ML20196J989
| ML20196J989 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/08/1998 |
| From: | Nick Hilton NRC (Affiliation Not Assigned) |
| To: | Hutchinson C ENTERGY OPERATIONS, INC. |
| References | |
| GL-97-01, GL-97-1, TAC-M98543, NUDOCS 9812110148 | |
| Download: ML20196J989 (6) | |
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WASHINGTON, D.C. 30666-0001 December 8, 1998 Mr. C. Randy Hutchinson Vice President, Operations ANO Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72801 l
SUBJECT:
GENERIC LETTER (GL) 97-01, " DEGRADATION OF CRDM/CEDM NOZZLE AND OTHER VESSEL CLOSURE HEAD PENETRATIONS," REQUEST FOR ADDITIONAL INFORMATION (RAl) FOR ARKANSAS NUCLEAP. ONE, UNIT 1 (TAC NO. M98543)
Dear Mr. Hutchinson:
l On April 1,1997, the staff issued 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 I
respective pressurized water reactor (PWR) designed plants. With respect to the issuance of the GL, the staff required the addressees to submit an initial response within 30 days of i
issuance informing the staff of the intent to comply with requested information and a follow-up l
response within 120 days of issuance containing the technical details to the staff's information l
requests. In the discussion section of the GL, the staff stated that "individuallicensees may l
wish to determine their inspection activities based on an integrated industry inspection program.
.., and indicated that it did not object to individual PWR licensees basing their inspection i
activities on an integrated industry inspection program.
As a result, the B&WOG determined that it was appropriate for its members to develop a l
cooperative integrated inspection program in response to GL 97-01. The B&WOG program is l
documented in Topical Report BAW-2301, " Degradation of CRDM/CEDM Nozzle and Other i
Vessel Closure Head Penetratione," which was prepared by Framatome Technologies, incorporated on behalf of the B&WOG and the following B&WOG member utilities and plants:
General Public Utilities - Three Mile Island Unit 1 Duke Power Company - Oconee Nuclear Station Units 1,2, and 3 Entergy Operations, Inc. - Arkansas Nuclear One Unit 1 Centerior Energy Corp. - Davis Besse Nuclear Plant l
Florida Power Corporation - Crystal River Unit 3 The B&WOG submitted its integrated program and Topical Report BAW-2301 to the staff on July 25,1997.
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Mr. C. Rrndy Hutchinson N.
l The staff has determined by letters dated April 30,1997 (0CAN049706), and July 29,1997 l
(OCAN079703), that you were a member of the B&WOG and a participant in the B&WOG integrated program that was developed to address the staff's requests in GL 97-01. In your letter of July 29,1997 (0CAN079703), you also indicated that the information in Topical Report BAW-2301 is applicable with respect to the assessment of VHP nozzles at Arkansas Nuclear One, Unit 1.
The staff has reviewed your responses to GL 97-01, dated April 30,1997 (0CAN049706), and July 29,1997 (0CAN079703), and requires further information to complete its review of the i
responses as they relate to the B&WOG's integrated program for assessing VHP nozzles at B&WOG member plants, and to the contents of Topical Report No. BAW-2301. The enclosure to this letter forwards staff's inquiries in the form of a RAl.
The enclosed request was discussed with Mr. Steve Bennett of your staff on November 18, l
1998. A mutually agreeable target date of March 1,1999, for your response was established.
If circumstances result in the need to revise the target date, please call me at the earliest opportunity. It should be noted that similar staff requests have been issued to the other B&WOG member utilities. As was the staffs position before, the staff encourages you to address these inquiries in integrated fashion with the B&WOG; however, the staff also requests l
that you identify any deviations from the B&WOG's !ntegrated program that may be specific to your facility. The staff appreciates the efforts expended with respect to this matter.
Sincerely, l
ORIGINAL SIGNED BY:
l Nicholas D. Hilton, Project Manager l
Project Directorate IV-1 l
Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation Docket No. 50-313 i
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Enclosure:
As stated cc w/ encl: See next page i
DISTRIBUTION:
l Docket File PUBLIC PDIV-1 r/f EAdensam (EGA1)
OGC l
ACRS JHarold CMarschall TSullivan CWwes NHilton CNolan JHannon JZwolinski TGwynn, RIV Document Name: AR198543198543RAI h/ D4-1 OFC PMlPD4_-1 PM/PD4-1 LA/PD4-1 NAME NHillod CNolan CHaN JHagnon l
DATE tL/ fr /98
//,/ 8 /98 h3 /98 h/98 f
COPY YES/NO YES/NO YES/NO / YES/NO OFFICIAL RECORD COPY V
Mr. C. Randy Hutchinson The staff has determined by letters dated April 30,1997 (OCAN049706), and July 29,1997 (OCAN079703), that you were a member of the B&WOG and a participant in the B&WOG integrated program that was developed to address the staffs requests in GL 97-01. In your letter of July 29,1997 (0CAN079703), you also indicated that the information in Topical Report BAW-2301 is applicable with respect to the assessment of VHP nozzles at Arkansas Nuclear One, Unit 1.
