ML20077J904

From kanterella
Revision as of 15:46, 25 April 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Forwards Table Listing Peak Cladding Temp Changes/Errors & Commitment Data Input Form,Constituting 30-day Rept of Changes or Errors Discovered in ECCS Calculations,Per 10CFR50.46
ML20077J904
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 07/31/1991
From: William Cahill
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TXX-91230, NUDOCS 9108050232
Download: ML20077J904 (4)


Text

. .. _ - _ _ _ _ .

M WA

. Log # TXX 91230

~

. Z File # 10010 ZZ  :: 915.6 Ref. # 10CFR50.46 7UELECTRIC wmiar J. cawn.Jr. July 31, 1991 (serwM ike (>ts&*st U. S. Nuclear Regulatory Commission Attn: Documen" Control Desk Washington, DC 20555

SUBJECT:

C0HANCHE PEAK STEAM ELECTRIC STATION (CPSES) - UNIT 1 DOCKET NO. 50-445 PEAK CLADDING TEM / ERA TURE CHANGES GREATER THAN 500F REF: 1. Letter loggel TXX-6444, dated May 18, 1987, from, W. G. Counsi to the NRC

2. Letter loggei'. TXX 89695, dated September ?1 1989, from W. J. Cahill, Jr. to the NRC Gentlemen:

Westinghouse Electric Corporation notified TU Elec+ 1c of errors in the CPSES Unit 1 ECCS calculation on July 1, 1991. 1ha p.ok fuel cladding temperature (PCT) for CPSES Unit I was calculated using the 1978 versicn of the Westinghouse ECCS evaluation model as identified in the !c+ter logged TXX 6444 Reference 1, and Supplemental Safety Evaluation Reports 21 and 24 tr. NUREG 0797. This report includes the changes / errors reported in the letter logged TXX 89695, Reference 2. with the value of 47.80F in PCT change as an annual report of changes in PCT for 1989. The recent notification of PCT penalty from Westinghouse was for steam generator tube collapse due to concurrent seismic and LOCA load with the value of 7.20F. Each change / error is identified 'n an attachment to this letter along with the res JItant Change in peak Cladding temperature.

The absolute magnitude of these changes total greater than 500F and in accordance with 10CFR50.46(a)(3)(i), have been classified as significant. This letter is TU Electric's 30 day report of changes or errors discovered in the ECCS calculations of PCT as required by 10CFR50.46(a)(3)(ii). Therefore, the information required by 10CFR50.46 is provided below.

Utilizing the attached list nf changes to the Unit 1 PCT consenatively. the maximum updated value for the Unit 1 PCT is 2065.70F. This updated value remains well below the 22000F limiting value establit,hed by Part 50.46(b)(1).

Therefore, the current analysis continues to demonstrate CPSES Unit I compliance with 10CFR50.46.

\

n o.>>t c F IiR R

A D O t...

,1 o, < 1 U AOMyG fIm h/q y

o I

400 North Obvc Street Lit hl Dallas. letas 75201

TXX-91230 Page 2 of 2 Furthermore, TV Electric is applying Advanced Nuclear Fuels methodology to perform a large Break LOCA analysis for CPSES Unit 1. Cycle 3. The schedule for completion and submittal of the CPSES Unit 1 Cycle 3 analysis is Hay 29. 1992.

If you have any questions, please contact Mr. J. D. Seawright at (214) 812 4375.

Sincerely, , ,

6 N (

William J. Cahill, Jr.

JDS/grp c Mr. R. D. Martin, Region IV Resident inspectors, CPSES (2)

Mr. T. A. Bergmap, HRR I

T'- pPW t t h tz@?-e 4* w w a'N'O- es rwa-4*-- *w->'tt-* v1 maw-3 *r M**+ammm@k->wN*qvWg*g4wc*'Ny' um amg'ecm-e*fw 7 wP *yy _ W y yv TwTW-- gt -wegrw 7P- P7 N id-9 7 Y p wW 91 gMWe 9 g are

Attachment to TXX 91230 Page 1 of 1 CPSES Unit 1 Peak Cladding Temperature Changes / Errors 11gJn QLanae in PCT L0fl Steam generator bypass flow modification 6.2 (increased hot leg temperature)

Hodification of accumulator water level 10 (reduced volume)

Reduced RHR flow due to mini flow operation 1 Allowance for WREFLOOD errors per NRC 12 Generic Letter 86-16 (6 to 120F)

Accomodation for 1% steam generator tube 6 plugging Correction of error in steam generator flow area 12.6 Steam generator tube collapse due to 7.2 concurrent seismic and LOCA loads Total Change 55.0 Base Calculation 2010.70F (1978 version of the Westinghouse ECCS evaluation model)

Total Peak Clad Temperature 2065.70F

, 7.-

OVEVED BY: corr REPORT DATE : 07/29/91

, COMMITHENT DATA INPUT FORM PAGE : 1 COMMITHENT INDEX INFORMATION C0HNITHENT TYPE : REG NUMBER : AUTHORITY : NRC COMMITHENT REGISTER NUMBER : HL-7269 UNITS  : INN STATUS IX : OPN STATUS 2X : NA COHHITHENT STATUS : OPN TITLE ECCS EVALUATION H0 DEL SUBJECT : AA LIC CONTACT : JDS PRlH ORG : NED/RE UNIT 1 HILESTONE : DUE DATE : 05/29/1992 SCHEDULE DATE :

UNIT 2 HILESTONE : DUE DATE : SCHEDULE DATE :

INFO VERIFIED : DATE VERIFIED : PRIORITY  : 01 LDCR : LDCR-COHHITHENT DESCRIPTION :

TV Electric is currently completing a large Break LOCA analysis using Advanced Nuclear fuels methodology applied by TV Electric for CPSES unit I cycle 3. The Schedule _for completion of the CPSES unit 1 analysis id' Hay 29, 1992.

[6-SOURCF DOCUMENT STATUS INFORMATION SOURCE DOCUMENT ISSUE TYPE LEVEL NUMBER SECTION PAGE REV DATE LTR 1 TXX-91230 07 30 91 ACTIVITY SUB ITEMS SUB ITEM CONTRIB ORG LEAD INITIATION DATE RE0'D C0HP DATE COMMITHENT COMMENTS l

COMMITHENT DOCUMENT CROSS REFERENCE INFORMATION KIND TYPE NUMBER ASSOCIATED COMMITHENT INFORMATION

  • ASSOC-STATUS TYPE NUMBER REVIEWER DATE CTG ENTRY DATE t