Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels in Accordance with the New Part 20ML031050574 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, 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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Issue date: |
06/12/1997 |
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From: |
Slosson M Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-97-034, NUDOCS 9706090329 |
Download: ML031050574 (11) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, 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 [[:Mcguire]] 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 [[:Mcguire]] 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 REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 June 12, 1997 NRC INFORMATION NOTICE 97-34: DEFICIENCIES IN LICENSEE SUBMITTALS
REGARDING TERMINOLOGY FOR
RADIOLOGICAL EMERGENCY ACTION LEVELS
IN ACCORDANCE WITH THE NEW PART 20
Addressees
All holders of operating licenses or construction permits for test and research reactors.
Puroose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to inform
addressees of the issuance of a revised Appendix I to NUREG-0849, "Standard Review Plan
for the Review and Evaluation of Emergency Plans for Research and Test Reactors." This
revised appendix provides guidance on incorporating the new 10 CFR Part 20 regulations
into the radiological emergency action levels (EALs). It is expected that recipients will review
the information for applicability to their facilities and consider actions, as appropriate.
However, suggestions contained in this information notice are not NRC requirements;
therefore, no specific action or written response is required.
Description of Circumstances
Part 20 was revised and the final rule was published in the FederalRegister on May 21,
1991 (56 FR 23360), with an original implementation date of January 1, 1993.
Subsequently, the implementation date was extended to January 1, 1994 (57 FR 38588). In
response to these regulations, many licensees of test and research reactors have submitted
to the NRC revised emergency plans that were intended to incorporate or reflect the
terminology introduced in the new regulations. Title 10 of the Code of Federal Regulations, Part 20 is referenced in the section of the emergency plan involving radiological EALs.
During its review of these submittals, the NRC staff noted that many licensees incorrectly
converted the wording of the EALs from the old terminology found in NUREG-0849. As an
example, (1) some licensees inappropriately converted "maximum permissible
concentrations" (MPCs) to "effluent concentrations" (ECs) and (2) some inaccurately used the
term "deep dose equivalent." Several licensees merely substituted the EC term for the MPC
term. Other licensees used various multipliers in an attempt to correct the differences
between the two values. Still other licensees replaced the MPC term with "derived air
concentration." These submittals indicate the need for additional guidance that could be
used to assist in updating EALs.
v52on ax? ,
IN 97-34 June 12, 1997 Discussion
If the errors in the revised EAL schemes are left uncorrected, they could potentially result in a
licensee taking some conservative actions that are unwarranted or in the licensee delaying
appropriate actions.
Guidance in the form of a revision to Appendix I to NUREG-0849 was issued in April 1997.
The revised appendix provides guidance on incorporating the current 10 CFR Part 20
regulations into the radiological EALs and, at the same time, corrects some omissions
in prior guidance and clarifies some other EALs for the implementation of the new
Part 20 regulations. Attachment 1 to this document is a copy of the revised Appendix I.
NUREG-0849, which was published in 1983, is available from the following sources:
- The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC
20037 (202-634-3380). (Document may be copied for a fee, currently $0.08 per
page.)
- The Superintendent of Documents, U.S. Govemment Printing Office, P. 0. Box 37082, Washington, DC 20402-9328 (202-512-1800), for a fee of $3.75.
- The National Technical Information Service, Springfield, VA 22161-0002 (703-487-
4650), for a fee of $24.50 (paper) and $12.50 (microfiche), plus a $4.00 handling fee.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact the technical contact listed
below or the appropriate regional office.
Marylee M. Slosson, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Lawrence K. Cohen
301-415-2923 E-mail: lkc@nrc.gov
Attachments:
1. Revised Appendix I of NUREG-0849
2. List of Recently Issued NRC information Notices
44AaJ p U
Attachment 1 IN 97-34 June 12, 1997 APPENDIX I
EMERGENCY CLASSES
ACTION LEVEL*
PURPOSE
Notification of Unusual Events INOUE)
Actual or projected radiological effluentt at the site * Ensure that the first step in any response later
boundary which is calculated (or measured) to result found to be necessary has been carried out.
In either of the following conditions, both of which
are based on an exposure of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less: * Bring the operating staff to a state of readiness.
(1) A deep dose equivalent of 0.15 milliSievert
(mSv) 115 mrem) * Provide systematic handling of unusual events
OR Information and decisionmaking.
