ML022610276
| ML022610276 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/17/2002 |
| From: | Henry A NRC/NRR/DRIP/RLEP |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML022610276 (15) | |
Text
NRC FORM 658 U.S. NUCLEAR REGULATORY COMMISSION (9-1999)
TRANSMITTAL OF MEETING HANDOUT MATERIALS FOR IMMEDIATE PLACEMENT IN THE PUBLIC DOMAIN This form is to be filled out (typed or hand-printed) by the person who announced the meeting (i.e., the person who issued the meeting notice). The completed form, and the attached copy of meeting handout materials, will be sent to the Document Control Desk on the same day of the meeting; under no circumstances will this be done later than the working day after the meeting.
Do not include proprietary materials.
DATE OF MEETING The attached document(s), which was/were handed out in this meeting, is/are to be placed 09/17/2002 in the public domain as soon as possible. The minutes of the meeting will be issued in the near future. Following are administrative details regarding this meeting:
Docket Number(s) 50-266 & 50-301 Plant/Facility Name Point Beach Nuclear Plant, Units 1 and 2 TAG Number(s) (if available)
Reference Meeting Notice ML022470347 Purpose of Meeting (copy from meeting notice)
To discuss reactor vessel evaluation methodologies for Point Beach, Units 1 and 2 NAME OF PERSON WHO ISSUED MEETING NOTICE TITLE Alvin J. Henry Project Manager OFFICE NRR DIVISION DRIP BRANCH RLEP Distribution of this form and attachments:
Docket File/Central File PUBLIC NRC FORM 658 (9-1999)
PRINTED ON RECYCLED PAPER This form was designed using InFormns
Tuesday, September 17, 2002 1:30 p.m. - 3:30 p.m.
AGENDA Welcome and introductions
Background:
Point Beach, Units 1 and 2, reactor vessels Reactor vessel evaluation methodologies End of current life projections and assumptions Extended life projections and assumptions Evaluation results submittal Public comments Meeting adjournment Attachment Point Beach Nuclear Plant, Units 1 and 2 A.
B.
C.
D.
E.
F.
G.
H.
September 4, 2002 MEMORANDUM FROM:
SUBJECT:
DATE & TIME:
LOCATION:
PURPOSE:
CATEGORY 1:*
PARTICIPANTS:
TO: Samson S. Lee, Chief License Renewal Section License Renewal and Enviror, nental Impacts Program Division of Regulatory. Improvement Programs, NRR A'-hn J. Henry, Project Manager IRA!
License Renewal Section License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs, NRR FORTHCOMING MEETING WITH NUCLEAR MANAGEMENT COMPANY (NMC) TO DISCUSS REACTOR VESSEL EVALUATION METHODOLOGIES FOR THE POINT BEACH NUCLEAR PLANT, UNITS 1 and 2, LICENSE RENEWAL Tuesday, September 17, 2002 1:30 p.m. - 3:30 p.m.
U.S. Nuclear Regulatory Commission Two White Flint North 11545 Rockville Pike, Room T2B1 Rockville, Maryland To discuss reactor vessel evaluation methodologies for the Point Beach, Units 1 and 2, license renewal.
This is a Category 1 Meeting. The public is invited to observe this meeting and will have one or more opportunities to communicate with the NRC after the business portion, but before the meeting is adjourned.
Participants from the NRC include members of the Office of Nuclear Reactor Regulation (NRR) and Office of Nuclear Reactor Research (RES).
NRC/NRR P.T. Kuo, NRR S. Coffin, NRR M. Mitchell, NRR D. Spaulding, NRR NRC/RES R. Tregoning, RES NMC R. Newton J. Knorr B. Kemp Docket Nos. 50-266 and 50-301
Attachment:
Agenda cc w/att: See next page MEETING CONTACT: Alvin Henry, NRR 301-415-4014 AJH @nrc.qov
- Commission's Policy Statement on "Enhancing Public Participation in NRC Meetings," 67 Federal Register 36920, May 28, 2002 MEMORANDUM TO: Samson S. Lee, Chief License Renewal Section
- -a.
-actor Vessel Evaluation Methodologies oint Beach Nuclear Plant eptember 17, 2002
ýCommitted to-Nuclear Excellence 7 7,-'
+,_ +++
a_.
