Recent Misadministrations Caused by Incorrect Calibrations of Strontium-90 Eye ApplicatorsML031050494 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
12/13/1996 |
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From: |
Cool D A NRC/NMSS/IMNS |
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To: |
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References |
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IN-96-066, NUDOCS 9612090360 |
Download: ML031050494 (15) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, D.C. 20555 December 13, 1996 NRC INFORMATION
NOTICE 96-66: RECENT MISADMINISTRATIONS
CAUSED BY INCORRECT
CALIBRATIONS
OF STRONTIUM-90
EYE APPLICATORS
Addressees
All U.S. Nuclear Regulatory
Commission
Medical Use Licensees
authorized
to use strontium-90 (Sr-90) eye applicators.
Purpose
The U.S. Nuclear Regulatory
Commission (NRC) is issuing this information
notice to alert addressees
to recent misadministrations
caused by incorrect source strength determinations
of Sr-90 eye applicators.
It is expected that recipients
will review the information
for applicability
to their facilities
and consider actions, as appropriate, to avoid similar problems.
However, suggestions
contained
in this information
notice are not NRC requirements;
therefore, no specific action nor written response is required.DescriDtion
of Circumstances
The primary causes of two recent events have been problems with calibration
and calculation
of the dose rates from Sr-90 applicators.
As a result, the administered
doses were not within 20 percent of the prescribed
dose.Case 1. In October 1995, during an inspection
of a licensee authorized
to use a Sr-90 eye applicator
in Mayag~ez, Puerto Rico, it was determined
that the calibration
record for the licensee's
Sr-90 eye applicator
was missing. A previous owner of the source lost the original calibration
certificate, and his medical physics consultant
performed
a check of the source strength.
This check was performed
with an inappropriate
measurement
instrument
and resulted in an incorrect
determination
of the source strength as 0.24 Gray (Gy)/sec 0 (24 rad/sec).
The licensee obtained the source in 1994 and relied on the erroneous
source strength determination
during treatments.
Also, the source had not been decay-corrected
by either owner since 1990. NRC urged the licensee to have the eye applicator
recalibrated
and to be instructed
in the D Fc2 proper method to calculate
the decay of the source.The licensee subsequently
had the eye applicator
recalibrated
by the National Institute
of Standards
and Technology.
The resultant
recalibration
revealed a dose rate of 0.53 Gray (53 rad)/sec rather than the 0.24 Gy (24 rad)/sec used by the licensee.
The licensee had prescribed
a total dose of between 10 to 25 Gy (1000 to 2500 rad) for approximately
9-0709036 f arr&0 C. Dr Ilt, 2a
IN 96-66 December 13, 1996 70 patients, but actually administered
about twice this amount. An NRC medical consultant
has reviewed the cases and has recommended
that the patients be evaluated
for any adverse effects.Case 2. In November 1995, while reviewing
treatment
records during a routine NRC inspection
of a licensee authorized
to use a Sr-90 eye applicator
in Honolulu, Hawaii, an NRC inspector
determined
that the licensee had incorrectly
calculated
the decay of the strength of a Sr-90 eye applicator
and subsequently
delivered
doses 20 percent over the prescribed
doses to 16 patients.
The root cause of this event was the licensee improperly
calculating
the decay of the Sr-90 source. Specifically, the licensee linearly decayed the strength of the source instead of logarithmically
decaying the source strength of the eye applicator.
Before May 1995, a technologist
had correctly
calculated
the decay of the source; however, when this technologist
left, the physician
incorrectly
calculated
the source decay based on a linear decay from the previous calculations.
In addition, the incorrect
half-life
of Sr-90 was used in the calculation.
