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
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021