View source for TMI-20-015, 2018-2019 Biennial 10 CFR 50.59 Summary Report and 2019 Commitment Revision Summary Report

{{Adams
| number = ML20121A006
| issue date = 04/30/2020
| title = 2018-2019 Biennial 10 CFR 50.59 Summary Report and 2019 Commitment Revision Summary Report
| author name = Orth T
| author affiliation = Exelon Generation Co, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000289
| license number = DPR-050
| contact person = 
| case reference number = TMI-20-015
| document type = Annual Operating Report, Letter type:TMI
| page count = 40
}}

=Text=
{{#Wiki_filter:Three Mile Island Nuclear Station, Unit 1 441 S. P.O. Box 480 Middletown, PA 17057 10 CFR 50.59(d)(2)
NEI 99-04 TMI-20-015 April 30, 2020 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Three Mile Island Nuclear Station, Unit 1 Renewed Facility License No. DPR-50 NRC Docket No. 50-289

==Subject:==
2018-2019 Biennial 10 CFR 50.59 Summary Report and 2019 Commitment Revision Summary Report

==References:==
: 1. Exelon Letter to NRC, "Certification of Permanent Cessation of Operations for Three Mile Island Nuclear Station," dated June 20, 2017 (ADAMS Accession No. ML17171A151)
: 2. Exelon Letter to NRC, "Certification of Permanent Removal of Fuel from the Reactor Vessel for Three Mile Island Nuclear Station, Unit 1," dated September 26, 2019 (ADAMS Accession No. ML19269E480)
This letter submits the 2018-2019 Biennial 10 CFR 50.59 Summary Report required by 10 CFR 50.59(d)(2) and the 2019 Annual Commitment Revision Summary Report required by SECY-00-0045 (NEI 99-04).
By letter dated June 20, 2017 (Reference 1), Exelon provided formal notification to the U.S. Nuclear Regulatory Commission (NRC) pursuant to 10 CFR 50.4(b)(8) and 10 CFR 50.82(a)(1)(i) of Exelon's determination to permanently cease operations at Three Mile Island Nuclear Station, Unit 1 (TMl-1) on or about September 30, 2019. On September 20, 2019, Exelon permanently ceased power operations at TMI-1. On September 26, 2019, pursuant to 10 CFR 50.82(a)(1)(ii) and 10 CFR 50.4(b)(9), Exelon provided certification to the NRC that all fuel had been permanently removed from the TMI-1 reactor vessel and placed in the spent fuel pool (SFP) (Reference 2). Since the certifications for permanent cessation of operations and permanent removal of fuel from the reactor vessel were submitted to the NRC pursuant to 10 CFR 50.82(a)(1)(i) and (ii), then pursuant to 10 CFR 50.82(a)(2), the 10 CFR 50 license no longer authorizes operation of the reactor or placement or retention of fuel in the reactor vessel.

U.S. Nuclear Regulatory Commission Biennial 50.59 and Annual Commitment Change Reports April 30, 2020 Page 2 Based on the possession only status, a review of prior commitments was conducted and determined that several commitments are no longer applicable. The results of the review are attached.
There were no procedure changes, tests or experiments, or facility modifications that required a 50.59 evaluation during the 2018-2019 reporting period.
There are no new regulatory commitments established by this submittal.
Should you have any questions concerning this letter, please contact Mr. Robert Brady at (717) 948-8776.
Respectfully, Trevor L. Orth Decommissioning Plant Manager Three Mile Island Nuclear Station, Unit 1

==Attachment:==
TMI-1 2019 Commitment Change Summary Report

U.S. Nuclear Regulatory Commission Biennial 50.59 and Annual Commitment Change Reports April 30, 2020 Page 3 cc:     w/ Attachments NRC Regional Administrator - NRC Region I NRC Project Manager, NRR Three Mile Island, Unit 1 NRC Project Manager, NMSS Three Mile Island Unit 1 Director, Bureau of Radiation Protection - PA Department of Environmental Resources

ATTACHMENT Three Mile Island Description of 2019 Commitment Revisions Part A: - One-Time Commitments Part B: - Programmatic Commitments tied to Generic Communications Part C: - Programmatic Commitments tied to Licensing Actions Part D: - Miscellaneous Programmatic Commitments Part E: - Items Classified as no longer being Regulatory Commitments

Commitment Change Summary Report                                                                               Attachment Part A - One-Time Commitments                                                                                Page 1 of 44 The following provides the update of one-time commitments that will be deleted based on the TMI-1 no longer being permitted to operate in accordance with 10 CFR 50.82(a)(2).
Letter Source:                                            Various - Refer to Table 1 for each item Exelon Tracking Number                                    Various - Refer to Table 1 for each item Nature of Commitment:                                     Table 1 list onetime open commitments that are related to inspections, analysis or responses to NRC generic communications (e.g. Bulletins, and Generic Letters), The table contains the commitment number, the commitment source, a summary of the commitment, and basis for the deletion of the commitment.
Each of the original regulatory commitments listed in Table 1 will be closed, since the actions are no longer applicable as a result of TMI1 being in a permanent shutdown state.
Justification for Change By letter dated September 26, 2019, Exelon provided certification that TMI1 was permanently shut down and defueled with all irradiated fuel being stored in the Spent Fuel Pool. In accordance with 10 CFR 50.82(a)2 TMI1 is no longer permitted to operate or place fuel in the reactor vessel. The only risk is the safe storage of irradiated fuel in the Spent Fuel Pool. The regulatory commitments in Table 1 no longer afford the original intent and protection. Table 1 provides additional basis for each action item.
Table 1 OneTime Commitments that are no longer applicable based on Permanent Shutdown Status Commitment          Commitment              Commitment Details                             Basis for Deletion Tracking             Source Number             Document 0135661904          Updated           TMI has elected to delay                T1R23 was a defueling outage in which the Commitment        implementation of the final scope       station certified per 50.82 that the station Schedule  RVI    of RVI MRP227A examinations           was completely defueled, and pursuant to MRP227A         from the T1R22 (2017) refueling         50.82 TMI is no longer permitted to Examinations      outage to the T1R23 (2019)              operate, or store fuel in the reactor vessel.
refueling outage.                       The need to perform RVI MRP227A examinations of Reactor Vessel internals were required to support long term operation, however since operation is no longer permitted the need to complete this vessel inspection is no longer germane.
Therefore, this commitment is being placed in history.

Commitment Change Summary Report                                                                      Attachment Part A - One-Time Commitments                                                                       Page 2 of 44 Table 1 (Continued)
Commitment      Commitment               Commitment Details                         Basis for Deletion Tracking          Source Number         Document 0151677404    TMI1 Resolution  The Commitment due date of June       T1R23 was a defueling outage in which the of Generic Letter 1, 2017, has been extended based      station certified per 50.82 that the station 200402           on the following excerpt from TMI     was completely defueled, and pursuant to Letter to USNRC (TMI17051): TMI     50.82 TMI is no longer permitted to (Commitment 4)    is an Option 2A plant with a          operate, or store fuel in the reactor vessel.
calculated invessel fiber debris     The scoped of Design Basis Accidents have bypass of 19.66 grams/fuel            been reduced to the Fuel Handling assembly, which exceeds the NRC       Accident in the Spent Fuel Pool. Loss of acceptance limit of 15 grams/fuel     Coolant Accident is no longer a credible assembly. Therefore, WCAP17788,      event based on the fact the unit is no "Comprehensive Analysis and Test      longer permitted to operate, and Program for GSI191 Y Generic         subsequent Emergency Core Cooling Safety Issue191 Closure,"            System response is no longer required to methodology is required to            mitigate a credible event. Therefore, this properly close out GL 200402 and     commitment is being placed in history.
GSI191. WCAP17788 is currently under NRC review with forecasted approval in 2018. The final calculations for invessel fiber debris, as well as the existing ECCS flow sump performance final calculations, will be performed together to allow efficient utilization of engineering resources.
The final updated supplemental response to support closure of GL 200402 for TMI, Unit 1 will be submitted within nine months following NRC approval of WCAP17788.
0242869301    TMI15038, Ltr   The full LBLOCA reanalysis will be   T1R23 was a defueling outage in which the to NRC dated      completed within 21 months            station certified per 50.82 that the station April 6, 2015     following NRC issuance of the final   was completely defueled, and pursuant to Safety Evaluation Report (SER) for    50.82 TMI is no longer permitted to 10 CFR 50.46      BAW10179 Revision 9, which           operate, or store fuel in the reactor vessel.
30Day Report     incorporates by reference the         The scoped of Design Basis Accidents have supplement to BAW10192PA            been reduced to the Fuel Handling TMI 1  Thermal   Revision 0.                           Accident in the Spent Fuel Pool. The Large Conductivity                                            Break Loss of Coolant Accident is no longer Degradation                                             a credible event based on the fact the unit (TCD)                                                   is no longer permitted to operate, and Commitment                                              subsequent Emergency Core Cooling System analysis is no longer required to mitigate a credible event. Therefore, this commitment is being placed in history.

Commitment Change Summary Report                                                                    Attachment Part A - One-Time Commitments                                                                      Page 3 of 44 Table 1 (Continued)
Commitment      Commitment             Commitment Details                         Basis for Deletion Tracking         Source Number        Document 0256770802     NRC Ltr dated  Inner Diameter (ID) surface          T1R23 was a defueling outage in which the September     breaking flaws greater than 50%      station certified per 50.82 that the station 15,2015     throughwall and subsurface flaws    was completely defueled, and pursuant to greater than 50% throughwall shall  50.82 TMI is no longer permitted to Approval of   be repaired or evaluated prior to    operate, or store fuel in the reactor vessel.
Relief Request plant restart. Evaluations shall be  Since this is a restart commitment and is RR1401 and   submitted to the NRC for review      no longer applicable this item will be SER      and approval prior to plant restart. placed in history.
0256941701     NRC Ltr dated  Inner Diameter (ID) surface          T1R23 was a defueling outage in which the September     breaking flaws greater than 50%      station certified per 50.82 that the station 15,2015     throughwall and subsurface flaws    was completely defueled, and pursuant to greater than 50% throughwall shall  50.82 TMI is no longer permitted to Approval of   be repaired or evaluated prior to    operate, or store fuel in the reactor vessel.
Relief Request plant restart. Evaluations shall be  Since this is a restart commitment and is RR1401 and   submitted to the NRC for review      no longer applicable this item will be SER (RMS)    and approval prior to plant restart. placed in history.

Commitment Change Summary Report                                                                            Attachment Part B - Programmatic Commitments tied to Generic Communications                                           Page 4 of 44 The following provides the update of programmatic commitments tied to Generic Communication responses that will be deleted based on the TMI-1 no longer being permitted to operate in accordance with 10 CFR 50.82(a)(2).
Letter Source:                                           Various - Refer to Table 2 for each item Exelon Tracking Number                                   Various - Refer to Table 2 for each item Nature of Commitment:                                    Table 2 list programmatic open commitments that are related to responses to NRC generic communications (e.g.
Bulletins, and Generic Letters), The table contains the commitment number, the commitment source, a summary of the commitment, and basis for the deletion of the commitment.
Each of the original regulatory commitments listed in Table 1 will be closed, since the actions are no longer applicable as a result of TMI1 being in a permanent shutdown state.
Justification for Change By letter dated September 26, 2019, Exelon provided certification that TMI1 was permanently shut down and defueled with all irradiated fuel being stored in the Spent Fuel Pool. In accordance with 50.82(a)(2), TMI1 is no longer permitted to operate or place fuel in the reactor vessel. The only risk is the safe storage of irradiated fuel in the Spent Fuel Pool. The commitments in Table 1 no longer afford the original intent and protection. Table 1 provides additional basis for each action item.

Commitment Change Summary Report                                                                     Attachment Part B - Programmatic Commitments tied to Generic Communications                                   Page 5 of 44 Table 2 Generic Communications Commitments that are subject to deletion based on Change of Plant Status to Permanently Shutdown Commitment      Commitment               Commitment Details                         Basis for Deletion Tracking         Source Number         Document 0112207201   6710962097       The original commitment is            Based on PDTS the Control Building GL 89013:         described in the updated response     Ventilation System will no longer be REVISED            provided to the NRC for GL 8913      classified as Safety Related.
RESPONSE           (6710962097 dated 6/6/1996):
The Control Building Chillers are not Nuclear Safety Related by design, however we acknowledge the important function they provide; thus we feel it is prudent to monitor their performance. The building cooled by this system is continually occupied. As such, degraded performance of a chiller would be detected through increased temperature in the Control Building. It should be noted that GL 8913 allows an alternative action of frequent regular maintenance in lieu of testing for degraded performance of the heat exchanger. Both regular maintenance (bimonthly PM and annual overhaul) and performance trending will be done for the Control Building Chillers.
0112207203   59280320148      The plant will improve the            Containment Integrity is no longer SIXTYDAY          containment closeout inspection       required, and Containment Closeout will RESPONSE TO        procedure to specifically address     no longer be required. There are no NRC BULLETIN       dirt, dust, and small debris          safety related components housed in the 200301            accumulation.                         RB.
0112207227   6710972253       GL 8910 closeout letter 671097    Based on Permanent Shutdown Status at GL 8910 CLOSE     2253 committed to:                    TMI, and implementation of the PDTS, OUT LETTER         1. TMI1 maintenance procedures       there are no active safety system at TMI.
for the MOVs will be revised to       The MOV program is no longer required ensure that any work on valve         and will be abandoned.
internals is evaluated for potential effects on stem thrust requirements. This will ensure that post maintenance dynamic testing is considered when appropriate.
These changes will be completed during the next operating cycle, TMI1 Operating Cycle 12.

