RS-11-123, Supplemental Information Related to License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for Rcs..

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Supplemental Information Related to License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for Rcs..
ML112280281
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 08/15/2011
From: Gullott D
Exelon Generation Co, Exelon Nuclear
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-11-123
Download: ML112280281 (15)
v • d • e


Text

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Exelon Generation Company, LLC www.exeloncorp.com 4300 Winfield Road Nuclear Warrenville, IL 60555 RS-11-123 10 CFR 50.90 August 15, 2011 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374

Subject:

Supplemental Information Related to License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, "Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation"

Reference:

Letter from J. L. Hansen (Exelon Generation Company, LLC (EGC)) to u. S. NRC, "License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, 'Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation,'" dated April 4, 2011 In the referenced letter, Exelon Generation Company, LLC (EGC) requested an amendment to the Technical Specifications (TS) of Facility Operating License Nos. NPF-11 and NPF-18 for LaSalle County Station, Units 1 and 2 (LSCS).

The referenced license amendment request proposed a revision the LSCS TS to define a new time limit for restoring inoperable Reactor Coolant System (RCS) leakage detection instrumentation to operable status; established alternate methods of monitoring RCS leakage when one or more required monitors are inoperable; and made 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. The proposed changes were consistent with NRC-approved Revision 3 to TSTF Improved Standard Technical Specification (STS) Change Traveler TSTF-514, "Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation."

Upon further review of the referenced license amendment request, it became clear that the proposed changes to TS 3.4.7 and TS Bases B 3.4.7 verbiage require administrative revisions to provide consistency with current TS and TS Bases. Specifically, EGC would like to substitute primary containment in the referenced letter with drywell, and substitute drywell floor drain sump monitoring system with drywell floor drain sump flow monitoring system. These revisions ensure that the intent of the TS and TS Bases is clear. Markups of the TS and TS Bases inserts provided in the referenced letter are included in Attachment 1 of this submittal. Attachments 2 and 3 of this submittal provide revised TS and TS Bases inserts that align more closely with

U. S. Nuclear Regulatory Commission August 15, 2011 Page 2 current TS and TS Bases, respectively. Please replace the TS and TS Bases inserts in Attachments 2 and 3 of the referenced letter with the revised inserts provided in Attachments 2 and 3 of this submittal. Additionally, the clean TS pages provided in Attachment 4 to this submittal supersede those provided in Attachment 4 of the referenced license amendment request.

This submittal is subdivided as follows:

  • Attachment 1 provides markups showing the revisions to the New TS 3.4.7 Condition D TS Insert and TS Bases Insert Nos. 1 and 2 provided in Attachments 2 and 3 of the referenced license amendment request, respectively.
  • Attachment 2 provides the revised TS Section 3.4.7 New Condition D TS insert which supersedes the New Condition D TS insert provided in Attachment 2 of the referenced license amendment request.
  • Attachment 3 provides the revised TS Bases Section B 3.4.7 inserts which supersede the TS Bases inserts provided in Attachment 3 of the referenced license amendment request.
  • Attachment 4 provides revised (clean) TS pages which should be used to supersede those provided in Attachment 4 of the referenced license amendment request.

The information provided in this letter does not affect the No Significant Hazards Consideration, or the Environmental Consideration provided in Attachment 1 of the original license amendment request as described in the Reference 1 submittal.

In accordance with 10 CFR 50.91(b), "State consultation," EGC is providing the State of Illinois with a copy of this letter and its attachments to the designated State Official.

This letter contains no new regulatory commitments. If you have any questions concerning this letter, please contact Mr. Mitchel A. Mathews at (630) 657-2819.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 15th day of August, 2011.

Respectfully, v--f~~&-

David M. Gullott Manager - Licensing : Markups showing Revisions to the Technical Specifications (TS) and TS Bases Inserts provided in the April 4, 2011 License Amendment Request : Revised New Technical Specifications (TS) 3.4.7 New Condition D Insert : Revised TS Bases Section B 3.4.7 Inserts : Revised Clean TS Pages cc: Illinois Emergency Management Agency - Division of Nuclear Safety

ATTACHMENT 1 LASALLE COUNTY STATION UNITS 1 AND 2 Docket Nos. 50-373 and 50-374 License Nos. NPF-11 and NPF-18 Markups showing Revisions to the Technical Specifications (TS) and TS Bases Inserts provided in the April 4, 2011 License Amendment Request Markup of Submitted New TS 3.4.7 Condition D Markup of Submitted TS B 4.4.7 TS Bases Insert No.1 Markup of Submitted TS B 3.4.7 TS Bases Insert No.2

Markup of Submitted New TS 3.4.7 Condition D

NOTE----------- 0.1 Analyze grab samples Once per Only applicable when the of the f3rimary 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Idrywalll ~rimary containment CO"tai".e"t~

atmospheric gaseous atmosphere.

radiation monitor is the drywall only OPERABLE monitor. AND 0.2 Monitor ReS LEAKAGE Once per O. Orywell floor drain by administrative 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

~~monitoring means.

