Text

Technical Requirements Manual Update to the NRC
	ML16154A863
Person / Time
Site:	Waterford
Issue date:	06/02/2016
From:	Jarrell J; Entergy Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	W3F1-2016-0040
	Download: ML16154A863 (36)
	v • d • e

Entergy Operations, Inc.

17265 River Road Killona, LA 70057-3093 Enteigy Tel 504-739-6685 Fax 504-739-6698 jjarrel@entergy.com John P. Jarrell Regulatory Assurance Manager Waterford 3 W3FI -2016-0040 10 CFR 50.71(e)

June 2, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Technical Requirements Manual Update to the NRC Waterford Steam Electric Station, Unit 3 (Waterford 3)

Docket No. 50-382 License No. NPF-38

Dear Sir or Madam:

Pursuant to Waterford Steam Electric Station Unit 3 (Waterford 3) Technical Specification (IS) 6.16, Entergy Operations, Inc. (EOl) hereby submits an update of all changes made to the Waterford 3 Technical Requirements Manual (TRM) since the last submittal per letter W3FI-2014-0078 (ADAMS Accession No. MLI 5086A208) dated December 23, 2014.

Additionally, this update satisfies the submittal frequency required by IS 6.16, which indicates that the TRM will be submitted at a frequency consistent with 10 CFR 50.71(e) and exemptions thereto.

Plant changes made under the provisions of 10 CFR 50.59 are reported to the NRC pursuant to the requirements of 10 CFR 50.59(b)(2) by separate submittal.

There are no commitments associated with this submittal. Should you have any questions or comments concerning this submittal, please contact the Regulatory Assurance Manager, John Jarrell, at (504) 739-6685.

Attachments:

1. Waterford 3 Technical Requirements Manual fIRM) Index Change List.

2. Waterford 3 Technical Requirements Manual (TRM) Index and Revised Pages.

W3FI -2016-0040 Page 2 of 2 cc: Mr. Mark L. Dapas RidsRgn4MailCenternrc.gov Regional Administrator U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Blvd.

Arlington, TX 76011-4125 NRC Senior Resident Inspector Frances. Ramirez@nrc.gov Waterford Steam Electric Station Unit 3 Chris.Speernrc.gov PD. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission April.Pulvirenti.nrc.gov Washington, DC 20555-0001

Attachment I to W3FI -2016-0040 Waterford 3 Technical Requirements Manual fTRM) Change List

Attachment I to W3FI -2016-0040 Page 1 of 2 Waterford 3 Technical Requirements Manual fIRM) Change List TRM Bases Implementation Affected TRM Topic of Change Amendment Date Pages No.

129 9/17/2015 ha, 3/4 9-2, Amendment #129 Refuel Machine &

3/4 9-3, IVa, implement Technical Specification.

B 3/4 5a, License Bases Document Change B 3/4 5b Request (LBDCR)15-024 implements (TS) Amendment #243 to move TS 3.9.6 & 3.9.7 to the TRM.

130 912212015 B 3/4 3 Amendment #130 to extend the Integrated Leak Rate Test (ILRT) frequency from 10 to 15 years.

License Bases Document Change Request (LBDCR)15-029 implements (TS) Amendment #244 approved this change.

131 10/15/2015 3/4 8-24 Amendment #131 Refuel Machine Breaker replacement TRM Table 3.8-1. License Bases Document Change Request (LBDCR)15-022 implements this change 132 10/2212015 B 3/4 5a Amendment #132 Refuel Machine changes regarding overload cutoff limits. License Bases Document Change Request (LBDCR)14-025 implements this change 133 11/9/2015 3/4 9-2 Amendment #133 Changes to B 3/4 5a Operability weights for the Refuel Machine. License Bases Document Change Request (LBDCR)15-036 Implements TRM 3.9.6 change.

134 11/18/2015 Ila, iv, Amendment #134 Spent Fuel Pool B 3/4 13 Instrumentation (SFP) 3/4.13.1 EC 48147 installs a new NS spent fuel pool level instrumentation & backup power supplies. License Bases Document Change Request (LBDCR)15-033 Implements this change.

135 11/25/2015 3/4 8-3 Amendment #135 Installs swing SUPS Al & SUPS B1 in TRM 3.8.3.1.

License Bases Document Change Request (LBDCR)15-008 & 15-009 implements this change.

Attachment I to W3FI -2016-0040 Page 2 of 2 TRM Bases Implementation Affected TRM Topic of Change Amendment Date Pages No.

136 5/26/2016 iv, ha, Iva, VI, Amendment #1 36 Beyond Design 3/4 3-21a, Bases External Event (BDBEE) 3/4 i 3.. (FLEX) 2 new TRM sections 3.13.2 &

3/4 13-2 3.13.3 to implement the requirements 3/4 13-3 contained in 1 1.5 of NEt 12-06.

FLEX equipment requited to be 3/4 IA operable at all times since a BDBEE I

could occur regardless of operational 3/4 13-6 mode. License Bases Document 3/4 1 37 Change Request (LBDCR)16-008 B 3/4 13 implements this change.

B 3/4 14 B 3/4 15

Attachment 2 to W3FI -2016-0040 Waterford 3 Technical Requirements (TRM) Revised Pages (There are 30 unnumbered pages following this cover page)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE (DRN 07-136 Am. 111) 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES 3/4 8-4 4-(DRN 07-136 Am. 111)

-(0RN 05-880, Am. 100)

MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES 3/4 8-62 4-(DRN 05-680, Am. 100) 3/4.9 REFUELING OPERATIONS (CBDCR 13-003, Am. 124) 3/4.9.5 COMMUNICATIONS 3/4 9-1

-(LBDCR 13-003, Am. 124) 3/4.9.6 REFUELING MACHINE 3/4 9-2 3/4.9.7 CRANE TRAVEL FUEL HANDLING BUILDING 3/4 9-3 (L8DCR 15-024, Am. 129) 3/4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM 3/4 9-4 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION 3/4 11-1 (DRN 02-216)

DOSE 3/4 11-16 LIQUID RADWASTE TREATMENT SYSTEM 3/4 11-17 3/4.11.2 GASEOUS EFFLUENTS

- DOSE RATE 3/4 11-18 GASEOUS EFFLUENTS DOSE RATE 3/4 11-25 DOSE IODINE-131, IODINE-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM 3/4 11-26 (DRN 02-912)

GASEOUS RADWASTE TREATMENT 3/4 11-27

÷-(DRN 02-91 2) 3/4.11.3 SOLID RADIOACTIVE WASTE 3/4 11-29 3/4.11.4 TOTAL DOSE 3/4 11-30

÷-(DRN 02-216) 314.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM 3/4 12-1 3/4.12.2 LAND USE CENSUS 3/4 12-13 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 3/4 12-14 Ila AMENDMENT NO. 58, 99,100, 118, 424, 129

,(LBDCR 15-024)

REFUELING OPERATIONS 3/4.9.6 REFUELING MACHINE LIMITING CONDITION FOR OPERATION 3.9.6 The refueling machine shall be used for movement of CEAs or fuel assemblies and shall be OPERABLE with:

a. A minimum capacity of 3200 pounds, and an overload cut off limit of less than or equal to 3350 pounds for the fuel mast.

b. A minimum capacity of 1600 pounds and an overload cut off limit of less than or equal to 1700 pounds for the CEA mast.

