ML20211K223

Forwards Txu Electric Comments of Rvid,Version 2

ML20211K223
Person / Time
Site:	Comanche Peak
Issue date:	08/31/1999
From:	Terry C, Walker R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TAC-MA0536, TAC-MA0537, TXX-99208, NUDOCS 9909070137
Download: ML20211K223 (3)

Text

E L'; y TXU TXU Electrk , C. Lance Terry Comanche Peak $enior Vice President & Principal Nuclear Officer

. Steam Electric Station P.O. Box 1002 q

' Glen Rose,TX 76043 Tel: 254 897 8920 Fax:254897 6652

. Ituryl@txu.com Log # TXX-99208 File # 10035 GL-92-01 Ref.# 10CFR50.54(f)

August 31,1999 U. S. Nuclear Regulatory Commission

' Attn: Document Control Desk I

- Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 TRANSMIT COMMENTS REGARDING THE REACTOR VESSEL INTEGRITY DATABASE (RVID) VERSION 2 (TAC NOS. MA0536 and MA0537)

REF: 1) NRC Letter from David H. Jaffe to C. Lance Terry dated

' June 29,1999 )

Gentlemen:

On June 29,1999, the NRC notified TXU Electric, via Reference 1, of the availability of the Reactor Vessel Integrity Database (RVID) Version 2 on the NRC home page (http//www.nrc. gov /NRR/RVID/index.html). Reference I noted the RVID was revised as a result of TXU Electric's responses to NRC Generic Letter 92-01, i Revision 1, Supplement 1, " Reactor Vessel Structural Integrity." The NRC recommended that TXU Electric review the RVID Version 2 data for acceptability and if necessary, submit comments by September 1,1999. TXU Electric comments on the RVID, Version 2, are attached to this letter.

I.

il!l 9909070137 990831 PDR ADOCK 03000445

\

Y PDR.

g) '

o-7o ,

s

c, TXU TXX-99208

, P, age 2 of 2 This communication contains no new licensing basis commitments regarding CPSES ,

Units 1 and 2. l l

If you have any questions please contact either Craig Harrington at 254-897-6705 or Carl Corbin at 254-897-0121.

i Sincerely,

'h, i C. L. Terry By: M '

Ro'ger d. Walker Regulatory Affairs Manager CBC/cbc Attachment c- E. W. Merschoff, Region IV J. I. Tapia, Region IV D. H. Jaffe, NRR Resident Inspectors, CPSES 4

,f l Attachment to TXX-99208 Page,1of1,  !

i 1

The NRC's Reactor Vessel Integrity Database, Version 2 data regarding Comanche Peak Units 1 and 2 was reviewed against plant records. This review identified the following specific discrepancies and editorial corrections: f Unit 1 L The 1/4 T Neutron Fluence @ EOL is identified as 1.811 E19 in RVID. This value is referenced 1 to WCAP-13422 but on page 1-3 of the subject WCAP, this value is stated to be 1.66 E19.

WCAP-13422 summarizes the USE values for Surveillance Capsule U on page 1-3 identifying the Plate Transverse Measured USE for Heat ID C4533-2 as 78.0 and the Weld Measured USE - )

for Heat ID 88112 as 125.0. The corresponding values in RVID for Surveillance Capsule U data are listed respectively as 87.0 and 126.0. j UniL2 The six Intermediate and Lower Shell Plate Heat Codes are identified respectively as A3807-1,2,3 and A3816-1,2,3. The original Materials Certification Reports identify these materials with '

the letter "R" rather than the letter "A". Therefore, the correct Heat Codes for the six plates

' listed are R3807-1,2,3 and R3816-1,2,3.

1 Lower Shell Plate R3816-3 carries the Heat Number NR64443-1 according to the Materials Certification Report rather than the NR64433-1 number erroneously reported in our previous

, correspondence TXX-94172, dated June 20,1994.

The 1/4 T Neutron Fluence @ EOL is identified as 1.811 E19 in RVID. This value is referenced to the Comanche Peak Unit I first surveillance capsule report WCAP-13422 but on page 1-3 of the subject WCAP, this value is stated to be 1.66 E19. Furthermore TXU has subsequently

. submitted WCAP 14315 (our correspondence TXX-95243, dated September 19,1995) documenting the analysis of Surveillance Capsule U from Unit 2 which identifies the 1/4 T Neutron Fluence @ EOL on page 1-3 to be 1.512 E19.

-