Text

Issuance of Amendment No. 213, Adopt Technical Specification Task Force Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation
	ML15258A510
Person / Time
Site:	Callaway
Issue date:	10/28/2015
From:	Klos L; Plant Licensing Branch IV
To:	Diya F; Union Electric Co
	Klos L
References
	CAC MF5856, GL-08-001
	Download: ML15258A510 (58)
	v • d • e

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 28, 2015 Mr. Fadi Diya Senior Vice President and Chief Nuclear Officer Union Electric Company P.O. Box 620 Fulton, MO 65251

SUBJECT:

CALLAWAY PLANT, UNIT 1 - ISSUANCE OF AMENDMENT RE:

REVISION OF TECHNICAL SPECIFICATIONS TO ADOPT TSTF-523-A, REVISION 2, "GENERIC LETTER 2008-01, MANAGING GAS ACCUMULATION" (CAC NO. MF5856)

Dear Mr. Diya:

The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the enclosed Amendment No. 213 to Renewed Facility Operating License No. NPF-30 for the Callaway Plant, Unit 1. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated March 12, 2015.

The amendment revises the TS requirements to address NRC Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems," as described in Technical Specification Task Force (TSTF)

Traveler TSTF-523, Revision 2, "Generic Letter 2008-01, Managing Gas Accumulation."

A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Klos, Project Manager Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-483

Enclosures:

1. Amendment No. 213 to NPF-30

2. Safety Evaluation cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 DOCKET NO. 50-483 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 213 License No. NPF-30

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Union Electric Company (UE, the licensee),

dated March 12, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

Enclosure 1

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-30 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan*

The Technical Spec!fications contained in Appendix A, as revised through Amendment No. 213 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This amendment is effective as of its date of issuance, and shall be implemented within 90 days of the date of issuance.

