contains the retyped TS page incorporating this change. The previously submitted evaluation for LAR 05-0002 is unaffected, including the technical analysis, no significant hazards consideration, and environmental consideration.

Docket Number 50-346 License Number NPF-3 Serial Number 3241 Page 2 , Commitment List, identifies that there are no commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Gregory A. Dunn, Manager - FENOC Fleet Licensing, at (330) 315-7243.

The statements contained in this submittal, including its associated enclosures are true and correct to the best of my knowledge and belief. I am authorized by the FirstEnergy Nuclear Operating Company to make this submittal. I declare under penalty of perjury that the foregoing is true and correct.

Executed on: lb (,>2OOX By: ,67 Mark A. Bezilla, Vice Presi ent-Nuclear MSH Enclosures cc: Regional Administrator, NRC Region III Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)

NRC/NRR Project Manager NRC Senior Resident Inspector Utility Radiological Safety Board

Docket Number 50-346 License Number NPF-3 Serial Number 3241 Page 1 of 2 REVISED PROPOSED RETYPED TECHNICAL SPECIFICATION PAGE 3/4 3-8 (TABLE 4.3-1)

(one page follows)

TABLE 4.3-1 (Continued)

Notation (1) - If not performed in previous 7 days.

(2) - Heat balance only, above 15% of RATED THERMAL POWER.

(3) - When THERMAL POWER [TP] is above 50% of RATED THERMAL POWER [RTP],

and at a steady state, compare out-of-core measured AXIAL POWER IMBALANCE

[APIO] to incore measured AXIAL POWER IMBALANCE [API1] as follows:

RTP [APIO - APIJ1 = Offset Error TP Recalibrate if the absolute value of the Offset Error is > 2.5%

(4) - AXIAL POWER IMBALANCE and loop flow indications only.

(5) - CHANNEL TFUNCTIONAL TEST is not applicable. Verify at least one decade overlap prior to each reactor startup if not verified in previous 7 days.

(6) - Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7) - Flow rate measurement sensors may be excluded from CHANNEL CALIBRATION.

However, each flow measurement sensor shall be calibrated at least once each REFUELING INTERVAL.

(8) - The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of both the undervoltage and shunt trip devices of the Reactor Trip Breakers.

(9) - Performed on a STAGGERED TEST BASIS.

(10) - If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found acceptance criteria band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. Ifthe as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the Limiting Trip Setpoint,. or a value that is more conservative than the Limiting Trip Setpoint; otherwise, the channel shall be declared inoperable. The Limiting Trip Setpoint and the methodology used to determine the Limiting Trip Setpoint, the predefined as-found acceptance criteria band, and the as-left setpoint tolerance band are specified in a document incorporated by reference into the Updated Safety Analysis Report.

• - With any control rod drive trip breaker closed.

• • - When Shutdown Bypass is actuated.

DAVIS-BESSE, UNIT 1 3/4 3-8 Amendment No. 43, 108, 123, 135, 185, 218,

Docket Number 50-346 License Number NPF-3 Serial Number 3241 Page 1 of 1 COMMITMENT LIST The following list identifies those actions committed to by the Davis-Besse Nuclear Power Station, Unit Number 1, (DBNPS) in this document. Any other actions discussed in the submittal represent intended or planned actions by the DBNPS. They are described only for information and are not regulatory commitments. Please notify Gregory A. Dunn, Manager -

Fleet Licensing (330-315-7243) of any questions regarding this document or associated regulatory commitments.