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MONTHYEARML24351A0262024-12-10010 December 2024 Duke Energy Fleet - Alternative Request for ASME Code Case N-572 RA-24-0276, EN 57402 - Catawba Nuclear Station Interim Part 21 Report2024-10-28028 October 2024 EN 57402 - Catawba Nuclear Station Interim Part 21 Report ML24197A1702024-07-15015 July 2024 Request for Additional Information Two Proposed Alternatives (RA-23-0242) for the Inspection of Reactor Vessel Closure Head Penetrations ML24192A3492024-07-10010 July 2024 Acceptance of Requested Licensing Action License Amendment Application to Revise Technical Specification 3.4.3, RCS Pressure and Temperature Limits ML24179A1292024-06-24024 June 2024 Acceptance Review for LAR to Revise TS to Adopt TSTF-234-A, Revision 1 ML24150A1662024-05-29029 May 2024 Document Request for Catawba Nuclear Station Units 1 & 2 - Radiation Protection Inspection - Inspection Report 2024-03 ML24066A0142024-03-0505 March 2024 Cat 2024-002 Radiation Safety Baseline Inspection Information Request ML24033A2372024-02-0202 February 2024 Acceptance of Requested Licensing Action Two Proposed Alternatives (RA-23-0242) for the Inspection of Reactor Vessel Closure Head Penetrations (Epids L-2024-LLR-0002 and L-2024-LLR-0003) ML23271A1792023-09-28028 September 2023 Request for Confirmation License Amendment Application to Revise Control Room Cooling TS 3.7.11 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23188A0732023-07-0707 July 2023 Acceptance of Requested Licensing Action License Amendment Application to Revise Control Room Cooling Technical Specifications ML23172A0132023-06-20020 June 2023 Duke Fleet - Correction to June 2, 2023, Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined ML23153A1892023-06-0202 June 2023 Duke Fleet - Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23124A1212023-05-0404 May 2023 Acceptance of Requested Licensing Action Duke Fleet Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23080A1892023-03-20020 March 2023 RP Inspection Document Request ML23073A2282023-03-13013 March 2023 Duke Fleet- Adoption of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements - Acceptance Review ML23058A0562023-02-27027 February 2023 Acceptance of Amendment to Revise Surveillance Frequencies for RCS Pressure Isolation Valve Operational Leakage Testing and Reactor Trip System Instrumentation ML23048A1512023-02-16016 February 2023 Acceptance Review - Proposed Alternative for Steam Generator Welds (L-2023-LLR-0003) ML22336A0692022-11-28028 November 2022 Final 2023 Catawba Nuclear Station (CNS) Commercial Grade Dedication (CGD) Inspection Information Request ML22303A0052022-10-24024 October 2022 EN 56178 - Tioga Final. LTR-TP-22-29 2021 10CFR Part 21 Improper Notification of NRC NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022 EN 55999 Valcor Coil Shell Assemblies Final Notification (004) ML22213A0472022-08-0101 August 2022 Document Request for Catawba Nuclear Station - Radiation Protection Inspection - Inspection Report 2022-03 NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22154A1312022-06-0303 June 2022 NRR E-mail Capture - Catawba Nuclear Station, Units 1 and 2 - Request for Additional Information Environmentally-Assisted Fatigue License Renewal Commitment ML22174A0802022-06-0101 June 2022 Transmittal External Distribution Notification TR-NUC-CN-014344 - SLC Manual Revision to Loes and SLC 16.7-5 ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22083A0702022-03-24024 March 2022 NRR E-mail Capture - Catawba Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, and McGuire Nuclear Station, Units 1 and 2 - Acceptance Review for TSTF-569 LAR ML22041A5312022-02-10010 February 2022 NRR E-mail Capture - Catawba Nuclear Station Unit 2 - Acceptance of Requested Licensing Action