FOR THE NUCLEAR REGULA TORY COMMISSION

~~~

Michael T. Markley, Chief*

Plant Licensing Branch IV-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License No. NPF-30 and Technical Specifications Date of Issuance: October 28, 2015

ATTACHMENT TO LICENSE AMENDMENT NO. 213 RENEWED FACILITY OPERATING LICENSE NO. NPF-30 DOCKET NO. 50-483 Replace the following pages of the Renewed Facility Operating License No. NPF-30 and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Renewed Facility Operating License REMOVE INSERT Technical Specifications REMOVE INSERT Table of Contents - pages 2 to 3 Table of Contents - pages 2 to 3 3.4-11 to 3.4-45 3.4-11 to 3.4-46 3.5-5 3.5-5 3.6-19 to 3.6-22 3.6-19 to 3.6-23 3.9-10 3.9-10 3.9-13 3.9-13

(3) UE, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) UE, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source of special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) UE, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level UE is authorized to operate the facility at reactor core power levels not in excess of 3565 megawatts thermal (100% power) in accordance with the conditions specified herein.

(2) Technical Specifications and Environmental Protection Plan*

The Technical Specifications contained in Appendix A, as revised through Amendment No. 213 and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Environmental Qualification (Section 3.11, SSER #3)**

Deleted per Amendment No. 169.

Amendments 133, 134, & 135 were effective as of April 30, 2000 however these amendments were implemented on April 1, 2000.

- The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

Renewed License No. NPF-30 Amendment No. 213

TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued) 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation .......................................................................... 3.3-59 3.3.6 Containment Purge Isolation Instrumentation ................................. 3.3-61 3.3.7 Control Room Emergency Ventilation System (CREVS)

Actuation Instrumentation ......................................................... 3.3-67 3.3.8 Emergency Exhaust System (EES) Actuation Instrumentation ......................................................................... 3.3-73 3.3.9 Boron Dilution Mitigation System (BDMS) ...................................... 3.3-79 3.4 REACTOR COOLANTSYSTEM (RCS) ................................................ 3.4-1 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ................................................... 3.4-1 3.4.2 RCS Minimum Temperature for Criticality ....................................... 3.4-3 3.4.3 RCS Pressure and Temperature (PIT) Limits .................................. 3.4-4 3.4.4 RCS Loops - MODES 1 and 2 ......................................................... 3.4-6 3.4.5 RCS Loops - MODE 3 ..................................................................... 3.4-7 3.4.6 RCS Loops - MODE 4 ..................................................................... 3.4-10 3.4.7 RCS Loops - MODE 5, Loops Filled ................................................ 3.4-13 3.4.8 RCS Loops - MODE 5, Loops Not Filled ......................................... 3.4-16 3.4.9 Pressurizer ....................................................................................... 3.4-18 3.4.10 Pressurizer Safety Valves ................................................................ 3.4-20 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) ...................... 3.4-22 3.4.12 Cold Overpressure Mitigation System (COMS) .................. : ............ 3.4-26 3.4.13 RCS Operational LEAKAGE ............................................................ 3.4-31 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage ................................ 3.4-33 3.4.15 RCS Leakage Detection Instrumentation ........................................ 3.4-37 3.4.16 RCS Specific Activity ....................................................................... 3.4~41 3.4.17 Steam Generator (SG) Tube Integrity .............................................. 3.4-44 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ........................... 3.5-1 3.5.1 Accumulators ................................................................................... 3.5-1 3.5.2 ECCS - Operating ........................................................................... 3.5-4 3.5.3 ECCS - Shutdown ............................................................................ 3.5-7 3.5.4 Refueling Water Storage Tank (RWST) ......................................... 3.5-9 3.5.5 Seal Injection Flow ........................................................................... 3.5-11 3.6 CONTAINMENT SYSTEMS ......... ,........................................................ 3.6-1 3.6.1 Containment ................................................................................... 3.6-1 3.6.2 Containment Air Locks ..................................................................... 3.6-3 3.6.3 Containment Isolation Valves ......................................................... 3.6-7 CALLAWAY PLANT 2 Amendment 213

TABLE OF CONTENTS 3.6 CONTAINMENT SYSTEMS (continued) 3.6.4 Containment Pressure ..................................................................... 3.6-16 3.6.5 Containment Air Temperature ......................................................... 3.6-17 3.6.6 Containment Spray and Cooling Systems ...................................... 3.6-18 3.6.7 Recirculation Fluid pH Control (RFPC) System ............................... 3.6-22 3.7 PLANT SYSTEMS ................................................................................. 3.7-1 3.7.1 Main Steam Safety Valves (MSSVs) ............................................... 3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs), Main Steam Isolation Valve Bypass Valves (MSIVBVs), and Main Steam Low Point Drain Isolation Valves (MSLPDIVs) ................................. 3.7-5 3.7.3 Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulating Valves (MFRVs), and Main Feedwater Regulating Valve Bypass Valves (MFRVBVs) .............................................. 3.7-9 3.7.4 Atmospheric Steam Dump Valves (ASDs) ...................................... 3.7-12 3.7.5 Auxiliary Feedwater (AFW) System ................................................. 3.7-15 3.7.6 Condensate Storage Tank (CST) .................................................... 3.7-19 3.7.7 Component Cooling Water (CCW) System ..................................... 3.7-21 3.7.8 Essential Service Water System (ESW) .......................................... 3.7-23 3.7.9 Ultimate Heat Sink (UHS) ................................................................ 3. 7-26 3.7.10 Control Room Emergency Ventilation System (CREVS) ................. 3.7-28 3.7.11 Control Room Air Conditioning System (CRACS) ........................... 3.7-32 3.7.12 Not Used .......................................................................................... 3.7-35 3.7.13' Emergency Exhaust System (EES) ................................................. 3.7-36 3.7.14 Not Used .......................................................................................... 3.7-39 3.7.15 Fuel Storage Pool Water Level ........................................................ 3.7-40 3.7.16 Fuel Storage Pool Boron Concentration .......................................... 3. 7-41 3.7.17 Spent Fuel Assembly Storage ......................................................... 3.7-43 3.7.18 Secondary Specific Activity .............................................................. 3.7-45 3.7.19 Secondary System Isolation Valves (SSIVs) ................................... 3.7-46 3.8 ELECTRICAL POWER SYSTEMS ........................................................ 3.8-1 3.8.1 AC Sources - Operating ................................................................... 3.8-1 3.8.2 AC Sources - Shutdown .................................................................. 3.8-18 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ....................................... 3.8-22 3.8.4 DC Sources - Operating .................................................................. 3.8-25 3.8.5 DC Sources - Shutdown .................................................................. 3.8-28 3.8.6 Battery Cell Parameters ................................................................... 3.8-30 3.8.7 Inverters - Operating ........................................................................ 3.8-34 3.8.8 Inverters - Shutdown ........................................................................ 3.8-36 3.8.9 Distribution Systems - Operating ..................................................... 3.8-38 CALLAWAY PLANT 3 Amendment 213

