ML17311B193
| ML17311B193 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde |
| Issue date: | 09/14/1995 |
| From: | Brian Holian NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9509250364 | |
| Download: ML17311B193 (25) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 14, 1995 LICENSEE:
Arizona Public, Service Company FACILITY:
Palo Verde Nuclear Generating Station, Unit Nos.
1, 2, and 3
SUBJECT:
SUMMARY
OF MEETING HELD ON JUNE 28,
- 1995, TO DISCUSS REACTOR POWER UPRATE PLANS On June 28, 1995, the NRC staff met with representatives of Arizona Public Service Company (APS) to discuss power uprate issues.
This meeting was a
followup to a meeting held on March 30, 1995, in which numerous fuel management issues were discussed.
Persons attending the meeting are listed in Attachment 1.
Viewgr aphs distributed at the meeting are contained in.
Highlights of the meeting are summarized below.
The licensee presented its basis for determining the scope of its "stretch power" project.
Host of the plant was designed and built to accommodate a
power of up to 4100 HWt (the main turbine was designed for 4000 MWt).
The licensee did feasibility studies of power uprates of 2, 5, and 10 percent.
A 2-percent "stretch power" project was selected as an initial project, because no modifications are necessary (other than setpoint changes).
Each of the three units is currently licensed for 3800 Mwt.
The licensee has formed a
joint project team with its vendor (Combustion Engineering) and expects to submit a license amendment request in January 1996 to increase the power level to 3876 HWt.
The licensee plans to integrate the stretch power project with several steam generator modifications.
The modifications are designed to increase the steam generators'ecirculation ratio.
A feedwater temperature reduction of about 20 degrees is also planned.
The reactor coolant system hot-leg temperature is expected to remain unchanged.
The licensee reviewed the planned scope of its reanalyses of Updated Final Safety Analysis Report (Chapter 6 and
- 15) events.
The staff requested the licensee to provide a summary for events that do not require reanalysis, with a synopsis of why the current analysis remains bounding (the staff made a
similar request last year for the hot-leg temperature reduction license r,f OO4~
95092503b4 950914 PDR ADOCK 05000528 P
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September 14, 1995 amendment).
The licensee will request that the amendment be approved by Hay 15, 1996, to support Unit 2 Cycle
- 7) operation.
Original Signed By Brian E. Holian, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-528, 50-529, and 50-530 Attachments:
- 1. Meeting Attendees
- 2. Viewgraphs cc w/atts:
See next page DISTRIBUTION w Atts 1 and 2:
- ,Docket File'.
Holian J.
- Dyer, RIV
~A<< I W. Russell/F. Hiraglia E.
Adensam E.
Peyton E. Jordan, T-4D118 J. Mitchell, EDO J.
Roe PUBLIC PDIV-2 Reading C.
Thomas R.
Zimmerman W.
NRC Participants DOCUMENT NAME:
PVJun28.HTS OFC LA:PDIV-2 PH: PDIV-2 BHolian:
9 K% 95 NAME EPey on DATE 9/'l95 OFFICIAL RECORD COPY
1 4'
~ I
September 14, 1995 cc w/atts:
Mr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street
- Phoenix, Arizona 85007 T.
E. Oubre, Esq.
Southern California Edison Company P.
O.
Box 800
- Rosemead, California 91770 Senior Resident Inspector USNRC P. 0.
Box 40
- Buckeye, Arizona 85326 Regional Administrator, Region IV U. S. Nuclear Regulatory Commission Harris Tower & Pavillion 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064
- Chairman, Board of Supervisors ATTN:
Chairman 301 W. Jefferson, 10th Floor
- Phoenix, Arizona 85003 Mr. Aubrey V. Godwin, Director Arizona Radiation Regulatory Agency 4814 South 40 Street
- Phoenix, Arizona 85040 Mr. Curtis Hoskins Executive Vice President and Chief Operating Officer Palo Verde Services 2025 N. 3rd Street, Suite 200
- Phoenix, Arizona 85004 Roy P.
Lessey, Jr.,
Esq.
Akin, Gump, Strauss, Hauer and Feld El Paso Electric Company 1333 New Hampshire Avenue, Suite 400 Washington, DC 20036 Ms. Angela K. Krainik, Manager Nuclear Licensing Arizona Public Service Company P.O.
