ML112430334

Issuance of Amendment No. 172, Adoption of TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation

ML112430334
Person / Time
Site:	River Bend
Issue date:	11/21/2011
From:	Wang A Plant Licensing Branch IV
To:	Entergy Operations
Wang, A B, NRR/DORL/LPLIV, 415-1445
References
TAC ME6048 TSTF-514, Rev. 3
Download: ML112430334 (16)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 November 21, 2011 Vice President, Operations Entergy Operations, Inc.

River Bend Station 5485 US Highway 61 N S1. Francisville, LA 70775 SUB..IECT: RIVER BEND STATION, UNIT 1 -ISSUANCE OF AMENDMENT RE:

ADOPTION OF TSTF-514, REVISION 3, "REVISE BWR OPERABILITY REQUIREMENTS AND ACTIONS FOR RCS LEAKAGE INSTRUMENTATION" (TAC NO. ME6048)

Dear Sir or Madam:

The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 172 to Facility Operating License No. NPF-47 for the River Bend Station, Unit 1. This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated April 11, 2011.

The amendment modifies TS 3.4.7, "RCS [Reactor Coolant System] Leakage Detection Instrumentation," to define a new time limit for restoring inoperable reactor coolant system (RCS) leakage detection instrumentation to operable status; establish alternate methods of monitoring RCS leakage when one or more required monitors are inoperable; and make TS Bases changes which reflect the proposed changes and more accurately reflect the contents of the facility design basis related to operability of the RCS leakage detection instrumentation.

These changes are consistent with NRC-approved Revision 3 to Technical Specification Task Force (TSTF) Change Traveler TSTF-514, "Revise BWR [Boiling-Water Reactor] Operability Requirements and Actions for RCS Leakage Instrumentation," as part of the consolidated line item improvement process.

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

Sincerely,

~WQ~

Alan Wang, Proj:c9M~nager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-458

Enclosures:

1. Amendment No. 172 to NPF-47

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

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ENTERGY GULF STATES LOUISIANA. LLC AND ENTERGY OPERATIONS, INC.

DOCKET NO. 50-458 RIVER BEND STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 172 License No. NPF-47

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

A. The application for amendment by Entergy Operations, Inc. (the licensee), dated April 11, 2011, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, 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 (ij) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this license 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.

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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 Facility Operating License No. NPF-47 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 172 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. EOI shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. The license amendment is effective as of its date of issuance and shall be implemented within 60 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License No. NPF-47 and Technical Specifications Date of Issuance: November 21, 2011

ATTACHMENT TO LICENSE AMENDMENT NO. 172 FACILITY OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-458 Replace the following pages of the Facility Operating License No. NPF-47 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.

Facility Operating License Remove

-3 Technical Specifications Remove 3.4-18 3.4-18

-3 (3) EOI, pursuant to the Act and 10 CFR Part 70, to receive, possess and to use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4) EOI, 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; (5) EOI, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) EOI, 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 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 EOI is authorized to operate the facility at reactor core power levels not in excess of 3091 megawatts thermal (100% rated power) in accordance with the conditions specified herein. The items identified in Attachment 1 to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 172 and the Environmental Protection Plan contained in Appendix 8, are hereby incorporated in the license. EOI shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Amendment No. 172

RCS Leakage Detection Instrumentation 3.4.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Drywell air cooler -----------------N OTE ------------.-

condensate flow rate Not applicable when the required monitoring system drywell atmospheric monitoring inoperable. system is inoperable.

C:1 Perform SR 3.4.7.1. Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />

---

NOTE------ D.1 Analyze grab samples of Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Only applicable when the the drywell atmosphere.

drywell atmospheric gaseous AND monitoring system is the only OPERABLE monitor. D.2 Monitor RCS leakage by

-_.... ..........-------_.. ........ administrative means.

Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D. Drywell floor drain sump AND monitoring system D.3.1 Restore drywell floor drain 7 days inoperable. sump monitoring system to AND OPERABLE status.

Drywell air cooler OR condensate flow rate D.3.2 Restore drywell air cooler 7 days monitoring system condensate flow rate inoperable. monitoring system to OPERABLE status.

