ML082610507: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
 
(2 intermediate revisions by the same user not shown)
Line 2: Line 2:
| number = ML082610507
| number = ML082610507
| issue date = 09/18/2008
| issue date = 09/18/2008
| title = St. Lucie, Unit 1, Request for Additional Information on Relief Request for Structural Weld Overlays
| title = Request for Additional Information on Relief Request for Structural Weld Overlays
| author name = Mozafari B L
| author name = Mozafari B
| author affiliation = NRC/NRR/DORL/LPLII-2
| author affiliation = NRC/NRR/DORL/LPLII-2
| addressee name = Stall J A
| addressee name = Stall J
| addressee affiliation = Florida Power & Light Co
| addressee affiliation = Florida Power & Light Co
| docket = 05000335
| docket = 05000335
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:September 18, 2008 Mr. J. A. Stall Senior Vice president, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 1400 Juno Beach, Florida 33408-0420  
{{#Wiki_filter:September 18, 2008 Mr. J. A. Stall Senior Vice president, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 1400 Juno Beach, Florida 33408-0420


==SUBJECT:==
==SUBJECT:==
REQUEST FOR ADDITIONAL INFORMATION - ST. LUCIE PLANT, UNIT 1 - RELIEF REQUEST FOR STRUCTURAL WELD OVERLAYS (TAC NO. MD9256)  
REQUEST FOR ADDITIONAL INFORMATION - ST. LUCIE PLANT, UNIT 1 -
RELIEF REQUEST FOR STRUCTURAL WELD OVERLAYS (TAC NO. MD9256)


==Dear Mr. Stall:==
==Dear Mr. Stall:==


By letter dated April 29, 2008, Florida Power & Light Company (FPL) submitted Relief Request Number 2 (RR-2), related to the fourth 10-year inservice inspection interval for the St. Lucie, Unit 1. In RR-2, FPL requested approval to install full structural weld overlays as an alternative method of repair on dissimilar metal butt welds. We have reviewed the submittal and have determined that we need additional information before we can complete our review. Enclosed is our request for additional information.  
By letter dated April 29, 2008, Florida Power & Light Company (FPL) submitted Relief Request Number 2 (RR-2), related to the fourth 10-year inservice inspection interval for the St. Lucie, Unit 1. In RR-2, FPL requested approval to install full structural weld overlays as an alternative method of repair on dissimilar metal butt welds. We have reviewed the submittal and have determined that we need additional information before we can complete our review. Enclosed is our request for additional information.
This request was discussed with Mr. Ken Frehafer of your staff on September 16, 2008. It was agreed that a final response would be provided by September 26, 2008. If you have any questions, please feel free to contact me at 301-415-2020.
Sincerely,
                                              /RA/
Brenda L. Mozafari, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-335


This request was discussed with Mr. Ken Frehafer of your staff on September 16, 2008. It was agreed that a final response would be provided by September 26, 2008. If you have any questions, please feel free to contact me at 301-415-2020.
==Enclosure:==
 
Request for Additional Information cc: See next page
Sincerely,        /RA/        Brenda L. Mozafari, Senior Project Manager Plant Licensing Branch II-2      Division of Operating Reactor Licensing      Office of Nuclear Reactor Regulation Docket No. 50-335


==Enclosure:==
REQUEST FOR ADDITIONAL INFORMATION ST. LUCIE NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-335 By letter dated April 29, 2008, Florida Power & Light proposed an alternative Relief Request 2 (RR-2) to the requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, for mitigating primary water stress corrosion cracking on dissimilar metal welds using full structural weld overlays at St. Lucie, Unit 1 (SL-1).
Request for Additional Information cc: See next page
Currently, the U.S. Nuclear Regulatory Commission (NRC) staff has approved the use of ASME Section XI Code Cases N-504-3, Alternative Rules for Repair of Class 1, 2, and 3 Austenitic Stainless Steel Piping Section XI, Division 1,: and N-638-1, Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW Temper Bead Technique Section XI, Division 1.
The NRC staff used the requirements of Code Cases N-504-3 and N-638-1 and NRC-approved criteria associated with similar full structural weld overlay (SWOL) applications to aid in the evaluation of the SL-1, RR-2, Attachment 2. To complete its review, the staff is requesting the following additional information:
: 1. Discuss whether the subject nozzles have been ultrasonically examined under the Inservice Inspection (ISI) program or Electric Power Research Institute report, MRP-139 in previous refueling outages. If so, discuss whether flaws have been detected in the subject nozzles.
: 2. In Section 1.1, page 1, the Examination Category for the subject welds is identified as R-A. This is a risk-informed ISI (RI-ISI) examination category.
(A)    Discuss whether after the weld overlay installation, will the ISI examinations be based on the RI-ISI program or the proposed Relief Request No. 2 (RR-2)?
(B)    Discuss whether the subject welds will be removed from the RI-ISI program after the weld overlay installation.
: 3. Paragraph 2(a) of Attachment 2 of RR-2 states that the size of all flaws detected or postulated in the original weldment shall be projected to the end of the expected life of the overlay. Provide/describe the expected life of the overlay.
: 4. Paragraphs g(2) and g(3) of American Society of Mechanical Engineers (ASME) Code Case N-504-3 require evaluations of residual stresses and flaw growth of the repaired weldments. Section 2 of Attachment 2 to RR-2 requires similar evaluations.
Section 2(b)7 of Attachment 2 states that effects of any changes in applied loads, as a result of weld shrinkage from the entire structural weld overlay on other items in the piping system, shall be evaluated.
(A)    Confirm that the analysis will be performed to show that the requirements of Subarticles NB-3200 and NB-3600 of the ASME Code, Section Ill are satisfied.


