RS-13-009, Clinton, Unit 1, Updated Licensing Basis Documents

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Clinton, Unit 1, Updated Licensing Basis Documents
ML13016A306
Person / Time
Site: Clinton Constellation icon.png
Issue date: 01/10/2013
From: Simpson P R
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
RS-13-009
Download: ML13016A306 (15)
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Text

\o4300 Winfield Road Warrenville, IL 60555 E E e n 630 657 2000 Office 10 CFR 50.4(b)(6) 10 CFR 50.71 (e)10 CFR 50.59(d)(2)

RS-13-009 January 10, 2013 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461

Subject:

Clinton Updated Licensing Basis Documents In accordance with the requirements of 10 CFR 50.71, "Maintenance of records, making of reports," paragraph (e)(4), Exelon Generation Company, (EGC), LLC submits Revision 15 to the Updated Safety Analysis Report (USAR) for Clinton Power Station.The USAR is being submitted on Optical Storage Media (OSM) in its entirety, including documents incorporated by reference (e.g., Operational Requirements Manual (ORM)).USAR pages changed as a result of this update are delineated with "REV. 15, JANUARY 2013" in the page footer.Changes to the USAR and ORM have been made under the provisions of 10 CFR 50.59,"Changes, tests, and experiments." EGC has evaluated these changes in accordance with 10 CFR 50.59 and concluded that the changes do not require prior NRC approval.Attachment A provides a brief summary of the changes incorporated into USAR Revision 15.Attachment B provides the required summary report pursuant to 10 CFR 50.59(d)(2).

Attachment C contains a summary of regulatory commitment changes.Attachment D summarizes the changes to the ORM.Attachment E contains the directory path, filename, and size of each individual file.AC)6-3 January 10, 2013 U. S. Nuclear Regulatory Commission Page 2 of 2 One DVD is included in this submission.

The DVD labeled, "Exelon Generation Clinton Station USAR Rev. 15 January 2013, ORM" contains the following components:

001 CPS USAR Rev 15.pdf, 727 megabytes (MB), publicly available 002 CPS ORM.pdf, 1.51 megabytes (MB), publicly available As Manager -Licensing, I certify that the information in this submittal accurately presents changes made since the previous submittal necessary to reflect information and analyses submitted to the NRC or prepared pursuant to NRC requirements, and changes made under the provisions of 10 CFR 50.59.There are no commitments made in this document.

Should you have any questions concerning this letter, please contact: Amy Hambly Exelon Nuclear 4300 Warrenville, IL 60555 Phone: (630) 657-2808 E-Mail: amy.hambly@exeloncorp.com Respectfully, Patrick R. Simpson Manager -Licensing Attachments Attachment A, "CPS USAR Revision 15 Change Summary Report" Attachment B, "10 CFR 50.59 Summary Report" Attachment C, "Summary of Regulatory Commitment Changes" Attachment D, "Summary of Operational Requirements Manual Changes" Attachment E, "OSM Directory Structure" cc: Regional Administrator

-NRC Region III NRC Senior Resident Inspector

-Clinton Power Station Attachment A CPS USAR Revision 15 Change Summary Report Page 1 of 3 USAR Change 2008-025 and 2008-029, Calculation IP-M-0734 was prepared to evaluate Loss of Offsite Power (LOOP) induced hydraulic transient loads in the Shutdown Service Water (SX) system. The results of the postulated water-hammer loads indicate that the upper levels of the SX system needed additional water hammer protection.

Added a 3/4 inch vacuum breaker assembly at the high point of both divisions of SX supply side. Engineering Change (EC) 369868 and EC 369622. 50.59 screen CL-2009-S-022.

USAR Change 2010-011, Stand-by Liquid Control valves 1 C41 F340B/ F341 B are redundant locked shut outboard Containment Isolation Valves (CIVs) for containment penetration 1 MC-1 16. A 2" diameter blind coupling was installed on the penetration line and the valves are abandoned in place. EC 371540. 50.59 screen CL-2010-S-022.

USAR Change 2010-014, Added clarifying information to the USAR description for Main Steam Isolation Valves (MSIVs) that the MSIV air accumulator piping and air volume downstream, including the accumulator check valves, are required to close the MSIVs in the required time. NEI 98-03 guidance.USAR Change 2010-016, Restored the Low Frequency Motor Generator (LFMG) auto start upon an End-of-Cycle Recirculation-Pump-Trip of the Reactor Recirculation Pumps.EC 369889. 50.59 screen CL-2010-S-037.

