ML040970230

From kanterella
Jump to navigation Jump to search

Technical Specification Change Request 321-1 to Eliminate Requirements for Hydrogen/Oxygen Monitors Using the Consolidated Line Item Improvement Process
ML040970230
Person / Time
Site: Oyster Creek
Issue date: 03/23/2004
From: Gallagher M
AmerGen Energy Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2130-03-20276
Download: ML040970230 (20)
v • d • e


Text

AmerGen Energy Company. LLC www.exeloncorp.com Amer~en An Exelon Company SM 200 Exelon Way Kennett Square, PA 19348 10 CFR 50.90 2130-03-20276 March 23, 2004 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001

SUBJECT:

Oyster Creek Generating Station Facility Operating License No. DPR-1 6 NRC Docket No. 50-219 Technical Specification Change Request 321-To Eliminate Requirements for Hydrogen/Oxygen Monitors Using The Consolidated Line Item Improvement Process

REFERENCES:

Technical Specification Task Force (TSTF) Standard Technical Specifications Change Traveler TSTF-447, Revision 1, "Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors" Federal Register, Volume 68, Number 186, Notice of Availability of Model Application Concerning Technical Specification Improvement to Eliminate Hydrogen Recombiner Requirement, and Relax the Hydrogen and Oxygen Monitor Requirements for Light Water Reactors Using the Consolidated Line Item Improvement Process, published September 25, 2003, (68FR55416).

In accordance with 10 CFR 50.90, "Application for Amendment of License or Construction Permit," AmerGen Energy Company, LLC proposes changes to Appendix A, Technical Specifications (TS) for the Oyster Creek Generating Station. The purpose of this license amendment request is to eliminate the requirements for hydrogen/oxygen monitors from the Technical Specifications. The proposed Technical Specification changes support implementation of the revisions to 10 CFR 50.44, "Standards for Combustible Gas Control System in Light-Water-Cooled Power Reactors," that became effective on October 16, 2003.

The proposed changes are consistent with Revision 1 of NRC-approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-447, "Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors." The availability of this TS improvement was announced in the Federal Register on September 25, 2003 as part of the Consolidated Line Item Improvement Process (CLIIP).

Enclosure 1 provides a description of the proposed change, the requested confirmation of applicability, and plant-specific verifications and commitments. Enclosure 2 provides the existing TS pages marked-up to show the proposed change. Enclosure 3 provides retyped TS pages with the proposed changes incorporated and Enclosure 4 provides a list of regulatory commitments made in this correspondence.

4O\D

2130-03-20276 March 23, 2004 Page 2 AmerGen Energy Company, LLC requests approval of the proposed changes by September 30, 2004, with the amendment being implemented within 60 days of issuance.

The proposed changes have been reviewed by the Plant Operations Review Committee and approved by the Nuclear Safety Review Board in accordance with the Section 6.5 of the Oyster Creek Technical Specifications.

In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b), AmerGen Energy Company, LLC is notifying the State of New Jersey of this application for changes to the TS by transmitting a copy of this letter and its attachments to the designated State Official.

If you have any questions or require additional information, please contact Dave Robillard at (610) 765- 5952.

I declare under penalty of perjury that the foregoing is true and correct.

Respectfully, Executed on 0- 0*' _ _7_ b __A Michael P. Gallagher Director, Licensing and Regulatory Affairs AmerGen Energy Company, LLC

Enclosures:

1) Description and Assessment of Proposed Changes
2) Proposed Technical Specification Changes (Mark-up)
3) Retyped Technical Specification Pages
4) List of Regulatory Commitments cc: H. J. Miller, Administrator, Region I, USNRC R. J. Summers, USNRC Senior Resident Inspector, OCGS P. S. Tam, Project Manager, USNRC File No. 03094

ENCLOSURE 1 Oyster Creek Technical Specification Change Request No. 321 Description and Assessment of Proposed Changes

2130-03-20276 Page 1 of 3

1.0 INTRODUCTION

In accordance with 10 CFR 50.90, "Application for Amendment of License or Construction Permit," AmerGen Energy Company, LLC proposes changes to Appendix A, Technical Specifications (TS), for the Oyster Creek Generating Station. The purpose of this license amendment request is to eliminate the requirements for hydrogen/oxygen monitors from the Technical Specifications. The proposed Technical Specification changes support implementation of the revisions to 10 CFR 50.44, "Standards for Combustible Gas Control System in Light-Water-Cooled Power Reactors," that became effective on October 16, 2003.