REQUEST FOR ADDITIONAL INFORMATION ST. LUCIE NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-335 By letter dated April 29, 2008, Florida Power & Light proposed an alternative Relief Request 2 (RR-2) to the requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, for mitigating primary water stress corrosion cracking on dissimilar metal welds using full structural weld overlays at St. Lucie, Unit 1 (SL-1). Currently, the U.S. Nuclear Regulatory Commission (NRC) staff has approved the use of ASME Section XI Code Cases  N-504-3, "Alternative Rules for Repair of Class 1, 2, and 3 Austenitic Stainless Steel Piping Section XI, Division 1,: and N-638-1, "Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW Temper Bead Technique Section XI, Division 1."  The NRC staff used the requirements of Code Cases N-504-3 and N-638-1 and NRC-approved criteria associated with similar full structural weld overlay (SWOL) applications to aid in the evaluation of the SL-1, RR-2, Attachment 2. To complete its review, the staff is requesting the following additional information: 1. Discuss whether the subject nozzles have been ultrasonically examined under the Inservice Inspection (ISI) program or Electric Power Research Institute report, MRP-139 in previous refueling outages. If so, discuss whether flaws have been detected in the subject nozzles. 2. In Section 1.1, page 1, the Examination Category for the subject welds is identified as R-A. This is a risk-informed ISI (RI-ISI) examination category.  (A) Discuss whether after the weld overlay installation, will the ISI examinations be based on the RI-ISI program or the proposed Relief Request No. 2 (RR-2)? (B) Discuss whether the subject welds will be removed from the RI-ISI program after the weld overlay installation. 3. Paragraph 2(a) of Attachment 2 of RR-2 states that the size of all flaws detected or postulated in the original weldment shall be projected to the end of the expected life of the overlay. Provide/describe the expected life of the overlay. 4. Paragraphs g(2) and g(3) of American Society of Mechanical Engineers (ASME) Code Case N-504-3 require evaluations of residual stresses and flaw growth of the repaired weldments. Section 2 of Attachment 2 to RR-2 requires similar evaluations. Section 2(b)7 of Attachment 2 states that effects of any changes in applied loads, as a result of weld shrinkage from the entire structural weld overlay on other items in the piping system, shall be evaluated.  (A) Confirm that the analysis will be performed to show that the requirements of Subarticles NB-3200 and NB-3600 of the ASME Code, Section Ill are satisfied.  (B) Confirm that the analysis includes the crack-growth calculations to demonstrate that crack growth in the weld overlay or base metal is acceptable and residual stress distribution in the weld overlay and original weld demonstrate favorable stress distribution. (C) The staff requests that the licensee submit the preliminary results of the evaluations prior to entry into Mode 4 from the refueling outage and the final evaluations within 60 days of the plant restart.  
(B)     Confirm that the analysis includes the crack-growth calculations to demonstrate that crack growth in the weld overlay or base metal is acceptable and residual stress distribution in the weld overlay and original weld demonstrate favorable stress distribution.
: 5. Paragraph I-2.1(g)(2) of Mandatory Appendix I of Attachment 2 to RR-2 provides a means of determining an Adjustment Temperature for the welding procedure qualification. This Adjustment Temperature was not a part of Code Case N-638-1 and, therefore, has not been approved by the U.S. Nuclear Regulatory Commission (NRC) staff. Explain the technical basis of this requirement. 6. Section 5.2 of RR-2, states that a barrier layer of austenitic stainless steel filler metal   across the austenitic stainless steel base metal will be used to reduce the risk of cracks.  
(C)     The staff requests that the licensee submit the preliminary results of the evaluations prior to entry into Mode 4 from the refueling outage and the final evaluations within 60 days of the plant restart.
(A) Discuss whether paragraph (e) of Code Case N-504-3 is applicable to the barrier layer if austenitic stainless steel filler metal is applied. Paragraph (e) requires existence of certain delta ferrite content in the welded metal when austenitic stainless steel weld metal is used. (B) Identify the austenitic stainless steel weld filler metal that will be used for the butter layer. (C) Confirm that the Certified Material Test Report (CMTR) for the austenitic stainless steel filler wire shows a minimum delta ferrite of a specified amount. Provide the maximum and minimum delta ferrite content for the heat of austenitic stainless steel filler wire to be used, as stated on the CMTR. 7. What are the beginning and end dates for the fourth 10-year ISI interval at SL-1? 8. The following typographical errors were identified in the proposed alternative and should be corrected: (A) On page 6, on the second line of the first full paragraph 2(b)(6) should be 2(b)(5), on the third line of the same paragraph 2(b)(7) should be 2(b)(6), on the eighth line of the paragraph 2(a)(2)(b) should be 2(a)(2)(a). (B) On page 25, Section 2(a)(2)(b) in the third line "(b) or (c) above" should be deleted. (C) On page 26, Section 2(b)(6) in the sixth line 2(b)(4), (5), or (6) should be 2(b)(3), (4), or (5). (D) On page 36, Section I-2.1(f) should be changed to I-2.1(f)(4). 9. Mandatory Appendix I to Attachment 2 of RR-2 Section I-3(e) lists a number of methods that can be used in the welding procedure to determine interpass temperature. The staff's position is that the temperature measurement in 1-3(e)(1) should be used. If 1-3(e)(1) cannot be performed, 1-3(e)(2) or 1-3(e)(3) may be used. Please describe the method that will be used at SL-1 and provide a discussion of its acceptability. 