|
---|
Category:Letter
MONTHYEARML24022A1172024-01-23023 January 2024 Acceptance of Requested Licensing Action Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML24012A2422024-01-16016 January 2024 Acceptance of Requested Licensing Action License Transfer Request ML23236A0042023-12-27027 December 2023 Issuance of Amendment 274 Re Changes to Perm Defueled Emergency Plan and Perm Defueled Emergency Action Level Scheme ML23355A1242023-12-26026 December 2023 Withdrawal of an Amendment Request Re License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML23192A0772023-12-26026 December 2023 Letter Exemption from the Requirements of 10 CFR 140.11(a)(4) Concerning Offsite Primary and Secondary Liability Insurance ML23191A5222023-12-22022 December 2023 Exemption Letter from the Requirements of 10 CFR 50.54(W)(1) Concerning Onsite Property Damage Insurance (EPID - L-2022-LLE-0032) ML23263A9772023-12-22022 December 2023 Exemption from Certain Emergency Planning Requirements and Related Safety Evaluation ML23354A2602023-12-21021 December 2023 Reference Simulator Inspection Request for Information L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 PNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations PNP 2023-035, Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements2023-12-12012 December 2023 Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements PNP 2023-028, Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments2023-12-0606 December 2023 Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23291A4402023-11-0303 November 2023 Acceptance of Requested Licensing Action Request for Exemption from 10 CFR 50.82(a)(2) to Support Reauthorization of Power Operations IR 05000255/20230032023-10-0404 October 2023 NRC Inspection Report No. 05000255/2023003(DRSS)-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23275A0012023-10-0202 October 2023 Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant PNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023 Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 PNP 2023-026, Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations2023-09-28028 September 2023 Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations PNP 2023-023, Special Report High Range Noble Gas Monitor Inoperable2023-08-0909 August 2023 Special Report High Range Noble Gas Monitor Inoperable ML23215A2302023-08-0303 August 2023 Notice of Organization Change - Chief Nuclear Officer IR 05000255/20230022023-07-19019 July 2023 NRC Inspection Report 05000255/2023002 DRSS-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23087A0362023-05-0202 May 2023 PSDAR Review Letter ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment PNP 2023-018, 2022 Annual Non-Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Non-Radiological Environmental Operating Report L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 PNP 2023-007, and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports2023-04-19019 April 2023 and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports PNP 2023-008, 2022 Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Radiological Environmental Operating Report L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations PNP 2023-002, 6 to Updated Final Safety Analysis Report2023-03-31031 March 2023 6 to Updated Final Safety Analysis Report ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance PNP 2023-006, Report of Changes to Security Plan, Revision 202023-03-29029 March 2023 Report of Changes to Security Plan, Revision 20 PNP 2023-012, Presentation on Regulatory Path to Reauthorize Power Operations2023-03-16016 March 2023 Presentation on Regulatory Path to Reauthorize Power Operations ML23038A0982023-03-15015 March 2023 Request for Withholding Information from Public Disclosure ML23095A0642023-03-14014 March 2023 American Nuclear Insurers, Notice of Cancellation Rescinded PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations PNP 2023-004, Report of Changes to Palisades Nuclear Plant Technical Specification Bases2023-03-0808 March 2023 Report of Changes to Palisades Nuclear Plant Technical Specification Bases PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23052A1092023-02-17017 February 2023 FEMA Letter to NRC, Proposed Commission Paper Language for Palisades Nuclear Plant Emergency Plan Decommissioning Exemption