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Category:Legal-Exhibit
MONTHYEARML15337A3522015-11-17017 November 2015 Official Exhibit - NYS000582-00-BD01 - Diagram of Strength Vs Amplitude by Dr. Richard T. Lahey ML15337A3372015-11-11011 November 2015 Official Exhibit - ENTR00726-00-BD01 - Track 2 Hearing Exhibit List ML15337A3322015-11-0505 November 2015 Official Exhibit - ENT000726-00-BD01 - Entergy Track 2 Hearing Exhibit List ML15337A3352015-11-0505 November 2015 Official Exhibit - RIVR14001-00-BD01 - Riverkeeper Tailored Track 2 Exhibit List ML15337A3362015-11-0505 November 2015 Official Exhibit - NRCR10001-00-BD01 - NRC Staff Track 2 Exhibit List ML15337A3332015-11-0404 November 2015 Official Exhibit - NYSR25001-00-BD01 - NYS Revised Tailored Exhibits List Relevant to Track 2 Contentions ML15337A3312015-11-0303 November 2015 Official Exhibit - NRC000230-00-BD01 - Corrections to Prefiled Testimony NRC000168 and NRC000197 ML15337A3262015-10-29029 October 2015 Official Exhibit - ENT000722-00-BD01 - Supplemental Testimony of Entergy Witnesses Nelson Azevedo, Timothy Griesbach & Randy Lott ML15337A3292015-10-29029 October 2015 Official Exhibit - ENTR16001-00-BD01 - Entergy Revised Exhibit List ML15337A3242015-09-23023 September 2015 Official Exhibit - NYS000576-00-BD01 - Pre-Filed Supplemental Testimony of Richard T. Lahey Re Contentions NYS-25, NYS-26B/RK-TC-1B & NYS-38/RK-TC-5 ML15337A3072015-09-0909 September 2015 Official Exhibit - NYS000573-PUB-00-BD01 - Supplemental Reply Statement of Position of the State of New York and Riverkeeper, Inc. in Support of Contention NYS-38/RK-TC-5 (Public, Redacted) (September 9, 2015) ML15337A2962015-09-0909 September 2015 Official Exhibit - NYS000570-PUB-00-BD01 - Supplemental Reply Statement of Position of the State of New York and Riverkeeper, Inc. in Support of Contention NYS-26B/RK-TC-1B (Public, Redacted) (September 9, 2015) ML15337A2832015-09-0909 September 2015 Official Exhibit - NYS000563-00-BD01 - Pressurized Water Reactor (PWR) Systems, USNRC Technical Training Center, Reactor Concepts Manual, Pages 4-1 to 4-28 ML15337A2952015-09-0909 September 2015 Official Exhibit - NYS000569-PUB-00-BD01 - Pre-filed Supplemental Reply Testimony of Richard T. Lahey, Jr. in Support of Contention NYS-26B/RK-TC-1B (Public, Redacted) (September 9, 2015) ML15337A2942015-09-0909 September 2015 Official Exhibit - NYS000568-PUB-00-BD01 - Supplemental Reply Statement of Position of the State of New York in Support of Contention NYS-25 (Public, Redacted) (September 9, 2015) ML15337A2932015-09-0909 September 2015 Official Exhibit - NYS000567-PUB-00-BD01 - Pre-filed Supplemental Reply Testimony of Richard T. Lahey, Jr. in Support of Contention NYS-25 (Public, Redacted) (September 9, 2015) ML15337A3042015-09-0909 September 2015 Official Exhibit - NYS000571-PUB-00-BD01 - Pre-filed Supplemental Reply Testimony of David J. Duquette in Support of Contention NYS-38/RK-TC-5 (Public, Redacted) (September 9, 2015) ML15337A2972015-09-0909 September 2015 Official Exhibit - RIV000164-00-BD01 - NUREG-1740, ACRS, Voltage-Based Alternative Repair Criteria: a Report to the Advisory Committee on Reactor Safeguards by the Ad Hoc Subcommittee on a Differing Professional Opinion (2001) ML15337A3062015-09-0909 September 2015 Official Exhibit - NYS000572-PUB-00-BD01 - Pre-filed Supplemental Reply Testimony of Richard T. Lahey, Jr. in Support of Contention NYS-38/RK-TC-5 (Public, Redacted) (September 9, 2015) ML15337A2822015-09-0909 September 2015 Official Exhibit - NYS000566-00-BD01 - Figure 1 for Supplemental Reply