APPLICABILITY: During movement of CEAs or fuel assemblies within the reactor pressure vessel ACTION:

a. With the above requirements for the fuel mast not satisfied, suspend use of the fuel mast from operations involving pre-planned movement of fuel assemblies, and place the refueling machine load (fuel assembly) in a safe condition.

b. With the above requirements for the CEA mast not satisfied, suspend use of the CEA mast from operations involving pre-planned movement of CEAs, and place the refueling machine load (CEA) in a safe condition.

SURVEILLANCE REQUIREMENTS 4.9.6.1 The fuel mast used for movement of fuel assemblies shall be demonstrated OPERABLE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to the start of such operations by performing a load test of at least 3200 pounds and demonstrating an automatic load cut off when the fuel mast load exceeds 3350 pounds.

4.9.6.2 The CEA mast used for movement of CEAs shall be demonstrated OPERABLE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to the start of such operations by performing a load test of at least 1600 pounds and demonstrating an automatic load cut off when the CEA mast exceeds 1700 pounds.

(LBDCR 15-024) 3/4 9-2 AMENDMENT NO. 129

,(LBDCR 15-024)

REFUELING OPERATIONS 3/4.9.7 CRANE TRAVEL FUEL HANDLING BUILDING LIMITING CONDITION FOR OPERATION 3.9.7 Cranes in the fuel handling building shall be restricted as follows:

a. The spent fuel handling machine shall be used* for the movement of fuel assemblies (with or without CEAs) and shall be OPERABLE with:

1. A minimum hoist capacity of 1800 pounds, and

2. An overload cutoff limit of less than or equal to 1900 pounds, and,

b. Loads in excess of 2000 pounds shall be prohibited from travel over irradiated fuel assemblies in the Fuel Handling Building, except over assemblies in a transfer cask using a single-failure-proof handling system.

APPLICABILITY: With irradiated fuel assemblies in the Fuel Handling Building.

ACTION:

a. With the spent fuel handling machine inoperable, suspend the use of the spent fuel handling machine for movement of fuel assemblies and place the crane load in a safe position.

b. Wth loads in excess of 2000 pounds over irradiated fuel assemblies in the Fuel Handling Building, except over assemblies in a transfer cask using a single-failure-proof handling system, place the crane load in a safe position.

c. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.7.1 The spent fuel handling machine shall be demonstrated OPERABLE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to the start of fuel assembly movement and at least once per 7 days thereafter by performing a load test of at least 1800 pounds and demonstrating the automatic load cutoff when the hoist load exceeds 1900 pounds.

4.9.7.2 The electrical interlock system which prevents crane main hook travel over irradiated fuel assemblies in the Fuel Handling Building, except over assemblies in a transfer cask using a single-failure-proof handling system, shall be demonstrated OPERABLE within 7 days prior to crane use and at least once per 7 days thereafter during crane operation.

4.9.7.3 Administrative controls which prevent crane auxiliary hook travel with loads in excess of 2000 pounds over the irradiated fuel assemblies in the Fuel Handling Building, including over assemblies in a transfer cask, shall be enforced during crane operations.

Not required for movement of new fuel assemblies outside the spent fuel pool and Cask Storage Pit.

(LBDCR 15-024) 3/4 9-3 AMENDMENT NO. 129

INDEX BASES SECTION PAGE 3/4.9 REFUELING OPERATIONS

(LBDCR 13-003, Am. 124) 3/4.9.5 COMMUNICATIONS B 3/4 5a 4(LBDCR 13-003, Am. 124)

(LBDCR 15-024, Am. 129) 3/4.9.6 REFUELING MACHINE B 3/4 5a 3/4.9.7 CRANE TRAVEL FUEL HANDLING BUILDING B3145b 4(LBDCR 15-024, Am. 129) 3/4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM B 3/4 &

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1.1 CONCENTRATION B 3/4 6 3/4.1 7.1.2 DOSE B 3/46 3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM B 3/4 7 3/4.11.2.1 DOSE RATE B 3/4 7 3/4.11.2.2 DOSE NOBLE GASES

- B 3/4 8

(DRN 02-216) 3/4.11.2.3 DOSE IODINE-I 31, IODINE-i 33, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM B 3/4 9 3/4.11.2.4 GASEOUS RADWASTE TREATMENT B 3/4 10 4(DRN 02-216) 3/4.11.3 SOLID RADIOACTIVE WASTE B 3/4 10 3/4.11.4 TOTAL DOSE B 3/4 10 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM B 3/4 11

fDRN 05-880, Am. 100) 3/4.12.2 LAND USE CENSUS B 3/4 12

+-(DRN 05-880, Am. 100) 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM B 3/4 12 IVa AMENDMENT NO. 124 129

3/48 ELECTRICAL POWER SYSTEMS BASES 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment electrical penetrations and penetration conductors are protected by either deenergizing circuits not required during reactor operation or by demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers during periodic surveillance.

The Surveillance Requirements applicable to lower voltage circuit breakers and fuses provides assurance of breaker and fuse reliability by testing at least one representative sample of each manufacturers brand of circuit breaker and/or fuse. Each manufacturers molded case and metal case circuit breakers and/or fuses are grouped into representative samples which are then tested on a rotating basis to ensure that all breakers and/or fuses are tested. If a wide variety exists within any manufacturers brand of circuit breakers and/or fuses it is necessary to divide that manufacturers breakers and/or fuses into groups and treat each group as a separate type of breaker or fuses for surveillance purposes.

The OPERABILITY of the motor-operated valves thermal overload protection and/or bypass devices ensures that these devices will not prevent safety related valves from performing their function. The Surveillance Requirements for demonstrating the OPERABILITY of these devices are in accordance with Regulatory Guide 1.106, Thermal Overload Protection for Electric Motors on Motor Operated Valves, Revision 1, March 1977.

Containment Penetration Conductor Overcurrent Protection Devices and Motor-Operated Valves Thermal Overload Protection and/or Bypass Devices, previously Tables 3.8-1 and 3.8-2, of the Technical Specifications have been incorporated into this manual.

3/49 REFUEL OPERATIONS

.-+(LBDCR 13-003, Am. 124) 3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during CORE ALTERATIONS.

-+(LBDCR 13-003, Am. 124)

-(LBDCR 15-024, Am.

3/49.6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine ensure that: (1) the refueling machine will be used for movement of CEAs and fuel assemblies, (2) each hoist has sufficient load capacity to lift a CEA or fuel assembly, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

The Technical Requirements Manual Actions a. and b. statements allow the movement of a fuel assembly or CEA to safe condition using administrative controls in the event of a refueling machine failure.

4(LBDCR 15-024, Am. 129)

B 3/4 5a AMENDMENT NO. 43, 50, 124, 129

3/49 REFUEL OPERATIONS BASES (LSDCR 15-024, Am. 129) 3/4.9.7 CRANE TRAVEL FUEL HANDLING BUILDING The fuel handling accident (UFSAR Section 15.7.3.4) analysis assumes protection against load movements with or over irradiated fuel assemblies that could cause fuel assembly damage.

