ML18059A917

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Summary of 940309 Meeting W/Util to Discuss Plant Activities Related to Pts.Attendees & Licensee Matl Encl
ML18059A917
Person / Time
Site: Palisades Entergy icon.png
Issue date: 03/25/1994
From: Hsia A
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 9404060232
Download: ML18059A917 (23)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555--0001 March 25, 1994 Docket No. 50-255 LICENSEE: Consumers Power Company FACILITY: Palisades Nuclear Generating Plant

SUBJECT:

SUMMARY

OF MEETING HELD ON MARCH 9, 1994, ON PRESSURIZED THERMAL SHOCK ISSUE On March 9, 1994, members of the NRC staff met with representatives of the Consumers Power Company (CPCo) to discuss the Palisades activities related to pressurized thermal shock (PTS). lists the meeting attendees. is a copy of the material presented by the licensee.

The meeting focused upon the project plans for Palisades reactor vessel integrity. The proposed project plan included the W-110 surveillance capsule analysis, data collection and analysis from the retired steam generator (SG) weld samples, integrated surveillance program, test reactor research and annealing demonstrations.

The licensee described its activities in obtaining and analyzing the available weld data as well as the planned activities in the surveillance program and vessel annealing consideration~.* The long-term supplemental surveillance plan which includes irradiation and annealing was also discussed.

The licensee is scheduled to submit a comprehensive PTS analysis including SG weld sample data analysis and results from the integrated surveillance program by February 1995.

The licensee expressed a desire to receive a safety evaluation of the latest PTS submittal dated February 23, 1994.

The staff noted that Palisades has been responsive to previous NRC comments on

  • PTS issues, and the February 1995 schedule is acceptable. However, the licensee was reminded that NRC needs to be informed as soon as possible of any project schedule slippage or discovery of unfavorable data. Furthermore, the licensee should submit (1) a data equivalency demonstration for the integrated surveillance program and steam ~enerator welds and, (2) an analysis on the effects of thermal aging on the steam generator welds.
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Consumers Power Company March 25, 1994 The licensee indicated that the samples removed from the retired SGs will be analyzed at three _locations evenly distributed throygh the cross-~ction of.

the weld.

The staff believes that d~e, to variabil*i.ty in the -coppel' coating on the weld wire, a best-estimate value for the amount'of copper in *a-*"weld should have more than three data points. Therefore, we.request that the chemical analysis of the retired SG weld samples include more than three measurements from each sample.

These measurements and the test results from drop weight and Charpy tests to determine the unirradiated reference temperatures are to be submitted for staff review as soon as possible.

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Enclosures:

1.

Meeting attendees

2.

Licensee slides cc:

w/enclosures See next page Anthony H. H ia, Project Manager

_. Project Directorate-111-1 J *Division of Reactor Projects - 111/IV/V Office of Nuclear Reactor Regulation

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Consumers Power Company, *

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March 25, 1994 1'

The licens~e indicated tHat the samples remrived fro~ the retired SGs will be analyzed a~ three locations evenly di.stributed.through the cross-section of the

~eld. The staff believes t,hat due to variabiH.ty'.in the copper coating on the weld wire, a be.st.-estimate value for-,the*.amount-of copper in a weld should have more than three data points.

Therefore, w.e-request that the chemical analysis of the retired SG w~Jd samples j,ncluae niore than._three measurements from each sample.

Tb~se meas~~emerits~and the test results from drop weight and Charpy tests to*:d~termi n'e' ;the.un.i rradi ated reference.. :temperratur.es are to be submitted for staff~.. ~eview as*fsoon. as pos'~'ible..

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Enclosures:

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Meeting attendees

  • 2.