Commitment Change Summary Report                                                              Attachment Part B - Programmatic Commitments tied to Generic Communications                             Page 6 of 44 Table 2 (Continued)
Commitment       Commitment             Commitment Details                      Basis for Deletion Tracking     Source Document Number 0112207228   19209820242    In response to NRC Generic Letter    Based on Permanent Shutdown Status at RESPONSE TO      9605, Three Mile Island Unit 1      TMI, and implementation of the PDTS, NRC'S SAFETY     committed to implement the Joint     there are no active safety system at TMI.
EVALUATION      Owners Group (JOG) Program for       The JOG MOV program is no longer JOINT OWNER'S    Motor Operated Valve Periodic        required and will be abandoned.
GROUP            Verification in accordance with MPR PROGRAM ON       1807 (Interim) and MPR2524A PERIODIC         Rev.1 (Final). Note: Not all GL9605 VERIFICATION OF  MOV Program Valves are within the MOVS             scope of the Final JOG Program.
0112207230   GL 96005: RAI   In response to item 3 of the NRC     Based on Permanent Shutdown Status at REGARDING        Request for Additional Information   TMI, and implementation of the PDTS, GPUN'S           dated 11/5/1998, the licensee        there are no active safety system at TMI.
RESPONSE TO GL   committed to address potential age  The JOG MOV program is no longer 96005 FOR       related degradation by performing    required and will be abandoned.
TMINS TMI1      the periodic static diagnostic or PERIODIC         preventive maintenance of MOV as VERIFICATION OF  required by the JOG program.
DESIGNBASIS CAPABILITY OF SAFETYRELATED MOTOR OPERATED VALVES (M97111) 0112207232   19209820605    GPUN letter (19209820605)          Containment is no longer a safety related GL 9804, GPUN   committed to evaluate the guidance   component and maintaining Safety RESPONSE         provided in EPRI TR109937,          Related coatings program is no longer "Guideline on Nuclear SafetyRelated required.
Coatings," dated April 1998 and implement any changes by 12/31/99.
0112207235   GQL 1202         GPUN COMMITTED TO THE NRC IN         Based on Permanent Shutdown Status at IEB 7901A: ASCO RESPONSE TO THE ORIGINAL             TMI, and implementation of the PDTS, SOLENOID VALVE   BULLETIN THAT MAINTENANCE            there are no active safety system at TMI.
SERVICE LIFE     PROCEDURE 1401P14 APPROVED          The need to maintain ASCO solenoid TO IMPROVE FUTURE                    valve controls are no longer required.
MAINTENANCE. MP 1410P14 PROVIDED UPGRADED DETAILED OVERHAUL AND ALIGNMENT INSTRUCTIONS AND REQUIRED MORE DETAILED DOCUMENTATION OF BOTH "ASFOUND" AND "AS LEFT" PUMP CONDITIONS.

Commitment Change Summary Report                                                           Attachment Part B - Programmatic Commitments tied to Generic Communications                          Page 7 of 44 Table 2 (Continued)
Commitment       Commitment             Commitment Details                   Basis for Deletion Tracking     Source Document Number 0112207237   IEB 7915: DEEP  GPUN COMMITTED TO THE NRC IN       Based on Permanent Shutdown DRAFT PUMP       RESPONSE TO THE ORIGINAL BULLETIN  Status at TMI, and implementation DEFICIENCIES     THAT MAINTENANCE PROCEDURE         of the PDTS, there are no active 1401P14 APPROVED TO IMPROVE       safety system at TMI. These systems FUTURE MAINTENANCE. MP 1410P14    are no longer required to meet PROVIDED UPGRADED DETAILED         ASME Section XI IST requirements.
OVERHAUL AND ALIGNMENT INSTRUCTIONS AND REQUIRED MORE DETAILED DOCUMENTATION OF BOTH "ASFOUND" AND "ASLEFT" PUMP CONDITIONS.
01122072     IEB 8012: DECAY GPUN COMMITTED TO THE NRC TO: 1)   This will no longer be required since 3800         HEAT REMOVAL     MODIFICATION OF OP 11044 TO       Decay Heat and the BWST are no SYSTEM           PROVIDE ADDITIONAL                 longer TS required functions to OPERABILITY      ADMINISTRATIVE CONTROL OVER THE    protect. There will no longer be fuel POSITION OF DHV6A AND DHV6B    stored in the RPV to protect.
(REACTOR BUILDING SUMP ISOLATION VALVES). DURING COLD SHUTDOWN AND REFUELING SHUTDOWN CONDITIONS, THE VALVES (EXCEPT DURING TESTING) WILL BE TAGGED CLOSED WITH THEIR BREAKERS OPEN TO PREVENT INADVERTENT OPENING AND POTENTIAL DRAINING OF THE BORATED WATER STORAGE TANK (BWST) TO THE REACTOR BUILDING SUMP.
0112207242   IEB 7925:       GPUN COMMITTED TO THE NRC          Based on Permanent Shutdown FAILURE OF       WITHIN TLL 005 DATED 1/10/80 THAT: Status at TMI, and implementation WESTINGHOUSE     (1) TMI1 USED WESTINGHOUSE TYPE   of the PDTS, there are no active BFD RELAYS IN    BFD, STYLE 5072A49, COIL STYLE     safety system at TMI. The SAFETY RELATED   1271C50G01 RELAYS AS CONTROL       Emergency Diesel Generators are no SYSTEMS          RELAYS FOR THE 1A AND 1B           longer safety related and this EMERGENCY DIESEL GENERATORS.       commitment is no longer applicable.
(2) THE DIESEL GENERATOR ANNUAL INSPECTION PROCEDURE WAS REVISED TO INCLUDE A FUNCTIONAL TEST ON EACH RELAY.
(3) THE DOCUMENTATION OF ALL RELAY FAILURES FOUND DURING THE INITIAL OR FOLLOWUP PROGRAM TESTING IN ACCORDANCE WITH THE REQUIREMENTS SET FORTH IN THE BULLETIN.

Commitment Change Summary Report                                                              Attachment Part B - Programmatic Commitments tied to Generic Communications                            Page 8 of 44 Table 2 (Continued)
Commitment       Commitment            Commitment Details                     Basis for Deletion Tracking          Source Number          Document 0112207244    GL 8121:        NATURAL CIRCULATION COOLDOWN     With certification required by 50.82 NATURAL          PROCEDURES & TRAINING.           submitted, TMI is no longer permitted to CIRCULATION                                       operate or store fuel in the reactor COOLDOWN                                          vessel. The protection afforded by this commitment is no longer required.
0112207247    5211822149     TOTAL AND PARTIAL LOSS OF        With certification required by 50.82 IEB 7927: LOSS  ICS/NNI POWER EMERGENCY          submitted, TMI is no longer permitted to OF NONCLASS    PROCEDURES.                      operate or store fuel in the reactor 1E                                                vessel. The protection afforded by this INSTRUMENTATI                                     commitment is no longer required.
ON AND CONTROL 0112207249    5211832040     COV10A/B LOCKED OPEN           EFW is no longer required. With GL 8114: EFW    REQUIREMENT.                     certification required by 50.82 SEISMIC                                           submitted, TMI is no longer permitted to QUALIFICATION                                    operate or store fuel in the reactor ATTACHMENTS                                       vessel. The protection afforded by this ITEM 4                                            commitment is no longer required.
0112207250    5211832055     EFW SEISMIC QUALIFICATION        EFW is no longer required. With GL 8114: EFW    Attachment(s): GPUN COMMITTED    certification required by 50.82 SEISMIC          TO THE NRC TO LOCK OPEN THE      submitted, TMI is no longer permitted to QUALIFICATION   RECIRCULATION LINES ON THE       operate or store fuel in the reactor ATTACHMENTS      EMERGENCY FEEDWATER (EFW)        vessel. The protection afforded by this ITEM 4           PUMPS.                           commitment is no longer required.
0112207252    5211832133:    EFW SEISMIC QUALIFICATION  CO  EFW is no longer required. With EFW SEISMIC      V27A/B                          certification required by 50.82 QUALIFICATION    Attachment(s): GPUN COMMITTED    submitted, TMI is no longer permitted to TO THE NRC TO LOCK CLOSE THE     operate or store fuel in the reactor VALVES COV27A AND COV27B     vessel. The protection afforded by this DURING OPERATION.                commitment is no longer required.
0112207254    5211832330     ATWS REVIEW ITEMS FROM GL 83    This event requires the reactor to be in GL 8328 ITEM    28.                              operations. With certification required 3.1.1: POSTTRIP                                  by 50.82 submitted, TMI is no longer REVIEW                                            permitted to operate or store fuel in the reactor vessel. The protection afforded by this commitment is no longer required.
0112207256    5211833222:    NATURAL CIRCULATION COOLDOWN     Natural Circulation cooldown requires NATURAL          PROCEDURE.                       the plant to be in operations. With CIRCULATION                                       certification required by 50.82 COOLDOWN                                          submitted, TMI is no longer permitted to (GENERIC LETTER                                   operate or store fuel in the reactor 8121)                                            vessel. The protection afforded by this commitment is no longer required.

Commitment Change Summary Report                                                            Attachment Part B - Programmatic Commitments tied to Generic Communications                          Page 9 of 44 Table 2 (Continued)
Commitment      Commitment             Commitment Details                    Basis for Deletion Tracking          Source Number         Document 0112207257   5211832330    ITEM 2.1 REQUIRED THE             Since no longer permitted to operate or GL 8328 ITEM   CONFIRMATION THAT ALL             place fuel in the reactor vessel, Reactor 2.1: EQUIPMENT  COMPONENTS WHOSE FUNCTIONING      Protection/Trip is no longer required.
CLASSIFICATION  WAS REQUIRED TO TRIP THE          Reactor Protection is no longer a safety AND VENDOR      REACTOR WERE IDENTIFIED AS        related system.
INTERFACE (RTS) SAFETY RELATED ON ALL DOCUMENTATION AND IN INFORMATION HANDLING SYSTEMS THAT WERE USED TO CONTROL ALL ACTIVITIES PERFORMED ON THAT SAFETY RELATED EQUIPMENT. THE NRC.
SER 5211873170 ACCEPTED THE GPUN RESPONSE AND CLOSED THE ITEM.
0112207258   5211832330    GPUN COMMITTED TO THE NRC THAT    Since no longer permitted to operate or GL 8228 SEC    SP 13134.1 PERFORMED ON LINE     place fuel in the reactor vessel, Reactor 4.5.1: REACTOR  TESTING OF THE REACTOR TRIP       Protection/Trip is no longer required.
TRIP SYSTEM     SYSTEM (RTS) ON A MONTHLY BASIS:
ONLINE         SP 13134.4 INCORPORATED THE FUNCTIONAL      CRDCS SCR TRIP TEST GUIDELINES TESTING         PROVIDED BY BABCOCK & WILCOX: SP 13034.1 WAS REVISED TO INCORPORATE TESTING OF TRIPPING THE CRDM POWER FEED CIRCUIT BREAKERS VIA THEIR SHUNT TRIP DEVICES.
0112207259   5211832330    PLANT COMPUTER SYSTEM POSTTRIP   Since no longer permitted to operate or GL 8328 ITEM   CHECKLIST  GPUN COMMITTED TO     place fuel in the reactor vessel, Reactor 1.2: POST TRIP  THE NRC TO INCORPORATE A          Protection/Trip is no longer possible and REVIEW (DATA    CHECKLIST OF PLANT COMPUTER       post trip review is not required.
AND             SYSTEM PARAMETERS FOR REACTOR INFORMATION     TRIP INTO TMI1 PROCEDURES TO CAPABILITY)     ENSURE ASSEMBLY OF COMPLETE DATA PACKAGE.
0112207260   5211832330    GPUN COMMITTED TO THE NRC TO      Since no longer permitted to operate or GL 8228 ITEM   INCORPORATE METHODS AND           place fuel in the reactor vessel, Reactor 1.2: POST TRIP  CRITERIA FOR COMPARING THE        Protection/Trip is no longer possible and REVIEW (DATA    EVENT INFORMATION WITH KNOWN      post trip review is not required.
AND             OR EXPECTED BEHAVIOR.
INFORMATION CAPABILITY)

