ML081790067
| ML081790067 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 04/12/2002 |
| From: | Bonaca M Advisory Committee on Reactor Safeguards |
| To: | |
| References | |
| Download: ML081790067 (26) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D.C. 20555*0001 April 12,2002 MEMORANDUM TO:
FROM:
ACRS Members Of j JM;Rb, FoA.
Robert Elliott, Senior Staff Engineer ACRS
SUBJECT:
CERTIFICATION OF THE
SUMMARY
/MINUTES OF THE ACRS SUBCOMMITTEE MEETING ON THE SAFETY EVALUATION REPORT RELATED TO THE LICENSE RENEWAL APPLICATION FOR TURKEY POINT UNITS 3 AND 4, MARCH 13,2002, - FLORIDA CITY, FLORIDA The minutes of the subject meeting, issued on March 18, 2002, have been certified as the official record of the proceedings of that meeting. A copy of the certified minutes is attached.
Attachment:
As stated cc via e-mail:
J. Larkins S. Bahadur ACRS Fellows and Technical Staff cc:
ACRS Secretary E. Barnard (3 copies)
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D.C. 20555-0001 geOJT MEMORANDUM TO: Noel Dudley, Senior Staff Engineer ACRS FROM:
Dr. Mario Bonaca, Chairman Plant License Renewal Subcommittee
SUBJECT:
CERTIFICATION OF THE MINUTES OF THE ACRS SUBCOMMITTEE MEETING ON THE SAFETY EVALUATION REPORT RELATED TO THE LICENSE RENEWAL APPLICATION FOR TURKEY POINT UNITS 3 AND 4, MARCH 13,2002, FLORIDA CITY, FLORIDA I hereby certify that, to the best of my knowledge and belief, the minutes of the sUbject meeting issued on March 18, 2002, are an accurate record of the proceedings for the meeting.
wv,~~~
D. Mario Bonaca, Chairman Plant License Renewal Subcommittee
UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D.C. 20555~0001 March 18, 2002 MEMORANDUM TO: Dr. Mario Bonaca, Chairman
~iBn~e ~~~ewal Subcommittee FROM:
Noel DUdl~Staff Engineer ACRS SUB~IECT:
WORKING COPY OF THE MINUTES OF THE ACRS SUaCOMMIITEE MEETING ON THE SAFETY EVALUATION REPORT RELATED TO THE LICENSE RENEWAL APPLICATION FOR TURKEY POINT UNITS 3 AND 4, MARCH 13,2002, - FLORIDA CITY, FLORIDA A working copy of the minutes for the subject meeting is attached for your review.
would appreciate your review and comment as soon as possible. Copies are being sent to the Plant License Renewal Subcommittee members for information and/or review.
Attachment:
As stated cc:
P. Ford T. Kress W. Shack J. Sieber J.Barton cc via e-mail:
J. Larkins S. Bahadur S. Duraiswamy
Issued:
3118/2002 CE TIF:EO Certified:
4/12/2002 ADVISORY COMMITTEE ON REACTOR SAFEGUARDS MINUTES OF ACRS SUBCOMMITTEE MEETING ON PLANT LICENSE RENEWAL TURKEY POINT UNITS 3 AND 4 MARCH 13, 2002 FLORIDA CITY, FLORIDA The ACRS Subcommittee on Plant License Renewal held a meeting on March 13, 2002, at the City Hall, 404 West Palm Drive, Florida City, Florida. The purpose of the meeting was to review the resolution of the open items identified in the Safety Evaluation Report (SER) related to the license renewal of Turkey Point Nuclear Plant, Units 3 and 4. Mr. Noel Dudley was the cognizant ACRS staff engineer for this meeting. The meeting was convened at 1:30 p.m. and adjourned at 4:30 p.m.
ATTENDEES:
ACRS M. Bonaca, Chairman J. Barton, Consultant P. Ford, Member S. Duraiswamy, ACRS Staff T. Kress, Member N. Dudley, ACRS Staff W. Shack, Member J. Sieber, Member NRC STAFF C. Grimes, NRR C. Julian, Region II R. Auluck, NRR C. Christensen, Region II J. Medoff, NRR FLORIDA POWER AND LIGHT COMPANY E. Abbott, FPL
. B. Beisler, FPL S. Hale, FPL J. Hoffman, FPL S. Collard, FPL J. Chrulski, FPL A member of the public provided written comments. No requests were received for time to make oral statements. One member of the public attended the meeting and made oral statements. A list of meeting attendees is available in the ACRS Office files.