USAR Change 2010-020, Deleted references to USAR Tables 15.6.5-3 and 15.6.5-5 which had been removed from the USAR by previous change package 2005-031, as reported in Revision 12. NEI 98-03 guidance.USAR Change 2011-002, Fire Protection changes from a site self assessment.

Changes included a position title change, procedure reference correction, address annual invite to local fire departments, correction of a non-fire rated ceiling thickness.

Fire Protection Change Regulatory Review form.USAR Change 2011-003, Installed curbs at doorway to three radwaste tank rooms to contain leaks or spills. EC 382144.USAR Change 2011-004, Fire Protection hose stations and extinguishers location changes from a site self assessment.

Added detail on Fire Protection Evaluation Report fire zones. NEI 98-03 guidance.USAR Change 2011-005, Revised the References listed under Regulatory Guide 1.137,"Fuel Oil Systems for Standby Diesel Generators," to include stored fuel requirements per ANSI N195-1976, and for consistency with Section 9.5.4.1, "Design Bases for Diesel Generator Fuel Oil Storage and Transfer System." NEI 98-03 guidance.USAR Change 2011-006, Section 6.3.2.8, "Manual Actions," revised shift manager title to shift management, updated reference to currently used log system, and added the Offsite Dose Calculation Manual (ODCM) as a reference.

NEI 98-03 guidance.USAR Change 2011-007, Secondary Containment drawdown time changes per License Amendment 167. Conforming change per NEI 98-03 guidance.

Attachment A CPS USAR Revision 15 Change Summary Report Page 2 of 3 USAR Change 2011-008, Added the Resin Storage Building to the outdoor radioactive storage area table. NEI 98-03 guidance.USAR Change 2011-009, Addition of a new Security Ballistic Resistant Enclosure.

EC 383182. 50.59 screen CL-201 1-S-009.USAR Change 2011-010, Clarified the reference to ASME Section Xl subsections applicable to pump and valve testing and inspections in USAR Section 6.6.1 and 9.2.1.2.4.

NEI 98-03 guidance.USAR Change 2011-012, Foundation for Cycled Condensate Tank replacement at new location.

EC 384689 and CL-201 1-S-022.USAR Change 2011-013, Revised description of the capability of safety related continuous-duty motors to operate 10% above and below motor nameplate rating, rather than "rated voltage." Also used consistent nomenclature for voltage designations, added diesel generator rated output, Class 1 E buses nominal rating. Exelon correspondence RS-1 1-104, dated July 1, 2011, Supplemental Information Related to License Amendment Request to Remove Operating Mode Restrictions for Performing Division 2 AC Sources Surveillance Testing. Issue Report (IR) 1225436 and IR 1226340. NEI 98-03 guidance.USAR Change 2011-016, Increased the Low Population Zone Total Effective Dose Equivalent (TEDE) from 7.28 to 7.33 REM for a Loss of Coolant Accident using the Alternate Source Term methodology.

EC 368331. 50.59 screen CL-201 1-S-029.USAR Change 2011-017, Corrected typographical errors in Appendix F, "Fire Protection Evaluation Report." NEI 98-03 guidance.USAR Change 2011-018, Allowed hydrogen injection into the feedwater system at low reactor power. EC 382883. 50.59 screen CL-201 1-S-030.USAR Change 2011-019, Removed a USAR figure which was intended to be removed in Revision 13 by Change Package 2007-016.

Corrected a repagination error. NEI 98-03 guidance.USAR Change 2011-020.

Cycled Condensate Tank replacement at new location.EC 384690. 50.59 screen CL-201 1-S-023.USAR Change 20011-022, Transition to Global Nuclear Fuels (GNF2). EC 380009 and 50.59 screen CL-201 1-S-027.USAR Change 2011-023, Removed two diesel fuel oil instruments from safe shutdown list. EC 385501 and NEI 98-03 guidance.