Commitment Change Summary Report                                                             Attachment Part B - Programmatic Commitments tied to Generic Communications                           Page 10 of 44 Table 2 (Continued)
Commitment        Commitment          Commitment Details                      Basis for Deletion Tracking     Source Document Number 0112207261    5211832330    POSTTRIP REVIEW & ANALYSIS       Since no longer permitted to operate or GL 8328 ITEM   ROLE & RESPONSIBILITY.            place fuel in the reactor vessel, Reactor 1.1: POSTTRIP                                    Protection/Trip is no longer possible and REVIEW                                            post trip review is not required.
(PROGRAM DESCRIPTION AND PROCEDURE)
ROLES 0112207262    5211832330    RESTART DECISION PREREQUISITE     Since no longer permitted to operate or GL 8228 ITEM   ACTIONS.                          place fuel in the reactor vessel, Reactor 1.1: POSTTRIP                                    Protection/Trip is no longer possible and REVIEW                                            post trip review is not required.
(PROGRAM DESCRIPTION AND PROCEDURE)
RESTART 0112207263    5211832330    INDEPENDENT REVIEW INITIATING     Since no longer permitted to operate or GL 8228 ITEM   CRITERIA.                         place fuel in the reactor vessel, Reactor 1.1: POSTTRIP                                    Protection/Trip is no longer possible and REVIEW                                            post trip review is not required.
(PROGRAM DESCRIPTION AND PROCEDURES) 0112207265    5211822229    POTENTIAL OF ERRONEOUS LEVEL      The temperature effect on the Steam IEB 7921:      INDICATIONS                       Generators or Pressurizer are related to TEMPERATURE     Attachment(s): GPUN COMMITTED     Normal Operating Pressure and EFFECTS ON      TO THE NRC TO REVISE              Temperatures conditions with respect to LEVEL           PROCEDURES 12026A, 12026B,      cold conditions. Both of the instruments MEASUREMENTS    12026C AND 120324 TO REMIND     are in the Reactor Coolant System which is THE OPERATORS OF THE              no longer safety related. The conditions POTENTIAL OF                      are no longer plausible since TMI is no ERRONEOUS STEAM GENERATOR         longer permitted to operate or place fuel AND PRESSURIZER LEVEL             in the reactor vessel.
INDICATIONS.
0112207266    5211832330    REACTOR TRIP SYSTEM TRIP          Since no longer permitted to operate or GL 8328 ITEM   FEATURE TESTING.                  place fuel in the reactor vessel, Reactor 4.5.1: REACTOR                                    Protection/Trip is no longer required.
TRIP SYSTEM RELIABILITY (SYSTEM FUNCTIONAL TESTING)

Commitment Change Summary Report                                                           Attachment Part B - Programmatic Commitments tied to Generic Communications                         Page 11 of 44 Table 2 (Continued)
Commitment       Commitment             Commitment Details                    Basis for Deletion Tracking     Source Document Number 0112207271    5211842286    REFUELING CAVITY WATER SEAL       Since Fuel is no longer permitted to be IEB 8403:      FAILURE                           placed in the reactor vessel, this action is POTENTIAL FOR   Attachment(s): GPUN COMMITTED IN  no longer required to protect the decay REFUELING       THE RESPONSE 5211842286 THAT    heat removal or protection of fuel in the CAVITY WATER    THE POTENTIAL FOR AND             reactor pressure vessel.
SEAL FAILURE    CONSEQUENCES OF A REFUELING CAVITY SEAL GASKET FAILURE HAS BEEN REVIEWED AND SUBMITTED A

==SUMMARY==
REPORT TO THE NRC.
0112207274    5211842072    HEAVY LOADS  INCORE              Since fuel is no longer permitted to be NUREG 0612:     INSTRUMENTATION                   placed in the reactor pressure vessel, CONTROL OF      Attachment(s): GPUN COMMITTED     heavy loads protection is no longer HEAVY LOADS     TO THE NRC TO REVISE PROCEDURE    required in the Reactor Building.
15081 ON INCORE INSTRUMENTATION PER ITEM 3 OF THE GPU CONTROL OF HEAVY LOADS IMPLEMENTATION SCHEDULE SO THAT THE PROCEDURE SATISFIED THE REQUIREMENTS OF 5.1.1(2) OF NUREG0612.
0112207276    5211842156    NATURAL CIRCULATION COOLDOWN      No longer permitted to operate reactor GL 8121:       PROCEDURE CHANGE.                 or place fuel in the reactor pressure GENERIC LETTER                                    vessel, therefore this mitigation strategy 8121  NATURAL                                   is no longer required.
CIRCULATION COOLDOWN 0112207278    5211852182    THREADED FASTENER DEGRADATION     The RCS pressure boundary is no longer IEB 8202:      IN RCS BOUNDARY.                  safety related, per 50.82(a)2 TMI is no DEGRADATION OF                                    longer permitted to operate or place fuel THREADED                                          in reactor vessel.
FASTENERS IN RC PRESSURE BOUNDARY 0112207279    5211842147    HEAVY LOADS PROCEDURE  SLING     Since fuel is no longer permitted to be NUREG 0612:     SELECTION/APPROVAL                placed in the reactor pressure vessel, CONTROL OF      Related to RPV Seal Plate.        heavy loads protection is no longer HEAVY LOADS                                       required in the Reactor Building.
0112207281    5211842200    POLAR CRANE OP PROC CRANE         Since fuel is no longer permitted to be NUREG 0612:     INSPECTION REQUIREMENT            placed in the reactor pressure vessel, CONTROL OF      Attachment(s): GPUN COMMITTED     heavy loads protection is no longer HEAVY LOADS     TO THE NRC TO REVISE PROCEDURE    required in the Reactor Building.
RP 15071 POLAR CRANE OPERATION TO INCLUDE A REQUIREMENT FOR INSPECTION PRIOR TO EACH LIFT USING SLINGS OR OTHER APPROVED DEVICES.

Commitment Change Summary Report                                                            Attachment Part B - Programmatic Commitments tied to Generic Communications                         Page 12 of 44 Table 2 (Continued)
Commitment       Commitment Source            Commitment Details               Basis for Deletion Tracking Number         Document 011220728300   5211842242           DIESEL GENERATOR RELIABILITY     Once the certification of GL 8415: PROPOSED     IMPROVEMENTS.                    50.82(a)2 were completed, TMI is STAFF ACTIONS TO                                        no longer permitted to operate or IMPROVE & MAINTAIN                                      place fuel in the reactor vessel, DG RELIABILITY                                          therefore with the implementation of the PDTS the Emergency Diesel Generators are no longer safety related.
011220728500   5211842179           BORON PRECIPITATION SHIELDING    Once the certification of NUREG 0737 II.B.2: TMI GPUN COMMITTED TO THE NRC TO     50.82(a)2 were completed, TMI is ACTION PLANT           LOCK OPEN THE VALVE DHV12B     no longer permitted to operate or SECTION II.B.2 DH      AND TO INSTALL A REACH ROD FOR   place fuel in the reactor vessel, PLANT SHIELDING        DHV64 SO THAT SUFFICIENT       Post LOCA conditions are no OPTION                 FLOW IS AVAILABLE FOR CORE       longer applicable therefore the COOLING AND BORON                protection afforded by this PRECIPITATION PREVENTION         commitment is no longer UNDER WORST CASE SINGLE          required.
FAILURES WITHOUT REQUIRING MANUAL ACTION IN AN INACCESSIBLE HIGH RADIATION AREA.
011220728600   5211842153:          ATP COMMITMENTS FROM ATOG        Once the certification of CONTROL ROOM           COMMITTEE                        50.82(a)2 were completed, TMI is DESIGN REVIEW          GPUN COMMITTED TO THE NRC        no longer permitted to operate or SUPPLEMENTAL           THE FOLLOWING ACTIONS:           place fuel in the reactor vessel, REPORT (NUREG 0737     (1) REVISE PROCEDURE 12107 STEP and there are no transients/ATP I.D.1)                 10 TO REDUCE THE RUNOUT LIMIT    required for the protection of the OF 1800 GPM TO A VALUE OF 1750   spent fuel pool.
GPM. (Historical see UPDATE 8/16/07 below)
(2) REVISE PROCEDURE 12107 SECTION 2.0 STEP 10 THAT THE PROCEDURAL LIMIT BE STATED IN TERMS OF THE NET PUMP FLOW AS INDICATED ON THE CONTROL ROOM INDICATOR. (Ongoing)
(3) REVISE PROCEDURE 121010 THAT THE MAKEUP PUMP PROCEDURAL LIMITS BE STATED IN TERMS OF NET INJECTION THROUGHT THE VIG'S.

Commitment Change Summary Report                                                           Attachment Part B - Programmatic Commitments tied to Generic Communications                         Page 13 of 44 Table 2 (Continued)
Commitment       Commitment            Commitment Details                    Basis for Deletion Tracking     Source Document Number 0112207288   5211832149     SG SHELL TO TUBE DIFFERENTIAL    Once the certification of 50.82(a)2 were NUREG 1019       TEMPERATURE LIMIT.               completed, TMI is no longer permitted to SUPP 1: STEAM                                     operate or place fuel in the reactor GENERATOR TUBE                                    vessel, therefore the Steam Generators REPAIR AND                                        are no longer safety related, and the RETURN TO                                         protections provided by this OPERATION                                         commitment is no longer required.
0112207289   5211832149     ISOLATED STEAM GENERATOR         Once the certification of 50.82(a)2 were NUREG 1019       PRESSURE CONTROL.                completed, TMI is no longer permitted to SUPP 1: STEAM                                     operate or place fuel in the reactor GENERATOR TUBE                                    vessel, therefore the Steam Generators REPAIR AND                                        are no longer safety related, and the RETURN TO                                         protections provided by this OPERATION                                         commitment is no longer required.
0112207291   5211843249:    CRDM CIRCUIT BREAKER TRIPPING    Once the certification of 50.82(a)2 were SER ACCEPTANCE   MECHANISM TESTING.               completed, TMI is no longer permitted to OF RESPONSE TO                                    operate or place fuel in the reactor GL 8328 ATWS                                     vessel, therefore Anticipated Transient ITEM 4.3                                          without SCRAM protection is no longer REACTOR TRIP;                                     required.
5211843249:
SYSTEM RELIABILITY 0112207294   5211842013     PROCEDURES FOR HEAVY LOADS IN    Since fuel is no longer permitted to be NUREG 0612:      REACTOR BUILDING.                placed in the reactor pressure vessel, CONTROL OF                                        heavy loads protection is no longer HEAVY LOADS                                       required in the Reactor Building 0112207295   5211842013     RV HEAD REMOVAL & INSTALLATION   Since fuel is no longer permitted to be NUREG 0612:      LIFT HEIGHT RESTRICTION.         placed in the reactor pressure vessel, CONTROL OF                                        heavy loads protection is no longer HEAVY LOADS                                       required in the Reactor Building.
0112207296   5211842013     RB POLAR CRANE SPECIAL LIFTING   Since fuel is no longer permitted to be NUREG 0612:      DEVICES.                         placed in the reactor pressure vessel, CONTROL OF                                        heavy loads protection is no longer HEAVY LOADS                                       required in the Reactor Building.
0112235501   5211862034     EFW PUMP STEAM BINDING PUMP      Once the certification of 50.82(a)2 were IEB 8501: STEAM RESTORATION.                     completed, TMI is no longer permitted to BINDING OF                                        operate or place fuel in the reactor AUXILIARY                                         vessel, therefore emergency feedwater is FEEDWATER                                         no longer a safety related system.
PUMP 0112235502   5211862034     EFW PUMP STEAM BINDING           Once the certification of 50.82(a)2 were IEB 8501: STEAM TEMPERATURE CHECKS.              completed, TMI is no longer permitted to BINDING OF                                        operate or place fuel in the reactor AUXILIARY                                         vessel, therefore emergency feedwater is FEEDWATER                                         no longer a safety related system.
PUMP

Commitment Change Summary Report                                                          Attachment Part B - Programmatic Commitments tied to Generic Communications                       Page 14 of 44 Table 2 (Continued)
Commitment       Commitment                 Commitment Details                 Basis for Deletion Tracking          Source Number          Document 0112235504    5211842200     HEAD & INTERNALS HANDLING FIXTURE     Since fuel is no longer permitted NUREG 0612:      WELD ISI PROG.                        to be placed in the reactor CONTROL OF                                             pressure vessel, heavy loads HEAVY LOADS                                            protection is no longer required in the Reactor Building.
0112235506    5211852092     REACTOR TRIP BREAKER MAINTENANCE. Once the certification of 50.82(a)2 Source                                                 were completed, TMI is no longer Document

==Title:==
permitted to operate or place fuel GL 8328 ITEM                                          in the reactor vessel, therefore 4.2.1: PERIODIC                                        Anticipated Transient without MAINTENANCE                                            SCRAM protection is no longer PROGRAM FOR                                            required.
REACTOR TRIP BREAKERS 0112235509    5211842013     HEAVY LOADS PROCEDURE  HEAD &        Since fuel is no longer permitted NUREG 0612:      INTERNALS HANDLING.                   to be placed in the reactor CONTROL OF                                             pressure vessel, heavy loads HEAVY LOADS                                            protection is no longer required in the Reactor Building.
0112235518    5211862186     GPUN COMMITTED TO THE NRC THAT TMI1  Once the certification of 50.82(a)2 IEB 8603:       DOES HAVE A SINGLE RECIRCULATION LINE were completed, TMI is no longer POTENTIAL        FOR THE HIGH PRESSURE INJECTION (HPI) permitted to operate or place fuel FAILURE OF       PUMPS WHICH ARE ISOLATED              in the reactor vessel, therefore MULTIPLE ECCS    AUTOMATICALLY ON EMERGENCY            any requirement related to ECCS PUMPS DUE TO     SAFEGUARDS (ES) ACTUATION.            performance criteria are no longer SINGLE FAILURE                                         required.
0112235522    5211862021     CHECK VALVE FAILUREDIESEL GENERATOR  EDG no longer safety related which references COOLING SYSTEM.
521183176 IEB 8303:
CHECK VALVE FAILURE IN DIESEL GENERATOR COOLING SYSTEM 0112235531    5211842013:    POLAR CRANE SAFE LOAD PATH FOR RB     Since fuel is no longer permitted RESPONSE TO      REGION D2.                           to be placed in the reactor NUREG 0612                                             pressure vessel, heavy loads CONTROL OF                                             protection is no longer required in HEAVY LOADS                                            the Reactor Building.