Testimony of Dr. Richard T. Lahey ML15337A3142015-09-0404 September 2015 Official Exhibit - ENTR00615-PUB-00-BD01 - Entergy'S Statement of Position Re Contention NYS-25 (Embrittlement) - Redacted ML15334A2842015-08-10010 August 2015 Official Exhibit - ENT000687-00-BD01 - NRC, Safety Evaluation Report, Topical Report on ASME Section III Piping and Component Fatigue Analysis Utilizing the Westems Computer Code (WCAP-17577, Revision 2) (Undated) ML15335A2932015-08-10010 August 2015 Official Exhibit - NRCR00104-00-BD01 - on Yee Statement of Professional Qualifications (Revised) ML15337A2642015-08-10010 August 2015 Official Exhibit - NRC000196-PUB-00-BD01 - NRC Staff'S Initial Statement of Position on Contention NYS-25 (Reactor Vessel Internals) ML15337A3192015-08-10010 August 2015 Official Exhibit - ENT000698-PUB-00-BD01 - Entergy'S Revised Statement of Position Regarding Contention NYS-38/RK-TC-5(Safety Commitments) (Aug. 10, 2015)Redacted ML15337A3202015-08-10010 August 2015 Official Exhibit - ENT000699-PUB-00-BD01 - Redacted Revised Testimony of Entergy Witnesses Nelson Azevedo, Robert Dolansky, Alan Cox, Jack Strosnider, Timothy Griesbach, Barry Gordon, Randy Lott, and Mark Gray Regarding Contention NYS-38/RK ML15337A3172015-08-10010 August 2015 Official Exhibit - ENT000678-PUB-00-BD01 - NL-07-140, Letter from F. Dacimo, Entergy, to NRC Document Control Desk, ?Reply to Request for Additional Information Regarding License Renewal Application? (Nov. 28, 2007)Redacted ML15337A2652015-08-10010 August 2015 Official Exhibit - NRC000197-PUB-00-BD01 - NRC Staff Testimony of Dr. Allen Hiser, Jeffrey Poehler, and Gary Stevens on NYS-25 and NYS-38/RK-TC-5 ML15337A2412015-08-10010 August 2015 Official Exhibit - NRCR00147-00-BD01 - NRC Staff'S Revised Statement of Position on State of New York and Riverkeeper'S Joint Contention NYS-38/RK-TC5 (Revised) ML15335A2902015-08-10010 August 2015 Official Exhibit - NRC000222-00-BD01 - IP3 FSAR Rev. 04 Chapter 3 (2011) (Excerpt) ML15334A2632015-08-10010 August 2015 Official Exhibit - ENT000648-00-BD01 - M. Mitchell, Chief, Vessels and Internals Integrity Branch, Response to Non-Concurrence Regarding Safety Evaluation for Topical Report MRP-227 Pressurized Water Reactor Internals Inspection and Evaluat ML15337A2622015-08-10010 August 2015 Official Exhibit - NRC000228-00-BD01 - Indian Point Unit 2 Technical Specifications 3.1.4 ML15337A2452015-08-10010 August 2015 Official Exhibit - NRC000227-00-BD01 - Gary Stevens Statement of Professional Qualifications ML15337A2632015-08-10010 August 2015 Official Exhibit - NRC000229-00-BD01 - Indian Point, Unit 3 Technical Specifications 3.1.4 ML15335A2192015-08-10010 August 2015 Official Exhibit - ENTR00031-00-BD01 - Curriculum Vitae of Alan B. Cox ML15335A2112015-08-10010 August 2015 Official Exhibit - ENTR20186-00-BD01 - Curriculum Vitae of Mark A. Gray ML15337A3162015-08-10010 August 2015 Official Exhibit - ENT000616-PUB-00-BD01 - Testimony of Entergy Witnesses Nelson F. Azevedo, Robert J. Dolansky, Alan B. Cox, Jack R. Strosnider, Timothy J. Griesbach, Randy G. Lott, and Mark A. Gray Regarding Contention NYS-25 (Embrittleme ML15337A2782015-08-10010 August 2015 Official Exhibit - NRC000168-PUB-00-BD01 - NRC Staff Testimony of Dr. Allen Hiser, Dr. Ching Ng, Mr. Gary Stevens, P.E., and Mr. on Yee, Concerning Contentions NYS-26B/RK-TC-1B and NYS-38/RK-TC-5 ML15337A2712015-08-10010 August 2015 Official Exhibit - NRC000223-00-BD01 - IP3 FSAR Rev. 04 Chapter 14 (2011) ML15337A2592015-08-10010 August 2015 Official Exhibit - NRC000224-00-BD01 - IP3 FSAR Rev. 04 