Clarified that Thermo-Lag insulation is not required on all cable trays. IR 1187435 and NEI 98-03 guidance.USAR Change 2011-024, Corrected inconsistency within USAR for Reactor Vessel flange elevation on Figure 3.8-31. IR 1288921. NEI 98-03 guidance.USAR Change 2011-025, Change in fire load classification designation for fire zone R-1i due to installation of Radiation Protection Office. EC 376604.

Attachment A CPS USAR Revision 15 Change Summary Report Page 3 of 3 USAR Change 2011-026, Fuel Cycle 14 Reload Update. EC 382424. 50.59 screen CL-2011-S-041.

USAR Change 2011-027, Incorporateds General Electric analysis for operation with certain Balance of Plant equipment out-of-service.

EC 381804. 50.59 screen CL-201 1-S-049.USAR Change 2012-001, Corrected inconsistencies in the Balance of Plant list of active valves and pumps table in the USAR. IR 1102406. NEI 98-03 guidance.USAR Change 2012-002, Abandon-in-place radwaste baler. EC 386238. 50.59 screen CL-2012-S-009.

USAR Change 2012-003, Changed dosimeter discussion from "thermoluminescent dosimeter" to "dosimeter of legal record." NEI 98-03 guidance.USAR Change 2012-005, Changed Table 6.2-47, "Isolation Valve Summary for Lines Penetrating Containment" to show four Main Steam Isolation Valve drain lines position from Shut to Open. Correction of error from incorporation of previously approved USAR change package. NEI 98-03 guidance.USAR Change 2012-007, Fire Protection Multiple Spurious Operations Motor Operated Valve changes to remove power and open breaker. MOVs 1 E12-F037A

& B.EC 386186 and EC 386212 and 50.59 screen CL-2011 -S-035.USAR Change 2012-008, Added clarifying information on description of circulating water pump trip logic. IR 1355130 and NEI 98-03 guidance.

Reconfigured scram discharge volume level circuit to disconnect cables associated with the process computer.EC 338275 and NEI 98-03 guidance.USAR Change 2012-009, Revised ANSI/ANS 3.5 from 1993 to 2009 version; revised Regulatory Guide 1.149 from Revision 2 to Revision 4; and updated Security Manager title. NEI 98-03 guidance.USAR Change 2012-011, Installation of a portable fire extinguisher in the Turbine Building.

EC 388444 and 50.59 screen CL-2012-S-012.

USAR Change 2012-013, Updates from a facilities impact evaluation.

IR 1400982, IR 1403121, and IR 1387576. NEI 98-03 guidance.USAR Change 2012-014, Updated chemical list. EC 389012. NEI 98-03 guidance.USAR Change 2012-015, Corrected typographical errors in Adjusted Reference Temperature Table for reactor vessel shell welds. IR 1414169. NEI 98-03 guidance.USAR Change 2012-016, Corrected reference to ANSI/ANS 56.8. IR 1413280. NEI 98-03 guidance.

Attachment B 10 CFR 50.59 Summary Report Page 1 of 3 This attachment contains the 50.59 evaluation summaries for this reporting period.Activity Number / Title CL-201 1 -E-002: EC 383218, Defeat Main Turbine Thrust Bearing Wear Detector Trip.Description of Activity Temporary Modification EC 383218 provides a means to temporarily defeat the main turbine thrust bearing wear detector (TBWD) trip, computer points and annunciator inputs associated with oil pressure switches 1 PS-TOO04A

& -B and 1 PS-TOO05A

& -B.The work is performed in panel 1 PA06J and involves lifting one lead for pressure switch 1 PS-TOO04B and one lead for pressure switch 1 PS-TOO05B.

The associated Operation Technical Decision Making (OTDM) is for the operator to manually trip the turbine on high TBWD wear indication concurrently with high thrust bearing temperature.

Reason for Activity On November 5, 2010, during performance of section Turbine Online Tests, it was expected that the position meter for the Turbine Bearing Wear Detector would read approximately

+75 mils (-100 to +100 mil scale) during testing. The actual reading was only +55 mils. It should be noted that at this point the "Upper Test OK" light did illuminate, and all other indications were as expected.

Since the actual cause of the meter deflection has not been determined, leads are being lifted in panel 1 PA06J to prevent a spurious turbine trip because annunciator pressure switches 1 PS-TOO04A and 1 PS-TOO05A are in series with the trip pressure switches 1 PS-TO004B and 1 PS-TO005B respectively.