RCS Loops - MODE 4 3.4.6 ACTIONS (continued)

COMPLETION CONDITION REQUIRED ACTION TIME B. Required loops inoperable. B.1 Suspend operations that Immediately would cause introduction into the RCS, coolant with boron concentration less No RCS or RHR loop in than required to meet operation. SOM of LCO 3.1.1.

B.2 Initiate action to restore Immediately one loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify one RHR or RCS loop is in operation. In accordance with the Surveillance Frequency Control Program SR 3.4.6.2 Verify SG secondary side narrow range water levels In accordance are ~ 7% for required RCS loops. with the Surveillance Frequency Control Program (continued)

CALLAWAY PLANT 3.4-11 Amendment No. 213

RCS Loops - MODE 4 3.4.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.6.3 Verify correct breaker alignment and indicated power In accordance are available to the required pump that is not in with the operation. Surveillance Frequency Control Program SR 3.4.6.4 --------------------------------- NOTE ----------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 4.

Verify required RHR loop locations susceptible to gas In accordance accumulation are sufficiently filled with water. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.4-12 Amendment No. 213

RCS Loops - MODE 5, Loops Filled 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4. 7 RCS Loops - MODE 5, Loops Filled LCO 3.4.7 One residual heat removal (RHR) loop shall be OPERABLE and in operation, and either:

a. One additional RHR loop shall be OPERABLE; or

b. The secondary side wide range water level of at least two steam generators (SGs) shall.be ;::: 86%.

N0 TES -------------------------------------------

1. The RHR pump of the loop in operation may be removed from operation for :s; 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SOM of LCO 3.1.1; and

b. Core outlet temperature is maintained at least 10°F below saturation temperature.

2. One required RHR loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided that the other RHR loop is OPERABLE and in operation.

3. No reactor coolant pump shall be started with any RCS cold leg temperature :s; 275°F unless the secondary side water temperature of each SG is :s; 50°F above each of the RCS cold leg temperatures.

4. All RHR loops may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

APPLICABILITY: MODE 5 with RCS loops filled.

CALLAWAY PLANT 3.4-13 Amendment No. 213 I

RCS Loops - MODE 5, Loops Filled 3.4.7 ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A One RHR loop inoperable. A.1 Initiate action to restore Immediately a second RHR loop to AND OPERABLE status.

Required SGs secondary OR side water levels not within limits. A.2 Initiate action to restore Immediately required SG secondary side water levels to within limits.

B. Required RHR loops B.1 Suspend operations that Immediately inoperable. would cause introduction into the RCS, coolant OR with boron concentration less than required to No RHR loop in operation. meet SOM of LCO 3.1.1.

AND B.2 Initiate action to restore Immediately one RHR loop to OPERABLE status and operation.

CALLAWAY PLANT 3.4-14 Amendment No. 213 I

RCS Loops - MODE 5, Loops Filled 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify one RHR loop is in operation. In accordance with the Surveillance Frequency Control Program SR 3.4.7.2 Verify SG secondary side wide range water level is In accordance

86% in required SGs. with the Surveillance Frequency Control Program SR 3.4.7.3 Verify correct breaker alignment and indicated power In accordance are available to the required RHR pump that is not in with the operation. Surveillance Frequency Control Program SR 3.4.7.4 Verify required RHR loop locations susceptible to gas In accordance accumulation are sufficiently filled with water. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.4-15 Amendment No. 213 I

RCS Loops - MODE 5, Loops Not Filled 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Loops - MODE 5, Loops Not Filled LCO 3.4.8 Two residual heat removal (RHR) loops shall be OPERABLE and one RHR loop shall be in operation.

N0 TES --------------------------------------------

1. All RHR pumps may be removed from operation for ~ 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months provided:

a. The core outlet temperature is maintained at least 10°F below saturation temperature.

b. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SOM of LCO 3.1.1; and

c. No draining operations to further reduce the RCS water volume are permitted.

2. One RHR loop may be inoperable for~ 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided that the other RHR loop is OPERABLE and in operation.

APPLICABILITY: MODE 5 with RCS loops not filled.

ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A One RHR loop inoperable. A.1 Initiate action to restore , Immediately RHR loop to OPERABLE status.

(continued)

CALLAWAY PLANT 3.4-16 Amendment No. 213 I

RCS Loops - MODE 5, Loops Not Filled 3.4.8 ACTIONS (continued)

COMPLETION CONDITION REQUIRED ACTION TIME B. Required RHR loops B.1 Suspend operations that Immediately inoperable. would cause introduction into the RCS, coolant with boron concentration less than required to No RHR loop in operation. meet SOM of LCO 3.1.1.

AND B.2 Initiate action to restore Immediately one RHR loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one RHR loop is in operation. In accordance with the Surveillance Frequency Control Program SR 3.4.8.2 Verify correct breaker alignment and indicated power In accordance are available to the required RHR pump that is not in with the operation. Surveillance Frequency Control Program SR 3.4.8.3 Verify RHR loop locations susceptible to gas In accordance accumulation are sufficiently filled with water. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.4-17 Amendment No. 213

Pressurizer 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Pressurizer LCO 3.4.9 The pressurizer shall be OPERABLE with:

a. Pressurizer water level ~ 92%; and

b. Two groups of backup pressurizer heaters OPERABLE with the capacity of each group ;::: 150 kW.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A Pressurizer water level not A.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months within limit.

AND A.2 Fully insert all rods. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND A.3 Place Rod Control 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months System in a condition I

incapable of rod withdrawal.

AND A.4 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months B. One required group of B.1 Restore required group 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months backup pressurizer heaters of backup pressurizer inoperable. heaters to OPERABLE status.

(continued)

CALLAWAY PLANT 3.4-18 Amendment No. 213 I

Pressurizer 3.4.9 ACTIONS (continued)

COMPLETION CONDITION REQUIRED ACTION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condi~ion B not AND met.

C.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Verify pressurizer water level is~ 92%. In accordance with the Surveillance Frequency Control Program SR 3.4.9.2 Verify capacity of each required group of backup In accordance pressurizer heaters is ~ 150 kW. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.4-19 Amendment No. 213 I

Pressurizer Safety Valves 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 O Pressurizer Safety Valves LCO 3.4.10 Three pressurizer safety valves shall be OPERABLE with lift settings

~ 2411 psig and s: 2509 psig.

APPLICABILITY: MODES 1, 2, and 3, MODE 4 with all RCS cold leg temperatures > 275°F.