Commitment Change Summary Report                                                            Attachment Part B - Programmatic Commitments tied to Generic Communications                        Page 15 of 44 Table 2 (Continued)
Commitment       Commitment             Commitment Details                   Basis for Deletion Tracking     Source Document Number 0112235535    C311882087    IEB 8804 ITEM 3: POTENTIAL SAFETY Once the certification of 50.82(a)2 IEB 8804:      RELATED PUMP LOSS                  were completed, TMI is no longer POTENTIAL       GPUN COMMITTED INTERNALLY THAT     permitted to operate or place fuel in SAFETY RELATED  IN RESPONSE TO IEB 8804 ITEM 3 AN the reactor vessel, there are no longer PUMP LOSS       INDEPTH STUDY TO PREDICT PUMP     any safety related pumps and the DAMAGE AND VERIFY PUMP             protection provided by this MINIMUM FLOW REQUIREMENTS WAS      commitment is no longer required.
NOT NECESSARY WHEN CONSIDERING THAT THE CURRENT INSERVICE TEST (IST) PROGRAM WAS IN PLACE TO DETECT SUCH DAMAGE.
0112235537    C311882138    EXAMINATION OF THREADED            The RCS pressure boundary is no IEB 8202:      FASTENERS PRIOR TO REUSE           longer safety related, per 50.82(a)2 DEGRADATION OF  GPUN COMMITTED TO THE NRC TO       TMI is no longer permitted to operate THREADED        PERFORM VISUAL EXAMINATIONS ON     or place fuel in reactor vessel.
FASTENERS IN    ALL REACTOR COOLANT PRESSURE THE RCPB OF     BOUNDARY (RCPB) FASTENERS PRIOR PWR PLANTS      TO REUSE AND TO PERFORM MAGNETIC PARTICLE (MT) OR PENETRANT EXAMINATIONS (PT) ALSO UNLESS THE RCPB FASTENER HAS ONLY EXPERIENCED SHORT TERM SERVICE LESS THAN OR EQUAL TO 3 MONTHS SINCE ITS LAST MT OR PT AND THE FASTENER WAS FOUND DRY AND WITHOUT EVIDENCE OF BORIC ACID CRYSTALS OR RUST.
0112235534    C311882087    ADEQUATE MINIMUM PUMP              Once the certification of 50.82(a)2 IEB 8804:      RECIRCULATION FLOW                 were completed, TMI is no longer POTENTIAL       GPUN COMMITTED TO THE NRC THAT     permitted to operate or place fuel in SAFETY RELATED  ALL PUMPS IN TMI1 SAFETYRELATED  the reactor vessel, there are no longer PUMP LOSS       SYSTEMS EVALUATED WITHIN IEB 88   any safety related pumps and the 04 RESPONSE WHICH HAD THE          protection provided by this MINIMUM RECIRCULATION              commitment is no longer required.
REQUIREMENT HAD ADEQUATE MINIMUM RECIRCULATION FLOW IN ACCORDANCE WITH THE PUMP SPECIFICATIONS.
0112235538    C311882165    GL 8817: GENERIC LETTER 8817     Once the certification of 50.82(a)2 GL 8817:       EXPEDITIOUS ACTION 2.              were completed, TMI is no longer GENERIC LETTER                                     permitted to operate or place fuel in 8817                                              the reactor vessel, therefore Decay EXPEDITIOUS                                        Heat in the reactor vessel is no longer ACTION 2                                           required. Therefore, any protection provided by this commitment is no longer required.

Commitment Change Summary Report                                                           Attachment Part B - Programmatic Commitments tied to Generic Communications                        Page 16 of 44 Table 2 (Continued)
Commitment      Commitment             Commitment Details                   Basis for Deletion Tracking         Source Number         Document 0112235539   C311882165   CONTINUOUS CORE EXIT               Once the certification of 50.82(a)2 were GL 8817:      TEMPERATURE MONITORING.            completed, TMI is no longer permitted GENERIC LETTER                                    to operate or place fuel in the reactor 8817                                             vessel, therefore Decay Heat in the EXPEDITIOUS                                       reactor vessel is no longer required.
ACTION 3 AND                                      Therefore, any protection provided by PROGRAMMED                                        this commitment is no longer required.
ENHANCEMENT; GL 8817: 1(B) 0112235540   C311882165   GL 8817: GENERIC LETTER 8817     Once the certification of 50.82(a)2 were GL 8817:      EXPEDITIOUS ACTION 4 AND           completed, TMI is no longer permitted GENERIC LETTER PROGRAMMED ENHANCEMENT; GL         to operate or place fuel in the reactor 8817          8817: 1(A).                       vessel, therefore Decay Heat in the EXPEDITIOUS                                       reactor vessel is no longer required.
ACTION 4 AND                                      Therefore, any protection provided by PROGRAMMED                                        this commitment is no longer required.
ENHANCEMENT; GL 8817: 1(A) 0112235541   C311882165   PROCEDURAL OPS GUIDANCE           Once the certification of 50.82(a)2 were GL 8817:      REDUCED INVENTORY                 completed, TMI is no longer permitted GENERIC LETTER PERTURBATIONS TO THERCS            to operate or place fuel in the reactor 8817                                             vessel, therefore Decay Heat in the EXPEDITIOUS                                       reactor vessel is no longer required.
ACTION 5                                          Therefore, any protection provided by this commitment is no longer required.
0112235542   C311892015   RCS INVENTORY ADDITION OTHER       Once the certification of 50.82(a)2 were GL 8817:      THAN DHR SYSTEM PUMPS.             completed, TMI is no longer permitted GENERIC LETTER                                    to operate or place fuel in the reactor 8817                                             vessel, therefore Decay Heat in the EXPEDITIOUS                                       reactor vessel is no longer required.
ACTION 6 AND                                      Therefore, any protection provided by PROGRAMMED                                        this commitment is no longer required.
ENHANCE

Commitment Change Summary Report                                                          Attachment Part B - Programmatic Commitments tied to Generic Communications                       Page 17 of 44 Table 2 (Continued)
Commitment       Commitment               Commitment Details                 Basis for Deletion Tracking    Source Document Number 0112235543   C311892015     GPUN COMMITTED TO THE NRC TO        Once the certification of 50.82(a)2 GL 8817:        MAKE PROCEDURAL CHANGES IN          were completed, TMI is no longer GENERIC LETTER   ADDITION TO THOSE COMMITTED TO      permitted to operate or place fuel 8817            WITHIN 5211872188 AND 521188    in the reactor vessel, therefore PROGRAMMED       2165 BY JULY 1989 TO IMPROVE        Decay Heat in the reactor vessel is ENHANCEMENT 2    OPERATOR GUIDANCE IN THE            no longer required. Therefore, any (PROCEDURES)     FOLLOWING FOUR AREAS:               protection provided by this BASED ON; GL 88 1) THE TIME BEFORE CORE BOILING AND commitment is no longer required.
17: ANALYSIS     CORE UNCOVERY FOLLOWING A LOSS OF DECAY HEAT REMOVAL (DHR).
: 2) PROVIDING SUFFICIENT REACTOR COOLANT SYSTEM (RCS) VENT AREA TO PERMIT ADEQUATE MAKEUP FLOW.
: 3) CONTAINMENT CLOSURE REQUIREMENTS.
: 4) RESTART OF DHR FROM SATURATED CONDITIONS.
0112235544   GENERIC LETTER   GPUN COMMITTED TO THE NRC THE       Once the certification of 50.82(a)2 8817            FOLLOWING VISUAL OR AUDIBLE         were completed, TMI is no longer PROGRAMMED       INDICATORS WERE AVAILABLE IN THE    permitted to operate or place fuel ENHANCEMENT      CONTROL ROOM TO ASSIST THE          in the reactor vessel, therefore 1(D)             OPERATOR IN THE IDENTIFICATION OF   Decay Heat in the reactor vessel is (INSTRUMENTATI   ABNORMAL CONDITIONS WHICH AFFECT    no longer required. Therefore, any ON)              HEAT REMOVAL.                       protection provided by this commitment is no longer required.
0112235546   GL 8904:        GPUN IS COMMITTED TO THE GUIDANCE   Once the certification of 50.82(a)2 GUIDANCE ON      IN GL 8904 "GUIDANCE ON DEVELOPING were completed, TMI is no longer DEVELOPING       ACCEPTABLE IST PROGRAMS" BY VIRTUE  permitted to operate or place fuel ACCEPTABLE IST   OF THE FACT THAT THIS GL WAS ISSUED in the reactor vessel, therefore with PROGRAMS         TO LICENSEES. THE GL CONTAINS       the implementation of the PDTS INTERPRETATIONS AND ADDITIONAL      there are no longer any safety GUIDANCE THAT MAY DIFFER FROM TMI  related pumps or valves and the IST 1 PROGRAMS AND PROCEDURES.          program is no longer required.

Commitment Change Summary Report                                                            Attachment Part B - Programmatic Commitments tied to Generic Communications                         Page 18 of 44 Table 2 (Continued)
Commitment      Commitment Source              Commitment Details                 Basis for Deletion Tracking           Document Number 0112235547    C311892032         GPUN COMMITTED TO THE NRC:            Once the certification of IEB 8804: POTENTIAL 1) THE DHR PUMP MINIMUM               50.82(a)2 were completed, TMI SAFETY RELATED       RECIRCULATION CAPACITY WAS            is no longer permitted to PUMP LOSS            ADEQUATE TO ENSURE THAT PUMP          operate or place fuel in the OPERABILITY WAS NOT AFFECTED BY       reactor vessel, therefore with MINIMUM RECIRCULATION OPERATION.      the implementation of PDTS
: 2) ADDITIONAL VIBRATION READINGS      Decay Heat is not safety WERE INCORPORATED INTO THE            related, and the protection SURVEILLANCE TEST PROCEDURES OPTM   provided by this commitment is 212201 / 202 / 203 / 204 / 205 / 206 no longer required.
13035.2 AND 13003A/B.
: 3) THE REVISION BY JUNE 1989 OF PROCEDURES TO PROVIDE ADDITIONAL GUIDANCE THAT WILL APPLY WHEN HIGHER VIBRATION LEVELS ARE ENCOUNTERED AT BLADE PASSING FREQUENCY WHILE OPERATING OR TESTING THE DHR PUMPS AT MINIMUM RECIRCULATION FLOW RATE.
: 4) THE COMPLETION OF STEPS TO MINIMIZE THE TIME THAT DHR PUMPS ARE OPERATED AT MINIMUM FLOW DURING TESTING.
: 5) THE NOTIFICATION OF THE NRC BY LETTER OF ANY ADDITIONAL ACTIONS THAT MAY BE REQUIRED IN THE FUTURE.
ALSO, TO PROVIDE THE JUSTIFICATION FOR CONTINUED OPERATION AS REQUESTED BY IEB 8804.
0112235548    5450890103         NRC COMMITTED GPUN TO USE SPECIFIC    Once the certification of GL 8331: SE OF      GENERIC GUIDANCE AS PROVIDED BY THE   50.82(a)2 were completed, TMI ABNORMAL             B&W OWNERS GROUP WHEN AVAILABLE.      is no longer permitted to TRANSIENT            DEVIATIONS FROM THAT GUIDANCE TO BE   operate or place fuel in the OPERATING            ADDRESSED BY EACH LICENSEE.           reactor vessel, there are no GUIDELINES                                                 longer any design basis threats that require any abnormal transient guidelines.
0112235550    C311892078         GPUN COMMITTED TO THE NRC TO          Once the certification of GL 8908: GL 8908   MODIFY THE EXISTING                   50.82(a)2 were completed, TMI EROSION/CORROSION    EROSION/CORROSION MONITORING          is no longer permitted to INDUCED PIPE WALL  PROGRAM AT TMI1 TO PROVIDE A LONG   operate or place fuel in the THINNING             TERM CORPORATE LEVEL APPROACH. THIS   reactor vessel, therefore there WILL BE COMPLETE IN TIME TO SUPPORT   is no condition that in the spent 09R OUTAGE SCHEDULED INSPECTIONS. fuel pool that would create a erosion/corrosion or pipe wall thinning event.

