ML20206P740

Proposed Tech Specs,Revising SLMCPR to Support Operation with GE-12 with 10x10 Pin Array

ML20206P740
Person / Time
Site:	Duane Arnold
Issue date:	05/10/1999
From:	IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
Shared Package
ML20206P730	List: ML20206P740 NG-99-0678, Application for Amend to License DPR-49,revising SLMCPR to Support Operation with GE-12 Fuel with 10x10 Pin Array
References
NUDOCS 9905180298
Download: ML20206P740 (5)

Text

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i TSCR-021 to NG-99-0678 Page1of1 PROPOSED CHANGE TSCR-021 TO THE DUANE ARNOLD ENERGY CENTER TECHNICAL SPECIFICATIONS The holders oflicense DPR-49 for the Duane Arnold Energy Center propose to amend the Technical Specifications by deleting the referenced page and replacing it with the enclosed new page.

SUMMARY

OF CHANGES:

Page Description of Chances 2.0-1 Revises 2.1.1.2 to revise the MCPR Safety Limits for two recirculation loop operation and single recirculation loop operation to support plant operation with GE-12 fuel with a 10x10 pin array.

9905180298 990510 PDR ADOCK 05000331 P

PDR

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SLs 2.0

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2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 Fuel Cladding Integrity - With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:

THERMAL POWER shall be s 25% RTP.

I 2.1.1.2 MCPR - With the reactor steam dome pressure a 785 psig and core flow a 10% rated core fl l,( b MCPR sh 1 be a 7 for two recirculation loop operation I

or a

.08 for sing e recirculation loop operation.

2.1.1.3 Reactor Vessel Water Level - Reactor vessel water level shall be greater than 15 inches above the top of active irradiated fuel.

2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be s 1335 psig.

2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

2.2.1 Restore compliance with all SLs: and l

2.2.2 Fully insert all insertable control rods.

l DAEC 2.0-1 Amendment 223

l TSCR-021 to i

NG-99-0678 Page1ofI SAFETY ASSESSMENT By letter dated May 10,1999, IES Utilities Inc. submitted a request for revision of the Technical Specifications for the Duane Arnold Energy Center (DAEC). The proposed amendment revises the Safety Limit Minimum Critical Power Ratio (SLMCPR). This change will support operation with a new fuel design, GE-12 with a 10x10 pin array, beginning with Cycle 17.

Evaluation:

The Updated Final Safety Analysis Report (UFSAR) Safety Design Bases,(Section 4.4, Thermal-Hydraulic Design) states that the thermal-hydraulic design of the core shall establish the safety limits for use in evaluating the safety margin relating the consequences of fuel barrier failure to public safety.

As discussed in the Technical Specification 2.1.1.2 BASES, the fuel cladding integrity Safety Limit (SL) is set such that no significant fuel damage is calculated to occur if the limit is not violated. The fuel cladding integrity SL is defined as the critical power ratio in the limiting fuel assembly for which more than 99.9% of the fuel rods in the core are expected to avoid transition boiling, considering the power distribution within the core and all uncertainties. This is consistent with Section 4.4 of the Standard Review Plan, NUREG 0800.

During Single Loop Operation (SLO), the SLMCPR must be increased by.01 to account for the increased uncertainty in the core flow and Traversing In-Core Probe readings.

General Electric letter TGR:99-004 provides the SLMCPR to support operation with GE-12 fuel. Se calculations, which consider the impact on SLMCPR of the combined GE-12 and GE-10 core, show that an increase in SLMCPR is necessary. All applicable conditions of the cycle specific SLMCPR process and method as specified in the NRC's approval of Amendment 25 to GESTAR-II have been satisfied.

The fuel to be used in the reactor at the start of Cycle 17 is comprised of the following:

120 bundles of GE-10 (8x8) burned one cycle 120 bundles of GE-10 (8x8) burned two cycles e

48 new bundles of GE-12 (10x10) Design GE12-P10DSB370-14GZ-100T-150-T e

80 new bundles of GE-12 (10x10) Design GE12-P10DSB371-120Z-100T-150-T These new bundle designs comply with the NRC's requirements in their approval of Amendment 22 to GESTAR-II.