ACRS SUBCOMMITTEE CHAIRMAN'S INTRODUCTION Dr. Mario Bonaca, Chairman of the Plant License Renewal Subcommittee, convened the meeting and stated that the purpose of the meeting was to review the staffs SER related to the license renewal application for Turkey Point Nuclear Plant, Units 3 and 4. He noted that the Subcommittee had reviewed the application and the associated SER with open items on September 25, 2001. Dr. Bonaca read the written comments from a member of the public and requested that the staff reply to the comments. A copy of the written comments are attached. He called upon Mr. Christopher Grimes, Office of Nuclear Reactor Regulations (NRR) to begin.
Plant License Renewal Subcommittee 2
March 13,2002 STAFF PRESENTATION Mr. Christopher Grimes, NRR, thanked the ACRS for its involvement in reviewing the Turkey Point Nuclear Plant license renewal application and associated SER. He then introduced the NRC staff members who would be making the presentation.
Safety Evaluation Report Dr. Raj AuJuck, NRR, summarized the written comments from a public citizen, provided an overview of the design of Turkey Point Nuclear Plant, Units 3 and 4, and outlined the staffs review schedule. He identified the requirements that the staff used to review the application.
The ACRS members and the staff discussed whether the review of the Turkey Point application was more efficient due to the lessons learned during the review of previous license renewal applications.
The staff explained that fewer requests for additional information (RAls) were issued compared to previous applications. However, more time was expended in resolving issues prior the issuance of RAls, and therefor there was no significant gain in overall efficiency.
Dr. Auluck and Mr. James Medoff, NRR, explained the staffs bases for accepting the applicant's resolution of the four open items identified in the SER with open items. The bases included the following:
- 1.
The applicant reevaluated class II non-safety-related piping that could fail due to aging mechanisms, such as erosion/corrosion, and adversely affect safety-related components. For the piping that was determined to meet this criteria, the applicant identified specific aging management programs.
- 2.
The applicant had inspected the intemals of three of the five water tanks, which are in the scope of license renewal. The applicant concluded that the existing coatings would prevent any aging degradation and committed to inspect the intemals of all five tanks prior to the end of the extended period to verify this conclusion.
- 3.
The applicant committed to inspect the penetrations in both reactor vessel heads and to comply with the industry's recommendations for any associated aging management programs, once they are developed.
- 4.
The applicant committed to two renewal application items identified in the Westinghouse report WCAP-15338 concerning reactor pressure vessel underclad cracking. One item was to verify that the number of design cycles and transients assumed in WCAP-15338 bounds the number of cycles for 60 years of operations. The second item was to ensure that the evaluation of the time limited aging analysis (TLAA) is summarily described in the Final Safety Analysis Report supplement.
The ACRS members and the staff discussed what criteria were used to judge the credibility of postulated nonsafety-related pipe failures that would adversely impact safety-related components and structures. They also discussed the use of operating experience from non-nuclear industries in concluding that the coatings on the internal surface of the water tanks are effective in preventing pitting and corrosion.
Plant License Renewal Subcommittee 3
March 13,2002 The ACRS members and the staff discussed how the identification of significant reactor vessel head penetration leakage at Davis-Besse Nuclear Power Plant affects the staff's SER conclusions. They discussed whether ultrasonic testing of the reactor vessel would identify cracks at the base metal and cladding interface.
Public Comments Mr. Stan Smilan, a public citizen, noted that the airline industry was also concerned about corrosion of airplanes. He provided examples where corrosion had led to component failures. He stated that there had been no credible intervention or adversarial technical review of the Turkey Point license renewal application. He recommended that the local, state, or federal government fund technical experts to protect the public's interest.
Mr. Smilan described his past experiences as a civilian at early nuclear weapon tests and his present concerns about federal health care programs for civilians exposed to the radiation during these tests.
He raised questions concerning terrorist threats associated with nuclear power plants, shipment of spent fuel through the Panama Canal, use of planes, and the likelihood of attacks being directed against the local Jewish population.
Dr. Bonaca expressed his appreciation for Mr. Smilan's views and noted that Mr. Smilan was welcome to present his concerns at the April 11-13, 2002 ACRS meeting in Rockville, Maryland.