The proposed changes are consistent with Revision 1 of NRC-approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-447, "Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors." The availability of this TS improvement was announced in the Federal Register on September 25, 2003 as part of the Consolidated Line Item Improvement Process (CLIIP).

2.0 DESCRIPTION

OF PROPOSED AMENDMENT Consistent with the NRC-approved Revision 1, of TSTF-447, the proposed TS changes include:

TS Section 3.13.F Drywell H2 Monitor Deleted Table 3.13.1 Item 4, Drywell H2 Monitor Deleted TS Section 4.13.D Drywell H2 Monitor Deleted Table 4.13-1 Item 4, Drywell H2 Monitor Deleted Other TS changes included in this application are limited to formatting changes that resulted directly from the deletion of the above requirements related to Hydrogen Monitors.

3.0 BACKROUND The background for this application is adequately addressed by the NRC Notice of Availability published on September 25, 2003 (68FR55416), TSTF-447, the documentation associated with the 10 CFR 50.44 rulemaking, and other related documents.

2130-03-20276 Page 2 of 3 4.0 REGULATORY REQUIREMENTS AND GUIDANCE The applicable regulatory requirements and guidance associated with this application are adequately addressed by the NRC Notice of Availability published on September 25, 2003 (68FR55416), TSTF-447, the documentation associated with the 10 CFR 50.44 rulemaking, and other related documents.

5.0 TECHNICAL ANALYSIS

AmerGen Energy Company, LLC has reviewed the safety evaluation published on September 25, 2003 (68FR55416) as part of the CLIIP. This verification included a review of the NRC staff's Safety Evaluation, as well as the supporting information provided to support TSTF-447. AmerGen Energy Company, LLC has concluded the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to the Oyster Creek Generating Station and justify this amendment for the incorporation of the changes to the Oyster Creek TS.

The Oyster Creek TS are in a custom format that does not coincide with the industry Standard Technical Specifications (STS). The STS include surveillance requirements with the Limiting Conditions for Operation while a separate section is provided in the Oyster Creek TS. Additionally, the Bases of the specifications are provided in a separate document in the STS but are included with the applicable specification in the Oyster Creek TS. No changes to the Oyster Creek Bases were required to support this proposed change.

6.0 REGULATORY ANALYSIS

A description of this proposed change and its relationship to regulatory requirements and guidance was provided in the NRC Notice of Availability published on September 25, 2003 (68FR55416), TSTF-447, the documentation associated with the 10 CFR 50.44 rulemaking, and other related documents.

6.1 Verification and Commitments AmerGen Energy Company, LLC is not proposing any variations or deviations from the requirements of the STS changes described in TSTF-447, Revision 1 or the NRC staff's model safety evaluation dated September 25, 2003. However, changes reflect the custom format of the Oyster Creek TS.

In accordance with the NRC staff's Safety Evaluation (SE) the hydrogen and oxygen monitoring capability will be maintained but no longer considered safety related as defined in 10 CFR 50.2. The model SE was published in the Federal Register on September 25, 2003 (68FR55416) for this TS improvement. AmerGen Energy Company, LLC is making the following verifications and regulatory commitments:

2130-03-20276 Page 3 of 3

1. AmerGen Energy Company, LLC has verified that a hydrogen monitoring system capable of diagnosing beyond design basis accidents is installed at Oyster Creek and is making a regulatory commitment to maintain that capability. The hydrogen monitors are included in the plant's Emergency Procedures, Operating Procedures, and Maintenance Procedures. This regulatory commitment is currently implemented.
2. Oyster Creek has an inerted containment. AmerGen Energy Company, LLC has verified that an oxygen monitoring system capable of verifying the status of the inerted containment is installed at Oyster Creek and is making a regulatory commitment to maintain that capability. The oxygen monitors are included in Operating Procedures and the plant's Maintenance Program. This regulatory commitment is currently implemented.