10. Section 3(c)2 of Attachment 2 of RR-2 states no credit can be given in any portion of the examination volume where the ultrasonic beam passes through the cast stainless steel material.   (A) Provide the weld overlay thickness. (B) Provide reduction in ultrasonic testing (UT) volume coverage for the weld overlay locations that involve cast stainless steel safe-ends, including estimated total UT examination coverage for preservice and ISI per sections 3(b) and 3(c) of RR-2. Discuss why reduction in examination coverage is acceptable. (C) Discuss whether a phased-array UT technique will be used in the volumetric examination. 11. Attachment 2 of RR-2, page 23, first paragraph, states that, "All Section XI references are to the 2004 Edition with the 2006 Addenda . . . ."  This statement is not applicable to SL-1 and should be eliminated because the code of record for the SL-1 fourth 10-year ISI interval in which RR-2 is applicable is the 2001 Edition through 2003 Addenda. In addition, Table 1 of Attachment 2 can be deleted since the additional code references do not apply. The staff notes that the NRC has not incorporated by reference the 2005 and 2006 Addenda of the ASME Code in Title 10, Code of Federal Regulations, Section 50.55a. 12. Section 2.0 of Attachment 2 of RR-2 states that the code of record for the current ISI 10-year interval is, "Section XI, 2001 Edition including Addenda through 2003 and 2001 with 2001 Addenda for Appendix VIII . . . ."  Please clarify the ASME Code Edition and Addenda that will be used for performance demonstration initiative examination per the ASME Code, Section XI, Appendix VIII because the 2001 Addenda of the ASME Code do not exist.  
: 5. Paragraph I-2.1(g)(2) of Mandatory Appendix I of Attachment 2 to RR-2 provides a means of determining an Adjustment Temperature for the welding procedure qualification. This Adjustment Temperature was not a part of Code Case N-638-1 and, therefore, has not been approved by the U.S. Nuclear Regulatory Commission (NRC) staff. Explain the technical basis of this requirement.
: 6. Section 5.2 of RR-2, states that a barrier layer of austenitic stainless steel filler metal across the austenitic stainless steel base metal will be used to reduce the risk of cracks.
(A)     Discuss whether paragraph (e) of Code Case N-504-3 is applicable to the barrier layer if austenitic stainless steel filler metal is applied. Paragraph (e) requires existence of certain delta ferrite content in the welded metal when austenitic stainless steel weld metal is used.
(B)     Identify the austenitic stainless steel weld filler metal that will be used for the butter layer.
(C)     Confirm that the Certified Material Test Report (CMTR) for the austenitic stainless steel filler wire shows a minimum delta ferrite of a specified amount.
Provide the maximum and minimum delta ferrite content for the heat of austenitic stainless steel filler wire to be used, as stated on the CMTR.
: 7. What are the beginning and end dates for the fourth 10-year ISI interval at SL-1?
: 8. The following typographical errors were identified in the proposed alternative and should be corrected:
(A)     On page 6, on the second line of the first full paragraph 2(b)(6) should be 2(b)(5),
on the third line of the same paragraph 2(b)(7) should be 2(b)(6), on the eighth line of the paragraph 2(a)(2)(b) should be 2(a)(2)(a).
(B)     On page 25, Section 2(a)(2)(b) in the third line (b) or (c) above should be deleted.
(C)     On page 26, Section 2(b)(6) in the sixth line 2(b)(4), (5), or (6) should be 2(b)(3),
(4), or (5).
(D)     On page 36, Section I-2.1(f) should be changed to I-2.1(f)(4).
: 9. Mandatory Appendix I to Attachment 2 of RR-2 Section I-3(e) lists a number of methods that can be used in the welding procedure to determine interpass temperature. The staffs position is that the temperature measurement in 1-3(e)(1) should be used. If 1-3(e)(1) cannot be performed, 1-3(e)(2) or 1-3(e)(3) may be used. Please describe the method that will be used at SL-1 and provide a discussion of its acceptability.
: 10. Section 3(c)2 of Attachment 2 of RR-2 states no credit can be given in any portion of the examination volume where the ultrasonic beam passes through the cast stainless steel material.
(A)     Provide the weld overlay thickness.
(B)     Provide reduction in ultrasonic testing (UT) volume coverage for the weld overlay locations that involve cast stainless steel safe-ends, including estimated total UT examination coverage for preservice and ISI per sections 3(b) and 3(c) of RR-2.
Discuss why reduction in examination coverage is acceptable.
(C)     Discuss whether a phased-array UT technique will be used in the volumetric examination.
: 11. Attachment 2 of RR-2, page 23, first paragraph, states that, All Section XI references are to the 2004 Edition with the 2006 Addenda . . . . This statement is not applicable to SL-1 and should be eliminated because the code of record for the SL-1 fourth 10-year ISI interval in which RR-2 is applicable is the 2001 Edition through 2003 Addenda. In addition, Table 1 of Attachment 2 can be deleted since the additional code references do not apply. The staff notes that the NRC has not incorporated by reference the 2005 and 2006 Addenda of the ASME Code in Title 10, Code of Federal Regulations, Section 50.55a.
: 12. Section 2.0 of Attachment 2 of RR-2 states that the code of record for the current ISI 10-year interval is, Section XI, 2001 Edition including Addenda through 2003 and 2001 with 2001 Addenda for Appendix VIII . . . . Please clarify the ASME Code Edition and Addenda that will be used for performance demonstration initiative examination per the ASME Code, Section XI, Appendix VIII because the 2001 Addenda of the ASME Code do not exist.