Request ML23032A3992023-02-0101 February 2023 Regulatory Path to Reauthorize Power Operations IR 05000255/20220032022-12-28028 December 2022 NRC Inspection Report No. 05000255/2022003(DRSS); 07200007/2022001 (Drss) Holtec Decommissioning International, LLC, Palisades Nuclear Plant L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 PNP 2022-037, Report of Changes to Security Plan, Revision 192022-12-14014 December 2022 Report of Changes to Security Plan, Revision 19 ML22321A2852022-11-17017 November 2022 LLC Master Decommissioning Trust Agreement for Palisades Nuclear Plant IR 05000255/20224012022-11-0909 November 2022 Decommissioning Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2022401 PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-035, International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations2022-11-0202 November 2022 International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations PNP 2022-024, Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance PNP 2022-026, Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance ML22292A2572022-10-25025 October 2022 Permanently Defueled Emergency Plan License Amendment RAI Letter 2024-01-23
[Table view] Category:Licensee Event Report (LER)
MONTHYEARML18344A4142018-12-10010 December 2018 LER 1979-037-00 for Palisades Nuclear Plant, Two Manual Three Inch Containment Isolation Valves in Bypass Line Were Discovered to Be Locked Open 05000255/LER-2017-0022017-07-17017 July 2017 Reactor Protection System Actuation While the Reactor was Shutdown, LER 17-002-00 for Palisades Regarding Reactor Protection System Actuation While the Reactor was Shutdown 05000255/LER-2017-0012017-05-24024 May 2017 Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design Conditions, LER 17-001-00 for Palisades Nuclear Plant Regarding Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design Conditions PNP 2014-100, Cancellation of Licensee Event Report (LER) 2004-002, Leak Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations2014-11-19019 November 2014 Cancellation of Licensee Event Report (LER) 2004-002, Leak Indications Identified in Reactor Pressure Vessel Head Nozzle Penetrations PNP 2011-009, Special Report of Inoperability of Main Steam Line Gross Gamma Activity Monitor2011-02-10010 February 2011 Special Report of Inoperability of Main Steam Line Gross Gamma Activity Monitor ML0726101822007-09-14014 September 2007 Cancellation of Licensee Event Report 07-003, Potential for Reduced Component Cooling Water Cooling Capability ML0609002832006-03-30030 March 2006 Cancellation of Licensee Event Report 05-006, Inoperable Containment Due to Containment Air Cooler Through-Wall Flaws ML18347B2971998-05-19019 May 1998 Submit, NPDES Notification Report, Incident No. Pal-98-05-NC138 for NPDES Permit No MI0001457 Re Difference from Daily Maximum Effluent Limitation for Facility ML18348A9021989-02-0707 February 1989 LER 1988-005-01 for Palisades, Inadequate Procedure Results in Valve Testing During Prohibited Conditions ML18346A2471981-06-19019 June 1981 LER 1981-020-00 for Palisades Nuclear Plant, Pcs Unidentified Leakage Greater than 1.0 Gpm ML18346A2481981-05-13013 May 1981 LER 1981-015-00 for Palisades Nuclear Plant, Safety Injection Tank Boron Concentration ML18346A2491981-02-20020 February 1981 LER 1981-005-00 for Palisades Nuclear Plant, Update - Inoperable Diesel Generator ML18346A2501981-02-19019 February 1981 LER 1981-007-00 for Palisades Nuclear Plant, Inoperable Auxiliary Feedwater Pump ML18346A2511981-01-26026 January 1981 LER 1981-002-00 for Palisades Nuclear Plant, Inadequate Mounting of DC Distribution Panel ML18346A2521981-01-16016 January 1981 LER 1981-001-00 for Palisades Nuclear Plant, During Charging of Station Batteries, Output Breakers of Both Batteries Were Inadvertently Opened for Approximately One Hour ML18346A2531981-01-14014 January 1981 LER 1980-046-00 for Palisades Nuclear Plant, Hydraulic Snubber Failure ML18346A2541981-01-0707 January 1981 LER 1980-045-00 for Palisades Nuclear Plant, Low Condensate Makeup Inventory ML18347A8141980-10-10010 October 1980 LER 1980-037-00 for Palisades Nuclear Plant, Pipe Support Sway Struts Identified to Have the Potential of the Bushing Becoming Loose And/Or Disengaged from the Clamp End of the Sway Strut ML18347A8461980-08-27027 August 1980 License Event Report 1980-027-00 