(2) A committed effective dose equivalent of 0.15 mSv [15 mrem] based on the following
considerations:
- 100 EC x 24 hr* = 2.4 x 103 EC-hr m 0.15 mSv (15 mrem) (for radionuclides other
than noble gases)
3
- 50 EC x 24 hr = 1.2 x 10 EC-hr m 0.15 mSv [15 mrem](for noble gases)t
Report or observation of a severe natural
phenomenon affecting the reactor site
Receipt of bomb threat affecting the reactor facility
Fire within the reactor facility not extinguished within
15 minutes
Alert
Actual or projected radiological effluentt at the site * Ensure that emergency personnel are readily
boundary which Is calculated (or measured) to result available to respond If the situation becomes
in either of the following conditions, both of which more serious or to perform confirmatory
are based on an exposure of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less: radiation monitoring If required.
(1) A deep dose equivalent of 0.75 mSv [5mrem] * Provide current offsite authorities with status
OR information.
(2) A committed effective dose equivalent of 0.75 mSv 15 mrem) based on the following
considerations:
- 500 EC x 24 hr = 1.2 x 104 EC-hr - 0.75 mSv [75 mrem] (for radionuclides other
than noble gases)
- 250 EC x 24 hr"= 6 x 1 3 EC-hr m 0.75 mSv (75 mrem] (for noble gases)tt
Actual or projected radiation levelst at the site
boundary of 0.2 mSv/hr deep dose equivalent [20
mremlhr] for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or 1.0 mSv 1100 mrem] to the
thyroid (committed dose equivalent)
Attachment I
IN 97-34 June 12. 1997 APPENDIX I (cont'd)
-. - W%1 At;I 1IUN LtVtL- Irumrvo
Site Area Emernencv
Actual or projected radiological effluentt at the site * Ensure that response centers are manned.
boundary which is calculated (or measured) to result
in either of the following conditions both of which * Ensure that monitoring teams are dispatched.
are based on an exposure of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less:
- Ensure that personnel required for evacuation of
(1) A deep dose equivalent of 3.75 mSv [375 onsite areas are at duty stations.
mrem]
OR * Provide consultation with offsite authorities.
(2) A committed effective dose equivalent of 3.75 mSv [375 mrem] based on the following * Provide Information for the public through offske
considerations: authorities.
- 2500 EC x 24 hr = 6 x IV0 EC-hr m3.75 mSv 1375 mrem] (for radionuclides other
than noble gases)
- 1250 EC x 24 hr* = 3 x I10 EC-hr m 3.75 mSv 1375 mrem](for noble gases)"
Actual or projected radiation levelst at the site
boundary of 1.0 mSv/hr [100 mremlhr] deep dose
equivalent for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or 5.0 mSv [500 mrem] to the
thyroid (committed dose equivalent)
General Emergency
Sustained actual or projected radiation levelst at the * Initiate predetermined protective actions for the
site boundary of 5.0 mSv/hr [500 mremlhr] deep public.
dose equivalent
- Provide continuous assessment of Information
Actual or projected doset at the site boundary in the from licensee and offsite organization
plume exposure pathway of 10 mSv 11 rem] (total measurements.
effective dose equivalent) or 50 mSv 15 rem] to the
thyroid (committed dose equivalent) * Initiate additional measures as Indicated by
actual or potential releases.
- Provide consultation with offsite authorities.
- Provide updates for the public through offsite
authorities.
- The situation that may lead to an emergency class described in the subsections of Section 4.0 may be
referenced as emergency action levels appropriate to the emergency class.
t It is expected that licensees will determine the relationship of the EAL dose levels at the site boundary to
instrumentation readings andlor safety analyses accident conditions for their specific facilities.
Attachment I
IN 97-34 June 12, 1997 Effluent concentration (EC) as fisted In Title 10 of the Code of Federal Regulations, Part 20 (10 CFR Part 20),
Standards for the Protection Against Radiation,* Appendix B. Table 2. If the exposure time Is less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the EC multiplier can be increased proportionately, provided that the values of 2.4 x 103 and 1.2 x 10 3 EC-hr are
used to declare a NOUE; the proportional Increase for an alert is 5 and for a site area emergency it Is 25.
" Table 2 of Appendix B to 10 CFR Part 20 lists the concentration values that are equivalent to the radionuclide
concentrations which, if Inhaled or Ingested continuously over the course of a year, would produce a total effective
dose equivalent of 0.5 mSv [50 mrem]. However, for noble gases where the submersion (external dose) Is
limiting, the concentration values would produce a total effective dose equivalent of I mSv [100 mremJ.
