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 proprietarymaterials.
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) (ifavailable)
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 A. Welcome and introductions B.
Background:
Point Beach, Units 1 and 2, reactor vessels C. Reactor vessel evaluation methodologies D. End of current life projections and assumptions E. Extended life projections and assumptions F. Evaluation results submittal G. Public comments H. Meeting adjournment Attachment Point Beach Nuclear Plant, Units 1 and 2
September 4, 2002 MEMORANDUM TO: Samson S. Lee, Chief License Renewal Section License Renewal and Enviror, nental Impacts Program Division of Regulatory. Improvement Programs, NRR FROM: A'-hn J. Henry, Project Manager IRA! - -a.
License Renewal Section License Renewal and Environmental Impacts Program Division of Regulatory Improvement Programs, NRR
SUBJECT:
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 DATE & TIME: Tuesday, September 17, 2002 1:30 p.m. - 3:30 p.m.
LOCATION: U.S. Nuclear Regulatory Commission Two White Flint North 11545 Rockville Pike, Room T2B1 Rockville, Maryland PURPOSE: To discuss reactor vessel evaluation methodologies for the Point Beach, Units 1 and 2, license renewal.
CATEGORY 1:* 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: Participants from the NRC include members of the Office of Nuclear Reactor Regulation (NRR) and Office of Nuclear Reactor Research (RES).
NRC/NRR NRC/RES NMC P.T. Kuo, NRR R. Tregoning, RES R. Newton S. Coffin, NRR J. Knorr M. Mitchell, NRR B. Kemp D. Spaulding, NRR 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
-actor Vessel Evaluation Methodologies oint Beach Nuclear Plant eptember 17, 2002
ýCommitted to-Nuclear Excellence
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Discussion Topics Con im ttud to Nucler Oicalien 0
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 S
Discussion
- Closin cRemarks Reactor Vessel Evaluation Methodology 1
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 Nu cl ea r E* ,, allen 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
CRDM ROD TRAVEL lHOUSING CRDM LATCH
~~HOUSING C=LORE HEWD OCME SAFE END NOZZLE SUPPORT PADS 37' 7-19/14" (11,4A2.9 mm)
""*INSTRUMEENTATIONTUBE 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 7-19-1967 7-25-1968
- ing License Fuel Load 11-16-1971 1% Power 5-25-1972 20% Power 7-28-1972 Full Power 10-5-1970 3-8-1973 Year License +40 +40 netric Power Increase Under Review Under Review lower Increase Future Future iration 10-5-2010 3-8-2013
+20 Operation +20 +20 10-5-2030 3-8-2033 Reactor Vessel Evaluation Methodology 5
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 NuclearEc henc.e 1999 Evaluation Unit I Unit 2 Limiting Location I/L Circ. Weld I/L Circ Weld EFPY 48(0) 48(0)
Surface Fluence (1019 n/cm 2) 3.38(0) 3.42(0)
Copper Content (%) 0.23 0.26 Nickel Content (%) 0.59 0.60 Initial Ref. NDT Temperature (OF) 10 -5 RTPTS Temperature (OF) 287(2) 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 EOLE EOLE EOLE 1 1 2 3 4 34 53 53 53 53 luence (1019 n/cm 2) 3.13 5.085 5.085 5.085 5.085 re (OF) -5 -5 -30 -38 (OF) 298 316 284 252 229 ins:
Location I/L Circ Weld ntent (%) 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 NU Ou r EtC4 C ne
- 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 NuclarE~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 NuclaarExcehance
- NMC Remarks e NRC Remarks Reactor Vessel Evaluation Methodology