~in inoperable AfiI2 0.3.1 Restore drywell floor 7 days Orywell air cooler drain sumpAmonitoring condensate flow rate system to O~ERABLE monitoring system status.

inoperable.

OR 0.3.2 Restore drywell air 7 days cooler condensate flow rate monitoring system to OPERABLE status.

Markup of Submitted TS B 3.4.7 TS Bases Insert No.1 This LeO requires instruments of diverse monitoring principles to be OPERABLE to provide confidence that small amounts of unidentified LEAKAGE are detected in time to allow actions to place the plant in a safe condition, when ReS LEAKAGE indicates possible RePB degradation.

The LeO requires three instruments to be OPERABLE.

The drywell floor drain sump;Qlonitoring system is required to quantify the unidentified LEAKAGE rate from the ReS. Thus, fof the system to be considered OPERABLE, either the flow monitoring or the sump level monitoring portion of the system must be OPERABLE and capable of determining the leakage rate. The identification of an increase in unidentified LEAKAGE will be delayed by the time required for the unidentified LEAKAGE to travel to the drywell floor drain sump and it may take longer than one hour to detect a 1 gpm increase in unidentified LEAKAGE, depending on the origin and magnitude of the LEAKAGE. This sensitivity is acceptable for containment sump monitor OPERABILITY. r-I

'V ,drywell I

The reactor coolant contains radioactivity that, when released to the primary Gontainment, can be detected by the gaseous or particulate . . atmos heric radioactivit monitor.

Only one of the two detectors is required to be OPERA LE. Radioactivity detection systems are included for monitoring both particulate and gaseous activities because of their sensitivities and rapid responses to ReS LEAKAGE, but have recognized limitations. Reactor coolant radioactivity levels will be low during initial reactor startup and for a few weeks thereafter, until activated corrosion products have been formed and fission products appear from fuel element cladding contamination or cladding defects. If there are few fuel element cladding defects and low levels of activation products, it may not be possible for thEJb,9aseous or particulate pri~ary Gontainment I I atmospheric radioactivity monitors to detect a 1 gpm Increase Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (luring normaldrywel!

operation. However, th~aseous or particulate Gontainment primary atmospheric radioactivity

\drywell I monitor is OPERABLE when it is capable of detecting a 1 gpm increase in unidentified LEAKAGE within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> given an ReS activity equivalent to that assumed in the design calculations for the monitors (Reference 6).

An increase in humidity of the drywell atmosphere could indicate the release of water vapor to the drywell. Drywell air cooler condensate flow rate is instrumented to detect when there is an increase above the normal value by 1 gpm. The time required to detect a 1 gpm increase above the normal value varies based on environmental and system conditions and may take longer than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This sensitivity is acceptable for drywell air cooler condensate flow rate monitor OPERABILITY.

The LeO is satisfied when monitors of diverse measurement means are available. Thus, the

~ drywell floor drain sump.J!l0nitoring system, in combination with a~aseous or particulate primary Id well I flow Gontainment atmospheric radioactivity monitor and drywell Gont~ment air cooler condensate ry flow rate monitoring system, provides an acceptabl

Markup of Submitted TS B 3.4.7 TS Bases Insert No.2 0.1. 0.2. 0.3.1. and 0.3.2

~With the drywell floor drain sumpj\..monitoring system and the drywell air cooler condensate flow

~rate monitoring system inoperabfe, the only means of detecting LEAKAGE is the primary r:-----::--;

Gontainment atmospheric gaseous radiation monitor. A Note clarifies this applicability of L-.-.::_..........!

drywell I Condition. T~primary Gontainment atmospheric gaseous radiation monitor typically cannot I

" " detect a 1 gpm leak within one hour when RCS activity is low. In addition, this configuration does not provide the required diverse means of leakage detection. Indirect methods of monitoring RCS leakage must be implemented. Grab samples of the . . tmosphere must be .--:---........".,..,

taken and analyzed and monitoring of RCS leakage by administrative means must be performed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to provide alternate periodic information.

