United States Nuclear Regulatory Commission - Protecting People and the Environment

Morning Report for January 28, 2003



                       Headquarters Daily Report

                         JANUARY 28, 2003

*******************************************************
                    REPORT             NEGATIVE       
                    ATTACHED           INPUT RECEIVED 

HEADQUARTERS          X                                      
REGION I                                 X                   
REGION II                                X                   
REGION III                               X                   
REGION IV                                X   

                
PRIORITY ATTENTION REQUIRED  MORNING REPORT - HEADQUARTERS JANUARY 28, 2003

MR Number: H-03-0005

                           NRR DAILY REPORT ITEM
                           GENERIC COMMUNICATIONS



Subject: Issuance of Information Notice 2002-36

Information Notice 2002-36, "INCOMPLETE OR INACCURATE INFORMATION        
PROVIDED TO THE LICENSEE AND/OR NRC BY ANY CONTRACTOR OR SUBCONTRACTOR   
EMPLOYEE" was issued December 27, 2002.  This notice was issued to all   
materials and fuel cycle licensees and certificate holders to inform them
of the importance of diligently ascertaining the accuracy of educational 
background and professional qualifications of any contractor or          
subcontractor employees subject to such qualification requirements. This 
IN also alerts addressees of the potential penalties that could result   
from intentionally providing incomplete or innacurate information to NRC.
                                                                         
Accession No. ML023650299                                                
                                                                         
Contacts:  Ivelisse M. Cabrera, NMSS            Thomas R. Decker, RII    
           (301) 415-8152                       (404) 562-4721           
           Email: imc1@nrc.gov                  Email: trd@nrc.gov       



HEADQUARTERS      MORNING REPORT     PAGE  2          JANUARY 28, 2003

MR Number: H-03-0006

                           NRR DAILY REPORT ITEM
                           GENERIC COMMUNICATIONS



Subject: Issuance of Regulatory Issue Summary 2003-01

Regulatory Issue Summary 2003-01: Examination of Dissimilar Metal Welds, 
Supplement 10 to Appendix VIII of Section XI of the ASME Code dated      
January 21, 2003                                                         
                                                                         
The U.S. Nuclear Regulatory Commission is issuing this regulatory issue  
summary to inform addressees of the NRC staff's position on the          
implementation of Supplement 10 to Appendix VIII, "Performance           
Demonstration for Ultrasonic Examination Systems," of Section XI of the  
American Society of Mechanical Engineers Boiler and Pressure Vessel Code 
(ASME Code), as required by Title 10, Section 50.55a(g)(6)(ii)(C), of the
Code of Federal Regulations [10 CFR 50.55a(g)96)(ii)(C)].  Supplement 10 
contains the qualification requirements for procedures, equipment, and   
personnel involved with examining dissimilar metal welds using ultrasonic
techniques, which licensees were required to implement by November 22,   
2002.                                                                    
                                                                         
ADAMS Accession No.:  ML030210002                                        
                                                                         
Contact:    Donald Naujock, NRR                                          
            301-415-2767                                                 
            E-mail: dgn@nrc.gov                                          
                                                                         


HEADQUARTERS      MORNING REPORT     PAGE  3          JANUARY 28, 2003

MR Number: H-03-0007

                           NRR DAILY REPORT ITEM
                           GENERIC COMMUNICATIONS



Subject: Issuance of Information Notice 2003-03

Information Notice 2003-03: Part 21 - Inadequately Staked Capscrew       
Renders Residual Heat Removal Pump Inoperable dated January 27, 2003     
                                                                         
The U.S. Nuclear Regulatory Commission is issuing this information notice
to inform addressees of recently observed inadequately staked capscrews  
on casing wear rings of residual heat removal pumps.                     
                                                                         
ADAMS Accession No.:  ML030240029                                        
                                                                         
Contacts:   D. Billings, NRR                G. Bedi, NRR                 
            301-415-1175                    301-415-1393                 
            E-mail: deb1@nrc.gov            E-mail: gsb2@nrc.gov         
                                                                         
            J. Zeiler, Region 2                                          
            706-554-9901                                                 
            E-mail: jxz@nrc.gov                                          



