ML20154H303
| ML20154H303 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/02/1998 |
| From: | Wiens L NRC (Affiliation Not Assigned) |
| To: | Cowan J FLORIDA POWER CORP. |
| References | |
| GL-97-01, GL-97-1, TAC-M98558, NUDOCS 9810140139 | |
| Download: ML20154H303 (6) | |
Text
-
.f%
[
4 UNITED STATES 4 j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001
%,*****p October 2, 1998 Mr. John Paul Cowan, Vice President Nuclear Operations (NA2E)
Florida Power Corporation Crystal River Energy Complex 15760 W. Power Line Street Crystal River, Florida 34428-6708
SUBJECT:
GENERIC LETTER 97-01, " DEGRADATION OF CRDM/CEDM NOZZLE AND OTHER VESSEL CLOSURE HEAD PENETRATIONS," RESPONSES FOR CRYSTAL RIVER UNIT 3 (TAC NO. M98558)
Dear Mr. Cowan:
On April 1,1997, the staff issued Generic Letter (GL) 97-01, " Degradation of CRDM/CEDM
[ Conto! Rod Drive Mechanism / Control Element Drive Mechanism) Nozzle and other Vessel Clostre Hcad Penetrations," to the industry requesting in part that addressees provide a description of plans to inspect the vessel head penetration (VHP) nozzles at their respective pressurized water reactor (PWR) designed plants. The staff requested addressees to submit an inicial response within 30 days of issuance of the GL, informing the staff whether the requested inforrnation would be provided and submittal of the detailed information requested by the staff within 120 days ofissuance of the GL. In the discussion section of the GL, the staff stated that
" individual licensees may 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 activities on en integrated industry inspection program.
As a result, the Babcock & Wilcox 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 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 Florida Power Corporation - Crystal River Unit 3 The B&WOG submitted its integrated program and Topical Report BAW-2301 to the staff on July 20,1997.
As stated in Florida Fower Corporation (FPC) letters dated May 1 and July 29,1997 Crystal River Unit 3 (CR-3) was a participant in the B&WOG integrated program that was developed to address the staffs requests in GL 97-01. In these letters it was indicated that the information in Topical Report BAW-2301 is applicable with respect to the assessment of VHP nozzles at CR-3.
1 N$C Ed idiNdi OsM
~
. -,, 4 n 9810140139 981002 PDR ADOCK 05000302 P
Mr. John Paul Cowan 2
The staff has reviewed the May 1 and July 29,1997, responses to GL 97-01, 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 requested information is identified in the enclosed request for additional information (RAI).
A response to this RAIis requested within 90 days of the date of this letter. It should be noted that similar staff requests have been issued to the other B&WOG member utilities. This RAI and the requested response date were discussed and agreed to by Mr. Tim Catchpole of your staff.
As was the staffs position before, the staff encourages you to address these inquiries in an 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 effort expended with respect to this matter.
Sincerely,
/D Leonard A. Wiens, Senior Project Manager Project Directorate ll-3 Division of Reactor Projects Illi Office of Nuclear Reactor Regulation Docket: 50-302
Enclosure:
Request for Additional Inforrnation cc w/ enc!: See next page
9 Mr. John Paul Cowan 2
October 2, 1998 The staff has reviewed the May 1 and July 29,1997, responses to GL 97-01, 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 requested information is identified in the enclosed request for additional information (RAl),
A response to this RAIis requested within 90 days of the date of this letter. It should be noted t
that similar ttaff requests have been issued to the other B&WOG member utilities. This RAI and the requested response date were discussed and agreed to by Mr. Tim Catchpole of your staff.
As was the staff's position before, the staff encourages you to addre's these inquines in an integrated fashion with the B&WOG; however, the sta,'f 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 effort expended with respect to this matter.