N0 TES --------------------------------------------

The lift settings are not required to be within the LCO limits during MODES 3 and 4 for the purpose of setting the pressurizer safety valves under ambient (hot) conditions. This exception is allowed for 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months following entry into MODE 3 provided a preliminary cold setting was made prior to heatup.

ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable. OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND OR B.2 Be in MODE 4 with any 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months RCS cold leg Two or more pressurizer temperature s: 275°F.

safety valves inoperable.

CALLAWAY PLANT 3.4-20 Amendment No. 213 I

Pressurizer Safety Valves 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is OPERABLE in In accordance with accordance with the lnservice Testing Program. the lnservice Following testing, lift settings shall be within +/- 1% of Testing Program 2460 psig.

CALLAWAY PLANT 3.4-21 Amendment No. 213 I

Pressurizer PORVs 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Operated Relief Valves (PO RVs)

LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

NOTE -----------------------------------------------------------

Separate Condition entry is allowed for each PORV and each block valve.

COMPLETION CONDITION REQUIRED ACTION TIME A. One or more PORVs A.1 Close and maintain 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable solely due to power to associated excessive seat leakage. block valve.

B. One PORV inoperable for B.1 Close associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reasons other than valve.

excessive seat leakage.

AND B.2 Remove power from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated block valve.

AND B.3 Restore PORV to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

(continued)

CALLAWAY PLANT 3.4-22 Amendment No. 213 I

Pressurizer PORVs 3.4.11 ACTIONS (continued)

COMPLETION CONDITION REQUIRED ACTION TIME

c. One block valve inoperable. ------------------- NOTE -------------------

Required Actions do not apply when block valve is inoperable solely as a result of complying with Required Actions B.2 or E.2.

C.1 Place associated PORV 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in manual control.

AND C.2 Restore block valve to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A, B, or C AND not met.

D.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E. Two PORVs inoperable for E.1 Close associated block 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months reasons other than valves.

excessive seat leakage.

AND E.2 Remove power from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated block valves.

AND E.3 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND E.4 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

CALLAWAY PLANT 3.4-23 Amendment No. 213 I

Pressurizer PORVs 3.4.11 ACTIONS (continued)

COMPLETION CONDITION REQUIRED ACTION TIME F. More than one block valve ------------------- NOTE -------------------

inoperable. Required Action F.1 does not apply when block valve is inoperable solely as a result of complying with Required Action B.2 or E.2.

F.1 Restore one block valve 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to OPERABLE status.

G. Required Action and G.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition F not AND met.

G.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months CALLAWAY PLANT 3.4-24 Amendment No. 213 I

Pressurizer PORVs 3.4.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 --------------------------------- N0 TE ----------------------------

Not required to be performed with block valve closed in accordance with the Required Actions of this LCO.

Perform a complete cycle of each block valve. In accordance with the Surveillance Frequency Control Program SR 3.4.11.2 Perform a complete cycle of each PORV. In accordance with the lnservice Testing Program CALLAWAY PLANT 3.4-25 Amendment No. 213 I

COMS 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Cold Overpressure Mitigation System (COMS)

LCO 3.4.12 COMS shall be OPERABLE with a maximum of zero safety injection pumps, one Emergency Core Cooling System (ECCS) centrifugal charging pump, and the normal charging pump capable of injecting into the RCS and the accumulators isolated and one of the following pressure relief capabilities:

a. Two power operated relief valves (PORVs) with lift settings within the limits specified in the PTLR, or

b. Two residual heat removal (RHR) suction relief valves with setpoints

o

436.5 psig and ~ 463.5 psig, or

c. One PORV with a lift setting within the limits specified in the PTLR and one RHR suction relief valve with a setpoint ;:o: 436.5 psig and

~ 463.5 psig, or

d. The RCS depressurized and an RCS vent of ;:o: 2.0 square inches.

N0 TES --------------------------------------------

1. Two ECCS centrifugal charging pumps may be made capable of injecting for ~ 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for pump swap operations.

2. One or more safety injection pumps may be made capable of injecting in MODES 5 and 6 when the RCS water level is below the top of the reactor vessel flange for the purpose of protecting the decay heat removal function. '

3. Accumulator may be unisolated when accumulator pressure is less than the maximum RCS pressure for the existing RCS cold leg temperature allowed by the PIT limit curves provided in the PTLR.

APPLICABILITY: MODE 4 with any RCS cold leg temperature ~ 275°F, MODE 5, MODE 6 when the reactor vessel head is on.

CALLAWAY PLANT 3.4-26 Amendment No. 213 I

COMS 3.4.12 ACTIONS

N 0 TE -----------------------------------------------------------

LC O 3.0.4.b is not applicable when entering MODE 4.

COMPLETION CONDITION REQUIRED ACTION TIME A. One or more safety A.1 Initiate action to verify a Immediately injection pumps capable of maximum of zero safety injecting into the RCS. injection pumps are capable of inje_cting into the RCS.

B. Two ECCS centrifugal 8.1 Initiate action to verify a Immediately charging pumps capable of maximum of one ECCS injecting into the RCS.

centrifugal charging pump and the normal charging pump capable of injecting into the RCS.

C. An accumulator not isolated C.1 Isolate affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months when the accumulator accumulator.

pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

(continued)

CALLAWAY PLANT 3.4-27 Amendment No. 213 I

COMS 3.4.12 ACTIONS (continued)

COMPLETION CONDITION REQUIRED ACTION TIME D. Required Action and D.1 Increase all RCS cold 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion leg temperatures to Time of Condition C not > 275°F.

met.

OR D.2 Depressurize affected 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months accumulator to less than the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

E. One required RCS relief E.1 Restore required RCS 7 days valve inoperable in relief valve to MODE 4. OPERABLE status.

F. One required RCS relief F.1 Restore required RCS 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months valve inoperable in relief valve to MODE 5 or6. OPERABLE status.

G. Two required RCS relief G.1 Depressurize RCS and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months valves inoperable. establish RCS vent of

~ 2.0 square inches.

OR Required Action and associated Completion Time of Condition A, B, D, E, or F not met.

OR COMS inoperable for any reason other than Condition A, B, C, D, E, or F.

CALLAWAY PLANT 3.4-28 Amendment No. 213 I

COMS 3.4.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 Verify a maximum of zero safety injection pumps are In accordance capable of injecting into the RCS. with the Surveillance Frequency Control Program SR 3.4.12.2 Verify a maximum of one ECCS centrifugal charging In accordance pump and the normal charging pump capable of with the injecting into the RCS. Surveillance Frequency Control Program SR 3.4.12.3 Verify each accumulator is isolated when In accordance accumulator pressure is greater than or equal to the with the maximum RCS pressure for the existing RCS cold Surveillance leg temperature allowed by the PIT limit curves Frequency provided in the PTLR. Control Program SR 3.4.12.4 Verify RHR suction isolation valves are open for each In accordance required RHR suction relief valve. with the Surveillance Frequency Control Program SR 3.4.12.5 Verify required RCS vent~ 2.0 square inches open. In accordance with the Surveillance Frequency Control Program (continued)