Following
a correct determination
of the source strength, the licensee determined
that 17 misadministrations
involving
16 patients occurred, from May 6, 1995 to November 16, 1995, including
one patient who was treated on both eyes. The delivered
doses range from 21.1 to 22.7 percent greater than the prescribed
dose of 40 Gy (4000 rad).Discussion
10 CFR 35.32, *Quality Management
Program," requires licensees
to develop written procedures
to meet five objectives
associated
with any brachytherapy
dose, including
assurance
that the prescribed
dose is the administered
dose.A necessary
part of this is to ensure that the dose rate emitted from an applicator
is correct. If the manufacturer's
certificate
of calibration
or original activity/dose
rate name plate is missing, the licensee should arrange with a qualified
expert to determine
the dose rate from the Sr-90 source.(For additional
details, see NRC IN 94-17, NSr-90 Eye Applicators:
Submission
of Quality Management
Plan, Calibration
and Use," dated March 11, 1994.)Failure to implement
the Quality Management
Rule and make required reports may subject a licensee to orders, civil penalties, and notices of violation.
In view of the nature of the cited events, it appears worthwhile
to review some of the properties
of Sr-90 eye applicators
and the related processes
for decay correction
over time. New Sr-90 eye applicators
typically
contain a 2 gigabecquerel (GBq) [54 millicurie(mCi)]
source, exhibiting
a surface dose rate of about 0.50 Gy (50 rad)/sec.
The half-life
of the parent Sr-90 is 28.5 yrs [maximum beta energy equal to 0.54 mega-electron
volts (MeY)], and the yttrium-90 (Y-90) daughter half-life
is 64.2 hrs (beta-max, 2.27 MeV);therefore, both isotopes are in equilibrium
on the eye applicator.
Since Sr-90 and Y-90 are in equilibrium, emissions
from both isotopes must be accounted
for in dosimetry
calculations.
IN 96-66 December 13, 1996 The dose rate (D,) at a time (t) can be calculated
from the initial dose rate (De) at the time of the most recent calibration
with the following
formula: D = D -(e-^t) (FI)where e, the base of the natural logarithm
(2.718), is raised to the power -Xt and is referred to as the 'decay factor' (df), where -X --0.693/Tx, T. is the half-life
of the isotope, and t is the elapsed time. For Sr-90, TX-28.5 years; therefore, X -(0.693)/(28.5 yrs) = 0.0243 yr'. The values for df can be used to determine
the fraction of original activity remaining
after t years. These values can then be used to calculate
dose rates by using the following
formula: D,= Dao df (F2)The fraction of activity remaining
after a given number of years from the original measurement
date is given in Table 1 (Attachment
1).For example An eye applicator
calibrated
by the manufacturer
on January 1, 1978, delivered an initial dose rate ( Do) of 0.75 Gy/sec (75 rad/sec) on contact. If, on January 1, 1996, the eye applicator
needs to be used, the elapsed time (in years) since calibration
is 18, and from Table 1, df = 0.646 for Sr-90.Using formula F2: D, = bo. df D18yaM -(0.75 Gy/sec)(0.646)
bigyea -0.485 Gy/sec (48.5 rad/sec)
IN 96-66 December 13, 1996 Table I may be extended using formula F1 and the value X -0.0243 yr' for Sr-90. Other values of df that need to be evaluated
by licensees
will need to be re-calculated
by using the appropriate
half-life
for that isotope.Alternatively, a semi-logarithmic
plot of the above data will yield a straight line, which may be extended beyond 25 years.This information
notice requires no specific action nor written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
regional office.Donald A. Cool, D rector Division of Industrial
and Medical Nuclear Safety Office of Nuclear Material Safety and Safeguards
Technical
contacts:
Jose M. Diaz-Velez, RII (404) 331-7438 E-mail: jxd2@nrc.gov
Emilio M. Garcia, RIV (510) 975-0239 E-mail: emg@nrc.gov
