ML20151T852
| ML20151T852 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/08/1998 |
| From: | Hansen A NRC (Affiliation Not Assigned) |
| To: | Jeffery Wood CENTERIOR ENERGY |
| References | |
| GL-97-01, GL-97-1, TAC-M98561, NUDOCS 9809100175 | |
| Download: ML20151T852 (6) | |
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September 8, 1998 Mr. John K. Wood Vice President - Nuclear, Davis-Besse Centerior Service Company c/o Toledo Edison Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
GENERIC LETTER 97-01, " DEGRADATION OF CRDM/CEDM N0ZZLE AND OTHER VESSEL CLOSURE HEAD PENETRATIONS," REQUEST FOR ADDITIONAL INFORMATION, DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 (TAC NO. M98561)
Dear Mr. Wood:
On April 1,1997, the staff issued Generic Letter (GL) 97-01, " Degradation of CRDM/CEDM Nozzle and Other Vessel Closure Head Penetrations," to the industry requesting in part that addressees provide a description of the plans to inspect the vessel head penetration nozzles (VHPs) at their respective pressurized water reactor (PWR) plants.
With respect to the issuance of the i
GL, the staff required the addressees to submit an initial response within 30 days of issuance informing the staff of the intent to provide requerted information and a follow-up response within 120 days of issuance containing the technical details to the staff's information requests.
In the discussion i
section of the GL, the staff stated that " individual licensees may wish to 4
determine their inspection activities based on an integrated industry i
inspection program...," and indicated that it did not object to individual PWR licensees basing their inspection activities on an integrated industry inspection program.
As a result, the B&W Owners' Group (B&WOG) determined that it was appropriate for its members to develop a cooperative integrated inspection program in response to GL 97-01.
The B&WOG program is documented in Topical Report BAW-2301, " Degradation of CRDM/CEDM Nozzle and Other Vessel Closure Head Penetrations," which was prepared by Framatome Technologies, Incorporated (FTI) on behalf of the B&WOG and the following B&WOG member utilities and plants:
General Public Utilities - Three Mile Island, Unit 1
\\ O Duke Power Company - Oconee Nuclear Station, Units 1, 2, and 3 Entergy Operatiors, Inc. - Arkansas Nuclear One, Unit 1 Centerior Energy Corp. - Davis Besse Nuclear Power Station, Unit I
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Florida Power Corporation - Crystal River, Unit 3.
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Y The B&WOG submitted its integrated program and Topical Report BAW-2301 to the staff on July 25, 1997.
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i J. Wood
- Based on your responses ~ dated April 23 and July 28, 1998, concerning the l
Davis-Besse Nuclear Power Station, the staff has determined that you are a participant in the B&WOG integrated program that was developed to address ti;e staff's requests in GL 97-01.
In your responses, you also indicated that the information in Topical Report BAW-2301 is applicable with respect to the l
assessment of VHP nozzles at Davis-Besse.
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The staff has initiated a review of your responses and requires additional information to complete the review.
The methodology developed by Framatome Technology Incorporated (FTI) for predicting the degradation susceptibility of vessel head penetration nozzles in B&WOG plant designs is provided in Appendix B to the report, " Description i
of CRDM Nozzle PWSCC Inspection and Repair Strategic Evaluation Model." The CRDM Nozzle PWSCC Inspection and Repair Strategic Evaluation (CIRSE) methodology for crack initiation is dependent on the calculation of a Relative Susceptibility Factor (RSF), which in part is a function of a number of
'+iplicative adjustment factors (for example, the material factors,
. rication factors,- and water chemistry factors).
FTI has assumed that there is little variability in the alloying chemistries and microstructures of the heats used to fabricate.the B&W CRDM penetration and thermocouple nozzles, and
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has therefore. set the values for these multiplicative adjustment factors to a value of 1.0.
This simplifies the CIRSE' crack initiation model to one that is simply-based on the applied nozzle stresses and nozzle operating temperatures.