Bases for Not Requiring Prior NRC Approval The trip associated with the main turbine TBWD is for asset protection and does not have any impact on USAR safety analysis.

No safety related parameters or SSC's are impacted by this Temporary Modification.

The trips will be restored after the cause of the spurious alarm has been determined and repaired in the next scheduled refuel outage, C1 R1 3, or before. A full 50.59 evaluation is required due to the adverse impact on the USAR description of the TBWD in Section 10.2.2.5 Turbine Protection System.The turbine thrust bearing wear detectors and associated trip instrumentation are non-safety-related, are not credited with preventing a turbine missile, and are not relied upon to mitigate accidents or transients.

Temporarily removing the TBWD trip will not prevent safety-related SSC's from fulfilling their design functions.

Temporarily removing the TBWD trip will decrease the probability of an inadvertent turbine trip, an anticipated operational occurrence analyzed in the USAR, since false trips from spurious signals will be prevented.

The turbine-generator is not required to effect or support safe shutdown of the reactor or to mitigate the consequences of an accident.

Site PORC approved on May 2, 2011, meeting Number 11-007.

Attachment B 10 CFR 50.59 Summary Report Page 2 of 3 Activity Number / Title CL-201 1 -E-043: EC 382424, Application of TRACG04P, Version 4.2.60.3, for the purpose of Oscillation Power Range Monitor (OPRM) Setpoint Determination.

Description of Activity This activity addresses the use of the General Electric Hitachi (GEH) advanced multi-purpose NSSS thermal-hydraulic transient code TRACG04P for the purpose of determining the OPRM setpoints for CPS. TRACG04P is a revised edition of the NRC approved TRACG02 used previously to determine the OPRM setpoints.

The TRACG04P code has not been generically approved by the NRC for OPRM setpoint determinations.

Therefore, use of the TRACG04P code constitutes a change in methodology.

Reason for Activity OPRM setpoints are determined for each operating cycle as part of the standard reload licensing process performed in accordance with General Electric Standard Application for Reactor Fuel (GESTAR II) methodology.

The cycle specific OPRM setpoints are included in the Core Operating Limits Report (COLR).Bases for Not Requiring Prior NRC Approval Benchmark testing between the TRACG02 version and the TRACG04P version of the code has shown that TRACG04P is slightly more conservative than the NRC approved TRACG02 version.The Reload Core Fuel Change Package identifies the physical changes to plant configuration to be made during a refueling outage and is performed to document compliance of the new reload design with GESTAR II. Additionally, the core operating limit values contained in the COLR are generated using NRC approved codes and methodologies and were designed to meet all fuel design/licensing criteria, which will continue to limit operation of the fuel to within the USAR analyses.

This evaluation has determined that the TRACG04P code produces results that are essentially the same as the NRC approved TRACG02 code. Therefore, TRACG04P may be applied without prior NRC approval.

Site PORC approved on December 9, 2011, meeting Number 11-030.

Attachment B 10 CFR 50.59 Summary Report Page 3 of 3 Activity Number / Title CL-2012-E-002:

EC 386215, Multiple Spurious Operation (MSO) Modification to open the breaker for Motor Operated Valve (MOV) 1 E12F094, and install an alarm bypass switch on the Motor Control Center (MCC) cubicle door to defeat the out-of-service alarm.Description of Activity This activity removes the electrical power to MOV 1 El 2F094 in the closed position.

The valve is on the Shutdown Service Water (SX) to Residual Heat Removal (RHR) cross-tie line. This activity also installs a switch at the MCC in the alarm circuit that is used to defeat the valve out-of-service alarm. A placard is installed to designate the valve as closed with power removed. This was identified during review of MSO scenario 2P. The valve is normally closed and is changed to closed with electrical power removed.Reason for Activity This activity is in response to NRC Enforcement Guidance Memorandum 09-002 and Regulatory Guide 1.189, Revision 2. A postulated fire can potentially initiate multiple hot shorts that could result in spurious repositioning of an MOV and possible damage to the valve could occur if it were driven past the torque switch cut off point Bases for Not Requiring Prior NRC Approval During the 1 OCFR 50.59 review process it was determined that removal of the power to this valve will adversely affect one of the USAR described SX functions of providing makeup to the Reactor, Suppression Pool, and Containment through the "B" train RHR system. A full 50.59 Evaluation was performed and it was concluded that removing the power to this valve and installing the alarm switch will not increase the frequency of any accident, or the likelihood or consequences of an accident or malfunction of equipment.