James A. Smith, NMSS (301) 415-7904 E-mail: jas4@nrc.gov
Attachments:
1. List of Recently Issued NMSS Information
Notices 2. List of Recently Issued NRC Information
Notices 42 T7SS I (/4e
Attachment
I IN 96-66 December 13, 1996 Page 1 of I TABLE 1 FRACTION (EXPRESSED
AS DECIMAL) OF ORIGINAL SR-90 ACTIVITY REMAINING
AFTER (t) YEARS Years (t) df Years (t) df Years (t) df Years (t) df.25 0.994 6.5 0.854 12.75 0.734 19 0.63.5 0.988 6.75 0.849 13 0.729 19.25 0.626.75 0.982 7 0.844 13.25 0.725 19.5 0.623 1 0.976 7.25 0.838 13.5 0.72 19.75 0.619 1.25 0.97 7.5 0.833 13.75 0.716 20 0.615 1.5 0.964 7.75 0.828 14 0.712 20.25 0.611 1.75 0.958 8 0.823 14.25 0.707 20.5 0.608 2 0.953 8.25 0.818 14.5 0.703 20.75 0.604 2.25 0.947 8.5 0.813 14.75 0.699 21 0.6 2.5 0.941 8.75 0.808 15 0.695 21.25 0.597 2.75 0.935 9 0.804 15.25 0.69 21.5 0.593 3 0.93 9.25 0.799 15.5 0.686 21.75 0.589 3.25 0.924 9.5 0.794 15.75 0.682 22 0.586 3.5 0.918 9.75 0.789 16 0.678 22.25 0.582 3.75 0.913 10 0.784 16.25 0.674 22.5 0.579 4 0.907 10.25 0.78 16.5 0.67 22.75 0.575 4.25 0.902 10.5 0.775 16.75 0.666 23 0.572 4.5 0.896 10.75 0.77 17 0.662 23.25 0.568 4.75 0.891 11 0.765 17.25 0.658 23.5 0.565 5 0.886 11.25 0.761 17.5 0.654 23.75 0.562 5.25 0.88 11.5 0.756 17.75 0.65 24 0.558 5.5 0.875 11.75 0.752 18 0.646 24.25 0.555 5.75 0.87 12 0.747 18.25 0.642 24.5 0.551 6 0.864 12.25 0.743 18.5 0.638 24.75 0.548 6.25 0.859 12.5 0.738 18.75 0.634 25 0.545 Attachment
2 IN 96-66 December 13, 1996 Page 1 of I UST OF RECENTLY ISSUED NMSS INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 96-63 96-57 96-54 96-53 96-52 96-51 Potential
Safety Issue Regarding
the Shipment of Fissile Material Incident-Reporting
Require-ments Involving
Intakes, During a 24-Hour Period that May Cause a Total Effective
Dose Equivalent
in Excess of 0.05 Sv (5 rem)Vulnerability
of Stainless Steel to Corrosion
When Sensitized
Retrofit to Amersham 660 Posilock Radiography
Camera to Correct Incon-sistency in 10 CFR Part 34 Compatibility
Cracked Insertion
Rods on Troxler Model 3400 Series Portable Moisture Density Gauges Residual Contamination
Remaining
in Krypton-85 Handling System After Venting 12/05196 10/30196 10/17/96 10115/96 09/26/96 09/11196 All U.S. Nuclear Regulatory
Commission
licensees authorized
to possess special nuclear material in unsealed quantities
greater than a critical mass All U.S. Nuclear Regulatory
Commission
licensees All material licensees All industrial
radiography
licensees All U.S. Nuclear Regulatory
Commission
portable gauge licensees
and vendors All material licensees
' >Attachment
3 IN 96-66 December 13, 1996 Page 1 of I UST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 96-65 96-64 96-63 96-62 96-61 96-60 Undetected
Accumulation
of Gas in Reactor Coolant System and Inaccurate
Reactor Water Level Indication
During Shutdown Modifications
to Con-tainment Blowout Panels Without Appropriate
Design Controls Potential
Safety Issue Regarding
the Shipment of Fissile Material Potential
Failure of the Instantaneous
Trip Function of General Electric RMS-9 Programmers
Failure of a Main Steam Safety Valve to Reseat Caused by an Improperly
Installed
Release Nut Potential
Common-Mode
Post-Accident Failure of Residual Heat Removal Heat Exchangers
1211 1/96 12/10196 12/05196 11120196 11/20/96 11/14/96 All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear reactors All U.S. Nuclear Regulatory
Commission
licensees
authorized
to possess special nuclear material in unsealed quantities
greater than a critical mass All holders of OLs and CPs for nuclear power plants All holders of OLs or CPs for nuclear power.reactors All holders of OLs or CPs for nuclear power reactors OL = Operating
License CP = Construction
Permit
IN 96-66.December 13, 1996 Table 1 may be extended using formula FH and the value x -0.0243 yr 1 for Sr-90. Other values of df that need to be evaluated
by licensees