Dr. Auluck and Mr. Medoff explained that the four issues identified in writing by a member of the public had been previously reviewed and resolved by the NRC staff. They presented the resolution of each of the four issues.
- 1.
In the early 1980s, voids were identified in the containment structure below the containment equipment hatch. FPL performed an analysis that concluded the structural strength of the containment was not affected by the voids and repaired the voids. The staff reviewed the reports and issued a safety evaluation that accepted the conclusions of the report. Pressure tests performed over the last 20 years have confirmed that the pressure integrity of the containment has been maintained.
- 2.
The design criteria of Turkey Point Units 3 and 4 bound the maximum hurricane wind speeds and storm wave heights that have been observed in the area. The Units survived hurricane Andrew without adverse consequences to the public health and safety. Procedures are in place to shut down the reactors and to take additional precautions if a severe storm is expected.
- 3.
Security at nuclear power plants is being reviewed by the Federal Government. The FPL has increased security at Turkey Point Nuclear Plant. The NRC may require additional security once a national policy is established. Due to the sensitive nature of security information, details of the revised security plans and proposed changes cannot be discussed in a public forum.
- 4.
Required spent fuel pool capacity is defined by technical specification. Plants are allowed to operate only if spent fuel pool capacity meets these requirements. This is an operating plant issue and is not within the scope of license renewal. FPL has the options of increasing the storage capacity of the spent fuel pool by reracking the fuel or building an independent spent fuel storage installation.
Plant License Renewa'i Subcommittee 4
March 13,2002 The ACRS members and the staff discussed the following:
generic implications of the voids identified in the containment structure, possible changes in the large early release frequency because of the identified voids, availability of diesel fuel oil from suppliers during station blackout events, and the possibility that radioactive water from a severe accident in the containment can get into the ground water through a leak in the water proofing membranes or water stops.
Inspections and Audits Mr. Caudle Julian, Region II, described the inspections and audits performed at Turkey Point Nuclear Plant to verify information in the application. The ACRS members and the staff discussed the available inspection guidance and the development of plant-specific inspection plans.
Dr. Auluck concluded that all open items had been resolved and that the applicant had met the requirements for license renewal, as required by 10 CFR 54.29, "Standards for issuance of a renewed license."
SUBCOMMITTEE COMMENTS, CONCERNS, AND RECOMMENDATIONS Dr. Shack noted that the application contained less technical information for accepting leak-before break as an aging management program for cast austenitic stainless steel piping, than for the acceptability of other aging management programs.
Dr. Bonaca noted that the application contained a description of the plant at one point in time. He stated that the staff review of the application was thorough and was dependent on the inspection and audit results. He recommended that the staff consider summarizing in the SER the changes made to the licensing bases as a result of license renewal.
Mr. Barton stated that based on his observation of workers and conditions of the structures and equipment during the site visit, the safety culture appeared to be good and the material condition of the plant was excellent considering the harsh environment.
STAFF AND FPL COMMITMENTS The staff agreed to determine whether there was any generic actions taken based on the identification of voids in the containment concrete.
The staff agreed to determine what effect, if any, the presence of voids in the containment wall would have on the large early release frequency.
SUBCOMMITTEE DECISIONS The Subcommittee requested that FPL provide an overview of the Turkey Point Nuclear Plant, Units 3 and 4 license renewal application at the April 11, 2002 ACRS meeting.
Plant License Renewal Subcommittee 5
March 13,2002 The Subcommittee requested that the staff summarize the information it presented to the Subcommittee at the April 11, 2002 ACRS meeting. In addition, the Subcommittee requested that the staff provide the status of the following:
staff review of WCAP reports, generic license renewal issue concerning station black out, and generic license renewal issue concerning class II over I piping.
FOLLOW-UP ACTIONS None.
PRESENTATION SLIDES AND HANDOUTS PROVIDED DURING THE MEETING The presentation slides and handouts used during the meeting are available in the ACRS Office files or as attachments to the transcript.
BACKGROUt\\ID MATERIAL PROVIDED TO THE SUBCOMMITTEE:
U.S. Nuclear Regulatory Safety Evaluation Report Related to the License Renewal of Turkey Point Nuclear Plant, Units 3 and 4, issued February 2002.