E. Required drywell E.1 Restore required drywell 30 days atmospheric monitoring atmospheric monitoring system inoperable. system to OPERABLE status.

AND OR Drywell air cooler condensate flow rate E.2 Restore drywell air cooler 30 days monitoring system condensate flow rate inoperable. monitoring system to OPERABLE status.

F. Required Action and F.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A. B. C. AND D. or E not met.

F.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> G. All required leakage G.1 Enter LCO 3.0.3. Immediately detection systems inoperable.

RIVER BEND 3.4-18 Amendment No. 81 1ae. 172

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 172 TO FACILITY OPERATING LICENSE NO. NPF-47 ENTERGY OPERATIONS, INC.

RIVER BEND STATION, UNIT 1 DOCKET NO. 50-458

1.0 INTRODUCTION

By application dated April 11, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11105A030), Entergy Operations, Inc. (Entergy, the licensee),

proposed changes to the Technical Specifications (TSs) River Bend Station, Unit 1 (RBS). The proposed changes would revise TS 3.4.7, "RCS [Reactor Coolant System] Leakage Detection Instrumentation," and include TS Bases changes that summarize and clarify the purpose of the TS and the specified safety function of the leakage detection monitors.

Specifically, the amendment would modify the TSs to define a new time limit for restoring inoperable reactor coolant system (RCS) leakage detection instrumentation to operable status; establish alternate methods of monitoring RCS leakage when one or more required monitors are inoperable; and make TS Bases changes which reflect the proposed changes and more accurately reflect the contents of the facility design basis related to operability of the RCS leakage detection instrumentation. These changes are consistent with U.S. Nuclear Regulatory Commission (NRC)-approved Revision 3 to Technical Specification Task Force (TSTF) Change Traveler TSTF-514, "Revise BWR [Boiling-Water Reactor] Operability Requirements and Actions for RCS Leakage Instrumentation." The availability of this TS improvement was announced in the Federal Register on December 17,2010 (75 FR 79048), as part of the consolidated line item improvement process. The availability of this proposed amendment to TS 3.4.7 and the no significant hazards consideration was published in the Federal Register on June 28,2011 (76 FR 37847).

2.0 REGULATORY EVALUATION

The NRC's regulatory requirements related to the content of the TSs are contained in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, "Technical specifications." Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control Enclosure 2

-2 settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements; (4) design features; and (5) administrative controls. The rule does not specify the particular requirements to be included in a plant's TSs. The regulations in 10 CFR 50.26(c)(2)(i), "Limiting conditions for operations," state, in part, that Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met.

The regulations in 10 CFR 50.36(c)(2)(ii) list four criteria for determining whether particular items are required to be included in the TS LCOs. Criterion 1 applies to "[i]nstalled instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary." As described in the Federal Register notice associated with this regulation (60 FR 36953; July 16, 1995), the scope of TSs includes two general classes of technical matters: (1) those related to prevention of accidents, and (2) those related to mitigation of the consequences of accidents. Criterion 1 addresses systems and process variables that alert the operator to a situation when accident initiation is more likely, and supports the first of these two general classes of technical matters which are included in TS.

The NRC's guidance for the format and content of boiling-water reactor (BWR) TSs can be found in NUREG-1434, Revision 3, "Standard Technical Specifications General Electric Plants, BWR/6" (STS) (ADAMS Accession No. ML041910220). STS 3.4.7, "RCS Leakage Detection Instrumentation," in NUREG-1434, Revision 3, contains the guidance specific to the RCS leakage detection instrumentation for BWRs.

The Bases for STS 3.4.7 contained in NUREG-1434, Revision 3, provide background information, the applicable safety analyses, a description of the LCO, the applicability for the RCS leakage detection instrumentation TS, and describe the Actions and Surveillance Requirements. The TS Bases provide the purpose or reason for the TS which are derived from the analyses and evaluation included in the safety analysis report, and for these Specifications, the ReS leakage detection instrumentation design assumptions and licensing basis for the plant.

As stated in NRC Information Notice (IN) 2005-24, "Nonconservatism in Leakage Detection Sensitivity," dated August 5,2005 (ADAMS Accession No. ML051780073), the reactor coolant activity assumptions for primary containment/drywell atmosphere gaseous radioactivity monitors may be nonconservative. This means the monitors may not be able to detect a 1-gallon per minute (gpm) leak within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> under all likely operating conditions.