Commitment Change Summary Report                                                            Attachment Part B - Programmatic Commitments tied to Generic Communications                         Page 19 of 44 Table 2 (Continued)
Commitment       Commitment                Commitment Details                    Basis for Deletion Tracking          Source Number          Document 0112235551    C311892068:   GPUN COMMITTED TO THE NRC TO INCLUDE     Once the certification of 10CFR50         A NOTE IN EP 120237, ITEM 13.K, TO THE  50.82(a)2 were completed, TMI is APPENDIX R  GL OPERATOR THAT A FAILED OPEN RCV1 MAY   no longer permitted to operate or 8112 RESPONSE  BE INDICATED BY RAPID RCS                place fuel in the reactor vessel, TO NRC          DEPRESSURIZATION, IN ORDER TO ENSURE     Appendix R fire protection is no QUESTIONS       CORRECTION OF SPURIOUS OPENING OF RC    longer required, and in the V1 DUE TO A FIRE.                       decommissioning state fire GPUN ALSO COMMITTED TO EXERCISING        protection is bounded by 480V MOLDED CASE BREAKERS IN             50.48(f).
ACCORDANCE WITH PROCEDURES; TO PROVIDE GUIDANCE IN 1420Y13 TO MAINTENANCE PERSONNEL THAT WHEN REPLACING FUSES, THEY ARE TO BE REPLACED WITH THE SAME SIZE AND TYPE AS THE FUSE REMOVED, TO REFER TO DRAWINGS, VENDOR MANUALS, OR OTHER REFERENCES IF THE SIZE AND TYPE CANNOT BE DETERMINED, OR REQUEST PLANT ENGINEERING TO PROVIDE APPROPRIATE RESOLUTION; TO UTILIZE THE GPUN OPERATIONAL QA PLAN FOR COMMERCIAL GRADE DEDICATION OF FUSES FOR SAFETY RELATED APPLICATIONS.
0112235552    C311902001    GPUN COMMITTED TO THE NRC TO REVISE      Once the certification of IEB 8903:      PROCEDURES GOVERNING FUEL LOADING TO     50.82(a)2 were completed, TMI is POTENTIAL LOSS  REFLECT THE FACT THAT FUEL ASSEMBLIES    no longer permitted to operate or OF REQUIRED     WILL NORMALLY ONLY BE LOADED INTO        place fuel in the reactor vessel, SHUTDOWN        THEIR FINAL CORE LOCATIONS; HOWEVER, IF  therefore the protection provided MARGIN DURING   A FUEL ASSEMBLY IS TO BE PLACED INTO ANY by this commitment is no longer REFUELING OPS   OTHER CORE LOCATION DUE TO FUEL          required.
HANDLING CONSTRAINTS, IT SHALL ONLY BE PLACED INTO CORE LOCATIONS THAT WOULD CONTAIN AN ASSEMBLY OF EQUAL OR HIGHER REACTIVITY AS DETERMINED BY THE APPROVED CORE RELOAD DESIGN.

Commitment Change Summary Report                                                             Attachment Part B - Programmatic Commitments tied to Generic Communications                         Page 20 of 44 Table 2 (Continued)
Commitment        Commitment              Commitment Details                   Basis for Deletion Tracking     Source Document Number 0112235553    C311893246     GL 8112: POSTFIRE SAFE SHUTDOWN    Once the certification of 50.82(a)2 GL 8112: POST  METHODOLOGY NRC.                     were completed, TMI is no longer FIRE SAFE                                             permitted to operate or place fuel SHUTDOWN                                              in the reactor vessel, Appendix R METHODOLOGY                                           fire protection is no longer NRC TECHNICAL                                         required, and in the EVALUATION; GL                                        decommissioning state fire 8112: REPORT                                         protection is bounded by 50.48(f).
0112235555    C311902031     GPUN COMMITTED TO THE NRC THAT       Once the certification of 50.82(a)2 GL 8919:       TMI1 OTSG OVERFILL PROTECTION IS    were completed, TMI is no longer REQUEST FOR      ADEQUATE BECAUSE OF THE OTSG HIGH    permitted to operate or place fuel ACTION RELATED   LEVEL ALARM RESPONSE PROCEDURES
* in the reactor vessel, therefore the TO RESOLUTION    AVAILABLE TO THE OPERATORS (MAIN     Steam Generators are no longer OF USI A47      ANUNCIATOR PANEL H, H11 (REV 12))  safety related, and the protections AND BECAUSE OF THE FOLLOWING         provided by this commitment is no SURVEILLANCES VERIFY THE OPERABILITY longer required.
AND CALIBRATION OF THE OTSG HIGH LEVEL MFW ISOLATION FEATURE OF THE HSPS.
0112235558    C311912015     GPUN COMMITTED TO THE NRC TO         Once the certification of 50.82(a)2 IEB 8811:       REDUCE FUTURE SURGE LINE THERMAL     were completed, TMI is no longer PRESSURIZER      CYCLES BY ADOPTING THE B&W           permitted to operate or place fuel SURGE LINE       RECOMMENDED LOWER (APPENDIX G)       in the reactor vessel, therefore the THERMAL          RCS SUBCOOLING MARGINS IN PLANT      protection provided by this STRATIFICATION  OPERATING AND PROCEDURES             commitment is no longer required.
DECEMBER 20,     PURSUANT TO ITS TOPICAL REPORT NO 1988             BAW2127 (FIGURE 8) AND "WHEN THE PREFERRED LOWER RCS SUBCOOLING MARGIN IS NOT MAINTAINED, (CONDUCT) AN EVALUATION OF ACTUAL PLANT PERFORMANCE, IN A PROGRAMMATIC MANNER, TO DETERMINE THE IMPACT(S) ON FATIGUE LIFE."
0112235559    C311912015     GPUN COMMITTED TO THE NRC TO         Once the certification of 50.82(a)2 IEB 8811:       ATAKE STEPS TO REDUCE FUTURE         were completed, TMI is no longer PRESSURIZER      (PRESSURIZER) SURGE LINE THERMAL     permitted to operate or place fuel SURGE LINE       CYCLES.                              in the reactor vessel, therefore the THERMAL                                               protection provided by this STRATIFICATION                                       commitment is no longer required.
DECEMBER 20, 1988

Commitment Change Summary Report                                                               Attachment Part B - Programmatic Commitments tied to Generic Communications                            Page 21 of 44 Table 2 (Continued)
Commitment       Commitment                  Commitment Details                    Basis for Deletion Tracking     Source Document Number 0112235561    C311922003:     GPUN COMMITTED TO THE NRC THAT:          Once the certification of STAFF REVIEW OF   1. STROKE TESTING IS PERFORMED AT        50.82(a)2 were completed, TMI is GL 9006          WYLE LABORATORIESA CERTIFIED OFFSITE    no longer permitted to operate or FACILITY IN ACCORDANCE WITH              place fuel in the reactor vessel, SPECIFICATION SP 110112087. TESTING IS therefore the protection provided PERFORMED AT NORMAL STEAM INLET          by this commitment is no longer CONDITIONS AND VERIFIES BOTH             required.
SETPOINTS; 2450 PSIG FOR POWER OPERATION AND 5592 PSIG FOR LTOP, CONDITIONS THAT ARE REPRESENTATIVE OF THE PORV OPERATING ENVIRONMENT.
: 2. 14012.1A, "REMOVE/INSTALL RCRV2 (PORV)" AND 13026.16 "SETPOINT AND REMOVE POSITION CHECK OF THE PORV (RCRV2)"," PROVIDES VERIFICATION OF PROPER REINSTALLATION OF THE PORV AND CONTROLS.
: 3. ALTHOUGH BENCH TESTING IS THE PREFERRED METHOD OF PORV TESTING, OPTM220203 PERMITS ACTUATION OF THE PORV IN PLACE AS AN ALTERNATIVE TEST METHOD. IN PLACE STROKE TESTING OF THE PORV USES STEAM AT RCS TEMPERATURE GREATER THAN 32913 DEGREES F AND RCS PRESSURE AT 500700 PSIG, CONDITIONS EQUIVALENT TO OR GREATER THAN STS MODE 3 AND MODE 4.
0112235562      C311932086      GPUN COMMITTED EXTERNALLY TO THE            Once the certification of IEB 9302: DEBRIS NRC IN RESPONSE TO BULLETIN 9302 THAT   50.82(a)2 were completed, TMI is PLUGGING OF           FIBROUS AIR FILTERS WHICH ARE      no longer permitted to operate or ECCS SUCTION       INSTALLED INSIDE CONTAINMENT ARE        place fuel in the reactor vessel, STRAINERS       PROTECTED FROM MIGRATING INTO THE       therefore the protection provided REACTOR BUILDING SUMP PRIOR TO, OR      by this commitment is no longer DURING A LOCA EVENT DUE TO ADEQAUTE                    required.
FILTER MAINTENANCE PROCEDURES, PROCEDURAL CONTROLS AND ENGINEERING EVALUATIONS WHICH DOCUMENT TEMPORARY SOURCES OF FIBROUS MATERIAL STORED IN CONTAINMENT, PROCEDURES WHICH REQUIRE REACTOR BUILDING WALKDOWNS AND INSPECTIONS PRIOR TO SETTING CONTAINMENT FOR PLANT OPERATIONS, AND PROCEDURAL CONTROLS

Commitment Change Summary Report                                                                Attachment Part B - Programmatic Commitments tied to Generic Communications                             Page 22 of 44 Table 2 (Continued)
Commitment       Commitment            Commitment Details                        Basis for Deletion Tracking     Source Document Number 0112235570   59280320148    The plant will develop a specific    Once the certification of 50.82(a)2 were SIXTYDAY        procedure for cleaning and           completed, TMI is no longer permitted to RESPONSE TO      inspecting the floor drains in       operate or place fuel in the reactor NRC BULLETIN     containment and will coordinate      vessel, therefore there is no need to 200301          this work with the containment       perform a containment close out closeout procedure.                  inspection. The protection provided by this commitment is no longer required.
0112235572   RESPONSE TO RAI  TMI will revise the site EOPs to     Once the certification of 50.82(a)2 were BULLETIN 2003 incorporate interim measures to      completed, TMI is no longer permitted to 01 "POTENTIAL    include initiating BWST refill after operate or place fuel in the reactor IMPACT OF        switchover to recirculation from the vessel, the need for LOCA protection in DEBRIS           containment sump.                    the RCS is no longer required.
BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED WATER REACTORS

Commitment Change Summary Report                                                                           Attachment Part C - Programmatic Commitments tied to Licensing Actions                                             Page 26 of 44 The following provides the update of programmatic commitments associated with Licensing Actions that impacted Technical Specifications (TS) that will be deleted based on the TMI-1 no longer being permitted to operate in accordance with 10 CFR 50.82(a)(2) and implementation of TS Amendment 297, which implemented the Permanently Defueled Technical Specifications.
Letter Source:                                           Various - Refer to Table 3 for each item Exelon Tracking Number                                   Various - Refer to Table 3 for each item Nature of Commitment:                                    Table 3 lists open programmatic regulatory commitments for Three Mile Island, Unit 1 (TMI1), that are related to licensing actions (e.g. LARs). Technical Specification Amendments 295 and 297 were implemented on September 27, 2019 and represents the Permanently Defueled Technical Specifications (PDTS). The table contains the commitment number, the commitment source, a summary of the commitment, and basis for the deletion of the commitment.
Each of the original regulatory commitments listed in Table 3 will be closed, since the actions are no longer applicable as a result of TMI1 being in a permanent shutdown state.
Justification for Change By letter dated September 26, 2019, Exelon provided certification that TMI1 was permanently shut down and defueled with all irradiated fuel being stored in the Spent Fuel Pool. In accordance with 10 CFR 50.82(a)2 TMI1 is no longer permitted to operate or place fuel in the reactor vessel. The only risk is the safe storage of irradiated fuel in the Spent Fuel Pool. The regulatory commitments in Table 3 no longer afford the original intent and protection. Table 3 provides additional basis for each action item.
Table 3 Programmatic Commitments tied to Licensing Actions that are no longer applicable based on Permanent Shutdown Status Commitment        Commitment          Commitment Details                              Basis for Deletion Tracking          Source Number            Document 0112207204       59280420162       TSCR NO. 326  ELIMINATION OF                   No longer permitted to perform TSCR NO. 326        CONTAINMENT EQUIPMENT HATCH                     fuel emplacement in the RPV. TS CLOSURE DURING REFUELING                        3.8 Fuel Loading and Refueling was Procedures will be in place which will          deleted in TS Amendment 297.
require the placement of continuously operated particulate and radioiodine air sampling equipment inboard of the open containment equipment hatch opening during fuel loading and refueling activities.