Use of Alternative Requirements of ASME Code for Embedded Flaw Repair Method on Reactor Vessel Closure Head Penetration 74 EPID L-2022-LLR-0010 ML22038A1572022-02-0707 February 2022 NRR E-mail Capture - Duke Energy Fleet - Acceptance of License Amendment Request Regarding Adoption of TSTF-541, Revision 2 ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22024A1112022-01-0707 January 2022 E-mail Capture- Catawba POV Inspection Information Request (1) ML21361A0122021-12-23023 December 2021 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Relocate Emergency Operations Facility ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21335A2252021-12-0101 December 2021 NRR E-mail Capture - Catawba Nuclear Station, Unit 2 - Request for Additional Information Spring 2021 Steam Generator Tube Inspection Report (L-2021-LRO-0043) ML21286A7812021-11-22022 November 2021 Acceptance of Requested Licensing Action Revision to the End of Cycle Moderator Temperature Coefficient Measurement Methodology ML21295A0372021-10-0505 October 2021 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Adopt TSTF-577 Revised Frequencies for Steam Generator Tube Inspections ML21189A2502021-07-0202 July 2021 NRR E-mail Capture - Acceptance Review: Duke Energy - Proposed Alternative to Use ASME Code Case N-885 for Catawba Nuclear Station Unit 2 - EPID: L-2021-LLR-0043 ML21117A1292021-04-26026 April 2021 NRR E-mail Capture - Catawba Verbal Relief Request RA-21-0145 ML21117A1222021-04-23023 April 2021 NRR E-mail Capture - (External_Sender) Catawba Nuclear Station Relief Request RA-21-0133 ML21117A1232021-04-23023 April 2021 NRR E-mail Capture - Catawba Verbal Relief Request Request for Additional Information ML21099A0742021-04-0909 April 2021 CAT_2021-02 Document Request for Upcoming RP Inspection ML21096A3002021-04-0606 April 2021 E-mail for Approval of Proprietary Withholding for Duke Energy Exemptions for the Magnastor Storage Cask ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML21007A3722021-01-0707 January 2021 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-19-0352 - Proposed Alternative for Reactor Vessel Close Stud Examinations (L-2020-LLR-0156) ML21006A4302021-01-0606 January 2021 Acceptance Review - Duke Fleet RA-20-0207 Request to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML20346A0212020-12-10010 December 2020 NRR E-mail Capture - Formal Release of RAIs - License Amendment to Change TS 3.8.1 Due Jan. 29, 2021 2024-07-15
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Loo, Wade From: Heather Gepford L.-f Sent: Thursday, May 15, 2008 8:04 AM To: Brian Bonser Cc: Wade Loo
Subject:
Catawba sump w/identified Sr-89 activity Attachments: P5144123.JPG; P5144122.JPG; P5144124.JPG; P5144120.JPG; P5144121 .JPG Catawba received their quarterly composite sample results for the groundwater drainage sumps yesterday.
Aux Bldg Groundwater Drainage Sump A, WZ-A, had a positive indication of Sr-89. Specifically, the sample contained 0.925 +/- 0.4 pCi/I of Sr-89. MDA was 0.6 pCi/l.
This activity is equal to 9.25E-10 uCi/ml. Release limit for Sr-89 in effluents is 8E-6 uCi/ml; release to sewer is 8E-5 uCi/ml.
The licensee's immediate corrective actions were to resample the sump (composite sample) yesterday afternoon and change the sampling frequency to monthly. Corporate is working with their groundwater monitoring consultant to determine what, if any, additional actions should be taken.
The aux bldg groundwater drainage sump is one of four sumps on site that will automatically discharge to the yard when a high level setpoint is reached. The discharge then drains to the yard drains which are routed to a holding pond. There is no indication at present of Sr-89 in the groundwater.
Pictures of the discharge piping, coming out of the sump, are attached.