\

CALLAWAY PLANT 3.4-29 Amendment No. 213 I

COMS 3.4.12 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.12.6 Verify PORV block valve is open for each required In accordance PORV. with the Surveillance Frequency Control Program SR 3.4.12.7 Not used.

SR 3.4.12.8 --------------------------------- N0 TE ----------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after decreasing any RCS cold leg temperature to ~ 275°F.

Perform a COT on each required PORV, excluding In accordance actuation. with the Surveillance Frequency Control Program SR 3.4.12.9 Perform CHANNEL CALIBRATION for each required In accordance PORV actuation channel. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.4-30 Amendment No. 213 I

RCS Operational LEAKAGE 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE;

b. 1 gpm unidentified LEAKAGE;

c. 1O gpm identified LEAKAGE; and

d. 150 gallons per day primary to secondary LEAKAGE through any one steam generator (SG).

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A. . RCS operational A.1 Reduce LEAKAGE to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months LEAKAGE not within limits within limits.

for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Pressure boundary LEAKAGE exists.

OR Primary to secondary LEAKAGE not within limit.

CALLAWAY PLANT 3.4-31 Amendment No. 213 I

RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 -------------------------- N0 TES -------------------------------

1. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

2. Not applicable to primary to secondary LEAKAGE Verify RCS operational LEAKAGE is within limits by In accordance performance of RCS water inventory balance. with the Surveillance Frequency Control Program SR 3.4.13.2 -------------------------- N 0 TE -------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

Verify primary to secondary LEAKAGE is~ 150 In accordance gallons per day through any one SG. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.4-32 Amendment No. 213 I

RCS PIV Leakage 3.4.14 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage LCO 3.4.14 Leakage from each RCS PIV shall be within limit.

APPLICABILITY: MODES 1, 2, and 3, MODE 4, except valves in the residual heat removal (RHR) flow path when in, or during the transition to or from, the RHR mode of operation.

ACTIONS

N0 TES --------------------------------------------------------*

1. Separate Condition entry is allowed for each flow path.

2. Enter applicable Conditions and Required Actions for systems made inoperable by an inoperable PIV.

COMPLETION CONDITION REQUIRED ACTION TIME A. One or more flow paths with A.1 ----------- NOTE ------------

leakage from one or more Each valve used to satisfy RCS PIVs not within limit. Required Action A.1 must have been verified to meet SR 3.4.14.1 and be in the reactor coolant pressure boundary.

Isolate the high pressure 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months portion of the affected system from the low pressure portion by use of one deactivated remote

manual or check valve.

A.2 Restore RCS PIV to within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months limits.

(continued)

CALLAWAY PLANT 3.4-33 Amendment No. 213

RCS PIV Leakage 3.4.14 ACTIONS (continued)

COMPLETION CONDITION REQUIRED ACTION TIME B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time for Condition A not AND met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. RHR suction isolation valve C.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months interlock function penetration by use of one inoperable. deactivated remote manual valve.

CALLAWAY PLANT 3.4-34 Amendment No. 213 I

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 --------------------------------- N0 TES --------------------------

1. Not required to be performed in MODES 3 and 4.

2. Not required to be performed on the RCS PIVs located in the RHR flow path when in the shutdown cooling mode of operation.

3. RCS PIVs actuated during the performance of this Surveillance are not required to be tested more than once if a repetitive testing loop cannot be avoided.

Verify leakage from each RCS PIV is equivalent to In accordance with

0.5 gpm per nominal inch of valve size up to a the Inservice maximum of 5 gpm at an RCS pressure;: :: 2215 psig Testing Program and:::; 2255 psig.

In accordance with the Surveillance Frequency Control Program Prior to entering MODE2 whenever the unit has been in MODE 5 for 7 days or more and if leakage testing has not been performed in the previous 9 months (continued)

CALLAWAY PLANT 3.4-35 Amendment No. 213 I

RCS PIV Leakage 3.4.14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 (continued) Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following check valve actuation due to flow through the valve SR 3.4.14.2 Verify RHR suction isolation valve interlock prevents In accordance

the valves from being opened with a simulated or with the actual RCS pressure signal z 425 psig except when Surveillance the valves are open to satisfy LCO 3.4.12. Frequency Control Program CALLAWAY PLANT 3.4-36 Amendment 213 I

RCS Leakage Detection Instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation LCO '3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:

a. The containment sump level and flow monitoring system;

b. One containment atmosphere particulate radioactivity monitor; and

c. The containment cooler condensate monitoring system.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS COMPLETION CONDITION

REQUIRED ACTION TIME A. Required containment sump A.1 ----------- NOTE ------------

level and flow monitoring Not required until system inoperable. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months A.2 Restore required 30 days containment sump level and flow monitoring system to OPERABLE

.status.

(continued)

CALLAWAY PLANT 3.4-37 Amendment No. 213 I

RCS Leakage Detection Instrumentation .

3.4.15 ACTIONS (continued)

COMPLETION CONDITION REQUIRED ACTION TIME B. Required containment B.1.1 Analyze samples of the Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months atmosphere particulate containment atmosphere.

radioactivity monitor inoperable. OR B.1.2 ----------- NOTE ------------

Not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND B.2.1 Restore required 30 days containment atmosphere particulate radioactivity monitor to OPERABLE status.

OR B.2.2 Verify containment air 30 days cooler condensate monitoring system is OPERABLE.

(continued)

CALLAWAY PLANT 3.4-38 Amendment No. 2131

RCS Leakage Detection Instrumentation

' 3.4.15 ACTIONS (continued)

COMPLETION CONDITION REQUIRED ACTION TIME C. Required containment C.1 Perform SR 3.4.15.1. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months cooler condensate monitoring system OR inoperable.

C.2 ----------- NOTE ------------

Not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation.

I Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months D. Required containment D.1 Restore required 30 days atmosphere particulate containment atmosphere radioactivity monitor particulate radioactivity inoperable. monitor to OPERABLE status.

AND OR Required containment cooler condensate D.2 Restore required 30 days monitoring system containment cooler inoperable. condensate monitoring system to OPERABLE status.

E. Required Action and E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND E.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months F. All required monitoring F.1 Enter LCO 3.0.3. Immediately methods inoperable.

CALLAWAY PLANT 3.4-39 Amendment No. 213 I