7.0 NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION AmerGen Energy Company, LLC has reviewed the proposed No Significant Hazards Consideration Determination (NSHCD) published in the Federal Register as part of the CLIIP. AmerGen Energy Company, LLC has concluded that the proposed NSHCD presented in the Federal Register notice (68FR55416) is applicable to the Oyster Creek Generating Station and is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91 (a).

8.0 ENVIRONMENTAL EVALUATION AmerGen Energy Company, LLC has reviewed the environmental evaluation included in the model safety evaluation dated September 25, 2003 (68FR55416) as part of the CLIIP. AmerGen Energy Company, LLC has concluded that the staff's findings presented in that evaluation are applicable to Oyster Creek and the evaluation is hereby incorporated by reference for this application.

9.0 PRECEDENT This application is being made in accordance with the CLIIP. AmerGen Energy Company, LLC is not proposing variations or deviations from the TS changes described in TSTF-447, Revision 1 or the NRC staff's model SE published on September 25, 2003 (68FR55416).

10.0 REFERENCES

1. Technical Specification Task Force (TSTF) Standard Technical Specifications Change Traveler TSTF-447, Revision 1, "Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors"
2. Federal Register, Volume 68, Number 186, Notice of Availability of Model Application Concerning Technical Specification Improvement to Eliminate Hydrogen Recombiner Requirement, and Relax the Hydrogen and Oxygen Monitor Requirements for Light Water Reactors Using the Consolidated Line Item Improvement Process, published September 25, 2003, (68FR55416).

ENCLOSURE 2 Oyster Creek Technical Specification Change Request No. 321 Proposed Technical Specification Changes (Mark-up)

The pages included in this enclosure are:

PAGES 3.13-2 3.13-3 3.13-5 4.13-1 4.13-2

C. In the event that any of theme monitoring channels become inoperable, they shall be made OPERABLE prior to stastup following the next COLD SHUTDOWN.

D. Wide Range Torus Water Level Monitor

1. Two wide range torus water level monitor channels shall be continuously indicated in the control room during POWER OPERATION.
2. With the number of OPERABLE accident monitoring channel. less than the total Number of Channels shown in Table 3.13.1, restore the inoperable channel(s) to OPERABLE status within 7 days or place the reactor in the SHUTDOWN CONDITION within the J next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3. With the number of OPERABLE accident monitoring 3 instrumentation channels loes than the Minimum Channels operable requirements of Table 3.13.1, restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or place the reactor in the SHUTDOWN CONDITION within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

E. Wide Ranqe Drvwell Pressure Monitor

1. Two Wide Range Drywell Pressure monitor channels shall be continuously indicated in the control room during POWER OPERATION.
2. With the number of OPERABLE accident monitoring channels less than the total Number of Channels shown in Table 3.13.1, restore the inoperable channel(s) to OPERABLE status within 7 days or place 3 the reactor in the SHUTDOWN CONDITION within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3. With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels operable requirements of 3.13.1, restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or place the reactor in the SHUTDOWN CONDITION within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

odryw lhydr enmoni r chan l Xapabl of contfi uously ndicati g in t con l PE ION.

OYSTER CREEK 3.13-2 Amendment No.: 54, 57, 94, 96, 123,158

1 the w ctor inme e HUihrn Cradiin witors nsl b4

3. With the number of OPERABLE chmn ets lessthan2he/nimum b Pannels anyableci requrdment d Table 3.1, tore at c one Reast thannelIoperableotatus witon 7 da or plsace wictohin the 7days thefailureorprepahin ae next 24 of G. Containment High-Range Radiation Monitor
1. Two containment high-range radiation monitors shall be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is required.
2. With the number of OPERABLE monitors less than 2:
a. Take appropriate action to restore the inoperable monitor(s) to OPERABLE status as soon as possible.
b. Perform any actions required by Table 3.c.1.
c. Restore the inoperable monitore(s) to OPERABLE status within 7 days of the failure or prepare and submit a Special Report within 14 days following the failure outlining thNoble asof inoperability, actions taken, and the planned schedule for restoring the monitors to i TOPERABLE status.
3. With the number of OPERABLE monitors less than 1, in addition to the actions of 3.13.G.2 above, restore at least I monitor to OPERABLE status within 7 days of the failure or have available a preplanned alternate method capable of being implemented to provide an estimate of the radioactive material in containment under accident conditions.

