Solubility Criteria for Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20ML031070039 |
Person / Time |
---|
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: |
01/28/1994 |
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From: |
Burnett R, Paperiello C NRC/NMSS/FCSS, NRC/NMSS/IMNS |
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To: |
|
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References |
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IN-94-007, NUDOCS 9401240059 |
Download: ML031070039 (9) |
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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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Category:NRC Information Notice
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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 MATERIAL SAFETY AND SAFEGUARDS
WASHINGTON, D.C. 20555 January 28, 1994 NRC INFORMATION NOTICE 94-07: SOLUBILITY CRITERIA FOR LIQUID EFFLUENT
RELEASES TO SANITARY SEWERAGE UNDER THE
REVISED 10 CFR PART 20
-
Addressees
All byproduct material and fuel cycle licensees with the exception of
licensees authorized solely for sealed sources.
Purpose
The U.S. Nuclear Regulatory Commission is issuing this information notice to
emphasize the changes in 10 CFR Part 20 with respect to liquid effluent
releases t: sanitary sewerage and to encourage you to prepare for these
revisions. It is expected that licensees will review this information for
applicability to their operations, distribute it to appropriate staff, and
consider actions to prepare for, and incorporate, these changes. Suggestions
contained in this information notice are only recommendations; therefore, no
specific action nor written response is required.
Background
On December 21, 1984, NRC released an information notice documenting several
instances of reconcentration of radionuclides released to sanitary sewerage
(IN No. 84-94, "Reconcentration of Radionuclides Involving Discharges into
Sanitary Sewage Systems Permitted under 10 CFR 20.303"). Several other
instances have since occurred in Portland, Oregon; Ann Arbor, Michigan; Erwin, Tennessee; and Cleveland, Ohio. The primary contributors, in some of these
cases, appear to have been insoluble materials released as dispersible
particulates or flakes. This issue was-addressed again on May 21, 1991, by
NRC, when it published its revision of Part 20 in the Federal Register
(56 FR 23360), which removed insoluble non-biological material from the types
of material that may be released to sanitary sewerage. Relative to this
issue, the NRC Office of Nuclear Regulatory Research is conducting a study to
clarify the mechanisms underlying reconcentration in sanitary sewerage and
sewage treatment facilities.
9401240059 PI) XD E 4o+#.e. 9t-..7 cL~oI~-
sewers for carrying off waste water and refuse, but excluding sewage treatment
facilities, septic tanks, and leach fields owned or operated by the licene
[emphasis added]."
IN 94-07 January 28, 1994
Description of Circumstances
To help prevent further reconcentration incidents at public sewage treatment
facilities, 10 CFR 20.2003(a)(1), effective January 1, 1994, was written as
follows:
§20.2003 Disposal by release into sanitary sewerage
(a) A licensee may discharge licensed material into sanitary sewerage
if each of the following conditions is satisfied:
(1) The material is readily soluble (or is readily dispersible
biological material) in water; and...
However, this revision to Part 20 did not contain an operational definition of
solubility, and this precipitated many questions, from licensees, concerning
how the solubility of a material may be demonstrated. Without the ability to
demonstrate compliance, these licensees were unable to determine whether new
procedures should be developed, new treatment systems installed, or whether
they should apply for an exemption, based on the principle of maintaining all
doses as low as is reasonably achievable (ALARA).
Discussion
In some of the known reconcentration incidents, the greatest reconcentrations
appear to have been due to compounds released to sanitary sewerage that were
not soluble. There are many approaches that may be used to determine a
chemical compound's solubility in water. The following discusses two of the
more common approaches:
1. Direct Determination of Compound Solubilitv Class, Formal Solubilitv, or Solubility Product (K~fs
This approach would be applicable whenever there is sufficient
knowledge of the chemical form of all materials contained in the
liquid effluent at the point of release. With this knowledge, it
would be possible to use one (or more) of the following methods:
(a) Solubility Class Determination:
The solubility class of the compound to be released could be
determined directly from common literature data (e.g., Handbook of
Chemistry and Physics - CRC Press, and Lange's Handbook of
Chemistry - McGraw- Hill Book Company). If a compound is
classified as "v s" (very soluble) or "s" (soluble), this would
indicate the compound is "readily soluble." On the other hand, if
it is classified as "i" (insoluble), "si s" (slightly soluble), or
"v sl s" (very slightly soluble), this would indicate materials
that are "not readily soluble." Certain compounds are designated
as class "d". (decompose). If the decomposed species of these
compounds are classified as either "v s" or "s," this would
indicate that the parent compound is "readily soluble." If these
decomposed species are simple ions, such compounds (class "d")
should be considered "readily soluble."