NOTE: Additional details of this meeting can be obtained from a transcript of this meeting available in the NRC Public Document Room, One White Flint North, 11555 Rockville Pike, Rockville, MD, (301) 415-7000, downloading or viewing on the Internet at "http://www.nrc.gov/ACRSACNW, or can be purchased from Neal R. Gross and Co., 1323 Rhode Island Avenue, NW, Washington, D.C. 20005, (202) 234-4433 (Voice), 387-7330 (Fax), e-mail: nrgross@nealgross.com.
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS PLANT LICENSE RENEWAL SUBCOMMITTEE MEETING TURKEY POINT UNITS 3 AND 4 MARCH 13, 2002 CITY HALL, 404 WEST PALM DRIVE FLORIDA CITY, FLORIDA
- PROPOSED AGENDA TOPIC PRESENTER I.
Opening Remarks:
M. Bonaca, ACRS 1:30-1:35 p.m.
Including Public Comments i:3D - 3:srS II.
Response to Comments from the Public R. Auluck, NRR 1:36 1:43 p.m.
Citizen I: '5 T -J:JS III.
Safety Evaluation Report R. Auluck, NRR 1-:46 a:08'p.m.
A.
Overview B.
Closure of Open Items
~:1.r-1:30
- BREAK-3.ee=3.1~ p.m.
{If f('i.e "J IIU/fIV, ~ 'IJ
'J: V so - Cf;(7D IV.
Results of Inspections and Audits R. l\\l::lh:lek, NRRt 3:163.45tp.m.
&f:",
V.
Discussion M. Bonaca, ACRS
~4:30 p.m.
VI.
Adjournment M. Bonaca, ACRS 4:30 p.m.
NOTE:
Presentation time should not exceed 50 percent of the total time allotted for specific item. The remaining 50 percent of the time is reserved for discussion.
Number of copies of the presentation materials to b,e provided to the ACRS - 25.
4764 Federal Register/Vol. 67, No. 21 /Thursd~y, January 31, 2002/Notices O'Claire, Chief, Radiological Branch, Ohio Emergency Management Agency, regarding the environmental impact of the proposed action. The state official had no comments.
Finding of No Significant Impact On the basis of the environmental assessment, the NRC concludes that the proposed action will not have a significant effect on the quality of the human environment. Accordingly, the NRC has determined not to prepare an environmental impact statement for the proposed action.
For further details with respect to the proposed action, see the licensee's letter dated December 21, 2000. Documents may be examined, and/or copied for a fee, at the NRC's Public Document Room (PDR), located at One White Flint North, 11555 Rockville Pike (first floor),
Rockville, Maryland. Publicly available records will be accessible electronically from the ADAMS Public Library component on the NRC Web site, http:/
/www.nrc.gov (the Public Electronic Reading Room). Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1-800-397-4209, or 301 415-4737, or bye-mail at pdr@nrc.gov.
Dated at Rockville, Maryland; this 25th day of January 2002.
For the Nuclear Regulatory Commission.
Anthony J. Mendiola, Chief, Section 2, Project Directorote m, Division ofLicensing Project Management, Office ofNuclear Reactor Regulation.
[FR Doc. 02-2375 Filed 1-30-02; 8:45 amI BILLING CODe 759G-01-P NUCLEAR REGULATORY COMMISSION
~ Advisory Committee on Reactor Safeguards; Meeting of the Subcommittee on Plant License Renewal; Notice of Meeting The ACRS Subcommittee on Plant License Renewal will hold a meeting on March 13, 2002, City Hall, 404 West Palm Drive, Florida City, Florida.
The entire meeting will be open to public attendance.
The agenda for the subject meeting shall be as follows: Wednesday, March 13,2002-1:30 p.m. until the conclusion ofbusiness.
The Subcommittee will review the NRC staff's final Safety Evaluation Report related to the license renewal of Turkey Point Nuclear Power Plant Units 3 and 4. The purpose of this meeting is to gather information, analyze relevant issues and facts, and to formulate proposed positions and actions, as appropriate, for deliberation by the full Committee.
Oral statements may be presented by members of the public with the concurrence of the Subcommittee Chairman; written statements will be accepted and made available to the Committee. Electronic recordings will be permitted only during those portions of the meeting that are open to the public, and questions may be asked only by members of the Subcommittee, its consultants, and staff. Persons desiring to make oral statements should notify the Designated Federal Official named below five days prior to the meeting, if possible, so that appropriate arrangements can be made.
