ML14064A342: Difference between revisions
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{{#Wiki_filter:Exeton Generation, Three Mile Island Unit | {{#Wiki_filter:Exeton Generation, Three Mile Island Unit 1 Route 441 South, P.O. Box 480 Middletown, PA 17057 Telephone 717-948-8000 February 28, 2014 TM1-14-028 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289 | ||
==SUBJECT:== | ==SUBJECT:== | ||
2013 ANNUAL | 2013 ANNUAL REPORT Attached is the 2013 Annual Report for TMI-1. This report is being submitted in accordance with TMI-1 Technical Specifications Sections 6.9.1.B.2 through 6.9.1.B.5 and 6.17. The attachments to this letter contain the following information: | ||
Attachment 1 -Attachment 2 -Attachment 3 -Attachment 4 -Attachment 5 -Aircraft movement data from the Harrisburg International Airport(per TMI-1 T.S. section 6.9.1..B.2). | Attachment 1 -Attachment 2 -Attachment 3 -Attachment 4 -Attachment 5 -Aircraft movement data from the Harrisburg International Airport (per TMI-1 T.S. section 6.9.1..B.2). | ||
Leak reduction program test information (per TMI-1 T.S.6.9.1 .B.3).Pressurizer power operated relief valve and pressurizer | Leak reduction program test information (per TMI-1 T.S.6.9.1 .B.3).Pressurizer power operated relief valve and pressurizer safety valve challenges (per TMI-1 T.S. section 6.9.1 .B.4).Results of specific activity analysis -primary coolant system (per TMI-1 T.S. section 6.9.1..B.5). | ||
-primary coolant system ( | Major changes to radioactive waste treatment systems (per TMI-1 T.S. section 6.17)Sincerely, M \ mer" Mark ewcre Plant Manager, Three Mile Island Unit 1 MN/mdf Attachments cc: TMI, Unit 1 Senior Resident Inspector Administrator, Region I TMI, Unit 1 Project Manager kL-Ld-C TM1-14-028 Attachment 1 ATTACHMENT 1 AIRCRAFT MOVEMENTS AT THE HARRISBURG INTERNATIONAL AIRPORT (HIA)JANUARY 1,2013 THROUGH DECEMBER 31, 2013 1. Total Aircraft Movements | ||
Major changes to radioactive waste treatment systems (per TMI- | -53,951 2. Estimated total number of movements of aircraft larger than 200,000 pounds -2510.This estimate is composed of two parts, 2260 movements of civilian aircraft, and 250 movements of U.S. Government and military aircraft. | ||
-53, | ATTACHMENT 2 TMI-14-028 TECHNICAL SPECIFICATION 6.9.1 .B.3 PERIODIC LEAK REDUCTION PROGRAM TEST RESULTS The results of the TMI-1 2013 periodic Leak Reduction Program Tests, which included visual inspections, are summarized in Table 1.These tests were performed in accordance with the surveillance procedures listed.TABLE 1 2013 LEAK REDUCTION PROGRAM TEST RESULTS, FOR TMI-1 DATE OF LEAKING RESULTING SURVEILLANCE PERFORMA COMPONENT MEASURED LEAK RATE MAINTENANCE PROCEDURES PROCEDURE TITLE / DESCRIPTION NCE I.D. AS-FOUND AS-LEFT UNDERTAKEN 1303-11.29 Waste Gas Disposal System Leak 04/04/2013 None 0 'Not Check required 1303-11.30 Reactor Coolant Sampling Leak Check 09/01/2013 None 0 Not required OP-TM-211-251 Leak Exam of MU system inside RB 11/24/2013 None 0 Not required OP-TM-211-261 MU Pump Suction Leak Check 11/21/2013 None 0 Not required OP-TM-211-262 HPI Lines 11/24/2013 None 0 Not required OP-TM-212-215 DH Train A/B VT-2 Exam 