The SX to RHR crosstie line is not taken credit for in any accidents or malfunctions of equipment evaluated in the USAR, and removing the power to this valve will not cause any new types of accidents or malfunctions, or types of accidents or malfunctions with different results. The change does not affect any fission product barrier limits or cause one to be exceeded.

Removal of the power to the valve will ensure SX flow diversion, and its associated consequences, does not occur. There are no USAR described evaluation methodologies that include opening this valve or operating this line. The valve is normally closed, and its safety function in the event of an accident is to remain closed to ensure SX flow is directed to the required place. This change does not include the use of an alternative evaluation methodology used to establish the design bases or used in the safety analyses.

Removing the power and preventing spurious operation of the valve ensures that the post fire required actions can be taken to bring the reactor to a safe shutdown condition.

Operating the plant with power removed from this normally closed valve is not inconsistent with any analyses in the USAR. This change will not cause operation of the valve outside its reference bounds of design. Site PORC approved on March 6, 2012, meeting Number 12-004.

Attachment C Summary of Regulatory Commitment Changes Page 1 of 4 Existing Commitment Description 2011-001.

The Extensive Damage Mitigation Guide (EDMG) will specify a preferred location for plant personnel to muster in the event that plant evacuation did not occur per the imminent threat procedure.

Since pre-warning did not occur, station personnel are assumed to be in the plant. The Maintenance Shop was selected as the preferred mustering location because of its distance from safety related equipment and its proximity to an outside door.The EDMG will require a member of the Security Force to muster with the other site personnel and it will require the Security Force to enable operator access to areas required for the initial response.Revised Commitment Description The EDMG will specify a preferred location for plant minimum staffing personnel to muster in the event that plant evacuation did not occur per the imminent threat procedure.

Since pre-warning did not occur, station personnel are assumed to be in the plant. The Outage Control Center (OCC) on the third floor of the Administration Building was selected as the preferred mustering location because of its distance from safety related equipment and its proximity to an outside door.The EDMG will require the individual with command and control to contact Security at the Central Alarm Station to coordinate the Operations and Security responses and it will require the Security Force to enable operator access to areas required for the initial response.Justification The OCC is a normal location for personnel to staff when a plant issue occurs and EDMG procedures are located in this facility.

In addition, identification card readers that are used for accountability are located in the OCC if required.

Due to Security Force Member response requirements per the Security Plan, personnel may not always be available to respond to the muster area. Operations and Security personnel response and support for operator access needs can adequately be coordinated through the Central Alarm Station.

Attachment C Summary of Regulatory Commitment Changes Page 2 of 4 Existing Commitment Description 2011-002.

Periodic sampling of the Co-60 activity in the reactor coolant should be performed to monitor the integrity of the Co-59/Co-60 target rods.Revised Commitment Description Delete commitment.

Justification A review of correspondence to the NRC related to License Amendment 190 did not identify any docketed regulatory commitment on this subject. This was validated with Corporate Licensing for License Amendment 190. The definition of a regulatory commitment as provided in Exelon procedure LS-AA-1 10, "Commitment Management," Step 2.5 is: "An explicit statement to take a specific action agreed to or volunteered by Exelon Nuclear and submitted in formal written regulatory correspondence to the NRC by authorized management." On this basis this issue is not a valid regulatory commitment.

In addition, the NRC expectation stated in the SE for "Periodic sampling of the Co-60 activity in the reactor coolant" is already being performed by the station as a routine activity on a weekly basis in accordance with the frequencies defined in Exelon procedure CY-AB-1 20-100, "Reactor Water Chemistry." This procedure defines the requirements for the Reactor Water Chemistry control program that are based on industry guidance and Exelon has no plans to eliminate this routine sampling and analysis activity.