The issue described in IN 2005-24 has raised questions regarding operability requirements for primary containment/drywell atmosphere gaseous radioactivity monitors. TSTF-514, Revision 3, revises the TS Bases to summarize the proposed TS changes and more accurately describe the contents of the facility design basis related to operability of the RCS leakage detection instrumentation. Part of the TS Bases changes revise the specified safety function of the RCS leakage detection monitors to specify the required instrument sensitivity level. In

-3 addition, TSTF-514, Revision 3, includes a new TS Condition for RCS leakage detection instrumentation to establish required actions for operation during conditions of reduced monitoring sensitivity because the gaseous radioactivity instrumentation is the only operable instrument.

The regulations in 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 30, "Quality of reactor coolant pressure boundary," require means for detecting and, to the extent practical, identifying the location of the source of RCS leakage. NRC Regulatory Guide (RG) 1.45, Revision 0, "Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973, describes acceptable methods of implementing the GDC 30 requirements with regard to the selection of leakage detection systems for the reactor coolant pressure boundary (RCPB).

RG 1.45, Revision 0, Regulatory Position C.2, states that, Leakage to the primary reactor containment from unidentified sources should be collected and the flow rate monitored with an accuracy of one gallon per minute (gpm) or better.

RG 1.45, Revision 0, Regulatory Position C.3 states that, At least three separate detection methods should be employed and two of these methods should be (1) sump level and flow monitoring and (2) airborne particulate radioactivity monitoring. The third method may be selected from the following:

a. monitoring of condensate flow rate from air coolers, [or]

b. monitoring of airborne gaseous radioactivity.

Humidity, temperature, or pressure monitoring of the containment atmosphere should be considered as alarms or indirect indication of leakage to the containment.

RG 1.45, Revision 0, Regulatory Position C.5 states that, The sensitivity and response time of each leakage detection system in regulatory position 3. above employed for unidentified leakage should be adequate to detect a leakage rate, or its equivalent, of one gpm in less than one hour.

RG 1.45, Revision 0, "Detector Response Time," states, in part, that, In analyzing the sensitivity of leak detection systems using airborne particulate or gaseous radioactivity, a realistic primary coolant radioactivity concentration assumption should be used. The expected values used in the plant environmental report would be acceptable.

The appropriate sensitivity of a plant's primary containmentldrywell atmosphere gaseous radioactivity monitors is dependent on the design assumptions and the plant-specific licensing basis as described in the plant's updated safety analysis report (USAR). The NRC staff's

-4 approval of the use of expected primary coolant radioactivity concentration values used in the environmental report creates a potential licensing conflict when a licensee is able to achieve and maintain primary coolant radioactivity concentration values lower than the value assumed in the environmental report.

RG 1.45, Revision 1, "Guidance on Monitoring and Responding to Reactor Coolant System Leakage," was issued in May 2008. RG 1.45, Revision 1, describes methods for implementing the GDC 30 requirements that are different from those in RG 1.45, Revision 0, and was developed and issued to support new reactor licensing. Revision 1 allows that having two TS leakage detection methods capable of detecting a 1 gpm leak within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provides adequate leakage detection capability from a safety perspective. It recommends that other potential indicators (including the gaseous radiation monitors) be maintained even though they may not have the same detection capability. These indicators, in effect, provide additional defense-in-depth.

RBS USAR Section 3.1.2.30, "Quality of Reactor Coolant Pressure Boundary (Criterion 30),"

states, in part, that, Criterion Components that are part of the RCPB shall be designed, fabricated, erected, and tested to the highest quality standards practical. Means shall be provided for detecting and, to the extent practical, identifying the location of the source of reactor coolant leakage.

Design Conformance By utilizing conservative design practices and detailed quality control procedures, the pressure-retaining components of the RCPB are designed and fabricated to retain their integrity during normal and postulated accident conditions.