Licensee slides cc:

w/enclosures See next page OFFICE LA: PD31 j*

  • oivision:'-~f,Reactor Projects - III/IV/V

, /:' Qffi ce of:, Nuclear Reactor Regulation

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PD:PD31 OFFICIAL RECORD COPY FILENAME: G:\\WPDOCS\\PALISADE\\PA309MTG.SUM

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Consumers Power Company cc:

Mr. Thomas J. Palmi~ano Plant General Manager (Acting)

Palisades Plant Consumers Power Company 27780 Blue Star Memorial Highway Covert, Michigan 49043 M. I. Mill~r, Esquire Sidley & Austin 54th Floor One First National Plaza Chicago, Illinois 60603 Mr. Thomas A. McNish, Secretary Consumers Power Company 212 West Michigan Avenue Jackson, Michigan' 49201 Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Regional Administrator, Region III U.S. Nuclear Regulatory Conunission 801 Warrenville Road Lisle, Illinois 60532-4351 Jerry Sarno Township Supervisor Covert Township 36197 M-140 Highway Covert, Michigan 49043 Office of the Governor Room 1 - Capitol Building Lansing, Michigan 48913 Mr. David W. Rogers Safety and Licensing Director Palisades Plant 27780 Blue Star Memorial Highway Covert, Michigan 49043 U.S. Nuclear Regulatory Conunission Resident Inspector Office Palisades Plant 27782 Blue Star Memorial Highway Covert, Michigan 49043

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Pal hades Pl ant Nuclear Facilities and Environmental

. Monitoring Sectio~ Office Divisioff"of Radiol~~1c~l Health Department of Public Health 3423 N. Logan Street P. 0. Box 30195 Lansing, Michigan 48909 Gerald Charnoff, Esquire Shaw, Pittman, Potts and Trowbridge 2300 N Street, N. W.

Washington DC 20037 Alora Davis Conunitment Tracking System Coordinator Palisades Plant Consumers Power Company 27780 Blue Star Memorial Hwy.

Covert, Mithigan 49043-9530 Mr. Robert A. Fenech Vice President, Nuclear Operations Consumers Power Company Palisades Plant 27780 Blue Star Memorial Highway Covert,* Michigan 49043

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MEETING

SUMMARY

,' FOR MEETING HELD ON 03/09/94

  • QATED:

DISTRIBUTION W/ENCLOSURES l"AND 2

  • Docket F.i.J e NRC & LPDRs PD31 Readin*g.*

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L. Lois, 8/E/23 J. Strosnider, 7/D/4 ACRS (10)

W. Dean, 17/G/21 A. Hiser, NLS 217/C

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Licensee &.Service List

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  • I March 25, 1994

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ENCLOSURE 1 MEETING WITH NRC AND CONSUMER POWER REGARDING PRESSURIZED THERMAL SHOCK Dick Smedley John Kneeland Jack Hanson David W. Rogers Guy Packard Bud Gerling Barry J. Elliot Keith Wichman Ed Hackett Jack Strosnider Lambros Lois Tad Marsh Tony Hsia John Zwolinski Kevin Graney

. Allen Hiser

  • Lynn Connor March 9, 1994 ORGANIZATION Consumers Power Co.

Consumers Power Co.

Consumers Power Co.

Consumers Power Co.

Consumers Power Co.

Consumers Power Co.

NRR/EMCB NRR/EMCB NRR/EMCB NRR/EMCB NRR/SRXB.

NRR/DRPW.

NRR/DRPW NRR/DRPW Serch Licensing/Bechtel Power NRC Research.

Southern Technical Svcs., Inc.