HEADQUARTERS      MORNING REPORT     PAGE  4          JANUARY 28, 2003

Licensee/Facility:                     Notification:

Part 21 Database                       MR Number: H-03-0008
General Electric                       Date: 01/28/03
                                                                          

Subject: Part 21 - General Electric identified the stability Option III  
         period based detection algorithm T-min specification has defect 


Discussion:

DATE OF DOCUMENT: 11/22/02          ACCESSION NUMBER: ML023310569        
                                                                         
SOURCE DOCUMENT: LETTER             REVIEWER: RORP, J. Dozier            
                                                                         
Stability solution Option III is implemented in the Oscillation Power    
Range Monitor (OPRM). Each OPRM channel contains 18 to 33 OPRM cells     
(depending upon plant size).  Each OPRM cell signal is summed from three 
to four closely spaced Local Power Range Monitor (LPRM) signals.  Each   
OPRM cell signal is processed through the Option III detection algorithms
to determine when a trip is required.  Trip of one OPRM cell causes its  
OPRM channel to trip, and when sufficient OPRM channels trip             
(one-out-of-two taken twice, or two-out-of-four), a reactor scram is     
initiated to terminate the oscillation.                                  
                                                                         
An OPRM trip is enabled for plant operation within the OPRM Armed Region 
as defined on the power/flow map.  The Armed Region extends from natural 
circulation to 60% of rated core flow.  The licensing basis for the OPRM 
is to detect all expected oscillations within the OPRM Armed Region, and 
initiate a reactor trip to suppress the oscillation and provide Minimum  
Critical Power Limit (MCPR) safety limit protection.                     
                                                                         
GE Letter NEDO-31960-A, Supplement 1, "BWR Owners' Group Long-Term       
Stability Solutions Licensing Methodology (Supplement 1)," November 1995,
describes the Option III detection algorithms.  The Period Based         
Detection Algorithm (PBDA) provides licensing basis MCPR safety limit    
protection.  Other algorithms provide defense-in-depth protection.  The  
PBDA includes two parameters called Tmin and Tmax.  The PBDA will not    
evaluate oscillations if the period is less than Tmin or greater than    
Tmax because these would not be indicative of an expected coupled        
neutronic/thermal - hydraulic instability.  The letter specifies that    
"typical" Tmin values are in the range of 1.0 to 1.4 seconds and         
"typical" Tmax values are in the range of 3.0 to 3.5 seconds.            
                                                                         
Contact:    J. Dozier, NRR                                               
            301-415-1014                                                 
            E-mail: jxd@nrc.gov                                          
                                                                         



HEADQUARTERS      MORNING REPORT     PAGE  5          JANUARY 28, 2003

Licensee/Facility:                     Notification:

Part 21 Database                       MR Number: H-03-0009
Framatome                              Date: 01/28/03
                                                                          

Subject: Part 21 - Framatome has identified that their "Powerplex"       
         monitoring software contains an error                           


Discussion:

VENDOR: Framatome                   PT21 FILE NO: 2002-32-0              
                                                                         
DATE OF DOCUMENT: 11/22/02          ACCESSION NUMBER: ML023310566        
                                                                         
SOURCE DOCUMENT: LETTER             REVIEWER: RORP, J. Dozier            
                                                                         
                                                                         
The MCPR calculation using the SPCB correlation in the MICROBURN-B2 and  
MICROBURN-B codes and associated POWERPLEX monitoring software contains  
an error. The error is in the determination of the axial adjustment      
factor for use in the SPCB CPR [Critical Power Ratio] correlation. This  
can lead to non-conservative CPR calculations when using the SPCB CPR    
correlation and potentially a violation of the MCPR [Minimum Critical    
Power Ratio] Technical Specification operating limit since the POWERPLEX 
incore monitoring code may under predict the MCPR for comparison to the  
operating limit. This error in MICROBURN-B2 and MICROBURN-B had no impact
on the operating limit itself. The POWERPLEX incore monitoring software  
in use at River Bend, Grand Gulf, and LaSalle Unit 1 is impacted by this 
error.                                                                   
                                                                         
Contact:    J. Dozier, NRR                                               
            301-415-1014                                                 
            E-mail: jxd@nrc.gov                                          


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