Examples of load movements include movement of new fuel assemblies, irradiated fuel assemblies, and the dummy fuel assembly. The load movements do not include the movement over assemblies in a transfer cask using a single-failure-proof handling system. The load movements do not include the movement of the spent fuel machine or refuel machine without loads attached. It also does not include load movements in containment when the reactor vessel head or Upper Guide Structure is still installed. Load movements also exclude suspended loads weighing less than 1000 Ibm (e.g. Westinghouse analysis CN-NFPE-09-57 describes no fuel failure for loads weighing less than 1000 Ibm based upon the 2000 Ibm analysis for drops distributed over two assemblies). Movements of loads using a single failure proof handling system, consisting of a crane that has been upgraded to meeting the single-failure-proof criteria of NUREG 0554 and NUREG 0612, and lifting devices that meet the requirements of ANSI N14.6 or ASME B30.9, do not require the assumption of a dropped load, and activity releases assumed in the safety analysis are not affected.

(LBDCR 15-024, Am. 129) 3/4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM The OPERABILITY of the Fuel Handling Building ventilation system insures that all radioactive material released from an irradiated fuel assembly will be monitored prior to discharge to the atmosphere. The safety analysis for a fuel handling accident in the Fuel Handling Building assumes no filtration and no holdup time.

3 B3/45 AMENDMENTNO.4.,5O,4.24, 129

3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the safety analyses. This restriction, in conjunction with the leakage rate limitation, will limit the SITE BOUNDARY radiation doses to within the limits 0110 CFR Part 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the safety analyses at the peak accident pressure, Pa. As an added conservatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 L or less than or equal to 0.75 L as applicable during performance of the periodic tests to account for possible degradation of the containment leakage barriers between leakage tests.

(LBDCR 15-029, Am. 130)

The surveillance requirements for measuring leakage rates are consistent with the requirements of Appendix J 0110 CFR Part 50. Technical Specification Amendment 244 was a by the on August 24, 2015. This amendment postpones the next Type A test performed after May 21, 2005 to no later than May 20, 2020. This results in intervals to be extended from no longer than 10 years to no longer than 15 years on a permanent basis, provided acceptable performance history and the requirements of NEI 94-01, Rev. 2-A are met.

(LsDcR 15-029, Am. 1 30)

-÷fDRN 04-1244, Am. 99) 4-(DRN 04-1244, Am. 99) 3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with the requirements of GDC 54 through GDC 57 of Appendix A to 10 CFR Part 50. Containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.

B 314 3 AMENDMENT NO. 12, 64, 99, 130

TABLE 3.8-1 (contd)

CONTAINMENT PENETRATION CON DUCTOR OVER-CURRENT PROTECTIVE DEVICES OVER-CURRENT PROTECTIVE DEVICES WITHIN EACH VOLTAGE LEVEL (ROMAN) MODES BREAKER IDENTIFYING TIME INTEG. INSP & FOR PROTEC./ NUMBER CURRENT FUNC. CHANNEL FUNC. PREy. WHICH AFFECTED OR CHARAC- TEST CALIB. TEST MAINT. SURV IS COMPONENTS DRAWING DESCRIPTION TYPE TERISTIC 4.8.4.1.a.2 4.8.4.1.a.1.a 4.8.4.1.a.1.b 4.8.4.1.b REQD 42 LP-304 a Primary 289-45 Breaker EF Note IV.2,IV.3 10% of Type NA NA every 60 M 1,2,3,4 perR LTNEBKR213A-1 IFL b Backup 289-45 Fuse TRS Note IV.4 NA NA NA NA 1,2,3,4 43 CONTAINMENT ELEVATOR D a Primary 289-47 Breaker EF Note IV.2, IV.3 10% of Type NA NA every 60 M 1,2,3,4 per R ELVEBKR2I 3B-I2CL b Backup 289-47 Fuse TRS Note IV.4 NA NA NA NA 1,2,3,4 44 REFUELING CAVITY DRAIN PUMP a Primary 289-48 Breaker EF Note IV.2, IV.3 10% of Type NA NA every 60 M 1,2,3,4 per R FS EBKR2J3B-IIJ b Backup 289-48 Fuse TRS Note IV.4 NA NA NA NA 1,2,3,4 (LBDCR -O2 Am.

45 REFUELING EQUIPMENT a Primary 289-50 Breaker EF r Note IV.2, IV.3 10% of Type NA NA every 60 M 1,2,3,4 HFD tLBDCR 15-022 Am, 31) per R FHSEBKR21 3B-1 2CR b Backup 289-50 Fuse TRS Note IV.4 NA NA NA NA 1,2,3,4 3/4 8-24 AMENDMENT NO. 131

3148 ELECTRICAL POWER SYSTEMS 314.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment electrical penetrations and penetration conductors are protected by either deenergizing circuits not required during reactor operation or by demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers during periodic surveillance.

The Surveillance Requirements applicable to lower voltage circuit breakers and fuses provides assurance of breaker and fuse reliability by testing at least one representative sample of each manufacturers brand of circuit breaker and/or fuse. Each manufacturers molded case and metal case circuit breakers and/or fuses are grouped into representative samples which are then tested on a rotating basis to ensure that all breakers and/or fuses are tested. If a wide variety exists within any manufacturers brand of circuit breakers and/or fuses it is necessary to divide that manufacturers breakers and/or fuses into groups and treat each group as a separate type of breaker or fuses for surveillance purposes.

The OPERABILITY of the motor-operated valves thermal overload protection and/or bypass devices ensures that these devices will not prevent safety related valves from performing their function. The Surveillance Requirements for demonstrating the OPERABILITY of these devices are in accordance with Regulatory Guide 1.106, Thermal Overload Protection for Electric Motors on Motor Operated Valves, Revision 1, March 1977.

Containment Penetration Conductor Overcurrent Protection Devices and uMotor Operated Valves Thermal Overload Protection and/or Bypass Devices, previously Tables 3.8-1 and 3.8-2, of the Technical Specifications have been incorporated into this manual.

3/49 REFUEL OPERATIONS

-*(CBDCR 13-003, Am. 124) 3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during CORE ALTERATIONS.

-(L8DCR 13-003, Am. 124)

CBDCR 15-024, Am. 129 LBDCF 14-025, Am. 132) 3/4.9.6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine ensure that: (1) the refueling machine will be used for movement of fuel assemblies, (2) the hoist has sufficient load capacity to lift a fuel assembly, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they ate inadvertently engaged during lifting operations.

The Technical Requirements Manual Action a. statement allows the movement of a fuel assembly to a safe condition using administrative controls in the event of a refueling machine failure.

The basis for the capacity of the Refueling Machine is determined by the sum of the weights of the Hoist box, Grapple, Fuel Assembly and CEA which is bounded by a minimum weight of 3200 lbs.

The basis for the overload cut off limit of 3350 lbs is calculated by adding 150 lbs to the capacity requirement of 3200 lbs. This overload cut off limit ensures the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged dw lifting operations.

LBDCR 15-024, Am. 129,14-025, Am. 132)

B 3/4 5a AMENDMENT NO. 13, 50, 124, 129, 132

-,(LBDCR 15-024, Am. 129)

REFUELING OPERATIONS 3/4.9.6 REFUELING MACHINE LIMITING CONDITION FOR OPERATION

,(LBDCR14-025,Am.132, )

3.9.6 The refueling machine shall be used for movement of fuel assemblies and shall be OPERABLE with:

a. A minimum capacity of 3100 pounds, and an overload cut off limit of less than or equal to 3250 pounds for the fuel mast.