The staff has reviewed your responses to GL 97-01, dated April 30,1997 (0CAN049706), and July 29,1997 (0CAN079703), and requires further information to complete its review of the responses as they relate to the B&WOG's integrated program for assessing VHP nozzles at B&WOG member plants, and to the contents of Topical Report No. BAW-2301. The enclosure to this letter fonvards staffs inquiries ln the form of a RAl.
The enclosed request was discussed with Mr. Steve Bennett of your staff on November 18, 1998. A mutually agreeable target date of March 1,1999, for your response was established.
if circumstances result in the need to revise the target date, please call me at the earliest opportunity. It should be noted that similar staff requests have been issued to the other B&WOG member utilities. As was the staff's position before, the staff encourages you to address these inquiries in integrated fashion with the B&WOG; however, the staff also requests that you identify any deviations from the B&WOG's integrated program that may be specific to your facility. The staff appreciates the efforts expended with respect to this matter.
Sincerely, Nicholas D. Hilton, Project Manager Project Directorate IV-1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation Docket No. 50-313
Enclosure:
As stated cc w/ encl: See next page a
Mr. C. R!ndy Hutchinson Entergy Operations, Inc.
Arkansas Nuclear One, Unit 1 cc:
Executive Vice President Vice President, Operations Support
& Chief Operating Officer Entergy Operations, Inc.
Entergy Operations, Inc.
P. O. Box 31995 P. O. Box 31995 Jackson, MS 39286-1995 Jackson, MS 39286-199 Wise, Carter, Child & Caraway Director, Division of Radiation P. O. Box 651 Control and Emergency Management Jackson, MS 39205 Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Winston & Strawn 1400 L Street, N.W.
Washington, DC 20005-3502 Manager, Rockville Nuclear Licensing Framatone Technologies 1700 Rockville Pike, Suite 525 Rockville, MD 20852 Senior Resident Inspector U.S. Nuclear Regulatory Commission i
P. O. Box 310 London, AR 72847 i
Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 County Judge of Pope County Pope Coun+y Courthouse Russellville, AR 72801
Request for Additional Information for Utilities Participating in the Babcock and Wilcox Owners Group (B&WOG) _
integrated Response to Generic Letter (GL) 97-01,
" Degradation of CRDM/CEDM Nozzle and Other Vessel Closure Head Penetrations" Applicability of Topical Report Number BAW-2301 to the Plant-Specific Responses to GL 97-01 for Participating Member Utilities and Plants in the B&WOG The methodology developed by Framatome Technology incorporated (FTI) for predicting the susceptibility of vessel head penetration nozzles in B&WOG plant designs is provided in Appendix B to the report, " Description of GRDM Nozzle PWSCC inspection and Repair Strategic Evaluation Model." The GRDM Nozzle PWSCC inspection and Repair Strategic Evaluation (CIRSE) methodology for crack initiation is dependent on the calculation of a Relative Susceptibility Factor, which in part is a function of a number of multiplicative djustment factors (e.g., the material factors, fabrication factors, and water chemistry factors).
FTl 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 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 provided in Table 1 of the report, "CRDM Nozzle Heats at B&W-Design Plant," 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 of the Oconee Nuclear Station Unit 2 (ONS-2) and at Crystal River Unit 3 (CR-3) plants. In addition, FTl has also indicated that additionalinspections of the thermocouple nozzles at Three Mile Island Unit 1 (TMi-1) and Oconee Nuclear Station Unit 1 (ONS-1) are tentatively scheduled for the year 2001. Therefore, with respect to the design of the CIRSE crack initiation and crack growth models, the susceptibility rankings for vessel tiead 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:
l ENCLOSURE
l 2-l
- 1. Provide a description of how the various product forms, material specifications, and heat treatments used to fabricate each CRDM penetration nozzle at the B&WOG member utilities 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 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 j
on the CIRSE model analysis results compiled from the analyses of the CRDM and' instrumentation nozzles at the facilities.
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