11/23/2013 None 0 Not required OP-TM-212-217 DH-V-6A to RB Sump Leak Check 11/13/2013 None 0 Not required OP-TM-212-218 DH-V-6B to RB Sump Leak Check 11/14/2013 None 0 Not required OP-TM-212-251 DH/LPI Train A leakage exam 02/08/2013 None 0 Not DH suction piping & BWST leak exam 04/17/2013 None 0 required OP-TM-214-253 BS Leakage Exam Train A 08/08/2013 None 0 Not I required _OP-TM-214-254 BS Leakage Exam Train B 07/20/2013 None 0 Not I required The following are Local Leak Rate Tests with units of standard cubic centimeters per minute (sccm)1303-11.17A Local Leak Rate Testing -Reactor 05/23/2013 Personnel 738 Not Building Personnel Hatch Airlock Hatch Airlock required MA-TM-244-204A Penetration 328 LLRT of CA-V-2, CA- 11/08/2013 CA-V-2 20 20 V-1 3, and CA-V-446 CA-V-1 3/446 20 20 MA-TM-244-204C Penetration 210 LLRT of CA-V-4B, CA- Not CA-V-449B relief valve I V-5B, and CA-V-449B 11/15/2013 CA-V-449B required 20 replacement MA-TM-244-206A Penetration 108 LLRT of CM-V-1 and 11/11/2013 CM-V-1 167 106 CM-V-1 AOV actuator PM ATTACHMENT 2 TMI-14-028 TECHNICAL SPECIFICATION 6.9.1.B.3 PERIODIC LEAK REDUCTION PROGRAM TEST RESULTS DATE OF LEAKING RESULTING SURVEILLANCE PERFORMA COMPONENT MEASURED LEAK RATE MAINTENANCE PROCEDURES PROCEDURE TITLE / DESCRIPTION NCE I.D. AS-FOUND AS-LEFT UNDERTAKEN CM-V-2 CM-V-2 20 20 MA-TM-244-206B Penetration 108 LLRT of CM-V-3 and 11/11/2013 CM-V-3 270 270 CM-V-4 CM-V-4 257 64 CM-V-4 AOV actuator PM MA-TM-244-207 Penetration 320 LLRT of DH-V-64 and 11/10/2013 DH-V-64 30 30 DH-V-69 DH-V-69 20 20 MA-TM-244-208 Penetration 216 LLRT of FS-V-401 and 11/23/2013 FS-V-401 & Not 2100 Blank Flange Blind Flange required MA-TM-244-209 Penetration 212 & 232 LLRT of East 11/20/2013 East Flange 20 20 and West Fuel Transfer Tubes (FTT) Canopy Seal 20 20 West Flange 20 20 Canopy Seal 20 20 MA-TM-244-210A Penetration 420S/101S LLRT of HM-V- 11/07/2013 HM-V-1A 20 20 1A & 1B and HM-V-2A & 2B HM-V-1B 20 20 HM-V-2A 20 20 HM-V-2B 20 20 MA-TM-244-210B Penetration 420S/1 01S LLRT of HM-V- 11/05/2013 HM-V-3A 20 20 3A & 3B and HM-V-4A & 4B HM-V-3B 20 20 HM-V-4A 20 20 HM-V-4B 20 20 MA-TM-244-211 Penetration 240 LLRT of HP-V-1 and 11/17/2013 HP-V-1 148 148 HP-V-6 HP-V-6 82 82 MA-TM-244-212 Penetration 109 LLRT of IA-V-6 and IA- 11/20/2013 IA-V-6/20 40 40 V-20 (combined test)MA-TM-244-213A Penetration 302 LLRT of IC-V-2, IC-V- 11/04/2013 IC-V-2 20 20 IC-V-1 02 relief valve 3, and IC-V-102 IC-V-3/102 172 269 replacement MA-TM-244-213B Penetration 333 LLRT of IC-V-4 and 11/17/2013 IC-V-4 304 97 IC-V-4 AOV actuator PM IC-V- 18 IC-V-18 51 51 MA-TM-244-213C Penetration 334 LLRT of IC-V-6 and 11/12/2013 IC-V-6 210 210 IC-V-6 AOV actuator PM IC-V- 16 IC-V-16 46 46 MA-TM-244-214A Penetration 415 LLRT of HR-V-2A/B, 11/22/2013 HR-V-2A/B 85 85 HR-V-22A/B, and Flanges HR-V-22A/B 105 105 MA-TM-244-214B Penetration 416 LLRT of HR-V-4A/B, 11/11/2013 HR-V-23A 20 20 HR-V-23A/B, and Flanges HR-V-23B 20 20 HR-V-4A/B 40 40 MA-TM-244-215A Penetration 309 LLRT of MU-V-2A, 11/16/2013 MU-V-2B 30 20 MU-V-2B MOV actuator PM MU-V-2B, MU-V-3, and MU-V-238 MA-TM-244-215D Penetration 337 LLRT of MU-V-20 and 11/08/2013 MU-V-20 192 192 MU-V-1 16 check valve