ML20056H125
| ML20056H125 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/23/1993 |
| From: | Bevan R Office of Nuclear Reactor Regulation |
| To: | Yelverton J ENTERGY OPERATIONS, INC. |
| References | |
| GL-92-01, GL-92-1, TAC-M83430, TAC-M83730, NUDOCS 9309080261 | |
| Download: ML20056H125 (6) | |
Text
August 23, 1993 Dorket Nos. 50-313 aad 50-368 Mr. Jerry W. Yelverton Vice President, Operations AN0 Entergy Operations, Inc.
Route 3 Box 13~G Russellville, Arkansas 72801
Dear Mr. Yelverton:
SUBJECT:
REQUEST FOR ADDITIONAL INF0F,MATION (RAI) REGARDING GENERIC LETTER 92-01, REVISION 1, " REACTOR VESSEL STRUCTURAL INTEGRITY", ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 (ANO-l&2) (TAC NOS. M83730 AND M83430)
By letter dated July 1,1992, Entergy Operations, Inc. submitted their responses to Generic Letter (GL) 92-01 for ANO-l&2. The purpose of GL 92-01 is to obtain information needed to assess compliance with requirements set forth in Appendices G and H to 10 CFR Part 50 and cormitments made in response to GL 88-11 regarding reactor vessel structural integiity. Other regulations requiring compliance are 10 CFR 50.60 and 10 CFR 50.61.
The NRC staff has completed a preliminary review of your responses for ANO-l&2 and has identified additional information needed to continue its review, as discussed in Enclosures 1 and 2.
We request your response within 60 days of receipt of this letter to enable the staff to complete its review in a timely manner.
The reporting requirements contained in this letter affect fewer than ten respondents; therefore, Office of Management and Budget clearance is not required under Public Law 96-511.
Sincerely, ORIGINAL SIGNED BY THOMAS W. ALEXION FOR:
ORIGINAL SIGNED BY:
Roby. B. Bevan, Project Manager Thomas W. Alexion, Project Manager Project Directorate IV-1 Project Directorate IV-1 Division of Reactor Projects III/IV/V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation Office of Nuclear Reactor Regulation
Enclosures:
RAls i
cc w/ enclosures:
See next page DISTRIBUTION:
Docket File NRC & LPDRs PDIV-1 r/f PNoonan JRoe EAdensam HRood RBevan TAlexion MSiemien, 0GC ABeach, RIV DMcDonald 0FC LA/PD4'-DI PM/PD4 ( k PM/PD4 d h (A)D/PITf k I
NAME PNoodan
/f,RBevan/
TAlexion HP,ood W DATE
$/h!f/93
(( $ / /93 I/7393 I f/7393 M
/
/
COPY YES k YES/NO YES/NO YES/NO UFFICIAL RECORD COPY Document Name: AR83430.RAI jI hth Q{ g 9309080261 930823 DR ADOCK 0500 3
[
L' w
August 23, 1993 Dockeit Nos. 50-313 3
and 50-368 Mr. Jerry W. Yelverton Vice President, Operations AN0 Entergy Operations, Inc.
Route 3 Box 137G Russellville, Arkansas 72801
Dear Mr. Yelverton:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING GENERIC LETTER 92-01, REVISION 1, " REACTOR VESSEL STRUCTURAL INTEGRITY", ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 (ANO-1&2) (TAC NOS. M83730 AND M83430)
By letter dated July 1, 1992, Entergy Operations, Inc. submitted their responses to Generic Letter (GL) 92-01 for AN0-1&2.
The purpose of GL 92-01 is to obtain information needed to assess compliance with requirements set forth in Appendices G and H to 10 CFR Part 50 and commitments made in response to GL 88-11 regarding reactor vessel structural integrity. Other regulations requiring compliance are 10 CFR 50.60 and 10 CFR 50.61.
The NRC staff has completed a preliminary review of your responses for ANO-l&2 and has identified additional information needed to continue its review, as discussed in Enclosures 1 and 2.
We request your response within 60 days of receipt of this letter to enable the staff to complete its review in a timely manner.
The reporting requirements contained in this letter affect fewer than ten respondents; therefore, Office of Management and Budget clearance is not required under Public Law 96-511.