Ki1_
Attachment 2 IN 97-34 June 12, 1997 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
97-33 Unanticipated Effect 06/11/97 All holders of OLs or CPs
of Ventilation System for nuclear power reactors
on Tank Level Indica- tions and Engineering
Safety Features Actua- tion System Setpoint
95-36, Potential Problems 06/10/97 All holders of OLs or CPs
Supp. 1 with Post-Fire Emer- for nuclear power reactors
gency Lighting
97-32 Defective Worm Shaft 06/10/97 All holders of OLs or CPs
Clutch Gears in for nuclear power reactors
Limitorque Motor- Operated Valve
Actuators'
97-31 Failures of Reactor 06/03/97 All holders of OLs or CPs
Coolant Pump Thermal for pressurized-water
Barriers and Check reactor plants
Valves in Foreign
Plants
97-30 Control of Licensed 06/03/97 All material and fuel
Material During Reorgan- cycle licensees
izations, Employee- Management Disagreements, and Financial Crises
97-29 Containment Inspection 05/30/97 All holders of OLs or CPs
Rule for nuclear power reactors
OL = Operating License
CP = Construction Permit
IN 97-34
' June 12, 1997 Discussion
If the errors in the revised EAL schemes are left uncorrected, they could potentially result in a
licensee taking some conservative actions that are unwarranted or in the licensee delaying
appropriate actions.
Guidance in the form of a revision to Appendix I to NUREG-0849 was Issued in April 1997.
The revised appendix provides guidance on incorporating the current 10 CFR Part 20
regulations into the radiological EALs and, at the same time, corrects some omissions
in prior guidance and clarifies some other EALs for the implementation of the new
Part 20 regulations. Attachment 1 to this document is a copy of the revised Appendix I.
NUREG-0849, which was published in 1983, is available from the following sources:
- The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC
20037 (202-634-3380). (Document may be copied for a fee, currently $0.08 per page.)
- The Superintendent of Documents, U.S. Government Printing Office, P. 0. Box 37082, Washington, DC 20402-9328 (202-512-1800), for a fee of $3.75.
- The National Technical Information Service, Springfield, VA 22161-0002 (703-487-4650),
for a fee of $24.50 (paper) and $12.50 (microfiche), plus a $4.00 handling fee.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact the technical contact listed
below or the appropriate regional office.
original signed by S.H. Weiss for
Marylee M. Slosson, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Lawrence K. Cohen
(301) 415-2923 E-mail: Ikcenrc.gov
Attachments:
1. Revised Appendix I of NUREG-0849
2. List of Recently Issued NRC information Notices
DOCUMENT NAME: S:\DRPM SEC\RAD51 IN *SEE PREVIOUS CONCURRENCE
To receive a copy of ths document, hIdicate hI the box: C' - Copy wlo
attachmenVenclosure E - Copy w/attachment/enclosure AN- - No copy
OFFICE TECH CONI C:PERB:DRPM C:PECB:DRPM D: DRPM 6W
NAME LKCohen* CLMiller* AEChaffee* MMSlosscn I
DATE 05/20/97 05/22/97 05/30/97 0 //O/97 OFFICIAL RECORD COPY.
I,
IN 97- May , 1997 Discussion
If the errors in the revised EAL schemes are left uncorrected, they could potentially result in a
licensee taking some conservative actions that are unwarranted or in the licensee delaying
appropriate actions..
Guidance in the form of a revision to Appendix I to NUREG-0849 was issued in April 1997.
The revised appendix provides guidance on incorporating the current 10 CFR Part 20
regulations into the radiological EALs and, at the same time, corrects some omissions
in prior guidance and clarifies some other EALs for the implementation of the new
Part 20 regulations. Attachment 1 to this document is a copy of the revised Appendix I.
NUREG-0849, which was published in 1983, is available from the following sources:
- The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC
20037 (202-634-3380). (Document may be copied for a fee, currently $0.08 per page.)
- The Superintendent of Documents, U.S. Govemment Printing Office, P. 0. Box 37082, Washington, DC 20402-9328 (202-512-1800), for a fee of $3.75.
- The National Technical Information Service, Springfield, VA 22161-0002 (703-487-4650),
for a fee of $24.50 (paper) and $12.50 (microfiche), plus a $4.00 handling fee.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact the technical contact listed
below or the appropriate regional office.
