ML20212J443

Discusses Responses to RAI Re GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity

ML20212J443
Person / Time
Site:	Nine Mile Point
Issue date:	06/25/1999
From:	Hood D NRC (Affiliation Not Assigned)
To:	Mueller J NIAGARA MOHAWK POWER CORP.
References
GL-92-01, GL-92-1, TAC-MA1200, TAC-MA1201, NUDOCS 9907060004
Download: ML20212J443 (6)

Text

.

pNMov Q Y'" 4- UNITED STATES

-g J~ =

,j t

NUCLEAR REGULA'. ORY COMMISSION WASHINGTON, D.C. 20555-0001

%' June 25, 1999 Mr. John H. Mueller Chief Nuclear Officer Niagara Mohawk Power Corporation

Nine Mile Point Nuclear Station -

' Operations Building, Second Floor P.O. Box 63 Lycoming, NY 113093

SUBJECT:

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING -

GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT.1,'" REACTOR VESSEL STRUCTURAL INTEGRITY," NINE MILE POINT NUCLEAR STATION, UNIT NOS.1 AND 2 (TAC NOS. MA1200 and MA1201)

Dear Mr. Mueller:

On May 19,1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 01, Revision 1, Supplement 1, " Reactor Vessel Structural Integrity," to holders of nuclear

)

power plant operating licenses. In that GL, the NRC staff requested that licensees review their -

reactor pressure vessel (RPV) structural integrity assessments in order to:

l (1) . Identify, collect, and report any new data pertinent to the analysis of the structural

~ integrity of their RPVs, and (2) Assess the impact of that data upon their RPV integrity analyses relative to the requirements of Section 50.60 to Part 50 of Title 10 of the Code of Federal Reaulations (10'CFR 50.60),10 CFR 50.61, Appendices G and H to 10 CFR Part 50 (which encompass pressurized thermal shock and upper shelf energy (USE) evaluations), and any potential impact on low temperature overpressure limits or pressure-temperature (P-T) limits.

The NRC staff's review of the responses submitted for each Nine Mile Point unit is separately discussed below: s Nine Mile Point Nuclear Station. Unit 1 (NMP1)

By letter dated August 16,1995, Niagara Mohawk Power Corporation (NMPC) submitted its initial response to GL 92-01, Revision 1, Supplement 1, and provided the requested information ,

relative to the structuralintegrity assessment for.NMP1. The NRC staff evaluated that i response and provided its conclusions by letter dated August 26,1996, noting that additional

~ data to be provided by owners groups could lead to further plant-specific reviews. Since August 26,1996, the Combustion Engineering (CE) Owners Group and the Babcock and

}h Wilcox (B&W) Owners Group have each submitted additional data regarding the alloying chemistries of beltline welds in CE and B&W fabricated vessels. The additional alloying data \

were submitted in Topical Reports CE NPSD-1039, Revision 2, and CE NPSD-1119, Revision 1 4 O\

for CE fabricated RPV welds; and in Topical Reports BAW-2325, Revision 1, for B&W \f fabricated RPV welds, in addition, Chicago Bridge and Iron BWR data are contained in BWR l Vessel and intemals Project's Topical Report BWRVIP-46. On the basis of the efforts by CE R i

s i

.F 9DR g

/

E,_ .

( l and B&W, the'NRC staff determined that additionalinformation was needed regarding the

. structural integrity assessments for NMP1.

By letter dated May 29,1998, the NRC staff requested additional information (RAl) regarding L (1) the alloying chemistries of beltline welds, (2) NMPC's assessment of surveillance data for NMP1, and (3) the impact upon the NMP1 P-T limits. Specifically, the NRC staff requested that NMPC reassess the alloying chemistries for the beltline welds and RPV surveillance welds relative to the chemistries provided in Topical Reports CE NPSD-1039, Revision 2 and CE

.NPSD-1119,' Revision 1, and provide the impact of any changes to the best-estimate

. chemistries for the beltline RPV welds upon the NMP1 structural integrity assessments relative to the requirements of 10 CFR 50.60,10 CFR 50.61, and Appendices G and H to 10 CFR Part 50,' as applicable to the NMP1 licensing bases.