H. High-Range Radioactive Noble Gas Effluent Monitor

1. The high range radioactive noble gas effluent monitors listed in Table 3.13.1 shall be OPERABLE during POWER OPERATION.
2. With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirements, restore the inoperable channel(s) to OPERABLE status within 7 days of the event or prepare and submit a Special Report within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the equipment to OPERABLE status.

BASES The purpose of the safety/relief valve accident monitoring instrumentation is to alert the operator to a stuck open safety/relief valve which could result in an inventory threatening event.

OYSTER CREEK 3.13-3 Amendment No.: 54,57,94,116,137,157,158 l

TABLE; .13 1 ACCIDEN MONITORING INSTRUMENTATION TOTAL NO. OF IMINIMUM CHANNELS INSTRUMIENT CHANNELS OPERABLE

1. Relief Valve Position Indicator Ilvalve (Primary Detector')

Relief Valve Position Indicator I/valve (Backup Indications")

2. Wide Range Drywell Pressure 2 1 Monitor (PTIPR-53 & 54)
3. Wide Range Torus Water Level 2 1 (LT/LR-31 & 38)
4. s> .Jiii wi4f. i)owro
o. Containment High Range Radiation 2 1
6. High Range Radioactive Noble Gas Effluent Monitor
a. Main Sack I I
b. Turbine Building Vents I Acoustic Monitor Thermocouple Thermnocouple TE 65A can be substituted for thermocouple TE2 W-43V, W, or X Thermocouple TE 65B can be substituted for thermocouple TE21(i-3Y or Z
  • 1 %J I 1-CR ac F-" t:1zV rs 3.13-5 Amendment No.: 54, 57, 88, 94, 1U6, 137, 214

4.13 ACCIDENT MONITORING INSTRUMENTATION Applicability: Applies to surveillance requirements for the accident monitoring instrumentation.

Objective: To verify the operability of the accident monitoring instrumentation.

Specification: A. Safety & Relief Valve Position Indicators Each accident monitoring instrumentation channel shall be demonstrated operable by performance of the Channel Check and Channel Calibration operations at the frequencies shown in Table 4.13-1.

B. Wide Range Orywell Pressure Monitor Each accident monitoring instrumentation channel shall be demonstrated operable by performance of the Channel Check and Channel Calibration operations at the frequencies shown in Table 4.13-1.

C. Wide Range Torus Water Level Monitor Each accident monitoring instrumentation channel shall be demonstrated operable by performance of the.Channel Check and Channel Calibration operations at the frequencies shown in Table 4.13-1.

D. r^ro-al WI WAMOMi^ INRIFI?4:

I h acc'ent ede torin X strume ation/hannel strat operab) by perf ance of the han s ,

5 Chec and C nnel Cal ration erati s at e freqencie shown i Table 4 E. Containment High-Range Radiation Monitor Each accident monitoring instrumentation channel shall be-demonstrated operable by performance of the Channel Check and Channel Calibration operations at the frequencies shown in Table 4.13-1.

F. High Range Radioactive Noble Gas Effluent Monitor Each accident monitoring instrumentation channel shall be demonstrated operable by performance of the Channel Check and Channel Calibration operations at the frequencies shown in Table 4.13-1.

Bases:

The operability of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident. This capability is consistent with NUREGs 0578 and 0737.