Commitment Change Summary Report                                                                  Attachment Part C - Programmatic Commitments tied to Licensing Actions                                    Page 27 of 44 Table 3 (Continued)
Commitment    Commitment      Commitment Details                         Basis for Deletion Tracking      Source Number        Document 0112207233   GQL0036         PERIODIC REACTOR COOLANT FLOW              Based on the fact that TMI is no longer TS AMENDMENT    VERIFICATION                               permitted to operate or place fuel in 17: NRC SER     Licensee committed to verify the           the vessel this verification would no DATED 5/18/76   reactor coolant flow rate will be verified longer be required. TS 3.5.1 for RPS every 6 months, plus or minus 30 days,     inputs and its associated SRs were to be done by the heat balance             deleted in Amendment 297.
technique described in the MetEd letter dated 4/8/76.
0112207245   NRC SER DATED   ATMOSPHERIC STEAM DUMP VALVES              With certification required by 50.82 8/28/81: ADV    SPURIOUS OPENING.                          submitted, TMI is no longer permitted SPURIOUS                                                   to operate or store fuel in the reactor OPENING UPON                                               vessel. TS 3.4.1 Decay Heat Removal LOSS OF NNI OR                                             with T>250F was deleted by ICS                                                        Amendment 297.
0112207267   5211832014    FHB ISOLATION DAMPER INTERLOCK             Technical Specification Amendment PERIODIC        TESTING                                    297 provided a new Fuel Handling TESTING OF AUX  Attachment(s): GPUN COMMITTED TO           Accident in the Spent Fuel Pool, and AND FHB         THE NRC TO REVISION OF THE                 concluded that Aux. Building and Fuel VENTILATION     SURVEILLANCE PROCEDURE (SP) 1303          Handling Building ESF Ventilation is not SYSTEM          4.15 TO INCLUDE THE TESTING OF THE         required for mitigation. TS 3.15.4 Fuel MODIFICATIONS   FUEL HANDLING BUILDING                     Handling Building ESF Air Treatment (FHB) ISOLATION DAMPER INTERLOCKS          System was deleted in TS Amendment WITH THE FHB VENTILATION SUPPLY            297.
FAN. THE EQUIPMENT WAS TESTED MONTHLY TO VERIFY PROPER OPERATION OF THE INTERLOCKS FOR THE ISOLATION DAMPERS AND THE SUPPLY FAN. THAT WAS ACCOMPLISHED BY SIMULATING A HIGH RADIATION SIGNAL FOR RMA4 (THE ATMOSPHERIC RADIATION MONITOR INTERLOCK) AND RMG9 (AREA RADIATION MONITOR INTERLOCK) WHICH TRIPPED THE FHB SUPPLY FAN AND CLOSED THE ISOLATION DAMPERS.
0112235525   5211962168    FUEL HANDLING BUILDING ESF                 Technical Specification Amendment TS AMENDMENT    VENTILATION SYSTEM Ensure system is       297 provided a new Fuel Handling 122: NRC SER    in service prior to Fuel Handling.         Accident in the Spent Fuel Pool, and DATED 12/12/86                                             concluded that Fuel Handling Building ESF Ventilation is not required for mitigation. TS 3.15.4 Fuel Handling Building ESF Air Treatment System was deleted in TS Amendment 297.

Commitment Change Summary Report                                                                    Attachment Part C - Programmatic Commitments tied to Licensing Actions                                      Page 28 of 44 Table 3 (Continued)
Commitment Commitment             Commitment Details                         Basis for Deletion Tracking       Source Document Number 0112235563 C311933140:         GPUN COMMITTED TO THE NRC TO               Once the certification of 50.82(a)2 TECH SPEC         INCORPORATE A MODIFIED BATTERY             were completed, TMI is no longer AMENDMENT 175      PERFORMANCE TEST AS DESCRIBED IN           permitted to operate or place fuel in IEEE STANDARD 4501993.                    the reactor vessel, implementation of the PDTS the electrical power system including the DC and battery systems are no longer safety related. TS 3.7 Electrical Power was deleted by Amendment 297.
0112235564 592800              99096 TSCR 283 DEGRADED GRID               Once the certification of 50.82(a)2 20120.001 TSCR     SETPOINT TOLERANCE AND TURBINE             were completed, TMI is no longer NO. 283  RAI      PLANT LOADING DESIGN LIMIT                 permitted to operate or place fuel in RESPONSE           REVISIONS.                                 the reactor vessel, implementation of CLARIFICATIONS                                                the PDTS the electrical power system PURSUANT TO                                                   including the Degraded Grid TELEPHONE                                                     protection are no longer safety CONFERENCE CALL                                               related. TS 3.5.3 was deleted by Amendment 297.
0112235567 59280120209         TMI Unit 1 Procedure 15051 will be        Once the certification of 50.82(a)2 RESPONSE TO       revised to reflect the proposed Technical were completed, TMI is no longer REQUEST FOR        Specification change and ensure            permitted to operate or place fuel in ADDITIONAL         continued awareness by the Shift           the reactor vessel. TS 3.6.1 INFORMATION       Operating/Refueling crews of the OPEN Containment Integrity was deleted by LICENSE            status of the containment during core      Amendment 297.
AMENDMENT          alterations and fuel handling.
REQUEST NO. 249 CONTAINMENT INTEGRITY DURING REFUELING OPERATIONS 0112235568 59280120209         Operating         Procedure      11013, Once the certification of 50.82(a)2 RESPONSE      TO "Containment Integrity and Access were completed, TMI is no longer REQUEST       FOR Limits," will be revised to provide for the permitted to operate or place fuel in ADDITIONAL         placement of continuously operated the reactor vessel. TS 3.6.1 INFORMATION       particulate and radioiodine air sampling Containment Integrity was deleted by LICENSE            equipment inboard open airlocks during Amendment 297.
AMENDMENT          core alteration and fuel handling REQUEST NO. 249 activities.
CONTAINMENT INTEGRITY DURING REFUELING OPERATIONS

Commitment Change Summary Report                                                                Attachment Part C - Programmatic Commitments tied to Licensing Actions                                  Page 29 of 44 Table 3 (Continued)
Commitment     Commitment      Commitment Details                        Basis for Deletion Tracking       Source Document Number 0112235569    59280230061   The NRC's Safety Evaluation based its     Once the certification of 50.82(a)2 SAFETY          acceptance of the tendon surveillance     were completed, TMI is no longer EVALUATION OF   and inspections as meeting the            permitted to operate or place fuel in PROCEDURES FOR  requirements of 10CFR50.55a(b)(2)(ix)     the reactor vessel, with PERFORMING      on the following AmerGen commitment       implementation of the PDTS the TS AND EVALUATING  from the 25th Year Tendon Surveillance    3.19 and SR 4.4.2 for RB Tendon THE REACTOR     Report (TR136) submittal dated           Surveillance were deleted in BUILDING        2/25/00 (59280020066): "the             Amendment 297.
TENDON          Mechanical/Structural Engineer shall SURVEILLANCE    perform continued monitoring of the (TAC NO.        grease leakage as part of its Repetitive MA9460)         Preventive Maintenance Task No.
9641." Therefore, performance of this PM Task becomes an ongoing commitment.
0112235571    59280510223   The asfound and asleft values will      Once the certification of 50.82(a)2 TSCR NO. 324   continue to be recorded and reviewed      were completed, TMI is no longer REACTOR         for consistency with the assumptions of   permitted to operate or place fuel in PROTECTION      the surveillance interval extension       the reactor vessel, the reaction SYSTEM TEST     analysis. The review will verify the test protection system is no longer INTERVAL        results meet acceptance criteria. Outof required to support protection of fuel EXTENSION       tolerance results will be                 clad and RCS pressure boundary. TS evaluated to determine if they meet the   3.5.1 was deleted by Amendment requirements outlined in BAW10167.       297.
0112235576    59280520253   Procedural controls will ensure that      Once the certification of 50.82(a)2 ADDITIONAL      during the movement of irradiated fuel    were completed, TMI is no longer INFORMATION    the Equipment Hatch/Missile Shield        permitted to operate or place fuel in TECHNCIAL       area will be manned 24 Hours/Day, 7       the reactor vessel, implementation of SPECIFICATION   Days/Week in support of the outage        the PDTS removed any controls or CHANGE          unless the Equipment Hatch is closed      constraints on refueling operations REQUEST NO. and 4 bolts are installed. The            since it no longer permitted. TS 3.8 326:            "committed date or outage" for this       Fuel Loading and Refueling was ELIMINATION OF  item is T1R16.                            deleted in TS Amendment 297.
CONTAINMENT EQUIPMENT HATCH CLOSURE DURING REFUELING

Commitment Change Summary Report                                                               Attachment Part C - Programmatic Commitments tied to Licensing Actions                                  Page 30 of 44 Table 3 (Continued)
Commitment     Commitment      Commitment Details                    Basis for Deletion Tracking       Source Document Number 0112235577    59280520253   TMI Unit 1 procedures will include    Once the certification of 50.82(a)2 were ADDITIONAL      the following requirements to         completed, TMI is no longer permitted to INFORMATION    ensure that General Design Criterion  operate or place fuel in the reactor TECHNCIAL       (GDC) 64 requirements will continue   vessel, implementation of the PDTS SPECIFICATION   to be met during the movement of      removed any controls or constraints on CHANGE          irradiated fuel:                      refueling operations since it no longer REQUEST NO.                                           permitted. TS 3.8 Fuel Loading and 326:                                                  Refueling was deleted in TS Amendment ELIMINATION OF                                        297.
CONTAINMENT EQUIPMENT HATCH CLOSURE DURING REFUELING 0112235578    59280720006   The VLPT Nominal Setpoint (NSP)       Once the certification of 50.82(a)2 were TSCR NO. 335   and Total Loop Uncertainty (TLU) are  completed, TMI is no longer permitted to REACTOR         determined using the methodology      operate or place fuel in the reactor COOLANT SYSTEM  provided by ANSI/ISAS67.04Part 1   vessel. TS 2.3 Limiting Safety System PRESSURE       1994. The predefined limits for NSP  Settings were deleted in Amendment TEMPERATURE     asfound tolerance will be            297.
SAFETY LIMITS   determined in accordance with the NRC accepted methodology described in NRC RIS 200617.
0112235581    59280720097   Install TSP buffer modification and   Once the certification of 50.82(a)2 were TECHNICAL       isolate NaOH tank BST2. At least    completed, TMI is no longer permitted to SPECIFICATION   one manual valve in each supply       operate or place fuel in the reactor CHANGE          train will be locked closed providing vessel, LOCA is no longer a credible DBA, REQUEST NO. 337 permanent isolation of the NaOH       therefore there is no need to provide "CHANGE OF    tank.                                 post LOCA ph control in containment. TS CONTAINMENT                                           3.3.1.3 RB Spray and RB Emergency EMERGENCY                                             Cooling System was deleted in SUMP SPRAY PH                                         Amendment 297.
CONTROL" 0112235582    59280720164   With regard to the VLPT setpoint      Once the certification of 50.82(a)2 were RESPONSE TO RAI calculation and the references of     completed, TMI is no longer permitted to TSCR # 335:   Sections 7 and 8 of Part 1 of ISA    operate or place fuel in the reactor REACTOR         S67.041994, TMI Unit 1 is in         vessel. TS 2.3 Limiting Safety System COOLANT SYSTEM  agreement with this Regulatory        Settings were deleted in Amendment PRESSURE       Position and commits to implement     297.
TEMPERATURE     Reg. Guide 1.105, Rev. 3.
SAFETY LIMIT

