ML20042G201
| ML20042G201 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 05/07/1990 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | Papanic G YANKEE ATOMIC ELECTRIC CO. |
| References | |
| TAC-71570, NUDOCS 9005110222 | |
| Download: ML20042G201 (4) | |
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May 7,1990
,t Docket No. 50 029 Mr. George Papanic, Jr.
Senior Project Engineer. Licensing Yankee Atomic Electric Company 580 Main Street Bolton, Massachusetts 01740 1398
Dear Mr. Papanic:
SUBJECT:
YANKEE R0WE REACTOR VESSEL INTEGRITY (TAC 71570)
As we discussed with Dr. Kadak on May 4, 1990, attached is a list of issues which we would like you to address at our May 9, 1990 meeting on reactor vessel integrity. We recognize that these issues have been transmitted to you with short notice prior to the scheduled meeting.
If you find that you need additional time for preparation, please contact me and we will reschedule L
the meeting for the earliest practical date.
Sincerely, kicha"rdH. "essman, Director Project Directorate 1 3 Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation
Enclosure:
Request for Information i
cc w/ enclosure:
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OFFICIAL RECORD COPY Document Name: YANKEE R0WE TAC 71570 r
lM.110222 900507 h
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ADOCK 05000029 1 f' pdc
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{j Mr. George Papanic, Jr.'
Yankee Rowe Cc:
Dr. Andrew C. Kadak, President and Chief Operating Officer Yankee Atomic Electric Company 580 Main Street Bolton, Massachusetts 01740-1398
. Thomas Dignan, Esquire Ropes and Gray 225 Franklin Street Boston, Massachusetts 02110 Mr. T. K. Henderson Acting Plant. Superintendent Yankee Atomic Electric Company Star Route Rowe, Massachusetts 01367 Resident inspector Yankee Nuclear Power Station U.S. Nuclear Regulatory Comission Post Office Box 28 Monroe Bridge, Massachusetts 01350 Regional Administrator, Region 1 U.S. Nuclear Regulatory Comission 475 Allendale Road King of Prussia, Pennsylvania 19406 l
y Robert M.-Hallisey, Director Radiation Control Program j
1 Massachusetts Department of Public Health 150 Tremont Street. 7th Floor I
L Boston, Massachutettr, 02111 Mr. George Sterzinger i
Comissioner Vermont Department of Public Service 120 State Street, 3rd Floor Montpelier, Vermont 05602 Ms. Jane M. Grant
-Senior Engineer - PLEX Licensing Yankee Atomic Electric Company l
580 Main Street 4
Bolton, Massachusetts 01740-1398
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ENCLOSURE REQUEST FOR INFORMATION 1)
Discuss installation of surveillance capsules in the reactor at accelerated (high flux) positions and at low flux positions.
2)
Discuss-removal of the shield tank or other plant structural changes i
necessary for UT inspection of the beltline.
3)
Provide fabrication history (welding and heat treatment) and inspection (both preservice and inservice) results for beltline materials and for other vessel materials that were fabricated in the same manner as the beltline materials.
4)
Discuss the fabrication history (cross-rolling and heat treatment) of beltline plates. Based on the f abrication history, what is the Charpy Upper S.helf Energy (USE) in the transverse direction for the beltline plates, unirradiated, in 1990 and in 20007 5)
Identify the heats numbers for the weld wire used to fabricate each beltline weld?
Are the heats of wire used to fabricate the Yankee Rowe reactor vessel beltline welds the same as the Belgium Reactor Unit 3 (BR-3) welds?
Based on the heats of wire used, what are the amounts of copper, nickel and phosphorus in each beltline weld? What is the Charpy USE for each beltline weld, unirradiated, in 1990 and in 2000?
l 6)
In NRL Report 6616, it is reported that the Yankee Rowe cold leg temperature was 495'F during cycle 11, 500*F during cycle til and 505'F during cycle IV.
In addition Yankee Rowe produced power during coastdown. At these reactor operating temperatures, the amount of neutron irradiation-embrittlement could be greater than predicted by RG 1.99, Rev.2 and the PTS rule, 50.61.
What is the average. cold leg temperature (excluding coastdown) l during each core cycle?
Does Yankee Rowe still operate with coastdown periods where the cold leg temperature is less than 500*F? When did coastdown operation stop?
What is the accumulated neutron fluence during these coastdown periods?
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7)
Based on BR-3 data in a report by A. Fabry dated October 22, 1983, the increase in reference temperature and decrease in Charpy USE is greater'at 500'F than at 550'F operating temperatures.
Since RG 1.99, Rev. 2 is applicable to plants with nominal irradiation temperatures of 550'F and Yankee Rowe operates below 525'F what is the predicted reference temperature and the Charpy USE for the circumferentiel beltline weld in 1990 and 20007 Provide all data which supports these values.
8)
Based on the Yankee Rowe surveillance data, the increase in reference temperature for the beltline plates could be greater than the values predicted following the tables in RG 1.99, Rev. 2.
Based on its surveillance data, what is the predicted reference temperature for each plate in 1990 and 2000? If there is other data available that Yankee Rowe is relying upon to predict the reference temperature of each plant in the beltline, provide it. Pased on this data, what is the reference temperature for each beltline plate in 1990 and 2000?
9)
Section V.C. in Appendix G, 10 CFR 50 identifies three requirements which must be satisfied to continue operation of a reactor vessel when its Charpy USE falls below 50 ft-lb. Discuss how Yankee Rowe plans to satisfy each of these requirements for the weld metal and plates that are predicted to have Charpy USE less than 50 ft-lb.
- 10) Discuss the need for, benefit and feasibility of performing an anneal at 650*F or 850'F.
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