Administrative means of monitoring RCS leakage include monitoring and trending parameters that may indicate an increase in RCS leakage. There are diverse alternative mechanisms from which appropriate indicators may be selected based on plant conditions. It is not necessary to utilize all of these methods, but a method or methods should be selected considering the current plant conditions and historical or expected sources of unidentified leakage. The administrative methods

~ are drywell floor drain sum~easurement, drywell equipment drain sump, drywell cooler drain flow, drywell pressure, drywell temperature, drywell air sampling, reactor vessel head closure seal annulus pressure, reactor water recirculation pump seal flow rate, safety/relief valve discharge piping temperature, valve packing leakage, 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, reactor building chiller amperage, and control rod drive system flange temperatures. These indications, coupled with the~tmospheric grab samples, are sufficient to Id II I alert the operating staff to an unexpected increase in unidentified LEAKAGE. rywe The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval is sufficient to detect increasing RCS leakage. The Required Action provides 7 days to restore another RCS leakage monitor to OPERABLE status to regain the intended leakage detection diversity. The 7 day Completion Time ensures that the plant will not be operated in a degraded configuration for a lengthy time period.

ATTACHMENT 2 LASALLE COUNTY STATION UNITS 1 AND 2 Docket Nos. 50-373 and 50-374 License Nos. NPF-11 and NPF-18 Revised Technical Specifications Section 3.4.7 New Condition D Insert

Revised Technical Specifications Section 3.4.7 New Condition D Insert

NO-E----------- 0.1 Ana yze grab samples Once per licable en the of the drywell 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> atmos heric a sphere.

gaseous radiation monitor is the 0 1y OPERABLE AND

'110 it~r.

D.2 Mon r ce per administrative 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> D. 0 11 floor drain means.

s &low monitori 9 system ina ra e. AND 0.3.1 Res:ore d 11 floor 7 d s d ra ins flow D 11 arc monitoring stem to condensate &low rate OPE ~E atus.

monitoring stem inoperab e.

0.3.2 Res:ore d 11 ai r 7 d s coo er conde sate

& ow rate monitori 9 s tern to OPERABLE status.

ATTACHMENT 3 LASALLE COUNTY STATION UNITS 1 AND 2 Docket Nos. 50-373 and 50-374 License Nos. NPF-11 and NPF-18 Revised Technical Specification (TS) Bases Section B 3.4.7 Inserts REVISED TS BASES INSERTS Revised TS Bases Insert No.1 Revised TS Bases Insert No.2

Revised TS Bases Insert No.1 This LCO requires instruments of diverse monitoring principles to be OPERABLE to provide confidence that small amounts of unidentified LEAKAGE are detected in time to allow actions to place the plant in a safe condition, when RCS LEAKAGE indicates possible RCPB degradation.

The LCO requires three instruments to be OPERABLE.

The drywell floor drain sump flow monitoring system is required to quantify the unidentified LEAKAGE rate from the RCS. Thus, for the system to be considered OPERABLE, either the flow monitoring or the sump level monitoring portion of the system must be OPERABLE and capable of determining the leakage rate. The identification of an increase in unidentified LEAKAGE will be delayed by the time required for the unidentified LEAKAGE to travel to the drywell floor drain sump and it may take longer than one hour to detect a 1 gpm increase in unidentified LEAKAGE, depending on the origin and magnitude of the LEAKAGE. This sensitivity is acceptable for containment sump monitor OPERABILITY.

The reactor coolant contains radioactivity that, when released to the drywell, can be detected by the gaseous or particulate drywell atmospheric radioactivity monitor. Only one of the two detectors is required to be OPERABLE. Radioactivity detection systems are included for monitoring both particulate and gaseous activities because of their sensitivities and rapid responses to RCS LEAKAGE, but have recognized limitations. Reactor coolant radioactivity levels will be low during initial reactor startup and for a few weeks thereafter, until activated corrosion products have been formed and fission products appear from fuel element cladding contamination or cladding defects. If there are few fuel element cladding defects and low levels of activation products, it may not be possible for the drywell gaseous or particulate atmospheric radioactivity monitors to detect a 1 gpm increase within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during normal operation. However, the drywell gaseous or particulate atmospheric radioactivity monitor is OPERABLE when it is capable of detecting a 1 gpm increase in unidentified LEAKAGE within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> given an RCS activity equivalent to that assumed in the design calculations for the monitors (Reference 6).

An increase in humidity of the drywell atmosphere could indicate the release of water vapor to the drywell. Drywell air cooler condensate flow rate is instrumented to detect when there is an increase above the normal value by 1 gpm. The time required to detect a 1 gpm increase above the normal value varies based on environmental and system conditions and may take longer than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This sensitivity is acceptable for drywell air cooler condensate flow rate monitor OPERABILITY.