Re Gaseous Release, Extended Due Date of Reporting by Region III on 8/26/1980 ML18347A8471980-08-12012 August 1980 License Event Report 1980-024-00 Re Containment High Radiation Monitor ML18347A8481980-08-0808 August 1980 License Event Report 1980-023-00 Re Containment High Radiation Monitor ML18347A8491980-08-0808 August 1980 License Event Report 1980-022-00 Re Inoperable Nuclear Instrumentation ML18347A8501980-08-0606 August 1980 License Event Report 1980-021-00 Re Misaligned Containment Sump Valve ML18347A8521980-07-29029 July 1980 License Event Report 1980-020-00 Re Misaligned Control Rod ML18347B2071980-06-19019 June 1980 Licensee Event Report 80-018 Regarding Oil Level in Snubber No. 2 Found to Be Less than Zero During Routine Testing of Hydraulic Snubbers ML18347B2081980-06-13013 June 1980 Licensee Event Reports 80-014, 80-015, and 80-016 Regarding Oil Level in Snubbers No. 5, 9, and 7 Were Found to Be Less than Zero During Routine Testing of Hydraulic Snubbers ML18347B2091980-05-15015 May 1980 Licensee Event Report 80-012 Regarding Bottom Half of the Barrier for Fire Penetration HO-12 Was Missing During Inspection of Fire Barriers ML18347B2101980-05-14014 May 1980 License Event Report 1980-011-00 Re Improper Return-to-Service of Porv'S ML18348A9071980-05-12012 May 1980 Submittal of LER 1980-006-00 Purge Valve T-Ring Air Supplies ML18348A9051980-05-12012 May 1980 Submittal of LER 1980-008-00 Update of Valve Leakage ML18347B1411978-09-0606 September 1978 LER 1978-029-00 for Palisades Plant Re Lower Level of Hydrazine in Iodine Removal Tank Due to Approximately 6% of Drainage from the Tank T-102 ML18347B1421978-08-18018 August 1978 LER 1978-028-00 for Palisades Plant Re Containment Building Purge Valve T-Ring in CV-1806 Was Not Pressurized ML18347B1441978-08-11011 August 1978 LER 1978-022-00 for Palisades Plant Re Four Incore Alarms Following Reactor Start-up ML18347B1451978-08-10010 August 1978 LER 1978-021-00 for Palisades Nuclear Plant, Containment Purge Supply Valve CV-1808 Failed to Open During Monthly Test ML18347B1491978-07-20020 July 1978 LER 1978-024-00 & LER 1978-025-00 for Palisades Nuclear Plant, Steam Generator Ph Dropped to 8.02 & One of Two Heaters for T-53B (Concentrated Boric Acid Tank) Failed ML18347B1781978-04-28028 April 1978 License Event Report LER-78-000-00 Re Out-of-Sequence Rod Withdrawal ML18347B1801978-04-19019 April 1978 License Event Report 78-008: Cycle 2 Core Axial Power Distribution Limits of TS 3.10.3 Were Exceeded by Approximately 12% for Steady State Operation During Cycle 2 ML18347B1811978-03-27027 March 1978 License Event Report 1978-007-00 Relates to Electrical Connectors Inside of Containment ML18347B1841978-03-13013 March 1978 Two Updated License Event Reports, LER-78-004 & LER-78-006 ML18348A1951978-03-0202 March 1978 License Event Report 1978-006-00 Re Shipping Cask Movement ML18347B1851978-03-0202 March 1978 License Event Report 1978-005-00 Re Steam Generator Level Instrumentation ML18348A1961978-03-0101 March 1978 License Event Report 1978-004-00 Re Steam Generator Pressure Instrumentation ML18348A1981978-02-0101 February 1978 License Event Report 1978-003-00 Re CV-3025 Failed Closed ML18348A1971978-02-0101 February 1978 License Event Report 1977-065-00 Re Operation in a Degraded Mode Permitted by a Limiting Condition for Operation ML18348A1991978-01-20020 January 1978 LER 1977-063-00 Re Iodine Removal System Hydrazene Tank, LER 1978-001-00 Re Containment Door Interlock Failure & LER 1978-002-00 Re Setpoints of Five Valves Were Outside Band ML18348A2001978-01-0606 January 1978 License Event Report 1977-062-00 Re Iodine Removal System Naoh Tank (T-103) ML18348A2011978-01-0606 January 1978 License Event Report 1977-064-00 Re HPSI Pump P-66B ML18348A2021977-12-21021 December 1977 LER 1977-054-00 Re Four Coincident In-Core Alarms, LER 1977-057-00 Re Pressure Set Point for Channel C, & LER 1977-058-00 Re De-Energized R Bus ML18348A2031977-12-16016 December 1977 License Event Report 1977-055-00 Re Loss of Off-Site Power and Plant Trip ML18348A2041977-12-12012 December 1977 License Event Report 1977-056-00 Re Gaseous Waste Discharge 2018-12-10
[Table view] |
Text
'\ ... --,_ ~
consumers
- Power company General Offices: 21?. West Michigan Avenue, Jackson, Michigan 49201
- Area Code 517 788-0550 July 20, 1978
..... --:-- :~-::
c)
~ ..... l - .