RCS Leakage Detection Instrumentation 3.4.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of the required In accordance containment atmosphere particulate radioactivity with the monitor. Surveillance Frequency Control Program SR 3.4.15.2 Perform COT of the required containment In accordance atmosphere particulate radioactivity monitor. with the Surveillance Frequency Control Program SR 3.4.15.3 Perform CHANNEL CALIBRATION of the required In accordance containment sump level and flow monitoring system. with the Surveillance Frequency Control Program SR 3.4.15.4 Perform CHANNEL CALIBRATION of the required In accordance containment atmosphere particulate radioactivity with the monitor. Surveillance Frequency Control Program SR 3.4.15.5 Perform CHANNEL CALIBRATION of the required In accordance containment cooler condensate monitoring system. with the Surveillance Frequency Coritrol Program CALLAWAY PLANT 3.4-40 Amendment No. 213 I

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 RCS DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A. DOSE EQUIVALENT ------------------- NOTE -------------------

1-131 not within limit. LCO 3.0.4.c is applicable.

A.1 Verify DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT 1-131

~ 60 µCi/gm.

AND A.2 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT 1-131 to within limit.

B. DOSE EQUIVALENT ------------------- NOTE -------------------

XE-133 not within limit. LCO 3.0.4.c is applicable.

8.1 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT XE-133 to within limit.

(continued)

CALLAWAY PLANT 3.4-41 Amendment No. 213 I

RCS Specific Activity 3.4.16 ACTIONS (continued)

COMPLETION CONDITION REQUIRED ACTION TIME C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A or B AND not met.

C.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR DOSE EQUIVALENT 1-131

> 60 µCi/gm.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 --------------------------------- N 0 TE ----------------------------

0 nIy required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT XE-133 In accordance specific activity :::; 225 µCi/gm. with the Surveillance Frequency Control Program continue CALLAWAY PLANT 3.4-42 Amendment No. 213 I

RCS Specific Activity 3.4.16 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.16.2 --------------------------------- N 0 TE ----------------------------

0 nIy required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 1-131 In accordance specific activity~ 1.0 µCi/gm. with the Surveillance Frequency Control Program Between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a THERMAL POWER change of ;:o: 15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period CALLAWAY PLANT 3.4-43 Amendment No. 213 I

SG Tube Integrity 3.4.17 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.17 Steam Generator (SG) Tube Integrity LCO 3.4.17 SG tube integrity shall be maintained.

All SG tubes satisfying the tube repair criteria shall be plugged in accordance with Steam Generator Program.

APPLICABILITY: MODES 1 2, 3, and 4.

ACTIONS

N0 TE -----------------------------------------------------------

Se pa rate Condition entry is allowed for each SG tube.

COMPLETION CONDITION REQUIRED ACTION TIME A One or more SG tubes A.1 Verify tube integrity of 7 days satisfying the tube repair the affected tube(s) is criteria and not plugged in maintained until the next accordance with the Steam refueling outage or Generator Program. inspection.

A.2 Plug the affected tube(s) Prior to entering in accordance with the MODE 4 following Steam Generator the next refueling Program. outage or SG tube inspection (continued)

CALLAWAY PLANT 3.4-44 Amendment No. 213 I

SG Tube Integrity 3.4.17 ACTIONS (continued)

COMPLETION CONDITION REQUIRED ACTION TIME B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A not AND met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SG tube integrity not maintained.

CALLAWAY PLANT 3.4-45 Amendment No. 213

SG Tube Integrity 3.4.17 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify SG tube integrity in accordance with the Steam In accordance with Generator Program. the Steam Generator Program SR 3.4.17.2 Verify that each inspected SG tube that satisfies the Prior to entering tube repair criteria is plugged in accordance with the MODE 4 following Steam Generator Program. a SG tube inspection CALLAWAY PLANT 3.4-46 Amendment No. 213 I

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify the following valves are in the listed position In accordance with power to the valve operator removed. with the Surveillance Number Position Function Frequency BNHV8813 Open Safety Injection to RWST Control Program Isolation Valve EMHV8802A Closed SI Hot Legs 2 & 3 Isolation Valve EMHV8802B Closed SI Hot Legs 1 & 4 Isolation Valve EMHV8835 Open Safety Injection Cold Leg Isolation Valve EJHV8840 Closed RHR/SI Hot Leg Recirc Isolation Valve EJHV8809A Open RHR to Accum Inject Loops 1 & 2 Isolation Valve EJHV8809B Open RHR to Accum Inject Loops 3 & 4 Isolation Valve SR 3.5.2.2 --------------------------------- N0 TE ----------------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each ECCS manual, power operated, and In accordance automatic valve in the flow path, that is not locked, with the sealed, or otherwise secured in position, is in the Surveillance correct position. Frequency Control Program SR 3.5.2.3 Verify ECCS locations susceptible to gas In accordance accumulation are sufficiently filled with water. with the Surveillance Frequency Control Program SR 3.5.2.4 Verify each ECCS pump's developed head at the test In accordance with flow point is greater than or equal to the required the Inservice developed head. Testing Program (continued)

CALLAWAY PLANT 3.5-5 Amendment No. 213

Containment Spray and Cooling Systems 3.6.6 ACTIONS (continued)

COMPLETION CONDITION REQUIRED ACTION TIME D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition C not AND met.

D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. Two containment spray E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months trains inoperable.

AND OR E.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Two containment cooling trains inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 -------------------~------------- N0 TE ----------------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each containment spray manual, power In accordance operated, and automatic valve in the flow path that is with the not locked, sealed, or otherwise secured in position is Surveillance in the correct position. Frequency Control Program SR 3.6.6.2 Operate each containment cooling train fan unit for In accordance

~ 15 minutes. with the Surveillance Frequency Control ~rogram (continued)

CALLAWAY PLANT 3.6-19 Amendment No. 213

Containment Spray and Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6.3 Verify each containment cooling train cooling water In accordance flow rate is ;;::: 2200 gpm. '-* with the Surveillance Frequency Control Program SR 3.6.6.4 Verify each containment spray pump's developed In accordance with head at the flow test point is greater than or equal to the lnservice the required developed head. Testing Program SR 3.6.6.5 Verify each automatic containment spray valve in the In accordance flow path that is not locked, sealed, or otherwise with the secured in position, actuates to the correct position on Surveillance an actual or simulated actuation signal. Frequency Control Program SR 3.6.6.6 Verify each containment spray pump starts In accordance automatically on an actual or simulated actuation with the signal. Surveillance Frequency Control Program SR 3.6.6.7 Verify each containment cooling train starts In accordance automatically and minimum cooling water flow rate is with the established on an actual or simulated actuation Surveillance signal. Frequency Control Program SR 3.6.6.8 Verify each spray nozzle is unobstructed. In accordance with the Surveillance Frequency Control Program (continued)

CALLAWAY PLANT 3.6-20 Amendment No. 213

Containment Spray and Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6.9 Verify containment spray locations susceptible to gas In accordance accumulation are sufficiently filled with water. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.6-21 Amendment No. 213