OYSTER CREEK 4.1 3-1 Amendment No.: V, 34, l) , 137

ACCIDENT HONTTORING INSTRUMNTrATION SU r-ILLANCr REQUIRX!NTS V TRYV HVC CALIBRAION~

1. Primary and Safety Valve Position A B Indicator (Primary fletector*)

Relief and Safety Valve Position A B Indicator (Backup Indications**)

Relief Valve Position Indicator C B (Cocmon Header Temperature Element**)

2. Wide Range Drywell Pressure Monitor A D (PT/PR 53 & 54)
3. Wide Range Torus Water Level Monitor A D (LT/LR 37 a 38)
4. 3 2,flite
5. Containment High Range Radiation Monitor A
6. High Range Radioactive Noble Gas Effluent Monitor
a. Main Stack A G
b. Turbine Building Vent A G Legend:

A - at least once per 31 days B - at least once per 24 months l C - at least once per 15 days until channel calibration is performed and thence at least once per 31 days 0 - at least once per 6 months E- L-e - bckitr 0 Ii Sp N_ abl _-0 F - each refueling outage G - once per 20 months Acoustic MonLtor Thermocouple Channel calibration. shall consist of electronic signal substitution of the channel, not including the detector, for all decades above lOR/hr and a one point calibration check of the detector at or below lOR/hr by means of a calibrated portable radiation source traceable to NBS.

OYSSER CREEK 4.13-2 Amendment No.: 4, 8f Corred146

_ Correzted

ENCLOSURE 3 Oyster Creek Technical Specification Change Request No. 321 Retyped Technical Specification Pages The pages included in this enclosure are:

PAGES 3.13-2 3.13-3 3.13-5 4.13-1 4.13-2

C. In the event that any of these monitoring channels become inoperable, they shall be made OPERABLE prior to startup following the next COLD SHUTDOWN.

D. Wide Range Torus Water Level Monitor

1. Two wide range torus water level monitor channels shall be continuously indicated in the control room during POWER OPERATION.
2. With the number of OPERABLE accident monitoring channels less than the total Number of Channels shown in Table 3.13.1, restore the inoperable channel(s) to OPERABLE status within 7 days or place the reactor in the SHUTDOWN CONDITION within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3. With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels operable requirements of Table 3.13.1, restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or place the reactor in the SHUTDOWN CONDITION within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

E. Wide Range Drvwell Pressure Monitor

1. Two Wide Range Drywell Pressure monitor channels shall be continuously indicated in the control room during POWER OPERATION.
2. With the number of OPERABLE accident monitoring channels less than the total Number of Channels shown in Table 3.13.1, restore the inoperable channel(s) to OPERABLE status within 7 days or place the reactor in the SHUTDOWN CONDITION within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3. With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels operable requirements of 3.13.1, restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or place the reactor in the SHUTDOWN CONDITION within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

F. DELETED OYSTER CREEK 3.13-2 Amendment No.: 51, 57, 94, 96, 123, 158,

G. Containment Uligh-Range Radiation Monitor I. Two containment high-range radiation monitors shall be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is required.

2. With the number of OPERABLE monitors less than 2:
a. Take appropriate action to restore the inoperable monitor(s) to OPERABLEI status as soon as possible.
b. Perform any actions required by Table 3. 1.1.
c. Restore the inoperable monitor(s) to OPERABLE status within 7 days of the failure or prepare and submit a Special Report within 14 days following the failure outlining the cause of inoperability, actions taken, and the planned schedule for restoring the monitors to OPERABLE status.
3. With the number of OPERABLE monitors less than 1, in addition to tile actions of 3.1 3.G.2 above, restore at least I monitor to OPERABLE status within 7 days of tile failure or have available a preplanned alternate method capable of being implemented to provide an estimate of the radioactive material in containment under accident conditions.

H. -hilh-Range Radioactive Noble Gas Effluent Monitor I. The high range radioactive noble gas effluent monitors listed in Table 3.13.1 shall be OPERABLE during POWER OPERATION.

2. With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirements, restore the inoperable channel(s) to OPERABLE status within 7 days of the event or prepare and submit a Special Report within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the equipment to OPERABLE status.

BAS ES The purpose of the safety/relief valve accident monitoring instrumentation is to alert the operator to a stuck open safety/relief valve which could result in an inventory threatening event.

