ML20211M916

Submits Review & Correction of Info in Reactor Vessel Integrity Database (Rvid),Version 2,re Pilgrim Station

ML20211M916
Person / Time
Site:	Pilgrim
Issue date:	08/31/1999
From:	Alexander J ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
ENGC-2.99.085, NUDOCS 9909090247
Download: ML20211M916 (2)

Text

_s g

s_

1*.

~{tm}

v Entergy Nuclear Genor!. tion Company Pilgrim Nuclear Power Station '

600 Rocky Hill Road Plymouth, MA 02360 August 31,1999 ENGC Ltr. 2.99.085

'J.F. Alexander, Director Nuclear Assessment Group U.S. Nuclear Regulatory Commission

' Attention: Document Control Desk Washington, DC 20555

Subject:

Entergy Nuclear Generating Company's Response to Review Information provided for Generic Letter (GL) 92-01, Revision 1, Supplement 1, " Reactor Vessel Structural Integrity" for Pilgrim Nuclear Power Station (dated July 26,1999)

This letter is Entergy Nuclear Generating Company's response to the Nuclear Regulatory Commission's request (dated July 26,1999) for a review of information which was provided by Pilgrim Nuclear Power Station in response to GL 92-01. The information provided by Pilgrim Station was included in the Reactor Vessel Integrity Database (RVID), which was released as RVID Version 2 (RVID2). This letter is a review and correction of the information provided in the RVID2.

The weld wire reported for the lower shell axial seam weld (identified as 2-338 A, B, C) was incorrectly identified as 27204/12008. The correct weld wire identification for this seam is Heat No. 27204, Lots 3714 and 3774, Flux Linde 1092, and Filler B4 Mod (Reference BECo Letter 2.98.10 , dated August 6,1998). l The Pilgrim Reactor Surveillance Capsule Material has not been identified in the RVib2. The following information is provided for the Pilgrim Surveillance Capsule:

1. The Capsule base metal was taken from the lower intermediate shell assembly. The plate material is identified as shell course G-3108-1, Heat No. C-2921-2.

2. The Capsule weld and HAZ plate material was also taken from two (2) shell courses of the lower intermediate shell assembly " trim offs" identified as G-3108-2 Heat No. C- 'kg 2945-1 and G-3108-3, Heat No. C-2945-2, 0

3. The Capsule weld is identified as the " Test Plate" seam 1-338. The weld wire is identified as Heat No. 20291/12008, Lot 3833, Flux Linde 1092, and Filler B4. Archival Si,0 33 ,

I ENGC Ltr. 2.99.085 I Page 2

• information on the Pilgrim capsule weld material, originally provided by CE, was  ;

considered either incomplete or incorrect and the data was not reported in previous I c7rrespondence with the NRC. CE had incorrectly identified the Capsule weld as Wire Hoat 132F,3 and later discovered the correct wire heat was 20291/12008.

i 2

RVID2 lists the Neutron Hence at End of Life (EOL) as 0.139e n/cm for all shells . The peak fluence value in the beltline region at the reactor vessel ID is 0.146e n/cm* and includes an azimuthal lead factor of 1.07, relative to the surveillance capsule fluence. The value reported in BECo letter 2.98.107, dated August 6,1998, of 0.138e n/cm2 represents the EOl i1uence vaice forthe 4 most limiting weld,1-338 A, B, C. This information was obtained from the r aneral F!:.um, report MDE l 277-1285, (Pilgrim Nuclear Power Station Unit 1 Reactor Pressure Vossel f as+ Neutron Flux as a Function of Fuel Cycle," dated November 27,1985, and Southwest Research laNta report 02-5951,  !

" Pilgrim Nuclear Power Station Unit 1 Reactor Vessel Irradiation Surveillance Program,- d& A:f 1981). The reports are referenced as References 5.b and 6, respectively, in Teledyne Technical Report TR 6052B-1, " Pilgrim Nuclear Power Station Reactor Vessel Temperature Limits," dated June 26,1986, which was previously submitted to the NRC.

The Pilgrim reactor vessel pressure-temperature limits were based on a " worst-case" chemistry factor of 272 (for 0.35% wt, Cu and 1.0% wt Ni), in accordance with the criteria of NRC Reg. Guide 1.99, Revision 2. This condition is more restrictive than the most limiting weld or plate material and remains the governing condition. l Weld wire heat chemistry was obtained from CE NPSD-1039, Revision 02, "Best Estimate Copper and Nickel Values in CE Fabricated Reactor Vessel Welds."

{

The column identified as ".70 % wt Nickel" for wire heat 13253 is incorrectly labeled in BECo letter 2.98.107, dated August 6,1998, and should be changed to ".80 % wt Nickel."

Our previous submittal (BECo Ltr. 2.98.107) reported incorrectly interpolated chemistry factors for Wire Heat No. 27204. However, the correct vanes are listed in RVID2. I After reviewing the information provided previously and that which is contained within this letter, potential changes to the RVID2 database were found to be minor in nature and have no effect on the information which is contained in RVlD2 for the Pilgrim Reactor Vessel.

I l

Should you require further information on Pilgrim's review of the RVID2 database, please contact P.M.

Itahler at (508) 830-7539.

)

J. exander 299085