The approach taken does not appear to be consistent with the ranges of data i
provided in Table 1 of the report, "CRDM Nozzle Heats at B&W-Design Plant,"
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which provides the yield strengths, ultimate tensile strengths, and carbon contents for the B&W CRDM penetration nozzle material heats. The data in Table 1 of the report imply that there may be some variability in the chemistries and microstructures of the Alloy 600 material heats used to fabricate the B&W CRDM penetration nozzles.
Topical Report No. BAW-2301 also provides the B&WOG's inspection schedule and scope for VHP nozzles in B&W-designed plants.
In this section, the B&WOG-indicated that the schedule for VHP nozzle inspections was developed based on the susceptibility assessments of the B&W CRDM penetration nozzles and thermocouple nozzle heats.
The specific results of the CRDM penetration nozzle susceptibility rankings for the B&WOG plants were not provided in the report.. However, the B&WOG has indicated that additional inspections of the B&W-fabricated CRDM penetration nozzles have been scheduled for the 1999 refueling outages (RFOs) of Oconee Nuclear Station, Unit 2 (ONS-2)_ and Crystal River, Unit 3 (CR-3) plants.
In addition, FTI has also indicated that additional inspections of the thermocouple nozzles at Three Mile' Island, 1
Unit.1 (TMI-1) and Oconee Nuclear Station Unit 1 (ONS-1) are tentatively
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scheduled for the year 2001.
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J, Wood,
September 8, 1998 Therefora, with respect to the design of the CIRSE crack initiation and crack growth models, the susceptibility rankings for vessel head penetrations in B&W-designed plants, the proposed CRDM nozzle inspections at ONS-2 and CP.-3, and the postulated inspections of the instrumentation nozzles at TMI-I and ONS-1, the staff requests the following information:
1.
Provide a description of how the various product forms, material specifications, and heat treatments used to fabricate each CRDM penetration nozzle are handled in the CIRSE model.
2.
Provide any additional information, if available, regarding how the model will be refined to allow the input of plant-specific inspection data into the model's analysis methodology.
3.
Describe how FTI's crack initiation and crack growth models for assessing postulated flaws in vessel head penetration nozzles were bench-marked, and provide a listing and discussion of the standards the models were bench-marked against.
4.
Provide the latest CiRSE model susceptibility rankings of B&W-designed facilities based on the CIRSE model analysis results compiled from the analyses of the CRDM and instrumentation nozzles at the facilities.
Please respond to this request within 90 days of the date of this letter.
Similar staff requests are being issued to the other B&WOG member utilities.
The staff encourages you to address these inquiries in integrated fashion with the B&WOG.
The staff also requests that you identify any deviations from the B&WOG's integrated program that may be specific to your facility.
Sincerely, Original signed by:
Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Decket No. 50-346 cc:
See next page i
DISTRIBUTION:
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Docket File PUBLIC l
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J. Wood '
September 8, 1998 Therefore, with respect to the design of the CIRSE crack initiation and crick growth modele, the susceptibility rankings for vessel head penetrations in B&W-designed plants, the proposed CRDM nozzle inspections at ONS-2 and CR-3, I
and the postulated inspections of the instrumentation nozzles at THI-l and ONS-1, the staff requests the following information:
1.
Provide a description of how the various product forms, material specifications, and heat treatments used to fabricate each CRDM penetration nozzle are handled in the CIRSE model.
2.
Provide any additional information if available, regarding how the model will be refined to allow the input of plant-specific inspection data into the model's analysis methodology.
3.
Describe how FTI's crack initiation and crack growth models for asses. sing postulated flaws in vessel head penetration nozzles were bench-marked, and provide a listing and discussion of the standards the models were bench-marked against.
4.
Provide the latest CIRSE model susceptibility rankings of B&W-i designed facilities based on the CIRSE model analysis results compiled from the analyses of the CRDM and instrumentation nozzles at the facilities.
Please respond to this request within 90 days of the date of this letter.
Similar staff requests are being issued to the other B&WOG member utilities.
The staff encourages you to address these inquiries in integrated fashion with the B&WOG.