Recirculation Fluid pH Control System 3.6.7 3.6 CONTAINMENT SYSTEMS 3.6.7 Recirculation Fluid pH Control (RFPC) System LCO 3.6.7 The RFPC System shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A RFPC System inoperable. A.1 Restore RFPC System 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time not met. AND B.2 Be in MODE 5. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.7.1 Verify the integrity of the RFPC System. In accordance with the Surveillance Frequency Control Program continue CALLAWAY PLANT 3.6-22 Amendment No. 213 I

Recirculation Fluid pH Control System 3.6.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.7.2 Verify the RFPC System ensures an equilibrium sump In accordance pH :;: : 7. 1. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.6-23 Amendment No. 213 I

RHR and Coolant Circulation - High Water Level 3.9.5 ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME A. RHR loop requirements not A.3 Initiate action to satisfy Immediately met. RHR loop requirements.

(continued)

Close all containment 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify one RHR loop is in operation and circulating In accordance reactor coolant at a flow rate of z 1000 gpm. with the Surveillance Frequency Control Program SR 3.9.5.2 Verify required RHR loop locations susceptible to gas In accordance accumulation are sufficiently filled with water. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.9-10 Amendment 213

RHR and Coolant Circulation - Low Water Level 3.9.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.9.6.2 Verify correct breaker alignment and indicated power In accordance available to the required RHR pump that is not in with the operation. Surveillance Frequency Control Program SR 3.9.6.3 Verify RHR loop locations susceptible to gas In accordance accumulation are sufficiently filled with water. with the Surveillance Frequency Control Program CALLAWAY PLANT 3.9-13 Amendment No. 213

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 213 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-30 UNION ELECTRIC COMPANY CALLAWAY PLANT, UNIT 1 DOCKET NO. 50-483

1.0 INTRODUCTION

By application dated March 12, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15071A403), Union Electric Company (the licensee) requested changes to Renewed Facility Operating License No. NPF-30 for the Callaway Plant, Unit 1 (Callaway Plant). The licensee proposes to revise the Technical Specification (TS) requirements in order to address U.S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems," dated January 11, 2008 (ADAMS Accession No. ML072910759), as*described in NRG-approved Technical Specification Task Force (TSTF)

Standard Technical Specifications (STS) Change Traveler TSTF-523-A, Revision 2, "Generic Letter- 2008-01, Managing Gas Accumulation" (ADAMS Accession No. ML13053A075).

The proposed changes would revise TS Surveillance Requirements (SRs) related to gas accumulation for the emergency core cooling system (ECCS). The proposed change would also add new SRs related to gas accumulation for the residual heat removal (RHR), shutdown cooling, and containment spray (CS) systems. The licensee also proposed TS Bases changes consistent with these SRs.

In its application, the licensee stated that it has reviewed the information contained in the NRC's model safety evaluation dated December 23, 2013 (ADAMS Accession No. ML13255A169), and that the license amendment request is not proposing any variations or deviations from the TS described in NRG-approved TSTF-523-A, Revision 2.

2.0 REGULATORY EVALUATION

2.1 Background Gas accumulation in reactor systems can result in water hammer, pump cavitation, and pumping of non-condensable gas into the reactor vessel. These effects may result in the Enclosure 2

subject system being unable to perform its specified safety function. The NRC issued GL 2008-01 in January 2008 to address the issue of gas accumulation in ECCS, decay heat removal or RHR at Callaway Plant, and CS systems. The industry and NRC staff agreed that a change to the STS and plant-specific TS would be necessary to address some issues discussed in GL 2008-01. TSTF-523-A, Revision.2 contains changes to the TS SRs and TS Bases to address some of the concerns in GL 2008-01. The licensee proposed amending the Callaway Plant TSs using a plant-specific adoption of the TSTF-523-A, Revision 2 changes.

2.2 Technical Specification Changes The licensee proposed changes to SRs 3.5.2.2, 3.5.2.3, and 3.6.6.1, as well as the addition of new SRs 3.4.6.4, 3.4.7.4, 3.4.8.3, 3.6.6.9, 3.9.5.2, and 3.9.6.3 to TS 3.4.6, "RCS [Reactor Coolant System] Loops - MODE 4," TS 3.4.7, "RCS Loops - MODE 5, Loops Filled," TS 3.4.8, "RCS Loops - MODE 5, Loops Not Filled," TS 3.5.2, "ECCS - Operating," TS 3.6.6, "Containment Spray and Cooling Systems," TS 3.9.5, "Residual Heat Removal (RHR) and Coolant Circulation - High Water Level," and TS 3.9.6, "Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level," respectively.

2.3 Regulatory Review The regulations in Appendix A, "General Design Criteria for Nuclear Power Plants," of Title 10 of the Code of Federal Regulations (10 CFR) Part 50 or similar plant-specific principal design criteria provide design requirements. Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50, the TSs, and the licensee quality assurance programs provide operating requirements. The regulatory requirements of 10 CFR Part 50, Appendix A, that are applicable to gas management in the subject systems include: General Design Criteria (GDC) 1, 34, 35, 36, 37, 38, 39 and 40. GDC 1, "Quality.

standards and records," requires that the subject systems be designed, fabricated, erected, and tested to quality standards. GDC 34, "Residual heat removal," requires an RHR system designed to maintain specified acceptable fuel design limits and to meet design conditions that are not exceeded if a single failure occurs and specified electrical power systems fail. GDC 35, "Emergency core cooling," GDC 36, "Inspection of emergency core cooling system," and GDC 37, "Testing of emergency core cooling system," require an ECCS design that meets performance, inspection, and testing requirements. Additionally, the regulations in 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," provide specified ECCS performance criteria. GDC 38, "Containment heat removal," GDC 39, "Inspection of containment heat removal system," and GDC 40, "Testing of a

containment heat removal system," require containment heat removal system design that meets performance, inspection, and testing requirements.

Quality assurance criteria provided in 10 CFR Part 50, Appendix B, that apply to gas

management in the subject systems include: Criteria Ill, V, XI, XVI, and XVII. Criterion Ill, "Design Control," and Criterion V, "Instructions, Procedures, and Drawings," require measures to ensure that applicable regulatory requirements and the design basis, as defined in 10 CFR 50.2, "Definitions," and as specified in the license application, are correctly translated into controlled specifications, drawings, procedures, and instructions. Criterion XI, "Test Control," requires a test program to ensure that the subject systems will perform satisfactorily in service and requires that test results shall be documented and evaluated to ensure that test

requirements have been satisfied. Criterion XVI, "Corrective Action," requires measures to ensure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances, are promptly identified and corrected, and that significant conditions adverse to quality are documented and reported to management. Criterion XVII, "Quality Assurance Records," requires maintenance of records of activities affecting quality.

The NRC's regulatory requirements related to the content of the TSs are contained in 10 CFR 50.36(c). The regulations at 10 CFR 50.36 require that the TSs include items in the following categories: (1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) SRs; (4) design features; and

.(5) administrative controls. Surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the LCOs will be met.

Typically, TS Section 5 requires that licensees establish, implement, and maintain written procedures covering the applicable procedures recommended in Appendix A to NRC