Chapter 16 ML15337A2442015-08-10010 August 2015 Official Exhibit - NRCR00161-00-BD01 - NRC Staff Testimony of Dr. Allen L. Hiser and Mr. Kenneth J. Karwoski Concerning Portions of State of New York and Riverkeeper, Inc. Joint Contention NYS-38/RK-TC5 (Revised) ML15334A2822015-08-10010 August 2015 Official Exhibit - ENT000680-00-BD01 - Curriculum Vitae of Barry M. Gordon ML15335A2912015-08-10010 August 2015 Official Exhibit - NRCR00118-00-BD01 - Indian Point Unit 3 Technical Specifications (Excerpt) (Revised) ML15334A2282015-08-10010 August 2015 Official Exhibit - ENT000634-00-BD01 - Entergy, IP2, FSAR Update, Revision 25 (2014) (Excerpts) ML15335A2822015-08-10010 August 2015 Official Exhibit - NRC000220-00-BD01 - Pressurized Water Reactor Owners Group (PWROG) Presentation Slides, Industry and NRC Coordination Meeting Materials Programs Technical Exchange: Clevis Insert Bolt Update, (June 2014) ML15337A2692015-08-10010 August 2015 Official Exhibit - NRC000169-00-BD01 - NRC000169 - Indian Point, Unit 2 Technical Specifications (Excerpt) ML15337A2602015-08-10010 August 2015 Official Exhibit - NRC000226-00-BD01 - Jeffrey C. Poehler Statement of Professional Qualifications ML15335A2732015-08-10010 August 2015 Official Exhibit - NRC000183-00-BD01 - NRC Inspection Manual, Inspection Procedure 71013, Site Inspection for Plants with a Timely Renewal Application (Sept. 25, 2013) ML15335A2202015-08-10010 August 2015 Official Exhibit - ENTR00184-00-BD01 - Curriculum Vitae of Jack R. Strosnider ML15335A3012015-08-10010 August 2015 Official Exhibit - NRC000206-00-BD01 - Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 25, Chapter 14 - Safety Analysis (2014) 2015-09-09
[Table view] |
United States Nuclear Regulatory Commission Official Hearing Exhibit NYS000190
Entergy Nuclear Operations, Inc.
In the Matter of:
(Indian Point Nuclear Generating Units 2 and 3) Submitted: December 16, 2011 c.,-VR REGU<..tr ASLBP #: 07-858-03-LR-BD01 l~"
Docket #: 05000247 l 05000286 Exhibit #: NYS000190-00-BD01 Identified: 10/15/2012
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~ Admitted: 10/15/2012 Withdrawn:
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, DC 20555-0001 March 3, 2004 NRC INFORMATION NOTICE 2004-05: SPENT FUEL POOL LEAKAGE TO ONSITE
GROUNDWATER
Addressees
All holders of operating licensees for nuclear power reactors (except those who have
permanently ceased operations and have certified that fuel has been permanently removed
from the reactor vessel) and for research and test reactors, and all holders of fuel storage
licenses and construction permits.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to inform
addressees of the recent identification of a longstanding leak to on site groundwater from the
spent fuel pool of an operating pressurized water reactor facility. 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 or written response is required.
Description of Circumstances
On September 18, 2002, the licensee for the Salem Nuclear Generating Station identified
evidence of radioactive water leakage through an interior wall located at the 24-meter (78-foot)
elevation of the Unit 1 auxiliary building mechanical penetration room, a radiologically controlled
area. The leak location, about 3 meters (10 feet) up a wall surface, was identified while the
licensee was following up low-level shoe contamination of personnel who had traversed the
room. The licensee established a comprehensive task action plan to identify and stop the
source of the leakage and evaluate possibly undetected leakage outside building structures.