September 18, 2008 Mr. J. A. Stall Senior Vice president, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 1400 Juno Beach, Florida 33408-0420  
September 18, 2008 Mr. J. A. Stall Senior Vice president, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 1400 Juno Beach, Florida 33408-0420


==SUBJECT:==
==SUBJECT:==
REQUEST FOR ADDITIONAL INFORMATION - ST. LUCIE PLANT, UNIT 1 - RELIEF REQUEST FOR STRUCTURAL WELD OVERLAYS (TAC NO. MD9256)  
REQUEST FOR ADDITIONAL INFORMATION - ST. LUCIE PLANT, UNIT 1 -
RELIEF REQUEST FOR STRUCTURAL WELD OVERLAYS (TAC NO. MD9256)


==Dear Mr. Stall:==
==Dear Mr. Stall:==


By letter dated April 29, 2008, Florida Power & Light Company (FPL) submitted Relief Request Number 2 (RR-2), related to the fourth 10-year inservice inspection interval for the St. Lucie, Unit 1. In RR-2, FPL requested approval to install full structural weld overlays as an alternative method of repair on dissimilar metal butt welds. We have reviewed the submittal and have determined that we need additional information before we can complete our review. Enclosed is our request for additional information.
By letter dated April 29, 2008, Florida Power & Light Company (FPL) submitted Relief Request Number 2 (RR-2), related to the fourth 10-year inservice inspection interval for the St. Lucie, Unit 1. In RR-2, FPL requested approval to install full structural weld overlays as an alternative method of repair on dissimilar metal butt welds. We have reviewed the submittal and have determined that we need additional information before we can complete our review. Enclosed is our request for additional information.
This request was discussed with Mr. Ken Frehafer of your staff on September 16, 2008, it was agreed that a final response would be provided by September 26, 2008. If you have any questions, please feel free to contact me at 301-415-2020.  
This request was discussed with Mr. Ken Frehafer of your staff on September 16, 2008, it was agreed that a final response would be provided by September 26, 2008. If you have any questions, please feel free to contact me at 301-415-2020.
 
