B18734, Day Reporting of Changes to & Errors in Emergency Core Cooling System Models or Applications

From kanterella
(Redirected from ML022680036)
Jump to navigation Jump to search
Day Reporting of Changes to & Errors in Emergency Core Cooling System Models or Applications
ML022680036
Person / Time
Site: Millstone Dominion icon.png
Issue date: 09/05/2002
From: Price J
Dominion Nuclear Connecticut
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
B18734
Download: ML022680036 (3)


Text

Dominion Nuclear Connecticut, Inc.

Millstone Power Station Rope Ferry Road Waterford, CT 06385 Dominion SEP 5 2002 Docket No. 50-336 B18734 RE: 10 CFR 50.46(a)

U.S. Nuclear Regulator' Comnmission Attention: Document ControlDesk Washington, D(

20555

- Millstone Power Station, Unit No.'2 30 Day Relorting of'Changes to and Errors in Eme¢g.nc*

Core Cooling System Models or Applications In accordance with 10 CFR 50.46!*(3)(i), Dominion Nuclear Connecticut, Inc. (DNC) hereby submits summaries of a dharge to aind an error in the Millstone Unit No. 2 Emergency Core Cooling System (ECCS) evaluation model of the small break loss of coolant accident (SBLOCA). This information is required to be submitted within 30 days of identifying changes or errors in the ECCS models or applications that result in a greater than 50OF change in the calculated peak cladding temperature (PCT).

In January 2002, the SBLOCA for Millstone Unit No. 2 was reanalyzed by Framatome ANP (FRA-ANP) using the approved S-RELAP5 based methodology. The Analysis of Record SBLOCA PCT was calculated to be 1941°F. In a notification dated August 16, 2002, FRA-ANP identified an error in the decay heat model which overpredicted the decay heat. The SBLOCA Analysis of Record was performed using the built-in decay heat model in S-RELAP5. During the timeframe the SBLOCA PCT is predicted to occur, the S-RELAP5 built-in decay heat model is overly conservative with respect to the model required by 10 CFR 50 Appendix K. Removal of the more conservative estimation of decay heat has resulted in a 133 0F reduction in PCT to 18080F.

FRA-ANP also provided an assessment of a revision to the SBLOCA Guideline in the August 16, 2002, notification. This guideline revision included more detailed modeling of the cold legs and steam generators to be consistent with the non-LOCA and realistic LOCA models. Assessment of this change in the evaluation model resulted in a 660F increase in PCT relative to the previous guideline revision.

However, since this 66OF increase has already been incorporated into the current Millstone Unit No. 2 SBLOCA Analysis of Record (PCT = 1941OF), there is no change in the calculated PCT.

A0 q11f5 A4/

1O 2

01

U.S. Nuclear Regulatory Commission B18734/Page 2 summarizes the FRA-ANP modifications in the ECCS model applicable to Millstone Unit No. 2. The corrected PCT for the limiting SBLOCA remains below the 2200°F limit specified by 10 CFR 50.46(b)(1).

This information satisfies the 30-day reporting requirements of 10 CFR 50.46(a)(3)(ii). In addition, no reanalysis or other actions are necessary as a result of the error identified.

There are no regulatory commitments contained within this letter.

If you have any additional questions concerning this submittal, please contact Mr. David W. Dodson at (860) 447-1791, extension 2346.

Very truly yours, DOMINION NUCLEAR CONNECTICUT, INC.

Site ce President - Millstone Attachments (1) cc:

H. J. Miller, Region I Administrator R. B. Ennis, NRC Senior Project Manager, Millstone Unit No. 2 NRC Senior Resident Inspector, Millstone Unit No. 2

  • 1 U.S. Nuclear Regulatory Commission B18734/Attachment 1/Page 1 Plant Name:

Utility Name:

10 CFR 50.46 Margin Utilization "Small Break LOCA Millstone Unit No. 2 Dominion Nuclear Connecticut, Inc.

Analysis Information EM:

PWR Small Break LOCA, Limiting Break Size:

0.08 ft2 S-RELAP5 Based Analysis Date:

01/02 Vendor:

Framatome ANP Peak Linear Power:15.1 kW/ft Notes:

None Clad Temp (OF)

Notes LICENSING BASIS Analysis of Record PCT 1941 (1)

MARGIN ALLOCATIONS (Delta PCT)

A.

Prior Permanent ECCS Model Assessments

1.

None 0

B.

Planned Plant Change Evaluations

1.

None 0

C.

2002 Permanent ECCS Model Assessments

1.

Decay Heat Model Error

-133

2.

Revised SBLOCA Guideline 0

(2)

D.

Temporary ECCS Model Issues

1.

None 0

E.

Other Margin Allocations

1.

None 0

LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT =

1808 NOTES:

(1)

New Analysis of Record using S-RELAP5 based methodology.

(2)

Assessment of this change resulted in a APCT = +66 0F. FRA-ANP provided this assessment for information.

The +66 0F assessment does not apply since the current Analysis of Record incorporates the revised SBLOCA guideline.