ML20204G776

Provides Annual Rept for ECCS Evaluation Model Changes & Errors for 1998 Model Yr That Effect Peak Cladding Temp for Plant IAW 10CFR50.46(a)(3)(ii)

ML20204G776
Person / Time
Site:	Wolf Creek
Issue date:	03/17/1999
From:	Muench R WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ET-99-0013, ET-99-13, NUDOCS 9903260271
Download: ML20204G776 (6)

Text

~ - . - . - - -. .~ . - . .

4 WQLF CREEK NLCLEAR OPERATING CORPORATION RiGwd A. Muench Vice President Enwineering -

g } 7 jggg CT 99-0013

-U. S. Nuclear Regulatory Commission ATTN: Document Control Desk '

Mail Station P1-137 Washington, D. C. 20555

Subject:

_ Docket No. 50-482: 10 CFR 50.46 Annual Report of ECCS Model Changes Gentlemen:

This letter provides the annual report for the Emergency Core Cooling System (ECCS) E/aluation Model changes and errors for the 1998 model year that effect the Peak Cladding Temperature (FCT) for the Wolf Creek Generating Station (WCGS). This letter is provided in accordance with the criteria and reporting i requirements of 10 CFR 50. 4 6 (a) (3) (li) , as clarified in Section 5.1 of WCAP-13451, " Westinghouse Methodology for Implementation of 10 CFR 50.46 Reporting." Regulation 10 CFR 50. 4 6 (a) (3) (ii) states, in part, "For each change to or error discovered in an acceptable ovaluation mode) or in the application of such a model that affects the temperature calculation, the applicant or licensee shall report the nature of the change or error and its estimated effect on the limiting ECCS analysis to the Commission at least annually as . .:pecified in 550.4. If the change or error is significant, the applicant or licensee shall provide this report within 30 days and include with the. report a proposed schedule for providing a reanalysis or taking other action as may be needed to shaw compliance with 550.46 requirements."

Wo1f Creek Nuclen - Operating co rporation (WCNGC) has reviewed the annual 10 CFR 50.46 summary report or ECCS Evaluation Model changes that were implemented by Westinghouse during 1998. The report (Westinghouse to WCNOC letter m "-99-114 dated March'5, 1999) concludes that there are no reportable Peak Clad Temperature ( PQ't) ihGacts for the NOTRUMP and BASH evaluation model analyses as:.ociated with the WCGS for 1998. )

Attachment 1 provides the calculated Large Bres.k LOCA and Small Break LOCA PCT margin alloc Ti ans in effect for the 1998 WCGS evaluation models. The PCT I values deter

• 1ed in the Smal) Break Md Large Bisak '^OA analyses of record, combined with all the PCT margin allocations, rema.. well below the 10 CFR 50.46 regulatory limit of 2200 degrees Fahrenheit. Therefore, WCGS is in compl!ance. with 550.46 requirements and no reanalysis or any other action is S

'. pl}

l - required.

9903260271 990317 "~

PDR ADOCK 05000402 PDR RO. B ox 411/ Burt ngtxi. KS 6se39 / Phone: (316) 304-8831 An Equa)pysturuty Errpoyer M FHcNET

~ ..

s ET 99-0013 page 2 of 2 I

Attachment 2 provides a summary of actions committed to by WCNOC in this documant.

If you have any questions concerning this matter, please call me at (316) 364-4034, or Mr. Michael J. Angus at (316) 364-4077.

Very truly yours, Ms44 Richard A. Muench RAM /rlr Attachments cc: W. D. Johnson (NRC), w/a E. W. Merschoff (NRC), w/a K. M. Thomas (NRC), w/a Scnior Resident Inspector (NRC), w/a i

l i

i l

i 1

h

Attachment 1 to ET 99-0013 Fage 1 of 3 ATTACHMENT 1 ECCS EVALUATION MODEL PEAK CLAD TEMPERATURE (PCT)

MARGIN ASSESSMENTS i

i i

1 l

l L

r

' Attachment! 1~ to ET 99-0013 Page~2 of 3

'~

• • • SMALL 3REAK PEAK CLAD TEMPERATURE (PCT) MARGIN UTILIZATION ***

,. Evaluation Model: 1985 EM with NOTRUMP Fuel: 17X17 V5H w/IFM, non-IFBA 275 psig Peaki.ng Factor: FO=2.50, EdH=1.65 SG Tube Plugging: 10%

Power Level: 3565 MWth

~ Limiting transient: 3-inch Break A. ANALYSIS OF RECORD (Rerating 8/92)

Peak Cladding Temperature -(PCT) : 1510 F (1)

B. PRIOR PERMANENT ECCS.MODEL ASSESSMENTS APCT = 31 F (2)

C. 10 CFR 50.59 SAFETY EVALUATIONS

1. Loose Parts APCT = 45'F (3)

2. Cycle l10 Fuel Assembly Design Changes APCT = 1*F (6)

3. Reduced Feedwater Inlet Temperature APCT = 10*F (4)

4. Fuel Rod Crad APCT = 4'F (5)

TOTAL 10 CFR 50.59 SMALL BREAK ASSESSMENTS APCT = 60*F D. 1998 10 CFR 50.46 MODEL ASSESSMENTS (Permanent Assessment of PCT Margin)

1. None APCT = 0F E. TEMPORARY ECCS MODEL ISSUES

1. None APCT = 0F F. OTHER MARGIN. ALLOCATIONS l'. Cold Leg Streaming Temperature Gradient APCT = 7F (7)

LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT = 1608 F Notes:

1. Westinghouse Topical Report WCAP-33456, " Wolf Creek Generating Station NSSS Rerating Licensing Report,"' October 1992.