(""~. c::
L~~.~~;
rq ....
(/'; f_J)
~:.: *.~:-.ls
=::-._-::;
-:c: --j Mr James G Keppler ':_)
Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET~'). LICENSE DPR PALISAD~T - LICENSEE EVENT REPORTS78-024 and 78-025
~'-fl(_c_Ktu.gjtt ~
David P Hoffman (j Assistant Nuclear Licensing Administrator 0
CC: Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement
--\.
Palisades NRC FORM366 U; S. NUCLEAR REGULATORY COMMISSION (7*771 LICENSEE EVENT REPORT CONTROL BLOCK: I I _J 0 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI 1 6
~IM1 1 iPIA!Ll 1 14101°1°1°1°1°1°1°1°1°19°101 4 1 1 1 1 LICENSE 1 1 1 1 10157 CAT I 1© 7 8 9 LICENSEE CODE / ,5 LICENSE NUMBER ~5 26 TY~E 30 58 CON'T ITII1 :~~~~ ~©1° I 5 1° Io I 0 12 I 5 15 K!)P 16 f P- 17 I 8 l@I o I 712 Io 17 I 8 IG) 7 B 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (,ii\
[§.J2J I During normal plant operation, 'lfteam generator ph drop:ped to 8. 02. Event occurred approx 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after condensate polishers were placed in service.
Occurrence is a degraded mode permitted by the LCO of TS 3.18.3. Ph was returned to within s:pecs within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by chemical addition, rerouting
(())] ~'~:--:-:::::-::-::-~"."";'""~--;-::-;--:-:;::-::~':""""'";----::~"";"":;"'~~"'.:".:".:'~~~~---,~~~=="",.-;,.~
of after condensate drains, and regulating blowdown flow rate. Event had
[))))
£IID I no adverse effect on public health or safety.
(]I[]
7 8 9 BO SYSTEM CAUSE CAUSE COMP. VALVE
~DE su~oDE I ~::NE ycAoE .H EJ u@ c:: . _r_.1 r c:: I@ L.!J coDe .H suecooE suBcooE
((II] 1H 1B I@ ~@
7 8 9 11) 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION*
r.::\ LER/RO EVENTYEAR REPDRTNO,. CODE;., ~E
\!.!l~J~~~~ 17 I Bl I ~I29 ~
0 I I 10 121 41 1.....-1 Io I ! 1b *1 ACTION FUTURE C 21 22 EFFECT 23 SHUTDOWN 24 26 27
('.;'.;'\
28 ATTACHMENT NPR~
30 PRIME COMP.
31 32 COMPONENT TAKEN ACTION ON 2-ANT ME~oo HBu'tl ~ sue'MTTED FORtt~us. . SUPPLIER MANUFACTURER
~@~@ 1..::J@ L:'.J@) Io I I I I L..J@) LJ'241 l1!.J'25' IC 14 I 910 1'26i.
33 34 35 36 37 40 41 42 l.:::J 43 ~ 44 . 47.~
CAUSE DESCRIPTION AND CORREC"rlVE ACTIONS {27)
IJ))] I The condensate polisher cati'i(n resin had one percent of the available transfer sites in the hydrogen form. This resulted in removal of amines
[JJJ]
from the condensate with a resultant ph depression. The resin vendor c:mJ has been notified of the problem~ Resins to be used in the future will IJ))] '--~~~~~~~~--~~~~~~~~~~~~~~~~~~~~~~~___J
~ be fully ammoniated in order to avoid amine transfer out of the condensate.
~ '--~~~~~~~~~~~.;..._~~~~~~~~~~~~~~~~~~~_.;..___JI 7 B 9 80 FACILITY
- f.::'I STATUS % POSEF\- /AOTHER STATUS ~
OJI] L.!J@ Io I I) !@)I N I cd~TENT 7 8 12 13 44 80 Al-rlVITY .