Commitment Change Summary Report                                                                      Attachment Part C - Programmatic Commitments tied to Licensing Actions                                         Page 31 of 44 Table 3 (Continued)
Commitment     Commitment         Commitment Details                      Basis for Deletion Tracking       Source Document Number 0112235583    59280720202      1) The elements and methodology         Once the certification of 50.82(a)2 were RESPONSE TO        of the proposed TS Table 4.15,         completed, TMI is no longer permitted to REQUEST FOR        Item 2.b surveillance testing will be   operate or place fuel in the reactor vessel, ADDITIONAL         clearly delineated in station           LOCA is no longer a credible DBA, INFORMATION       surveillance procedures.                therefore there is no need to provide post TECHNICAL          (Programmatic)                          LOCA ph control in containment. TS 3.3.1.3 SPECIFICATION      2) Procedures will ensure that          RB Spray and RB Emergency Cooling CHANGE             samples are taken within the basket     System was deleted in Amendment 297.
REQUEST NO.        at both interior and peripheral 337: REACTOR       locations to obtain a representative BUILDING           sample. (Programmatic)
EMERGENCY          3) Use of the WCAP 16530NP SUMP PH            model is being considered, and if CONTROL SYSTEM     utilized, this issue (ref. Q.9) will be BUFFER CHANGE      addressed in the TMI Unit 1 Generic Letter 200402 response. (One Time Action) 0112235593    59280820132      Control rod patch verification will     Once the certification of 50.82(a)2 were AmerGen Energy     be performed by moving each             completed, TMI is no longer permitted to Co. LLC (Exelon)   control rod to verify correct           operate or place fuel in the reactor vessel, to U. S. Nuclear   group/rod assignment following          inadvertent criticality or reactivity Regulatory         any software recompiling and            management is no longer a concern. SR Commission         download.                               4.7 Reactor Control Rod System Test were dated September                                            deleted in Amendment 297.
29, 2008. See also Technical Specification Amendment 273.
0256938101    TMI14121         TMI Periodic Leak Reduction             Once the certification of 50.82(a)2 were Response to        Program Incorporate a description       completed, TMI is no longer permitted to Request for        of the Periodic Leak Reduction          operate or place fuel in the reactor vessel, Additional         Program into the licensing basis by     since a LOCA is no longer a credible DBA, Information        revising UFSAR Section 6.4,             quantifying leakage into the Aux Building Regarding License  "Engineered Safeguards Leakage          in the event of sump recirculation Amendment          and Radiation Considerations."          exceeding Part 100 limits is no longer a Request to                                                 concern. SR 4.5.4 ESF system leakage was Eliminate Certain                                          deleted in Amendment 297.
Technical Specification Reporting Requirements.

Commitment Change Summary Report                                                                       Attachment Part D - Miscellaneous Programmatic Commitments                                                     Page 37 of 44 The following provides the update of Miscellaneous Programmatic Commitments that will be deleted based on the TMI-1 no longer being permitted to operate in accordance with 10 CFR 50.82(a)(2).
Letter Source:        5211872059 - LTR to NRC: RCPS Thermal Barrier Cooling and Injection.
C311882010 - LTR to NRC: 10 CFR 50 APPENDIX R LOSS OF HVAC Exelon Tracking       0112235527 Number                0112235530 Nature of             Both listed commitments are associated with compliance with 10 CFR 50, Appendix R.
Commitment:
0112235527  Reactor Coolant Pumps Appendix R exemption. The licensee committed to the NRC that in the event of a control room or relay room fires, mitigation response procedures to restore reactor coolant pump seal barrier coolant at the remote shutdown panel.
0112235530  10 CFR 50 Appendix R - Loss of HVAC. The licensee committed to monitor diesel engine parameters during diesel generator operations to ensure EDG is adequately cooled during loss of ventilation in the diesel rooms due to an Appendix R Fire.
Each of the original regulatory commitments will be closed, since the actions are no longer applicable as a result of TMI1 being in a permanent shutdown state.
Justification for Change By letter dated September 26, 2019, Exelon provided certification that TMI1 was permanently shut down and defueled with all irradiated fuel being stored in the Spent Fuel Pool. In accordance with 50.82(a)(2), TMI1 is no longer permitted to operate or place fuel in the reactor vessel. As a result, the requirements of 10 CFR 50.47.(b)(2) and Appendix R are no longer applicable and fire protection for a decommissioning plant is covered by 10 CFR 50.48(f).
Letter Source:        5211842015 LTR to NRC GL 8233 RESPONSE NUREG 0737 ITEM IC1 ATOG IMPLEMENTATION 5211842154  LTR to NRC: NUREG 0737 ITEM I.C.1 RESPONSE TO SER QUESTIONS Exelon Tracking       0112207264 Number                0112207277 Nature of             Both listed commitments are associated with implementation Abnormal Transient Commitment:           Operating Guidelines (ATOG) in Emergency Operating Procedures (EOPs).
0112207264 - Abnormal Transient Operating Guidelines (ATOGs). The licensee committed to the NRC that the ATOGs would be integrated into the Abnormal Transient Procedures, which ultimately become the EOPs. The guidance to follow the ATOGs was placed in AP 1001E, "Writers Guide for Abnormal Transient Procedures."
0112207277 - EOP Upgrade Program. The licensee committed to correct NRC concerns on Writers Guide Administrative Procedures for Abnormal Transient Procedures.
Justification for Change By letter dated September 26, 2019, Exelon provided certification that TMI1 was permanently shut down and defueled with all irradiated fuel being stored in the Spent Fuel Pool. In accordance with 50.82(a)(2), TMI1 is no longer permitted to operate or place fuel in the reactor vessel. As a result, the need for EOPs that meet the ATOGs are no longer necessary, since the transients in question are not applicable to a defueled facility that is no longer licensed to operate. In addition, the requirement to maintain a writer's guide procedure for the maintenance of these procedures is no longer required.

Commitment Change Summary Report                                                                       Attachment Part D - Miscellaneous Programmatic Commitments                                                     Page 38 of 44 Letter Source:         TMI15120 - LTR to NRC: Fleet Commitment to Maintain Severe Accident Management Guidelines (SAMGs)
Exelon Tracking        0261101222 Number Nature of              0261101222Fleet Commitment to Maintain Severe Accident Management Guidelines Commitment:            (SAMGs). The licensee committed to implement the Nuclear Energy Institute (NEI) Nuclear Strategic Issues Advisory Committee (NSIAC) approved initiative to implement SAMGs. The SAMGs would be used by emergency response personnel during accident conditions that progress beyond the mitigation capabilities described in EOPs. SAMG strategies are intended to arrest the progression of fuel damage, maintain the capability of the containment as long as possible, and minimize radiological releases.
The original regulatory commitment listed above will be closed, since the actions are no longer applicable as a result of TMI1 being in a permanent shutdown state.
Justification for Change By letter dated September 26, 2019, Exelon provided certification that TMI1 was permanently shut down and defueled with all irradiated fuel being stored in the Spent Fuel Pool. In accordance with 50.82(a)(2), TMI1 is no longer permitted to operate or place fuel in the reactor vessel. As a result, the need for EOPs that meet the ATOGs are no longer necessary, since the transients in question are not applicable to a defueled facility that is no longer licensed to operate. Therefore, the need to provide SAMGs to provide strategies to arrest the progression of fuel damage or maintain the capability of containment. Although the SAMGs provided spent fuel mitigation strategies in the event of a loss of water to the spent fuel pool, these Extensive Damage Mitigation Strategies to ensure water sources to the Spent Fuel Pool are already built into the Abnormal Operating procedure to address the loss of spent fuel pool cooling.
Letter Source:         TMI15120 - LTR to NRC: Response Providing Information Regarding Implementation Details for the B.5.b Phases 2 and 3 Mitigation Strategies Exelon Tracking        0112207215 Number                 0112207217 Nature of              112207215 B.5.b Commitments  Three Mile Island Nuclear Station Unit 1 will include the Commitment:            command and control enhancement strategies as described in the general description in Attachment 1 in plant procedures (Tables A.31) 112207217 B.5.b Commitments  Three Mile Island Nuclear Station Unit 1 will list the viable sitespecific reactor/containment strategies described in Attachment 1 that could be used by emergency response organization or plant personnel in appropriate procedures (Table A.6.1).
The original regulatory commitment listed above will be closed, since the actions are no longer applicable as a result of TMI1 being in a permanent shutdown state.
Justification for Change By letter dated September 26, 2019, Exelon provided certification that TMI1 was permanently shut down and defueled with all irradiated fuel being stored in the Spent Fuel Pool. In accordance with 50.82(a)(2), TMI1 is no longer permitted to operate or place fuel in the reactor vessel. The B.5.b commitments are part of the broader Extensive Damage Mitigation Strategies that are required by 10 CFR 50.155, Mitigation of beyonddesignbasis events. Pursuant to 50.155.(a)2(i), once the certifications described in 50.82 are submitted, the licensee need only comply with the by EDGM strategies associated with spent fuel pool cooling capabilities.

Commitment Change Summary Report                                                                         Attachment Part D - Miscellaneous Programmatic Commitments                                                        Page 39 of 44 Letter Source:         GPUN letters to NRC C311902073, 5211853262 and C311903248 concerning TMI Fire Brigade Training.
Exelon Tracking        0112235510 Number                 0112235557 Nature of              In letter to NRC, 5211853262 GPUN committed THAT INDIVIDUALS WHO SERVE ON THE Commitment:            FIRE BRIGADES OF BOTH UNIT 1 AND UNIT 2 ARE (1) COGNIZANT OF CHANGES IN THE FIRE PROTECTION PLAN, PROCEDURES, AND EQUIPMENT OF EACH UNIT (2) PARTICIPATED IN DRILLS ON BOTH UNITS (3) PERIODICALLY EVALUATED ON A SCHEDULE COMMENSURATE WITH CURRENT EVALUATION CRITERIA.
In C311902073, GPUN COMMITTED TO THE NRC THAT EACH FIRE BRIGADE MEMBER SHALL PARTICIPATE IN:
: 1) AT LEAST TWO DRILLS PER YEAR AT TMI1 TO REMAIN QUALIFIED
: 2) AT LEAST ONE DRILL PER YEAR FOR EACH TMI1 OPERATING SHIFT SHALL BE CONDUCTED IN TMI2.
THESE DRILLS SHALL BE SCHEDULED SUCH THAT AT LEAST ONE DRILL PER QUARTER TAKES PLACE IN TMI2.
In C311903248, dated 11/21/90, documents the NRC Staff review and approval of the GPU proposed commitment. The new commitment required one fire drill per shift per year in Unit 2.
These commitments will be closed. Training requirements for the Incipient Fire Brigade will conform to RG 1.191 and NFPA 600 requirements as described in the TMI Incipient Fire Brigade Evaluation. The TMI Fire Protection Program procedure 1038 will describe the training, qualification and drill requirements for the Incipient Fire Brigade.
Justification for Change In 1985 and 1990 when these commitments were made, the regulatory framework for Fire Protection was being developed. By 2000, NRC had issued Regulatory Guide 1.189 to provide guidance for Fire Protection at an operating facility. In May 2001, NRC issued Regulatory Guide 1.191 to provide guidance for compliance with 10CFR50.48(f) for a permanently defueled facility.
In September 2019, TMI1 was permanently defueled and the TMI1 Fire Hazards Analysis (9901745) was modified to ensure compliance with 10CFR50.48(f) and Regulatory Guide 1.191. In January 2020, the TMI2 Fire Protection Program Evaluation (9903017) was modified to ensure compliance with 10CFR50.48(f) and Regulatory Guide 1.191.
The operating plant requirements for fire brigade training will be maintained until the Incipient Fire Brigade is implemented. The Incipient Fire Brigade Evaluation (Technical Evaluation 421497115) identified how the requirements of RG 1.191 would be satisfied when TMI transitions to an Incipient Fire Brigade. This included fire brigade training, qualification and drill requirements.
The program requirements of Reg Guide 1.191 supersede the purpose for the original commitments. The original commitments should be eliminated when the Incipient Fire Brigade is implemented. The TMI Fire Protection program will continue to comply with Reg Guide 1.191.