Page 1of1 CONSUMERS POWER COMPANY - PALISADES NUCLEAR PLANT Schedule for Palisades Reactor Vessel Integrity Project Plans Numeric/Alpha designation in () refers to preceding paragraphs 3/811994 DESCRIPTION 19~

1~5 1900 19~

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01'94 I 0794 I Q3'94 I 04'94 01'95 I 0795 I 03'95 I Q4'95 01'96 I 02'96 I o3'96 I 04'96 01'91 I 02'91 I Q3'91 I 04'97 01'98 I 02'98 I 03'98 I 04'98 (I) W110 SURVEILLANCE CAPSULE (I) INTEGRATED SURVEILLANCE PROGRAM (II) FUEL MANAGEMENT REPLACE/ ANAL XZE DOSIMETRY (Ill.A) ACQUIRE/ TEST MATERIAL (111.8) IMPROVE SURVEILLANCE PROGRAM FABRICATE/ INSTALL TWO CAPSULES REMOVE/ ANALYZE FIRST CAPSULE

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TABLE 2 2 PALISAOES RPV WELOS Weld Seam Location Weld Oeposit Upper Shell Axial Seams RACO 3 Heat W5214 Linde 1092 Lot 361 7 1*11 2 A/C Ni 200 Heat N* 7753A E8018 Electrodes CBBF. JBFG (Repair)

  • 2-112A/C Intermediate Shell RACO 3 Heat W5214 Linde 1092 Lot 361 7 Axial Seams Ni 200 Heat N-7753A E8018 Electrodes (None)
  • 3.112 A/C Lower Shell RACO 3 Heat W5214 Linde 1092 Lot 3692 Axial Seams RACO 3 Heat 348009 Linde 1092 Lot 3692 Ni 200 Heat N* 7753A E8018 Electrode CBBF (Repair)
    • 1-112 Upper Shell to Flange RACO 3 Heat W5214 Linde 1092 Lot 3692 Circumferential Seam RACO 3 Heat 34B009 Linde 1092 Lot 3692 Ni 200 Heat N-7753A and Heat N-98674 E8018 Electrode COGG IBackweldl E808 Electrode DAGG (Weld Gridoutl
  • *0-112 Upper to Intermediate RACO 3 Heat 34B009 Linde 1092 Lot 3692 Shell Circumferential Ni 200 Heat N-98674 Seam E8018 Electrode 7B-47B. COFC (Back Weldl
  • 9-1, 2 Intermediate to Lower 6MIL-B4 Mod, Heat 27204 Linde 1092 Lot 3714 Shell Circumferential 6E8018 Electrode JBFG (Back Weld)

Seam MIL-84 Mod. Heat 27204 Linde 124 Lot 3687 (Weld Repair)

E8018 Electrode LODG (First Layer and Back Weld)

(Weld Repair)

..10-112 Lower Shell to Bonom MIL*B4 Mod. Heat 27204 Linde 1092 Lot 371.4 Head Circumferential E8018 Electrode HAEG (First Layer and Back Weld)

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..12-112 Seal Ledge to Flange RACO 3 Heat W5214 Linde 1092 Lot 3617 Seam E7018 Electrode HOHF (Back Weld and Fillet)

E7018 Electrode ABCG (Ledge Ring Repair) 1*113 A/F Bottom Head Torus Axial EBO 1 8 Electrode 6M 1 OB Seams E8018 Electrode 704B (Weld Repair)

.. 4-113 Bottom Head Dome to MIL*B4 Mod. Heat 12420 Linde 1092 Lot 3708 Torus Circumferential E8018 Electrode CBB4 (Back Weld)

Seam 1 *118 A/F Closure Head Torus Axial RACO 3 Heat W5214 Linde 1092 Lot 361 7 Seams Ni 200 Heat N* 7753A

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MIL*B4 Mod. Heat 12420 Linde 1092 Lot 3708 ential Seams E8018 Electrode CBBF !Back Weldl Surveillance Program RACO 3 Heat 3277 Linde 1092 Lot 3833 Weld Ni 200 Heat N-0591 A (Face Weld Only)

E8018 Electrode HAOH (Back Weld. Base Metal Repair)

Welds in the Reactor Vessel Beltline Region Single Arc for Entire Weld, Other Joints Used Tandem Arc A

This is the Initial Weld which was Entirely Removed and Rewelded

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