IN 94-07 January 28, 1994 (b) Solubility Product (Kp) Determination:
The solubility product constant of the compound could also be used
to determine if a compound is readily soluble in water. The
solubility product constant, K8p, for a strong electrolyte MmAa is
expressed as:
KSP NM]' [A]a
where [M] and "m" are the ionic concentration (mole/liter) and the
number of moles, respectively, of the dissolved cation; and [A]
and "a" are the ionic concentration and the number of moles, respectively, of the dissolved anion.
For a simple electrolytic compound, with one mole of a dissolved
cation species and one mole of a dissolved anion species, a K
greater than 1.00 E-05 mole2/liter would indicate that a comp und
is "readily soluble." For other compounds with more complex.
dissolution reactions (i.e., more than one mole dissolved for each
species and/or more anionic or cationic species present in the
dissolved products), the Kp constant would increase
exponentially, based on the number of moles and/or the number of
dissociated species. For example, if three moles are present (two
for the anion and one for the cation), the unit of K wculd be
mole'/liter3, and the corresponding Ks would be (1 E!%5) / or
3.2 E-08 mole 3 /liter ; the same principle could be applied for
more complex dissolution reactions.
(c) Formal Solubility Determination:
Compound solubilities (g/100 ml or mole fraction per 100 ml) are
also listed in the chemical literature. From a review of general
scientific literature, "formal solubilities" greater than 0.003 mole/liter would indicate that a compound is "readily soluble."
The general relation between the formal solubility, Sf, and the solubility
product, K8p, of a strong electrolyte MA. in water is given by:
S5f K ap
\f+j
m '"a
where K is the solubility product, (M] is the molar concentration of the metal
ion (cafion), (A] is the molar concentration of the anion, "m" is the number of
moles of dissolved cation per mole of dissolved substance, and "a" is the number
of moles of the dissolved anion per mole of dissolved substance.
For further discussion on the determination of solubility products and formal
solubility, refer to Chapter 6, "Precipitation and Dilution," from Water
Chemistry, by Vernon L. Snoeyink and David Jenkins (John Wiley and Sons: 1983)
or texts relating to physical and/or analytical chemistry.
1 be94-07 January 28, 1994 Formal solubilities less than 0.003 mole/liter would indicate
compounds that are "not readily soluble."
It should be pointed out that all values mentioned above (e.g.,
solubility class, formal solubility, and solubility product)
correspond to measurements taken under standard conditions (e.g.,
25*C, 101.3 kPa, pH of 7, and Eh of 0.
2. Filtration and Radiometric Analysis of Suspended Solids
This approach may be used if knowledge of the chemical form of all
materials contained in the liquid effluent at the point of release is
incomplete. It is most applicable when releases are made in a batch
mode. This approach involves the use of standard laboratory
procedures to test representative samples of the waste stream for the
presence of suspended radioactive material.
The following two laboratory procedures were developed specifically to
determine the suspended solids content of water: ASTM Method D 1888-
78, "Standard Test Methods for Particulate and Dissolved Matter, Solids, or Residue in Water," and the American Public Health
Association's Method 7110, "Gross Alpha and Gross Beta Radioactivity
(Total, Suspended, and Dissolved)" from Standard Methods for the
Examination of Water and Wastewater. It should be noted that ASTM
Method D 1888-78 was developed to measure the total suspended solids
content of water, not just the radioactive portion. In either case, activity in the suspended solids portion of effluent greater than that
found in similarly processed background water samples would indicate
the presence of insoluble radioactive material.
Whether one of the above approaches or a self-developed alternative is used, it is a good health physics practice to document this approach in the form of
a procedure. Procedures such as these usually include provisions for the
documentation of any models, calculations, analytical measurements, and/or
quality control 'measures used. This information is usually maintained with
the applicable release records, to demonstrate that the developed procedure
will ensure compliance with the regulations.
If material to be released would not qualify as being "readily soluble,"
10 CFR 20.2003(a)(1) would prohibit release to sanitary sewerage unless an
exemption has been granted. Exemptions will be judged on a case-by-case
basis, when it is demonstrated that release to sanitary sewerage is in
accordance with the ALARA principle, consistent with applicable regulations, and in the public interest.
It is expected that licensees will review this information for applicability
to their operations, and consider actions, as appropriate to their licensed
activities. However, suggestions contained in this information notice are not
NRC requirements; therefore, no specific action nor written response is
required.
IN 94-07 January 28, 1994 If you have any questions about the information in this information notice, please contact one of the technical contacts listed below or the appropriate
regional office.