NMPC responded to the NRC staff's RAI for NMP1 by letter dated September 4,1998. On the basis of its review of NMPC's responses to GL 92-01, Revision 1; GL 92-01, Revision 1, Supplement 1; and the Supplement 1 RAI, the NRC staff has revised the information in the RPV: Integrity Database (RVID) and is releasing it as RVID Version 2. Please note that there are some variations in the data inputted by the NRC staff, and the corresponding values that

' NMPC repor1ed in its response to the GL 92-01, Revision 1, Supplement 1 RAI. The deviations between the data are explained in the reference sections for each unit, or the individual component screen notes (i.e., each forging, plate, and weld has a specific area for notes, which is a new feature of the database). They are summarized as follows:

The chemistry data reported in NMPC's response of September 4,1998, for the weld fabricated with weld wire heat 1248 (Weld 1248) has not been implemented by the NRC staff. Although NMPC's report NMEL-90001 (P. L-9) indicates that the surveillance weld is W5214, reports CE NPSD-1039, Revision 2 and CE NPSD-1119, Revision 1, indicate that NMP1's surveillance weld is Weld 1248. NMPC should resolve this dispute with CEOG, reassess the current P-T limits evaluation, and provide its response by September 1,1999. Currently, the chemistry data for Weld 1248, as reported in the RVID, is from NMPC's letter dated August 16,1995.

The new database diskettes are posted on the NRC's internet web page at http://www.nrc. gov /NRR/RVID/index.html. We recommend that NMPC review this information.-

Future submittals on P-T limits, or USE should reference the most current information.

Nine Mile Point Nuclear Station. Unit 2 (NMP2f By letter dated August 16,1995, NMPC submitted its response to GL 92-01, Revision 1, l Supplement 1, and provided the requested information relative to the structural integrity assessment for NMP2. . By letter dated November 20,1995, NMPC supplemented its initial ,

response and evaluated all data relevant to the assessment of NMP2. The NRC staff evaluated l NMPC's response to GL 92-01, Revision 1, Supplement 1, and provided its conclusion by letter  !

dated August 26,1996. Subsequently, the NRC staff has reviewed the information that NMPC

- submitted and has determined that it adequately reflects the information contained in BWRVIP-46, the topical report that provided a bounding assessment for BWR vessel materials.

Therefore, the NRC staff has determined that NMPC's previous response to GL 92-01, l Revision 1, Supplement 1, remains valid for NMP2.

I

f! , .

L

. 1 4

I

' On the basis of its review of NMPC's responses to GL 92-01, Revision 1, and to GL 92-01, Revision 1, Supplement 1, the NRC staff has revised the information in the RVID and is releasing it as RVID Version 2. ~ The new database diskettes are posted on the NRC's internet web page at http://www.nrc. gov /NRR/RVID/index.html. We recommend that NMPC review this information, if the NRC staff does not receive comments by September 1,1999, we will assume that the data entered into the RVID are acceptable for NMP2. No additional information is necessary with regard to the structural integrity assessments. Future submittals on P-T limits or USE should reference the most current information.

Accordingly, for NMP1 and NMP2, the NRC staff concludes that NMPC has adequately _

responded to GL 92-01 as revised and supplemented.~ This completes the NRC staff's efforts under TAC Nos. MA1200 and MA1201 for NMP1 and NMP2, respectively. Thank you for your support in this matter. If you have questions, contact me by phone at 301-415-3049 or by-electronic mail at dsh@nrc. gov.

Sincerely, I

DaJAld,4 Darl S. Hood, Sr. Project Manager, Section 1 Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation l l

Docket Nos. 50-220 and 50-410 j cc: See next page

Nine Mile Point Nuclear Station' l Unit Nos.1 and 2 Regional Administrator, Region l Charles Donaldson, Esquire ,

U.S. Nuclear Regulatory Commission Assistant Attorney General l 475 Allendale Road New York Department of Law King of Prussia, PA 19406 120 Broadway i New York, NY 10271 l Resident inspector U.S. Nuclear Regulatory Commission Mr. Paul D. Eddy .

P.O. Box 126 - State of New York Department of  ;

Lycoming, NY 13093 Public Service  !

Power Division, System Operations i Mr. Jim Rettberg . 3 Empire State Plaza New York State Electric & Gas Albany, NY 12223 Corporation Corporate Drive Mr. Timothy S. Carey Kirkwood Industrial Park Chair and Executive Director P.O. Box 5224 State Consumer Protection Board Binghamton, NY 13902-5224 5 Empire State Plaza, Suite 2101 l Albany, NY 12223 Supervisor Town of Scriba Mark J. Wetterhahn, Esquire Route 8, Box 382. Winston & Strawn Oswego, NY 13126 1400 L Street, NW Washington, DC 20005-3502 )

Mr. Richard Goldsmith Syracuse University Gary D. Wilson, Esquire. .