MU-V-1 16 MU-V-1 16 20 20 --inspection ATTACHMENT 2 TM I-14-028 TECHNICAL SPECIFICATION 6.9.1 .B.3 PERIODIC LEAK REDUCTION PROGRAM TEST RESULTS DATE OF LEAKING RESULTING SURVEILLANCE PERFORMA COMPONENT MEASURED LEAK RATE MAINTENANCE PROCEDURES PROCEDURE TITLE / DESCRIPTION NCE I.D. AS-FOUND AS-LEFT UNDERTAKEN MA-TM-244-216 Penetration 307 LLRT of NI-V-26 and 11/07/2013 NI-V-26 20 20 NI-V-27 NI-V-27 20 20 MA-TM-244-217B Penetration 347 LLRT of NS-V-4, NS- Not NS-V-211 relief valve V-35, and NS-V-211 11/02/2013 NS-V-211 required 20 replacement MA-TM-244-218A LLRT of Flanged Penetrations 104, 11/22/2013 P-104 20 105,106 11/22/2013 P-105 Not 20 11/07/2013 P-106 required 20 MA-TM-244-218B LLRT of Flanged Penetrations 221, 11/08/2013 P-221 20 222, 240/241, and 414 11/22/2013 P-222 Not 20 11/20/2013 P-240/241 required 90 11/22/2013 P-414 20 MA-TM-244-221 Penetration 201 E LLRT 10/31/2013 P-201E 85 85 MA-TM-244-222 Penetration 421 & 422 LLRT of RB-V- 11/13/2013 RB-V-2A 20 20 2A and RB-V-7 RB-V-7 20 20 MA-TM-244-223 Penetration 304 LLRT of SF-V-22 and 11/12/2013 SF-V-22 20 20 SF-V-23 SF-V-23 20 20 MA-TM-244-224 Penetration 104 LLRT of SA-V-2 and 11/21/2013 SA-V-2/3 20 20 SA-V-3 (combined test)MA-TM-244-225 Penetration 330 LLRT of WDG-V-3 and 11/09/2013 WDG-V-3 200 200 WDG-V-4 WDG-V-4 20 20 MA-TM-244-226A Penetration 331 LLRT of WDL-V-303, 11/13/2013 WDL-V-303 20 20 WDL-V-304 AOV actuator WDL-V-304, and WDL-V-727 WDL-V-304/727 130 20 PM MA-TM-244-226B Penetration 353 LLRT of WDL-V-534 11/05/2013 WDL-V-534/535 20 20 and WDL-V-535 (combined test)MA-TM-244-227 Penetration 418 LLRT of Equipment 10/28/2013 Flange O-rings 79 Removed & later re-installed Hatch Flange O-rings 11/21/2013 Flange O-rings 20 Equipment hatch OP-TM-823-251 LLRT of Purge Exhaust Penetration 11/23/2013 AH-V-1 A/B Not 2643 Removed, then later reset Valves (combined test) required 300 stops OP-TM-823-252 LLRT of Purge Supply Penetration 11/23/2013 AH-V-1C/D Not 1593 Removed, then later reset Valves (combined test) required 300 stops; and AH-V-1 C motor replacement Notes: 1. Local Leak Rate Testing is performed under the Option B provisions of 10CFR50 Appendix J, and the minimum LLRT leakage value used is 20 sccm based on the low end of the calibration range of the flow instrumentation. | ||
ATTACHMENT 2 TMI-14-028 TECHNICAL SPECIFICATION 6.9.1 .B. | |||
_OP-TM-214-254 BS Leakage Exam Train B 07/20/2013 None 0 | |||
& Not | |||
: 2. 'As-Left' testing is not required if the 'As-found' leakage was acceptable and no maintenance was performed. | : 2. 'As-Left' testing is not required if the 'As-found' leakage was acceptable and no maintenance was performed. | ||
: 3. 'As-Found' testing is not required for LLRT components not on extended test intervals nor for containment penetration flanges that | : 3. 'As-Found' testing is not required for LLRT components not on extended test intervals nor for containment penetration flanges that are simply reinstalled at the end of an outage. | ||