During the initial portion of the meeting, the Subcommittee, along with any of its consultants who may be present, may exchange preliminary views regarding matters to be considered during the balance of the meeting.
The Subcommittee will then hear presentations by and hold discussions with representatives of the NRC staff and other interested persons regarding this review.
Further information regarding topics to be discussed, whether the meeting has been canceled or rescheduled, and the Chairman's ruling on requests for the opportunity to present oral statements and the time allotted therefor, can be obtained by contacting the Designated Federal Official, Mr.
Noel F. Dudley (telephone 301/415 6888) between 7:30 a.m. and 4:15 p.m.
(EST). Persons planning to attend this meeting are urged to contact the above named individual one or two working days prior to the meeting to be advised of any potential changes to the agenda, etc., that may have occurred.
Dated: January 24, 2002.
Sam Duraiswamy, Acting Associate Directorfor Technical Support, ACRSIACNW.
[FR Doc. 02-2374 Filed 1-30-02; 8:45 amI BILLING CODe 759O-f1-P NUCLEAR REGULATORY COMMISSION Updated and Consolidated Decommissioning Policy and Guidance of the Nuclear Regulatory Commission's Office of Nuclear Material Safety and Safeguards; Notice of Availability AGENCY: Nuclear Regulatory Commission.
ACTION: Notice of availability and request for public comment.
SUMMARY
- The Nuclear Regulatory Commission's (NRC) Office of Nuclear Material Safety and Safeguards (NMSS) is announcing the availability of a draft document "Consolidated NMSS Decommissioning Guidance:
Decommissioning Process" (NUREG 1757, Vol. 1). for public comment. This document provides guidance for the planning and implementation of the termination of licenses issued through NMSS's licensing programs. The guidance is intended for NRC staff.
licensees, and the public and is being developed in response to the NMSS performance goals, in the NRC's Strategic Plan, of: Making NRC activities and decisions more effective, efficient, and realistic; and reducing unnecessary regulatory burden on stakeholders. NRC is seeking public comment in order to receive feedback from the widest range of interested parties and to ensure that all information relevant to developing the document is available to the NRC staff. This draft document is being issued for comment only and is not intended for interim use. The NRC will review public comments received on the draft document. Suggested changes will be incorporated, where appropriate. in response to those comments, and a final document will be issued for use.
DATES: Comments on this draft document should be submitted by May 1,2002. Comments received after that date will be considered to the extent practicable.
ADDRESSES: NUREG-1757 is available for inspection and copying for a fee at the Commission's Public Document Room, U.S. NRC's Headquarters Building, 11555 Rockville Pike (First Floor), Rockville, Maryland, and electronically from the ADAMS Electronic Reading Room on the NRC Web site at, http://www.nrc.gov/reading-rm/
adams.html. NUREG-1757 is also available on the NRC web site at:
http://www.nrc.gov/reading-rm/doc coJIections/nuregs/staffor http://
www.nrc.gov/materials/
decommissioning/regs-guides comm.html.
A free single copy ofNUREG-1757 will be available to interested parties until the supply is exhausted. Such copies may be requested by writing to the U.S. Nuclear Regulatory Commission, Distribution Services, Washington, DC 20555-0001 or submitting e-mail to distribution@nrc.gov.
ADVISORY COMMITTEE ON REACTOR SAFEGUARDS SUBCOMMITTEE MEETING ON PLANT LICENSE RENEWAL MARCH 13, 2002 ATTENDEES - PLEASE SIGN BELOW PLEASE PRINT NAME AFFILIATION i3#/!/iJpt!
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ACRS SUBCOMMITTEE MEETING IN REVIEW OF THE FINAL SAFETY ANALYSIS REPORT FOR LICENSE RENEWAL OF THE TURKEY POINT NUCLEAR PLANT, UNITS 3 AND 4 MARCH 13, 2002 RAJ AULUCK PROJECT MANAGER NRR
COMMENTS FROM A PUBLIC CITIZEN Effects of voids on aging degradation rates and the structural integrity of concrete containment structures Effect of design basis hurricane wind speeds and storm waves on safe operation of Turkey Point Nuclear Plant Effect of terrorist air attacks on the safety and operability of the Turkey Point nuclear units Turkey Point spent fuel capacity ACRS slides R7.wpd 2
ACRS Slides - Turkey Point LRA SER
OVERVIEW Background Information Application Submitted by Letter Dated September 8, 2000 First Westinghouse Pressurized Water Reactor 3-Loop Westinghouse PWR, 2 Unit Site, Each Designed for 2300 MWT Plant Located in Dade County, Florida City, Florida, Approximately 25 Miles South of Miami Unit 3: License Expires July 19, 2012. Requests Renewal Through July 19, 2032.