Sincerely, ORIGINAL SIGNED BY THOMAS W. ALEXION FOR:
ORIGINAL SIGNED BY:
Roby. B. Bevan, Project Manager Thomas W. Alexion, Project Manager Project Directorate IV-1 Project Directorate IV-1 Division of Reactor Projects III/IV/V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation Office of Nuclear Reactor Regulation
Enclosures:
RAls cc w/ enclosures:
See next page DISTRIBUTION:
Docket File NRC & LPDRs PDIV-1 r/f PNoonan JRoe EAdensam HRood RBevan l
TAlexion MSiemien, OGC ABeach, RIV DMcDonald 0FC LA/PD4 PM/P d h PM/PD4 (A)D/PU d NAME PNoo
[9-RBevan/v\\ w r TAlexion
/,
v (HRood y w
DATE $41i93
(( h/ /93 I/73 3
[ f/13/93 N
/9 COPY YE k YES/NO YES/NO YES/NO OFFICIAL RECORD COPY Document Name: AR83430.RAI
f
,,.y 3
g E
UNITED STATES NUCLEAR REGULATORY COMMISSION k-
,/
wasmNOTON, D.C. M555-@M August 23, 1993 Docket Nos. 50-313 and 50-368 Mr. Jerry W. Yelverton Vice President, Operations ANO Entergy Operations, Inc.
Route 3 Box 137G Russellville, Arkansas 72801
Dear Mr. Yelverton:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING GENERIC LETTER 92-01, REVISION 1, " REACTOR VESSEL STRUCTURAL INTEGRITY", ARKANSAS NUCLEAR ONE, UNITS 1 AND 2 (ANO-l&2) (TAC NOS. M83730 AND M83430)
By letter dated July 1,1992, Entergy Operations, Inc. submitted their responses to Generic Letter (GL) 92-01 for ANO-l&2.
The purpose of GL 92-01
{
is to obtain information needed to assess compliance with requirements set i
forth in Appendices G'and H to 10 CFR Part 50 and commitments made in response to GL 88-11 regarding reactor vessel structural integrity. Other regulations i
requiring compliance are 10 CFR 50.60 and 10 CFR 50.61.
The NRC staff has completed a preliminary review of your responses for ANO-1&2
-l and has identified additional information needed to continue its review, as discussed in Enclosures 1 and 2.
We request your response within 60 days of 1
receipt of this letter to enable the staff to complete its review in a timely manner.
The reporting requirements contained in this letter affect fewer than ten respondents; therefore, Office of Management and Budget clearance is not required under Public Law 96-511.
Sincerely, b(1d
'jy W
~c t
Roby. B. Bevan, Proj ct Manager Thomas W. Alexion, Project Manager Project Directorate IV-1 Project Directorate IV-1 6
1 Division of Reactor Projects III/IV/V Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation Office of Nuclear Reactor Regulation j
Enclosures:
RAls cc w/ enclosures:
See next page
l Mr. Jerry W. Yelverton Entergy Operations, Inc.
Arkansas Nuclear One, Units 1 & 2 i
cc:
Mr. Harry W. Keiser, Executive Vice Mr. John R. McGaha President & Chief Operating Officer Vice President, Operations Support Entergy Operations, Inc.
Entergy Operations, Inc.
P. O. Box 31995 P. O. Box 31995 Jackson, Mississippi 39286 Jackson, Mississippi 39286 Mr. Robert B. McGehee Mr. James J. Fisicaro Wise, Carter, Child & Caraway Director, Licensing P. O. Box 651 Entergy Operations, Inc.
Jackson, Mississippi 39205 Route 3 Box 137G Russellville, Arkansas 72801 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations Mr. Nicholas S. Reynolds ABB Combustion Engineering Nuclear Power Winston & Strawn 12300 Twinbrook Parkway, Suite 330 1400 L Street, N.W.
Rockville, Maryland 20852 Hashington, D.C.