Therefore, there is no need to track this issue as a regulatory commitment Attachment C Summary of Regulatory Commitment Changes Page 3 of 4 Implementation of GL 2008-01 was five days late. (IR 1301272)Condition

==

Description:==

On December 7, 2011, during an NRC commitment audit, the NRC Project Manager (PM) questioned if NRC notification should have been made for a commitment that was not implemented by the date committed in the Exelon response to Generic letter 2008-01, which committed to completing procedure revisions by 1/9/09. The procedure revisions were not completed until 1/14/09 due to errors in extending the commitment due date in the action tracking item. The Senior Resident Inspector was notified at that time of the late completion and had no concerns, and completing the commitments 5 days late also had no other adverse affects.IR 867053 dated 1/15/09, identified this deficiency and the gaps in performance, and actions were completed to close the gaps. No NRC notification was completed at the time of the issue since the revision of Exelon Procedure LS-AA-1 10, "Commitment Management," Revision 6, in effect at the time had guidance for NRC notification when a due date extension is needed (known in advance), but had no guidance on notifications when a commitment was found to have been completed late and the commitment was already implemented.

The Corporate Commitment Coordinator discussed this issue with the NRC PM and they agreed that neither LS-AA-1 10 nor NEI 99-04, "Guidelines for Managing NRC Commitment Changes," address this type of issue but that the station should document the late completion for implementing the procedures in the commitment changes section of the next USAR update.

Attachment C Summary of Regulatory Commitment Changes Page 4 of 4 Existing Commitment Description 2012-001.

In response to NRC Generic Letter (GL) 96-05, Clinton Power Station (CPS)committed to implement the Joint Owners Group (JOG) Program for Motor Operated Valve (MOV) Periodic Verification (PV), as described in the Boiling Water Reactor Owner's Group Topical Report NEDC-32719.

The results and final requirements of which are documented in report MPR-2524-A Rev. 1 (Final). However, not all GL 96-05 MOV Program Valves are covered in the scope of the Final JOG Program. This was not known when the original commitment was made.Revised Commitment Description At CPS a number of GL 96-05 MOV Program Valves are not covered by the Final JOG Program Report (MPR-2524-A) such that JOG MOV PV evaluations for service related degradation effects are not directly applicable.

GL 96-05 MOVs not within the scope of the JOG MOV PV Final Report are referred to as JOG Class D MOVs. Per the final report, individual plants are responsible for justifying the PV approaches for Class D MOVs. This change serves as notification to the NRC of the CPS approach to comply with GL 96-05 for Class D valves.Applicable to: Unbalanced Globe Valve -1 E51 F076 -This unbalanced globe valve is classified as JOG Class D due to being in a Steam, Air, or Nitrogen system with flow rates greater than 86 ft/sec.Plug Valves -1 SX01 3A/B/C --These valves are classified as Class D due to being plug valves.Butterfly Valves -1CC075A/B, 1CC076A/B, 1 FC016A/B, IFC024A/B, 1 HGO01, 1 HGO04, 1 HGO05, 1 HG008, 1 SM001 A/B, 1 SM002A/B, 1 SX006C, 1 SX008A/B/C, 1 SX01 2A/B, 1 SX01 4A/B/C, 1 SX020A/B, 1 SX062A/B and 1 SX063A/B -These valves are classified as Class D due to Microseal

/ Melanite treated 316 SS bearings.Engineering assessment concluded that the configuration and application of these valves, their similarity to other valves in the JOG Program and the conservatisms used in assessing their valve factor capability preclude susceptibility to unexpected performance degradation.

Therefore, these valves can continue to be tested in accordance with the requirements of Class "B" valves under the updated JOG PVT Program. This assessment was performed using the guidance documented in BWROG-TP-09-033 Rev. 1, dated 12/22/09, "Generic Methodology for JOG MOV Periodic Verification (PV)Program-Category D MOV Evaluations." Justification The JOG Class D MOVs have been installed at CPS since original construction and tested in accordance with the requirements of Generic Letters 89-10 and 96-05. CPS is following the JOG program requirements to develop and justify an alternative method to address service related degradation.

This change is in accordance with the guidance provided in NRC Regulatory Issue Summary 2011-13, "Follow Up To Generic Letter 96-05 For Evaluation Of Class D Valves Under Joint Owners Group Motor-Operated Valve Periodic Verification Program."