OYSTER CREEK 3.13-3 Amendment No.: 5',57,91,116,137,157,15°,

Corrected Letter dated 6/15/1992

TABLE 3.13.1 ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT TOTAL NO. OF MINIMUM CHANNELS CHANNELS OPERABLE 1 Relief Valve Position Indicator 1/valve (Primary Detector*)

Relief Valve Position Indicator 1/valve (Backup Indications"*)

2. Wide Range Drywell Pressure 2 1 Monitor (PT/PR-53 & 54)
3. Wide Range Torus Water Level 2 1 (LT/LR-37 & 38)
4. DELETED I
5. Containment High Range Radiation 2 1
6. High Range Radioactive Noble Gas Effluent Monitor
a. Main Stack 1 1
b. Turbine Building Vents 1 1
  • Acoustic Monitor
    • Thermocouple Thermocouple TE 65A can be substituted for thermocouple TE210-43V, W, or X Thermocouple TE 65B can be substituted for thermocouple TE210-43Y or Z OYSTER CREEK 3.13-5 Amendment No.: 51, 57, 88, 91,116,137, 214,

4.13 ACCIDENT MONITORING INSTRUMENTATION Applicability: Applies to surveillance requirements for the accident monitoring instrumentation.

Obiective: To verify the operability of the accident monitoring instrumentation.

Specification: A. Safety & Relief Valve Position Indicators Each accident monitoring instrumentation channel shall be demonstrated operable by performance of the Channel Check and Channel Calibration operations at the frequencies shown in Table 4.13-1.

B. Wide Range Drywell Pressure Monitor Each accident monitoring instrumentation channel shall be demonstrated operable by performance of the Channel Check and Channel Calibration operations at the frequencies shown in Table 4.13-1.

C. Wide Range Torus Water Level Monitor Each accident monitoring instrumentation channel shall be demonstrated operable by performance of the Channel Check and Channel Calibration operations at the frequencies shown in Table 4.13-1.

D. DELETED E. Containment High-Range Radiation Monitor Each accident monitoring instrumentation channel shall be demonstrated operable by performance of the Channel Check and Channel Calibration operations at the frequencies shown in Table 4.13-1.

F. High Range Radioactive Noble Gas Effluent Monitor Each accident monitoring instrumentation channel shall be demonstrated operable by performance of the Channel Check and Channel Calibration operations at the frequencies shown in Table 4.13-1.

Bases:

The operability of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident. This capability is consistent with NUREGs 0578 and 0737.

OYSTER CREEK 4.13-1 Amendment No.: 51, 91,116,137,

TABLE 4.13-1 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT CHECK CALIBRATION

1. Primary and Safety Valve Position A B Indicator (Primary Detector*)

Relief and Safety Valve Position A B Indicator (Backup Indications**)

Relief Valve Position Indicator C B (Common Header Temperature Element**)

2. Wide Range Drywell Pressure Monitor A D (PT/PR 53 & 54)
3. Wide Range Torus Water Level Monitor A D (LT/LR 37 & 38)
4. DELETED
5. Containment High Range Radiation Monitor A F***
6. High Range Radioactive Noble Gas Effluent Monitor
a. Main Stack A G
b. Turbine Building Vent A G Legend:

A = at least once per 31 days B = at least once per 24 months C = at least once per 15 days until channel calibration is performed and thence at least once per 31 days D = at least once per 6 months E =DELETED F = each refueling outage G = once per 20 months Acoustic Monitor Thermocouple Channel calibration shall consist of electronic signal substitution of the channel, not including the detector, for all decades above 1OR/hr and a one point calibration check of the detector at or below 1OR/hr by means of a calibrated portable radiation source traceable to NBS.

OYSTER CREEK 4.13-2 Amendment No.: 54,r88,-94, 116, 127,111, 116, Corrected

ENCLOSURE 4 Oyster Creek Technical Specification Change Request No. 321 List of Regulatory Commitments

List of Requlatorv Commitments The following table identifies those actions committed to by AmerGen Energy Company, LLC in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments. Please direct questions regarding these commitments to Dave Robillard at (610) 765-5952.

Regulatory Commitments Due Date / Event AmerGen Energy Company, LLC will maintain Currently implemented in the emergency, the capability of monitoring containment operating, and maintenance procedures.

Hydrogen for beyond design basis accidents.

AmerGen Energy Company, LLC will maintain Currently implemented in plant operation and the capability of monitoring containment maintenance procedures.

Oxygen to verify the status of the inerted containment.

Retrieved from "https://kanterella.com/w/index.php?title=ML040970230&oldid=2623920"