APPLICABILITY: During movement of fuel assemblies within the reactor pressure vessel ACTION:

a. With the above requirements for the fuel mast not satisfied, suspend use of the fuel mast from operations involving pre-planned movement of fuel assemblies, and place the refueling machine load (fuel assembly) in a safe condition.

SURVEILLANCE REQUIREMENTS 4.9.6.1 The fuel mast used for movement of fuel assemblies shall be demonstrated OPERABLE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to the start of such operations by performing a load test of at least 3100 pounds and demonstrating an automatic load cut off when the fuel mast load is less than or equal to 3250 pounds.

4fLBDCR 15-024, Am. 129, LBDCR 14-025, Am. 132, LBDCR 15-036, Am. 133) 3/4 9-2 AMENDMENT NO. 42,432, 133

3/4 8 ELECTRICAL POWER SYSTEMS BASES 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment electrical penetrations and penetration conductors are protected by either deenergizing circuits not required during reactor operation or by demonstrating the OPERABILITY of primary and backup overcurrent protection circuit breakers during periodic surveillance.

The Surveillance Requirements applicable to lower voltage circuit breakers and fuses provides assurance of breaker and fuse reliability by testing at least one representative sample of each manufacturers brand of circuit breaker and/or fuse. Each manufacturers molded case and metal case circuit breakers and/or fuses are grouped into representative samples which are then tested on a rotating basis to ensure that all breakers and/or fuses are tested. If a wide variety exists within any manufacturers brand of circuit breakers and/or fuses it is necessary to divide that manufacturers breakers and/or fuses into groups and treat each group as a separate type of breaker or fuses for surveillance purposes.

The OPERABILITY of the motor-operated valves thermal overload protection and/or bypass devices ensures that these devices will not prevent safety related valves from performing their function. The Surveillance Requirements for demonstrating the OPERABILITY of these devices are in accordance with Regulatory Guide 1.106, Thermal Overload Protection for Electric Motors on Motor Operated Valves, Revision 1, March 1977.

Containment Penetration Conductor Overcurrent Protection Devices and Motor-Operated Valves Thermal Overload Protection and/or Bypass Devices, previously Tables 3.8-1 and 3.8-2, of the Technical Specifications have been incorporated into this manual.

3/49 REFUEL OPERATIONS

(LBDCR 13-003, Am. 124) 3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during CORE ALTERATIONS.

(LBDCR 13-003, Am. 124)

LBDCR 15-024, Am. 129 LBDCR 14-025, Am. 132, LBDCR 15-036, Am.

3/4.9.6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine ensure that: (1) the refueling machine will be used for movement of fuel assemblies, (2) the hoist has sufficient load capacity to lift a fuel assembly, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

The Technical Requirements Manual Action a. statement allows the movement of a fuel assembly to a safe condition using administrative controls in the event of a refueling machine failure.

The basis for the capacity of the Refueling Machine is determined by the sum of the weights of the Hoist box, Grapple, Fuel Assembly and CEA which is bounded by a minimum weight of 3100 lbs.

The basis for the overload cut off limit of 3250 lbs is calculated by adding 150 lbs to the capacity requirement of 3100 lbs. This overload cut off limit ensures the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

- LBDCR 15-024, Am. 129,14-025, Am. 132, LBDCR 6, Am. )

B 3/4 5a AMENDMENT NO. 13, 50, 121, 129, 132, 133

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE (DRN 07-136 Am. 111) 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES 3/4 8-4 4(DRN 07136 Am. 111)

-(DRN 05-880, Am. 100)

MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES 3/4 8-62

-(DRN 05-880, Am, 100) 3/4.9 REFUELING OPERATIONS (LBDCR 13-003, Am. 124) 3/4.9.5 COMMUNICATIONS 3/4 9-1

.(LBDCR 13-003, Am. 124)

-+(LBDCR 15-024, Am. 129) 3/4.9.6 REFUELING MACHINE 3/4 9-2 3/4.9.7 CRANE TRAVEL FUEL HANDLING BUILDING 3/4 9-3

.-(CBDCR 15-024, Am. 129) 3/4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM 3/4 9-4 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION 3/4 11-1

-.(DRN 02-216)

DOSE 3/4 11-16 LIQUID RADWASTE TREATMENT SYSTEM 3/4 11-17 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE 3/4 11-18 GASEOUS EFFLUENTS DOSE RATE 3/4 11-25 DOSE IODINE-131, IODINE-133, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM 3/4 11-26 (DRN 02-912)

GASEOUS RADWASTE TREATMENT 3/411-27

÷-(DRN 02-912) 3/4.11.3 SOLID RADIOACTIVE WASTE 3/4 11-29 3/4.11.4 TOTAL DOSE 3/4 11-30

÷-fDRN 02-216) 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM 3/4 12-1 3/4.12.2 LAND USE CENSUS 3/4 12-13 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 3/4 12-14

(LBDCR 15-033, Am. 134) 3/4.13 BEYOND DESIGN BASIS COMPONENTS 3/4.13.1 SPENT FUEL POOL INSTRUMENTATION 3/4 13-1 fLB0CR 15-033, Am 134) ha AMENDMENT NO. 58, 99,100, 118, 424, 42, 134

RESPONSIBILITY MATRIX SECTION ORGANIZATION CONTAINMENT SYSTEMS SHIFT TECHNICAL ADVISERS AIR TEMPERATURE SAFETY & ENGINEERING ANALYSIS CONTAINMENT ISOLATION VALVES OPERATIONS PLANT SYSTEMS COMPONENT COOLING WATER APPENDIX R SYSTEM ENGINEERING ELECTRICAL

-*(EC-15515, Am. 118) DESIGN ENGINEERING PROGRAM &

SNUBBERS COMPONENTS 4(EC-15515, AM. 118)

FIRE SUPPRESSION SYSTEMS SYSTEM ENGINEERING ELECTRICAL VENTILATION SYSTEMS SYSTEM ENGINEERING MECHANICAL ESSENTIAL SERVICES CHILLED WATER SYSTEM CHILLERS APPENDIX R SYSTEM ENGINEERING ELECTRICAL ELECTRICAL POWER SYSTEMS ELECTRICAL EQUIPMENT PROTECTIVE DEVICES DESIGN ENGINEERING ELECTRICAL RADIOACTIVE EFFLUENTS LIQUID & GASEOUS EFFLUENTS AND RADIOLOGICAL ENVIRONMENTAL MONITORING CHEMISTRY

-.(CBDCR 15-033, Am. 134)

BEYOND DESIGN BASIS COMPONENTS SPENT FUEL POOL LEVEL INSTRUMENTATION DESIGN ENGINEERING I&C

+..(CBDCR 15-033, Am. 134) iv AMENDMENT 17, 118, 134

(LBDCR 15-033, Am. 134) 3/4.13 BEYOND DESIGN BASIS COMPONENTS BASES 3/4.13.1 SPENT FUEL POOL LEVEL INSTRUMENTATION The spent fuel pool level instrumentation (SFPI) provides the capability of monitoring the spent fuel pooi water Jevel during an extended loss of offsite power following a Beyond Design Basis External Event (BDBEE) and meets the requirements of NRC Order EA-12-051, Issuance of Order To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation. The design, installation, maintenance and testing conforms to guidance provided in NEI 12-02 (Revision 1), Industry Guidance for Compliance with NRC Order EA-1 2-051, To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation.