'2. Westinghouse to WCNOC letter SAP-98-ll5, " Wolf Creek Nuclear Operating Corporation, Wolf Creek' Generating Station, 10 CFB 50.46 Notification and Reporting for 1997,"

February 27, 1998

3. Westinghouse to WCNOC latter SAP-90-148, " Wolf Creek Nuclear Operating Corporation, RCS Loose Parts Evaluation," April 18, 1990.

4. Westinghouse to WCNOC letter SAP-96-119, " Wolf Creek Nuclear Operating Corporation, Wolf Creek Generating Station, Small Break LOCA Evaluation for Reduced Feedwater Temperature,".May 30, 1996.

5. Westinghouss to WCHOC letter 97 SAP-G-0075, " Wolf Creek Nuclear Operating Corporation, Wolf Creek Generating Station, Wolt Creek Crud Deposition 4Nial Of fset

Anomaly ' Safety Evaluation," September 29, 1997. -(This penalty will be carried until'such time '.t is determined to no longer apply) .

6. Westinghouse to' WCNOC letter 97 SAP-G-0009, " Wolf Creek Nuclear Operating

. Corporation, Wolf Creek Generating Station, Safety Assessment for the Wolf Creek Generating' Station with ZIRLO" Fuel Assemblies," February 7, 1997.

7. Westinghouse to WCNOC letter SAP-93-701, " Wolf Creek Nuclear Operating Corporation, Wolf. Creek Generating Station, 10 CFR 50.46 Notification and Reporting Information," January 25, 1993, i l

, Attachment 1 to ET 99-0013 Page 3 of 3

• • • LARGE BREAK LOCA PEAK CLAD TEMPERATURE (PCT) MARGIN UTILIZATION ***

Eval,uation Model: 1981 EM with BACH Fuel: 17X17 V5H w/IFM, non-IFBA 275 psig Peaking Factor: FO=2.50, EdH' 55 SG Tube Plugging: 10%

Power Level: 3565 MWth Limiting transient: C D=0.4, Min. SI, Reduced Tavg A. ANALYSIS OF RECORD (Rerating 8/92)

Peak Cladding Temperature (PCT): 1916 F (1)

B. PRIOR PERMANENT ECCS MODEL ASSESSMENTS APCT = 0F (2)

C. 10 CFR 50.59 SAFETY EVALUATIONS

1. Loose Parts APCT = 20*F (3)

2. Containment Purge Evaluation APCT = 0*F (4)

3. Cycle 10 Fuel Assembly Design Changes APCT = 95*F (5)

4. Fuel Rod Crud APCT = 0*F (6)

TOTAL 10 CFR 50.59 LARGE BREAK ASSESSMENTS APCT = 115 F D. 1998 10 CFR 50.46 MODEL ASSESSMENTS (Permanent Assessment of PCT Margin)

1. None APCT = 0F E. TEMPORARY ECCS MODEL ISSUES APCT = 0F F. OTHER MARGIN ALLOCATIONS

1. Transition Core (STD to V5H) APCT = 50 F (7)

2. Cold Leg Streaming Temperature Gradient APCT = 0F (8)

LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT = 2081 F Notes:

1. Westinghouse Topical Report WCAP-13456, " Wolf Creek Generating Station NSSS Rerat' ng Licensing Report," October 1992.

2. Westinghouse to WCNOC letter SAP-98-115, " Wolf Creek Nuclear Operating Corporation, Wolf Creek Generating Station, 10 CFR 50.46 Notification and Repor.ing for 1997,"

February 27, 1998

3. Westinghouse to WCNOC letter SAP-90-148, " Wolf Creek Nuclear Operating Corporation, RCS Loose Parts Evoluation," April 18, 1998.

4. Westinghouse to WCNOC letter SAP-94-102, " Containment Mini purge Isolation Valve Stroke Time Increase," January 12, 1994.

5. Westinghouse to WCNOC letter 97 SAP-G-0009, " Wolf Creek Nuclear Operating Corporation, Wolf Creek Generating Station, Safety Assessment for the Wolf Creek Generating Station with ZIRLO" Fuel Assemblies," February 7, 1997

6. Westinghouse to WCNOC letter 97 SAP-G-0075, " Wolf Creek Nuclear Operating Corporation, Wolf Creek Generating Station, Wolf Creek Crud Deposition / Axial Offset Anomaly Safety Evaluation," September 29, 1997. (This penalty will be carried until such time it is determined to no longer apply).

7. Westinghouse to WCNOC letter SAP-93-111, " Wolf Creek Nuclear Operating Corporation, Wolf Creek Generating Station, LOCA PCT Summary Sheets," April 14, 1993.

(Transition core penalty applies on a y le-specific basis for reloads utilizing both V5H (with 1FMs) and STD fuel until a full core of V5H is achieved).

8. Westinghouse to WCNOC letter SAP-93-701, " Wolf Creek Nuclear Operating Corporation, Wolf Creek Generating Station, 10 CFR 50.46 Notification and Reporting Inf orma t f or., " January 25, 1993. [A PCT benefit of 2.5 degrees Fahrenheit was assessed; however, a benefit of zero (0) degrees Fah.anheit will be tracked for reporting purposes).

n . - -

Attachment 2 to ET 99-0013

. Page 1 of 1 LIST OF COHt4ITMENTS The following table identifies those actions committed to by Wolf Creek Nucleat Operating Corporation (WCNOC) 1., this document. Any other statements in this submittal are provided for information purposes and are not considered to be commitments. Please direct questions regarding these commitments to Mr.

Michael J ingus, Manager Licensing and Corrective Action at Wolf Creek Generating station, (316) 364-4077 cot 44ITMENT Due Date/ Event None N/A a

d l

4 4

Y