The LCO is satisfied when monitors of diverse measurement means are available. Thus, the drywell floor drain sump flow monitoring system, in combination with a drywell gaseous or particulate atmospheric radioactivity monitor and the drywell air cooler condensate flow rate monitoring system, provides an acceptable minimum.

Revised TS Bases Insert No.2 0.1.0.2.0.3.1. and 0.3.2 With the drywell floor drain sump flow monitoring system and the drywell air cooler condensate flow rate monitoring system inoperable, the only means of detecting LEAKAGE is the drywell atmospheric gaseous radiation monitor. A Note clarifies this applicability of the Condition. The drywell atmospheric gaseous radiation monitor typically cannot detect a 1 gpm leak within one hour when RCS activity is low. In addition, this configuration does not provide the required diverse means of leakage detection. Indirect methods of monitoring RCS leakage must be implemented. Grab samples of the drywell atmosphere must be taken and analyzed and monitoring of RCS leakage by administrative means must be performed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to provide alternate periodic information.

Administrative means of monitoring RCS leakage include monitoring and trending parameters that may indicate an increase in RCS leakage. There are diverse alternative mechanisms from which appropriate indicators may be selected based on plant conditions. It is not necessary to utilize all of these methods, but a method or methods should be selected considering the current plant conditions and historical or expected sources of unidentified leakage. The administrative methods are drywell floor drain sump flow measurement, drywell equipment drain sump, drywell cooler drain flow, drywell pressure, drywell temperature, drywell air sampling, reactor vessel head closure seal annulus pressure, reactor water recirculation pump seal flow rate, safety/relief valve discharge piping temperature, valve packing leakage, 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, reactor building chiller amperage, and control rod drive system flange temperatures. These indications, coupled with the drywell atmospheric grab samples, are sufficient to alert the operating staff to an unexpected increase in unidentified LEAKAGE.

The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval is sufficient to detect increasing RCS leakage. The Required Action provides 7 days to restore another RCS leakage monitor to OPERABLE status to regain the intended leakage detection diversity. The 7 day Completion Time ensures that the plant will not be operated in a degraded configuration for a lengthy time period.

ATTACHMENT 4 LASALLE COUNTY STATION UNITS 1 AND 2 Docket Nos. 50-373 and 50-374 License Nos. NPF-11 and NPF-18 Revised Technical Specifications (TS) (Clean) Pages REVISED TS PAGES 3.4.7-2 3.4.7-3 3.4.7-4

RCS Leakage Detection Instrumentation 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Drywell air cooler - - - - - - - - - - - - NOTE - - - - - - - - - - - --

condensate flow rate Not applicable when the monitoring system required drywell atmospheric inoperable. monitoring 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----------- 0.1 Analyze grab samples Once per Only applicable when the of the drywell 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> drywel1 atmospheri c atmosphere.

gaseous radiation monitor is the only OPERABLE monitor.

0.2 Monitor RCS LEAKAGE Once per by administrative 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> D. Drywell floor drain means.

sump flow monitoring system inoperable.

0.3.1 Restore drywell fl oor 7 days drain sump flow Drywell air cooler monitoring system to condensate flow rate OPERABLE status.

monitoring system inoperable.

0.3.2 Restore drywell ai r 7 days cooler condensate flow rate monitoring system to OPERABLE status.

(contlnued)

LaSalle 1 and 2 3.4.7-2 Amendment No.

RCS Leakage Detection Instrumentation 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. Required drywell E.1 Restore required 30 days atmospheric monitoring drywell atmospheric system inoperable. monitoring system to OPERABLE status.

Drywell air cooler condensate flow rate E.2 Restore drywell air 30 days monitoring system cooler condensate inoperable. flow rate 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, AND B, C, 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 LCD 3.0.3. Immediately detection systems inoperable.

LaSall eland 2 3.4.7-3 Amendment No.

RCS Leakage Detection Instrumentation 3.4.7 SURVEILLANCE REQUIREMENTS

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NOT E- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the other required leakage detection instrumentation is OPERABLE.

SURVEILLANCE FREQUENCY SR 3.4.7.1 Perform CHANNEL CHECK of required drywell In accordance atmospheric monitoring system. with the Surveillance Frequency Control Program SR 3.4.7.2 Perform CHANNEL FUNCTIONAL TEST of required In accordance leakage detection instrumentation. with the Surveillance Frequency Control Program SR 3.4.7.3 Perform CHANNEL CALIBRATION of required In accordance leakage detection instrumentation. with the Survei 11 ance Frequency Control Program LaSalle 1 and 2 3.4.7-4 Amendment No.

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