Channel 1 or Channel 2 instruments can be out of service for testing, maintenance and/or calibration up to 90 days provided the other channel is functional. Additionally, compensatory actions must be taken if the instrumentation channel is not expected to be restored or is not restored within 90 days.

If both channels are inoperable, then actions to restore one channel must be initiated within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and implement compensatory measures within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

The TRM is annotated with a 3.0.4 exemption, allowing entry into the applicable Mode to be made with spent fuel pool level instrumentation INOPERABLE, as required by the Actions.

The SFPI system is self-calibrating with no need for periodic user calibration after initial installation and testing. The SR 4.13.1.7 day CHANNEL CHECK demonstrates (in conjunction with the instruments self-monitoring) continued operability and consistency with local spent fuel pool level measurement device.

SR 4.13.2 to verify functionality of each channel 60 days prior to the planned refueling outages is specifically required by NEI 12-02 and increases assurance that the instrumentation will be operable when the greatest heat load is in the spent fuel pool. Functionality is verified continuously throughout the operating cycle by the weekly CHANNEL CHECK (SR 4.13.1) which also confirms changes in level indication subsequent to spent fuel pool level changing evolutions.

.-(LBDCR 15-033. Am. 134)

B 3/4 13 AMENDMENT NO. 134

-4(ORN 02.1639)

ELECTRICAL POWER SYSTEMS 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS OPERATING LIMITING C0NDmON FOR OPERATION 3.8.3.1 The rectifiers for the following Static Uninterruptible Power Supplies (SUPS) shall be OPERABLE.

a. SUPS-1-S

b. SUPS-3MB-S

c. SUPS-3MC-S U. SUPS-3E3i

e. SUPS-3A-S

f. SUPS-3B-S

g. SUPS-3AB-S 4(LBDCR 15-008 Am. 135, LBDCR 15-009 Am. 135)

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

(DRN 04-1191, Am. 91)

a. With any of the above listed SUPS rectifiers inoperable and the associated SUPS is not being supplied from the bypass AC power, restore the rectifier to operable status or verify the two associated battery chargers are in service within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; otherwise, enter TRM LCO 3.0.3.

(DRN 04-1191, Am. 91)

SURVEILLANCE REQUIREMENTS 4.8.3.1 No additional surveillance requirements other than those required by Technical Specifications 4.8.3.

÷-(DRN 02-1639)

(DRN 02-1639; 05-1013,07-136, Am. 111) 3/4 8-3 AMENDMENT NO. 34, 67, 91, 4Q3 4-44, 135 (0RN 02-1639; 05-1013,07-136, Am. 111)

RESPONSIBILITY MATRIX SECTION ORGANIZATION CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE -------SHIFT TECHNICAL ADVISERS AIR TEMPERATURE SAFETY & ENGINEERING ANALYSIS CONTAINMENT ISOLATION VALVES --OPERATIONS PLANT SYSTEMS COMPONENT COOLING WATER APPENDIX R--- SYSTEM ENGINEERING ELECTRICAL

(EC-15515, Am. 118)

-DESIGN ENGINEERING PROGRAM &

-fEC-15515,AM. 118) COMPONENTS FIRE SUPPRESSION SYSTEMS----- SYSTEM ENGINEERING ELECTRICAL VENTILATION SYSTEMS-----------------------SYSTEM ENGINEERING MECHANICAL ESSENTIAL SERVICES CHILLED WATER SYSTEM CHILLERS APPENDIX R SYSTEM ENGINEERING ELECTRICAL ELECTRICAL POWER SYSTEMS ELECTRICAL EQUIPMENT PROTECTIVE DEVICES DESIGN ENGINEERING ELECTRICAL RADIOACTIVE EFFLUENTS LIQUID & GASEOUS EFFLUENTS AND RADIOLOGICAL ENVIRONMENTAL MONITORING CHEMISTRY

-(LBOCR 15-033, Am. 134)

BEYOND DESIGN BASIS COMPONENTS SPENT FUEL POOL LEVEL INSTRUMENTATION DESIGN ENGINEERING I&C 4(LBDCR 15-033, Am. 134)

(LBD(R 16-0Q.., Ary,. 136)

DIVERSE AND FLEXIBLE COPING STRATEGIES (FLEX) EQUIPMENT OPERATIONS FLEX FLUID AND ELECTRICAL CONNECTIONS OPERATIONS (LBDCR 16-008, Am. 136) iv AMENDMENT 17, 118, 4-34T 136

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE

,(DRN 07-136 Am. 111) 3)4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES 3/4 8-4 HDRN 07-136 Am. 111)

-÷(DRN 05-880, Am. 100)

MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES 3/4 8-62

-(DRN 05-880. Am. 100) 3/4.9 REFUELING OPERATIONS (LBDCR 13-003, Am. 124) 3/4.9.5 COMMUNICATIONS 3/4 9-1

÷-(LBDCR 13-003, Am. 124)

-.(LBDCR 15-024, Am. 129) 3/4.9.6 REFUELING MACHINE 3/4 9-2 3/4.9.7 CRANE TRAVEL FUEL HANDLING BUILDING 3/4 9-3 i(CBDCR 15-024, Am. 129) 3/4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM 3/4 94 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS CONCENTRATION 3/4 11-1 (DRN 02-216)

DOSE 3/4 11-16 LIQUID RADWASTE TREATMENT SYSTEM 3/4 11-17 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE 3/4 11-18 GASEOUS EFFLUENTS DOSE RATE 3/4 11-25 DOSE IODINE-131, IODINE-I 33, TRITIUM AND RADIONUCLIDES IN PARTICULATE FORM 3/4 11-26 (DRN 02-91 2)

GASEOUS RADWASTE TREATMENT 3/4 11-27 4(DRN 02-912) 3/4.11.3 SOLID RADIOACTIVE WASTE 3/4 11-29 3/4.11.4 TOTAL DOSE 3/4 11-30

+-(DRN 02-216) 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM 3/4 12-1 3/4.12.2 LAND USE CENSUS 3/4 12-13 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM 3/4 12-14

-(LBDCR 15-033, Am. 134) 3/4.13 BEYOND DESIGN BASIS COMPONENTS 3/4.13.1 SPENT FUEL POOL INSTRUMENTATION 3/4 13-1 (CBDCR 15-033, Am 134)

-(LB0CR 16-008, Am. 136) 3/4.13.2 DIVERSE AND FLEXIBLE COPING STRATEGIES (FLEX) EQUIPMENT 3/4 13-2 3/4.13.3 FLEX FLUID AND ELECTRICAL CONNECTIONS 3/4 13-5

, {LBDCR 16-008, Am. 136)

Ila AMENDMENT NO. 58, 99, 100, 118, 124, 129, 134, 136

INDEX SECTION PAGE 3/4.9 REFUELING OPERATIONS

(CBUCR 13-003, Am. 124) 3/4.9.5 COMMUNICATIONS B 3/4 5a 4(LBDCR 13-003, Am. 124)