Sincerely,
Sincerely,       /RA/
                                              /RA/
Brenda L. Mozafari, Senior Project Manager       Plant Licensing Branch II-2       Division of Operating Reactor Licensing       Office of Nuclear Reactor Regulation  
Brenda L. Mozafari, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-335
 
Docket No. 50-335  


==Enclosure:==
==Enclosure:==
Request for Additional Information cc: See next page DISTRIBUTION
Request for Additional Information cc: See next page DISTRIBUTION:
: PUBLIC   RidsOgcRp   RidsNrrDorlDpr LPL2-2 R/F   RidsAcrsAcnwMailCenter RidsNrrDciCpnb RidsNrrPMBMozafari   RidsRgn2MailCenter   K. Hoffman RidsNrrLABClayton (Hard Copy) RidsNrrDorlLpl2-2   T. Chan ADAMS Accession Number:   ML082610507     NRR-088 OFFICE LPL2-2/PM LPL2-2/PM LPL2-2/LA DCI/CPNB LPL2-2/BC NAME TOrf BMozafari BClayton TChan By memo dated TBoyce (BMoroney for) DATE   9/18/08 9/18/08   9/18/08 9/18/08   9/18/08 OFFICIAL RECORD COPY Florida Power and Light Company  ST. LUCIE PLANT cc:Mr. Mano Nazar Senior Vice President      and Nuclear Chief Operating Officer  Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408 Senior Resident Inspector    St. Lucie Plant              U.S. Nuclear Regulatory Commission P.O. Box 6090 Jensen Beach, Florida  34957 Craig Fugate, Director  Division of Emergency Preparedness Department of Community Affairs 2740 Centerview Drive          Tallahassee, Florida 32399-2100 M. S. Ross, Managing Attorney  Florida Power & Light Company P.O. Box 14000 Juno Beach, FL  33408-0420                        Marjan Mashhadi, Senior Attorney Florida Power & Light Company 801 Pennsylvania Avenue, NW. Suite 220 Washington, DC 20004 Mr. Douglas Anderson County Administrator  St. Lucie County 2300 Virginia Avenue      Fort Pierce, Florida 34982                            Mr. William A. Passetti, Chief Department of Health Bureau of Radiation Control 2020 Capital Circle, SE, Bin #C21 Tallahassee, Florida  32399-1741 Mr. Gordon L. Johnston Site Vice President St. Lucie Nuclear Plant          6351 South Ocean Drive              Jensen Beach, Florida  34957-2000 Mr. Christopher R. Costanzo Plant General Manager        St. Lucie Nuclear Plant        6351 South Ocean Drive Jensen Beach, Florida  34957 Mr. Terry Patterson Licensing Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida  34957
PUBLIC                                 RidsOgcRp                             RidsNrrDorlDpr LPL2-2 R/F                             RidsAcrsAcnwMailCenter               RidsNrrDciCpnb RidsNrrPMBMozafari                     RidsRgn2MailCenter                   K. Hoffman RidsNrrLABClayton (Hard Copy)         RidsNrrDorlLpl2-2                     T. Chan ADAMS Accession Number: ML082610507                                                 NRR-088 OFFICE LPL2-2/PM LPL2-2/PM               LPL2-2/LA       DCI/CPNB             LPL2-2/BC TChan                TBoyce NAME       TOrf         BMozafari       BClayton       By memo dated         (BMoroney for)
 
DATE         9/18/08     9/18/08         9/18/08       9/18/08                 9/18/08 OFFICIAL RECORD COPY
Don E. Grissette Vice President, Nuclear Operations, South Region  Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Abdy Khanpour Vice President - Engineering Support Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. J. Kammel Radiological Emergency      Planning Administrator Department of Public Safety 6000 Southeast Tower Drive Stuart, Florida 34997