The licensee did identify other locations where radioactive water was leaking through interior
walls or penetrations into both the Unit 1 auxiliary building and the Unit 1 fuel handling building
(FHB).
On February 6, 2003, the licensee identified the radionuclide tritium (H-3) in groundwater in two
test locations near the Unit 1 FHB. The test locations were within the licensee-controlled
restricted area. The licensee identified other locations of groundwater contamination in the
general vicinity of the Unit 1 FHB and within the restricted area. No other reactor-produced
radionuclides were detected in the groundwater sampling test locations.
ML040580454 OAGI0000173_000001 The licensee obtained technical support and concluded (based on leak testing of suspect
systems, chemical analysis of water samples, system and building configuration reviews, and a
geohydrological evaluation) that the likely source of the tritium was the Unit 1 spent fuel pool
(SFP). The licensee believes that the leakage was the result of the obstruction of the leakage
detection and collection system of the SFP stainless steel liner.
Discussion:
The Salem Unit 1 FHB is a seismically qualified structure that contains the Unit 1 SFP. Unit 1 SFP support systems in the Unit 1 auxiliary building pass through adjacent building walls to the
Unit 1 FHB. The walls are separated by a Styrofoam -filled 15-cm (6-inch) seismic gap and
the support systems traverse the seismic gap.
The Unit 1 SFP is a concrete structure with a stainless steel liner. The SFP includes an integral
liner leakage detection and collection system, consisting of an extensive network of collection
lines running both horizontally and vertically within the narrow gap between the SFP liner and
the concrete SFP structure. The collected liner leakage is discharged to a collection trough
through 17 drain lines (tell-tale drains). The tell-tale drains provide a means to detect, monitor, and quantify potential leakage from the SFP liner. The collected leakage is subsequently
directed to the liquid radioactive waste system for processing.
The licensee's reviews discovered that over the years since initial facility startup, materials such
as boric acid residue and minerals accumulated within the leak collection and detection system
and restricted the normal drainage of liquid. The reviews also found that a modification to the
tell-tale drains in 1998 resulted in the inadvertent introduction of sealant into the tell-tale drains, further restricting the free drainage of leakage from the liner. As a result, through-liner leakage
accumulated between the SFP liner and the concrete structure of the SFP. The accumulated
water, containing tritium, subsequently migrated to other locations through penetrations, concrete construction joints, and cracks. The seismic gap was confirmed to contain water with
radionuclides characteristic of Unit 1 SFP water. The water is believed by the licensee to have
made its way to the groundwater in the restricted area via the seismic gap.
The licensee cleaned the tell-tale drains, improving the drainage of the accumulated water
between the liner and spent fuel pool concrete structure and stopping the through-wall and
penetration leakage. After the cleaning effort, the leak rate from the tell-tale drains increased
from about 19 liters per day (5 gallons per day) to about 380 liters per day (100 gpd). The
leakage was properly collected.
The NRC conducted a special inspection of this issue (NRC Inspection Report 50-272/2003-
006; 50-311/2003-006, ADAMS Accession No. ML032890212). The NRC's and the licensee's
reviews identified the following information about this situation.
OAGI0000173 000002 1. The licensee took actions to identify specific leak locations, repair and mitigate the leak, and assess potential health and safety impacts. A comprehensive groundwater
sampling and analysis program was implemented. Although the licensee believes, with
a high degree of confidence, that the leak originated from the SFP, the licensee is
continuing evaluations to confirm this conclusion. The leakage itself was not
accompanied by large fluctuations in SFP water levels and was likely masked by
approximately equal volumes of evaporation from the SFP.
2. The licensee stopped the identified through-wall leakage by cleaning the tell-tales and
resumed controlled collection of SFP liner leakage via the installed leakage detection
and collection system. Extent-of-condition reviews revealed no apparent accumulation
of water between the SFP liner and concrete structure at Salem Unit 2.