Therefore, we have concluded that the proposed revision to the DAEC Technical Specifications is acceptable.

1

TSCR-021 to NG-99-0678 Page1ofI ENVIRONMENTAL CONSIDERATION 10 CFR Section 51.22(c)(9) identifies certain licensing and regulatory actions which are eligible for categorical exclusion from the requirement to perform an environmental assessment. A proposed amendment to an operating license for a facility requires no environmental assessment if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant hazards consideration; (2) result in a 1

significant change in the types or significant increase in the amounts of any effluents that may be released offsite; and (3) result in a significant increase in individual or cumulative occupational radiation exposure. IES Utilities Inc. has reviewed this request and determined that the proposed amendment meets the eligibility criteria fbr categorical exclusion set forth in 10 CFR Section 51.22(c)(9). Pursuant to 10 CFR Section 51.22(b),

no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the amendment. The basis for this determination follows:

Basis The change meets the eligibility criteria for categorical exclusion set forth in 10 CFR Section 51.22(c)(9) for the following reasons:

1.

As demonstrated in Attachment I to this letter, the proposed amendment does not involve a significant hazards consideration.

2.

There is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite. The way in which the fuel assemblies will be operated is not being changed by this revision to the Safety Limit Minimum Critical Power Ratio (SLMCPR). The SLMCPR values are designed to ensure that fuel damage from transition boiling does not occur in at least 99.9% of the fuel rods as a result of the limiting postulated accident and there are no new accidents being introduced.

3.

There is no significant increase in individual or cumulative occupational radiation exposure. The SLMCPR values are designed to ensure that fuel damage from transition boiling does not occur in at least 99.9% of the fuel rods as a result of the limiting postulated accident and there are no new accidents being introduced.

i There are no changes in reactor operation that would increase the dose rate.

{m o

.- v GENuclearEn:rgy Tammy G. Ranson Nuclear fuelProduct Management ivelProject Manager GeneralElectnc Company Cast'. Heyne Roact. P.0 Box 180. MIC A33 Wilmington, NC 284010780 910675 5752, DC 8*292 5752. fax 910 675 5684 Pager 888 325-7G74. Tammy Reason @ gene ge com April 12,1999 cc: R. D. Ballou TGR:99-004 T. A. Evans G. N. Marrotte D. J. Mienke R. A. Rossi Mr. M. Brandt Alliant - IES Utilities Inc.

Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324

Subject:

Safety Limit Based on Reference Fuel Cycle 403R58

Dear Matt:

Safety Limit MCPR (SLMCPR) calculations have been verified and documented in DRF J11-03266, Volume 7, for the Duane Arnold Cycle 17 loading pattern used in the release fuel cycle, FMS 403R58. These calculations, which consider the impact on SLMCPR of the combined GE12 and GE10 core, show that an increase in SLMCPR is necessary to support operation of Cycle 17.

Specifically, this analysis determined that the dual loop SLMCPR is 1.09 and the single loop SLMCPR is 1.10. Changes that could occur to the loading pattern during the upcoming licensing analysis have the potential to cause these results to increase (although increase beyond 0.01 are considered unlikely).

Use of the GE12 fuel design has been analyzed by GE. All applicable conditions of the NRC's approval of the cycle specific SLMCPR process and the associated method as specified in the NRC SER Letter, Frank Akstulewicz (NRC) to Glen A. Watford (GE), " Acceptance for Referencing of Licensing Topical Reports NEDC-32601P, Afethodology and Uncertaintiesfor Safety Limit AfCPR Evaluations; NEDC-32694P, Power Distribution Uncertaintiesfor Safety Limit AfCPR Evaluation; and Amendment 25 to NEDE-24011-P-A on Cycle Specific Safety Limit AfCPR (TAC Nos. M97490, M99069 and M97491), March 11,1999 have been satisfied.

Best reg

/

T. G. Reason