TM1-14-028 Attachment | TM1-14-028 Attachment 3 ATTACHMENT 3 PRESSURIZER POWER OPERATED RELIEF VALVE AND PRESSURIZER SAFETY VALVE CHALLENGES IN 2013 There were no challenges to the pressurizer power operated relief valve (PORV) o[ either of the two pressurizer (PZR) safety valves during the entire calendar year of 2013.A review of the Reactor Coolant System (RCS) pressure indication trend data concluded that the RCS pressure operated well below the PORV set point of 2450 psig, and both PZR safety valve set points of 2500 psig throughout the calendar year of 2013. Therefore no challenges to the PORV or PZR safety valves occurred during 2013. | ||
TM1-14-028 Attachment | TM1-14-028 Attachment 4 ATTACHMENT 4 RESULTS OF SPECIFIC ACTIVITY ANALYSIS-PRIMARY COOLANT SYSTEM Technical Specification 6.9.1 .B.5 requires annual reporting of certain information regarding the results of specific activity analyses in which the primary coolant exceeded the limits of Technical Specification (TS) 3.1.4.1. The limits ol TS 3.1.4.1 were not exceeded at TMI-1 at any time during the year 2013. The figure of RCS activity for 2013 shows that the limit of 0.35 microcurie/gram dose equivalent 1-131 (DEI) was not exceeded in 2013.TMI-1 Dose Equivalent Iodine (DEI) in 2013 1.OOE+00 1.00E-01 1.OOE-02'd)0E-03 a 1 .00E-04 Il______kj.4d | ||
The limits ol TS 3.1.4.1 were not exceeded at TMI-1 at any | .%4 1.00E-05 ......2-Jan 3-Feb 7-Mar 8-Apr 1 0-May 11-Jun 13-Jul 14-Aug1 5-Sepl 7-Oct 8-NoN20-Dec Date TMI-14-028 Attachment 5 ATTACHMENT 5 MAJOR CHANGES TO RAD WASTE TREATMENT SYSTEMS Technical Specification Section 6.17 requires reporting of Major changes to Radioactive Waste Treatment Systems. Major changes are interpreted to mean changes that would alter how the system functions or changes that would affect operational exposures, offsite dose rates or integrated doses. There were no major changes to the liquid, gaseous, or solid radioactive waste treatment systems at TMI-1 during the year of 2013.}} | ||
.% | |||
......2-Jan 3-Feb 7-Mar 8-Apr 1 0-May 11-Jun 13-Jul 14-Aug1 5-Sepl 7-Oct 8-NoN20-Dec Date TMI-14-028 Attachment | |||
Major changes are interpreted |
Revision as of 21:44, 9 July 2018
ML14064A342 | |
Person / Time | |
---|---|
Site: | Three Mile Island |
Issue date: | 02/28/2014 |
From: | Newcomer M Exelon Generation Co |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
TM1-14-028 | |
Download: ML14064A342 (8) | |
Text
Exeton Generation, Three Mile Island Unit 1 Route 441 South, P.O. Box 480 Middletown, PA 17057 Telephone 717-948-8000 February 28, 2014 TM1-14-028 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289
SUBJECT:
2013 ANNUAL REPORT Attached is the 2013 Annual Report for TMI-1. This report is being submitted in accordance with TMI-1 Technical Specifications Sections 6.9.1.B.2 through 6.9.1.B.5 and 6.17. The attachments to this letter contain the following information:
Attachment 1 -Attachment 2 -Attachment 3 -Attachment 4 -Attachment 5 -Aircraft movement data from the Harrisburg International Airport (per TMI-1 T.S. section 6.9.1..B.2).
Leak reduction program test information (per TMI-1 T.S.6.9.1 .B.3).Pressurizer power operated relief valve and pressurizer safety valve challenges (per TMI-1 T.S. section 6.9.1 .B.4).Results of specific activity analysis -primary coolant system (per TMI-1 T.S. section 6.9.1..B.5).