3. The licensee's evaluations did not identify any immediate health and safety
consequences to on site workers or members of the public. No radionuclides associated
with the leakage were detected outside the onsite areas administered as access- controlled areas for purposes of radiation protection. The licensee did not detect any
tritium associated with this leak in areas accessible to the public (i.e., the unrestricted
area). The licensee subsequently developed and implemented an on site groundwater
remedial investigation work plan in conjunction with State of New Jersey
representatives.
4. The Unit 1 SFP had exhibited detectable leakage from the tell-tales since initial plant
operations. To monitor leakage from the tell-tales, the licensee established a
surveillance program. Over the years, the leakage from the tell-tales diminished but the
licensee was not able to tell from leakage changes if they needed further evaluation.
There was also a missed opportunity to evaluate earlier through-wall contaminated
leakage for possible accumulation of water between the Unit 1 FSP liner and concrete
structure.
5. There was no periodic maintenance of the SFP leakage detection and collection system
to ensure that drainage channels remained free and clear so that the system could
perform its design function of preventing water from accumulating behind the FHB walls.
The licensee initiated actions to develop a cleaning and maintenance process.
6. The licensee conducted evaluations of potential short-term adverse impacts to the SFP
structure. The preliminary evaluations did not identify any adverse effects that would
impact the design bases of the SFP or FHB structure. Nonetheless, the licensee
initiated laboratory testing of the effects of boric acid on concrete. The results of these
tests are being evaluated by the licensee for potential long-term effects.
The licensee developed numerous corrective action documents to track the review, evaluation, and correction of identified deficiencies.
OAGI0000173 000003 This information notice requires no specific action or written response. If there are any
questions about this notice, contact one of the persons listed below or the appropriate Office of
Nuclear Reactor Regulation (NRR) project manager.
IRA!
William D. Beckner, Chief
Reactor Operations Branch
Division of Inspection Program Management
Office of Nuclear Reactor Regulation
Technical Contacts: Ronald Nimitz, Region I Stephen Klementowicz, NRR
(610) 337-5267 (301) 415-1084 E-mail: rln@nrc.gov E-mail: sxk@nrc.gov
Suresh Chaudhary, Region I Jason Jang, Region I
(610) 337-5335 610-337-5220
E-mail: skc@nrc.gov E-mail jcj@nrc.gov
Attachment: List of Recently Issued NRC Information Notices
OAGI0000173 000004
NAME VCHODGE PKleene RNIMITZ TREIS
DATE 02/ /2004 02/10/2004 02/26/2004 02/25/2004 OFFICE C;IROB;DIPM
NAME WDBECKNER
DATE 03/03/2004
Attachment LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
2004-04 Fuel Damage During Cleaning 02/24/2004 All holders of operating licenses
at a Foreign Pressurized Water for light-water reactors, except
Reactor those who have permanently
ceased operations and have
certified that fuel has been
permanently removed from the
reactor.
2004-03 Radiation Exposures to 02/24/2004 All well-logging licensees.
Members of the Public in
Excess of Regulatory Limits
Caused by Failures to Perform
Appropriate Radiation Surveys
During Well-logging
Operations
2004-02 Strontium-gO Eye Applicators 02/05/2004 All U.S. Nuclear Regulatory
New Calibration Values and Commission (NRC) medical-use
Use licensees and NRC master
materials license medical-use
Permittees.
2004-01 Auxiliary Feedwater Pump 01/21/2004 All holders of operating licenses
Recirculation Line Orifice or construction permits for
Fouling - Potential Common nuclear power reactors, except
Cause Failure those that have permanently
ceased operations and have
certified that fuel has been
permanently removed from the
reactor.