Attachment D Summary of Operational Requirements Manual Changes Page 1 of 2 The following revisions to the Clinton Power Station (CPS) Operational Requirements Manual (ORM) have been made in accordance with approved station procedures.

Changes to the ORM are reviewed per 10 CFR 50.59. These changes have been implemented since the submittal of the CPS USAR Revision 14 to the NRC, through December 1, 2012.Revision Scope of Revision Number Revision 70

Adopt 2004 Edition, no Addenda of the ASME OM Code -Subsections ISTA and ISTD for IS[ Examination of snubbers and relocation of certain Snubber Program requirements from ORM to site-specific procedure.

50.59 screening CL-201 1-S-013.* 2.5.2 Motor Operated Valve Thermal Overload Protection.

Change the frequency of verification for the Motor Operated Valve Thermal Overload Bypass Protection function from: "At least once every 24 months" to "At least once every 6 years" to align with the associated breaker Preventive Maintenance schedule.

50.59 screening CL-201 1-S-011.Revision 71

  • 2.6.3 Refueling Platform.

Deleted Refueling Bridge down travel mechanical cutoff on the main hoist. This interlock is intended to stop the hoist lower motion when the full limits of down travel have been reached. The main hoist position encoder provides redundancy to the mechanical down travel cutoff which senses hoist position and stops the hoist when it reaches full down limit. EC 385900 and 50.59 screening CL-201 1-S-038.* Attachment 2, Trip Setpoint Tables. Table 17, Nominal Trip Setpoints,'

clarification to separate Reactor Vessel Pressure -low pressure injection permissive setpoint values by pressure transmitter group. Calculation IP-C-0062.Revision 72

Raised setpoint to accommodate drift. EC 373775 and 50.59 screening CL-2010-S-038.

Revision 73

Attachment D Summary of Operational Requirements Manual Changes Page 2 of 2 Revision 74

  • Section 2.1, Control Rod Drive Housing Support. Correct typographical error in Update Safety Analysis Report section. NEI 98-03 guidance.* Section 2.2.11, Main Condenser Off gas Treatment System Explosive Gas Monitoring Instrumentation.

Remove Action c. "The provisions of Operational Requirements 1.2.3 and 1.2.4 are not applicable." Improve wording after benchmarking other Exelon sites. IR 1261258.* Section 2.4.1 Snubbers.

Remove 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> snubber removal allowance.

IR 1324828 and IR 1338297. NEI 98-03 guidance.* Attachment 4, Containment Isolation Valves (CIVs). Remove abandoned Standby Liquid Control (SLC) valves from CIV list completely, rather than by note which was completed by Revision 73. EC 371540 and 50.59 screening CL-201 0-S-022.Revision 75 o Attachment 1, Remote Shutdown System Controls, and Attachment 4, Containment Isolation Valves. Multiple Spurious Operations (MSO)modification to Residual Heat Removal (RHR) system valves 1 El 2F037A & B.RHR to Containment Pool Cooling Isolation Valves will be closed and remove electric power. ECs 386186 and 386212. 50.59 screening CL-201 1-S-035 Revision 1.* Attachment 1, Remote Shutdown System Controls.

MSO modification to Shutdown Service Water (SX) system valves 1 SX003A and 1 SX004A to open valves and remove electric power. EC 386210.

Attachment E OSM Directory Structure Page 1 of 1 All files listed- below are oubliclv .........