will need to be re-calculated
by using the appropriate
half-life
for that isotope.Alternatively, a semi-logarithmic
plot of the above data will yield a straight line, which may be extended beyond 25 years.This information
notice requires no specific action nor written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
regional office.Donald A. Cool, Director Division of Industrial
and Medical Nuclear Safety Office of Nuclear Material Safety and Safeguards
Technical
contacts: Jose M. Diaz-Velez, RII (404) 331-7438 E-mail: jxd2@nrc.gov
Emilio M. Garcia, RIV (510) 975-0239 E-mail: emg@nrc.gov
James A. Smith, NMSS (301) 415-7904 E-mail: jas4enrc.gov
Attachments:
1. List of Recently 2. List of Recently Issued NMSS Information
Notices Issued NRC Information
Notices Official Record Copy S:\Jsmith\imns5350.JAS
OFC IMAB I E IMAB lIMAB I IMOB I Tech Ed I KANE JASmith SLMerchant
LWCamper o JMPiccone
o EKraus o DATE 1 11/26/96 11/26/96 1 10/28/96 10/29/96 8/01/96 OFC J JE I OGC I DD/IMNS I D/IMNS I NAME JLiebermano
SATreby o FCCombso DACool DATE 08/07/96 1 1/07/96 11/12/96 I 11/29/96-COWVER E = COVER & Attachment
N -NO COPY o- See Previous Concurrence
eIN 96-##'J November .1996 Table 1 may be extended using formula F1 and the value A = 0.0243 yr" for Sr-90. Other values of df that need to be evaluated
by licensees
will need to be re-calculated
by using the appropriate
half-life
for that isotope.Alternatively, a semi-logarithmic
plot of the above data will yield a straight line, which may extended beyond 25 years.This information
notice requires no specific action nor written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
regional office.Donald A. Cool, Director Division of Industrial
and Medical Nuclear Safety Office of Nuclear Material Safety and Safeguards
Contacts: Jose M. Diaz-Velez, RII (404) 331-7438 Internet:
JXD2@NRC.GOV
Emilio M. Garcia, RIV (510) 975-0239 Internet:
EMG@NRC.GOV
James A. Smith, NMSS (301) 415-7904 Internet:JAS4@NRC.GOV
Attachments:
1. Table of decay factors 2. List of Recently Issue(3. List of Recently Issue(fffirial Rernrd COnY Svisr d NMSS Information
Notices d NRC Information
Notices nith\imns5350JAS
OFC IMAB lE IMAB lIMAB lIMOB j Tech Ed NAME JASmi SLM@f@I~nt
LWCamper o JMPiccone
o EKraus @DATE it /96 i 10/8/ 9 6 10/29/96 8/01/96 OFC OE I OGC DD/IMNS DlIMNS NAME JLieberman@
SATreby @ FCCombs@ _____ __ _ _l DATE 08/07/96 11/07/96 11/12/96 ///t11/96= COVER E = COVER & Attachment
N = NO COPY ?--See Previous Concurrence
N 96-Il-N ovember 91996 This information
notice requires no specific action nor written respons .If you have any questions
about the information
in this notice, please c tact one of the technical
contacts listed below or the appropriate
reglo 1 office.Donald A. Cool, Director, Division of Industrial
and Medical Nuclear Sa ty Office of Nuclear terial Safety and Safeguards
Contacts:
Jose M. Diaz-Velez, RI (404) 331-7438 Internet:
JXD2@NRC.GOV
Emilio M. Garcia, RIV (510) 975-0239 Internet:
EMG@NRC.GOV
James A. Smith, NMSS (301) 415-7904 Internet:JAS4@NRC.GOV
Attachments:
1. Table of decay factors 2. List of Recently Issued NMS Information
Notices 3. List of Recently Issued MR Information
Notices Official Record Copy 5: \smitinins5350.JAS
OFC IMAB I E IMAB//1S IMAB I IMOB I Tech E NAME JASmithm SL e rc nt LWCamper o JMPiccone
a EKraus o DATE t/ /14/96 A/ 96 10/28/96 10/29/96 8/01/96 OFC OE l OGC DD/IMNS D/IMNS NAME JLiebermanq/
SATreby o FCCombso DACool DATE 08/07/9 11/07/96 11/12/96 / /96 C = COVER E M OVER h Attachment
N a NO COPY o- See Previous Concurrence
- . N 96-##a *-i ovember .1996 D 18year " (0.75 Gy/sec)(0.646)
blyrs, 0G 0.485 Gy/sec Table 1 may be extended using formula F1 and the value A 0.0243 yr-.Alternatively, a semi-logarithmic
plot of the above dat will yield a straight line, which may extended beyond 20 years.This information
notice requires no specific actio nor written response.