Accordingly, components which compose the RCPB are designed, fabricated, erected, and tested in accordance with recognized industry codes and standards listed in Chapter 5. Further, product and process quality planning is provided as described in Chapter 17 to assure conformance with the applicable codes and standards, and to retain appropriate documented evidence verifying compliance.

Because the subject matter of this criterion deals with aspects of the RCPB, further discussion on this subject is treated in the response to Criterion 14, Reactor Coolant Pressure Boundary.

Means are provided for detecting reactor coolant leakage. The leak detection system consists of sensors and instruments to detect, annunciate, and in some cases, isolate the RCPB from potential hazardous leaks before predetermined limits are exceeded. Small leaks are detected by temperature and pressure changes, high-sensitivity sump level measurement, increased frequency of sump pump operation, and by measuring fission product concentration. In addition to these means of detection, large leaks are detected by changes in flow rates in process lines and by changes in reactor water level. The allowable leakage rates have been based on the predicted and experimentally determined behavior of

- 5 cracks in pipes, the ability to make up coolant system leakage, the normally expected background leakage due to equipment design, and the detection capability of the various sensors and instruments. The total leakage rate limit is established so that, in the absence of normal ac [alternating current] power concurrent with a loss of feedwater supply, makeup capabilities are provided by the RCIC [reactor core isolation cooling] system. While the leak detection system provides protection from small leaks, the ECCS [emergency core cooling system] provides protection for the complete range of discharges from ruptured pipes. Thus, protection is provided for the full spectrum of possible discharges.

The RCPB and the leak detection system are designed to meet the requirements of Criterion 30.

RBS USAR Section 5.2.5.2, "Leak Detection Instrumentation and Monitoring," provides a description of the leakage detection devices associated with the RCPB. RBS USAR Section 5.2.5.2.1, "Leak Detection Instrumentation and Monitoring Inside Drywell," describes the systems within the scope of TSTF-514 (floor drain sump measurement, cooler condensate drain, and fission product monitoring) as follows:

1. Floor Drain Sump Measurement The normal design leakage collected in the drywell and pedestal floor drain sumps includes unidentified leakage from the CRDs, valve flange leakage, component cooling water, service water, air cooler drains, and any leakage not connected to the equipment drain sump. Equipment drain sump instrumentation is identical to that of the floor drain sump. Both floor drain sumps have level transmitters that send 4-20 ma [milliamps] signals to the control room where the signal is monitored by a programmable controller and also sent to a recorder.

The programmable controller checks the increase in level every 15 [minutes] and calculates the leakage rate into each sump it monitors. It totalizes unidentified leakage and actuates an alarm if that total exceeds 5 gpm. The programmable controller totalizes unidentified and identified leakage and actuates an alarm if the total exceeds 25 gpm. It calculates the average total leakage for the last 24 hr [hours] and prints a report giving the leakage rate into each sump it monitors, showing the last four calculations to indicate a trend and printing the total unidentified, total identified, their sum, and the 24-hr average. The programmable controller will print this report any time an alarm value is exceeded. The printout can be ordered manually or can be automatic on a 1- or 8-hr basis.

A recorder located in the main control room provides independent indication of the identified and unidentified leakage levels. The recorder is a backup for the leak rate detector because it records the change in leakage inventory over time and thereby provides the leakage rate over a specified time period. Abnormal leakage rates are alarmed in the main control room.

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3. Cooler Condensate Drain Condensate from the drywell coolers is routed to the drywell floor drain sump and is monitored by use of a flow transmitter which measures flow in the condensate drain line and sends signals for indication instrumentation in the main control room. The condensate is measured twice, once as condensate flow rate and then as a portion of the drywell leakage floor drain sump flow rate.

5. Fission Product Monitoring The drywell air sampling system is used along with the temperature, pressure, and flow variation method described above to detect leaks of the RCPB. The system continuously monitors the drywell atmosphere for airborne radioactivity (iodine, noble gases, and particulates). The sample is drawn from the drywell. A sudden increase of activity, which may be attributed to steam or reactor water leakage, is annunciated in the main control room (Section 7.6). The radiation detectors associated with fission product monitoring in the drywell air sampling system are powered from a Class 1E source.

Each of the required leak detection systems (LOSs) inside the drywell is designed with a capability to detect leakage less than the established leakage rate limits.