Marylee M. Slosson, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Lawrence K. Cohen
(301) 415-2923 E-mail: lkc@nrc.gov
Attachments:
1. Revised Appendix I of NUREG-0849
2. List of Recently Issued NRC information Notices
DOCUMENT NAME: S:\DRPM SEC\RAD51 IN *SEE PREVIOUS CONCURRENCE
To receive a copy of this document. indcite inthe box: 'C- - Copy w/o
attachmentlenclosure E' - Copy w/attachmentlenclosure 'N' - No copy
OFFICE TECH CONT C:PERB:DRPM C:PECB:DRPM D:DRPM I
NAME LKCohen* CLMiller* AEChaffee blo, MlMS'lossonl
DATE 05/20/97 05/22/97 05/so/97 )5/ /97
0!
OFFICIAL RECORD COPY ,41brJ i41M I
IN 97- May , 1997 Discussion
If the errors in the revised EAL schemes are left uncorrected, they could potentially result in a
licensee taking some conservative actions that are unwarranted or in the licensee delaying
appropriate actions.
Guidance in the form of a revision to Appendix I to NUREG-0849 was issued on April 1997.
This revised appendix provides guidance on incorporating the current 10 CFR Part 20
regulations into the radiological EALs and, at the same time, corrects some omissions
in prior guidance and clarifies some other EALs for the implementation of the new
Part 20 regulations. Attachment I to this document is a copy of the revised Appendix I.
NUREG-0849, which was published in 1983, is available from the following sources:
- The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC
20037 (202-634-3380). (Document may be copied for a fee, currently $0.08 per page.)
- The Superintendent of Documents, U.S. Govemment Printing Office, P. 0. Box 37082, Washington, DC 20402-9328 (202-512-1800), for a fee of $3.75.
- The National Technical Information Service, Springfield, VA 22161-0002 (703-487-4650),
for a fee of $24.50 (paper) and $12.50 (microfiche), plus a $4.00 handling fee.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact the technical contact listed
below or the appropriate regional office.
Marylee M. Slosson, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Lawrence K. Cohen
(301) 415-2923 E-mail: lkc@nrc.gov
Attachments:
1. Revised Appendix I of NUREG-0849
2. List of Recently Issued NRC information Notices
DOCUMENT NAME: S:\DRPM SEC\RAD51 IN *SEE PREVIOUS CONCURRENCE
To receive a copy of this document. kidicate inthe box: * - Copy w/o
attachment/enclosure 'E' - Copy wlattachment/enclosure *N0 - No copy
OFFICE TECH CONT
NAMELKC ohen*
C:PERB:DRPM
ICLMiller*
C:PECB:DRPM
AEChaffee
D:DRPM
MMSosson
H
DATE
.FFICALREOR /20/97 COYe
05/22/97 05/ /97 05/ /97
IN 97- May, 1997 Discussion
If the errors in the revised EAL schemes are left uncorrected, they could potentially result in a
licensee taking some conservative actions that are unwarranted or in the licensee delaying
appropriate actions.
Guidance in the form of a revision to Appendix I to NUREG-0849 was issued on April 1997.
This revised appendix provides guidance on incorporating the current 10 CFR Part 20
regulations into the radiological EALs and, at the same time, corrects some omissions
in prior guidance and clarifies some other EALs for the implementation of the new
Part 20 regulations. Attachment 1 to this document is a copy of the revised Appendix I.
NUREG-0849, which was published in 1983, is available from the following sources:
- The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC
20037 (202-634-3380). (Document may be copied for a fee, currently $0.08 per page.)
- The Superintendent of Documents, U.S. Government Printing Office, P. 0. Box 37082, Washington, DC 20402-9328 (202-512-1800), for a fee of $3.75.
- The National Technical Information Service, Springfield, VA 22161-0002 (703-487-4650),
for a fee of $24.50 (paper) and $12.50 (microfiche), plus a $4.00 handling fee.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact the technical contact listed
below or the appropriate regional office.
Marylee M. Slosson, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Lawrence K. Cohen
(301) 415-2923 E-mail: lkcenrc.gov
Attachments:
1. Revised Appendix I of NUREG-0849
2. List of Recently Issued NRC information Notices
DOCUMENT NAME: S:\DRPM SEC\RAD51 IN
To receive
- copy Of this document. hndIcite In the box: C*'- Copy w/o
attachment/enclosure 'E' - Copy wlattachmentlenclosure 'N' - No copy
OFFICE TECH CONT C:PERB:DRPM C:PECB:DRPM D:DRPM
INAME LKCohens..t CLMiller (Lb, 1AEChaffee I MMS1osson I I
DATE 0/24/97 9&zV97 /97 97 OFFICIAL RECORD COPY S. -, A
' ' FIN 97- May , 1997 Discussion
If the errors in the revised EAL schemes are left uncorrected, they could potentially result in a
licensee taking some conservative actions that are unwarranted or in the licensee delaying
appropriate actions.