(LBDCR 15-024, Am. 129) 3/4.9.6 REFUELING MACHINE B 3/4 5a 3/4.9.7 CRANE TRAVEL FUEL HANDLING BUILDING B 3/4 5b 4(LBDCR 15-024, Am. 129) 3/4.9.12 FUEL HANDLING BUILDING VENTILATION SYSTEM B 3/4 5b 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1.1 CONCENTRATION B3/46 3/4.11.1.2 DOSE B3/46 3/4.11.1.3 LIQUID RADWASTE TREATMENT SYSTEM B 3/47 3/4.11.2.1 DOSE RATE B 3/47 3/4.11.2.2 DOSE NOBLE GASES

- B 3148

+(DRN 02-216) 3/4.11.2.3 DOSE IODINE-131, IODINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM B 3/49 3/4.11.2.4 GASEOUS RADWASTE TREATMENT 83/4 10

<tORN 02-216) 3/4.11.3 SOLID RADIOACTIVE WASTE B 3/4 10 3/4.11.4 TOTAL DOSE 83/4 10 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM B 3/4 11

(DRN 05-880, Am. 100) 3/4.12.2 LAND USE CENSUS B 3/4 12

<(DRN 05-880, Am. 100) 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM B 3/412 (LBDCR 16-008, Am. 136) 3/4.13 BEYOND DESIGN BASES COMPONENTS 3/4.13.1 SPENT FUEL POOL LEVEL INSTRUMENTATION 83/4 13 3/4.13.2 DIVERSE AND FLEXIBLE COPING STRATEGIES (FLEX) EQUIPMENT B 3/4 14 3/4.13.3 FLEX FLUID AND ELECTRICAL CONNECTIONS-- B 3/4 14 (LSDCR 16.008, Am. 136)

IVa AMENDMENT NO. 124 129 136

INDEX LIST OF TABLES TABLE PAGE CORN 05480, Mi. 100) 3.7-1 IMPACTED FIRE AREAS WITH CCW PUMP(S) INOPERABLE 3/4 7-le CORN 05480, Am. 100) 3.7-2 SPRAY AND/OR SPRINKLER SYSTEMS 3/4 7-6 3.7-4 FIRE HOSE STATIONS 3/4 7-9 3.7-5 YARD FIRE HYDRANTS AND ASSOCIATED HYDRANT HOSE HOUSES 3/4 7-12 3.7-12 IMPACTED FIRE AREAS WITH CHW PUMP(S) OR CHILLER(S)

INOPERABLE 3/4 7-I 4aY (EC-15515,Am. 118) 3.7.8-1 LIST OF SNUBBERS WITH SEISMIC LOADS ONLY 3/4 7-le(3) 3.7.8-2 LIST OF SNUBBERS WITH DYNAMIC LOADS 3/4 7-Ie(5)

÷ (EC-15515 Am. 118)

-* CORN 02-912) 3.8-1 CONTAINMENT PENETRATION CONDUCTOR OVER-CURRENT PROTECTIVE DEVICES 3/4 8-la 3.8-2 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND/OR BYPASS DEVICES 3/4 8-62

÷ (DRN 02-912)

Am. 136) 3.13-1 FLEX EQUIPMENT THAT DIRECTLY PERFORMS A FLEX MITIGATION STRATEGY FOR THE KEY SAFETY FUNCTIONS 3/4 13-4 3.13-2 FLEX CONNECTIONS THAT DIRECTLY PERFORM A FLEX MITIGATION STRATEGY FOR THE KEY SAFETY FUNCTIONS 3/4 13-6

- (LBDCR 16-008, Am. 136) 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING -

AND ANALYSIS PROGRAM 3/4 11-2

- (DRN 02-216) 4.11-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 314 11-19

- (DRN 02-216) 3.12-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3/4 12-3 3.12-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES 3/4 12-10 4.12-f DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS 3/4 1 2-11

-+ CORN 04-1244, Am 99) 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7-1 (DRN 04-1244, Am 99)

VI AMENDMENT NO. 38, 47, 60, 51, 58, 99, 100, 44&, 136

TABLE 3.3-11 (Continued)

FIRE DETECTION INSTRUMENTS FIRE ELEVATION HEAT SMOKE AREA ROOM NAME/NUMBER *(/y) *(xly)

(ft)

1. REACTOR AUXILIARY BUILDING (Continued)

RAB 22 Drumming Station ÷21 0/5 RAB 23 Corridor to CCW Pumps, Corridor +21 0/18 to CCW Heat Exchangers and Corridor to Emergency Diesel Gen.

RAB 24 Hot Machine Shop +21 17/0 RAB 25 Equip. Access Area Wing Area +21 12/0 RAB 27 H&V Room +7 0/4

+(DRN 02-818, Am. 63)

Electrical Area and Health Physics +7 0/31

(DRN 02-818, Am. 63)

Offices l&C Room +7 0/5

+(DRN 04.450, Am. 88)

Communications Equip. Room +7 1/0

+(DRN 04-956, Am. 89)

+(DRN 02450, Am. 88)

+(DRN 04-956, Am. 89)

+(DRN 06-876, Am. 115)

RAB 30 Administration Area (HP) -4 32/0

(DRN 06-876, Am. 115)

RAB 31 Corridors and Passageways 0/17 RAB 32 Wing Area Auxiliary Component

- -35 22/0 Cooling Water Pump -4 21/0 RAB 33 S/D Cooling Heat Exchangers A&B -35 0/9 RAB 34 Valve Gallery Room A&B A -15.5 5/0 RAB 35 Safety Injection Pump Room B -35 5/0 RAB 36 Safety lnjection Pump Room A -35 6/0 RAB 37 Motor-Driven Emergency Feedpump A -35 0/1 RAB 38 Motor-Driven Emergency Feedpump B -35 1/0

+(EC-1939, Am. 126)

RAB 39 Corridors & General Equip. Areas 8/22

+(EC-1939, Am. 126)

RAB 40 Diesel Storage Tank A -35 1/0 RAB 41 Diesel Storage Tank B -35 1/0 3(EC-48145, LBDCR 14.028, Am. 136)

RAB 44 FLEX Diesel Generator Enclosure +41 2/0 ffEC48145, LBDCR 14-028, Am. 136)

2. REACTOR CONTAINMENT BUILDING**

+(DRN 02-238, Am. 52)

+(EC-25884, Am. 123)

RCB Electrical Penetration Area A&B +21 44/0 RCB Reactor Cable Trays +46 16/0 CTA Cooling Tower A 16/0 1/0 CTB Cooling Tower B 2/0 1/0 3/4 3-21a AMENDMENT NO. 22,52 63, 88, 89,115, 4-23 426, 136

)LBDCR 16-008, Am. 136)

BEYOND DESIGN BASIS COMPONENTS

- tLBDCR1S-008,Am. 136)

(CBDCR 15-033, Am. 134) 3/4.1 3.1 SPENT FUEL POOL LEVEL INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.13.1 BOTH spent fuel pool level instruments shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a. With Channel I or Channel 2 spent fuel pool level instrument inoperable, restore the spent fuel pool level instrument within 90 days or implement compensatory measures.

b. With Channel I and Channel 2 spent fuel pool level instruments inoperable, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months initiate actions to restore one of the channels of instrumentation and within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months implement compensatory measures.

c. TRM LCO 3.0.4 is not applicable.