r.-r::;"'lRELEASED OF R&l..EASE N/A ~MOUNT OF ACTIVllY@ N/A LOCATION OF RELEASE @
~ Lj@ l.:J@I *1 7 B 9 10 11 45 80 PERSONNEL EXPOSURES ~
O'UM~Ro ~r2'E DE~xloN 1
lIJ2] I I I l'81L:'..J@).._.~~ ~~~~~~~~~~~~~~~~~~~~___J 1 8 9 11 12 13 80 PERSONNEL INJURIES ~
c)IUM::R O DE~IPJIION~
[iJI]
7 8 9 I I ~ 11
!@ I J
. ~12;--~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
LOSS OF OR DAMAGE TO FACILITY '4J'I 80 TY'C DESCW1'J'tON ~
~ l.j@).___~~~~~~~~~~~~~~~~~~~~~~~~~__J 7 8 9 10 BO PUBLICITY (.;;\ NRC,USE ONLY r::-r;:i ISSUEDt,;:;\ DESCRIPTION~
~ Llil~~N~/A~~~~~~~~~~~~~~~~~~~~~ I I I I I I I I I I I I80I 7 8 9 10 68 69
.... *"' ... \,,*
Palisades NRC FORM:i66 U.S. NUCLEAR REGULATORY COMMISSION (7*771 LICENSEE EVENT REPORT
. CONTROL BLOCK: I 1
10 6
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
ITI2J 7 8 jM I I I p I 9 LICENSEE CODE Al LI 1 101 ° 14 ,5 I 0 1° I 0 1° I 0 1° LICENSE NUMBER I 0 p
CON'T CilIJ :~~~~;~10151010101215151C?)!OP1211111BIG)10111210111s10 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES@
[§JI) I During normal plan~ operation, one of the two heaters for T-53B (concen-(2JI] trated boric acid tank) failed. Repairs necessitated removing the tank 1
from service. This occurrence is a degraded.mode permitted by the LCO of
[Q))J T.S. 3.2.3. Event had no adverse.effect on public health or safety.
((TI]
I))))
[ill]
[))))
7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE. CODE SUBCODE COMPONENT CODE SUBCOOE SUBCOOE III!] !RI Bl@ L.!J@ L!J@) jH I E!A IT !E jR !@ ~@ ~@
7 B 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION*
~ LER/RO CEVENT Y~AR REPORT N!2. COOjl_ "'O'PE
~
\!.:)REPORT 171tjl I I 10121'1 ,.,......., 1op1 L:::_J I I LJ NUMBER 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN
- h;\* ATTACHMENT NPRD4 PRIME COMP. COMPONENT TA'CfN ACTzaN ON PZ"'NT MET~OD H9YRo :-Er SUB.N11TTEO FOir :iUB. SUP:ftlER MANUl'/'IC'l'URE~
~@L.::J@
33 34 L..:'.J@
35 LJ 36 I
37 0
I .1 I 40I E.J@
41 Ll@
42
~@)
43 I w I ulo I :1 I@
44 47 CAUSE DESCRIPTION ANO CORREC"rlVE ACTIONS@
[I((] I The electric heater for T-53B burned out. The heater was replaced and the tank was returned to service. This type of failure is considered to be normal; no further corrective action is contemplated.
OJI) 7 8 9 80 FACILITY !Jc)\ METHOD OF (.;'.:;\
STATUS % PO~ER JTHER STATUS ~ 01sizivERY N/A DISCOVERY DESCRIPTION ~
IJ]}]
7 8 9 l!J@ I10 01 tjl 51@1 12 13 NA 44 I l::.J@)'"""I 45 . 46
.....J 80 ACTIVITY CONTENT ~
RE~SEO OF RezEASE N £MOUNT OF ACTIVITY N/A LOCATION OF RELEASE @
ITfil 7 8
~@~@I 9 10 11
/ .
44 I
45 BO PERSONNEL EXPOSURES (.;d\
ITIII Ior11j'b l@i~PEI@) oes~moN 7 8 9 11 1 2 1~3~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~8~0 PERSONNEL INJURIES ~
ONU~Efj] DES~}"JtON6
[I]!]
7 B 9 I I I 11!@)~-----------------------~
12 LOSS OF OR DAMAGE TO FACILITY G 80 TYPE DESCRIPTION ~
~@)!-!--_N/~A------------------------------------------------------1
[!l2]
7 B 9 10 - BO PUBLICITY C\ NRC USE ONLY 1IIIJ IS~l,IEOc,;\
~~...__N_;A DESCRIPj!"ION ~
________________________________________, I I I IIII I I I II I 7 B 9 10 68 69 80