Unit 4: License Expires April 10, 2013. Requests Renewal Through April 10, 2033.
ACRS slides R7.wpd 3
ACRS Slides - Turkey Point LRA SER
OVERVIEW (CONT.)
Turkey Point License Renewal Application Review Schedule MILESTONE TARGET DATE ACTUAL DATE Receive License Renewal Application 09/11/00 09/11/00 Notice Application Tendered 09/26iOO 09/26/00 Complete Acceptance Review of Application 10/10/00 10/04/00 Publish Acceptance Review & Docket Application/Notice of Opportunity for Hearing 10/17/00 10/12/00 Notice of Intent/Notice of Environmental Scoping Meeting 10/20/00 10/24/00 Deadline for Filing Hearing Requests and Petitions for Intervention Environmental Scoping Meeting EIS Scoping Period Ends Staff Complete Environmental RAls Staff Complete Safety RAls Applicant Responds to Environmental RAls Applicant Responds to Safety RAls Complete Scoping Inspection Staff Issue Draft EIS for Comment Staff Issue SER & Identify Open Items Public Meeting to Discuss DEIS ACRS Subcommittee Meeting ACRS Full Committee Meeting Complete Aging Management Review Inspection End of DEIS Comment Period Applicant Completes Responses to SER Open Items Staff Issue Final EIS Complete Optional Final Inspection Staff Issue SSER ACRS Subcommittee Meeting Regional Administrator's Letter ACRS Full Committee Meeting ACRS Letter Issue SER as NUREG Commission Paper W/Staff Recommendations Commission Decision 4
11/17/00 12/06/00 12/22/00 01/31/01 02/05/01 03/30/01 04/23/01 06/22/01 07/17/01 08/17/01 07/17/01 09/25/01 10/4-5/01 09/14/01 09/06/01 11/16/01 01/29/02 01/15/02 02/28/02 03/13/02 03/08/02 04/12/02 04/19/02 04/30/02 05/17/02 07/17/02 11/13/00 12/06/00 12/22/00 01/31/01 02/02/01 03/30/01 04/19/01 OS/25/01 06/12/01 08/17/01 07/17/01 09/25/01 10/05/01 09/14/01 09/06/01 11/07/01 01/11/02 01/15/02 02/27/02 02/01/02
OVERVIEW (CaNT.)
The applicant has met the requirements for license renewal, as required by 10 CFR 54.29 Actions have been identified and have been or will be taken such that there is reasonable assurance that activities will continue to be conducted during the Turkey Point renewal terms in accordance with the current licensing bases for the units.
The applicable requirements of 10 CFR Part 51 have been satisfied.
Matters raised under 10 CFR 2.758 have been addressed.
ACRS slides R7.wpd 5
ACRS Slides - Turkey Point LRA SER
OVERVIEW (CaNT.)
Westinghouse Electric License Renewal Reports Four Westinghouse Generic Reports (WCAPs) submitted for NRC Staff Review:
WCAP-14574, "License Renewal Evaluation: Aging Management Evaluation for Pressurizers." Final NRC safety evaluation issued on Oct. 26, 2000.
WCAP-14575, "License Renewal Evaluation: Aging Management Evaluation of Class 1 Piping and Associated Pressure Boundary Components." Final NRC safety evaluation issued on Nov. 8, 2000.
WCAP-14577, "License Renewal Evaluation: Aging Management Evaluation Reactor Internals." Final NRC safety evaluation issued on Feb. 10, 2001.
WCAP-14422, "License Renewal Evaluation: Aging Management for Reactor Coolant System Supports." Final NRC safety evaluation issued on Nov. 17, 2000.
Application addressed applicability of WCAPs to Turkey Point.