..., _..... +
Discussion Topics Con im ttud to Nucler Oicalien g Purposes and 2 Reactor Vessel Background actor Vessel Evaluation Methodologies minal Extended Life Evaluation / Assumptions tended Life Evaluation / Assumptions
.luation Results Submittal - Preferred Methodology Discussion cRemarks Reactor Vessel Evaluation Methodology 1
0 S
- Closin
Meeting Purposes Committed to Nuclear Ekc~eheanc" stablish familiarity with PBNP reactor vessels Discuss fracture toughness evaluation methodologies Apply methodologies to PBNP reactor vessels Discuss preferred methodology
-Discuss method of obtaining NRC approval of methodology i and application to the PBNP reactor vessels
- --Discuss subsequent schedule of activities' Reactor Vessel Evaluation Methodology 2
luUnit I and Unit 2 Reactor Vessels C an am'tt 1: to N u c l ea r E *,, alle n c e
"* PBNP Reactor Pressure Vessel Schematic
" Unit 1
- Manufactured by Babcock and Wilcox (B&W)
- Per 1965 Edition Section III ASME Code
"* Unit 2
- Manufactured initially by B&W, completed by Combustion Engineering
- Per 1968 Edition Section III ASME code through Winter 1968 Addenda
" General Information
- Categorized as a standard Westinghouse 132 inch ID two loop reactor vessel
- Reactor Vessel Shell Plate (Unit 1)
SA-302, Gr. B
- Shell Forging (Unit 2)
A-508 Class II Nozzle Shell & Nozzle Forgings A-508 Class II Cladding, Stainless Weld Rod Type 304 Equivalent
- Thermal Shield and Internals A-240, Type 304
- Insulation SS-SS Foil-SS Reactor Vessel Evaluation Methodology 3
SAFE END NOZZLE SUPPORT PADS 37' 7-19/14" (11,4A2.9 mm)
CRDM ROD TRAVEL lHOUSING CRDM LATCH
~~HOUSING C=LORE HEWD OCME
""*INSTRUMEENTATION TUBE SAFE ENDS BOTTOM MOUNTED INSTRUMENTATION (SEE FIGURE 24-)
Point Beach Reactor Pressure Vessel Schemadc
Point Beach Background Co n*atod to Nuclear EA0el,'I a
Unit 1 Unit 2 1*i"'
n Permit
- ing License Fuel Load 1% Power 20% Power Full Power 7-19-1967 7-25-1968 11-16-1971 5-25-1972 7-28-1972 10-5-1970 3-8-1973 Year License netric Power Increase lower Increase iration Under Review Future 10-5-2010 Under Review Future 3-8-2013 Operation 10-5-2030 3-8-2033 Reactor Vessel Evaluation Methodology 5
+40
+20
+40
+20
+20
Evaluation Methodologies Commtted to Nuclear Excellen
- 1. Current NRC approved methodology 10 CFR 50.61 (RG 1.99 Rev 2)
- 2. Approach endorsed in B&W-2308 Initial RTTO established using fracture toughness data Charpy shift used to account for irradiation effects
- 3. NRC approved Kewaunee Master Curve approach
- 4. Direct measurement Master Curve approach Reactor Vessel Evaluation Methodology 6
Nominal Extended Life Projections / Assumptions Cot rmtted to Nuclear Ec henc. e 1999 Evaluation Limiting Location Unit I I/L Circ. Weld EFPY 48(0)
Unit 2 I/L Circ Weld 48(0)
Surface Fluence (1019 n/cm 2)
Copper Content (%)
Nickel Content (%)
Initial Ref. NDT Temperature (OF)
RTPTS Temperature (OF) 3.38(0) 0.23 0.59 10 287(2) 3.42(0) 0.26 0.60
-5 301(2)
Assumptions:
(1) Current power level, current operating configuration (2) Methodology using Regulatory Guide 1.99 Rev 1 Reactor Vessel Evaluation Methodology 7
Extended Life Evaluation I Assumptions Cornmitted to Nuclear Ekcolonco 2002 Unit2 Evaluation EOL EOLE 1
34 luence (1019 n/cm 2) 3.13 re (OF)
(OF)
-5 298 1
53 EOLE 2
53 EOLE 3
53 EOLE 4
53 5.085 5.085 5.085 5.085
-5 316
-30 284
-38 252 229 ins:
Location ntent (%)
(%)
I/L Circ Weld 0.261 0.602 Power level i
,ases, removal of hafnium neutron suppression assemblies Reactor Vessel Evaluation Methodology 8
Evaluation Results Submittal C'omi*nitod t Ou r EtC4 ne NU C
rq7`rred Methodology Sethod 2: B&W-2308 approach Meets PTS screening criteria for extended operation
-4 Uses B&W methodology which has been submitted to the NRC for review' and approval 7 PBNP would become lead plant for methodology
PBNP Reactor Vessels Submittal Would Include:
Preferred methodology and plant specific results
-- Etxtended operation assumptions for both units
-`Sr -
ciJj@ne capsule program for both units Approval for generic methodology and plant specific results Approval could be referenced for extended operation Reactor Vessel Evaluation Methodology 9
Open Discussion Commirtted to Nuclar E~cehenc
"° Schedule of submittal
"* NRC review time period
"* NRC expectations for lead plant submittal onal discussion items Reactor Vessel Evaluation Methodology 10
Closing Remarks Committed to Nuclaar Excehance
- NMC Remarks e NRC Remarks Reactor Vessel Evaluation Methodology