Mark E. Warner Vice President, Nuclear Plant support Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Peter Wells, Acting VP, Nuclear Training and Performance Improvement Florida Power & Light Company P.O. Box 14000 Juno Beach, FL 33408-0420 Mr. Michael Page Acting Operations Manager St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, Florida 34957-2000}}
Florida Power and Light Company        ST. LUCIE PLANT cc:
Mr. Mano Nazar                          Mr. Christopher R. Costanzo Senior Vice President                  Plant General Manager and Nuclear Chief Operating Officer St. Lucie Nuclear Plant Florida Power & Light Company          6351 South Ocean Drive P.O. Box 14000                          Jensen Beach, Florida 34957 Juno Beach, FL 33408 Mr. Terry Patterson Senior Resident Inspector              Licensing Manager St. Lucie Plant                        St. Lucie Nuclear Plant U.S. Nuclear Regulatory Commission      6351 South Ocean Drive P.O. Box 6090                          Jensen Beach, Florida 34957 Jensen Beach, Florida 34957 Don E. Grissette Craig Fugate, Director                  Vice President, Nuclear Operations, Division of Emergency Preparedness      South Region Department of Community Affairs        Florida Power & Light Company 2740 Centerview Drive                  P.O. Box 14000 Tallahassee, Florida 32399-2100        Juno Beach, FL 33408-0420 M. S. Ross, Managing Attorney          Mr. Abdy Khanpour Florida Power & Light Company          Vice President - Engineering Support P.O. Box 14000                          Florida Power & Light Company Juno Beach, FL 33408-0420              P.O. Box 14000 Juno Beach, FL 33408-0420 Marjan Mashhadi, Senior Attorney Florida Power & Light Company          Mr. J. Kammel 801 Pennsylvania Avenue, NW.            Radiological Emergency Suite 220                                  Planning Administrator Washington, DC 20004                    Department of Public Safety 6000 Southeast Tower Drive Mr. Douglas Anderson                    Stuart, Florida 34997 County Administrator St. Lucie County                        Mark E. Warner 2300 Virginia Avenue                    Vice President, Nuclear Plant support Fort Pierce, Florida 34982              Florida Power & Light Company P.O. Box 14000 Mr. William A. Passetti, Chief          Juno Beach, FL 33408-0420 Department of Health Bureau of Radiation Control            Peter Wells, Acting VP, Nuclear 2020 Capital Circle, SE, Bin #C21      Training and Performance Improvement Tallahassee, Florida 32399-1741        Florida Power & Light Company P.O. Box 14000 Mr. Gordon L. Johnston                  Juno Beach, FL 33408-0420 Site Vice President                    Mr. Michael Page St. Lucie Nuclear Plant                Acting Operations Manager 6351 South Ocean Drive                  St. Lucie Nuclear Plant Jensen Beach, Florida 34957-2000        6351 South Ocean Drive Jensen Beach, Florida 34957-2000}}

Latest revision as of 12:52, 14 November 2019

Request for Additional Information on Relief Request for Structural Weld Overlays
ML082610507
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 09/18/2008
From: Mozafari B
Plant Licensing Branch II
To: Stall J
Florida Power & Light Co
Orf, Tracy J.; NRR/DORL 415-2788
References
TAC MD9256
Download: ML082610507 (6)
v • d • e


Text

September 18, 2008 Mr. J. A. Stall Senior Vice president, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 1400 Juno Beach, Florida 33408-0420

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - ST. LUCIE PLANT, UNIT 1 -

RELIEF REQUEST FOR STRUCTURAL WELD OVERLAYS (TAC NO. MD9256)

Dear Mr. Stall:

By letter dated April 29, 2008, Florida Power & Light Company (FPL) submitted Relief Request Number 2 (RR-2), related to the fourth 10-year inservice inspection interval for the St. Lucie, Unit 1. In RR-2, FPL requested approval to install full structural weld overlays as an alternative method of repair on dissimilar metal butt welds. We have reviewed the submittal and have determined that we need additional information before we can complete our review. Enclosed is our request for additional information.

This request was discussed with Mr. Ken Frehafer of your staff on September 16, 2008. It was agreed that a final response would be provided by September 26, 2008. If you have any questions, please feel free to contact me at 301-415-2020.

Sincerely,

/RA/

Brenda L. Mozafari, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-335

Enclosure:

Request for Additional Information cc: See next page

REQUEST FOR ADDITIONAL INFORMATION ST. LUCIE NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-335 By letter dated April 29, 2008, Florida Power & Light proposed an alternative Relief Request 2 (RR-2) to the requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, for mitigating primary water stress corrosion cracking on dissimilar metal welds using full structural weld overlays at St. Lucie, Unit 1 (SL-1).

Currently, the U.S. Nuclear Regulatory Commission (NRC) staff has approved the use of ASME Section XI Code Cases N-504-3, Alternative Rules for Repair of Class 1, 2, and 3 Austenitic Stainless Steel Piping Section XI, Division 1,: and N-638-1, Similar and Dissimilar Metal Welding Using Ambient Temperature Machine GTAW Temper Bead Technique Section XI, Division 1.

The NRC staff used the requirements of Code Cases N-504-3 and N-638-1 and NRC-approved criteria associated with similar full structural weld overlay (SWOL) applications to aid in the evaluation of the SL-1, RR-2, Attachment 2. To complete its review, the staff is requesting the following additional information:

1. Discuss whether the subject nozzles have been ultrasonically examined under the Inservice Inspection (ISI) program or Electric Power Research Institute report, MRP-139 in previous refueling outages. If so, discuss whether flaws have been detected in the subject nozzles.
2. In Section 1.1, page 1, the Examination Category for the subject welds is identified as R-A. This is a risk-informed ISI (RI-ISI) examination category.

(A) Discuss whether after the weld overlay installation, will the ISI examinations be based on the RI-ISI program or the proposed Relief Request No. 2 (RR-2)?

(B) Discuss whether the subject welds will be removed from the RI-ISI program after the weld overlay installation.