If you have any questions
about the information
in t s notice, please contact one of the technical
contacts listed below or t appropriate
regional office.Donald .Cool. Director Divis on of Industrial
and M ical Nuclear Safety Ofice of Nuclear Material Safety and Safeguards
Contacts:
Jose M. Diaz-Velez, (404) 331-7438 Internet:JMD2@NRC.
V Emilio M. Garci , RIV (510) 975-0239/Internet:EM
C.GOV James A. S ,th NMSS (301) 415- 904 Internet- AS4@NRC.GOV
Attachments:
1. List of Recent y Issued NMSS Information
Notices 2. List of Rece ly Issued NRC Information
Notices Official Recordo S:\jsmith\imns5350.JAS
OFC IMA E IMAB jI I I MOB I Tech Ed i NAME I ant LWCamper o JMPiccone
@ EKraus o DATE / /1196 le /6///96 10/28/96 10/29/96 8/01/96 OFC / OE I OGC DD/IMNS D/IMNS lAM JLiebermano
SATreby o FCCombso DACool D0/07/96 11/07/96 11/12/96 / /96 ,COVER E = COVER & Attachment
N = NO COPY @- See Previous Concurrence
N 96-ft<iovember
,1996 D (0.75 Gy/sec)(0.646)
.0.485 Gy/sec Table 1 may be etended using formula F1 and the value X -0.0243 yr 1.Alternatively, a mi-logarithmic
plot of the above data will yield a straight line, which may ext nded beyond 20 years.This information
noti requires no specific action nor written response.
If you have any questions
bout the information
in this notice, please contact (one of) the technical
c tact(s) listed below or the appropriate
regional office.Donald A. Cool, Director Division of Industrial
and Medical Nuclear Safety Office of Nuclear Material Safety and Safeguards
Contacts:
Jose M. Diaz-Velez, RII (404) 331-7438 Internet:JMD2@NRC.GOY
Emilio M. Garcia, RIV (510) 975-0239 Internet:EMG@NRC.GOV
James A. Smith, NMSS (301) 415-7904 Internet:JAS4@NRC.GOV
Attachments:
1. List of Recently Issued NMSS Information
Notices 2. List of Recently Issued NRC Information
Notices Official Record Copy S:\Jsmith\imns5350.JAS
\OFC qIMABiLW B IM4AB -IMOB l E\Tech Ed NAME JASm1 i SL chant LWCamper a JMPiccone
c EKraus o DATE I I 1/96 _ / j 10/28/96 10/29/96 8/01/96 OFC OE OGC DD/IMNS D/IMNS NAME JLiebermano
SATreby a F (Cm DACool DATE 08/07/96 11/07/96 / /96 C a COVER E a CUVLK & Attacnment
N = mU LUr1'u- aee rrevmuUs IA0ICUIIrCLM.
,N 96-##' "-'-6ctober
,1996 ble8.. -(0.75 Gy/sec)(0.646)
l 0.4 y/sec Table 1 may be extended using fo ula F1 and the value X -0.0243 yre.Alternatively, a semi-logarithmic
lot of the above data will yield a straight line, which may extended beyond 20 ars.This information
notice requires no sp ific action nor written response.
If you have any questions
about the in frma ion in this notice, please contact (one of) the technical
contact(s)
listed elow or the appropriate
regional office.Donald A. -ool, Director Division o Industrial
and Medical Ntclear Safety Office of N clear Material Safety and Safegu rds Contacts:
Jose M. Diaz-Velez, RII (404) 331-7438 Internet:JMD2@NRC.
