Morning Report for January 20, 1999
Headquarters Daily report
JANUARY 20, 1999
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REPORT NEGATIVE NO INPUT
ATTACHED INPUT RECEIVED RECEIVED
HEADQUARTERS X
REGION I X
REGION II X
REGION III X
REGION IV X
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PRIORITY ATTENTION REQUIRED MORNING REPORT - HEADQUARTERS JANUARY 20, 1999
MR Number: H-99-0002
NRR DAILY REPORT ITEM
GENERIC COMMUNICATIONS
Subject: N/A
Information Notice 99-02, "GUIDANCE TO USERS ON THE IMPLEMENTATION OF A
NEW SINGLE-SOURCE, DOSE CALCULATION FORMALISM AND REVISED AIR-KERMA
STRENGTH STANDARD FOR IODINE-125 SEALED SOURCES," will be issued on
January 21, 1999.
This notice is being issued to all medical licensees authorized to
conduct brachytherapy treatments to alert them to two changes affecting
I-125 sealed source dosimetry. If not properly implemented, these
changes may result in unintended differences in doses delivered to
patients.
Contact: Robert L. Ayres, NMSS
301-415-5746
E-mail: rxa1@nrc.gov
PRIORITY ATTENTION REQUIRED MORNING REPORT - HEADQUARTERS JANUARY 20, 1999
Licensee/Facility: Notification:
Part 21 Database MR Number: H-99-0003
Sulzer Bingham Pumps Date: 01/20/99
Subject: Part 21 - Potential stress corrosion cracking in service
water pump
Reportable Event Number: N/A
Discussion:
VENDOR: Sulzer Bingham Pumps PT21 FILE NO: 99-02-0
DATE OF DOCUMENT: 12/14/98 ACCESSION NUMBER: 9812210318
SOURCE DOCUMENT: LETTER REVIEWER: PECB, V. Hodge
NEW ISSUE. The vendor, Sulzer Bingham Pumps, reports a potential site
where the necessary criteria for stress corrosion cracking or hydrogen
embrittlement could occur in a pump it supplied to the Oconee licensee
for auxiliary service water duty. The problem centers around the use of
very high hardness AISI 440 A martensitic stainless steel shaft sleeves
at the center and throttle sleeve locations. The vendor reviewed designs
of all pumps incorporating an interference fit sleeve and finds the
subject pump to be the only candidate for this defect. The vendor
recommends that materials in the pump be corrected. This defect is
similar to one identified in May 1988 in auxiliary feedwater pumps.
PRIORITY ATTENTION REQUIRED MORNING REPORT - HEADQUARTERS JANUARY 20, 1999
Licensee/Facility: Notification:
Part 21 Database MR Number: H-99-0004
Westinghouse Date: 01/20/99
Subject: Part 21 - Logic error in LOCBART computer code
Reportable Event Number: N/A
Discussion:
VENDOR: Westinghouse PT21 FILE NO: 99-03-0
DATE OF DOCUMENT: 12/22/98 ACCESSION NUMBER: 9812300224
SOURCE DOCUMENT: LETTER REVIEWER: PECB, E. Goodwin
NEW ISSUE. The vendor, Westinghouse, reports a logic error in the
LOCBART computer code. This causes cladding oxidation calculations to be
performed three times per time step. Preliminary investigation indicates
that correction of the error reduces local cladding oxidation but
increases the corresponding heat deposition, resulting in an undetermined
increase in large break loss of coolant accident peak cladding
temperature. Westinghouse expects its evaluation to be completed by
June 30, 1999.
PRIORITY ATTENTION REQUIRED MORNING REPORT - HEADQUARTERS JANUARY 20, 1999
Licensee/Facility: Notification:
Part 21 Database MR Number: H-99-0005
General Electric Nuclear Energy Date: 01/20/99
Subject: Part 21 - Terminal block phenolic cracking
Reportable Event Number: N/A
Discussion:
VENDOR: General Electric Nuclear Energy PT21 FILE NO: 99-04-0
DATE OF DOCUMENT: 12/22/98 ACCESSION NUMBER: 9812300181
SOURCE DOCUMENT: LETTER REVIEWER: PECB, D. Skeen
NEW ISSUE. The vendor, General Electric Nuclear Energy (GE-NE), reports
observed cracking in the terminal block phenolic material of type DC2800
or IC2800 series DC contactors. Such cracking is postulated to cause
short-circuiting of the wire terminations during normal operation or a
seismic event. However, no failures have been reported to GE-NE. The
vendor recommends that any of the DC28xx or IC28xx contactors installed
in safety-related applications be inspected during the next scheduled
maintenance interval. If any cracked terminal blocks are found, they
should be replaced. A licensee observed this cracking in two contactors
manufactured seven years apart. GE-NE has dedicated these contactors
(and the terminal blocks) and supplied them to several nuclear power
plants as basic components for unspecified, safety-related applications.