Regulatory Guide (RG) 1.33, "Quality Assurance Program Requirements (Operation)."

Appendix A to RG 1.33 identifies instructions for filling and venting the ECCS and decay heat removal system, as well as for draining and refilling heat exchangers. The STS and most licensee TSs include SRs to verify that at least some of the subject systems piping is filled with

'water. Callaway Plant's TS 5.4.1 requires that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in RG 1.33, Revision 2, Appendix A, February 1978 (ADAMS Accession No. ML003739995). The NRC's guidance for the format and content of licensee TSs can be found in NUREG-1431, Revision 4, "Standard Technical Specifications - Westinghouse Plants," April 2012 (STS) (ADAMS Accession No. ML12100A222).

NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition," (SRP), is not the regulatory basis of the proposed TSs changes, and the licensee is not required to confirm that the SRP guidance is applicable to the Callaway Plant.

Regulatory guidance for the NRC staff's review of containment heat removal systems, ECCS, and RHR systems is provided in the following revisions and sections of the SRP during the review.

Revision 5 of SRP Section 6.2.2, "Containment Heat Removal Systems," dated March 2007 (ADAMS Accession No. ML070160661), provides the procedures concerning the review of containment heat removal under post-accident conditions to help ensure compliance with GDCs 38, 39, and 40.

Revision 3 of SRP Section 6.3, "Emergency Core Cooling System," dated March 2007 (ADAMS Accession No. ML070550068), provides the procedures concerning the review of ECCS to help ensure compliance with GDCs 35, 36, and 37.

Revision 5 of SRP Section 5.4.7, "Residual Heat Removal (RHR) System," dated May 2010 (ADAMS Accession* No. ML100680577), provides the procedures concerning

the review of RHR system as it is used to cool the reactor coolant system (RCS) during and following shutdown to help ensure compliance with GDC 34.

3.0 TECHNICAL EVALUATION

3.1 Proposed TS Changes The proposed changes adopted the TS format and content, with the exception of changes due to plant-specific nomenclature, contained in the changes made by TSTF-523-A, Revision 2 to NUREG-1431, "Standard Technical Specifications Westinghouse Plants."

The NRC staff compared the proposed changes to the existing SR.s, as well as the regulatory requirements of 10 CFR 50.36(c). The licensee proposed the following TS changes:

1. Add SR 3.4.6.4, which states, "Verify required RHR loop locations susceptible to gas accumulation are sufficiently filled with water," with a note that states "Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 4," and a frequency of "In accordance with the Surveillance Frequency Control Program."

2. Add SR 3.4.7.4, which states, "Verify required RHR loop locations susceptible to gas accumulation are sufficiently filled with water," with a frequency of "In accordance with the Surveillance Frequency Control Program."

3. Add SR 3.4.8.3, which states "Verify RHR loop locations susceptible to gas accumulation are sufficiently filled with water," with a frequency of "In accordance with the Surveillance Frequency Control Program."

4. Add a note to SR 3.5.2.2, which states, "Not required to be met for system vent flow paths opened under administrative control."

5. Revise the language for SR 3.5.2.3 from "Verify ECCS piping is full of water" to "Verify ECCS locations susceptible to gas accumulation are sufficiently filled with water."

6. Add a note to SR 3.6.6.1, which states, "Not required to be met for system vent flow paths opened under administrative control."

7. Add SR 3.6.6.9, which states, "Verify containment spray locations susceptible to gas accumulation are sufficiently filled with water," with a frequency of "In accordance with the Surveillance Frequency Control Program."

8. Add SR 3.9.5.2, which states, "Verify required RHR loop locations susceptible to gas accumulation are sufficiently filled with water," with a frequency of "In accordance with the Surveillance Frequency Control Program."

9. Add SR 3.9.6.3, which states, "Verify RHR loop locations susceptible to gas accumulation are sufficiently filled with water," with a frequency of "In accordance with the Surveillance Frequency Control Program."

Editorial changes to the TS table of contents were proposed to reflect page number changes due to the addition of new SRs.

3.2 NRC Staff Evaluation The new language for the SRs was developed using licensee responses to GL 2008-01 and the NRC discussion contained in Task Interface Agreement (TIA) 2008-03, "Emergency Core Cooling System Voiding Relative to Compliance with Surveillance Requirements (SR) 3.5.1.1, 3.5.2.3, and 3.5.3.1," dated October 21, 2008 (ADAMS Accession No. ML082560209). Many of the GL 2008-01 responses stated that licensees identified system locations susceptible to gas accumulation. In the TIA, the NRC stated that the intent of the TS SRs, which state "full of water," may be met if the licensee can establish, through an Operability Determination, that there is a reasonable expectation that the system in question will perform its specified safety function. Therefore the phrase, "sufficiently filled with water" was recommended for the proposed TS changes. In the TS, "sufficiently filled with water" is understood to mean "sufficiently filled with water to support Operability." The regulation at 10 CFR 50.36(c)(3) states that one of the purposes of the SR is to verify that the LCO is met. Therefore, the new SR language, "Verify the [system name] locations susceptible to gas accumulation are sufficiently filled with water," is acceptable, since this language will allow the licensee to make a conclusion as to whether or not a system is operable.

The language for the notes that state that the SR does not have to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 4 is acceptable because the note provides a limited time to perform the Surveillance after entering the Applicability of the LCO; however, under the STS usage rules (STS Section 1.4), the requirement to manage gas accumulation is not affected. Licensees must have confidence that the SR can be met or the LCO must be declared not met.

The language for the notes that allow the SRs to not be met for system vent flow paths opened under administrative control is necessary to allow the licensee to credit administratively controlled manual action to close the system vent flow path in order to maintain system.

Operability during system venting and performance of the proposed gas accumulation SR.

Therefore, these notes are acceptable.

The NRC staff concludes that the proposed SRs meet the regulatory requirements of 10 CFR 50.36 because they provide assurance that the necessary quality of systems and components will be maintained and that the LCO will be met. Based on the above, the NRC staff concludes that the proposed amendment is acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Missouri State official, Mr. R. Stout, was notified on September 15, 2015, of the proposed issuance of the amendment. The State official had no comments.

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5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding published in Federal Register on June 9, 2015 (80 FR 32630). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b ), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: M. Hamm, NRR/DSS/STSB Date: October 28, 2015

ML15258A510 OFFICE N RR/DORULPL4-1 /PM NRR/DORL/LPL4-1/LA NRR/DSS/STSB/BC NAME JKlos JBurkhardt RElliott DATE 10/1/2015 9/16/15 10/6/2015 OFFICE OGC- NLO N RR/DORL/LPL4-1 /BC N RR/DORULPL4-1 /PM NAME A Ghosh MMarkley JKlos DATE 10/14/15 10/28/15 10/28/15

v t e Letter Sequence Approval
CAC:MF5856, (Approved, Closed)
Initiation Request Acceptance... Administration Questions Answers Results Approval Other:
MONTHYEAR2015-10-28 [Table View]

ML15258A510

Text

SUBJECT:

Dear Mr. Diya:

Enclosures:

Attachment:

1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 STATE CONSULTATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 CONCLUSION

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