SURVEILLANCE REQUIREMENTS 4.13.1 Perform a Channel Check between both electronic spent fuel pool level instruments and the local level measurement device every 7 days.

4.13.2 Verify functionality of Channel 1 and Channel 2 within 60 days of each planned refueling outage.

-(LBDCR 15-033, Am. 134) 3/4 13-1 AMENDMENT 434, 136

-*(LBDCR 16-008, Am. 136)

BEYOND DESIGN BASES COMPONENTS 3/4.13.2 DIVERSE AND FLEXIBLE COPING STRATEGIES (FLEX) EQUIPMENT LIMITING CONDITION FOR OPERATION 3.13.2 The FLEX equipment shown in Table 3.13-1 shall be OPERABLE.

APPLICABILITY: At alt times.

ACTION:

NOTE: Separate entry is allowed for each component listed in TRM Table 3.13-1.

a. With one or more N+1 Building FLEX components (Column 3) specified in Table 3.13-1 inoperable, restore the FLEX component within 90 days.

b. With one j more N RAB FLEX components (Column 2) specified in Table 3.13-1 inoperable either:

1) Relocate the N+1 Building FLEX component to meet N RAB FLEX capability within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and restore the N RAB FLEX component within 90 days if the N÷1 Building FLEX component relocation can satisfy the FLEX functions for all events; OR

2) Relocate the NH Building FLEX component to meet N RAB FLEX capability within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and restore the N RAB FLEX component within 45 days if the N÷1 Building FLEX component relocation cannot completely satisfy the FLEX functions for all events.

c. With both the N RAB FLEX and N-i-i Building FLEX components for any FLEX Function specified in Column 1 of Table 3.13-1 inoperable, restore the FLEX function within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

d. The provisions of TRM LCO 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.13.2.1 Each FLEX Diesel Generator shall be demonstrated OPERABLE by:

a. Performing an unloaded engine run and verifying proper operation at least once per 6 months, and

b. Performing a 30% of rated prime load test for a minimum of two hours once per year, and

c. Performing a 100% of rated prime load test for a minimum of two hours once per 3 years, and

d. Applicable to the N RAB FLEX Generator only, verify the fuel oil tank is maintained at least 7/8 full at least once per 31 days and after each operation of the N RAB FLEX Diesel Generator.

- (LBDCR 16-008, Am. 136) 3/4 13-2 AMENDMENT 136

(LB0CR 16-008, Am. 136)

BEYOND DESIGN BASES COMPONENTS 3/4.13.2 DIVERSE AND FLEXIBLE COPING STRATEGIES (FLEX) EQUIPMENT SURVEILLANCE REQUIREMENTS (Continued) 4.13.2.2 Each FLEX Core Cooling Pump shall be demonstrated OPERABLE by:

a. Ensuring the shaft rotates freely by hand with no binding at least once per 3 months, and

b. Performing motor insulation test and a motor/pump bump test once per 5 years.

4- (LBDCR 16-008, Am. 136)

/

3/4 13-3 AMENDMENT 136

tLBDCR 16-008, Am. 136)

Table 3.1 3-1 FLEX EQUIPMENT THAT DIRECTLY PERFORMS A FLEX MITIGATION STRAEGY FOR THE KEY SAFETY FUNCTIONS FLEX FUNCTION N RAB FLEX N+1 BUILDING FLEX (Column 1) COMPONENTS COMPONENTS (Column 2) (Column 3)

AC Power Source for FLEX FLEX Diesel Generator FLEX Diesel Generator Equipment Required to Implement (FLEXMDSGOO1) (FLEXMDSGOO2) the FLEX Strategies Core Cooling via Steam FLEX Core Cooling Pump FLEX Core Cooling Pump Generators (Modes 1-4) (FLEXMPMP000I) (FLEXMPMP0005)

OR Reactor Coolant System Makeup (Modes 5, 6)2 TABLE NOTATIONS 1

Separate entry is allowed for each component listed in TRM Table 3.13-1.

2 Function is NOT required if reactor pressure vessel is defueled (Core Off-load).

(LBOCR 16-008, Am. 136) 3/4 13-4 AMENDMENT 136

(LBDCR 16-008, Am. 136)

BEYOND DESIGN BASES COMPONENTS 3I4.13.3 FLEX FLUID AND ELECTRICAL CONNECTIONS LIMITING CONDITION FOR OPERATION 3.13.3 The FLEX Fluid and Electrical Connection Components Required to Implement the FLEX Strategy when the FLEX Equipment is connected at the point specified in Table 3.1 3-2 shall be OPERABLE.

APPLICABILITY: In accordance with Table 3.1 3-2.

ACTION:

NOTE: Separate entry is allowed for each component listed in TRM Table 3.13-2.

a. With the Primary or Secondary Connection for one or more Safety Functions/FLEX components specified in Table 3.1 3-2 inoperable, restore the FLEX connection within 90 days.

b. With the Primary and Secondary Connection for one or more Safety Functions/FLEX components specified in Table 3.13-2 inoperable, restore site FLEX capability within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

c. The provisions of TRM LCO 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS NONE (LBDCR 16-008, Am. 136) 3/4 13-5 AMENDMENT 136

-*(LBDCR 16-006, Mi. 136)

Table 3.1321 FLEX CONNECTIONS THAT DIRECTLY PERFORM A FLEX MITIGATION STRATEGY FOR THE KEY SAFETY FUNCTIONS CONNECTION PURPOSE APPLICABLE MODE PRIMARY SECONDARY OR OTHER SPECIFIED CONNECTION CONNECTION CONDITION POINT POINT FLEX Diesel Generator At All Times FLEXEPNL0001 Output Connection Panel FLEX Diesel Generator Input FLEXEPNL31B FLEXEPNL31A At All Times toSwitchgear3lAand3lB FLEXEBKR31 B-8C FLEXEBKR31 A-6B FLEX Core Cooling Pump FLEXEDSC3IAB-4C1 FLLXEDSC31AB4C1 1 ,2,3,4 Power Source2 FLEXEDSC31 B-6C1 FLEXEDSC31A-5C1 FLEX Core Cooling Pump 5,6 FLEXEDSC31B-6C1 Power Source7 91 FLEXEDSC31 A-5C1 91 FLEXEDSC31 AB4C1 FLEX Core Cooling Pump 1,2,3,4 EFW-2121B EFW-2121A Injection to SG5 FLEX Core Cooling Pump 5,6 SI-2071A SI-2071AB flJeCt)Ofl to RCS67 Safety Injection Tank 1,2,3,4 FLEXEDSC311B-2D Isolation Valves Power and Source Connections3 FLEXEDSC31 JA-2D Wet Cooling Tower Suction 1 ,2,3,4 ACC-1 OOA Source Connection4 Refueling Water Storage At All Times Sl-7151 Pool Suction Source Connection4 Condensate Storage Pool 1,2,3,4 EFW-1O71AB Suction Piping FLEX Connection4 Component Cooling Water At All Times CMU-5041 B Make-Up Pump Spent Fuel Pool Cooling Suction4

- (CBOCR 16-008, Am. 136) 3/4 13-6 AMENDMENT 136

(LBDCR 16-008, Am. 136)

TABLE 3.13-2 (Continued)

TABLE NOTATIONS Separate entry is allowed for each component listed in TRM Table 3.13-2.