The basic component of concern is GE-NE terminal block Q144A1364G1 (GE
Industrial Systems part numbers 144A1364G1 and 808651P1), a renewal part
for these contactors. GE-NE has provided safety-related replacement
contactors DD317A7888P001-P008. The most probable cause of the cracking
is excessive flaring of the terminal nut during the assembly process.
This creates stresses that eventually cause the terminal block to crack.
PRIORITY ATTENTION REQUIRED MORNING REPORT - HEADQUARTERS JANUARY 20, 1999
Licensee/Facility: Notification:
Part 21 Database MR Number: H-99-0006
Rosemount Date: 01/20/99
Subject: Part 21 - Model 1153 pressure transmitter reference document
errors
Reportable Event Number: N/A
Discussion:
VENDOR: Rosemount PT21 FILE NO: 99-05-0
DATE OF DOCUMENT: 01/12/99 ACCESSION NUMBER:
SOURCE DOCUMENT: EN 35243 REVIEWER: PECB, D. Skeen
NEW ISSUE. The vendor, Rosemount Nuclear Instruments, Incorporated
discovered two errors in the specification and outline dimension drawings
for Rosemount Model 1153 Series B (e.g. - AB, DB, GB, HB) Alphaline
Nuclear Pressure Transmitters during a product literature update. The
error was discovered when the drawings were compared to product data
sheets and the product manual. The first error could result in
overestimating the transmitter qualified life for all of the Series B
transmitters by 5 years (15 years vs. the correct 10 years), if the
drawings are used to estimate the qualified life instead of the product
data sheet or the users manual. The second error could result in the
wrong output code "R" accuracy being used (for Model 1153 DB transmitters
only). Following exposure of 22 megarads of gamma radiation, the
accuracy of the output code "R" should be +/- 4.0% of the upper range
limit, instead of +/- 1.5% as stated in the 1153 DB drawing (drawing
number 01153-1610). The vendor has informed all of its customers of
record of the errors. It is believed that the most likely documents used
to specify the transmitters are the product data sheet or the users
manual, so the errors in the specification and outline drawings may not
constitute a significant generic concern. However, the vendor recommends
that end users determine the full scope of this deviation as it relates
to plant operations and plant safety and take any actions deemed
necessary.
PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION I JANUARY 20, 1999
Licensee/Facility: Notification:
Peco Energy Company MR Number: 1-99-0004
Peach Bottom 2 3 Date: 01/20/99
Philadelphia,Pennsylvania
Dockets: 50-277,50-278
BWR/GE-4,BWR/GE-4
Subject: ANNOUNCEMENT OF MANAGEMENT CHANGES
Reportable Event Number: N/A
Discussion:
On January 15, 1999, the licensee announced the following management
changes at Peach Bottom Atomic Power Station to support the PECO/Amergen
purchase of the Three Mile Island Unit 1:
Bruce Allshouse, currently the Director - Maintenance and I and C, and
Drew Odell, Chemistry Manager, will assume new positions with the
PECO/Amergen transition team at Three Mile Island (TMI)-1. Chuck Mayer,
currently Senior Manager - Outage Planning and Scheduling, will become
the new Director - Maintenance and I and C. Jim Stanley, currently a unit
outage manager, will become the new Senior Manager - Outage Planning and
Scheduling. A Chemistry Manager replacement has not been announced.
Regional Action:
None.
Contact: C. Cowgill (610)337-5233
Page Last Reviewed/Updated Wednesday, March 24, 2021
Page Last Reviewed/Updated Wednesday, March 24, 2021