3. Paragraph 2(a) of Attachment 2 of RR-2 states that the size of all flaws detected or postulated in the original weldment shall be projected to the end of the expected life of the overlay. Provide/describe the expected life of the overlay.
4. Paragraphs g(2) and g(3) of American Society of Mechanical Engineers (ASME) Code Case N-504-3 require evaluations of residual stresses and flaw growth of the repaired weldments. Section 2 of Attachment 2 to RR-2 requires similar evaluations.

Section 2(b)7 of Attachment 2 states that effects of any changes in applied loads, as a result of weld shrinkage from the entire structural weld overlay on other items in the piping system, shall be evaluated.

(A) Confirm that the analysis will be performed to show that the requirements of Subarticles NB-3200 and NB-3600 of the ASME Code, Section Ill are satisfied.

(B) Confirm that the analysis includes the crack-growth calculations to demonstrate that crack growth in the weld overlay or base metal is acceptable and residual stress distribution in the weld overlay and original weld demonstrate favorable stress distribution.

(C) The staff requests that the licensee submit the preliminary results of the evaluations prior to entry into Mode 4 from the refueling outage and the final evaluations within 60 days of the plant restart.

5. Paragraph I-2.1(g)(2) of Mandatory Appendix I of Attachment 2 to RR-2 provides a means of determining an Adjustment Temperature for the welding procedure qualification. This Adjustment Temperature was not a part of Code Case N-638-1 and, therefore, has not been approved by the U.S. Nuclear Regulatory Commission (NRC) staff. Explain the technical basis of this requirement.
6. Section 5.2 of RR-2, states that a barrier layer of austenitic stainless steel filler metal across the austenitic stainless steel base metal will be used to reduce the risk of cracks.

(A) Discuss whether paragraph (e) of Code Case N-504-3 is applicable to the barrier layer if austenitic stainless steel filler metal is applied. Paragraph (e) requires existence of certain delta ferrite content in the welded metal when austenitic stainless steel weld metal is used.

(B) Identify the austenitic stainless steel weld filler metal that will be used for the butter layer.

(C) Confirm that the Certified Material Test Report (CMTR) for the austenitic stainless steel filler wire shows a minimum delta ferrite of a specified amount.

Provide the maximum and minimum delta ferrite content for the heat of austenitic stainless steel filler wire to be used, as stated on the CMTR.

7. What are the beginning and end dates for the fourth 10-year ISI interval at SL-1?
8. The following typographical errors were identified in the proposed alternative and should be corrected:

(A) On page 6, on the second line of the first full paragraph 2(b)(6) should be 2(b)(5),

on the third line of the same paragraph 2(b)(7) should be 2(b)(6), on the eighth line of the paragraph 2(a)(2)(b) should be 2(a)(2)(a).

(B) On page 25, Section 2(a)(2)(b) in the third line (b) or (c) above should be deleted.

(C) On page 26, Section 2(b)(6) in the sixth line 2(b)(4), (5), or (6) should be 2(b)(3),

(4), or (5).

(D) On page 36, Section I-2.1(f) should be changed to I-2.1(f)(4).

9. Mandatory Appendix I to Attachment 2 of RR-2 Section I-3(e) lists a number of methods that can be used in the welding procedure to determine interpass temperature. The staffs position is that the temperature measurement in 1-3(e)(1) should be used. If 1-3(e)(1) cannot be performed, 1-3(e)(2) or 1-3(e)(3) may be used. Please describe the method that will be used at SL-1 and provide a discussion of its acceptability.
10. Section 3(c)2 of Attachment 2 of RR-2 states no credit can be given in any portion of the examination volume where the ultrasonic beam passes through the cast stainless steel material.

(A) Provide the weld overlay thickness.

(B) Provide reduction in ultrasonic testing (UT) volume coverage for the weld overlay locations that involve cast stainless steel safe-ends, including estimated total UT examination coverage for preservice and ISI per sections 3(b) and 3(c) of RR-2.

Discuss why reduction in examination coverage is acceptable.

(C) Discuss whether a phased-array UT technique will be used in the volumetric examination.

11. Attachment 2 of RR-2, page 23, first paragraph, states that, All Section XI references are to the 2004 Edition with the 2006 Addenda . . . . This statement is not applicable to SL-1 and should be eliminated because the code of record for the SL-1 fourth 10-year ISI interval in which RR-2 is applicable is the 2001 Edition through 2003 Addenda. In addition, Table 1 of Attachment 2 can be deleted since the additional code references do not apply. The staff notes that the NRC has not incorporated by reference the 2005 and 2006 Addenda of the ASME Code in Title 10, Code of Federal Regulations, Section 50.55a.
12. Section 2.0 of Attachment 2 of RR-2 states that the code of record for the current ISI 10-year interval is,Section XI, 2001 Edition including Addenda through 2003 and 2001 with 2001 Addenda for Appendix VIII . . . . Please clarify the ASME Code Edition and Addenda that will be used for performance demonstration initiative examination per the ASME Code,Section XI, Appendix VIII because the 2001 Addenda of the ASME Code do not exist.