20005-3502 Admiral Kinnaird R. McKee, USN (Ret)
Mr. Robert B. Borsum 214 South Morris Street Licensing Representative Oxford, Maryland 21654 B&W Nuclear Technologies 1700 Rockville Pike, Suite 525 Mr. Michael D. Sellman i
Rockville, Maryland 20852 General Manager, Plant Operations i
Entergy Operations, Inc.
i Senior Resident Inspector Route 3, Box 137G U.S. Nuclear Regulatory Commission Russellville, Arkansas 72801 1 Nuclear Plant Road Russellville, Arkansas 72801 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Honorable C. Doug Luningham County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 Ms. Greta Dicus, Director Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street i
Little Rock, Arkansas 72205-3867 i
l i
J
ENCLOSURE 1 3
Question 2a in GL 92-01 The response to GL 92-01 indicates that the initial upper-shelf energy (USE) value of 123 ft-lb for plate C5120-1 is from report BAW-1820. A review of report BAW-1820 reveals that the initial USE value of plate AYN131 is unknown, and that all plate initial USE values listed there may be from longitudinal Charpy specimens.
Further, Surveillance Report BAW-2075, Rev. I labeled all Charpy data in Table A-1 as
" longitudinal", and Surveillance Report BAW-1440 reported that the initial longitudinal USE value is 132 ft-lb for the surveillance plate C5114-1, close to the 129 ft-lb reported for the same plate in BAW-1820. Confirm orientation and update end-of-life (EOL) USE values for all plates.
For plate AYN131, either provide the Charpy USE or provide the Charpy USE and analysis from materials that were fabricated using the same vendor, fabrication time frame, fabrication process, and material specification to demonstrate that this plate will meet the USE requirements of Appendix G, 10 CFR Part 50.
If this cannot be provided for plate AYN131, or the updated E0L USE values for other plates are below 50 ft-lb based on NRC criteria, then submit an analysis which demonstrates that lower values of USE will provide margins of safety against fracture equivalent to those required by Appendix G of the ASME Code.
The response indicates that the E0L USE value for weld WF-112 will fall below the screening criterion of 50 ft-lb.
An owners group report on USE equivalent margin analysis regarding beltline welds with low USE values for Levels A & B is under preparation by Babcock-Wilcox Owners Group (B&WOG); a similar B&WOG report for Levels C & D (BAW-2178P) is under NRC review now. The licensee must confirm that these two topical reports will be used as its licam;og bases to demonstrate that all beltline welds will meet the U" requirements of Appendix G, 10 CFR Part 50.
Question 2b in GL 92-01 The response provides the chemistry data for all beltline materials except weld SA-1788.
Further investigation reveals that report BAW-1803, Revision 1 lists the copper and nickel contents of weld SA-1788 as 0.25% and 0.54%, while report BAW-2075, Revision I lists them as 0.29% and 0.47%.
Resolve this discrepancy.
The response indicates that a generic initial RT of -5 f, which is the mean RT value for 34 Linde 80 welds (BAW-1Ed3, Revision 1), has m
been used for all welds.
Provide justification for not using the generic mean value for Linde 80 welds of 0 F as required by 10 CFR 50.61.
L=
l ENCLOSURE 2 i
Question 2b in GL 92-01 The response indicates that the initial RT values for plate C8009-1,
-2, C8010-1,
-2, -3, andweld9-203are-2I,y 0, 12, -28, -30, and
-10 *F.
The corresponding values in the pressurized thermal shock submittal dated January 22, 1986, are 2 to 31 degrees higher. The discrepancies were explained in a letter dated May 8,1991, from ABB Combustion Engineering to Entergy Operations that, "The newer values (Reference 1) resulted from a more rigorous application of MTEB 5-2 to the data and the use of baseline surveillance data for the surveillance program plate (TR-MCD-002, March 1976)." Provide details
- . bout this new evaluation and its application to plates C8009-1,
-2, and C8010-3.
i The response reports two initial RT., values for weld 9-203: one is
-40 *F with the identification "9-2$", and ti.e other is -10 *F with the identification "Surv. Weld (Same consumables as 9-203)".
Confirm that the initial RT value of -10 'F will be used in any future RT calculation for welE79-203 consistent with the justification given,in 1
the same letter mentioned above (dated May 8,1991).
i t
a l
1
!