Robert F. Burnett, Director Carl J. Paper llo, Director
Division of Fuel Cycle Safety Division of Industrial and
and Safeguards Medical Nuclear Safety
Office of Nuclear Material Office of Nuclear Material
Safety and Safeguards Safety and Safeguards
Technical contacts: Rateb (Boby) Abu-Eid, NMSS
(301) 504-3446 Cynthia G. Jones, NMSS
(301) 504-2629 Attachments:
1. List of References
2. List of Recently Issued NMSS Information Notices
3. List of Recently Issued NRC Information Notices
NMSS Editor
EKraus
01/03/94 *See Drevious concurrence
OFC IMOB* I IMOB* I IMOB* lI LW LLWM I FC
NAME BRadcliffe CJones FCombs BEid* JGreeves RBurnett
DATE 12/15/93 - 12/16/93 , 12/16/93 12/29/93 12/21/93 ,01 I/94 OFC RES* I OGC* I IMNS* I IMiS. /2 II
NAME BMorris STreby EWBrach C}P4II
Pi eil Io
DATE 12/21/93 12/30/93 01/06/94 401//94 DOC NAME: IN94-07.CGJ
Attachment 1 IN 94-07 January 28, 1994 REFERENCES
Annual Book of ASTM Standards. Volume 11.01, "Water (I)." American Society
for Testing and Materials, Easton, MD, 1989.
CRC Handbook of Chemistry and Physics. CRC Press, Inc., Boca Raton, FL, 65 th
ed, 1984.
Lange's Handbook of Chemistry. McGraw-Hill, Inc., New York, NY, 13th ed,
1985.
Snoeyink, Vernon L. and David Jenkins, Water Chemistry. John Wiley & Sons, Inc., New York, NY, 1980.
Standard Methods for the Examination of Water and Wastewater. American Public
Health Association, Washington, DC, 17 ed, 1989.
tchment
% 2 IN 94-07 January 28, 1994 LIST OF RECENTLY ISSUED
NMSS INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-100 Reporting Requirements 12/22/93 All U.S. Nuclear Regulatory
for Bankruptcy Commission licensees.
93-80 Implementation of the 10/08/93 All byproduct, source, and
Revised 10 CFR Part 20 special nuclear material
licensees.
93-77 Human Errors that Result 10/04/93 All nuclear fuel cycle
in Inadvertent Transfers licensees.
of Special Nuclear Material
at Fuel Cycle Facilities
93-69 Radiography Events at 09/02/93 All holders of OLs or CPs
Operating Power Reactors for nuclear power reactors
and all radiography
licensees.
licensees.
93-60 Reporting Fuel Cycle and 08/04/93 All fuel cycle and materials
Materials Events to the licensees.
NRC Operations Center
93-50 Extended Storage of 07/08/93 All licensees authorized
Sealed Sources to possess sealed sources.
93-36 Notifications, Reports, 05/07/93 All U.S. Nuclear Regulatory
and Records of Misadmin- Commission medical
istrations licensees.
93-31 Training of Nurses 04/13/93 All U.S. Nuclear Regulatory
Responsible for the Commission medical
Care of Patients with licensees.
Brachytherapy-Implants
93-30 NRC Requirements for 04/12/93 All U.S. Nuclear Regulatory
Evaluation of Wipe Commission medical
Test Results; Cali- licensees.
bration of Count Rate
Survey Instruments
At\ chment 3 IN 94-07 January 28, 1994 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
94-06 Potential Failure of 01/28/94 All holders of OLs or CPs
Long-Term Emergency for boiling water reactors.
Nitrogen Supply for the
Automatic Depressurization
System Valves
93-85, Problems with X-Relays 01/20/94 All holders of OLs or CPs
Rev. 1 in DB- and DHP-Type for nuclear power reactors.
Circuit Breakers Manu- factured by Westinghouse
94-05 Potential Failure of 01/19/94 All holders of OLs or CPs
Steam Generator Tubes for pressurized water
with Kinetically Welded reactors (PWRs).
Sleeves
94-04 Digital Integrated 01/14/94 All NRC licensees except
Circuit Sockets with licensed operators.
Intermittent Contact
94-03 Deficiencies Identified 01/11/94 All holders of OLs or CPs
during Service Water System for nuclear power reactors.
Operational Performance
Inspections
94-02 Inoperability of General 01/07/94 All holders of OLs or CPs
Electric Magne-Blast for nuclear power reactors.
Breaker Because of Mis- alignment of Close-Latch
Spring
94-01 Turbine Blade Failures 01/07/94 All holders of OLs or CPs
Caused by Torsional for nuclear power reactors.