September 18, 2008 Mr. J. A. Stall Senior Vice president, Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 1400 Juno Beach, Florida 33408-0420

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - ST. LUCIE PLANT, UNIT 1 -

RELIEF REQUEST FOR STRUCTURAL WELD OVERLAYS (TAC NO. MD9256)

Dear Mr. Stall:

By letter dated April 29, 2008, Florida Power & Light Company (FPL) submitted Relief Request Number 2 (RR-2), related to the fourth 10-year inservice inspection interval for the St. Lucie, Unit 1. In RR-2, FPL requested approval to install full structural weld overlays as an alternative method of repair on dissimilar metal butt welds. We have reviewed the submittal and have determined that we need additional information before we can complete our review. Enclosed is our request for additional information.

This request was discussed with Mr. Ken Frehafer of your staff on September 16, 2008, it was agreed that a final response would be provided by September 26, 2008. If you have any questions, please feel free to contact me at 301-415-2020.

Sincerely,

/RA/

Brenda L. Mozafari, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-335

Enclosure:

Request for Additional Information cc: See next page DISTRIBUTION:

PUBLIC RidsOgcRp RidsNrrDorlDpr LPL2-2 R/F RidsAcrsAcnwMailCenter RidsNrrDciCpnb RidsNrrPMBMozafari RidsRgn2MailCenter K. Hoffman RidsNrrLABClayton (Hard Copy) RidsNrrDorlLpl2-2 T. Chan ADAMS Accession Number: ML082610507 NRR-088 OFFICE LPL2-2/PM LPL2-2/PM LPL2-2/LA DCI/CPNB LPL2-2/BC TChan TBoyce NAME TOrf BMozafari BClayton By memo dated (BMoroney for)

DATE 9/18/08 9/18/08 9/18/08 9/18/08 9/18/08 OFFICIAL RECORD COPY

Florida Power and Light Company ST. LUCIE PLANT cc:

Mr. Mano Nazar Mr. Christopher R. Costanzo Senior Vice President Plant General Manager and Nuclear Chief Operating Officer St. Lucie Nuclear Plant Florida Power & Light Company 6351 South Ocean Drive P.O. Box 14000 Jensen Beach, Florida 34957 Juno Beach, FL 33408 Mr. Terry Patterson Senior Resident Inspector Licensing Manager St. Lucie Plant St. Lucie Nuclear Plant U.S. Nuclear Regulatory Commission 6351 South Ocean Drive P.O. Box 6090 Jensen Beach, Florida 34957 Jensen Beach, Florida 34957 Don E. Grissette Craig Fugate, Director Vice President, Nuclear Operations, Division of Emergency Preparedness South Region Department of Community Affairs Florida Power & Light Company 2740 Centerview Drive P.O. Box 14000 Tallahassee, Florida 32399-2100 Juno Beach, FL 33408-0420 M. S. Ross, Managing Attorney Mr. Abdy Khanpour Florida Power & Light Company Vice President - Engineering Support P.O. Box 14000 Florida Power & Light Company Juno Beach, FL 33408-0420 P.O. Box 14000 Juno Beach, FL 33408-0420 Marjan Mashhadi, Senior Attorney Florida Power & Light Company Mr. J. Kammel 801 Pennsylvania Avenue, NW. Radiological Emergency Suite 220 Planning Administrator Washington, DC 20004 Department of Public Safety 6000 Southeast Tower Drive Mr. Douglas Anderson Stuart, Florida 34997 County Administrator St. Lucie County Mark E. Warner 2300 Virginia Avenue Vice President, Nuclear Plant support Fort Pierce, Florida 34982 Florida Power & Light Company P.O. Box 14000 Mr. William A. Passetti, Chief Juno Beach, FL 33408-0420 Department of Health Bureau of Radiation Control Peter Wells, Acting VP, Nuclear 2020 Capital Circle, SE, Bin #C21 Training and Performance Improvement Tallahassee, Florida 32399-1741 Florida Power & Light Company P.O. Box 14000 Mr. Gordon L. Johnston Juno Beach, FL 33408-0420 Site Vice President Mr. Michael Page St. Lucie Nuclear Plant Acting Operations Manager 6351 South Ocean Drive St. Lucie Nuclear Plant Jensen Beach, Florida 34957-2000 6351 South Ocean Drive Jensen Beach, Florida 34957-2000

Retrieved from "https://kanterella.com/w/index.php?title=ML082610507&oldid=2153272"