The staff also requests that you identify any deviations from the B&WDC":, integrated program that may be specific to your facility.
Sincerely, Original signed by:
Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV l
Office of Nuclear Reactor Regulation l
Docket No. 50-346 L
cc: See next page DISTRIBUTION:
Docket File PUBLIC l
PD33 r/f EGA1 RBellamy JHarold EMCB OGC ACRS GGrant, Region 3 DOCUMENT MMEi:
b\\DAVISBES\\DB98561.RAI 0FFICE L%TDIDO O 'PM:PDIII-b p
NAME
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DATE M/%/0//
'// '/ / 97 0FFICIAL RECORD COPY
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J. Wood -
Therefore, with respect to the design of the CIRSE crack initiation and crack growth models, the susceptibility rankings for vessel head penetrations in B&W-designed plants, the proposed CRDM nozzle inspections at ONS-2 and CR-3, and the postulated inspections of the instrumentation nozzles at TMI-1 and ONS-1, the staff requests the following information:
1.
Provide a description of how the various product forms, material specifications, and heat treatments used to fabricate each CRDM penetration nozzle are handled in the CIRSE model.
2.
Provide any additional information, if available, regarding now the model will be refined to allow the input of plant-specific i
inspection data into the model's analysis methodology.
3.
Describe how FTI's crack initiation and crack growth models for assessing postulated flaws in vessel head penetration nozzles were bench-marked, and provide a listing and discussion of the standards the models were bench-marked against.
4.
Provide the latest CIRSE model susceptibility rankings of B&W-designed facilities based on the CIRSE model analysis results compiled from the analyses of the CRDM and instrumentation nozzles at the facilities.
Please respond to this request within 90 days of the date of this letter.
Similar staff requests are being issued to the other B&WOG member utilities.
The staff encourages you to address these inquiries in integrated fashion with the B&WOG, The staff also requests that you identify any deviations from the B&WOG's integrated program that may be specific to your facility.
Sincerely, A
Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-346 cc:
See next page
John K. Wood Davis-Besse Nuclear Power Station, Unit 1 Toledo Edison Company cc:
Mary E. O'Reilly Robert E. Owen, Chief FirstEnegy Bureau of Radiological Health Davis-Besse Nuclear Power Station Service 5501 North State - Route 2 Ohio Department of Health Oak Harbor, OH 43449-9760 P.O. Box 118 Columbus, OH 43266-0118 James L. Freels i
Manager-Regulatory Affairs Toledo Edison Company James R. Williams, Chief of Staff Davis-Besse Nuclear Power Station Ohio Emergency Management Agency 5501 North State - Route 2 2855 West Dublin Granville Road Oak Harbor, OH 43449-9760 Columbus, OH 43235-2206 Jay E. Silberg, Esq.
Donna Owens, Director Shaw, Pittman, Potts Ohio Department of Commerce and Trowbridge Division of Industrial Compliance 2300 N Street, NW.
Bureau of Operations & Maintenance Washington, DC 20037 6606 Tussing Road P.O. Box 4009 Regional Administrator Reynoldsburg, OH 43068-9009 U.S. Nuclear Regulatory Commission 801 Warrenville Road Ohio Environmental Protection Agency Lisle, IL 60523-4351 DERR-Compliance Unit ATTN: Zack A. Clayton Robert B. Borsum P.O. Box 1049 Babcock & Wilcox Columbus, OH 43266-0149 Nuclear Power Generation Division 1700 Rockville Pike, Suite 525 State of Ohio Rockville, MD 20852 Public Utilities Commission 180 East Broad Street Resident inspector columbus, OH 43266-0573 U.S. Nuclear Regulatory Commission 5503 North State Route 2 Attorney General Oak Harbor, OH 43449 Department of Attomey 30 East Broad Street James H. Lash, Plant Manager Columbus, OH 43216 Toledo Edison Company Davis-Besse Nuclear Power Station President, Board of County 5501 North State Route 2 Commissioners of Ottawa County Oak Harbor, OH 43449-9760 Port Clinton, OH 43252
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