RBS USAR Section 7.6.1.2, "Leak Oetection System (LOS)," states, in part that, The LOS instrumentation and controls are designed to monitor leakage from the RCPB and initiate alarms and/or isolation when predetermined limits are exceeded.

RBS USAR Section 7.6.2.4, "Conformance to NRC Regulatory Guides," states, in part, that:

The following is a discussion of conformance to those Regulatory Guides which apply specifically to the safety-related systems discussed in this section.

Regulatorv Guide 1.45 Provisions are made to monitor systems connected to the RCPB for signs of intersystem leakage, including radioactivity monitoring of process fluids and reactor vessel water level monitoring.

The LOS is qualified for operation following an OBE [operating basis earthquake).

Indicators and alarms for each leakage detection subsystem are provided in the main control room.

Note that RBS is committed to RG 1.45, Revision 0, May 1973. Revision 1 of RG 1.45 was issued in May 2008; however, RBS is not committed to Revision 1 of RG 1.45.

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3.0 TECHNICAL EVALUATION

3.1 Proposed Changes In adopting the changes to TSS included in TSTF-514, Revision 3, the licensee proposed to revise TS 3.4.7, "RCS Leakage Detection Instrumentation," Conditions and Required Actions.

The licensee proposed adding new Condition D to TS 3.4.7, which would state:

---

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

Only applicable when the drywell atmospheric gaseous monitoring system is the only OPERABLE monitor.

D. Drywell floor drain sump monitoring system inoperable.

Drywell air cooler condensate flow rate monitoring system inoperable.

The Required Actions for new Condition D would state:

D.1 Analyze grab samples of the drywell atmosphere.

D.2 Monitor RCS leakage by administrative means.

D.3.1 Restore drywell floor drain sump monitoring system to OPERABLE status.

D.3.2 Restore drywell air cooler condensate flow rate monitoring system to OPERABLE status.

In addition, the licensee proposed minor changes in TS 3.4.7 to ensure continuity of the TS format. These changes include re-Iettering current Condition D, which applies when the drywell floor drain sump monitoring system is the only operable RCS leakage detection instrument, to Condition E, current Condition E, which applies when the required action and the associated Completion Time are not satisfied, to Condition F, and current Condition F, which applies when all required leakage detection systems are inoperable, to Condition G. Similar changes were made to the associated Required Actions.

New Condition D would be applicable when the drywell atmospheric gaseous radiation monitor is the only operable RCS leakage detection monitor. This new Condition is necessary because improved fuel integrity and the resulting lower primary coolant radioactivity concentration affect the response of a plant's drywell atmosphere gaseous radioactivity monitor to a greater extent

- 8 than the response of other RCS leakage detection monitors to leakage radioactivity. The proposed Required Actions for new Condition D require the licensee to analyze grab samples of the drywell atmosphere once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, restore either the drywell air cooler condensate flow rate monitoring system or the required drywell floor drain sump monitoring system to operable status within 7 days, and monitor RCS leakage by administrative means once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Administrative means of monitoring RCS leakage include trending parameters that may indicate an increase in RCS leakage. There are diverse alternative methods from which appropriate indicators for identifying RCS leakage may be selected based on plant conditions. Entergy will utilize the following methods considering the current plant conditions and historical or expected sources of unidentified leakage, as their TS administrative means: drywell pressure, drywell temperature, component cooling water system outlet temperatures, component cooling water system makeup, reactor recirculation system pump seal pressure and temperature, reactor recirculation system pump motor cooler temperatures, drywell cooling fan outlet temperatures, control rod drive system flange temperatures, and/or safety relief valve tailpipe temperature.

3.2 NRC Staff Evaluation The NRC staff determined that the proposed Condition D is more restrictive than the current requirement, because there is no current TS condition for the plant condition of the drywell atmospheric gaseous radioactivity monitor being the only operable RCS leakage detection monitor. The associated proposed Actions and Completion Times are adequate because monitoring the RCS by administrative means, coupled with drywell atmospheric grab samples, are sufficient to alert the operating staff to an unexpected increase in unidentified leakage. The drywell atmospheric grab samples provide a method of detecting particulate and gaseous radioactive material in the drywell atmosphere. However, taking frequent grab samples will ensure there is no significant loss of monitoring capability during the Required Action Completion Time. The 12-hour interval is reasonable given the availability of the drywell atmospheric gaseous radiation monitor. Allowing 7 days to restore another RCS leakage monitor to operable status is reasonable given the diverse methods employed in the Required Actions to detect an RCS leak and the low probability of a large RCS leak during this period.