GOY Emilio M. Garcia, RIV (510) 975-0239 Internet:EMG@NRC.GOV
James A. Smith, NMSS (301) 415-7904 Internet:JAS4@NRC .GOV Attachments:
1. List of Recently Issued NMSS Information
Notices 2. List of Recently Issued NRC Information
Notices Official Record Copy S:\Jsmithi\mns5350.JAS
\OFC IMAB AB IMAB I l IMOB l \l,Tech EdlNAME JASai R SUM nt LWCamper a JMPiccone
o EKraus o DATE / -J/ 10/28/96 10/29/96 8/01/96 OFC OE DD/IMNS D/IMNS KANE JLiebermano
S ireb NIL FCCombs DACool DATE 08/07/96 l/ /1/96 / /96 / /96 aCOVER E a COVER & Attachment
K = ND COPY o- See Previous Concurrence
\
C, 6 I< ~N 96-#t 4 October ,1996 We have Dlew. -(0.75 Gy/sec)(0.646)
Table I may be extended using formula FH and the value X -0.0243 yr 1.Alternatively, a semi-icgarithmic
plot of the above data will yield a straight line, which may extended be~yond 20 years.This information
notice requires no specific action nor written response.
If you have any questions
about the information
in this notice, please contact (one of) the technical
contact(s)
listed below or the appropriate
regional office.Donald A. Cool, Director Division of Industrial
and Medical Nuclear Safety Office cf Nuclear Material and Safrguards
Safety Contacts: Jose M. Diaz-Velez, RII (404) 331-7438 Internet:JMD2@NRC.60V
Emilio M. Garcia, RIV (510) 975-0239 Internet:EMG@NRC.GOY
James A. Smith, NMSS (301) 415-7904 Internet:JAS4@NRC.GOV
Attachments:
1. List 2. List Official of Recently of Recently Record CODY Issued NMSS Information
Notices Issued NRC Information
Notices SA:smithkimtns535GJAS
OFC IMAB E IMAB Tech NAME JASmi S on rchant C rer EKraus o DATE It /1 /96 /96 96 /09 /96 8/01/96 OFC OE lOGC lDD/IMNS l D/IMNS l~KANE JLiebermano
SATreby FCCombs DACool DATE 08/07/96 / /96 I /96 / /96:* COVER E a COVER & Attachment
N = NO COPY e- See Previous Concurrence
A 'IN 96-##August ,1996 This informat n not1ce requires no specific action nor written response.
If you have any qu tions about the information
in this notice, please contact (one of) the techn cal contact(s)
listed below or the appropriate
regional office.Donald A. Cool, Director Division of Industrial
and Medical Nuclear Safety Office of Nuclear Material Safety and Safeguards
Contacts:
Jose M. Diaz-Velez, RII (404) 331-7438 Emilio M. Garcia, RIV (510) 975-0239 James A. Smith, NMSS (301) 415-7904 Attachments:
1. List of Recently Issued NMSS Information
Notices 2. List of Recently Issued NRC Information
Notices Official Record Copy G:\imns5350.JAS , )OFC IMAB l E I OGC lTech Ed NAME JASmi'W per SATreby EKraus a DATE *in /96 __ /________
\___96 / /96 8/01/96 OFC \ lI I DD/IMNS l D/IMNS lNAME Q jeerman FCCombs DACool DATE ___9_ / /96: w COVER 'E i. COVER & Attachment
N = NO COPY o- See Previous Concurrence
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list | - Information Notice 1996-01, Potential For High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-01, Potential for High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-02, Inoperability of Power-Operated Relief Valves Masked by Downstream Indications During Testing (5 January 1996, Topic: Stroke time)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation as a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation As a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-04, Incident Reporting Requirements for Radiography Licensees (10 January 1996, Topic: Brachytherapy)
- Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel (18 January 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-06, Design & Testing Deficiencies of Tornado Dampers at Nuclear Power Plants (25 January 1996)
- Information Notice 1996-07, Slow Five Percent Scram Insertion Times Caused by Viton Diaphragms in Scram Solenoid Pilot Valves (26 January 1996)
- Information Notice 1996-08, Thermally Induced Pressure Locking of a High Pressure Coolant Injection Gate Valve (5 February 1996, Topic: Anchor Darling, Cold shutdown justification)
- Information Notice 1996-09, Damage in Foreign Steam Generator Internals (12 February 1996, Topic: Earthquake)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which Is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential For Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996)
- Information Notice 1996-12, Control Rod Insertion Problems (15 February 1996)