Guidance in the form of a revision to Appendix I to NUREG-0849 was issued on April 1997.
This revised appendix provides guidance on incorporating the current 10 CFR Part 20
regulations into the radiological EALs and, at the same time, corrects some omissions
in prior guidance and clarifies some other EALs for the implementation of the new
Part 20 regulations. Attachment 1 to this document is a copy of the revised Appendix I.
NUREG-0849, which was published in 1983, is available from the following sources:
- The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC
20037 (202-634-3380). (Document may be copied for a fee, currently $0.08 per page.)
- The Superintendent of Documents, U.S. Govemment Printing Office, P. 0. Box 37082, Washington, DC 20402-9328 (202-512-1800), for a fee of $3.75.
- The National Technical Information Service, Springfield, VA 22161-0002 (703-487-4650),
for a fee of $24.50 (paper) and $12.50 (microfiche), plus a $4.00 handling fee.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact the technical contact listed
below or the appropriate regional office.
Marylee M. Slosson, Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: Lawrence K. Cohen
(301) 415-2923 E-mail: lkc@nrc.gov
Attachments:
1. Revised Appendix I of NUREG-0849
2. List of Recently Issued NRC information Notices
DOCUMENT NAME: S:\DRPM SEC\RAD51 IN
To receive a copy of this document. hIdfice hI the box: ACT - Copy w/o
attachmentlenclosure 'E' - Copy w/attachmentlenclosure 'N - No copy
OFFICE TECH CONT C:PERB:DRPM C:PECB:DRPM D:DRPM
NAME LKCohen %4V CLMiller AEChaffee MMSlosson
DATE 06711/97 04/ /97 04/ /97 04/ /97 OFFICIAL RECORD COPY
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list | - Information Notice 1997-01, Improper Electrical Grounding Results in Simultaneous Fires in the Control Room and the Safe-Shutdown Equipment Room (8 January 1997, Topic: Safe Shutdown, Emergency Lighting)
- Information Notice 1997-02, Cracks Found in Jet Pump Riser Assembly Elbows at Boiling Water Reactors (6 February 1997)
- Information Notice 1997-03, Defacing of Labels to Comply with 10 CFR 20.1904(b) (20 February 1997)
- Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents (24 February 1997, Topic: Backfit)
- Information Notice 1997-05, Offsite Notification Capabilities (27 February 1997, Topic: Earthquake)
- Information Notice 1997-06, Weaknesses in Plant-Specific Emergency Operating Procedures for Refilling the Secondary Side of Dry Once-Through Steam Generators (4 March 1997)
- Information Notice 1997-07, Problems Identified During Generic Letter 89-10 Closeout Inspections (6 March 1997, Topic: Hot Short, Safe Shutdown, Weak link)
- Information Notice 1997-08, Potential Failures of General Electric Magne-Blast Circuit Breaker Subcomponents (12 March 1997, Topic: Coatings, Weak link)
- Information Notice 1997-09, Inadequate Main Steam Safety Valve (MSSV) Setpoints and Performance Issues Associated with Long MSSV Inlet Piping (12 March 1997)
- Information Notice 1997-10, Liner Plate Corrosion in Concrete Containments (13 March 1997)
- Information Notice 1997-11, Cement Erosion from Containment Subfoundations at Nuclear Power Plants (21 March 1997)
- Information Notice 1997-12, Potential Armature Binding in General Electric Type Hga Relays (24 March 1997)
- Information Notice 1997-13, Deficient Conditions Associated with Protective Coatings at Nuclear Power Plants (24 March 1997, Topic: Coatings)
- Information Notice 1997-14, Assessment of Spent Fuel Pool Cooling (28 March 1997, Topic: Time to boil, Coatings)
- Information Notice 1997-15, Reporting of Errors and Changes in Large-Break Loss-of-Coolant Accident Evaluation Models of Fuel Vendors and Compliance with 10 CFR 50. 46(a)(3) (4 April 1997, Topic: Coatings, Fuel cladding)
- Information Notice 1997-16, Preconditioning of Plant Structures, Systems, and Components Before ASME Code Inservice Testing or Technical Specification Surveillance Testing (4 April 1997, Topic: Stroke time, Coatings)
- Information Notice 1997-17, Cracking of Vertical Welds in the Core Shroud and Degraded Repair (4 April 1997, Topic: Coatings)
- Information Notice 1997-18, Problems Identified During Maintenance Rule Baseline Inspections (14 April 1997, Topic: Probabilistic Risk Assessment, Coatings, Emergency Lighting)