,,o,,, .. .......... .. Directory, Path File Name' Site~E:\001 CPS USAR Rev 15 000 USAR Cover and LOEP.pdf 424 KB E:\001 CPS USAR Rev 15 001 CH 01 Intro and General Desc.pdf 968 KB E:\001 CPS USAR Rev 15 002 CH 02 Site Characteristics.pdf 1583 KB E:\001 CPS USAR Rev 15 003 CH 02 Figures Part 1 of 5.pdf 23175 KB E:\001 CPS USAR Rev 15 004 CH 02 Figures Part 2 of 5.pdf 23489 KB E:\001 CPS USAR Rev 15 005 CH 02 Figures Part 3 of 5.pdf 40490 KB E:\001 CPS USAR Rev 15 006 CH 02 Figures Part 4 of 5.pdf 29233 KB E:\001 CPS USAR Rev 15 007 CH 02 Figures Part 5 of 5.pdf 7718 KB E:\001 CPS USAR Rev 15 008 CH 03 Design of Struct Comp Equip.pdf 3836 KB E:\001 CPS USAR Rev 15 009 CH 03 Figures 3.3-1 thru 3.5-6.pdf 1985 KB E:\001 CPS USAR Rev 15 010 CH 03 Figure 3.6-1 Part 1 of 9.pdf 39748 KB E:\001 CPS USAR Rev 15 011 CH 03 Figure 3.6-1 Part 2 of 9.pdf 37239 KB E:\001 CPS USAR Rev 15 012 CH 03 Figure 3.6-1 Part 3 of 9.pdf 45495 KB E:\001 CPS USAR Rev 15 013 CH 03 Figure 3.6-1 Part 4 of 9.pdf 34492 KB E:\001 CPS USAR Rev 15 014 CH 03 Figure 3.6-1 Part 5 of 9.pdf 46280 KB E:\001 CPS USAR Rev 15 015 CH 03 Figure 3.6-1 Part 6 of 9.pdf 29362 KB E:\001 CPS USAR Rev 15 016 CH 03 Figure 3.6-1 Part 7 of 9.pdf 39270 KB E:\001 CPS USAR Rev 15 017 CH 03 Figure 3.6-1 Part 8 of 9.pdf 30180 KB E:\001 CPS USAR Rev 15 018 CH 03 Figure 3.6-1 Part 9 of 9.pdf 37779 KB E:\001 CPS USAR Rev 15 019 CH 03 Figures 3.6-2 thru 3.6-16.pdf 776 KB E:\001 CPS USAR Rev 15 020 CH 03 Figure B3.6 and D3.6 series.pdf 24820 KB E:\001 CPS USAR Rev 15 021 CH 03 Figures 3.7-1 thru 3.11-16.pdf 21781 KB E:\001 CPS USAR Rev 15 022 CH 04 Reactor.pdf 2873 KB E:\001 CPS USAR Rev 15 023 CH 05 RCS and Connect Systems.pdf 3003 KB E:\001 CPS USAR Rev 15 024 CH 06 Engineered Safety Features.pdf 18803 KB E:\001 CPS USAR Rev 15 025 CH 07 Instrument and Control Sys.pdf 6198 KB E:\001 CPS USAR Rev 15 026 CH 08 Electric Power.pdf 1198 KB E:\001 CPS USAR Rev 15 027 CH 09 Auxiliary Systems.pdf 3762 KB E:\001 CPS USAR Rev 15 028 CH 10 Steam and Power Conv.pdf 1022 KB E:\001 CPS USAR Rev 15 029 CH 11 Radioactive Waste Mgmt.pdf 1604 KB E:\001 CPS USAR Rev 15 030 CH 12 Radiation Protection.pdf 2512 KB E:\001 CPS USAR Rev 15 031 CH 13 Conduct of Operations.pdf 583 KB E:\001 CPS USAR Rev 15 032 CH 14 Initial Test Program.pdf 963 KB E:\001 CPS USAR Rev 15 033 CH 15 Accident Analysis.pdf 8273 KB E:\001 CPS USAR Rev 15 034 CH 16 Technical Specifications.pdf 43 KB E:\001 CPS USAR Rev 15 035 CH 17 Quality Assurance.pdf 52 KB E:\001 CPS USAR Rev 15 036 APP A Glossary.pdf 94 KB E:\001 CPS USAR Rev 15 037 APP B Const Matl Stds and QC.pdf 152 KB E:\001 CPS USAR Rev 15 038 APP C Computer Programs.pdf 7112 KB E:\001 CPS USAR Rev 15 039 APP D TMI Requirements.pdf 2387 KB E:\001 CPS USAR Rev 15 040 APP E Fire Protection Report.pdf 1050 KB E:\001 CPS USAR Rev 15 041 APP E Figures Part 1 of 2.pdf 37196 KB E:\001 CPS USAR Rev 15 042 APP E Figures Part 2 of 2.pdf 33701 KB E:\001 CPS USAR Rev 15 043 APP E Figures Cable Tray Dwgs.pdf 49156 KB E:\001 CPS USAR Rev 15 044 APP F Safe Shutdown.pdf 43325 KB E:\002 CPS ORM 001 CPS ORM.pdf 1548 KB

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