Proposed Condition D is conservative relative to the STS, sufficiently alerts the operating staff, provides a comparable ability to detect RCS leakage, and provides time intervals that are reasonable. Based on the above, the NRC staff concludes that proposed Condition D provides an adequate assurance of safety when judged against current regulatory standards.

The licensee proposes minor changes to ensure continuity of the TS format. These changes re-Ietter current Condition D, which applies when the drywell floor drain sump monitoring system is the only operable RCS leakage detection instrument, to Condition E, current Condition E, which applies when the required action and the associated Completion Time are not satisfied, to Condition F, and current Condition F, which applies when all required leakage detection systems are inoperable, to Condition G. Similar changes were made to the associated Required Actions. The NRC staff concludes that these changes are editorial and are, therefore, acceptable.

In adopting TSTF-514, Revision 3, the licensee proposed changes that would revise the Bases for TS 3.4.7 to reflect the proposed TS changes and more accurately describe the contents of the facility design basis related to operability of the RCS leakage detection instrumentation and

-9 reflect the proposed TS changes. The regulation at 10 CFR 50.36(a)(1) requires a summary statement of the TS Bases or reasons for such specifications be included with the application.

The proposed TS Bases changes related to operability of the RCS leakage detection instrumentation are acceptable because they are consistent with the design basis of the facility and provide: background information, applicable safety analyses, a description of the limiting condition for operation, and the applicability for the RCS leakage detection instrumentation TS.

These instruments satisfy Criterion 1 of 10 CFR 50.36(c)(2)(ii) in that they are installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the RCPB.

The NRC staff evaluated the licensee's proposed changes against the applicable regulatory requirements listed in Section 2.0 of this safety evaluation. The NRC staff also compared the proposed changes to the changes made to STS by TSTF-514, Revision 3. The NRC staff concludes that all the proposed changes afford adequate assurance of safety when judged against current regulatory standards. Therefore, the NRC staff concludes that the proposed changes are acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Louisiana State official was notified of the proposed issuance of the amendment. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to 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 the Federal Register on June 28, 2011 (76 FR 37847). Accordingly, the amendments meet 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) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: A. Wang Date: November 21, 2011

November 21, 2011 Vice President, Operations Entergy Operations, Inc.

River Bend Station 5485 US Highway 61 N St. Francisville, LA 70775

SUBJECT:

RIVER BEND STATION, UNIT 1 -ISSUANCE OF AMENDMENT RE:

ADOPTION OF TSTF-514, REVISION 3, "REVISE BWR OPERABILITY REQUIREMENTS AND ACTIONS FOR RCS LEAKAGE INSTRUMENTATION" (TAC NO. ME6048)

Dear Sir or Madam:

The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 172 to Facility Operating License No. NPF-47 for the River Bend Station, Unit 1. This amendment consists of changes to the Technical Specifications (TSs) in response to your application dated April 11, 2011.

The amendment modifies TS 3.4.7, "RCS [Reactor Coolant System] Leakage Detection Instrumentation," to define a new time limit for restoring inoperable reactor coolant system (RCS) leakage detection instrumentation to operable status; establish alternate methods of monitoring RCS leakage when one or more required monitors are inoperable; and make TS Bases changes which reflect the proposed changes and more accurately reflect the contents of the facility design basis related to operability of the RCS leakage detection instrumentation.

These changes are consistent with NRC-approved Revision 3 to Technical SpeCification Task Force (TSTF) Change Traveler TSTF-514, "Revise BWR [Boiling-Water Reactor] Operability Requirements and Actions for RCS Leakage Instrumentation,"as part of the consolidated line item improvement process.

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

Sincerely.

IRA!

Alan Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-458

Enclosures:

1. Amendment No. 172 to NPF-47

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

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