- Information Notice 1997-19, Safety Injection System Weld Flaw at Sequcyah Nuclear Power Plant, Unit 2 (18 April 1997, Topic: Boric Acid)
- Information Notice 1997-20, Identification of Certain Uranium Hexafluoride Cylinders That Do Not Comply with ANSI N14.1 Fabrication Standards (17 April 1997)
- Information Notice 1997-21, Availability of Alternate AC Power Source Designed for Station Blackout Event (18 April 1997, Topic: Main transformer failure)
- Information Notice 1997-22, Failure of Welded-Steel Moment Resisting Frames During Northridge Earthquake (25 April 1997, Topic: Earthquake)
- Information Notice 1997-23, Evaluation and Reporting of Fires and Unplanned Chemical Reaction Events at Fuel Cycle Facilities (7 May 1997, Topic: Earthquake)
- Information Notice 1997-24, Failure of Packing Nuts on One-Inch Uranium Hexafluoride Cylinder Valves (8 May 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-25, Dynamic Range Uncertainties in the Reactor Vessel Level Instrumentation (9 May 1997, Topic: Earthquake)
- Information Notice 1997-26, Degradation in Small-Radius U-Bend Regions of Steam Generator Tubes (19 May 1997, Topic: Earthquake)
- Information Notice 1997-27, Effect of Incorrect Strainer Pressure Drop on Available Net Positive Suction Head (16 May 1997, Topic: Earthquake)
- Information Notice 1997-28, Elimination of Instrument Response Time Testing Under the Requirements of 10 CFR 50.59 (30 May 1997, Topic: Enforcement Discretion)
- Information Notice 1997-29, Containment Inspection Rule (30 May 1997)
- Information Notice 1997-30, Control of Licensed Material During Reorganizations, Employee-Management Disagreements, and Financial Crises (3 June 1997)
- Information Notice 1997-31, Failures of Reactor Coolant Pump Thermal Barriers and Check Valves in Foreign Plants (3 June 1997)
- Information Notice 1997-32, Defective Worm Shaft Clutch Gears in Limitorque Motor-Operated Valve Actuators (10 June 1997)
- Information Notice 1997-33, Unanticipated Effect of Ventilation System on Tank Level Indications and Engineering Safety Features Actuation System Setpoint (11 June 1997)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels in Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels In Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (Inc) IR100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (INC) Ir100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-36, Unplanned Intakes by Worker of Transuranic Airborne Radioactive Materials and External Exposure Due to Inadequate Control of Work (20 June 1997)
- Information Notice 1997-37, Main Transformer Fault with Ensuing Oil Spill Into Turbine Building (20 June 1997)
- Information Notice 1997-38, Level-Sensing System Initiates Common-Mode Faulure of High-Pressure-Injection Pumps (24 June 1997, Topic: Hydrostatic)
- Information Notice 1997-39, Inadequate 10 CFR 72.48 Safety Evaluations of Independent Spent Fuel Storage Installations (26 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-40, Potential Nitrogen Accumulation Resulting from Backleakage from Safety Injection Tanks (26 June 1997)
- Information Notice 1997-41, Revised - Potentially Undersized Emergency Diesel Generator (EDG) Oil Coolers (27 June 1997)
- Information Notice 1997-42, Management Weaknesses Resulting in Failure to Comply with Shipping Requirements for Special Nuclear Material (27 June 1997)
- Information Notice 1997-43, License Condition Compliance (1 July 1997, Topic: Ultimate heat sink)
- Information Notice 1997-44, Failures of Gamma Metrics Wide-Range Linear Neutron Flux Channels (1 July 1997)
- Information Notice 1997-45, Environmental Qualification Deficiency for Cables & Containment Penetration Pigtails (2 July 1997)
- Information Notice 1997-46, Unisolable Crack in High-Pressure Injection Piping (9 July 1997, Topic: Flow Induced Vibration)
- Information Notice 1997-47, Inadequate Puncture Tests for Type B Packages Under 10 CFR 71.73(c)(3) (27 June 1997)
- Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures (9 July 1997, Topic: Safe Shutdown, Unanalyzed Condition, Fire Barrier, Emergency Lighting, Continuous fire watch, Fire Protection Program, Fire Watch)
... further results |
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