Similar Documents at Salem |
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Category:Letter
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Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) LR-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023 Core Operating Limits Report Cycle 27 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location ML23089A0942023-04-17017 April 2023 NRC to PSEG Hope Creek, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23087A1492023-04-17017 April 2023 NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23103A3232023-04-13013 April 2023 Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - 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[Table view] Category:Written Event Report (30 or 60 day)
MONTHYEARLR-N23-0055, Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days2023-08-0303 August 2023 Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days LR-N21-0083, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2021 & 30 Day Report for Salem Unit 2 Upflow Conversion2021-11-24024 November 2021 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2021 & 30 Day Report for Salem Unit 2 Upflow Conversion ML0333606682003-11-24024 November 2003 Special Report 03-002 Re Condenser Off Gas Monitor Being Inoperable for Greater than Seven Days ML19031A9121997-02-25025 February 1997 LER 1977-009-01 for Salem Unit 1 No. 12 Containment Fan Coil Unit Inoperable ML19031B1781977-02-25025 February 1977 LER 1977-010-01 for Salem, Unit 1 No. 12 Containment Fan Coil Unit Inoperable ML19031B0621977-02-24024 February 1977 LER 1977-011-01 and LER 1977-013-01 for Salem Unit 1 Industrial Waste Was Discharged from the Treatment Area When the Ph Was Outside the Range of 6~5 to 8.5 ML19031B1791977-02-15015 February 1977 LER 1977-006-01 for Salem Unit 1 #12 Reactor Coolant Flow Channel 1 Inoperable ML19031A9151977-02-15015 February 1977 LER 1977-007-01 for Salem Unit 1 No. 12 Steam Generator Steam Flow Channel II Inoperable ML19031B0631977-02-15015 February 1977 LER 1977-008-01 for Salem Unit 1 No. 13 Steam Generator Steam Flow Channel I Inoperable ML19031A9161977-02-0707 February 1977 LER 1977-004-01 for Salem, Unit 1, #13 Auxiliary Feed Pump Fail to Start ML19031B5731977-02-0101 February 1977 LER 1976-029-01 for Salem Unit 1 Phase III Test Procedure ML19031A8271977-01-31031 January 1977 LER 1977-005-01 for Salem, Unit 1, Hydraulic Line Flange on Nos. 11 and 12 Main Steam Isolation Valves and Subsequent Violation of Technical Specification 3.0.3 ML19031B0641977-01-28028 January 1977 LER 1976-031-01 for Salem, Unit 1, Boron Injection Tank Inoperable ML19031B0651977-01-28028 January 1977 LER 1977-001-01 for Salem, Unit 1, Containment Pressure Protection, Channel II, PT-948C, Inoperable ML19031B0671977-01-28028 January 1977 LER 1977-002-01 for Salem, Unit 1, Pipe Failure on Letdown Vent Line ML19031B5741977-01-28028 January 1977 LER 1976-030-01 for Salem Unit 1 No. 11 and No. 12 Boric Acid Storage Tanks Inoperable ML19031B1801977-01-19019 January 1977 LER 1976-028-42 for Salem, Unit 1 Radioactive Spill and Unauthorized Release ML19031B0681977-01-14014 January 1977 LER 1976-026-01 for Salem, Unit 1, Boron Injection Tank Inoperable ML19031A7621977-01-14014 January 1977 LER 1976-020-01 for Salem, Unit 1 High Reactor Coolant System Chlorides ML19031B1811977-01-14014 January 1977 LER 1976-025-01 for Salem Unit 1 Reduction of Shutdown Margin During Special Test Exceptions ML19031A9191977-01-0404 January 1977 LER 1976-024-01 for Salem, Unit 1, Failure of Radiation Monitoring System Channel Rlla, Containment/Plant Vent Air Particulate Monitor ML19031A5471977-01-0404 January 1977 LER 1976-017-01 for Salem, Unit 1 Inoperable Personnel Air Lock - Elevation 100' ML19031A9201977-01-0303 January 1977 LER 1976-016-01 for Salem Unit 1 Improper Use of Test Leads ML19031A9181976-01-0707 January 1976 LER 1976-021-01 for Salem, Unit 1, Boron Injection Tank Inoperable 2023-08-03
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I Frederick W. Schneider 80 Park Place Newark, N.J. 07101 201/622-7000 Vice President Production January 7, 1976
Dear Mr. O'Reilly:
LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 76-21/3L Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6.9.1, we are submitting Licensee Event Report for Reportable Occurrence 76-21/3L. This
- report is required within thirty*(30) days of tJ;ie occurrence.
Sincerely yours, p~
CC: Director, Office of Inspection and Enforcement (30 copies)
Director, Office of Management Information and Program Control (3 copies)
Report Number: 76~il/3L Report Date: 1.6/76 Occurrence Date: 12/10/76
!tacility -Salem Generating Station Public Service Electric & Gas Company .
Hancocks Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:
Boron Injection Tank. Inoperable.
CONPITIONS PRIOR TO OCCURRENCE: .
- Mode 3 operation, Plant pressure 2235 psig, Plant temperature 547°F.
pESCRIPTION OF OCCURRENCE:
On 12/10/76; at 5:45 AM, the Chemistry Technician reported the Boron Injection Tank sample analysis for boron concentration was 19~899 ppm.