Major changes to radioactive waste treatment systems (per TMI-1 T.S. section 6.17)Sincerely, M \ mer" Mark ewcre Plant Manager, Three Mile Island Unit 1 MN/mdf Attachments cc: TMI, Unit 1 Senior Resident Inspector Administrator, Region I TMI, Unit 1 Project Manager kL-Ld-C TM1-14-028 Attachment 1 ATTACHMENT 1 AIRCRAFT MOVEMENTS AT THE HARRISBURG INTERNATIONAL AIRPORT (HIA)JANUARY 1,2013 THROUGH DECEMBER 31, 2013 1. Total Aircraft Movements
-53,951 2. Estimated total number of movements of aircraft larger than 200,000 pounds -2510.This estimate is composed of two parts, 2260 movements of civilian aircraft, and 250 movements of U.S. Government and military aircraft.
ATTACHMENT 2 TMI-14-028 TECHNICAL SPECIFICATION 6.9.1 .B.3 PERIODIC LEAK REDUCTION PROGRAM TEST RESULTS The results of the TMI-1 2013 periodic Leak Reduction Program Tests, which included visual inspections, are summarized in Table 1.These tests were performed in accordance with the surveillance procedures listed.TABLE 1 2013 LEAK REDUCTION PROGRAM TEST RESULTS, FOR TMI-1 DATE OF LEAKING RESULTING SURVEILLANCE PERFORMA COMPONENT MEASURED LEAK RATE MAINTENANCE PROCEDURES PROCEDURE TITLE / DESCRIPTION NCE I.D. AS-FOUND AS-LEFT UNDERTAKEN 1303-11.29 Waste Gas Disposal System Leak 04/04/2013 None 0 'Not Check required 1303-11.30 Reactor Coolant Sampling Leak Check 09/01/2013 None 0 Not required OP-TM-211-251 Leak Exam of MU system inside RB 11/24/2013 None 0 Not required OP-TM-211-261 MU Pump Suction Leak Check 11/21/2013 None 0 Not required OP-TM-211-262 HPI Lines 11/24/2013 None 0 Not required OP-TM-212-215 DH Train A/B VT-2 Exam 11/23/2013 None 0 Not required OP-TM-212-217 DH-V-6A to RB Sump Leak Check 11/13/2013 None 0 Not required OP-TM-212-218 DH-V-6B to RB Sump Leak Check 11/14/2013 None 0 Not required OP-TM-212-251 DH/LPI Train A leakage exam 02/08/2013 None 0 Not DH suction piping & BWST leak exam 04/17/2013 None 0 required OP-TM-214-253 BS Leakage Exam Train A 08/08/2013 None 0 Not I required _OP-TM-214-254 BS Leakage Exam Train B 07/20/2013 None 0 Not I required The following are Local Leak Rate Tests with units of standard cubic centimeters per minute (sccm)1303-11.17A Local Leak Rate Testing -Reactor 05/23/2013 Personnel 738 Not Building Personnel Hatch Airlock Hatch Airlock required MA-TM-244-204A Penetration 328 LLRT of CA-V-2, CA- 11/08/2013 CA-V-2 20 20 V-1 3, and CA-V-446 CA-V-1 3/446 20 20 MA-TM-244-204C Penetration 210 LLRT of CA-V-4B, CA- Not CA-V-449B relief valve I V-5B, and CA-V-449B 11/15/2013 CA-V-449B required 20 replacement MA-TM-244-206A Penetration 108 LLRT of CM-V-1 and 11/11/2013 CM-V-1 167 106 CM-V-1 AOV actuator PM ATTACHMENT 2 TMI-14-028 TECHNICAL SPECIFICATION 6.9.1.B.3 PERIODIC LEAK REDUCTION PROGRAM TEST RESULTS DATE OF LEAKING RESULTING SURVEILLANCE PERFORMA COMPONENT MEASURED LEAK RATE MAINTENANCE PROCEDURES PROCEDURE TITLE / DESCRIPTION NCE I.D. AS-FOUND AS-LEFT UNDERTAKEN CM-V-2 CM-V-2 20 20 MA-TM-244-206B Penetration 108 LLRT of CM-V-3 and 11/11/2013 CM-V-3 270 270 CM-V-4 CM-V-4 257 64 CM-V-4 AOV actuator PM MA-TM-244-207 Penetration 