Commitment Change Summary Report                                                                           Attachment Part E - Items Classified as no longer being Regulatory Commitments                                     Page 40 of 44 Letter Source:          NUREG1928, Safety Evaluation Report Related to the License Renewal of Three Mile Island Nuclear Station, Unit 1, Appendix A dated October 2009.
Exelon Tracking         See Table 4 Number Nature of               Table 4 list all of the open License Renewal Commitments provided in NUREG1928, Safety Commitment:             Evaluation Report Related to the License Renewal of Three Mile Island Nuclear Station, Unit 1, Appendix A dated October 2009.
Each of the original commitments listed in Table 4 will be reassigned as aging management items and no longer be categorized as regulatory commitments as they no longer meet the NEI definition of a regulatory commitment.
Justification for Change Upon approval of the license renewal license amendment request, the NRC issued a license condition to the TMI 1s Renewed Facility Operating License (2.c.(20)), that required that the regulatory commitments related to license renewal be incorporated into the station UFSAR. This condition was satisfied in Revision 20 of the UFSAR and provided in Appendix A of the TMI UFSAR. License Condition 2.c.(20) was deleted in TS Amendment 297, Permanently Defueled Technical Specifications. Since these items are no in the UFSAR, they are controlled under the 50.59 change process and reported to the NRC in accordance with 50.71(e).
Table 4 License Renewal Commitments ReClassified as No Longer being Regulatory Commitments Commitment                 Commitment                                          Commitment Details Tracking Number 0060357301        ASME Sec XI ISI IWB, IWC,         This assignment captures the License Renewal commitments and IWD Aging Mgmt                associated with the ASME Section XI Inservice Inspection, Subsections Program                           IWB, IWC, and IWD Aging Management Program (Reference TMI1 License Renewal Application sections A.2. 1.1 and B.2.1.1) 0060357302        Water Chemistry Aging             This assignment captures the License Renewal commitments Management Program                associated with the Water Chemistry Aging Management Program (Reference TMI1 License Renewal Application sections A.2.1.2 and B.2.1.2). When all of the sub assignments due on or before 4/19/2014 are completed, the due date for this assignment shall be changed to 4/19/2034.
0060357303        Reactor Head Closure Studs        This assignment captures the License Renewal commitments Aging Management                  associated with the Reactor Head Closure Studs Aging Management Program B.2.1.3                   Program (Reference TMI1 License Renewal Application sections A.2.1.3 and B.2.1.3) 0060357304        Boric Acid Corrosion Aging        This assignment captures the License Renewal commitments Management Program                associated with the Boric Acid Corrosion Aging Management Program (Reference TMI1 License Renewal Application sections A.2.1.4 and B.2.1.4) 0060357305        Ni Alloy Rx Head Nozzle           This assignment captures the License Renewal commitments Penetration AMP                   associated with the NickelAlloy Penetration Nozzles Welded to the Upper Reactor Vessel Closure Heads of Pressurized Water Reactors Aging Management Program (Reference TMI 1 License Renewal Application sections A.2.1.5 and B.2.1.5)

Commitment Change Summary Report                                                                 Attachment Part E - Items Classified as no longer being Regulatory Commitments                            Page 41 of 44 Table 4 (Continued)
Commitment           Commitment                                   Commitment Details Tracking Number 0060357306     FlowAccelerated          This assignment captures the License Renewal commitments Corrosion Aging           associated with the FlowAccelerated Corrosion Aging Management Management Program        Program (Reference TMI1 License Renewal Application sections A.2.1.6 and B.2.1.6) 0060357307     Bolting Integrity Aging   This assignment captures the License Renewal commitments Management Program        associated with the Bolting Integrity Aging Management Program (Reference TMI1 License Renewal Application sections A.2.1.7 and B.2.1.7) 0060357308     Steam Generator Tube      This assignment captures the License Renewal commitments Integrity Aging Mgmt      associated with the Steam Generator Tube Integrity Aging Program                   Management Program (Reference TMI1 License Renewal Application sections A.2.1.8 and B.2.1.8) 0060357309     OpenCycle Cooling        This assignment captures the License Renewal commitments Aging Management          associated with the OpenCycle Cooling Water System Aging Program                   Management Program (Reference TMI1 License Renewal Application sections A.2.1.9 and B.2.1.9). Includes implementation of programmatic work orders.
0060357310     ClosedCycle Cooling      This assignment captures the License Renewal commitments Aging Management          associated with the ClosedCycle Cooling Water System Aging Program                   Management Program (Reference TMI1 License Renewal Application sections A.2.1.10 and B.2.1.10). Includes implementation of programmatic work orders.
0060357311     Cranes & Hoists Aging     This assignment captures the License Renewal commitments Management Program        associated with the Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems Aging Management Program (Reference TMI 1 License Renewal Application Sections A.2.1.11 and B.2.1.11).
0060357312     Compressed Air            This assignment captures the License Renewal commitments Monitoring Aging Mgmt     associated with the Compressed Air Monitoring Aging Management Program                   Program (Reference TMI1 License Renewal Application sections A.2.1.12 and B.2.1.12). When all of the sub assignments due on or before 4/19/2014 are completed, the due date for this assignment shall be changed to 4/19/2034.). Includes implementation of programmatic work orders.
0060357313     Fire Protection Aging     This assignment captures the License Renewal commitments Management Program        associated with the Fire Protection Aging Management Program (Reference TMI1 License Renewal Application sections A.2.1.13 and B.2.1.13). Includes implementation of programmatic work orders.
0060357314     Fire Water System Aging   This assignment captures the License Renewal commitments Management Program        associated with the Fire Water System Aging Management Program (Reference TMI1 License Renewal Application sections A.2.1.14 and B.2.1.14). When all of the sub assignments due on or before 4/19/2014 are completed, the due date for this assignment shall be changed to 4/19/2034). Includes implementation of programmatic work orders.

Commitment Change Summary Report                                                                    Attachment Part E - Items Classified as no longer being Regulatory Commitments                              Page 42 of 44 Table 4 (Continued)
Commitment           Commitment                                     Commitment Details Tracking Number 0060357315     Aboveground Steel          This assignment captures the License Renewal commitments Tanks Aging                associated with the Aboveground Steel Tanks Aging Management Management Program         Program (Reference TMI1 License Renewal Application sections A.2.1.15 and B.2.1.15). Includes implementation of programmatic work orders.
0060357316     Fuel Oil Chemistry Aging   This assignment captures the License Renewal commitments Management Program         associated with the Fuel Oil Chemistry Aging Management Program (Reference TMI1 License Renewal Application sections A.2.1.16 and B.2.1.16). When all of the sub assignments due on or before 4/19/2014 are completed or extended, the due date for this assignment should be changed to 4/19/2034. Includes implementation of programmatic work orders.
0060357317     Reactor Vessel             This assignment captures the License Renewal commitments Surveillance Aging         associated with the Reactor Vessel Surveillance Aging Management Management Program         Program (Reference TMI1 License Renewal Application sections A.2.1.17 and B.2.1.17). Includes implementation of programmatic work orders.
0060357320     Buried Piping and Tanks    This assignment captures the License Renewal commitments Aging Management           associated with the Buried Piping and Tanks Inspection Aging Program                    Management Program (Reference TMI1 License Renewal Application sections A.2.1.20 and B.2.1.20). When all of the sub assignments due on or before 4/19/2024 are completed or extended, the due date for this assignment should be changed to 4/19/2034. Includes implementation of programmatic work orders.
0060357321     External Surfaces          This assignment captures the License Renewal commitments Monitoring Aging           associated with the External Surfaces Monitoring Aging Management Management Program         Program (Reference TMI1 License Renewal Application sections A.2.1.21 and B.2.1.21). Includes implementation of programmatic work orders.
0060357322     Internal Surfaces          This assignment captures the License Renewal commitments Inspection Aging           associated with the Inspection of Internal Surfaces in Miscellaneous Management Program         Piping and Ducting Components Aging Management Program (Reference TMI 1 License Renewal Application sections A.2.1.22 and B.2.1.22) When all of the specific commitment activities required to be performed by 4/19/2014 are completed, this commitment due date should be reset to coincide with the termination of the operating license in 2034. Includes implementation of programmatic work orders and volumetric Exams of SS of SCCs.
0060357323     Lubricating Oil Analysis   This assignment captures the License Renewal commitments Aging Management           associated with the Lubricating Oil Analysis Aging Management Program                    Program (Reference TMI1 License Renewal Application sections A.2.1.23 and B.2.1.23). Includes implementation of programmatic work orders.
0060357324     ASME Section XI,           This assignment captures the License Renewal commitments Subsection IWE Aging       associated with the ASME Section XI, Subsection IWE Aging Management Program         Management Program (Reference TMI1 License Renewal Application sections A.2.1.24 and B.2.1.24).

Commitment Change Summary Report                                                                  Attachment Part E - Items Classified as no longer being Regulatory Commitments                             Page 43 of 44 Table 4 (Continued)
Commitment           Commitment                                   Commitment Details Tracking Number 0060357325     ASME Section XI,          This assignment captures the License Renewal commitments Subsection IWL Aging      associated with the ASME Section XI, Subsection IWL Aging Management Program        Management Program (Reference TMI1 License Renewal Application sections A.2.1.25 and B.2.1.25) When all the implementing document changes required by 4/19/2014 have been made, the due date for this commitment should be changed to 4/19/2034, the end of the operating period.
0060357326     ASME Section XI,          This assignment captures the License Renewal commitments Subsection IWF Aging      associated with the ASME Section XI, Subsection IWF Aging Management Program        Management Program (Reference TMI1 License Renewal Application sections A.2.1.26 and B.2.1.26) When all of the procedure changes required by 4/19/2014 have been completed, reset the due date for this commitment to 4/19/2034, the end of the operating period.
0060357327     10 CFR Part 50,           This assignment captures the License Renewal commitments Appendix J Aging          associated with the 10 CFR Part 50, Appendix J Aging Management Management Program        Program (Reference TMI1 License Renewal Application sections A.2.1.27 and B.2.1.27).
0060357328     Structures Monitoring     This assignment captures the License Renewal commitments Program Aging             associated with the Structures Monitoring Program Aging Management Program        Management Program (Reference TMI1 License Renewal Application sections A.2.1.28 and B.2.1.28) When all of the assignments with due dates on or before 4/19/2014 have been completed, this assignment should be changed to 04/19/2034, the end of the operating period.
Includes implementation of programmatic work orders.
0060357329     Protective Coatings       This assignment captures the License Renewal commitments Aging Management          associated with the Protective Coating Monitoring and Maintenance Program                   Program Aging Management Program (Reference TMI 1 License Renewal Application sections A.2.1.29 and B.2.1.29). Includes implementation of programmatic work orders.
0060357330     NonEQ Cables and         This assignment captures the License Renewal commitments Connections Aging         associated with the Electrical Cables and Connections Not Subject to Management Program        10 CFR 50.49 Environmental Qualification Requirements Aging Management Program (Reference TMI 1 License Renewal Application sections A.2.1.30 and B.2.1.30) When all of the sub assignments due on or before 4/19/2014 are completed or extended, the due date for this assignment should be changed to 4/19/2034. Includes implementation of programmatic work orders.

Commitment Change Summary Report                                                                  Attachment Part E - Items Classified as no longer being Regulatory Commitments                            Page 44 of 44 Table 4 (Continued)
Commitment            Commitment                                  Commitment Details Tracking Number 0060357331      NonEQ Instrument        This assignment captures the License Renewal commitments Cables and Connections   associated with the Electrical Cables and Connections Not Subject to AMP                      10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits Aging Management Program (Reference TMI 1 License Renewal Application sections A.2.1.31 and B.2.1.31). When all of the sub assignments due on or before 4/19/2014 are completed or extended, the due date for this assignment should be changed to 4/19/2034. Includes implementation of programmatic work orders.
0060357332     Inaccessible Medium      This assignment captures the License Renewal commitments Voltage Cable AMP        associated with the Inaccessible Medium Voltage Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Aging Management Program (Reference TMI 1 License Renewal Application sections A.2.1.32 and B.2.1.32). Includes implementation of programmatic work orders.
0060357333     Metal Enclosed Bus       This assignment captures the License Renewal commitments Aging Management         associated with the MetalEnclosed Bus Aging Management Program Program                  (Reference TMI1 License Renewal Application sections A.2.1.33 and B.2.1.33). Includes implementation of programmatic work orders.
0060357335     Nickel Alloy Aging       This assignment captures the License Renewal commitments Management Program       associated with the Nickel Alloy Aging Management Program (Reference TMI1 License Renewal Application sections A.2.2.1 and B.2.2.1).
0060357336     PWR Vessel Internals     This assignment captures the License Renewal commitments Aging Management         associated with the PWR Vessel Internals Aging Management Program Program                  (Reference TMI1 License Renewal Application Section A.5 No. 36).
Includes Reactor Internals Inspection Plan.
0060357337     RC Pressure Boundary     This assignment captures the License Renewal commitments Metal Fatigue AMP        associated with the Metal Fatigue of Reactor Coolant Pressure Boundary Aging Management Program (Reference TMI1 License Renewal Application sections A.3.1.1 and B.3.1.1).
0060357338     Concrete Containment     This assignment captures the License Renewal commitments Tendon PreStress Aging   associated with the Concrete Containment Tendon Prestress Aging Mgmt Program             Management Program (Reference TMI1 License Renewal Application sections A.3.1.2 and B.3.1.2).
0060357339     EQ of Electrical         This assignment captures the License Renewal commitments Components Aging         associated with the Environmental Qualification (EQ) of Electrical Management Program       Components Aging Management Program (Reference TMI 1 License Renewal Application sections A.3.1.3 and B.3.1.3).
0060357343     Boral and Metamic Test   This assignment captures the License Renewal commitment Coupon Surveillance      associated with the Boral Test Coupon Surveillance as committed in RAI response letter # 59280820229 and the 2010 10 CFR 54.37b report identifying the Metamic fuel racks as a "newly identified SCC" that require aging management review.}}