2 Enter Action b. FLEXEDSC31AB-4C1 is required to be operable to support the core cooling strategy and is not dependent upon which FLEX Core Cooling Pump power source has been selected for FLEX implementation.

Enter Action b. Both breakers and connection points are required to be operable to allow operation of the SIT Outlet Isolation Valves.

Enter Action b. All suction path components associated with the listed connection point(s) must be functional to support FLEX implementation.

The FLEX Core Cooling Pump will be able to inject water to the Steam Generators once the pressure is 250 psia to 260 psia.

6 Makeup to the RCS with Steam Generators not available Function is NOT required if reactor pressure vessel is defueled (Core Off-load).

(LBDCR 16-008, Am. 136) 3/4 13-7 AMENDMENT 136

-(LBDCR 15-033, Am. 134) 3/4.13 BEYOND DESIGN BASIS COMPONENTS BASES 3/4.13.1 SPENT FUEL POOL LEVEL INSTRUMENTATION The spent fuel pool level instrumentation (SFPI) provides the capability of monitoring the spent fuel pool water level during an extended loss of offsite power following a Beyond Design Basis External Event (BDBEE) and meets the requirements of NRC Order EA-1 2-051, Issuance of Order To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation. The design, installation, maintenance and testing conforms to guidance provided in NEI 12-02 (Revision 1),

Industry Guidance for Compliance with NRC Order EA-12-051, To Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation.

Channel I or Channel 2 instruments can be out of service for testing, maintenance and/or calibration up to 90 days provided the other channel is functional. Additionally, compensatory actions must be taken if the instrumentation channel is not expected to be restored or is not restored within 90 days.

If both channels are inoperable, then actions to restore one channel must be initiated within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and implement compensatory measures within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

The TRM is annotated with a 3.0.4 exemption, allowing entry into the applicable Mode to be made with spent fuel pool level instrumentation INOPERABLE, as required by the Actions.

The SEPt system is self-calibrating with no need for periodic user calibration after initial installation and testing. The SR 4.13.1 7-day CHANNEL CHECK demonstrates (in conjunction with the instruments self-monitoring) continued operability and consistency with local spent fuel pool level measurement device.

SR 4.13.2 to verify functionality of each channel 60 days prior to the planned refueling outages is specifically required by NEI 12-02 and increases assurance that the instrumentation will be operable when the greatest heat load is in the spent fuel pool. Functionality is verified continuously throughout the operating cycle by the weekly CHANNEL CHECK (SR 4.13.1) which also confirms changes in level indication subsequent to spent fuel pool level changing evolutions.

(CBDCR 15-033, Am. 134)

-.(CBDCR 16-008, Am. 138) 3/4.13.2 and 3/4.13.3 DIVERSE AND FLEXIBLE COPING STRATEGIES (FLEX) EQUIPMENT AND FLEX FLUID AND ELECTRICAL CONNECTIONS NRC Order EA-1 2-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, required plants to provide reliable diverse and flexible strategies (FLEX) in partial response to the March 2011 Fukushima accident. NRC interim staff guidance ]LD-ISG-2012-Q1 endorsed NEI 12-06, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, as an acceptable approach for satisfying the requirements of Order EA-12-049. TRM Sections 3.13.2 and 3.13.3 directly implement the requirements contained in Section 11.5 of NEI 12-06. Primary and backup methods and equipment have been established to ensure key safety functions can be met during a Beyond Design Basis External Event (BDBEE). FLEX equipment is required to be OPERABLE at all times since a BDBEE could occur regardless of an operational MODE.

(LBDCR 16.008, Am. 136)

B 3/4 13 AMENDMENT NO. 4-34, 136

3/4.13 BEYOND DESIGN BASIS COMPONENTS BASES (LBDCR 16-008, Am. 136) 3/4.13.2 and 3/4.13.3 DIVERSE AND FLEXIBLE COPING STRATEGIES (FLEX) EQUIPMENT AND FLEX FLUID AND ELECTRICAL CONNECTIONS (Continued)

The Conditions, Required Actions, and Completion Times are in accordance with Section 1 1.5 of NEI 12-06. Potential compensatory measures which may be considered include obtaining additional equivalent backup equipment.

If a Technical Specification LCO has been entered and is limiting the out-of-service time for an associated FLEX component or flow path, then the requirements of the Technical Specification govern the action of restoration of the FLEX equipment. The associated Flex TRM does not need to be entered in these instances.

FLEX electrical connection points are identified by the FLEX electrical disconnect associated with the component of concern. However, this does not mean that the TRM is applicable to the identified electrical disconnect only. The electrical connection point also would apply to any associated receptacle, disconnect, transfer switch, breaker, power panel, or switchgear that is requited to provide the electrical power to the specified component. For example, the associated charging pump breaker(s) would be required to supply power to the FLEX Core Cooling Pump from the associated 31 bus(es).

FLEX mechanical connection points are the point of connecting FLEX associated fluid piping. If the mechanical connection point is isolated by other valves such that fluid flow cannot be transferred as required, even if the TRM identified connection valve is intact then the IRM would be applicable.

NEI 12-06 provides guidance for Shutdown and Refueling Modes of operation. NEI 12-06 discusses that FLEX Strategies are not explicitly designed for outage conditions due to the small fraction of the operating cycle spent in an outage condition, generally less than 10%. NEI 12-06 does require that FLEX equipment remains available during outages to support Reactor Coolant System makeup to support core cooling. The guidance states a systematic approach to shutdown safety risk identification and planning along with the availability of the FLEX equipment is the most effective way to enhance safety during periods the unit is shutdown. The objective required to manage risk and maintain key safety functions goes beyond compliance with Technical Specifications during shutdown.

FLEX consists of N and N÷1 components. The N components are those items which have been pre-staged in the Reactor Auxiliary Building (RAB) along with the required support equipment to allow implementation. The N+l components are staged in the N+1 Building outside of the Protected Area which are primarily redundant major components of those pre staged in the RAB. The LCO time for N components is of a shorter duration in the event they are declared inoperable due to the reliance on them to be the primary method of implementing the FLEX Strategy.

-(LBOCR16-008,Am. 136)

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3/4.13 BEYOND DESIGN BASIS COMPONENTS BASES

(LBDCR 16-008. Am. 136) 3/4.13.2 and 3/4.13.3 DIVERSE AND FLEXIBLE COPING STRATEGIES (FLEX) EQUIPMENT AND FLEX FLUID AND ELECTRICAL CONNECTIONS (Continued)

Action 3.13.2.b.1 applies to N-f-I FLEX Building components which have actually been located to take the place of N RAB FLEX components and can satisfy the FLEX functions for all events.

Action 3.13.2.b.2 applies to N-i-i FLEX Building components which have been located to take the place of N RAB FLEX components and the FLEX functions are not satisfied for all events. For example, moving the N+1 FLEX Diesel Generator into the RAB does not satisfy all events since it is required to be moved outside of the RAB to allow it to be operated; therefore, this does not allow the functions for a flooded site to be met.

Moving the N+1 FLEX Core Cooling Pump into the RAB does not satisfy FLEX requirements unless it is actually placed on the -35 elevation of the RCA to allow access to the connection points.

- (LBDCR 16-008, Am. 136)

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