320 LLRT of DH-V-64 and 11/10/2013 DH-V-64 30 30 DH-V-69 DH-V-69 20 20 MA-TM-244-208 Penetration 216 LLRT of FS-V-401 and 11/23/2013 FS-V-401 & Not 2100 Blank Flange Blind Flange required MA-TM-244-209 Penetration 212 & 232 LLRT of East 11/20/2013 East Flange 20 20 and West Fuel Transfer Tubes (FTT) Canopy Seal 20 20 West Flange 20 20 Canopy Seal 20 20 MA-TM-244-210A Penetration 420S/101S LLRT of HM-V- 11/07/2013 HM-V-1A 20 20 1A & 1B and HM-V-2A & 2B HM-V-1B 20 20 HM-V-2A 20 20 HM-V-2B 20 20 MA-TM-244-210B Penetration 420S/1 01S LLRT of HM-V- 11/05/2013 HM-V-3A 20 20 3A & 3B and HM-V-4A & 4B HM-V-3B 20 20 HM-V-4A 20 20 HM-V-4B 20 20 MA-TM-244-211 Penetration 240 LLRT of HP-V-1 and 11/17/2013 HP-V-1 148 148 HP-V-6 HP-V-6 82 82 MA-TM-244-212 Penetration 109 LLRT of IA-V-6 and IA- 11/20/2013 IA-V-6/20 40 40 V-20 (combined test)MA-TM-244-213A Penetration 302 LLRT of IC-V-2, IC-V- 11/04/2013 IC-V-2 20 20 IC-V-1 02 relief valve 3, and IC-V-102 IC-V-3/102 172 269 replacement MA-TM-244-213B Penetration 333 LLRT of IC-V-4 and 11/17/2013 IC-V-4 304 97 IC-V-4 AOV actuator PM IC-V- 18 IC-V-18 51 51 MA-TM-244-213C Penetration 334 LLRT of IC-V-6 and 11/12/2013 IC-V-6 210 210 IC-V-6 AOV actuator PM IC-V- 16 IC-V-16 46 46 MA-TM-244-214A Penetration 415 LLRT of HR-V-2A/B, 11/22/2013 HR-V-2A/B 85 85 HR-V-22A/B, and Flanges HR-V-22A/B 105 105 MA-TM-244-214B Penetration 416 LLRT of HR-V-4A/B, 11/11/2013 HR-V-23A 20 20 HR-V-23A/B, and Flanges HR-V-23B 20 20 HR-V-4A/B 40 40 MA-TM-244-215A Penetration 309 LLRT of MU-V-2A, 11/16/2013 MU-V-2B 30 20 MU-V-2B MOV actuator PM MU-V-2B, MU-V-3, and MU-V-238 MA-TM-244-215D Penetration 337 LLRT of MU-V-20 and 11/08/2013 MU-V-20 192 192 MU-V-1 16 check valve MU-V-1 16 MU-V-1 16 20 20 --inspection ATTACHMENT 2 TM I-14-028 TECHNICAL SPECIFICATION 6.9.1 .B.3 PERIODIC LEAK REDUCTION PROGRAM TEST RESULTS DATE OF LEAKING RESULTING SURVEILLANCE PERFORMA COMPONENT MEASURED LEAK RATE MAINTENANCE PROCEDURES PROCEDURE TITLE / DESCRIPTION NCE I.D. AS-FOUND AS-LEFT UNDERTAKEN MA-TM-244-216 Penetration 307 LLRT of NI-V-26 and 11/07/2013 NI-V-26 20 20 NI-V-27 NI-V-27 20 20 MA-TM-244-217B Penetration 347 LLRT of NS-V-4, NS- Not NS-V-211 relief valve V-35, and NS-V-211 11/02/2013 NS-V-211 required 20 replacement MA-TM-244-218A LLRT of Flanged Penetrations 104, 11/22/2013 P-104 20 105,106 11/22/2013 P-105 Not 20 11/07/2013 P-106 required 20 MA-TM-244-218B LLRT of Flanged Penetrations 221, 11/08/2013 P-221 20 222, 240/241, and 414 11/22/2013 P-222 Not 20 11/20/2013 P-240/241 required 90 11/22/2013 P-414 20 MA-TM-244-221 Penetration 201 E LLRT 10/31/2013 P-201E 85 85 MA-TM-244-222 Penetration 421 & 422 LLRT of RB-V- 11/13/2013 RB-V-2A 20 20 2A and RB-V-7 RB-V-7 20 20 MA-TM-244-223 Penetration 304 LLRT of SF-V-22 and 11/12/2013 SF-V-22 20 20 SF-V-23 SF-V-23 20 20 MA-TM-244-224 Penetration 104 LLRT of SA-V-2 and 11/21/2013 SA-V-2/3 20 20 SA-V-3 (combined test)MA-TM-244-225 Penetration 330 LLRT of WDG-V-3 and 11/09/2013 WDG-V-3 200 200 WDG-V-4 WDG-V-4 20 20 MA-TM-244-226A Penetration 331 LLRT of WDL-V-303, 11/13/2013 WDL-V-303 20 