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Enclosure 4.11 RP/O/B/5000/013 Event Notitication Report Page 1 of 2 STATE:"-"IISIS Till CATAWBA NUCI..EAR SrlE IN NRC RECGION 2 MAKING AN EVENTNOTrIFICATION REPORT' EN #
N.iTICATION UNIT CALLER'S NAMIE CALlBACK TELEPHONF #: NRCPI'ERtATIONS Ot-FFICF.ER, UTIMFI.ATE ENS 1 803L*392(l (CIR) CONTACTED or I 8"1 .-2 174 (TSC-NRC OPERATION TELEPHONE NUMIBER: PRIMARY 301-816-510M) or 1-800-532-3469; BACKUPS - listl 1-301-95110550 or 1-800-4,19-3694:
[2id.l 1-301 -415,0550; and f3rdl 1-301-415-1553 EVENT TIME &ZONE I-EV:,NT I1OWER/MODIi IWEFORE POWEIUMOC)lEA'TER
. II.I OATE (time) (zone) I 8-41R NON-EMERGENCY 10CFR72.75(c)
IMMEDIATE 4-11R NON-EMERGENCY 10CFI172.75(hl)ISFSt ISFSI EVENT CLASSIHICATION (GE, SAF- ALRIR, (I) TS Deviation for ISFSI (Ii ID)efect in ISFSI SSC NOUE) 50.72 *r 7275 SSI) ...(2) Offsite Nification for ISFSIt (2)ý ISFSI Confinement System I'tlYSIC:At, PRO'ItCTI*ION Of l'laNT OR (3) Offsite medical (ISFSI)
MATERIALS 8-ITR NON-EMERGENCY 10 CFR 50.72(b)(2)
TRANSPORTATION 1 0 CFR 20) (liXA) Degraded Condition 24-11OUR NON-EMERGENCY ISFSI MATERIAIJtEXP(OUSI.R (M!ICI-1( 20) (ii)tB) Unanalyzed Condition Radiolugical Exposure I tWFR20.2202 (iv)(A) Valid System Actuation Fitness For Duty IOCFl26.73:
I-FtR NON-EMERGl*ENCY IIICFR50.72(h)(1) (v)(A) Safe S/D Capability Operating, License Deviation TS l)eviatiorr.pursumnt to IOCFR5(I.54(x) (v)(B) tIIR Capability Accidental Criticality or Lossf1lielt of Material (v)(C) Control of Radiological 24-11OUR NON-EMERGENCY ISFSI (v)(D) Accident Mitigation ISFSI Lost Safety Function 72.75(d)(I) 4-tlR NON-EMERGENCY 10CFR50.72(I)(2) (xii) Offsitc Medical (i) TSlRequired S/D (kiii) Lost ENS 30 DAY NON EMERGENCY (iv(A) ECCS
- Discharge to RCS (xiii) List Emergency AssessmCnt 10C1R2O:2201 (iv)(B) RPS Actuation whet Rx is critical (xiii) Lost OfTsite Communications Theft, Lost or Missing Material (xi) Offsitc Notification (xiii) Emergency Siren Inoperable 60-DAY ovriONAI. 10CUR 50.730)( I)
Inrvalid Specifikd Sysetem Actuation oTrWR UNSIPECIFIED REQUI REM ENT FIDENTIFY)
Retraction EVEN'T DEISCRIPTION (Include: Systems affected. actuations & their initiating signals, causes, effect of event on plant.actions taken or planned. PARs etc.)
CATE'GORY INITIATION SIGNAL Thirty new ground water monitoring wells were recently installed at Cattawba Nuclear REACTOR'!]II_ Station iii support of the Nuclear Energy Institute (NEI) ground water initiative. The ESF ACTUJATION initial sairplingof one ofthese wells'displayed a level of Itritiurn that triggered the conltllunication protocol of the NEI initiative on ground water protection. The tritium
____ ECCS ACTIJATI"ON _____concentration for this well was 42,335 picocuries per liter (pCiI). Th) threshold tor St FLOW initiating the communication protocol is 20,000 pCi/I. This Wecll is inside the owner
.LCO controlled area. Adjacent wells sirrotinding this well do not hIave similar tritium levels.
"the slation is continuing to investigate the source of the tritium identifted in this well.
SYSTI'EM Samples from Ihe.remaining wells are far below the communication protocol threshold.
COMPONENT __ There is no public health risk associated with this well sample. llTcre is no indication that tritium has migrated off the Catawba site in the ground water at the communication threshold. Also this well is not a drinking water source arrd therefore, there is
...... PRSONNEt. ERROR -ER OTH__ no potential (lose to plant workers or the public..
Continue ont Enelosure 4.11 page 2 of 2 if neetms~iry.
NOTIFICATIONS YES NO WILLt BlE ANYTIIING UNUSUAL OR NOT UNIDERSTOOD? 0E YEl:S 0 NO NRC RESII)ENT (Explain above)
STATE(s) NC )I)ID All, SYSTEMS FUNCI1ON 0 YES 01 NO SC AS REQUIRtDJ (Explain ablxe)
LO.CAl. York County MOI)E OF OPERATI(oN UNTIL E'STIMATED Gastonl (*tltty CORII 17CTI): IRESTART I)AI.
Nleklenkunr1, C01ntty O0111ERI GOV A(GFENCtES MIUI)lVI'IAESS SREL:ASE _.__......