ACRS slides R7.wpd 6
ACRS Slides - Turkey Point LRA SER
LIST OF OPEN ITEMS Scoping for Seismic II over I (II/I) piping systems Acceptance criteria for Field Erected Tanks Internal Inspection Aging Management Program Scope of Reactor Vessel Head Alloy 600 Penetration Inspection Program Reactor Pressure Vessel Underclad Cracking ACRS slides R7.wpd 7
ACRS Slides - Turkey Point LRA SER
OPEN ITEMS Scoping of Seismic 11/1 Piping Systems Structures, systems, and components (SSC) identified as Seismic II/I should be included in the scope of license renewal and subject to AMRs, as consistent with the scoping requirements of 10 CFR 54.4(a)(2).
Staff's position has always been that Seismic 11/1 piping systems whose failure could prevent safety-related systems and structures from accomplishing their intended functions should be within the scope of license renewal.
In response to the staff's position on Seismic II/I, the applicant included additional components as being within the scope of license renewal and identified appropriate aging AMPs to manage the aging effects that correspond to these components.
ACRS slides R7.wpd 8
ACRS Slides - Turkey Point LRA SER
OPEN ITEMS Acceptance Criteria for Field Erected Tanks Internal Inspection The applicant uses the Field Erected Tanks Internal Inspection Program to manage aging effects associated with field erected tanks in the auxiliary feedwater and condensate storage system, feedwater and blowdown system, and safety injection system.
This program is a new aging management program - acceptance criteria and other program attributes were not developed at the time of the draft SER.
In response, the applicant provided the information related to the acceptance criteria, provisions for additional examinations, and justification for one-time inspections to resolve the issue ACRS slides R7.wpd 9
ACRS Slides - Turkey Point LRA SER
OPEN ITEMS Reactor Vessel Head Alloy 600 Penetration Inspection Program (RVHPIP)
LRA submitted prior to issuance of NRC Bulletin 2001-01, "Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles."
Open Item to address whether the RVHPIP was current with Bulletin 2001-01 and the latest industry programs for monitoring for PWSCC in U.S. VHP nozzles.
Applicant's response to Open Item:
referred to FPL response to Bulletin 2001-01 as current status of the program Bulletin response indicates continued participation in the industry-wide program Bulletin response provides the revised susceptibility rankings Bulletin response proposes timely VT-2 examinations of bare metal surfaces Information in the applicant's responses to the Open Item and to Bulletin 2001-01 provide a sufficient basis that PWSCC will be managed effectively in the Turkey Point VHP nozzles during the extended periods of operation. Staff considers Open Item 3.9.12-1 to be resolved.
ACRS slides R7.wpd 10 ACRS Slides - Turkey Point LRA SER
OVERVIEW - OPEN ITEMS Reactor Pressure Vessel (RPV) Underclad Cracking WCAP-15338 provides Westinghouse Electric's generic evaluation for growth of potential RPV underclad cracks by thermal fatigue. FPL's evaluation of this type of aging effect is addressed appropriately as a time-limited aging analysis (TLAA) covered under the scope Section 4.3 of the application.
NRC safety evaluation on WCAP-15338 indicated applicant's for renewal of Westinghouse 3-100p plants would need to address two Renewal Application Items:
applicant would need to indicate whether the number of design cycles and transients assumed in WCAP-15338 bounds the number of cycles for 60 years of operation of the applicant's RPVs under review. (RAI 4.3.2-1) applicants referencing the report would need to ensure that the evaluation of the TLAA is summarily described in the FSAR supplement. (Open Item 4.3-1)
Conformance with the first item resolved in response to RAI 4.3.2-1 (4/19/01)
Conformance with the second item resolved in FPL response to Open Item 4.3-1 dated November 1, 2001.
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COMMENTS FROM A PUBLIC CITIZEN Discussion of Concerns Effects of voids on aging degradation rates and the structural integrity of concrete containment structures Effect of design basis hurricane wind speeds and storm waves on safe operation of Turkey Point Nuclear Plant Effect of terrorist air attacks on the safety and operability of the Turkey Point nuclear units Turkey Point spent fuel capacity ACRS slides R7.wpd 12 ACRS Slides - Turkey Point LRA SER
INSPECTION ACTIVITIES Scoping and Screening Methodology Inspection Aging Management Program Inspection Open Item Resolution Inspection (optional)
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CONCLUSIONS The staff has completed its review of the Turkey Point License Renewal Application.
All Open Items have been resolved The applicant has met the requirements for license renewal, as required by 10 CFR 54.29.