.. College of Law Niagara Mohawk Power Corporation  !

E.l. White Hall Campus 300 Erie Boulevard West Syracuse, NY 12223 Syracuse, NY 13202 Mr. John V.' Vinquist, MATS Inc. Mr. F. William Valentino, President P.O. Box 63 New York State Energy, Research, Lycoming, NY 13093 and Development Authority Corporate Plaza West ,

286 Washington Avenue Extension Albany, NY 12203-6399 i b

, June'25, 1999 On ths basis of its rivi:w of NMPC's r:sponsts to GL 92-01, Rt. vision 1, and to GL 92-01,

~

R:vi:lon 1, Suppl:m:nt 1, tha NRC str.ff his r:vi:ed tha inform; tion in ths RVID cnd is releasing it as RVID Version 2. The new database diskettes are posted on the NRC's internet web page at http //www.nrc. gov /NRR/RVID/index.html. We recommend that NMPC review this information. if the NRC staff does not receive comments by September 1,1999, we will assume that the data entered into the RVID are acceptable for NMP2. No additional information is necessary with regard to the structuralintegrity assessments. Future submittals on P-T limits or USE should reference the most current information.

Accordingly, for NMP1 and NMP2, the NRC staff concludes that NMPC has adequately responded to GL 92-01 as revised and supplemented. This completes the NRC staff's efforts under TAC Nos. MA1200 and MA1201 for NMP1 and NMP2, respectively. Thank you for your support in this matter. If you have questions, contact me by phone at 301-415-3049 or by electronic mail at dsh@nrc. gov.

i Sincerely, Original signed by:

Darl S. Hood, Sr. Project Manager, Section 1 Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-220 and 50-410 cc: See next page DISTRIBUTION:

gDocket File S. Bajwa A. Lee .

PUBLIC S. Little S.Sheng PDl-1 R/F D. Hood B. Elliot EMCB R/F M. Mitchell l

l l

DOCUMENT NAME: G:\PDI-1\NMP12\GL9201SE.WPD To receive a copy of this document, Indicate in the box: 'C' = Copy without attachment / enclosure 'E' = Copy with attachment / enclosure 'N' = No copy 0FFICE PM:PDI-1 _

lE LA:PDI-13V l D:PDI-1 , @ l l NAME DHood/rsl -p3 It Slittle}.V SBajwa. F F DATE 06/25/99 06/ 8 5/99 06/ 1 6 /99 Official Record Copy

June 25, 1999 k3 . On the bisis of its r;vi:w of NMPC's responses to GL 92-01, R: vision 1, and to GL 92-01, Revision 1, Supplement 1, the NRC staff has revised the information in the RVID and is releasing it as RVID Version 2. The new database dis.cettes are posted on the NRC's internet web page at http//www.nrc. gov /NRR/RVID/index.html. We recommend that NMPC review this information. If the NRC staff does not receive comments by September 1,1999, we will assume that the data entered into the RVID are acceptable for NMP2. No additional information is necessary with regard to the structuralintegrity assessments. Future submittals on P-T limits or USE should reference the most current information.

Accordingly, for NMP1 and NMP2, the NRC staff concludes that NMPC has adequately responded to GL 92-01 as revised and supplemented. This completes the NRC staff's efforts under TAC Nos. MA1200 and MA1201 for NMP1 and NMP2, respectively. Thank you for your support in this matter. If you have questions, contact me by phone at 301-415-3049 or by electronic mail at dsh@nrc. gov.

Sincerely, Original signed by:

Darl S. Hood, Sr. Project Manager, Section 1 Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-220 and 50-410 cc: See next page DISTRIBUTION:

Docket File S. Bajwa A. Lee PUBLIC S. Little S.Sheng PDl 1 R/F D. Hood B. Elliot EMCB R/F M. Mitchell DOCUMENT NAME: G:\PDl-1\NMP1-2\GL9201SE.WPD To receive a copy of this document, indicate in the iwx: "C" = Copy without attachment / enclosure "E" = Copy with attachment /ennosure "N' = No copy 0FFICE PM:PD!-l lE LA:PDI-1pG (___ f D:PDI-l,g% l l NAME DHood/rsi -pS it SLittlejJ' SBajwa F F DATE Gd/p/99 06/6L5/99 06/1,5/99 Official Record Copy L