Box 52034
- Phoenix, Arizona 85072-2034 Mr. William L. Stewart Executive Vice President, Nuclear Arizona Public Service Company
- Phoenix, Arizona 85072-3999
POWER UP TE HEETING ATTENDEES ARIZONA PUBLIC SERVICE COHPANY 0
V DE NUCLE GENERATI G
S ATION U IT OS JUN 2S 1995 Attachment I ND NRC C. Liang B. Holian C.
Thomas I. Ahmed D.
Shum D. Carter ri o ubl'c Service Com an P.
Crawley S.
Bauer H. Sauvageau J. Taggert Combustion En ineerin E. Jageler I. Rickard Viewgraphs
re c ower ro'ec
,P 4
June 28, 1995
Paul Crawley - Nuclear Fuel Management Scott Bauer - Nuclear Regulatory Affairs Mare Sauvageau
- Nuclear Fuel Management John Taggart - Nuclear Fuel Management Ernie Jageler - ABB CE Projects lan Rickard - ABB CE Licensing
ur oseo 88 IA Present APS Stretch Power Program
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Basis for Determining Scope of Project
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Analyses to be Performed
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Review Schedule Initiate Dialog with NRR
re c ower ro ec Is 0 Feasibility Study - 4'" Quarter 1994 4
Introduced to NRR - March 1995 ABB CE Initial Proposal - April 1995 Project Team Formed - May 1995 Detailed Scope/Schedule
- May 1995
ro ec ana emen ri eria Milestone Schedule
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Amendment Submittal to HRR -1/96
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Reload Deliverables on Site - 5/96 Joint Project Team 3800 MWth Assured Well Defined Detailed Scope I Schedule Daily Communication
ro ec ri eria Safety Meet all Nuclear, Environmental, Safety, Regulatory Limits 8 Standards I
Steam Generator Integration
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Steam Generator Modifications
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Feedwater Temperature Reduction
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No increase in T
re ec ri eria Minimize Plant Modifications
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No Modifications Identified Except Setpoints 3800 MWth Assured
ra e x erience Calvert Cliffs 1 &2-5'/0 Fort Calhoun - 6'/0 Saint Lucie 1 & 2 - 5%
Maine Yankee - 8%
Millstone 2 - 5%
Palisades
- 15/0 Zl'Al>>COh.ppl
re c ower ro ec vefvlew Plant Systems Review Safety Analysis Review Licensing Review
'PE Impact Review EQ Impact Review Operations Review Simulator Verification
Stretch Power Project Overview Balance of Plant Review Main Turbine - 4000 MWth
~ Excess high pressure turbine flowarea 2-3%
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Condensate Pumps 150%
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Main Feedpumps 150%
an 0
arame er an esa a e erma ower
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Power Increase 76 MWth T,d Decrease 1'F Delta T Increase 1'F Feedwater Temperature Decrease 2QoF Feedwater I Steam Flow Decrease 1%
Steam Generator Pressure Increases 10 psi MWe Increases 16 l Unit
\\
co e e ermina ion Recent Uprate Requests ABB CE Experience Review UFSAR Chapter 6 8 15 Events
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Power Dependent Events
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Limiting Events in Each Category Source Terms Mechanical Integrity
co e e efmina ien UFSAR Chapter 6 Analysis
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Large Break I OCA
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Small Break LOCA Long Term Cooling Containment Pressure I Temperature LOCA and MSLB
co e e ermina ion UFSAR Chapter 15 Analyses
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Reload Activities Summary of Transients Potentially Affected Events
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Increased Heat Removal
~ Steam Line Break
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Decreased Heat Removal
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Decreased Reactor Coolant Flaw
~ RCP Shaft Seizure
0 4
Potentially Affected Events Reactivity Anomalies
~ CEA Misoperation I Ejection
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Decrease in RCS inventory
~ Steam Generator Tube Ruptures
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Asymmetric Steam Generator Tube Plugging
Oml USIOA 4
Discussion
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Questions 8 Answers
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lhsues / Concerns / Action Items NRR / APS Communication Plan