20 WDL-V-304 AOV actuator WDL-V-304, and WDL-V-727 WDL-V-304/727 130 20 PM MA-TM-244-226B Penetration 353 LLRT of WDL-V-534 11/05/2013 WDL-V-534/535 20 20 and WDL-V-535 (combined test)MA-TM-244-227 Penetration 418 LLRT of Equipment 10/28/2013 Flange O-rings 79 Removed & later re-installed Hatch Flange O-rings 11/21/2013 Flange O-rings 20 Equipment hatch OP-TM-823-251 LLRT of Purge Exhaust Penetration 11/23/2013 AH-V-1 A/B Not 2643 Removed, then later reset Valves (combined test) required 300 stops OP-TM-823-252 LLRT of Purge Supply Penetration 11/23/2013 AH-V-1C/D Not 1593 Removed, then later reset Valves (combined test) required 300 stops; and AH-V-1 C motor replacement Notes: 1. Local Leak Rate Testing is performed under the Option B provisions of 10CFR50 Appendix J, and the minimum LLRT leakage value used is 20 sccm based on the low end of the calibration range of the flow instrumentation.
- 2. 'As-Left' testing is not required if the 'As-found' leakage was acceptable and no maintenance was performed.
- 3. 'As-Found' testing is not required for LLRT components not on extended test intervals nor for containment penetration flanges that are simply reinstalled at the end of an outage.
TM1-14-028 Attachment 3 ATTACHMENT 3 PRESSURIZER POWER OPERATED RELIEF VALVE AND PRESSURIZER SAFETY VALVE CHALLENGES IN 2013 There were no challenges to the pressurizer power operated relief valve (PORV) o[ either of the two pressurizer (PZR) safety valves during the entire calendar year of 2013.A review of the Reactor Coolant System (RCS) pressure indication trend data concluded that the RCS pressure operated well below the PORV set point of 2450 psig, and both PZR safety valve set points of 2500 psig throughout the calendar year of 2013. Therefore no challenges to the PORV or PZR safety valves occurred during 2013.
TM1-14-028 Attachment 4 ATTACHMENT 4 RESULTS OF SPECIFIC ACTIVITY ANALYSIS-PRIMARY COOLANT SYSTEM Technical Specification 6.9.1 .B.5 requires annual reporting of certain information regarding the results of specific activity analyses in which the primary coolant exceeded the limits of Technical Specification (TS) 3.1.4.1. The limits ol TS 3.1.4.1 were not exceeded at TMI-1 at any time during the year 2013. The figure of RCS activity for 2013 shows that the limit of 0.35 microcurie/gram dose equivalent 1-131 (DEI) was not exceeded in 2013.TMI-1 Dose Equivalent Iodine (DEI) in 2013 1.OOE+00 1.00E-01 1.OOE-02'd)0E-03 a 1 .00E-04 Il______kj.4d
.%4 1.00E-05 ......2-Jan 3-Feb 7-Mar 8-Apr 1 0-May 11-Jun 13-Jul 14-Aug1 5-Sepl 7-Oct 8-NoN20-Dec Date TMI-14-028 Attachment 5 ATTACHMENT 5 MAJOR CHANGES TO RAD WASTE TREATMENT SYSTEMS Technical Specification Section 6.17 requires reporting of Major changes to Radioactive Waste Treatment Systems. Major changes are interpreted to mean changes that would alter how the system functions or changes that would affect operational exposures, offsite dose rates or integrated doses. There were no major changes to the liquid, gaseous, or solid radioactive waste treatment systems at TMI-1 during the year of 2013.