- Information Notice 1996-13, Potential Containment Leak Paths Through Hydrogen Analysis (26 February 1996)
- Information Notice 1996-14, Degradation of Radwaste Facility Equipment at Millstone Nuclear Power Station, Unit 1 (1 March 1996)
- Information Notice 1996-15, Unexpected Plant Performance During Performance of New Surveillance (8 March 1996)
- Information Notice 1996-16, BWR Operation with Indicated Flow Less than Natural Circulation (14 March 1996)
- Information Notice 1996-17, Reactor Operation Inconsistent with the Updated Final Safety Analysis Report (18 March 1996)
- Information Notice 1996-18, Compliance with 10 CFR Part 20 for Airborne Thorium (25 March 1996, Topic: Brachytherapy)
- Information Notice 1996-19, Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal (2 April 1996)
- Information Notice 1996-20, Demonstration of Associated Equipment Compliance with 10 CFR 34.20 (4 April 1996, Topic: Brachytherapy)
- Information Notice 1996-21, Safety Concerns Related to the Design of the Door Interlock Circuit on Nucletron High-Dose Rate and Pulsed Dose Rate Remote Afterloading Brachytherapy Devices (10 April 1996, Topic: Brachytherapy)
- Information Notice 1996-22, Improper Equipment Settings Due to Use of Nontemperature-Compensated Test Equipment (11 April 1996, Topic: Brachytherapy)
- Information Notice 1996-23, Fires in Emergency Diesel Generator Exciters During Operation Following Undetected Fuse Blowing (22 April 1996, Topic: Brachytherapy)
- Information Notice 1996-24, Preconditioning of Molded-Case Circuit Breakers Before Surveillance Testing (25 April 1996, Topic: Brachytherapy)
- Information Notice 1996-25, Traversing In-Core Probe Overwithdrawn at Lasalle County Station, Unit 1 (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems with Overhead Cranes (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems With Overhead Cranes (30 April 1996)
- Information Notice 1996-27, Potential Clogging of High Pressure Safety Injection Throttle Valves During Recirculation (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-28, Suggested Guidance Relating to Development and Implementation of Corrective Action (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-29, Requirements in 10 CFR Part 21 for Reporting and Evaluating Software Errors (20 May 1996, Topic: Brachytherapy)
- Information Notice 1996-30, Inaccuracy of Diagnostic Equipment for Motor-Operated Butterfly Valves (21 May 1996)
- Information Notice 1996-31, Cross-Tied Safety Injection Accumulators (22 May 1996)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (II) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Non-Destructive Examination)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (ii) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Nondestructive Examination)
- Information Notice 1996-33, Erroneous Data From Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-33, Erroneous Data from Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-34, Hydrogen Gas Ignition During Closure Welding of a VSC-24 Multi-Assembly Sealed Basket (31 May 1996)
- Information Notice 1996-35, Failure of Safety Systems on Self-Shielded Irradiators Because of Inadequate Maintenance and Training (11 June 1996)
- Information Notice 1996-36, Degradation of Cooling Water Systems Due to Icing (12 June 1996, Topic: High winds, Ultimate heat sink, Frazil ice)
- Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown (18 June 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-38, Results of Steam Generator Tube Examinations (21 June 1996)
- Information Notice 1996-39, Estimates of Decay Heat Using ANS 5.1 Decay Heat Standard May Vary Significantly (5 July 1996)
- Information Notice 1996-40, Defciencies in Material Dedication and Procurement Practices and in Audits of Vendors (7 October 1996, Topic: Coatings, Troxler Moisture Density Gauge)
- Information Notice 1996-41, Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation (26 July 1996)
- Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves (5 August 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-43, Failures of General Electric Magne-Blast Circuit Breakers (2 August 1996)
... further results |
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