This value*is below the minimum concentration of .20,100 ppm as specified in Tech Spec L.C.O. paragraph 3.5.4.l(b). The Shift Supervisor imple-mented Technical Specification Action Statement for L.C.O. paragraph 3.5.4.1 and requested additional samples be taken and analyzed. At 10:00 AM,* on 12/10/76, the Chemistry Technician reported the re-analysis indicated the Boron Injection Tank boron concentration was 20,540 ppm.
Technical Specification Action Statement was cancelled.
DESIGNATION OF APPARENT-CAUSE OF OCCURRENCE:
Personnel error in analyzing the boron concentration of the Boron Injec-tion Tank. . The Chemistry Technician did not run a duplicate analysis as stated in the procedur~ to verify the first sample analysis.
ANALYSIS OF OCCURRENCE:
Improper sampling analytical techniques declared the Boron Injection Tank inoperable. SuQsequent sample analysis verifieq proper boron concentra-
. tion in the Boron Injection Tank. At no time was there any hazard to the general public or site personnel.
CORRECTIVE ACTION:
The Chemistry Technician was re-instructed on sample analytical tech-niques and procedural instructions which requires duplicate analysis to be performed. ...
FAILURE DATA:
This is the second failure of this type.
Equipment Identification: .Not Applicable B. Canfield Manager - Station SORC. Meeting No. 122-76
~~~~~~~
CONTROL BLOCK L.ICENSEE I
. Ll&SEE EVENT REPORT 6
L.ICENSE
... -~
NAME L.ICENSE NUMBER TYPE TYPE:
@ITJ4N1J-1s1G1s1~1 ts°101--1010101010-1-101qJ 141111111 lJo WJ.14.
REPORT REPORT CATEGORY TY~ SOURCE OOC:KET NUMBER EVENT CATE REPORT CATE roJ11 coN"TtRJ..Qj
~ 57 58 IL I 59
~
60 I 0 I 51 0 I -I 0 I 21 71 2J 61 111 2 111 0 17 I 6 I 69 74 11121 1 I 6 I 7 I
. 75 6J EVENT DESCRIPTION
@li] I On 12/10/76, at 5:45 AM, the Chemistry Technician reported the Boron In-1 7 8 9 so
@:ill j ec tion Tank sample analysis for boron concentration was 19,899 ppm.
7 89
.@El This value is below .the minimum concentration of 20, 100 ppm as specified 7 8 .
liifill in Technical Specification L.C.O. paragraph 3.5.4.l(b). The Shift Super7 7 89 eo
~ [ visor implemented Tech Spec Action Statement for L.C.O. paragraph 3.5.4.lj 1 a 9 SYSTEM CAUSE PRIME COMPONENT COMPONENT eo COOE cooe: COMPONENT cooe SUPflt.IER MANUFACTURER VIOLATION
@))IS IF I lA.1 IX I X I X I X I X-1.X.] l!J I Z I 919I91 lliJ 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION
@]fil I Personnel error in analyzing the boron concentration of the Boron Injec-1
~9 * . so l.!Ll!ll tion Tank. Manufacturer's nameplate data not applicable. The Technician I 7 B 9 SO
[@]I was re-instructed on sample analytical techniques and procedural I 1 89 eo FACIL.ITV METHOOOF r.r.1 STATUS ** ~POWER OTHER STATUS DISCOVERY OISC:OVERY OESCRIPTION l!-l.!..I . . Lill . 10 lo 10 I l~,__~Nul~A,,___.;;.__.I @J I* Chemistry Analysis 1 a 9 10 12 13 44 45 46 80
- FORM OF ACTIVITY CONTENT REl..EASEO OF REI.EASE AMOUNT OF ACTIVl*Tv LOCATION OF RELEASE
.7 GE8 LkJ 9
l!J 10 I
11 N/A
~
I '~-----N~/A
~
_________~I 80 PERSc;lNNEL. EXPOSURES
- r.r.;'J NUMBER TYPE OESCRIPTION t!.2.J\010101 !].JI~---~~~N~/=A~~--.-~--.----~~~--.-~-----.-~~~~--,,.,!I 7 8 9 11 12 13 80 PERSONNEL. INJURIES
- NUMBER. OESCRIPTION G:EJto 101011I 7 a§ N A
~12:r--------------..;;;....l,---'--------------------------------------------------ao~
~ .*
OFFSITE CONSEQUENCSS
~~ ... N/A LOSS OR OAMAG& TO FACILITY TYPE CESCAIPTION l"a! t;J ~~a.----------_.,.....N. ./=A'--------.,..---------~-.'"""'J PUSL.ICITY GIB0~9------..,..-------------------=~:i...---------------..,..---------------------------------!so 1
AOOITIONAL. FACTORS III!JI EVENT DESCRIPTION AND CAUSE DESCRIPTION (Continued on Page 2) I 7 8 9 eo ITEJ'c;"-~----------~~------~----------------~----~-------------..._.i 1 ai ao NAME=-------=B:;...;..**_. .;:;;E~*;__C~a~n_f_:i.._*e_l~d_ _ __ PHONE: (609) 365-7000 Ext.Salem-525: i
-l- 12/16/76
~
EVEN! DESCRIPTION (Continued)
~
- l and requested additional samples be taken and analyzed. At 10:00 AM, on 12/10/76, the* Chemistry Technician reported the re-analysis indicated that the Boron Injection Tank boron concentration was 20,540 ppm. Technical Specification Action Statement was cancelled.
The Boron Injection Tank is a passive component common to both ECCS subsystems and therefore, no redundant component exists. This is the second occurrence of this type. (76~21/3L).
CAUSE DESCRIPTION (Continued) instructions to perform duplicate analysis.