Sincerely, Original signed by:
Leonard A. Wiens, Senior Project Manager Project Directorate 11-3 Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation Docket: 50-302 Enclusure: Request for Additional information cc w/ encl: See next page DISTRIBUTION:
Docket file 2] ACRS PUBLIC OGC Crystal r/f LPlisco, Rll j
JZwolinski JHarold i
FHebdon TSullivan, EMCB LWiens BClayton DOCUMENT NAME: G:\\ CRYSTAL \\GL9701.RAI i
To receive a copy of this document, indicate in the box:
"C" = Copy without attachment / enclosure "E" =
Copy with attachment / enclosure "N" = No copw I
0FFICE PDil 3/PM,_
l4 PDI!-3/LA /) !/
/
l l P0ll 3/D
,)
lC NAME LWiens:cw /f6W BClayton Jr / '.O /Y FHebdon N
DATE 10/ v/98 "
10/ % 98 i
/
10/ t/98 10/ /98
/
OFFICIAL RECORD COPY
gr Mr. John Paul Cowan CRYSTAL RIVER UNIT NO. 3 Florida Power Corporation GENERATING PLANT cc:
Mr. R. Alexander Glenn Chairman Corporate Counsel Board of County Commissioners Florida Power Corporation Citrus County MAC-ASA 110 North Apopka Avenue P.O. Box 14042 Invemess, Florida 34450-4245 St. Petersburg, Florida 33733-4042 Mr. Robert E. Grazio, Director Mr. Charles G. Pardee, Director Nuclear Regulatory Affairs (SA2A)
Nuclear Plant Operations (NA2C)
Florida Power Corporation Florida Power Corporation Crystal River Energy Complex Crystal River Energy Complex 15760 W. Power Line Street 15760 W. Power Line Street Crystal River, Florida 34428-6708 Crystal River, Florida 34428-6708 Senior Resident inspector Mr. Robert B. Borsum Crystal River Unit 3 i
Framatome Technologies Inc.
U.S. Nuclear Regulatory Commiss;on 1700 Rockville Pike, Suite 525 6745 N. Tallahassee Road i
Rockville, Maryland 20852 Crystal River, Florida 34428 Mr. William A. Passetti, Chief Mr. Gregory H. Halnon Department of Health Director, Quality Programs (SA2C)
Bureau of Radiation Control Florida Power Corporation i
2020 Capital Circle, SE, Bin #C21 Crystal River Energy Complex Tallahassee, Florida 32399-1741 15760 W. Power Line Street Crystal River, Florida 34428-6708 Attomey General Depertment of Legs! Affairs Regional Administrator, Region 11 The Capitol U.S. Nuclear Regulatory Commission Tallahassee, Florida 32304 61 Forsyth Street, SW., Suite 23T85 Atlanta, GA 30303-3415 Mr.' Joe Myers, Director Division of Emergency Preparedness Mr. Leonard D. Wert Department of Community Affairs U.S. Nuclear Regulatory Commission 2740 Centerview Drive 61 Forsyth Street, SW., Suite 23T85 Tallahassee, Florida 32399-2100 Atlanta, GA 30303-3415
e _ _ _ _ _ _.
F l
Request for Additional Information for Utilities Participating in the Babceck and Wilcox Owners Group (B&WOG)
Integrated Response to Generic Letter (GL) 97-01, "Degr'adation of CRDM/CEDM Nozzle and Other l
Vessel Closure Head Penetrations" Applicability of Topical Report Number BAW-2301 to the t
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 Babcock & Wilcox Owners Group (B&WOG) plant designs is provided in Appendix B to the report, " Description of GRDM Nozzle PWSCC Inspection and Bepair Strategic Evaluation Model." The GRDM Nozzle PWSCC inspection and Bepair 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 j
multiplicative adjustment 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 l
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.
i Topical Report No. BAW-2301 also provides the B&WOG's inspection schedule and scope for vessel head penetration (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 iusceptibility 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 additionalinspections of the B&W fabricated CRDM penetration nozzles have been scheduled for the 1999 refueling outages (RFOs) 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 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 TMl-1 and ONS-1, the staff requests the fotbwing information:
1.
Provide a description of how the various product forms, material specifications, and heat treatments used to fabricate each CRDM penetration nozzle at Crystal River Unit 3 are handled in the CIRSE model.
i 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 j
methodology.
e 2-3.
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 on the CIRSE model analysis results compiled from the analyses of the CRDM and instrumentation nozzles at the facilities.
\\
l
-