NL-02-057, Annual 10 CFR 50.46 Report

Annual 10 CFR 50.46 Report

ML021160005
Person / Time
Site:	Indian Point
Issue date:	04/24/2002
From:	Dacimo F Entergy Nuclear Northeast
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-02-057
Download: ML021160005 (6)

Text

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

Indian Point Energy Center

'--te 295 Broadway, Suite 1 P.O. Box 249 Buchanan, NY 10511-0249 April 24, 2002 Re: Indian Point Unit No. 2 Docket No. 50-247 NL 02-057 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, D.C. 20555-0001

Subject:

Annual 10 CFR 50.46 Report for Indian Point Unit 2

Dear Sir:

Pursuant to 10 CFR 50.46(a)(3)(ii), Entergy Nuclear Operations, Inc. (ENO) hereby submits the annual reports (attached) pertaining to the emergency core cooling system (ECCS) evaluation models which affect peak cladding temperature (PCT) for the limiting transients at Indian Point Unit 2 (IP-2).

ENO's vendor for performing the large and small break loss of coolant accident (LOCA) analyses, Westinghouse Electric Company, has reviewed the year 2001 analyses for IP-2 and has advised ENO of the changes which have been made to the ECCS evaluation models. The values provided in these reports are the result of plant specific evaluations and sensitivity studies and demonstrate that the current PCT penalty and peak cladding temperatures are within acceptable limits. The current large break LOCA peak cladding temperature (PCT) is 2188F, and the current small break LOCA PCT is 2116F. These values remain unchanged from previously reported values. Because of changes to 10 CFR 50.59 reporting requirements, minor title revisions were made to Sections B and C in the reports.

No new regulatory commitments are made by ENO in this correspondence.

Should you or your staff have any concerns regarding this matter, please contact Mr. John F.

McCann, Manager, Nuclear Safety and Licensing, at (914) 734-5074.

Fred Dacimo Vice President - Operations Indian Point 2 Attachments

C: Mr. Patrick D. Milano Senior Project Manager - Project Directorate I-1 Division of Licensing Project Management U.S. Nuclear Regulatory Commission Mail Stop O-8-2C Washington, DC 20555-0001 Mr. Hubert J. Miller Regional Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector U.S. Nuclear Regulatory Commission Indian Point Unit 2 P.O. Box 38 Buchanan, NY 10511

ATTACHMENT 1 10 CFR 50.46 Report Best Estimate Large Break Loss of Coolant Accident Entergy Nuclear Operations, Inc.

Indian Point Unit No. 2 Docket No. 50-247

NL 02- 057 Attachment 1 Page 1 of 1 Westinghouse LOCA Peak Clad Temperature Summary For Best Estimate Large Break Clad Temp ('F)

LICENSING BASIS Analysis-Of-Record PCT 2152 MARGIN ALLOCATIONS (Delta PCT)

A. PRIOR PERMANENT ECCS MODEL ASSESSMENTS

1. Total- previously reported 28 B. PLANNED PLANT CHANGE EVALUATIONS

1. Missing Fuel Assembly Alignment Pin 5

2. Reduced Power in Peripheral Assemblies 4

3. Replacement Steam Generators (44 to 44F) 7

4. Changes to Containment Pressure Calculation Assumptions 11

5. Reduction in F delta H from 1.72 to 1.7 -8

6. Reduction in SGTP from 25% to 20% -15 C. CURRENT YEAR PERMANENT ECCS MODEL ASSESSMENTS (Permanent Assessments of PCT Margin)

1. None 0 D. TEMPORARY ECCS MODEL ISSUES

1. None 0 E. OTHER

1. Increase in Maximum Accumulator Pressure 4 LICENSING BASIS PCT + MARGIN ALLOCATIONS 2188

ATTACHMENT 2 10 CFR 50.46 Report Small Break Loss of Coolant Accident Entergy Nuclear Operations, Inc.

Indian Point Unit No. 2 Docket No. 50-247

NL 02- 057 Attachment 2 Page 1 of 1 Westinghouse LOCA Peak Clad Temperature Summary For Small Break Clad Temp (fF)

LICENSING BASIS Analysis-Of-Record PCT 1766 MARGIN ALLOCATIONS (Delta PCT)

A. PRIOR PERMANENT ECCS MODEL ASSESSMENTS

1. Total - Previously reported 25 B. PLANNED PLANT CHANGE EVALUATIONS

1. Previously reported 136 C. CURRENT YEAR PERMANENT ECCS MODEL ASSESSMENTS (Permanent Assessments of PCT Margin)

1. None 0 D. TEMPORARY ECCS MODEL ISSUES

1. None 0 E. OTHER

1. Tavg Uncertainty- Previously reported 5

2. Burst and Blockage/Time in Life - Previously reported 184 LICENSING BASIS PCT + MARGIN ALLOCATIONS 2116