Note: NRC generic communications may be received in electronic format shortly after they are
issued by subscribing to the NRC listserver as follows:
To subscribe send an e-mail to <listproc@nrc.gov >, no subject, and the following
command in the message portion:
subscribe gc-nrr firstname lastname
OL = Operating License
CP = Construction Permit
OAGI0000173 000006
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list | - Information Notice 2004-01, Auxiliary Feedwater Pump Recirculation Line Orifice Fouling - Potential Common Cause Failure (21 January 2004, Topic: Zebra Mussel)
- Information Notice 2004-02, Strontium-90 Eye Applicators: New Calibration Values and Use (5 February 2004, Topic: Brachytherapy)
- Information Notice 2004-04, Fuel Damage During Cleaning at a Foreign Pressurized Water Reactor (24 February 2004, Topic: Shutdown Margin, Fuel cladding, Recently irradiated fuel)
- Information Notice 2004-04, Fuel Damage During Cleaning At a Foreign Pressurized Water Reactor (24 February 2004, Topic: Shutdown Margin, Fuel cladding, Recently irradiated fuel)
- Information Notice 2004-05, Official Exhibit - NYS000190-00-BD01 - NRC Information Notice 2004-05, NRC Office of Nuclear Reactor Regulation, Spent Fuel Pool Leakage to Onsite Groundwater, (Salem, New Jersey, Nuclear Power Generating Sta (3 March 2004, Topic: Boric Acid, Through-Wall Leak)
- Information Notice 2004-05, Spent Fuel Pool Leakage To Onsite Groundwater (3 March 2004, Topic: Boric Acid, Through-Wall Leak)
- Information Notice 2004-06, Loss of Feedwater Isokinetic Sampling Probes At Dresden Units 2 and 3 (26 March 2004)
- Information Notice 2004-06, Loss of Feedwater Isokinetic Sampling Probes at Dresden Units 2 and 3 (26 March 2004)
- Information Notice 2004-07, Plugging of Safety Injection Pump Lubrication Oil Coolers with Lakeweed (7 April 2004)
- Information Notice 2004-08, Reactor Coolant Pressure Boundary Leakage Attributable to Propagation of Cracking In Reactor Vessel Nozzle Welds (22 April 2004, Topic: Weld Overlay, Hydrostatic, Nondestructive Examination, Pressure Boundary Leakage, Through-Wall Leak, Dissimilar Metal Weld)
- Information Notice 2004-08, Reactor Coolant Pressure Boundary Leakage Attributable to Propagation of Cracking in Reactor Vessel Nozzle Welds (22 April 2004, Topic: Weld Overlay, Hydrostatic, Nondestructive Examination, Pressure Boundary Leakage, Through-Wall Leak, Dissimilar Metal Weld)
- Information Notice 2004-09, Corrosion of Steel Containment and Containment Liner (27 April 2004, Topic: Coatings, Moisture barrier)
- Information Notice 2004-10, Loose Parts in Steam Generators (4 May 2004)
- Information Notice 2004-11, Cracking in Pressurizer Safety and Relief Nozzles and in Surge Line Nozzle (6 May 2004, Topic: Boric Acid, Weld Overlay, Dissimilar Metal Weld)
- Information Notice 2004-13, Registration, Use, and Quality Assurance Requirements for NRC-Certified Transportation Packages (30 June 2004)
- Information Notice 2004-14, Use of Less Then Optimal Bounding Assumptions In Criticality Safety Analysis at Fuel Cycle Facilities (19 July 2004)
- Information Notice 2004-14, Use of Less Then Optimal Bounding Assumptions in Criticality Safety Analysis at Fuel Cycle Facilities (19 July 2004)
- Information Notice 2004-15, Dual-Unit Scram At Peach Bottom Units 2 and 3 (22 July 2004, Topic: Hydrostatic, Condition Adverse to Quality, Significance Determination Process)
- Information Notice 2004-15, Dual-Unit Scram at Peach Bottom Units 2 and 3 (22 July 2004, Topic: Hydrostatic, Condition Adverse to Quality, Significance Determination Process)
- Information Notice 2004-18, Recent Safety Related Event at Panaromic Wet-Source-Storage Irradiator (26 October 2004)
- Information Notice 2004-19, Problems Associated with Back-up Power Supplies to Emergency Response Facilities and Equipment (4 November 2004)
- Information Notice 2004-20, Recent Issues Associated with NRC Medical Requirements for Licensed Operators (24 November 2004)
- Information Notice 2004-21, Additional Adverse Effect of Boric Acid Leakage: Potential Impact on Post-Accident Coolant pH (24 November 2004, Topic: Boric Acid)
- Information Notice 2004-21, Additional Adverse Effect of Boric Acid Leakage: Potential Impact on Post-Accident Coolant Ph (24 November 2004, Topic: Boric Acid, Pressure Boundary Leakage)
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