Excitation from Electrical
System Disturbance
93-101 Jet Pump Hold-Down Beam 12/17/93 All holders of OLs or CPs
Failure for boiling-water reactors.93-100 Reporting Requirements 12/22/93 All U.S. Nuclear Regulatory
for Bankruptcy Commission licensees.
OL = Operating License
CP - Construction Permit
K>
IN 93-XX
December XX, 1993 Page 5 of X
This information notice requires no specific action nor written response f
you have any question about the information in this notice, please co ct one
of the technical contacts listed below or the appropriate regional fice.
Brian K. Grimes, Director Carl . Paperiello, Director
Division of Operating Reactor Div ion of Industrial and
Support edical Nuclear Safety
Office of Nuclear Reactor ffice of Nuclear Material
Regulation Safety and Safeguards
Techinical Contacts: Rateb (Bob Abu-Eid, NMSS
(301) 50 3446 Cynth G. Jones, NMSS
(30 504-2629 Attachments:
1. List of Referens
2. List of Recen y Issued NMSS Information Notices
3. List of Rec ly Issued NRC Information Notices
OFC IMOB lO ,l MBB LLM LLWM l FCSS NRR/DRSS
NAME BRadcliffe go es Fl s' ___-d _ JGreeves RBurnett FCongel
DATE 12/AS-93 /IH/0/93 3 t /.2q/93 / /93 / /93 / /93 OFC RES _ OGC I MNS I IMNS l LNRR/DORS Ili
NAME BMorris STreby EWBrach CPaperiello BGrimes
DATE /93 / I 93 / /93 / /93
/ /_/93 _ ___
C . COVER E = COVER & ENCLOSURE N a NO COPY
OFFICIAL RECORD COPY: G:INFOSWR2.311
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list | - Information Notice 1994-01, Turbine Blade Failures Caused by Torsional Excitation from Electrical System Disturbance (7 January 1994)
- Information Notice 1994-02, Inoperability of General Electric Magne-Blast Breaker Because of Misalignment of Close-Latch Spring (7 January 1994)
- Information Notice 1994-03, Deficiencies Identified During Service Water System Operational Performance Inspections (11 January 1994, Topic: Biofouling)
- Information Notice 1994-04, Digital Integrated Circuit Sockets with Intermittent Contact (14 January 1994)
- Information Notice 1994-05, Potential Failure of Steam Generator Tubes with Kinetically Welded Sleeves (19 January 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-06, Potential Failure of Long-Term Emergency Nitrogen Supply for the Automatic Depressurization System Valves (28 January 1994)
- Information Notice 1994-07, Solubility Criteria for Liquid Effluent Releases to Sanitary Sewerage Under the Revised 10 CFR Part 20 (28 January 1994)
- Information Notice 1994-08, Potential for Surveillance Testing to Fail to Detect an Inoperable Main Steam Isolation Valve (1 February 1994)
- Information Notice 1994-09, Release of Patients with Residual Radioactivity from Medical Treatment & Control of Areas Due to Presence of Patients Containing Radioactivity Following Implementation of Revised 10 CFR Part 20 (3 February 1994, Topic: Brachytherapy)
- Information Notice 1994-10, Failure of Motor-Operated Valve Electric Power Train Due to Sheared or Dislodged Motor Pinion Gear Key (4 February 1994)
- Information Notice 1994-11, Turbine Overspeed and Reactor Cooldown During Shutdown Evolution (8 February 1994, Topic: Overspeed trip, Overspeed)
- Information Notice 1994-12, Insights Gained from Resolving Generic Issue 57: Effects of Fire Protection System Actuation on Safety-Related Equipment (9 February 1994, Topic: Overspeed)
- Information Notice 1994-13, Unanticipated and Unintended Movement of Fuel Assemblies and Other Components Due to Improper Operation of Refueling Equipment (28 June 1994)
- Information Notice 1994-14, Failure to Implement Requirements for Biennial Medical Examinations and Notification to the NRC of Changes in Licensed Operator Medical Conditions (24 February 1994, Topic: Overspeed)
- Information Notice 1994-15, Radiation Exposures During an Event Involving a Fixed Nuclear Gauge (2 March 1994, Topic: Overspeed)
- Information Notice 1994-16, Recent Incidents Resulting in Offsite Contamination (3 March 1994, Topic: Overspeed)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (QMP), Calibration, and Use (11 March 1994, Topic: Brachytherapy, Overspeed)
- Information Notice 1994-17, Strontium-90 Eye Applicators: Submission of Quality Management Plan (Qmp), Calibration, and Use (11 March 1994, Topic: Brachytherapy, Overspeed)
- Information Notice 1994-18, Accuracy of Motor-Operated Valve Diagnostic Equipment (Responses to Supplement 5 to Generic Letter 89-10) (16 March 1994)
- Information Notice 1994-19, Emergency Diesel Gemerator Vulnerability to Failure from Cold Fuel Oil (16 March 1994)
- Information Notice 1994-20, Common-Cause Failures Due to Inadequate Design Control and Dedication (17 March 1994)
- Information Notice 1994-21, Regulatory Requirements When No Operations Are Being Performed (18 March 1994)
- Information Notice 1994-22, Fire Endurance & Ampacity Derating Test Results for 3-Hour Fire-Rated Thermo-Lag 330-1 Fire Barriers (16 March 1994, Topic: Fire Barrier)
- Information Notice 1994-23, Guidance to Hazardous, Radioactive and Mixed Waste Generators on the Elements of a Waste Minimization Program (25 March 1994, Topic: Fire Barrier)
- Information Notice 1994-24, Inadequate Maintenance of Uninterruptible Power Supplies & Inverters (24 March 1994, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1994-25, Failure of Containment Spray Header Valve to Open Due to Excessive Pressure from Inertial Effects of Water (15 March 1994, Topic: Fire Barrier, Water hammer)
- Information Notice 1994-26, Personnel Hazards and Other Problems from Smoldering Fire-Retardant Material in the Drywell of a Boiling-Water Reactor (28 March 1994, Topic: Fire Barrier)
- Information Notice 1994-27, Facility Operating Concerns Resulting from Local Area Flooding (31 March 1994, Topic: Fire Barrier)
- Information Notice 1994-28, Potential Problems with Fire-Barrier Penetration Seals (5 April 1994, Topic: Fire Barrier, Operability Determination)
- Information Notice 1994-29, Charging Pump Trip During a Loss-of-Coolant Event Caused by Low Suction Pressure (11 April 1994, Topic: Boric Acid)
- Information Notice 1994-30, Leaking Shutdown Cooling Isolation Valves at Cooper Nuclear Station (19 August 1994, Topic: Fire Barrier, Local Leak Rate Testing)
- Information Notice 1994-31, Potential Failure of Wilco, Lexan-Type HN-4-L Fire Hose Nozzles (14 April 1994, Topic: Hydrostatic, Stress corrosion cracking)
- Information Notice 1994-32, Revised Seismic Estimates (29 April 1994, Topic: Stress corrosion cracking, Earthquake)
- Information Notice 1994-33, Capacitor Failures in Westinghouse Eagle 21 Plant Protection Systems (9 May 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-34, Thermo-LAG 330-660 Flexi-Blanket Ampacity Derating Concerns (13 May 1994, Topic: Fire Barrier, Stress corrosion cracking)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(Mmr) from the Facepiece on the Mine Safety Appliances (16 May 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-35, Niosh Respirator User Notices, Inadvertent Separation of the Mask-Mounted Regulator(MMR) from the Facepiece on the Mine Safety Appliances (16 May 1994)
- Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System (24 May 1994, Topic: Reactor Vessel Water Level, Stress corrosion cracking, Integrated leak rate test)
- Information Notice 1994-37, Misadministration Caused by a Bent Interstitial Needle During Brachytherapy Procedure (27 May 1994, Topic: Stress corrosion cracking, Brachytherapy)
- Information Notice 1994-38, Results of Special NRC Inspection at Dresden Nuclear Power Station, Unit 1 Following Rupture of Service Water Inside Containment (27 May 1994)
- Information Notice 1994-39, Identified Problems in Gamma Stereotactic Radiosurgery (31 May 1994)
- Information Notice 1994-40, Failure of a Rod Control Cluster Assembly to Fully Insert Following a Reactor Trip at Braidwood, Unit 2 (26 May 1994)
- Information Notice 1994-41, Problems with General Electric Type Cr124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-41, Problems with General Electric Type CR124 Overload Relay Ambient Compensation (7 June 1994)
- Information Notice 1994-42, Cracking in the Lower Region of the Core Shroud in Boiling-Water Reactors (7 June 1994, Topic: Stress corrosion cracking)
- Information Notice 1994-43, Determination of Primary-to-Secondary Steam Generator Leak Rate (10 June 1994, Topic: Grab sample)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand Because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-44, Main Steam Isolation Valve Failure to Close on Demand because of Inadequate Maintenance and Testing (16 June 1994)
- Information Notice 1994-45, Potential Common-Mode Failure Mechanism for Large Vertical Pumps (17 June 1994, Topic: Biofouling)
- Information Notice 1994-46, Nonconservative Reactor Coolant System Leakage Calculation (20 June 1994, Topic: Unidentified leakage)
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